United
Nuclear Regulatory
Commission
United
Department of
Energy
United
Environmental
Protection Agency
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ISCORS Technical Report 2003-02
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Prepared by: Andrea R. Jones
United
Nuclear
Commission
United
Department
of Energy
United
Protection
Agency
State of New Jersey
Department of
Environmental
Protection
Middlesex County
Utilities
Authority
Northeast Ohio
Regional
Sewer District
ISCORS Technical Report 2003-02
Date Published: November 2003
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ABSTRACT
From 1998 to 2000, through the Interagency Steering Committee on Radiation Standards
(ISCORS), the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental
Protection Agency (EPA) conducted a joint survey (hereafter referred to as the ISCORS sewer
survey) to collect information on radioactivity in sewage sludge and ash from sewage treatment
plants referred to in the industry as publicly owned treatment works (POTWs).
The objectives of the survey were to (1) obtain national estimates of high-probability
occurrences of elevated levels of radioactive materials in sludge and ash at POTWs,
(2) estimate how much radioactive contamination comes from NRC and Agreement State
licensees and how much from naturally occurring radioactivity, and (3) support rulemaking
decisions by NRC and EPA.
The voluntary survey had two components: a questionnaire and a program for sampling and
analyzing sewage sludge and incinerator ash. Questionnaires were sent to 631 POTWs,
requesting information regarding wastewater sources, wastewater and sludge treatment
processes, and sewage sludge disposal practices. Using the information from the 420 returned
questionnaires, NRC and EPA selected 313 POTWs to be sampled. The selection emphasized
POTWs with the greatest potential to receive waste from licensees and in areas with higher
levels of naturally occurring radioactive material (NORM). Altogether 311 sewage sludge
samples and 35 ash samples were taken. Approximately half of the samples were analyzed by
the U.S. Department of Energy's Oak Ridge Institute for Science and Education (ORISE) in
Oak Ridge, Tennessee, under contract to NRC, and the remainder were analyzed by the EPA's
National Air and Radiation Environmental Laboratory (NAREL) in Montgomery, Alabama.
The results of the analyses revealed that samples primarily contained NORM such as radium.
With the exception of NORM, most other samples were at or near the limit of detection. Based
on the results obtained, ISCORS found that the levels are generally comparable to what is
found in other media (e.g. soil and fertilizer). The specific results of the analyses and data
obtained by the questionnaire are discussed in detail in this report.
The survey and the sampling and analysis program results respond, in part, to the
recommendations of the 1994 GAO report (GAO/RCED-94-133) that the NRC estimate the
occurrence of elevated levels of radioactive materials at POTWs. The Subcommittee is
preparing several supplemental reports (both to be published in final form after public review
and comment). The first is a dose assessment report that describes exposure scenarios for
sewage sludge processing, use, and disposal. The parameters used in the dose modeling for
the scenarios and the dose conversion factors calculated for each radionuclide detected are
included. A second report provides recommendations for POTW operators on determining
sources of radioactivity at POTWs, describe sampling and analysis procedures, and suggest
alternative courses of action if circumstances (e.g. location in a high NORM area) or actual
measurements indicate that a problem may exist. The reports and laboratory data used in the
sewage sludge analyses can be publicly accessed at http://www.iscors.org/.
in
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CONTENTS
ASTRACT
FOREWORD ix
ACKNOWLEDGMENTS x
ABBREVIATIONS xi
1 INTRODUCTION 1
1.1 Congressional Interest 1
1.2 POTW Industry Interest 1
1.3 Sources of Radioactivity at POTWs 1
1.4 Federal Agency Regulations and Guidance 2
1.5 1998/2000 Sewage Sludge Survey 3
2 SURVEY DESIGN AND IMPLEMENTATION 4
2.1 Survey Objectives 4
2.2 Questionnaire Phase 4
2.3 Sampling Phase 5
2.3.1 POTW Selection Process 5
2.3.2 Sample Collection 6
2.3.3 General Analytical Procedures 7
2.3.4 Sampling and Data Quality Limitations 8
3 QUESTIONNAIRE SUMMARY 10
3.1 Characteristics of the Population of 313 POTWs 10
4 RADIOACTIVITY DATA ANALYSIS 13
4.1 Summary of Concentrations of Radionuclides in Sewage and Ash 13
4.2 Comparison of Radioactivity in Sewage Sludge and Ash to Radioactivity in
Other Products 16
4.3 Correlation Analysis 18
4.4 Association of Questionnaire Responses with Radionuclide Concentrations .... 20
4.5 Results 20
4.5.1 Physiographic Divisions 22
4.5.2 Primary Source of Drinking Water 23
4.5.3 Average Daily Flow 24
REFERENCES 25
APPENDIX A
Radiological Analysis Results A-1
APPENDIX B
Supporting Statement for Joint NRC/EPA Survey of Sewage
Sludge/Ash B-1
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APPENDIX C
Sewage Sludge Questionnaire C-1
APPENDIX D
Quality Assurance Project Plan D-1
Figures
Figure 1 POTWs Located by Geographic Division 7
Figure D.1 Alpha Analysis Decision Tree D-8
Figure D.2 Beta Analysis Decision Tree D-9
Figure D.3 Gamma Analysis Decision Tree D-10
Figure D.4 Comparison of Critical Level to Detection Limit D-11
Figure D.5 Data Flow Process D-29
Figure D.6 RISSAD Data Handling Process D-37
Tables
Table 2.1 Samples from POTWS in Each Physiographic Region 6
Table 3.1 Summary of Survey Questionnaire Responses of 313 Facilities Samples .... 11
Table 4.1 Summary of Concentrations of Detected Radionuclides in Sludge 14
Table 4.2 Summary of Concentrations of Detected Radionuclides in Ash 15
Table 4.3 Survey Concentration Ranges and Typical U.S. Background Concentrations of
Radionuclides in Soil, Fertilizer, and Common Building Materials 17
Table 4.4 Expected Groupings/Clustering of Radionuclides Based on Process and
Degradation Relationships 19
Table 4.5 Summary of Direction of Effect for Questionnaire Response less Predictive for
Radionuclide Concentration in Sludge 21
Table 4.6 Relationships of Physiographic Division to Concentrations of Radionuclides in
Sludge Samples 22
Table 4.7 Relationships of Primary Drinking Water Source to the Relative Concentration
of Radionuclides 23
Table 4.8 Effect of Average Daily Flow on Radionuclide Concentration 24
Table A.1 Concentrations of Radionuclides in Sludge Summarized
by Geographic Division A-1
Table A.2 Concentrations of Radionuclides in Ash Summarized by Geographic
Division A-14
Table A.3 Concentrations of Radionuclides in Sludge Summarized by Level(s) of
Wastewater Treatment Achieved by POTW A-27
Table A.4 Concentrations of Radionuclides in Ash Summarized by Level(s) of Wastewater
Treatment Achieved by POTW A-39
Table A.5 Concentrations of Radionuclides in Sludge Summarized by Annual Average
Flow Rate A-51
Table A.6 Concentrations of Radionuclides in Ash Summarized by Annual Average
Flow Rate A-57
Table A.7 Concentrations of Radionuclides in Sludge Summarized by Primary Sources of
Drinking Water for Your Community A-63
Table A.8 Concentrations of Radionuclides in Ash Summarized by Primary Sources of
Drinking Water for Your Community A-78
VI
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Table A.9 Concentrations of Radionuclides in Sludge Summarized by Receipt of
Discharges of Drinking Water Treatment Residuals A-87
Table A. 10 Concentrations of Radionuclides in Ash Summarized by Receipt of Discharges
of Drinking Water Treatment Residuals A-91
Table A. 11 Concentrations of Radionuclides in Sludge Summarized by Whether or Not the
POTW has Combined Sanitary and Storm Water Sewers A-94
Table A. 12 Concentrations of Radionuclides in Ash Summarized by Whether or Not the
POTW has Combined Sanitary and Storm Water Sewers A-97
Table A. 13 Concentrations of Radionuclides in Sludge Summarized by Receipt of Sludge
from other POTWs A-100
Table A. 14 Concentrations of Radionuclides in Ash Summarized by Receipt of Ash from
other POTWs A-103
Table A. 15 Concentrations of Radionuclides in Sludge Summarized by Receipt of Septage
for Processing A-106
Table A. 16 Concentrations of Radionuclides in Ash Summarized by Receipt of Septage
for Processing A-110
Table A. 17 Concentrations of Radionuclides in Sludge Summarized by Percentage of
Industrial Annual Average Daily Total Flow Rate A-114
Table A. 18 Concentrations of Radionuclides in Ash Summarized by Percentage of
Industrial Annual Average Daily Total Flow Rate A-118
Table A. 19 Concentrations of Radionuclides in Sludge Summarized by Number of Final
Sewage Sludge Production Facility Locations A-122
Table A.20 Concentrations of Radionuclides in Ash Summarized by Number of Final
Sewage Sludge Production Facility Locations A-125
Table D.1 Format of Monthly Data Report D-16
Table D.2 Minimum Detectable Concentrations for Selected Gamma Emitters D-20
Table D.3 Minimum Detectable Concentrations for Selected Radionuclides D-21
Table D.4 NAREL Data Handling Equipment D-31
Table D.5 ORISE Data Handling Equipment D-32
VII
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FOREWORD
This report is prepared in response to a May 1994 U.S. General Accounting Office (GAO)
report, "Nuclear Regulation: Action Needed to Control Radioactive Contamination at Sewage
Treatment Plants" (GAO/RCED-94-133), and Congressional interest expressed in joint
House/Senate hearings. Through the Interagency Steering Committee on Radiation Standards
(ISCORS)*, the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental
Protection Agency (EPA) conducted a survey of radioactivity in sewage sludge and ash from
publicly owned treatment works (POTWs) to determine whether the public's health and safety
and the environment are being adequately protected. The objectives of the survey were to
(1) obtain national estimates of high-probability occurrences of elevated levels of radioactive
materials in sludge and ash at POTWs, (2) estimate the extent to which radioactive
contamination comes from either NRC/Agreement State licensees or naturally occurring
radioactivity, and (3) support rulemaking decisions by NRC and EPA.
The sewage sludge/ash survey was coordinated by a subcommittee of ISCORS. The Sewage
Sludge Subcommittee was formed in 1995 to coordinate efforts to address the
recommendations of the 1994 GAO report.
This report summarizes the information collected in the survey and developed through the
analysis of samples. It also presents the sampling results in a series of tables broken down
with respect to the characteristics of classes of POTWs that participated in the survey.
Companion reports address the significance of the measured values of radionuclides present in
sewage sludge and ash and provide recommendations for POTW operators on how to deal with
any potential future problems.
Farouk Eltawila, Director
Division of Systems Analysis and Regulatory
Effectiveness
Office of Nuclear Regulatory Research
ISCORS was formed in 1994 to address inconsistencies, gaps, and overlaps in current radiation
protection standards. ISCORS is co-chaired by representatives of the NRC and the EPA, and includes
representation by the Department of Defense, the Department of Energy, the Department of Labor's
Occupational Safety and Health Administration, the Department of Transportation, and the Department
of Health and Human Services. Representatives of the Office of Management and Budget, the Office of
Science and Technology Policy, and various State and local regulatory agencies are observers at
ISCORS meetings.
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ACKNOWLEDGMENTS
The Sewage Sludge Subcommittee of the federal ISCORS (1) conducted a survey to collect
information concerning radioactive materials in sewage sludge and ash from POTWs;
(2) performed dose modeling to help with the interpretation of the results of the survey; and
(3) developed a guidance on radioactive materials in sewage sludge and ash for POTW owners
and operators. Sewage Sludge Subcommittee members who actively participated in the
development of the three reports associated with this project include (listed alphabetically):
Lee Abramson, NRC/Office of Nuclear Regulatory Research
Kevin Aiello, Middlesex County (New Jersey) Utilities Authority
James Bachmaier, DOE/Office of Environment, Safety and Health
Bob Bastian, EPA/Office of Wastewater Management
Lydia Chang, NRC/Office of Nuclear Material Safety and Safeguards
Weihsueh Chiu, EPA/Office of Research and Development
Chris Daily, NRC/Office of Nuclear Regulatory Research
Mark Doehnert, EPA/Office of Radiation and Indoor Air
Giorgio Gnugnoli, NRC/Office of Nuclear Material Safety and Safeguards
Paula Goode, EPA/EPA/Office of Radiation and Indoor Air
Jenny Goodman, New Jersey Department of Environmental Protection
Dale Hoffmeyer, EPA/Office of Radiation and Indoor Air
Rosemary Hogan, NRC/Office of Nuclear Regulatory Research
Anthony Huffert, NRC/Office of Nuclear Material Safety and Safeguards
Andrea Jones, NRC/Office of Nuclear Regulatory Research
Tom Lenhart, Northeast Ohio Regional Sewer District
Jill Lipoti, New Jersey Department of Environmental Protection
Roy Lovett, Department of Defense
Tin Mo, NRC/Office of Nuclear Regulatory Research
Donna Moser, NRC/Region II, Division of Nuclear Materials Safety
Robert Neel, NRC/Office of Nuclear Material Safety and Safeguards
Bob Nelson, NRC/Office of Nuclear Material Safety and Safeguards
Tom Nicholson, NRC/Office of Nuclear Regulatory Research
Tom O'Brien, NRC/Office of State and Tribal Programs
Judy Odoulamy, DOE/Office of General Counsel
William R. Ott, NRC/Office of Nuclear Regulatory Research
Hal Peterson, DOE/Office of Environment, Safety and Health
Alan Rubin, EPA/Office of Science and Technology
Steve Salomon, NRC/Office of State and Tribal Programs
Patricia Santiago, NRC/Office of Nuclear Material Safety and Safeguards
Dave Saunders, EPA/National Air and Radiation Environmental Laboratory
Duane Schmidt, NRC/Office of Nuclear Material Safety and Safeguards
Loren Setlow, EPA/Office of Radiation and Indoor Air
Behram Shroff, EPA/Office of Radiation and Indoor Air
Phyllis Sobel, NRC/Office of Nuclear Material Safety and Safeguards
Scott Telofski, EPA/National Air and Radiation Environmental Laboratory
Mary Thomas, NRC/RIII, Division of Nuclear Materials
Mary Wisdom, EPA/National Air and Radiation Environmental Laboratory
Anthony Wolbarst, EPA/Office of Radiation and Indoor Air
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ABBREVIATIONS
Am-241 americium-241
AMSA Association of Metropolitan Sewerage Agencies
Be-7 beryllium-7
Bi-212/214 bismuth-212/214
Bq becquerel
C-14 carbon-14
Ce-141 cerium-141
Ci curie
C F R Code of Federal Regulations
Co-57/60 cobalt-57/60
Cr-51 chromium-51
Cs-137 cesium-137
CWNS Clean Water Needs Survey
EHA Environmental Health Associates
EPA U.S. Environmental Protection Agency
Eu-154 europium-154
Fe-59 iron-59
FR Federal Register
GAO General Accounting Office
GBq gigabecquerel
ISCORS Interagency Steering Committee on Radiation Standards
ICR information collection request
H-3 hydrogen-3 (tritium)
1-125/131 iodine-125/131
ln-111 indium-111
K-40 potassium-40
kg kilogram
La-138 lanthanum-138
MDC minimum detectable concentration
MGD million gallons per day
NAREL National Air and Radiation Environmental Laboratory
NCRP National Council on Radiation Protection
ND not detected
NORM Naturally Occurring Radioactive Material
NPDES National Pollution Discharge Elimination System
NR not reported
NRC U.S. Nuclear Regulatory Commission
NSSS National Sewage Sludge Survey
OMB U.S. Office of Management and Budget
ORIA Office of Radiation and Indoor Air
P probability
Pa-234 protactinium-234
Pb-210/214 lead-210/214
PCS Permit Compliance System
PE Performance Evaluation
XI
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pCi
POTWs
QAPP
Ra-228
Sm-153
Sr-89
Th-227/228/230
TI-201/208
U-234/235/238
U.S.
Pu-238/239
Rn-219
Sm-153
Sr-89/90
WEF
Zn-65
ABBREVIATIONS (con't)
picocurie
publicly owned treatment works
Quality AssurOance Project Plan
radium-228
samarium-153
strontium-89
thorium-227/230
thalium-201/208
uranium-234/235/2388
United States
plutonium-238/239
radon-219
samarium-153
strontium-89/90
Water Environment Federation
zinc-65
XII
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1 INTRODUCTION
1.1 Congressional Interest
This survey responds, in part, to recommendations in the 1994 General Accounting Office
(GAO) report, "Nuclear Regulation: Action Needed to Control Radioactive Contamination at
Sewage Treatment Plants" (GAO/RCED-94-133). The GAO report recommended that NRC
determine the extent to which radioactive contamination of sewage sludge, ash, and related
byproducts from sewage treatment plants is occurring; directly notify the treatment plants that
receive discharges from NRC's and the Agreement State's licensees of the potential for
radioactive contamination because of the concentration of radioactive materials and of the
possibility that the plants may need to test or monitor their sludge for radioactive content; and
establish acceptable limits for radioactivity in sludge, ash, and related byproducts to protect the
health and safety of treatment workers and the public.
A joint House/Senate hearing was held in 1994 to officially release and address questions
raised in the GAO report. The hearing (U.S. Congress, 1994) was prompted by concerns
associated with elevated levels of radioactivity in incinerator ash at a major sewage treatment
plant in the Cleveland, Ohio, area. The GAO stated that, over the past 20 years, NRC had
documented elevated levels of radioactivity in sewage sludge or sludge incinerator ash from
certain publicly owned treatment works (POTWs). There had been no national surveys of
radiation levels present in sewage sludge or sludge incinerator ash to determine the extent of
potential radioactive contamination.
On the basis of limited information on radiation levels in sewage sludge and ash across the
country, GAO concluded that reconcentration of radionuclides may have been associated with
authorized effluent releases from both NRC and Agreement State licensees (GAO documented
this information and used it as a basis for its 1994 report). However, these problems occurred
prior to revisions to NRC's regulations with regard to releases from NRC licensees which
became effective in 1991.
1.2 POTW Industry Interest
In 1996, the Association of Metropolitan Sewerage Agencies (AMSA) conducted a limited,
confidential, voluntary survey of concentrations of radioactivity in sewage sludge and ash
samples from some of its member POTWs. The objective was to develop a better estimate of
the concentration of radioactivity in sewage sludges and sludge incinerator ashes. Samples
from 55 wastewater treatment plants in 17 States were supplied voluntarily and analyzed for
radioactivity. These plants were distributed across the country and ranged in size from small to
some of the largest POTWs in the U.S. The most significant levels of radioactivity were the
potassium and radium isotopes, which are naturally occurring radioactive materials.
1.3 Sources of Radioactivity at POTWs
Radionuclides are found naturally throughout the United States in varying concentrations
(Eisenbud and Gesell, 1997). Levels of naturally occurring radioactive materials (NORM) vary
throughout the States in soil and water used for drinking and industrial processes. Sewage
treatment facilities receive waste flows from residential, commercial, and industrial uses.
NORM from industrial process and drinking water treatment residuals (e.g., filter backwash, ion
1
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exchange fluids) may be a source of radioactive material entering a POTW. Another possible
source of radioactivity at a POTW is the authorized release of man-made radioactive materials
into the sewer system by NRC and Agreement State licensees.1 A major source of these
releases is radioactive materials used for medical diagnosis and treatment. Patient excreta
containing medical isotopes may contribute a significant fraction of the radioactive materials
released to sewer systems, but the significance would vary by location and by the facilities and
population served by the collection system. The removal and concentration of many
contaminants into residual solids by various processes used by POTWs and the reduction of
the volume of organic solids that contain these contaminants (e.g., by digestion or incineration
of sludge solids) can cause reconcentration of radioactive materials in the sewage treatment
facility's sewage sludge or ash.
Background information on the nature of radioactivity in sewage sludge can be found in NRC
reports entitled "Evaluation of Exposure Pathways to Man From Disposal of Radioactive
Materials Into Sanitary Sewer Systems" (NUREG/CR-5814) and "Reconcentration of
Radioactive Material Released to Sanitary Sewers in Accordance with 10 CFR 20"
(NUREG/CR-6289), published in 1992 and 1994 respectively. Another useful background
document is a report entitled "Radioactivity of Municipal Sludge" (EPA, 1986), issued by EPA
during the development of the first round of rulemaking for the 40 CFR Part 503 Biosolids Rule.
Two useful publications on naturally occurring radioactive materials are Environmental
Radioactivity from Natural, Industrial, and Military Sources by Eisenbud and Gesell (1997) and
"Evaluation of Guidelines for Exposures to Technologically Enhanced Naturally Occurring
Radioactive Materials" by the National Academy of Sciences (1999).
1.4 Federal Agency Regulations and Guidance
Federal and State regulations allow the disposal of specific amounts and concentrations of
radioactivity into sanitary sewer systems. In 1991, NRC revised its sewer disposal criteria,
partially in response to evidence that certain radioactive materials were reconcentrating in
sewage sludge or incinerator ash. The revised NRC regulations further limited the radioactive
materials that NRC licensees are allowed to discharge to sewer systems. The current NRC
regulations in 10 CFR 20.2003 permit release of specific quantities of soluble material into a
sanitary sewer. Monthly average concentrations must not exceed the concentrations listed in
Table 3 of Appendix B to Part 20, and the total quantities released in a year must not exceed
185 gigabecquerel (GBq) (5 curies [Ci]) of H-3, 37 GBq (1 Ci) of C-14, and 37 GBq (1 Ci) of all
other radionuclides combined. These limits do not apply to excreta from patients undergoing
diagnosis or treatment with radioactive material.
The EPA technical standard for the use and disposal of sewage sludge (biosolids) in
40 CFR Part 503 does not include limits for radioactive material. Some POTW operators have
requested that EPA regulations address radioactive materials to provide a basis for POTWs to
restrict discharges of radioactive materials to the sewage collection system.
Industrial users of radioactive materials that hold active licenses from the NRC or a State which
licenses theses activities based on an agreement with the NRC.
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1.5 1998-2000 Sewage Sludge Survey
Based on the 1994 GAO report recommendations, NRC and EPA decided to jointly fund a
voluntary survey of POTW sewage sludge and ash to help assess the potential need for NRC
and/or EPA regulatory decisions. While developing the information collection request (ICR) and
working with the U.S. Office of Management and Budget (OMB) to receive approval to conduct
the full survey, the agencies conducted a pilot study involving nine POTWs to field-test the
questionnaire for eliciting operating information from POTWs validate the sampling methods
and analytical procedures, and obtain feedback from the participating POTWs. The results of
the pilot study were summarized in a report issued jointly by NRC and EPA in 1999
(EPA 833-R-99-900, May 1999). The final survey procedures were slightly refined based on the
experiences with the pilot test cases and public comments on the ICR submitted to OMB for
approval of the survey. The final survey began in 1998 when the questionnaires was sent to
631 POTWs. More than 66% of the POTWs (420) responded by returning completed
questionnaires. Sewage sludge and ash samples from approximately 25 POTWs per month
were collected and shipped to the survey labs for analyses between October 1999 and
November 2000.
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2 SURVEY DESIGN AND IMPLEMENTATION
2.1 Survey Objectives
The objectives of the sewage sludge/ash survey were to (1) obtain national estimates of high-
probability occurrences of elevated levels of radioactive materials in sludge and ash at POTWs,
(2) estimate the extent to which radioactive contamination comes from either NRC/Agreement
State licensees or naturally occurring radioactivity, and (3) support rulemaking decisions by
NRC and EPA.
The important parameters of the survey are as follows (1) it is a voluntary survey, (2) only one
sample was collected at most POTWs at a single point in time, and (3) the survey was biased
to POTWs with the greatest potential to receive releases of radionuclides from NRC and
Agreement State licensees and to POTWs in areas of higher concentrations of NORM. The
reason for selecting POTWs for the survey was to obtain sufficient samples with radionuclides
above the minimum detection limits to allow some characterization of the levels and sources of
radioactivity and therefore, meet the objectives of this survey. The survey results are not a
statistically valid representation of radionuclide levels in sludge and ash nationwide. However,
the survey does provide a range for the possible concentrations of radionuclides in sludge and
ash nationwide.
2.2 Questionnaire Phase
The Subcommittee developed a questionnaire (Appendix C) to obtain information from POTWs
about their wastewater sources, wastewater and sludge treatment processes, and sewage
sludge disposal practices. The questionnaire also requested the ZIP codes for their collection
systems so that NRC could match licensees to their POTWs. NRC requested from each
Agreement State the names and addresses of licensees that could discharge to sewage
treatment facility sewer systems. The questionnaire was sent to 631 POTWs selected from the
more than 16,000 POTWs across the country. The Subcommittee used information from many
sources to identify POTWs with the greatest potential to receive radionuclides from licensees or
from naturally occurring sources. Information was obtained from the EPA regional offices,
EPA's Permit Compliance System2 and the 1996 NEEDS Survey,3 the NRC, the Association of
Metropolitan Sewerage Agencies (AMSA), the Water Environment Federation (WEF), the State
Water Pollution Control Programs and State Radiation Programs, Agreement State licensee
lists, and various State and Federal agency reports.
2 EPA's Permit Compliance System (PCS) is the system used by EPA to track permits issued
under the NPDES (National Pollution Discharge Elimination System) Program, which controls water
pollution by regulating point sources that discharge effluents into waters of the U.S.
3 The 1996 Needs Survey is the latest available report to Congress on the estimated clean water
needs of the U.S. The survey is a product of the Clean Water Needs Survey (CWNS), which is a joint
effort by the States and EPA to provide information on POTW collection and treatment facilities in
response to §205(a) and §516(b)(1) of the Clean Water Act.
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2.3 Sampling Phase
2.3.1 POTW Selection Process
The data from the POTWs that responded to the questionnaire were entered into a database
developed and maintained by Environmental Health Associates (EHA)4. Each month, the
Subcommittee Co-chairs selected 25 different POTWs from this database. The selection
process considered POTWs in one or more of the following categories:
1. All geographic areas of the U.S.
2. Recommended by States
3. High NORM areas as designated in the September 1998 EPA/Office of Radiation and Indoor
Air (ORIA) contractor report, "Identification of POTWs for NORM Analysis"
4. Receive discharges from landfills (receiving landfill leachates) or Superfund or Federal
cleanup sites
5. Have (or used to have had) sludge incinerators
6. Different flow rates serving different size service areas
7. Sampled in the National Sewage Sludge Survey
8. Receive drinking water treatment plant residuals
9. Serve areas with industrial uses of radioactive materials likely to discharge to the sewer
system
Samples were obtained from POTWs in each of the 10 physiographic regions of the US
(Table 2.1). The divisions were obtained from Fenneman and Johnson (1946). Figure 1 shows
the approximate geographic locations of the 313 POTWs sampled.
4EHA has an NRC contract to manage the database survey.
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TABLE 2.1 Samples From POTWS in Each Physiographic Region
Physiographic Division No. of POTWs
Alaska 2
Appalachian Highlands 91
Atlantic Plain 58
Hawaii 4
Interior Highlands 4
Interior Plains 106
Intermontane Plateaus 18
Laurentian Upland 2
Pacific Mountain System 24
Rocky Mountain System 4
Total 313
2.3.2 Sample Collection
A list of selected POTWs for sample collection and analyses was sent to ORISE each month.
ORISE assigned survey codes and sent sampling kits to the POTWs. This process was
repeated monthly to accommodate the workload at the laboratories. The POTW operators
collected the samples using containers and guidance provided to them in the sampling kit from
ORISE. The POTWs were instructed to follow procedures similar to those they use to take
routine samples for monitoring chemical pollutants. The samples were shipped to the
designated laboratory. ORISE maintained the key to the assigned codes to ensure anonymity
(a feature of the survey intended to encourage participation). The key was later transferred to
the data management contractors (EHA) to allow reporting back to the facilities of their
individual results.
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Figure 1 POTWs Located by Geographic Division
2.3.3 General Analytical Procedures
Sludge/ash analyses were performed by ORISE and EPA's National Air and Radiation
Environmental Laboratory (NAREL) in Montgomery, Alabama. Each laboratory used approved
analytical procedures for routine environmental samples. The comparability of these
procedures was previously evaluated during the pilot study. Additional information on analytical
procedures is contained in the Quality Assurance Project Plan (QAPP) (Appendix D). The
laboratories screened operate under laboratory quality assurance/quality control programs and
participate in external performance evaluation (PE) programs. Quality assurance activities
conducted on the project included an audit conducted by U.S. EPA headquarters to assess
NAREL compliance with the QAPP. The audit concluded that activities relating to the QAPP
were in compliance. The laboratories screened samples using their standard procedures for
gross alpha, gross beta, and gamma spectrometry. Each month a minimum of 10% of the
sludge/ash samples that had gross alpha or gross beta activity detected were chosen for
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radionuclide-specific analysis. The specific radionuclides analyzed were Sr-89, Sr-90, several
isotopes of thorium and uranium, and their progeny, Pu-238, Pu-239, and Am-241. These
radionuclides are of specific interest because of their potential presence in sewage sludge and
ash. The isotopes of uranium and thorium are present in rock in the earth and leach into
surface waters on the earth by natural processes such as erosion after rain and floods. Such
radionuclides are referred to as NORM. Uranium and plutonium may be found in the effluents
of nuclear fuel processing facilities. Certain radionuclides are commonly used in medical
procedures including Co-57, Cr-51, ln-111, 1-125, 1-131, Sm-153, Sr-89, TI-201, and TI-202. All
detectable radionuclides were decay corrected to the time of the sample collection.
Uncertainties were rounded to one significant figure. Concentrations were rounded to the same
decimal place as the corresponding uncertainty.
2.3.4 Sampling and Data Quality Limitations
The survey was not random. It was biased to favor those POTWs most likely to have
measurable levels of radioactivity. The survey was also voluntary and individual sewage
treatment facilities could choose not to participate. Because the survey was biased and
voluntary, statistical inference and probability cannot be used to interpret the results as
representative of radionuclide levels in sludge and ash nationwide. The survey was designed to
obtain data on the levels of radioactivity in sludge and ash at POTWs from across the country
emphasizing POTWs with the greatest potential to have detectable levels of radioactive
materials.
Use of this data to characterize sewage sludge at a particular POTW is inappropriate. The
results cannot be used to make any conclusions about the levels of radioactive materials in
sewage sludge and ash products over a longer period of time, nor can the results be used to
determine whether any of the measured results were in fact levels that occurred only for a
shorter period of time. This would require a much more extensive survey focused on individual
POTWs of interest.
Some facilities have more than one type of sewage sludge product (e.g., liquid slurry,
dewatered cake, compost, heat dried pellets). These facilities were requested to send a
sample for each of their final products. Thirty-five POTWs sent ash samples resulting from
incineration of their sewage sludge. No samples were lost in transit or during analysis, and no
resampling was conducted. In total, sludge or ash samples from 313 POTWs (2 of which sent
only an ash sample) were analyzed, and these results were included in all further data analyses
conducted in this study.
The greatest uncertainty in the survey results is probably due to the field sample design.
Specifically, the field sample design did not assess the variability over spatial and temporal
boundaries either at a particular POTW or over all POTWs or groups of POTWs. Field
uncertainty was not controlled more closely because of the voluntary participation by the
POTWs and because of a small number of samples and because the POTWs particpated
voluntarily and did the sampling. The field sample design uncertainty was not estimated and
quantitative values are not provided.
With respect to the actual field sampling procedures used and the representativeness of each
sample, there was control in that the field sampling procedures provided to the POTWs were
8
-------
based on the same procedures that POTWs use for compliance with the 40 CFR Part 503
Biosolids Rule (EPA, November 9, 1990). Only basic assumptions can be made about the
representativeness of a particular sample because the sample collection is based on the
judgement of the POTW operator who took the samples and on the processes sampled. Since
each POTW collected its own samples, a higher field sampling variability was expected than if
one organization collected all samples. There is also the possibility of intrasample variability,
which is more significant for certain analyses such as alpha spectrometry.
Sources of field uncertainty include sample shipping error and sample contamination (e.g.,
cross-contamination) but are assumed to be minimal. Seals and chain of custody were used
(see QAPP, Appendix D), and radioactivity likely to be the source of cross contamination was
controlled by transportation regulations. The likelihood of field bias is low because the sample
procedures are based on the same procedures that POTWs use for their routine regulatory
compliance sampling. Likelihood of field sampling loss is low because the likelihood of sample
loss (e.g., volatiles) is low for most radionuclides.
The field results are not reproducible individually, especially if there is variability of radioactivity
concentration over space and/or time. However, in the aggregate, they are considered to be
representative of the upper range of the distribution of values of radionuclide concentrations in
sludge and ash. The lab results were designed to be reproducible and comparable (a major
objective of the pilot study discussed in Section 1.5 of this document).
-------
3 QUESTIONNAIRE SUMMARY
The Radiological Survey Questionnaire is reproduced in Appendix C. While 420 POTWs
responded to the survey, only 313 facilities actually supplied sludge and/or ash samples.
Responses to the survey questionnaire from these 313 POTWs are summarized in table format
(see Table 3.1) to provide a detailed description of the population of POTWs that participated in
the full survey.
3.1 Characteristics of the Population of 313 POTWs
Although not a statistically valid representation of the more than 16,000 POTWs in operation in
the U.S. the population of 313 POTWs generally exhibits characteristics that are typical of
POTWs serving most areas of the country. The majority of the 313 POTWs in the survey
(86%) employ at least a secondary level of treatment of the wastewater stream. Many (nearly
40%) employ advanced treatment techniques. Most of the POTWs are small or medium sized.
Approximately half of the POTWs reported a flow rate of 10 million gallons per day (MGD) or
less. Only 15 of the 313 POTWs indicated that they treat greater than 100 MGD. This size
range is comparable to that of the POTWs nationwide, where approximately 97% treat 10 MGD
or less, and less than 1% have a capacity of 100 MGD or greater. Over 90% of the POTWs
state that the industrial component of the wastewater stream is less than 50%. Approximately
30% of the POTWs have combined sanitary and storm water collection systems.
10
-------
TABLE 3.1 Summary of Survey Questionnaire Responses of 313 Facilities Sampled
Treatment level
Primary 180
Secondary 271
Advanced 121
Flow Rate
lOMGDorless 153
More than 10 MGD, less than/equal to 50 MGD 96
More than 50 MGD, less than/equal to 100 MGD 30
Greater than 100 MGD 15
No response/no units reported 19
Treatment Process
No processing in the last 12 months 7
Thickening 239
Mechanical dewatering 239
Heat treatment/wet air oxidation 12
Aerobic digestion 64
Anaerobic digestion 146
Composting 32
Lime stabilization 34
Alkaline stabilization 16
Air drying beds 37
Heat drying/pelletizing 6
Sewage sludge treatment/storage lagoon(s) 29
Sewage sludge storage bins or piles 44
Incineration 54
Other sewage sludge treatment processes 24
Use and Disposal Practice
Land application 175
Surface disposal 21
Disposal in municipal solid waste landfill 130
Transfer to another facility 60
Other disposal 35
No Response 1
Primary Drinking Water Source
Municipal water supply from surface water(s) 193
Municipal water supply from groundwater well(s) 166
Private wells 54
Private water supply from surface water source(s) 19
No Response 3
11
-------
TABLE 3.1 Summary of Survey Questionnaire Responses of 313
Facilities Sampled (con't)
Receive Discharges of Drinking Water Residuals
Yes 102
No 208
No response 3
Combined Sanitary and Storm Water Sewers
Yes 94
No 219
Receive Sludge From Other Facilities for Processing
Yes 80
No 233
Receive Septage
Yes 187
No 120
No response 6
Percentage of Annual Average Daily Flow Rate That Is Industrial
Less than 50% 285
50% or greater 15
No response/unknown 13
Have Previously Tested for Radioactive Materials
Yes 61
No 249
No response 3
More Than One Final Sewage Sludge Production Facility
Yes 32
No 281
State Recommendation From Request in State Letter (NRC, 1998)
Yes 64
No 249
Located in High NORM Area From EPA/ORIA report,
"Identification of POTWs for NORM Analysis" (EPA, 1998)
Yes 89
No 224
Potentially Receives From Landfill, SUPERFUND, or Federal Cleanup Sites
Yes 28
No 285
Participated in National Sewage Sludge Survey
Yes 87
No 226
12
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4 RADIOACTIVITY DATA ANALYSIS
4.1 Summary of Concentrations of Radionuclides in Sewage Sludge and Ash
After the data were entered into the database, summary statistics (including median, minimum
and maximum detected concentrations, 95th percentile, and frequency of detection) were
calculated for each radionuclide in each sampled medium (ash and sludge). Negative
concentrations were treated as not detected for these calculations. In cases where there was
an even number of analyses and the median fell between a nondetected (ND) and detected
concentration, a range was reported. For example, the results of a set of four analyses were
(ND, ND, 5, and 7), the median would be reported as "ND to 5." The minimum detectable
concentration (MDC) of a radionuclide in a sample is the smallest concentration of analyte
expressed in this study as pCi/g (1 pCi/g = 37 Bq/kg) of sludge or ash that produces a signal
with a 95% confidence of exceeding a decision (detection) level. Finally, the number of times a
radionuclide was detected relative to the total number of analyses is listed to provide for a more
complete perspective for interpreting the results. These summary statistics presented in
Tables 4.1 and 4.2 allow the reader to examine patterns of occurrence.
No widespread or nationwide public health concern was identified by the survey because no
significant adverse condition or excessive concentrations of radioactivity were observed in
sludge or ash. The survey was not designed to identify unique or isolated instances in which
high levels of radionuclides may be present in sewage sludge or ash, and inferences to high
levels of radionuclides cannot be made from the survey results alone (see Section 3.4.4). The
dose modeling report, survey results and recommendations will provide information that may be
useful in making decisions as to site-specific sampling or testing.
13
-------
Table 4.1 Concentrations of Radionuclides in Sludge:
All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37
Bq/kg.
Radionuclide
Alpha
Beta
Am-241
Be-7
Bi-212
Bi-214
C-14*
Ce-141
Co-57
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
H-3*
1-125
1-131
ln-111
K-40
La-138
Pa-234m
Pb-210
Pb-212
Pb-214
Pu-238
Pu-239
Ra-223
Ra-224
Ra-226
Ra-228
Rn-219
Sm-153
Sr-89
Sr-90
Th-227
Th-228
Th-230
Th-232
Th-234
TI-201
TI-202
TI-208
U-234
U-235
U-238
Zn-65
Min
ND
1.7
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
0.09
0.02
ND
ND
ND
ND
0.18
ND
0.18
ND
* Indicates concentrations fort
Median
7
13
ND
1.2
ND
0.3
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.3
ND
1.8
ND
4
ND
ND
ND
0.44
0.31
0.01
0.003
ND
ND
2
0.82
ND
ND
0.35
0.1
ND
0.605
0.34
0.2
0.6
ND
ND
0.07
1.95
ND
1.4
ND
95th P
34
34
ND
9
1.3
2.3
1
ND
ND
ND
ND
ND
0.11
ND
ND
5
ND
51
0.04
12
ND
7
4
1.9
2.6
0.07
0.04
ND
0.9
13
5.1
ND
ND
20
1
0.1
4.1
1
0.6
6.7
46
0.53
0.96
17
0.45
12
ND
Max
137
93
2.5
22
13
16
3
0.016
0.26
5.1
3.5
0.04
3.6
21
0.4
8
40
840
3.6
26
0.07
27
13
15
17
0.19
0.12
0.09
12
47
38
ND
27
70
9.4
0.5
9
1.7
1.6
23
241
1.16
4.8
44
3.1
26
0.06
No. Detects/
No. Analyses
309/311
311/311
10/311
263/311
101/311
238/311
63/158
1/311
6/311
13/311
6/311
1/311
133/311
1/311
1/311
111/158
11/311
246/311
19/311
308/311
1/311
80/311
135/311
303/311
253/311
75/92
68/92
2/311
47/311
289/311
271/311
0/311
1/311
68/98
64/98
49/207
92/92
92/92
92/92
191/311
151/311
73/311
180/311
92/92
112/311
92/92
1/311
his radionuclide are expressed in pCi/g wet.
14
-------
Table 4.2 Concentrations of Radionuclides in Ash:
All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37
Bq/kg.
Radionuclide
Alpha
Beta
Am-241
Be-7
Bi-212
Bi-214
C-14*
Ce-141
Co-57
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
H-3*
1-125
1-131
ln-111
K-40
La-138
Pa-234m
Pb-210
Pb-212
Pb-214
Pu-238
Pu-239
Ra-223
Ra-224
Ra-226
Ra-228
Rn-219
Sm-153
Sr-89
Sr-90
Th-227
Th-228
Th-230
Th-232
Th-234
TI-201
TI-202
TI-208
U-234
U-235
U-238
Zn-65
Minimum
5
15
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
7.4
ND
ND
ND
0.36
0.61
ND
ND
ND
ND
ND
0.65
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1.2
ND
0.8
ND
Median
27
43
ND
4.3
1.2
2.4
ND
ND
ND
ND
ND
ND
0.07
ND
ND
ND
ND
0.22
ND
14.2
ND
3
ND
1.5
2.9
0.015
0.01
ND
ND
3
2.5
ND
ND
1
0.2
ND
1.6
0.75
0.505
3.6
0.62
ND
0.66
5.55
0.15
3.3
ND
95th P
93
95
ND
15.4
3.5
14
1
ND
ND
ND
0.3
ND
0.23
ND
ND
4
0.4
20
ND
20.9
ND
11
8.5
3.3
14.8
0.1
0.06
0.2
2
18
17
0.2
ND
60
1
0.3
6.7
2.3
1
11
73
0.99
2.3
49
0.7
35
ND
Maximum
178
140
0.21
30
15.7
16
1
ND
0.17
3.46
35
ND
0.37
ND
ND
8
1
81
ND
22.4
ND
77
12.3
15
16.4
0.1
0.17
0.8
4.9
22
30
0.4
ND
300
6
1.1
14
2.6
1.7
80
105
1.53
13.5
91
3.4
74
0.06
No. Detects/
No. Analyses
35/35
35/35
2/35
34/35
25/35
34/35
5/18
0/35
1/35
2/35
5/35
0/35
34/35
0/35
0/35
7/18
4/35
23/35
0/35
35/35
0/35
30/35
16/35
35/35
35/35
20/28
21/28
4/35
15/35
33/35
35/35
3/35
0/35
20/30
24/30
14/33
27/28
27/28
27/28
31/35
19/35
7/35
32/35
28/28
30/35
28/28
1/35
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
15
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4.2 Comparison of Radioactivity in Sewage Sludge and Ash to Radioactivity in Other
Products
To provide a perspective for interpreting the data in this report, Table 4.3 provides a
comparison of concentrations of radionuclides detected in sludge and ash samples analyzed in
this survey to typical ranges of radionuclide concentrations previously reported in U.S. soils and
commonly used products such as phosphate fertilizers and building materials. The sources for
these values are noted in the footnotes to Table 4.3. Although concentrations for some
radionuclides in phosphate fertilizers are high relative to the other sources considered,
phosphate fertilizers are usually blended with other fertilizer components (containing nitrogen
and potassium) before application, frequently before point-of-sale. This results in a 10% to
50% reduction of the concentrations listed in Table 4.3 at the point-of-use for typical fertilizers
or in commercially available blended fertilizer products (National Council on Radiation
Protection and Measurements [NCRP],1987). Therefore, it is inappropriate to use the values in
this table to infer possible levels of radionuclides in commercially available fertilizers, in
fertilizers at point-of-use, or in the soil after application. Values in this table do not reflect the
uncertainty associated with the ranges.
16
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Table 4.3 Survey Concentration Ranges and Typical U.S. Background Concentrations of
Radionuclides in Soil, Fertilizer, and Common Building Materials
(All values are in pCi/g-dry weight)1
Radionuclide Soil2 Phosphate Building Sludge Ash
Fertilizer3 Materials2 Concentrations4 Concentrations4
Bi-212
Bi-214
Cs-137
K-40*
Pa-234m*
Pb-212*
Pb-214*
Ra-223*
Ra-224*
Ra-226*
Ra-228*
Th-227*
Th-228*
Th-230*
Th-232*
Th-234*
TI-208*
U-234*
U-235*9
U-238*
0.1 -3.5
0.1 -3.8
0.1 -0.26
2.7-19
0.1 -3.8
0.1 -3.5
0.1 -3.8
<0.1 -0.2
0.1 -3.5
0.1 -3.8
0.1 -3.5
<0.1 -0.2
0.1 -3.5
0.1 -3.8
0.1 -3.5
0.1 -3.8
0.1 -3.5
0.1 -3.8
<0.1 -0.2
0.1 -3.8
0.1 -4.6
4.0- 140
NDA7
32-1608
4.0-140
0.1 -4.6
4.0-140
0.2-6.6
0.1 -4.6
0.1 -24
0.1-4.6
0.2-6.6
0.1 -4.6
4.0- 140
0.1 -4.6
4.0-140
0.1 -4.6
4.0- 140
0.2-6.6
4.0-140
0.1 -3.7
2.5-5.05
NDA
0.8-30
0.2-5.05
0.1 -3.7
0.2-5.0
0.1 -0.25
0.1 -3.72
0.1 -3.5
0.1 -3.72
0.1 -0.2
0.1 -3.7
0.2-5.0
0.1 -3.7
0.2-5.0
0.1 -3.7
0.2-5.0
0.1 -0.2
0.2-5.05
0-13
0-16
0-3.6
0-26
0-27
0-15
0-17
0-0.09
0-12
0-47
0-38
0-0.5
0.07-9
0.09-1.7
0.02-1.6
0-23
0-4.8
0.18-44
0-3.1
0.18-26
0-16
0-16
0-0.37
7.4 - 22
0-77
0.36-15
0.61 -16
0.1 -0.8
0-4.9
0-22
0.65-30
0-1.1
0- 14
0-2.6
0-1.7
0-80
0-14
1.2-91
0-3.4
0.8 - 74
' Naturally occurring radionuclide
Notes:
1.
The curie (Ci) is the unit for expressing a quantity of radioactivity. The unit normally used to describe the
concentrations of radioactivity in the environment is picocuries per gram (pCi/g); 1 pCi/g=37 Bq/kg.
Low-Level Environmental Radioactivity - Sources and Evaluation (1995) by Tykva and Sabol is the
source of data for concentrations of radionuclides in soil and building materials, except for the
concentrations of U-238, U-235, and Cs-137, which came from References 9 and 6, respectively. The
concentrations of the daughters or decay products of U-238 (such as Th-234 and Ra-226) those of
U-235 (such as Th-227 and Ra-223) and those of Th-232 are set equal to those of their respective
parent radionuclides by assuming that the daughters are in secular radioactive equilibrium with the
parent radionuclides.
NCRP Report No. 95 (pp. 24-32) is the source of data for the concentrations of radionuclides in
phosphate fertilizers (not typical blended fertilizers), except for the concentration of K-40 in phosphate
fertilizers, which came from the reference in Note 8. The concentrations of typical blended commercial
fertilizers would be 10% to 50% of these values.
A value of zero as the lower boundary of the range occurs when a very low concentration is rounded to
reflect the same number of decimal places as the two sigma laboratory uncertainty. Nondetected values
are not included in this range.
Eisenbud and Gesell, 1997.
The Cs-137 concentration range in soil was obtained from Figure 4-4 (p. 94) of NCRP Report No. 50,
1976.
NDA means no data available
Source for data on K-40 in fertilizers, S. Cohen and Associates, 1997.
The values for U-235 in soil, fertilizer, and building materials are based on the concentrations of U-238 in
the same materials and the natural ratio of U-235 to U-238.
17
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4.3 Correlation Analysis
To examine the relationships among the different radionuclide concentrations observed in the
survey, a correlation analysis was run. The analysis grouped radionuclides into clusters having
similar patterns of concentrations in the survey data. Because so few ash samples were
submitted, only the sludge samples were considered in this analysis. Data were standardized
to a distribution with a mean of zero and a standard deviation equal to one both with and
without a logarithmic transformation. Standardization of concentration values provides a
consistent variable for comparing radionuclides in the survey, and a logarithmic transformation
often increases the efficiency of the calculations used in the correlation analysis. When log-
transformed, nondetected values were set to a minimal value of 0.001 pCi/g, and a sensitivity
analysis confirmed that treating nondetected values in this way did not change the overall
results. The correlations were determined by examining the correlation matrix of the data for
clusters, both by inspection of the matrix itself and through principal component analysis.
Clusters among the members of the Ra-226 and Ra-228 decay chains in the survey (Ra-226,
Bi-214, Pb-214, Ra-228, Th-228, Ra-224, Pb-212, Bi-212, and TI-208) indicate a not
unexpected strong association in the samples for these radionuclides. A strong clustering was
also found among the uranium isotopes U-234, U-235, U-238 and the U-238 decay chain
daughters Th-234 and Pa-234m. Again, such a relationship would be expected from the decay
chain relationship. A negative correlation was observed between detection of the radium group
and the uranium group. This correlation indicates that when radium was present in relatively
high concentrations in a sample, it is likely that uranium was present at relatively low
concentrations or not detected, and vice versa. In addition, the medical isotopes ln-111, 1-131,
TI-201, TI-202, and Co-57 tended to cluster together. Due to the limitations of the survey
design, weaker correlations were not considered adequate to support conclusions about
general relationships and are not discussed in this report.
18
-------
These observed clusters are generally in line with what would be expected due to common
radionuclide sources and their degradation products. Examples of expected clusters are
summarized in the following table.
Table 4.4 Expected [Groupings] Clustering of Radionuclides Based on Process and
Degradation Relationships
up Radionuclides
Medical radionuclides5 Co-57, Cr-51, ln-111, 1-125, 1-131, Sm-153, Sr-89,
TI-201.TI-202
Fission and activation products Cr-51, Fe-59, Co-57, Co-60, Zn-65, Sr-89, Sr-90,
other than Medical Ba-140, Cs-134, Cs-137, Ce-141, Sm-153, Eu-154
Radionuclides
C-14 and H-3 C-14 and H-3
NORM other than U or Th series Be-7, K-40, La-138
Th-232 decay series Th-232, Ra-228, Th-228, Ra-224, Pb-212, Bi-212, TI-208
Transuranics Pu-238, Pu-239, Am-241
U-235 decay series U-235, Th-227, Ra-223, Rn-219
U-238 decay series U-238, Th-234, Pa-234m, Pa-234, U-234, Th-230,
Ra-226, Pb-214, Bi-214, Pb-210
Physical processes in the environment and types of radionuclide releases are likely to underlie
some of the observed correlations among clusters of radionuclides. For example, the negative
correlation between radium and uranium could be explained by the pH-dependent solubility of
the two elements. In natural waters of pH 7-10, uranium ions in geologic formations form
complexes with carbonate and become soluble, thereby entering the drinking water source
(Cothern and Rebers, 1990). Radium becomes soluble at a lower pH (5 or less), and is,
therefore, most likely to be present in acidic groundwater (USGS, 1998). Little can be
concluded about other expected groups (e.g., fission/activation products) because lower
activities in these radionuclides were observed, and the correlations were weaker.
Further analyses of the data were performed to determine if geographic location or POTW
characteristics, as identified in the questionnaire responses, had any relationship to
radionuclide concentrations. The radionuclide concentrations were grouped by relationships of
source or decay series as shown in Table 4.4 above. The data were sorted by these
radionuclide groupings and by information provided by the POTWs in response to the survey
questionnaires. The tables in Appendix A show the summary statistics of minimum, median,
95th percentile, maximum radionuclide concentration, and frequency of detection. Tables 4.1
and 4.2 summarize the complete data set. The remaining tables in Appendix A summarize the
data by radionuclide group for other POTW characteristics identified in the questionnaire
responses.
5University of Arkansas for Medical Sciences, College of Pharmacy
(http://nuclearpharmacy.uams.edu/RPLIST.html)
19
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4.4 Association of Questionnaire Responses With Radionuclide Concentrations
Analyses were performed to determine whether different questionnaire response categories
were related to shifts in radionuclide concentrations. The analyses were restricted to
radionuclides with at least a 50% frequency of detection, except for Cs-137 (detect rate = 43%).
Cesium-137 was included because it had the highest detect rate of any radionuclide analyzed in
all 311 samples of the fission and activation product group. Altogether 23 radionuclides were
analyzed.
Performing multiple analyses (N = 23 radionuclides) for each survey question increases the
chances of defining spurious relationships in the data. In other words, because statistical
significance is defined as a relationship with a very low probability of occurrence, the more tests
performed, the more likely it is that low-probability findings will occur through chance alone. To
correct for this effect and increase the confidence that reported significant relationships were
the result of actual associations and not simply chance, only relationships with less than a
probability of 0.002 were assumed to represent a potentially useful (significant) association
between questionnaire response categories and radionuclide concentrations.
4.5 Results
Table 4.5 shows the strength of the association between the factors considered in the survey
questionnaire and against the 23 radionuclides analyzed. Physiographic division was the
POTW characteristic most strongly associated with radionuclide concentrations (Section 4.5.1).
Other POTW characteristics showing strong associations with radionuclide concentrations were
(1) the primary source of drinking water and (2) the average daily flow in (million gallons per day
[MGD]). No questionnaire responses were associated with differences in radionuclide
concentrations in sludge for the C-14 and H-3 group.
The relationship between radionuclide concentrations and the response categories for specific
items on the questionnaire was sometimes positive and sometimes negative. In other words,
the characteristic or level of response to a questionnaire item was sometimes associated with
higher concentrations of a particular radionuclide or radionuclide group, while other categories
were sometimes associated with lower concentrations of those or other radionuclides. The
direction of association between questionnaire responses and radionuclide concentrations is
discussed in the following sections and summarized in Tables 4.6 through 4.9 for the three
POTW characteristics most strongly associated with radionuclide concentration patterns:
physiographic province, drinking water source, and average daily flow through the POTW.
20
-------
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4.5.1 Physiographic Divisions
As expected, the location of POTWs within major physiographic divisions of the United States
(Figure 1) affected radionulide concentrations. Physiographic divisions represent distinctive
areas having common topography, rock types and structure, and geologic and geomorphic
history (Fenneman and Johnson, 1946) and should have similar levels of naturally occurring
radioactive materials (NORM). Concentrations of U-234 and U-238 were higher than the
average in the Intermontane Plateaus and lower than the average in the Atlantic Plain.
However, some other members of the U-238 series (Bi-214 and Pb-214) were highest in the
Atlantic Plain and the Interior Plains. The Interior Plains showed a strong association with
higher concentrations of Ra-228, while Hawaii and the Pacific Mountains showed a strong
association with the lower concentrations. These relationships are summarized in Table 4.6.
Table 4.6 Relationships of Physiographic Division to Concentrations of Radionuclides in Sludge
Samples
Group
Nuclide1 Lower concentrations2 Higher concentrations3
Fission and
Activation
Products
Medical
Isotopes
NORM
U-238 Decay
Series
Cs-137
TI-201
Be-7
K-40
Th-232 Decay Pb-212
Series
Ra-2281
TI-208
Bi-2141
Pb-2141
Ra-226
Th-230
Th-2341
U-2341
U-2381
Atlantic Plain
Rocky Mountains
Appalachian Highlands
Rocky Mountains, Hawaii Appalachian Highlands
Rocky Mountains
Atlantic Plain
Intermontane Plateaus,
Pacific Mountains
Hawaii, Pacific
Mountains
Intermontane Plateaus,
Pacific Mountains,
Hawaii
Hawaii, Pacific
Mountains, Appalachian
Highlands
Hawaii, Pacific
Mountains, Appalachian
Highlands
Appalachian Highlands
Atlantic Plain
Atlantic Plain
Interior Plains
Rocky Mountains, Interior Plains,
Atlantic Plain
Atlantic Plain, Interior Plains
Atlantic Plain, Interior Plains
Atlantic Plain, Interior Plains
Atlantic Plain
Intermontane Plateaus, Rocky
Mountains
Intermontane Plateaus
Intermontane Plateaus
1. These radionuclides showed a strong association with the distribution of responses identifying
the physiographic location of the POTW.
2. "Lower concentrations" are significantly lower than the average concentration.
3. "Higher concentrations" are significantly higher than the average concentration.
22
-------
4.5.2 Primary Source of Drinking Water
Concentrations of radionuclides in sludge showed a stronger association with whether drinking
water came from groundwater or surface water than with whether water supplies were public or
private. Only two radionuclides, Be-7 and Bi-214, showed strong associations with the source
of drinking water. Sludge that included groundwater sources had higher concentrations of
Bi-214, while municipal supplies served by surface water had lower concentrations. Sludge
from areas with surface water sources showed higher concentrations of Be-7, while areas
served primarily by groundwater had lower concentrations. Table 4.7 tabulates these and the
weaker relationships observed.
Table 4.7 Relationships of Primary Drinking Water Source to the Relative Concentration
of Radionuclides
Group Nuclide Lower Higher
Concentrations Concentrations
Fission and Activation Products
NORM
Th-232 Decay Series
U-238 Decay Series
Cs-137
Be-7*
Ra-228
Th-228
Th-232
TI-208
Bi-214*
Pb-214
Ra-226
B
BC, B
A
A, ABC
AB
NR, A
A
A
A
A, ABC
B
BC
A
B
B
B
A = municipal supply from surface water
B = municipal supply from groundwater
C = private wells
D = private surface water
NR = not reported
*Radionuclides showing a strong association with the questionnaire response regarding primary source
of drinking water.
23
-------
4.5.3 Average Daily Flow
Daily flow volume from POTWs did not show a consistent relationship to radionuclide
concentrations. Qualitative correlation of concentrations with flow can be assessed by the
pattern of pluses and minuses in Table 4.8. The pluses and minuses indicate flow categories
with significantly higher or lower concentrations. Radionuclides with higher concentrations at
higher flow volumes have an overall positive correlation and radionuclides with higher than
average concentration at low flow volumes have an overall negative correlation with flow
volume. Based on this approach, the medical isotopes showed a strong association with
increased flow. Thorium-228 showed a strong relationship with POTWs with lower daily flow.
Table 4.8 includes other radionuclides showing weaker relationships.
Table 4.8 Effect of Average Daily Flow on Radionuclide Concentration
Flow (millions of gallons per day)
Group Nuclide <10 10-50 50-100 >100 NR
Medical Isotopes
NORM
Th-232 Decay Series
Transuranics
1-131 - +
TI-201 - +
Be-7 +
Pb-212 +
Ra-228 +
Th-228 +
Th-232
Pu-239 +
Plus and minus symbols identify categories with significantly higher and lower than average
concentrations of radionuclides.*
24
-------
REFERENCES
Code of Federal Regulations, Title 40, U.S. Environmental Protection Agency, Part 503,
"National Sewage Sludge Survey: Availability of Information and Data, and Anticipated Impacts
on Proposed Regulations; Proposed Rule," Federal Register. Vol. 55, No. 218, pp. 47210-
47283, November 9, 1990.
S. Cohen and Associates, "Final Draft NORM Waste Characterization,"EPA Contract
No. 68D20155, WA No.5-09, pp. B-3-1 to B-3-24, 1997.
Cothern, Richard C., and Rebers, Paul A., "Removal of Uranium from Drinking Water by
Conventional Treatment Methods ", Radon, Radium and Uranium in Drinking Water, Lewis
Publishers, Chelsea, Michigan, 1990.
Eisenbud, M. and Gesell, T., Environmental Radioactivity from Natural, Industrial, and Military
Sources, 4th Edition, Academic Press, San Diego, 1997.
Environmental Protection Agency (U.S.) (EPA), "Radioactivity of Municipal Sludge," Office of
Water Regulations and Standards, EPA: Washington, D.C.,1986.
. EPA 832-R-97-003, "1996 Clean Water Needs Survey Report to Congress
Assessment of Needs for Publicly Owned Wastewater Treatment Facilities, Correction of
Combined Sewer Overflows, and Management of Storm Water and Nonpoint Source Pollution
in the United States," Office of Water, EPA: Washington, D.C., September 1997.
.EPA Contract No. No. 68-D5-0174, "Identification of POTWs for NORM Analysis,"
EPA, Washington, D.C.,1998.
. EPA 832-R-99-900, "Joint NRC/EPA Sewage Sludge Radiological Survey: Survey
Design and Test Site Results," May 1999.
. EPA/NRC, "Quality Assurance Project Plan, EPA/NRC Sewage Sludge Survey,"
October 2001.
Fenneman, Nevin M., and Johnson, Douglas W.,"Physical Divisions of the United States,"
U.S. Geological Survey (USGS) special map, USGS, Washington, D.C, 1946.
GAO/RCED-94-133, "Nuclear Regulation: Action Needed to Control Radioactive
Contamination at Sewage Treatment Plants," May 1994.
National Academy of Sciences, "Evaluation of Guidelines for Exposures to Technologically
Enhanced Naturally Occurring Radioactive Materials," Committee on Evaluation of EPA
Guidelines for Exposure to Naturally Occurring Radioactive Materials, National Research
Council, National Academy Press, Washington, D.C. 1999.
25
-------
National Council on Radiation Protection and Measurements (NCRP), NCRP Report No. 50.
"Environmental Radiation Measurements," Recommendations of the National Council on
Radiation Protection and Measurements, Figure 4-4, p. 94, 1976.
. NCRP Report No. 95, "Radiation Exposure of the U.S. Population from Consumer
Products and Miscellaneous Sources," pp. 24-32, 1987.
Nuclear Regulatory Commission (NRC) (U.S.), NUREG/CR-5814, "Evaluation of Exposure
Pathways to Man From Disposal of Radioactive Materials Into Sanitary Sewer Systems,"
NRC, Washington, D.C., 1992.
. NUREG/CR-6289, "Reconcentration of Radioactive Material Released to Sanitary
Sewers in Accordance with 10 CFR 20, 1994," NRC, Washington, D.C., 1994.
. (SP-98-086). Letter from Frederick C. Combs to ALL AGREEMENT STATES
MINNESOTA, OHIO, OKLAHOMA, PENNSYLVANIA, WISCONSIN, "TRANSMITTAL OF
STATE AGREEMENTS PROGRAM INFORMATION: JOINT NRC/EPA NATIONAL SURVEY
OF SEWAGE SLUDGE/ASH AND REQUEST FOR COMMENTS ON DRAFT GUIDANCE
FOR SEWAGE TREATMENT PLANTS," November 4, 1998.
. (SP-99-066). Letter from Frederick C. Combs to ALL AGREEMENT STATES
MINNESOTA, OKLAHOMA, PENNSYLVANIA, WISCONSIN, "OTHER INFORMATION:
AVAILABILITY OF THE JOINT NRC/EPA SEWAGE SLUDGE RADIOLOGICAL SURVEY:
SURVEY DESIGN AND TEST SITE RESULTS REPORT," September 23, 1999.
Tykva, R., and Sabol, J., "Low-Level Environmental Radioactivity Sources and Evaluation,"
Technomic Publishing Company, Inc., Lancaster, Pennsylvania, 1995.
U.S. Congress, "Radioactive Contamination at Sewage Treatment Plants," Joint Hearing
Before the Committee on Governmental Affairs, U.S. Senate, and the Subcommittee on
Environment, Energy, and Natural Resources of the Committee on Government Operations,
House of Representatives, One Hundred Third Congress, Second Session, June 21,1994,
S. Hrg. 103-1034, ISBN 0-16-047201-6, U.S. Government Printing Office, Washington, D.C.,
1994.
USGS/EPA Report 00-4273, "Occurrence of Selected Radionuclides in Ground Water Used for
Drinking Water in the United States: A Reconnaissance Survey," 1998.
26
-------
-------
28
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Alaska
Appalachian
Highlands
Atlantic
Plains
Hawaii
Interior
Highlands
Interior
Plains
Intermontane
Plateaus
Laurentain
Upland
Pacific
Mountain
System
Rocky
Mountain
System
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
0.05
0.135
0.22
0.22
2/2
ND
ND
ND
ND
0/2
ND
NDto
0.3
0.3
0.3
1/2
ND
0.2
0.9
1.5
54/84
ND
ND
6
22
23/84
ND
ND
4
13
38/84
ND
0.405
6
13
49/60
ND
ND
3
6
11/60
ND
ND
3.2
6
19/60
ND
NDto
0.05
0.07
0.07
2/4
ND
ND
ND
ND
0/4
ND
NDtoO
0.4
0.4
2/4
ND
1
1.5
1.5
3/4
ND
ND
ND
ND
0/4
ND
0.5
1.1
1.1
3/4
ND
0.38
4.1
16
97/1 1 0
ND
ND
9
11
28/1 1 0
ND
ND
4.3
9
47/1 1 0
ND
0.24
0.51
1
18/20
ND
2.5
20
27
12/20
ND
0.55
2
3
12/20
0.36
0.38
0.4
0.4
2/2
ND
ND
ND
ND
0/2
ND
NDto 4
4
4
1/2
ND
ND
0.4
1
8/21
ND
ND
4
10
4/21
ND
ND
11
12
9/21
ND
0.45
0.52
0.52
3/4
ND
NDto 2
4
4
2/4
ND
1.45
4
4
3/4
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Pb-214
Ra-226
Th-230
Th-234
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
Alaska
ND
ND
ND
ND
0/2
ND
NDto
0.4
0.4
0.4
1/2
~
~
-
-
~
ND
NDto
1.2
1.2
1.2
1/2
Appalachian
Highlands
ND
0.3
1.1
1.5
64/84
ND
1.95
9
17
74/84
0.1
0.415
1.6
1.7
14/14
ND
0.15
5
16
46/84
Atlantic
Plains
ND
0.43
4
15
51/60
ND
3
19
30
57/60
0.14
0.495
1
1.2
24/24
ND
0.4
3
4
33/60
Hawaii
ND
NDto
0.06
0.14
0.14
2/4
ND
1.2
4.6
4.6
3/4
~
~
-
-
~
ND
0.8
4.9
4.9
3/4
Interior
Highlands
ND
1.05
1.6
1.6
3/4
ND
1.4
2
2
3/4
~
~
-
-
~
ND
0.45
1
1
3/4
Interior
Plains
ND
0.41
4.4
17
100/110
ND
2.15
17
47
106/110
0.12
0.28
0.6
1.7
39/39
ND
0.8
7.8
12
70/1 1 0
Intermontane
Plateaus
ND
0.26
0.54
0.7
19/20
ND
2
8
11
19/20
0.09
0.29
0.4
0.42
11/11
ND
2.75
15
23
18/20
Laurentain
Upland
0.4
0.405
0.41
0.41
2/2
0.8
0.9
1
1
2/2
~
~
-
-
ND
NDto 2
2
2
1/2
Pacific
Mountain
System
ND
ND
0.5
2
9/21
ND
1.2
11
16
20/21
0.22
0.22
0.22
0.22
1/1
ND
0.5
5
19
12/21
Rocky
Mountain
System
ND
0.48
0.58
0.58
3/4
1
1.8
4
4
4/4
0.23
0.46
0.6
0.6
3/3
1.1
2.8
7
7
4/4
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
U-234
U-238
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Alaska
-
-
-
~
~
~
-
-
~
Appalachian
Highlands
0.43
1.7
20
25
14/14
0.37
1.45
15
16
14/14
Atlantic
Plains
0.18
1.1
2.1
2.3
24/24
0.19
0.95
2
2
24/24
Hawaii
-
-
-
~
~
~
-
-
~
Interior
Highlands
-
-
-
~
~
~
-
-
~
Interior
Plains
0.39
2.2
12
15.4
39/39
0.18
1.4
9
12.5
39/39
Intermontane
Plateaus
1.1
12
34
44
11/11
0.55
6.6
12
26
11/11
Laurentain
Upland
-
-
-
~
~
-
-
Pacific
Mountain
System
2.6
2.6
2.6
2.6
1/1
2
2
2
2
1/1
Rocky
Mountain
System
1.9
2
8
8
3/3
1.5
1.6
4.5
4.5
3/3
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
ND
ND
ND
ND
0/1
ND
ND
ND
ND
0/1
ND
ND
1
3
16/45
ND
0.6
5
6
35/45
ND
ND
1
2
12/26
ND
0.2
5
7
19/26
ND
ND
ND
ND
0/2
ND
NDto 1
1
1
1/2
ND
NDtol
2
2
2/4
ND
NDto 0.1
0.3
0.3
2/4
ND
ND
1
2
21/51
ND
0.3
4
6
35/51
ND
ND
0
1
5/13
ND
0.3
4
8
9/13
0
0
0
0
1/1
0.7
0.7
0.7
0.7
1/1
ND
ND
0
0.5
4/12
ND
0.2
2
3
8/12
ND
ND
2
2
1/3
ND
ND
2
2
1/3
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Alaska
Appalachian
Highlands
Atlantic
Plains
Hawaii
Interior
Highlands
Interior
Plains
Intermontane
Plateaus
Laurentain
Upland
Pacific
Mountain
System
Rocky
Mountain
System
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
ND
ND
ND
ND
0/2
0.08
0.165
0.25
0.25
2/2
ND
ND
ND
ND
0/2
0.15
0.375
0.6
0.6
2/2
ND
ND
1
1.3
28/84
ND
0.435
1.2
1.9
81/84
ND
ND
0.7
1.1
11/84
ND
0.87
3.1
5
74/84
ND
ND
2
4
23/60
ND
0.585
2.5
3.3
59/60
ND
ND
0.6
3
11/60
ND
0.87
8.9
13
54/60
ND
ND
ND
ND
0/4
0.03
0.105
0.6
0.6
4/4
ND
ND
0.4
0.4
1/4
ND
ND
0.14
0.14
1/4
ND
ND
ND
ND
0/4
0
0.27
0.5
0.5
4/4
ND
ND
ND
ND
0/4
ND
0.75
1.4
1.4
3/4
ND
ND
2.3
13
41/110
ND
0.48
2.7
15
108/110
ND
ND
1.4
12
20/1 1 0
ND
1.05
9.7
38
101/110
ND
ND
0.7
0.8
2/20
ND
0.3
0.7
1
19/20
ND
ND
0.7
5
2/20
ND
0.85
3.4
4.6
19/20
ND
NDtoO.7
0.7
0.7
1/2
0.4
0.49
0.58
0.58
2/2
ND
ND
ND
ND
0/2
0.43
0.715
1
1
2/2
ND
ND
0.6
1
4/21
ND
0.3
1.3
1.9
20/21
ND
ND
ND
0.4
1/21
ND
0.4
1.7
6
12/21
ND
NDtol
1.4
1.4
2/4
0.5
0.855
1.6
1.6
4/4
ND
ND
1.1
1.1
1/4
ND
0.85
1.5
1.5
3/4
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Th-228
Th-232
TI-208
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Alaska
-
-
-
-
~
-
-
ND
NDto
0.02
0.02
0.02
1/2
Appalachian
Highlands
0.16
0.75
1.3
1.8
14/14
0.08
0.335
1.1
1.6
14/14
ND
0.08
0.8
1.8
50/84
Atlantic
Plains
0.19
0.7
3.3
4.1
24/24
0.07
0.18
0.56
0.9
24/24
ND
0.085
1.8
3.1
36/60
Hawaii
-
-
-
-
~
-
-
ND
NDto
0.02
0.03
0.03
2/4
Interior
Highlands
-
-
-
-
~
-
-
ND
ND
ND
ND
0/4
Interior
Plains
0.19
0.7
6.8
9
39/39
0.08
0.18
0.4
0.6
39/39
ND
0.1
1.3
4.8
71/110
Intermontane
Plateaus
0.07
0.4
0.6
1.1
11/11
0.02
0.2
0.35
0.4
11/11
ND
ND
0.32
0.6
7/20
Laurentain
Upland
-
-
-
-
~
-
-
ND
NDto 0.1
0.17
0.17
1/2
Pacific
Mountain
System
0.25
0.25
0.25
0.25
1/1
0.14
0.14
0.14
0.14
1/1
ND
ND
0.15
0.17
9/21
Rocky
Mountain
System
0.33
0.61
0.9
0.9
3/3
0.16
0.46
0.6
0.6
3/3
ND
0.505
1.44
1.44
3/4
Radionuclide Group: Medical Isotopes
1-125
1-131
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
ND
ND
ND
ND
0/2
3.2
22.6
42
42
2/2
ND
ND
0.8
40
6/84
ND
1.55
65
230
70/84
ND
ND
ND
5.9
3/60
ND
0.855
64
840
43/60
ND
ND
ND
ND
0/4
ND
1.085
1.8
1.8
3/4
ND
ND
0.7
0.7
1/4
0.92
12.5
29
29
4/4
ND
ND
ND
1.1
1/110
ND
1.5
42
98
86/1 1 0
ND
ND
ND
ND
0/20
ND
3.3
51
105
18/20
ND
ND
ND
ND
0/2
0.4
4.35
8.3
8.3
2/2
ND
ND
ND
ND
0/21
ND
5.1
220
280
17/21
ND
ND
ND
ND
0/4
ND
ND
3.4
3.4
1/4
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
ln-111
TI-201
TI-202
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Alaska
ND
ND
ND
ND
0/2
2.5
26.25
50
50
2/2
ND
NDto
0.7
0.7
0.7
1/2
Appalachian
Highlands
ND
ND
ND
1.19
4/84
ND
1.6
56
241
48/84
ND
ND
0.54
1.16
18/84
Atlantic
Plains
ND
ND
0.09
3.5
5/60
ND
ND
26
46
23/60
ND
ND
0.51
0.95
16/60
Hawaii
ND
ND
ND
ND
0/4
ND
NDto
48
71
71
2/4
ND
NDto
0.66
0.88
0.88
2/4
Interior
Highlands
ND
ND
ND
ND
0/4
ND
ND
176
176
1/4
ND
ND
ND
ND
0/4
Interior
Plains
ND
ND
0.04
3.6
8/110
ND
ND
35
138
52/1 1 0
ND
ND
0.45
0.92
25/1 1 0
Intermontane
Plateaus
ND
ND
ND
0.4
1/20
ND
ND
42
110
9/20
ND
ND
0.55
0.85
4/20
Laurentain
Upland
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
Pacific
Mountain
System
ND
ND
ND
0.12
1/21
ND
2.6
16
24
14/21
ND
ND
0.22
0.4
7/21
Rocky
Mountain
System
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
0.5
0.7
0.9
0.9
2/2
2
2.6
3.2
3.2
2/2
ND
1.5
11
17
79/84
ND
4
13
15.9
82/84
ND
0.95
4
22
49/60
0.9
3.8
10.5
19
60/60
ND
0.4
0.56
0.56
3/4
0.3
1.75
4
4
4/4
ND
1.75
3
3
3/4
3.4
7
14
14
4/4
ND
1.1
8
13.5
88/1 1 0
ND
4
9.1
22
109/110
ND
0.85
2.4
4
18/20
1.3
3.85
7.7
8
20/20
0.9
1.7
2.5
2.5
2/2
3
3.95
4.9
4.9
2/2
ND
1.4
9
10.7
18/21
1.8
3.2
25
26
21/21
ND
ND
1
1
1/4
12
13
15.5
15.5
4/4
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
La-138
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Alaska
ND
ND
ND
ND
0/2
Appalachian
Highlands
ND
ND
ND
ND
0/84
Atlantic
Plains
ND
ND
ND
0.07
1/60
Hawaii
ND
ND
ND
ND
0/4
Interior
Highlands
ND
ND
ND
ND
0/4
Interior
Plains
ND
ND
ND
ND
0/110
Intermontane
Plateaus
ND
ND
ND
ND
0/20
Laurentain
Upland
ND
ND
ND
ND
0/2
Pacific
Mountain
System
ND
ND
ND
ND
0/21
Rocky
Mountain
System
ND
ND
ND
ND
0/4
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
ND
ND
ND
ND
0/2
-
~
~
-
~
~
~
-
-
~
ND
ND
ND
0.14
1/84
ND
0.0005
0.03
0.03
11/14
ND
0.001
0.04
0.1
8/14
ND
ND
ND
2.5
3/60
ND
0.01
0.14
0.19
19/24
ND
0.01
0.11
0.12
21/24
ND
ND
ND
ND
0/4
-
~
~
-
~
~
~
-
-
~
ND
ND
ND
ND
0/4
-
~
~
-
~
~
~
-
-
~
ND
ND
ND
0.1
5/110
ND
0.01
0.04
0.1
32/39
ND
0.002
0.01
0.04
29/39
ND
ND
ND
0
1/20
ND
0.01
0.03
0.07
9/11
ND
0
0.01
0.04
7/11
ND
ND
ND
ND
0/2
-
~
~
-
~
~
-
-
~
ND
ND
ND
ND
0/21
0.006
0.006
0.006
0.006
1/1
0.003
0.003
0.003
0.003
1/1
ND
ND
ND
ND
0/4
0.01
0.02
0.04
0.04
3/3
ND
0.01
0.05
0.05
2/3
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Alaska
Appalachian
Highlands
Atlantic
Plains
Hawaii
Interior
Highlands
Interior
Plains
Intermontane
Plateaus
Laurentain
Upland
Pacific
Mountain
System
Rocky
Mountain
System
Radionuclide Group: Actinium ( U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/1
ND
ND
ND
ND
0/2
ND
ND
ND
0.06
1/84
ND
ND
ND
ND
0/84
ND
ND
0.07
0.19
5/50
ND
ND
0.31
1.1
19/84
ND
ND
ND
ND
0/60
ND
ND
ND
ND
0/60
ND
ND
0.1
0.2
14/40
ND
ND
0.19
0.3
29/60
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/110
ND
ND
ND
ND
0/110
ND
ND
0.1
0.5
22/73
ND
ND
0.5
0.61
46/1 1 0
ND
ND
ND
ND
0/20
ND
ND
ND
ND
0/20
ND
ND
0.06
0.1
7/20
ND
0.095
1.3
3.1
11/20
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/1
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/21
ND
ND
ND
ND
0/21
ND
ND
ND
ND
0/12
ND
ND
0.3
0.43
4/21
ND
ND
0.09
0.09
1/4
ND
ND
ND
ND
0/4
ND
ND
0.04
0.04
1/4
ND
0.115
0.19
0.19
3/4
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Alaska
Appalachian
Highlands
Atlantic
Plains
Hawaii
Interior
Highlands
Interior
Plains
Intermontane
Plateaus
Laurentain
Upland
Pacific
Mountain
System
Rocky
Mountain
System
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Cr-51
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/84
ND
ND
ND
ND
0/84
ND
ND
ND
0.07
2/84
ND
ND
ND
3.5
2/84
ND
ND
ND
ND
0/60
ND
ND
ND
0.06
2/60
ND
ND
0.07
1.16
4/60
ND
ND
ND
0.8
2/60
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
0.016
1/110
ND
ND
ND
0.05
1/110
ND
ND
ND
0.3
4/110
ND
ND
ND
0.3
1/110
ND
ND
ND
ND
0/20
ND
ND
ND
0.01
1/20
ND
ND
ND
5.1
1/20
ND
ND
ND
ND
0/20
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/21
ND
ND
0.04
0.26
2/21
ND
ND
0
0.03
2/21
ND
ND
ND
2.8
1/21
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Cs-134
Cs-137
Eu-154
Fe-59
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Alaska
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
Appalachian
Highlands
ND
ND
ND
ND
0/84
ND
ND
0.11
1.5
37/84
ND
ND
ND
21
1/84
ND
ND
ND
ND
0/84
Atlantic
Plains
ND
ND
ND
0.04
1/60
ND
ND
0.12
3.6
24/60
ND
ND
ND
ND
0/60
ND
ND
ND
ND
0/60
Hawaii
ND
ND
ND
ND
0/4
ND
ND
0.01
0.01
1/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
Interior
Highlands
ND
ND
ND
ND
0/4
ND
ND
0.03
0.03
1/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
Interior
Plains
ND
ND
ND
ND
0/110
ND
ND
0.06
0.1
46/1 1 0
ND
ND
ND
ND
0/110
ND
ND
ND
0.4
1/110
Intermontane
Plateaus
ND
ND
ND
ND
0/20
ND
ND
0.4
1.1
8/20
ND
ND
ND
ND
0/20
ND
ND
ND
ND
0/20
Laurentain
Upland
ND
ND
ND
ND
0/2
0.07
0.09
0.11
0.11
2/2
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
Pacific
Mountain
System
ND
ND
ND
ND
0/21
ND
ND
0.3
0.3
10/21
ND
ND
ND
ND
0/21
ND
ND
ND
ND
0/21
Rocky
Mountain
System
ND
ND
ND
ND
0/4
0.08
0.12
0.3
0.3
4/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
-------
Table A.1 Concentrations of Radionuclides in Sludge,
Summarized by Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Sm-153
Sr-89
Sr-90
Zn-65
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Min
Median
95th Percentile
Max
No. Detects/
No. Analyses
Alaska
ND
ND
ND
ND
0/2
~
~
~
~
~
~
-
-
ND
ND
ND
ND
0/2
Appalachian
Highlands
ND
ND
ND
27
1/84
ND
0.1
3
10
9/15
ND
0.1
9
9.4
10/15
ND
ND
ND
0.06
1/84
Atlantic
Plains
ND
ND
ND
ND
0/60
ND
1.1
20
30
20/24
ND
0.1
0.4
1
15/24
ND
ND
ND
ND
0/60
Hawaii
ND
ND
ND
ND
0/4
~
~
~
~
~
~
-
-
ND
ND
ND
ND
0/4
Interior
Highlands
ND
ND
ND
ND
0/4
~
~
~
~
~
~
-
-
ND
ND
ND
ND
0/4
Interior
Plains
ND
ND
ND
ND
0/110
ND
0.3
30
70
24/38
ND
0.1
0.6
2
26/38
ND
ND
ND
ND
0/110
Intermontane
Plateaus
ND
ND
ND
ND
0/20
ND
0.3
2
2
9/13
ND
0
0.3
0.7
8/13
ND
ND
ND
ND
0/20
Laurentain
Upland
ND
ND
ND
ND
0/2
~
~
~
~
~
~
-
-
ND
ND
ND
ND
0/2
Pacific
Mountain
System
ND
ND
ND
ND
0/21
0
0.65
1
1
4/4
ND
NDtoO.1
0.1
0.1
2/4
ND
ND
ND
ND
0/21
Rocky
Mountain
System
ND
ND
ND
ND
0/4
ND
NDtoO
0
0
2/4
ND
0.15
1
1
3/4
ND
ND
ND
ND
0/4
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Alaska
Appalacian
Highlands
Atlantic
Plains
Hawaii
Interior
Highlands
Interior
Plains
Intermontane
Plateaus
Laurentain
Upland
Pacific
Mountain
System
Rocky
Mountain
System
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
2.15
9
13.7
15/16
ND
3
10
11
14/16
ND
NDto2.5
6.4
12.3
8/16
0.92
2.3
10
14.8
16/16
2.8
3.8
16
16
5/5
ND
3
5
5
4/5
ND
ND
4.2
4.2
2/5
3.1
4.1
16.4
16.4
5/5
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
1.7
3.25
14.1
14.1
10/10
ND
4.5
9
9
9/10
ND
ND
8.5
8.5
3/10
1.9
3.6
15.1
15.1
10/10
-
-
-
-
-
-
-
-
~
-
-
-
-
~
-
-
-
-
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
0.62
0.68
1.3
1.3
4/4
ND
6.5
77
77
3/4
ND
2.35
8.9
8.9
3/4
0.61
0.715
1.32
1.32
4/4
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Ra-226
Th-230
Th-234
U-234
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Alaska
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Appalacian
Highlands
ND
2.5
17
18
15/16
0.3
0.8
2.3
2.6
11/11
ND
2.55
7.3
10
14/16
1.3
2.9
13
49
11/11
Atlantic
Plains
ND
9.5
15
15
4/5
0.6
0.7
1.5
1.5
5/5
ND
3.8
21
21
4/5
1.2
1.9
18
18
5/5
Hawaii
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Interior
Highlands
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Interior
Plains
2
6.2
22
22
10/10
ND
0.9
2.2
2.2
8/9
ND
3.75
7.5
7.5
9/10
2.7
6.9
7.6
7.6
9/9
Intermontane
Plateaus
-
-
-
-
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Laurentain
Upland
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Pacific
Mountain
System
0
1.05
1.1
1.1
4/4
0.4
0.64
0.9
0.9
3/3
1
6.35
80
80
4/4
2.7
19
91
91
3/3
Rocky
Mountain
System
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
U-238
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Alaska
-
-
-
-
~
Appalacian
Highlands
0.8
2.8
9
35
11/11
Atlantic
Plains
1.1
1.7
6.4
6.4
5/5
Hawaii
-
-
-
-
~
Interior
Highlands
-
-
-
-
~
Interior
Plains
2.5
4.3
6.2
6.2
9/9
Intermontane
Plateaus
-
-
-
-
~
Laurentain
Upland
-
-
-
-
~
Pacific
Mountain
System
2.5
15
74
74
3/3
Rocky
Mountain
System
-
-
-
-
~
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
-
-
-
-
~
-
-
-
-
~
ND
ND
1
1
1/8
ND
0.75
8
8
6/8
ND
ND
ND
ND
0/2
ND
ND
ND
ND
0/2
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
0
0
2/5
ND
ND
ND
ND
0/5
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
0
1
1
2/3
ND
ND
4
4
1/3
-
-
-
-
~
-
-
-
-
~
Radionuclide Group: Thorium-232 DecaySeries
Bi-212
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
-
-
-
~
ND
1.3
2
2.4
13/16
1.2
3.5
15.7
15.7
5/5
-
~
-
-
~
-
~
-
-
~
ND
NDto
0.8
1.8
1.8
5/10
-
~
-
-
~
-
~
-
-
~
ND
NDto 0.3
1.4
1.4
2/4
-
~
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Pb-212
Ra-224
Ra-228
Th-228
Th-232
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Alaska
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Appalacian
Highlands
0.74
1.55
2.5
2.6
16/16
ND
NDtoO.4
2
2.4
8/16
0.71
2.6
6.3
17
16/16
0.8
1.5
3.4
3.7
11/11
0.3
0.7
0.9
0.9
11/11
Atlantic
Plains
1.3
3.3
15
15
5/5
ND
0.4
4.9
4.9
3/5
3.4
9.6
30
30
5/5
1.7
3
14
14
5/5
0.46
0.8
1.7
1.7
5/5
Hawaii
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Interior
Highlands
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Interior
Plains
0.73
1.28
1.9
1.9
10/10
ND
ND
1.3
1.3
4/10
1.6
2.15
9.9
9.9
10/10
ND
1.4
2.4
2.4
8/9
ND
0.5
1
1
8/9
Intermontane
Plateaus
-
-
-
-
-
-
-
-
~
-
-
-
-
-
-
-
-
~
-
-
-
-
~
Laurentain
Upland
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Pacific
Mountain
System
0.36
1.025
1.3
1.3
4/4
ND
ND
ND
ND
0/4
0.65
1.24
2.2
2.2
4/4
0.4
0.68
0.7
0.7
3/3
0.22
0.39
0.49
0.49
3/3
Rocky
Mountain
System
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
TI-208
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Alaska
~
~
~
~
~
Appalacian
Highlands
0.23
1.01
2
2.3
16/16
Atlantic
Plains
0.4
2
13.5
13.5
5/5
Hawaii
~
~
~
~
~
Interior
Highlands
~
~
~
~
~
Interior
Plains
ND
0.415
1.66
1.66
7/10
Intermontane
Plateaus
~
~
~
~
~
Laurentain
Upland
~
~
~
~
~
Pacific
Mountain
System
0.11
0.9
1.16
1.16
4/4
Rocky
Mountain
System
~
~
~
~
~
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
ND
ND
ND
0.4
1/16
ND
NDtoO.1
1.6
20
8/16
ND
ND
ND
ND
0/16
ND
ND
0.8
0.8
1/5
ND
0.68
46
46
3/5
ND
ND
ND
ND
0/5
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
ND
ND
0.3
0.3
1/10
ND
0.23
4.3
4.3
8/10
ND
ND
ND
ND
0/10
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
ND
ND
1
1
1/4
0.03
4.285
81
81
4/4
ND
ND
ND
ND
0/4
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
TI-201
TI-202
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Alaska
-
-
-
-
~
-
-
-
-
~
Appalacian
Highlands
ND
ND
31
35
7/16
ND
ND
0.99
1.1
3/16
Atlantic
Plains
ND
6.8
105
105
4/5
ND
ND
1.53
1.53
1/5
Hawaii
-
-
-
-
~
-
-
-
-
~
Interior
Highlands
-
-
-
-
~
-
-
-
-
~
Interior
Plains
ND
ND
12.4
12.4
4/10
ND
ND
0.1
0.1
2/10
Intermontane
Plateaus
-
-
-
-
~
-
-
-
-
~
Laurentain
Upland
-
-
-
-
~
-
-
-
-
~
Pacific
Mountain
System
26
54.5
73
73
4/4
ND
ND
0.77
0.77
1/4
Rocky
Mountain
System
-
-
-
-
~
-
-
-
-
~
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
-
-
-
-
~
-
-
-
-
~
ND
5.95
15
27
15/16
7.4
15.9
20
22.4
16/16
1.2
2.3
8.1
8.1
5/5
8.4
9.4
22
22
5/5
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
0.5
5.7
30
30
10/10
7.9
14.1
20.9
20.9
10/10
-
-
-
-
-
-
-
-
-
-
-
-
~
-
-
-
-
~
1.9
3.95
15.4
15.4
4/4
10.8
13.9
15
15
4/4
-
-
-
-
~
-
-
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
La-138
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Alaska
-
-
-
-
~
Appalacian
Highlands
ND
ND
ND
ND
0/16
Atlantic
Plains
ND
ND
ND
ND
0/5
Hawaii
-
-
-
-
~
Interior
Highlands
-
-
-
-
~
Interior
Plains
ND
ND
ND
ND
0/10
Intermontane
Plateaus
-
-
-
-
~
Laurentain
Upland
-
-
-
-
~
Pacific
Mountain
System
ND
ND
ND
ND
0/4
Rocky
Mountain
System
-
-
-
-
~
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
ND
0.21
1/16
ND
0.01
0.09
0.1
7/11
ND
0.008
0.04
0.06
9/11
ND
ND
0.04
0.04
1/5
ND
0.02
0.05
0.05
3/5
ND
0.02
0.17
0.17
3/5
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
ND
ND
0/10
ND
0.02
0.1
0.1
8/9
ND
0.01
0.04
0.04
7/9
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
ND
ND
0/4
ND
0
0
0
2/3
ND
0.01
0.05
0.05
2/3
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Alaska
Appalacian
Highlands
Atlantic
Plains
Hawaii
Interior
Highlands
Interior
Plains
Intermontane
Plateaus
Laurentain
Upland
Pacific
Mountain
System
Rocky
Mountain
System
Radionuclide Group: Actinium ( U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
0.5
0.8
3/16
ND
ND
0.2
0.4
2/16
ND
ND
0.3
1.1
6/14
ND
0.11
0.5
1.7
13/16
ND
ND
ND
ND
0/5
ND
ND
0.2
0.2
1/5
ND
0.1
0.6
0.6
3/5
0.03
0.07
0.7
0.7
5/5
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
0.1
0.1
1/10
ND
ND
ND
ND
0/10
ND
ND
0.2
0.2
4/10
ND
0.24
0.6
0.6
9/10
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
0.04
0.04
1/4
ND
0.44
3.4
3.4
3/4
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Alaska
Appalacian
Highlands
Atlantic
Plains
Hawaii
Interior
Highlands
Interior
Plains
Intermontane
Plateaus
Laurentain
Upland
Pacific
Mountain
System
Rocky
Mountain
System
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Cr-51
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
ND
ND
0/16
ND
ND
ND
0.17
1/16
ND
ND
ND
ND
0/16
ND
ND
ND
0.8
1/16
ND
ND
ND
ND
0/5
ND
ND
ND
ND
0/5
ND
ND
3.46
3.46
1/5
ND
ND
0.2
0.2
1/5
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
ND
ND
0/10
ND
ND
ND
ND
0/10
ND
ND
0.038
0.038
1/10
ND
ND
0.3
0.3
1/10
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
ND
NDtoO.3
35
35
2/4
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Cs-134
Cs-137
Eu-154
Fe-59
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Alaska
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Appalacian
Highlands
ND
ND
ND
ND
0/16
ND
0.075
0.18
0.27
15/16
ND
ND
ND
ND
0/16
ND
ND
ND
ND
0/16
Atlantic
Plains
ND
ND
ND
ND
0/5
0.03
0.04
0.37
0.37
5/5
ND
ND
ND
ND
0/5
ND
ND
ND
ND
0/5
Hawaii
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Interior
Highlands
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Interior
Plains
ND
ND
ND
ND
0/10
0.04
0.07
0.23
0.23
10/10
ND
ND
ND
ND
0/10
ND
ND
ND
ND
0/10
Intermontane
Plateaus
-
-
-
-
~
-
-
-
-
-
-
-
-
~
-
-
-
-
~
Laurentain
Upland
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Pacific
Mountain
System
ND
ND
ND
ND
0/4
0.02
0.06
0.1
0.1
4/4
ND
ND
ND
ND
0/4
ND
ND
ND
ND
0/4
Rocky
Mountain
System
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-------
Table A.2 Concentrations of Radionuclides in Ash, Summarized by
Geographic Division
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Sm-153
Sr-89
Sr-90
Zn-65
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Min
Median
95th Percentile
Max
No. Detects/No.
Analyses
Alaska
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Appalacian
Highlands
ND
ND
ND
ND
0/16
ND
NDtoO
20
60
6/12
ND
0.25
1
1
10/12
ND
ND
ND
ND
0/16
Atlantic
Plains
ND
ND
ND
ND
0/5
ND
2
12
12
4/5
0
0.1
1
1
5/5
ND
ND
ND
ND
0/5
Hawaii
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Interior
Highlands
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Interior
Plains
ND
ND
ND
ND
0/10
ND
1
300
300
7/9
ND
0.4
6
6
8/9
ND
ND
0.06
0.06
1/10
Intermontane
Plateaus
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Laurentain
Upland
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
Pacific
Mountain
System
ND
ND
ND
ND
0/4
ND
1.2
30
30
3/4
ND
ND
0.1
0.1
1/4
ND
ND
ND
ND
0/4
Rocky
Mountain
System
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
-
-
-
-
~
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
Response
Min
Median
95tnP
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
0.05
ND
ND
ND
0.27
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.24
ND
0.05
0.24
0.21
0.29
0.4
0.38
ND
ND
ND
ND
ND
ND
ND
ND-0
ND
ND
ND
ND
ND
0.27
0.28
0.31
0.4
0.4
1.7
1.9
7.9
2.1
0.9
2.9
ND
8
7
4
1.3
9
ND
5
3
3.1
1.2
4.3
1.8
2
8.3
2.6
0.9
3
1.7
16
13
16
0.9
4.1
ND
17
22
27
1.3
17
ND
13
12
9
1.2
6
1.8
17
15
17
0.9
4.4
3/3
63/90
23/33
81/101
5/5
63/79
0/3
26/90
11/33
20/101
2/5
21/79
0/3
45/90
13/33
38/101
2/5
37/79
1/3
72/90
25/33
81/101
5/5
69/79
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
Ra-226
Th-230
Th-234
U-234
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
0.4
ND
ND
ND
ND
ND
1.2
0.1
0.09
0.12
0.4
0.09
ND
ND
ND
ND
0.4
ND
1.9
0.5
0.4
0.56
1
0.18
Median
2.1
1.95
1.8
2.2
1.1
2.2
1.2
0.435
0.38
0.375
0.4
0.25
1.4
0.55
0.5
0.5
0.6
1
1.9
1.6
2.3
2.2
1
2.1
95tnP
8
11
21
13
2
10.1
1.2
0.8
1.6
1.2
0.4
0.49
1.6
6.8
5
4.9
1
7.8
1.9
14
20
17
1
15.4
Max
8
47
30
27
2
25
1.2
1
1.6
1.7
0.4
0.5
1.6
15
19
23
1
15
1.9
17
20
44
1
25
No. Detects/
No. Analyses
3/3
80/90
30/33
96/101
4/5
76/79
1/1
24/24
7/7
34/34
1/1
25/25
2/3
56/90
22/33
56/101
5/5
50/79
1/1
24/24
7/7
34/34
1/1
25/25
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
U-238
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
1.7
0.43
0.4
0.5
0.72
0.18
Median
1.7
1.25
2
1.55
0.72
1.3
95tnP
1.7
10.3
16
8
0.72
12.5
Max
1.7
12
16
26
0.72
15
No. Detects/
No. Analyses
1/1
24/24
7/7
34/34
1/1
25/25
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1
ND
0.4
0.35
0.25
0.3
0.3
1
2
1
1
1
5
2
5
4
3
2
2
3
1
2
7
3
8
4
6
22/55
6/16
16/44
2/3
16/40
41/55
12/16
28/44
2/3
28/40
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1.3
1
1.4
0.6
1.1
ND
13
4
6.8
0.6
3.7
0/3
28/90
10/33
38/101
2/5
23/79
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
Pb-212
Ra-224
Ra-228
Th-228
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
0.08
ND
0.07
ND
0.09
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.3
ND
0.2
0.16
0.22
0.25
0.23
0.07
Median
0.08
0.45
0.32
0.5
0.19
0.44
ND
ND
ND
ND
ND
ND
0.15
0.8
0.7
0.83
0.6
1
0.2
0.7
1.1
0.75
0.23
0.4
95tnP
0.21
1.5
2.2
1.9
0.7
1.9
0.4
0.6
1.1
0.7
0.6
1
0.4
4
9.7
5.1
0.64
4.8
0.2
6.7
4.6
3
0.23
2.4
Max
0.21
15
3
5.4
0.7
4.2
0.4
12
3
2.7
0.6
5
0.4
20
13
24
0.64
38
0.2
9
4.6
6.8
0.23
9
No. Detects/
No. Analyses
3/3
89/90
33/33
100/101
5/5
73/79
1/3
9/90
5/33
15/101
2/5
15/79
2/3
78/90
29/33
88/101
5/5
69/79
1/1
24/24
7/7
34/34
1/1
25/25
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
Th-232
TI-208
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
0.14
0.07
0.06
0.08
0.15
0.02
0.02
ND
ND
ND
ND
ND
Median
0.14
0.215
0.19
0.265
0.15
0.18
0.03
0.055
ND
0.09
ND
0.08
95tnP
0.14
0.6
1.1
0.65
0.15
0.4
0.04
0.8
0.37
1.4
0.22
0.88
Max
0.14
0.9
1.1
1.6
0.15
0.44
0.04
4.1
0.93
4.8
0.22
2.5
No. Detects/
No. Analyses
1/1
24/24
7/7
34/34
1/1
25/25
3/3
48/90
16/33
65/101
2/5
46/79
Radionuclide Group: Medical Isotopes
1-125
1-131
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
ND
ND
ND
ND
ND
ND
1.2
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1.8
1.35
2.9
0.87
0.13
3.6
ND
0.3
ND
ND
ND
ND
3.2
51
29
101
34
50
ND
40
ND
4
ND
1.5
3.2
220
145
840
34
105
0/3
5/90
0/33
5/101
0/5
1/79
3/3
68/90
28/33
76/101
4/5
67/79
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
ln-111
TI-201
TI-202
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.05
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
48
ND
ND
ND
ND
0.35
0.66
ND
ND
ND
ND
ND
95tnP
ND
ND
ND
0.12
ND
0.044
50
46
42
34
1.8
35
0.7
0.4
0.14
0.54
0.085
0.51
Max
ND
0.18
ND
3.6
ND
3.5
50
207
241
176
1.8
189
0.7
1.16
0.85
0.95
0.085
0.72
No. Detects/
No. Analyses
0/3
4/90
0/33
8/101
0/5
7/79
2/3
41/90
16/33
49/101
2/5
41/79
3/3
18/90
9/33
26/101
1/5
16/79
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
0.3
ND
ND
ND
ND
ND
0.4
1.1
1
1.2
0.58
1.4
0.5
11
4.6
8
3
9.9
0.5
22
9.5
17
3
13.5
3/3
76/90
27/33
85/101
3/5
69/79
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
K-40
La-138
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
0.8
ND
1.3
ND
2.3
0.9
ND
ND
ND
ND
ND
ND
Median
1.3
4.05
3.4
4
2.9
4
ND
ND
ND
ND
ND
ND
95tnP
2
13
9
13.3
8.3
10
ND
ND
ND
ND
ND
ND
Max
2
26
25
22
8.3
12
ND
0.07
ND
ND
ND
ND
No. Detects/
No. Analyses
3/3
88/90
33/33
100/101
5/5
79/79
0/3
1/90
0/33
0/101
0/5
0/79
Radionuclide Group: Transuranics
Am-241
Pu-238
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
ND
ND
ND
ND
ND
ND
0.02
ND
ND
ND
0
ND
ND
ND
ND
ND
ND
ND
0.02
0.0105
0
0.01
0
0.007
ND
0.1
ND
ND
ND
ND
0.02
0.14
0.1
0.03
0
0.04
ND
2.5
0.1
0.03
ND
0.08
0.02
0.19
0.1
0.1
0
0.05
0/3
5/90
1/33
1/101
0/5
3/79
1/1
18/24
5/7
30/34
1/1
20/25
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
Pu-239
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
0.02
ND
ND
ND
ND
ND
Median
0.02
0.0035
0.01
0.003
ND
0.003
95tnP
0.02
0.1
0.03
0.04
ND
0.01
Max
0.02
0.11
0.03
0.12
ND
0.04
No. Detects/
No. Analyses
1/1
18/24
6/7
24/34
0/1
19/25
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.04
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.04
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.04
0.06
0.2
0.1
ND
0.1
ND
0.09
ND
0.06
ND
ND
ND
ND
ND
ND
ND
ND
0.04
0.5
0.2
0.19
ND
0.5
0/3
1/90
0/33
1/101
0/5
0/79
0/3
0/90
0/33
0/101
0/5
0/79
1/1
10/65
6/22
20/64
0/3
12/52
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
U-235
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
0.06
ND
95tnP
0.12
0.43
0.2
0.4
0.08
0.58
Max
0.12
1.3
0.7
3.1
0.08
0.7
No. Detects/
No. Analyses
1/3
30/90
7/33
40/101
3/5
31/79
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.05
ND
ND
ND
ND
ND
ND
ND
0.016
ND
ND
ND
ND
ND
0.26
ND
0.06
ND
1.16
0.016
5.1
ND
0.1
0/3
0/90
0/33
1/101
0/5
0/79
0/3
0/90
0/33
3/101
0/5
3/79
0/3
6/90
1/33
3/101
0/5
3/79
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
Cr-51
Cs-134
Cs-137
Eu-154
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.03
ND
ND
ND
ND
ND
ND
ND
95tnP
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.19
0.11
0.11
0.06
0.08
ND
ND
ND
ND
ND
ND
Max
ND
2.8
ND
3.5
ND
0.8
ND
0.04
ND
ND
ND
ND
ND
3.6
0.73
1.1
0.06
0.3
ND
21
ND
ND
ND
ND
No. Detects/
No. Analyses
0/3
1/90
0/33
1/101
0/5
4/79
0/3
1/90
0/33
0/101
0/5
0/79
0/3
44/90
7/33
44/101
4/5
34/79
0/3
1/90
0/33
0/101
0/5
0/79
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
Fe-59
Sm-153
Sr-89
Sr-90
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
20
ND
ND
ND
0
ND
0.1
ND
ND
ND
0
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
20
0.5
ND
0
1
1
0.1
0.1
0.1
0.1
0.04
0.1
95tnP
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
20
5
10
10
1
30
0.1
1
0.3
0.7
0.3
1
Max
ND
0.4
ND
ND
ND
ND
ND
27
ND
ND
ND
ND
20
5
10
70
1
30
0.1
9.4
0.3
9
0.3
2
No. Detects/
No. Analyses
0/3
1/90
0/33
0/101
0/5
0/79
0/3
1/90
0/33
0/101
0/5
0/79
1/1
22/28
4/9
19/34
3/3
19/23
1/1
16/28
7/9
24/34
3/3
13/23
-------
Table A.3 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Indicate the Level(s) of Wastewater Treatment Achieved by this Treatment Works
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi = 0.037 Bq.)
Radionuclide
Zn-65
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary,
and Advanced
Min
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
95tnP
ND
ND
ND
ND
ND
ND
Max
ND
0.06
ND
ND
ND
ND
No. Detects/
No. Analyses
0/3
1/90
0/33
0/101
0/5
0/79
* Indicates concentrations for this radionuclide are expressed in pCi/g wet
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
2.2
0.64
0.72
0.62
2.8
ND
3
1.1
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2.4
0.69
0.74
0.61
3.1
0.92
2.2
1.7
1.7
2.4
5.9
3.2
3
5
3
3
ND-2
5
ND
ND
ND
3.4
ND
ND
2.4
1.9
1.9
2.9
6.55
3.5
2.2
3.1
6.3
14.1
9
14
3
6
11
7
2
77
ND
5
5.3
8.5
ND
8.9
2.4
3.4
6.8
15.1
10
14.6
2.2
3.1
6.3
16
9
14
3
6
11
10
2
77
ND
5
5.3
12.3
ND
8.9
2.4
3.4
6.8
16.4
10
14.6
1/1
7/7
7/7
11/11
2/2
6/7
1/1
7/7
6/7
9/11
1/2
6/7
0/1
2/7
3/7
8/11
0/2
3/7
1/1
7/7
111
11/11
2/2
7/7
A-39
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
Ra-226
Th-230
Th-234
U-234
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
3.4
1.1
ND
1.1
9.5
1
1.4
0.4
0.3
ND
0.6
0.55
2.7
ND
1
1
ND
ND
5.3
2.7
1.3
1.2
1.9
6
Median
3.4
2.5
2
4
13.75
6.6
1.4
0.85
0.8
1.1
0.6
0.65
2.7
4.7
3.6
2.7
ND
4.7
5.3
5.4
2.4
6.05
2.05
7.45
95th P
3.4
9.4
7.1
17
18
18
1.4
2.2
2.6
2.3
0.6
1.3
2.7
7.2
21
5.5
ND
80
5.3
9
19
49
2.2
91
Max
3.4
9.4
7.1
22
18
18
1.4
2.2
2.6
2.3
0.6
1.3
2.7
7.2
21
7.3
ND
80
5.3
9
19
49
2.2
91
No. Detects/
No. Analyses
1/1
111
5/7
11/11
2/2
111
1/1
4/4
111
7/8
2/2
6/6
1/1
6/7
7/7
11/11
0/2
6/7
1/1
4/4
111
8/8
2/2
6/6
A-40
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
U-238
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
4.3
2.5
0.8
1.1
1.4
2.8
Median
4.3
4.25
1.9
3.65
1.55
4.75
95th P
4.3
6.4
15
35
1.7
74
Max
4.3
6.4
15
35
1.7
74
No. Detects/
No. Analyses
1/1
4/4
7/7
8/8
2/2
6/6
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Secondary
Advanced
Primary and
Secondary
Primary,
Secondary, and
Advanced
Secondary
Advanced
Primary and
Secondary
Primary,
Secondary, and
Advanced
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
ND
ND
3
ND
ND
ND-0.5
1
ND
0
1
8
1
2
4
1
ND
0
1
8
1
2
4
2/3
0/3
2/8
1/4
2/3
1/3
2/8
2/4
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
0.9
ND
ND
ND
1.2
ND
0.9
0.8
0.9
1.6
1.65
1.4
0.9
1.8
5.5
3.5
2.1
1.6
0.9
1.8
5.5
15.7
2.1
1.6
1/1
6/7
4/7
8/11
2/2
4/7
A-41
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
Pb-212
Ra-224
Ra-228
Th-228
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
1.14
0.36
0.99
0.73
2
1
0.8
ND
ND
ND
0.4
ND
2.3
0.65
1.46
0.68
5.7
2
1.4
0.4
0.68
ND
1.7
0.7
Median
1.14
1.3
1.4
1.8
2.2
1.6
0.8
ND
0.8
ND
1.2
ND
2.3
1.8
2.5
3.7
11.35
3
1.4
1
1.3
2.25
2.7
1.7
95th P
1.14
1.7
6.6
3.3
2.4
1.7
0.8
0.5
4.9
1.3
2
1.8
2.3
3.4
24
9.9
17
8.2
1.4
1.7
6.7
14
3.7
2.4
Max
1.14
1.7
6.6
15
2.4
1.7
0.8
0.5
4.9
2.4
2
1.8
2.3
3.4
24
30
17
8.2
1.4
1.7
6.7
14
3.7
2.4
No. Detects/
No. Analyses
1/1
111
111
11/11
2/2
111
1/1
3/7
4/7
3/11
2/2
2/7
1/1
7/7
7/7
11/11
2/2
111
1/1
4/4
111
7/8
2/2
6/6
A-42
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
Th-232
TI-208
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
0.7
0.22
0.39
ND
0.3
0.34
0.36
ND
0.3
0.34
0.61
ND
Median
0.7
0.75
0.8
0.505
0.4
0.495
0.36
0.29
1.05
1.03
0.67
0.55
95th P
0.7
1
0.9
1.7
0.5
0.8
0.36
1.48
2
3.1
0.73
1.6
Max
0.7
1
0.9
1.7
0.5
0.8
0.36
1.48
2
13.5
0.73
1.6
No. Detects/
No. Analyses
1/1
4/4
7/7
7/8
2/2
6/6
1/1
6/7
7/7
11/11
2/2
5/7
Radionuclide Group: Medical Isotopes
1-125
1-131
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
ND
ND
ND
ND
ND
ND
3.8
ND
ND
ND
0.22
ND
ND
ND
ND
ND
ND
ND
3.8
ND
1.6
0.22
0.68
0.03
ND
ND
ND
ND
ND
1
3.8
7.4
81
1.17
1.14
4.2
ND
ND
ND
0.8
ND
1
3.8
7.4
81
1.2
1.14
4.2
0/1
0/7
0/7
1/11
0/2
3/7
1/1
3/7
5/7
8/11
2/2
4/7
A-43
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
ln-111
TI-201
TI-202
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
ND
ND
ND
ND
ND
ND
1.3
ND
ND
ND
1.3
ND
0.07
ND
ND
ND
0.14
ND
Median
ND
ND
ND
ND
ND
ND
1.3
ND
0.36
1
47.15
ND
0.07
ND
ND
ND
0.835
ND
95th P
ND
ND
ND
ND
ND
ND
1.3
26
105
12.4
93
61
0.07
0.77
1.1
0.1
1.53
ND
Max
ND
ND
ND
ND
ND
ND
1.3
26
105
48
93
61
0.07
0.77
1.1
0.99
1.53
ND
No. Detects/
No. Analyses
0/1
0/7
0/7
0/11
0/2
0/7
1/1
1/7
4/7
8/11
2/2
3/7
1/1
1/7
1/7
2/11
2/2
0/79
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
8.3
0.8
ND
0.14
4.3
0.5
8.3
1.2
3.6
7.6
6
4.3
8.3
13
15
15.4
7.7
27
8.3
13
15
30
7.7
27
1/1
7/7
6/7
11/11
2/2
7/7
A-44
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
K-40
La-138
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
11.4
9.7
7.4
7.9
9.4
12
ND
ND
ND
ND
ND
ND
Median
11.4
15
12.7
16
11.45
14
ND
ND
ND
ND
ND
ND
95th P
11.4
22
22.4
19.8
13.5
17.9
ND
ND
ND
ND
ND
ND
Max
11.4
22
22.4
20.9
13.5
17.9
ND
ND
ND
ND
ND
ND
No. Detects/
No. Analyses
1/1
111
111
11/11
2/2
111
0/1
0/7
0/7
0/11
0/2
0/7
Radionuclide Group: Transuranics
Am-241
Pu-238
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
ND
ND
ND
ND
ND
ND
0.02
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.02
0.03
0.01
0.01
ND-
0.09
0.01
ND
ND
ND
ND
ND
0.21
0.02
0.1
0.06
0.1
0.09
0.08
ND
ND
ND
0.04
ND
0.21
0.02
0.1
0.06
0.1
0.09
0.08
0/1
0/7
0/7
1/11
0/2
1/7
1/1
3/4
6/7
5/8
1/2
4/6
A-45
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
Pu-239
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
ND
ND
ND
ND
ND
ND
Median
ND
0.02
0.01
0
ND-0.04
0
95th P
ND
0.04
0.06
0.17
0.04
0.01
Max
ND
0.04
0.06
0.17
0.04
0.04
No. Detects/
No. Analyses
0/1
3/4
6/7
5/8
1/2
6/6
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.2
ND
0.2
ND
ND
ND
0.1
ND
ND
ND
ND
ND
ND-0.5
ND
ND
ND
ND
ND
0.2
ND
0.2
ND-
0.04
0.02
ND
0.2
ND
ND
ND
ND
ND
0.5
0.2
ND
ND
ND
ND
0.2
ND
0.2
0.2
0.6
1.1
0.3
0.2
ND
ND
ND
0.8
0.5
0.2
ND
ND
ND
0.4
0.2
ND
0.2
0.2
0.6
1.1
0.3
0.2
0/1
0/7
0/7
1/11
1/2
2/7
0/1
0/7
0/7
1/11
2/2
0/7
1/1
3/6
4/7
2/10
2/2
2/7
A-46
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
U-235
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
0.3
ND
0.06
ND
0.03
ND
Median
0.3
0.18
0.11
0.14
0.05
0.18
95th P
0.3
0.4
0.7
0.7
0.07
3.4
Max
0.3
0.4
0.7
1.7
0.07
3.4
No. Detects/
No. Analyses
1/1
5/7
7/7
9/11
2/2
6/7
Radionuclide Group:Fission and Activation Products
Ce-141
Co-57
Co-60
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.03
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.038
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.17
ND
ND
ND
0.038
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.17
ND
ND
ND
0.038
ND
ND
3.46
ND
ND
0/1
0/7
0/7
0/11
0/2
0/7
0/1
0/7
1/7
0/11
0/2
0/7
1/1
0/7
0/7
1/11
0/2
0/7
A-47
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
Cr-51
Cs-134
Cs-137
Eu-154
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.09
0.02
ND
0.03
0.04
0
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.09
0.06
0.05
0.08
0.055
0.08
ND
ND
ND
ND
ND
ND
95th P
ND
0.3
35
0.3
ND
ND
ND
ND
ND
ND
ND
ND
0.09
0.09
0.11
0.23
0.07
0.27
ND
ND
ND
ND
ND
ND
Max
ND
0.3
35
0.8
ND
ND
ND
ND
ND
ND
ND
ND
0.09
0.09
0.11
0.37
0.07
0.27
ND
ND
ND
ND
ND
ND
No. Detects/
No. Analyses
0/1
2/7
1/7
2/11
0/2
0/7
0/1
0/7
0/7
0/11
0/2
0/7
1/1
7/7
6/7
11/11
2/2
111
0/1
0/7
0/7
0/11
0/2
0/7
A-48
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
Fe-59
Sm-153
Sr-89
Sr-90
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1
ND
ND
ND
1
ND
0.6
ND
ND
ND
0.1
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1
0.6
0.4
2
6.5
ND
0.6
0.1
0.1
0.1
0.55
0.3
95th P
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1
30
20
300
12
1
0.6
1
1
6
1
0.9
Max
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1
30
20
300
12
1
0.6
1
1
6
1
0.9
No. Detects/
No. Analyses
0/1
0/7
0/7
0/11
0/2
0/7
0/1
0/7
0/7
0/11
0/2
0/7
1/1
3/5
4/7
8/9
2/2
2/6
1/1
3/5
5/7
8/9
2/2
5/6
A-49
-------
Table A.4 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Indicate the level(s) of wastewater treatment achieved by this treatment works."
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/gm = 37 Bq/kg)
Radionuclide
Zn-65
Response
Primary
Secondary
Advanced
Primary and
Secondary
Secondary and
Advanced
Primary,
Secondary, and
Advanced
Min
0.06
ND
ND
ND
ND
ND
Median
0.06
ND
ND
ND
ND
ND
95th P
0.06
ND
ND
ND
ND
ND
Max
0.06
ND
ND
ND
ND
ND
No. Detects/
No. Analyses
1/1
0/7
0/7
0/11
0/2
0/7
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-50
-------
Table A.5 Concentrations of Radionuclides in Sludge Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Flow Rate
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
10 MGD or less
1 0+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
0.11
0.18
0.09
0.17
0.1
ND
ND
ND
ND
ND
0.18
0.5
1.2
0.8
2.1
0.36
0.3
0.21
0.26
0.205
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.4
0.31
0.255
0.24
0.285
2
2
2.05
2.4
2
0.36
0.35
0.3
0.4
0.48
0.7
0.3
0.9
1.3
0.45
1.6
2.1
6.95
2.1
4.4
3.5
1.9
1
1.2
0.71
8
6
6
11
3
4
4.7
4.3
3.6
1.5
3.9
2.1
1.4
0.9
0.78
18
10
12
8
5
1.2
0.8
0.42
0.8
1.6
7
5
3
10.6
3.4
25
8.5
15
12
14
16
6
2.1
1.37
1.8
27
17
7
11
4
13
12
11
4
2.2
17
4.4
2.2
1.42
1.9
47
19
16
10.1
9.6
1.7
1.7
0.42
1
1.6
23
19
5.7
12
5
44
17
15
15.4
14
115/153
72/91
24/32
16/19
11/16
36/153
23/91
10/32
7/19
4/16
75/153
32/91
15/32
6/19
7/16
126/153
72/91
25/32
17/19
13/16
141/153
85/91
29/32
19/19
15/16
49/49
23/23
6/6
11/11
3/3
97/153
50/91
22/32
13/19
9/16
49/49
23/23
6/6
11/11
3/3
A-51
-------
Table A.5 Concentrations of Radionuclides in Sludge Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Flow Rate
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: C-14 and H-3
C-14*
H-3*
10 MGD or less
1 0+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
0.3
0.3
0.45
0.1
0.1
2
1
ND
0.6
0
5
3
4
2
6
3
2
0.5
0.6
0
8
4
4
2
6
34/85
18/39
1/16
7/10
3/8
58/85
27/39
13/16
6/10
7/8
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
0.16
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.16
0.19
0.07
0.19
0.8
ND
ND
ND
ND
ND
0.51
0.4
0.275
0.55
0.255
ND
ND
ND
ND
ND
1
0.8
0.55
0.9
0.67
0.9
0.5
0.27
0.6
1.1
2
0.8
0.3
0.8
1
2.7
1.16
1
1.4
0.8
1
0.6
0.4
0.6
0.4
9.7
2.9
3
3
1.3
6.8
1.7
0.48
1.4
6.7
13
1.6
1.1
0.9
3
15
2
2.5
1.55
2.5
12
5
0.8
0.7
1
38
6
4.3
4.8
7.8
9
1.8
0.48
1.7
6.7
52/153
32/91
5/32
6/19
6/16
151/153
88/91
30/32
19/19
15/16
25/153
12/91
4/32
4/19
2/16
138/153
75/91
26/32
17/19
15/16
49/49
23/23
6/6
11/11
3/3
A-52
-------
Table A.5 Concentrations of Radionuclides in Sludge Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Th-232
TI-208
Flow Rate
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
Min
0.08
0.07
0.02
0.09
0.2
ND
ND
ND
ND
ND
Median
0.2
0.17
0.1
0.39
0.22
0.08
0.08
0.03
0.07
0.06
95th P
0.6
0.4
0.4
0.56
1.1
1.3
0.41
0.35
0.69
0.53
Max
0.7
1.6
0.4
0.9
1.1
4.8
1.8
2.3
0.88
2.4
No. Detects/
No. Analyses
49/49
23/23
6/6
11/11
3/3
87/153
55/91
17/32
11/19
10/16
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.7
2.6
4.4
5.6
2.1
ND
ND
ND
ND
ND
ND
0.9
4.95
2.7
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
37
101
34
28
27
ND
ND
0.12
0.033
0.13
25
56
42
31
35
0.19
0.53
0.85
0.28
0.48
0.8
40
1.5
ND
ND
840
280
105
65
60.5
1.19
1.9
3.5
0.18
3.6
241
207
110
49
40
1.16
0.92
0.95
0.59
0.51
4/153
5/91
2/32
0/19
0/16
111/153
75/91
29/32
16/19
15/16
3/153
5/91
5/32
2/19
4/16
61/153
49/91
24/32
11/19
6/16
22/153
28/91
12/32
5/19
6/16
A-53
-------
Table A.5 Concentrations of Radionuclides in Sludge Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Flow Rate
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
0.8
2.3
1.8
ND
ND
ND
ND
ND
1.1
0.9
2.15
2
0.95
4
3.4
3.65
5.1
4.35
ND
ND
ND
ND
ND
6
8
9
19
2.9
12
13
12
10
6
ND
ND
ND
ND
ND
17
14.9
13.5
22
3.2
22
25
26
10
10
ND
0.07
ND
ND
ND
123/153
78/91
31/32
17/19
14/16
151/153
90/91
32/32
19/19
16/16
0/153
1/91
0/32
0/19
0/16
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
ND
ND
ND
ND
ND
0.01
0.01
0.02
0.01
ND
0.003
0.002
0
0.005
ND
ND
ND
ND
ND
ND
0.1
0.02
0.07
0.07
0
0.05
0.01
0.01
0.04
0.1
0.14
2.5
ND
ND
ND
0.19
0.03
0.07
0.14
0
0.12
0.03
0.01
0.07
0.1
5/153
5/91
0/32
0/19
0/16
40/49
19/23
5/6
10/11
1/3
35/49
17/23
4/6
11/11
1/3
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.09
ND
ND
0.06
ND
1/153
0/91
0/32
1/19
0/16
A-54
-------
Table A.5 Concentrations of Radionuclides in Sludge Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Rn-219
Th-227
U-235
Flow Rate
10 MGD or less
1 0+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.06
ND
95th P
ND
ND
ND
ND
ND
0.1
0.05
0.02
0.1
0.07
0.41
0.42
0.21
0.58
0.3
Max
ND
ND
ND
ND
ND
0.5
0.15
0.04
0.1
0.07
3.1
1.3
0.7
0.6
0.6
No. Detects/
No. Analyses
0/153
0/91
0/32
0/19
0/16
26/1 1 1
12/51
4/20
6/16
1/9
59/153
31/91
6/32
11/19
5/16
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Cr-51
Cs-134
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.016
ND
ND
ND
ND
ND
ND
0.6
ND
ND
ND
ND
ND
ND
ND
ND
0.016
ND
ND
ND
0.01
0.05
0.06
0.04
0.26
5.1
0.1
ND
0.03
ND
ND
ND
2.8
3.5
ND
0.04
ND
ND
ND
ND
0/153
1/91
0/32
0/19
0/16
1/153
1/91
2/32
1/19
1/16
9/153
3/91
0/32
1/19
0/16
0/153
0/91
5/32
1/19
0/16
1/153
0/91
0/32
0/19
0/16
A-55
-------
Table A.5 Concentrations of Radionuclides in Sludge Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Flow Rate
10 MGD or less
1 0+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
Zn-6550+MGDto100
MGD
More than 100 MGD
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.1
ND
ND
ND
ND
ND
Median
ND
ND
0.01
0.02
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1
0.2
0.5
0.45
0.05
0.1
0.2
0.05
0.1
0.1
ND
ND
ND
ND
ND
95th P
0.11
0.06
0.05
0.14
0.3
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
7
20
30
5
10
2
0.4
0.5
0.4
0.1
ND
ND
ND
ND
ND
* Indicates concentrations for this radionuclide are expressed in pC
Max
3.6
0.3
0.3
0.19
0.73
21
ND
ND
ND
ND
0.4
ND
ND
ND
ND
27
ND
ND
ND
ND
30
70
30
40
10
9.4
1
0.5
1
0.1
0.06
ND
ND
ND
ND
No. Detects/
No. Analyses
66/153
32/91
17/32
13/19
5/16
1/153
0/91
0/32
0/19
0/16
1/153
0/91
0/32
0/19
0/16
1/153
0/91
0/32
0/19
0/16
32/49
14/23
8/10
11/12
3/4
31/49
16/23
6/10
7/12
4/4
1/153
0/91
0/32
0/19
0/16
/g wet.
A-56
-------
Table A.6 Concentration of Radionuclides in Ash Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g = 37 Bq/kg.)
Radionuclide
Flow Rate
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
10 MGD or less
1 0+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
0.62
0.64
2.1
0.72
ND
ND
2
2
3
ND
ND
ND
ND
1.8
0.92
0.61
0.69
2.2
0.74
1
ND
1.1
2.5
0
ND
0.3
0.4
0.9
0.55
1.1
ND
1.7
1.1
1.9
1.2
1.3
2.7
5
2.7
2.2
2.8
1.7
3.1
1.7
3
2
5
5
5
3.4
ND
ND
ND
1.9
2.4
3.1
1.9
3.4
1.9
3.4
3.4
2
4
2
0.64
0.8
0.7
1
0.595
2.7
1.8
5.1
3.8
3.6
6
2.6
6.9
5.8
10.85
16
13.7
3.8
14.1
1.8
77
7
9
6
11
8.9
5.3
5
6.4
8.5
16.4
14.6
4.1
15.1
2
15
18
9
22
2.9
2.3
1.5
1.3
2.2
0.64
80
7.3
7.5
5.1
11
91
18
9
7
19
16
14
3.8
14.1
1.8
77
10
9
6
11
8.9
12.3
5
6.4
8.5
16.4
14.8
4.1
15.1
2
15
18
9
22
2.9
2.3
2.6
1.3
2.2
0.64
80
21
7.5
5.1
11
91
49
9
7
19
6/7
15/15
5/5
5/5
3/3
6/7
11/15
5/5
5/5
3/3
5/7
5/15
2/5
1/5
3/3
7/7
15/15
5/5
5/5
3/3
7/7
13/15
5/5
5/5
3/3
6/7
13/13
3/3
3/3
2/2
111
11/15
5/5
5/5
3/3
7/7
13/13
3/3
3/3
2/2
A-57
-------
Table A.6 Concentration of Radionuclides in Ash Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g = 37 Bq/kg.)
Radionuclide
U-238
C-14*
H-3*
Flow Rate
10 MGD or less
1 0+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
Min
1.1
0.8
2.5
3.8
2.5
ND
ND
ND
ND
ND
ND
ND
3
ND
ND
Median
4.3
2.4
6.2
4.7
8.75
ND
ND
ND-1
ND-0
ND
0.5
ND
5.5
ND
ND
95th P
74
6.2
6.4
5.1
15
1
0
1
0
ND
4
1
8
ND
ND
Max
74
35
6.4
5.1
15
1
0
1
0
ND
4
1
8
ND
ND
No. Detects/
No. Analyses
7/7
13/13
3/3
3/3
2/2
2/5
1/6
1/2
1/2
0/3
3/5
2/6
2/2
0/2
0/3
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
0.3
ND
ND
1.14
0.74
0.36
0.91
0.73
ND
ND
ND
ND
ND
1.8
0.68
0.65
1.6
1.8
ND
0.9
0.4
0.9
0.68
1.5
1.2
1.6
0.9
ND
1.7
1.6
1.5
1.42
1.1
ND
0.4
ND
0.5
ND
3
4.7
2.2
2.4
1.9
1.3
2.2
1.7
1.1
0.84
15.7
3.5
1.8
1.4
ND
15
3.3
1.7
1.5
1.2
1.8
2.4
1.3
1.3
ND
30
17
3.4
9.9
2.9
14
3.7
1.7
2.3
1
15.7
5.5
1.8
1.4
ND
15
6.6
1.7
1.5
1.2
1.8
4.9
1.3
1.3
ND
30
24
3.4
9.9
2.9
14
6.7
1.7
2.3
1
6/7
10/15
5/5
4/5
0/3
7/7
15/15
5/5
5/5
3/3
2/7
8/15
2/5
3/5
0/3
111
15/15
5/5
5/5
3/3
6/7
13/13
3/3
3/3
2/2
A-58
-------
Table A.6 Concentration of Radionuclides in
Annual Average Flow Rate Expressed in Million
(All concentrations are expressed in pCi/g dry, unless
Ash Summarized by
Gallons per Day (MGD)
noted; 1 pCi/g = 37 Bq/kg.)
Radionuclide
Th-232
TI-208
Flow Rate
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
Min
ND
0.3
0.22
0.5
0.39
0.36
ND
0.11
ND
0.63
Median
0.49
0.8
0.8
0.7
0.425
1.4
0.66
0.47
0.34
1.03
95th P
0.7
0.9
0.8
1
0.46
13.5
2.3
1.48
1.6
1.05
Max
0.7
1.7
0.8
1
0.46
13.5
3.1
1.48
1.6
1.05
No. Detects/
No. Analyses
6/7
13/13
3/3
3/3
2/2
7/7
13/15
5/5
4/5
3/3
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
0.05
0.22
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.62
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.13
0.39
ND
0.17
1.2
ND
ND
ND
ND
ND
3.3
ND
ND
ND
1
ND
ND
ND
ND
ND
1
ND
ND
ND
ND
3.8
20
7.4
4.3
81
ND
ND
ND
ND
ND
61
93
26
35
73
0.07
1.1
0.77
0.99
ND
1
0.3
ND
ND
ND
3.8
46
7.4
4.3
81
ND
ND
ND
ND
ND
61
105
26
35
73
0.07
1.53
0.77
0.99
ND
3/7
1/15
0/5
0/5
0/3
5/7
9/15
1/5
5/5
3/3
0/7
0/15
0/5
0/5
0/3
6/7
7/15
1/5
2/5
3/3
1/7
3/15
1/5
2/5
0/3
A-59
-------
Table A.6 Concentration of Radionuclides in
Annual Average Flow Rate Expressed in Million
(All concentrations are expressed in pCi/g dry, unless
Ash Summarized by
Gallons per Day (MGD)
noted; 1 pCi/g = 37 Bq/kg.)
Radionuclide
Flow Rate
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
2.2
ND
0.5
3.5
3.6
11.4
7.4
13
11
7.9
ND
ND
N D
ND
ND
4.3
5.3
0.8
12.5
6.1
13.7
14
17.4
15
10.8
ND
ND
ND
ND
ND
8.3
15
1.9
27
30
19.8
20
22
16
20.9
ND
ND
ND
ND
ND
8.3
15.4
1.9
27
30
19.8
22.4
22
16
20.9
ND
ND
ND
ND
ND
111
14/15
5/5
5/5
3/3
7/7
15/15
5/5
5/5
3/3
0/7
0/15
0/5
0/5
0/3
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
0
0
ND
ND
ND
0
0.01
ND
ND
ND
ND
ND
ND
0.02
0.03
0.01
0.01
ND
0.01
0.01
0.02
0.03
0.21
ND
ND
ND
ND
0.1
0.08
0.05
0.1
0.02
0.03
0.06
0.02
0.04
0.05
0.21
ND
ND
ND
ND
0.1
0.09
0.05
0.1
0.02
0.03
0.17
0.02
0.04
0.05
2/7
0/15
0/5
0/5
0/3
3/7
10/13
2/3
3/3
2/2
3/7
11/13
2/3
3/3
2/2
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.2
0.5
0.1
ND
ND
0.2
0.8
0.1
ND
ND
1/7
2/15
1/5
0/5
0/3
A-60
-------
Table A.6 Concentration of Radionuclides in
Annual Average Flow Rate Expressed in Million
(All concentrations are expressed in pCi/g dry, unless
Ash Summarized by
Gallons per Day (MGD)
noted; 1 pCi/g = 37 Bq/kg.)
Radionuclide
Rn-219
Th-227
U-235
Flow Rate
10 MGD or less
1 0+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND-0.02
0.04
ND-0.2
ND
0.3
0.11
0.18
0.18
0.14
95th P
ND
0.2
ND
ND
ND
0.2
0.6
0.2
0.2
ND
3.4
0.7
0.6
0.4
0.7
Max
ND
0.4
ND
ND
ND
0.2
1.1
0.2
0.2
ND
3.4
1.7
0.6
0.4
0.7
No. Detects/
No. Analyses
0/7
3/15
0/5
0/5
0/3
2/7
7/14
3/5
2/4
0/3
111
14/15
3/5
4/5
2/3
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Cr-51
Cs-134
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.038
ND
ND
ND
ND
ND
ND
0.3
0.8
35
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.17
ND
ND
ND
0.038
3.46
ND
ND
ND
ND
ND
0.3
0.8
35
ND
ND
ND
ND
ND
0/7
0/15
0/5
0/5
0/3
0/7
1/15
0/5
0/5
0/3
1/7
1/15
0/5
0/5
0/3
0/7
0/15
2/5
2/5
1/3
0/7
0/15
0/5
0/5
0/3
A-61
-------
Table A.6 Concentration of Radionuclides in Ash Summarized by
Annual Average Flow Rate Expressed in Million Gallons per Day (MGD)
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g = 37 Bq/kg.)
Radionuclide
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Flow Rate
10 MGD or less
1 0+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
10 MGD or less
10+ MGD to 50 MGD
50+ MGD to 100 MGD
More than 100 MGD
NR
Min
0
ND
0.02
0.04
0.04
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.6
0.4
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
0.07
0.06
0.08
0.08
0.07
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1.15
ND
3
2.7
0
0.2
0.95
0.1
ND-0.4
ND
ND
ND
ND
ND
95th P
0.11
0.18
0.09
0.27
0.23
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2
20
30
300
5
1
1
1
6
0.4
0.06
ND
ND
ND
ND
Max
0.11
0.37
0.09
0.27
0.23
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2
60
30
300
5
1
1
1
6
0.4
0.06
ND
ND
ND
ND
No. Detects/
No. Analyses
7/7
14/15
5/5
5/5
3/3
0/7
0/15
0/5
0/5
0/3
0/7
0/15
0/5
0/5
0/3
0/7
0/15
0/5
0/5
0/3
3/7
11/14
1/4
3/3
2/2
6/7
12/14
3/4
2/3
1/2
1/7
0/15
0/5
0/5
0/3
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-62
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
ND
ND
ND
ND
ND
ND
ND
0.17
ND
ND
0.17
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
3
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.245
0.485
0.32
0.26
0.39
0.27
0.4
0.17
0.19
ND
0.34
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
3
ND
ND
ND
ND
2.2
1.2
ND
ND
ND
ND
ND
ND
1.5
ND
1.1
6.8
1.6
1
1.8
0.8
7.9
0.17
0.8
ND
1.23
0.2
7
5
1
6
9
2
6
ND
6
3
2.6
ND
4
2.5
3.1
8
6
2.5
1.4
ND
2.5
ND
3
0
1.5
16
1.6
1.4
4.1
1.2
13
0.17
2.1
ND
1.23
0.2
16
27
1
17
20
6
17
ND
22
3
2.6
ND
13
9
3.1
11
12
3
4.7
ND
2.7
ND
3
0
79/106
74/84
2/3
8/11
33/48
10/13
14/17
1/1
10/17
0/1
5/5
2/5
32/106
15/84
1/3
3/11
15/48
2/13
3/17
0/1
7/17
1/1
1/5
0/5
48/106
35/84
2/3
8/11
18/48
6/13
7/17
0/1
7/17
0/1
3/5
1/5
A-63
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Pb-214
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
Min
ND
ND
0.27
ND
ND
ND
ND
0.28
ND
0.2
0.15
ND
Median
0.265
0.545
0.33
0.29
0.4
0.31
0.48
0.28
0.24
0.2
0.39
0.2
95th P
1.3
7.6
1.8
1.3
2
0.8
8.3
0.28
0.9
0.2
1.4
0.4
Max
1.5
17
1.8
2
4.4
1
15
0.28
2.2
0.2
1.4
0.4
No. Detects/
No. Analyses
79/106
75/84
3/3
9/11
36/48
11/13
14/17
1/1
15/17
1/1
5/5
4/5
Radionuclide Group: Uranium-238 Decay Series
Ra-226
Th-230
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
ABC
ND
ND
0
ND
ND
0
0.3
3.2
0
5
ND
ND
0.1
0.12
0.61
0.21
0.09
0.49
0.11
0.17
2
3
3
2.2
2
1.7
3
3.2
1.5
5
1.2
2
0.435
0.31
0.61
0.35
0.36
0.49
0.315
0.3
10
24
5.6
4
11
3
19
3.2
10
5
2.2
4
1.2
0.8
0.61
1.7
0.57
0.49
0.5
0.38
17
47
5.6
5
15
4
30
3.2
12
5
2.2
4
1.6
1.7
0.61
1.7
0.62
0.49
0.5
0.38
96/106
78/84
3/3
9/11
46/48
13/13
17/17
1/1
17/17
1/1
4/5
4/5
24/24
38/38
1/1
3/3
12/12
1/1
8/8
5/5
A-64
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Th-234
U-234
U-238
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
ABC
A
B
C
D
AB
AC
BC
ABC
Min
ND
ND
ND
ND
ND
ND
ND
1.2
ND
ND
ND
ND
0.43
0.39
1
0.71
0.8
2.1
0.18
0.8
0.37
0.18
1
0.53
0.7
1.4
0.19
0.6.
Median
0.7
0.5
0.5
1
0.9
1
0.1
1.2
0.5
ND
0.9
ND
2.1
1.95
1
2.1
2.05
2.1
0.85
1.3
1.9
1.35
1
2
1.6
1.4
0.65
1.3
95th P
7.8
5
1.3
2.3
8
2.3
3.6
1.2
5
ND
2.7
3
14
14
1
17
15
2.1
25
20
10.3
6.6
1
12
8
1.4
15
16
Max
15
23
1.3
11
19
6.8
15
1.2
16
ND
2.7
3
15.4
34
1
17
44
2.1
25
20
12.5
26
1
12
12
1.4
15
16
No. Detects/
No. Analyses
65/106
50/84
2/3
9/11
32/48
8/13
9/17
1/1
9/17
0/1
4/5
2/5
24/24
38/38
1/1
3/3
12/12
1/1
8/8
5/5
24/24
38/38
1/1
3/3
12/12
1/1
8/8
5/5
Radionuclide Group: C-14 and H-3
C-14*
A
B
C
D
AB
AC
BC
ABC
ABCD
NR
ND
ND
0
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.5
ND
ND
ND
0.5
ND
ND
ND
1
1
1
2
1
0
1
2
ND
ND
2
2
1
2
3
0
1
2
ND
ND
23/58
15/40
2/2
3/8
9/23
2/7
5/8
3/8
0/3
0/1
A-65
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
H-3*
Response
A
B
C
D
AB
AC
BC
ABC
ABCD
NR
Min
ND
ND
0
0.1
ND
ND
ND
ND
0
ND
Median
0.25
0.25
3.5
1
0.5
ND
ND- 1
0.45
0.4
ND
95th P
4
4
7
3
3
4
8
6
4
ND
Max
5
6
7
3
5
4
8
6
4
ND
No. Detects/
No. Analyses
39/58
27/40
2/2
8/8
18/23
3/7
4/8
7/8
3/3
0/1
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
ND
ND
ND
ND
ND
ND
ND
1
ND
0.6
ND
ND
ND
ND
0.57
0.2
ND
ND
0.07
1.2
0.12
0.47
0.21
0.2
ND
ND
ND
ND
ND
ND
ND
1
ND
0.6
ND
0.5
0.435
0.555
0.8
0.47
0.4
0.49
0.47
1.2
0.27
0.47
0.28
0.4
1
3.3
0.7
ND
1.4
0.7
1.3
1
0.9
0.6
ND
1
1
3
3.1
1.4
1.9
1.4
2.5
1.2
0.58
0.47
2.5
0.6
1.3
13
0.7
0.4
2.6
0.8
4
1
0.9
0.6
ND
1
1.55
15
3.1
1.9
2.9
1.4
3
1.2
0.62
0.47
2.5
0.6
38/106
29/84
1/3
1/11
12/48
4/13
6/17
1/1
5/17
1/1
0/5
3/5
102/106
82/84
3/3
11/11
47/48
12/13
17/17
1/1
17/17
1/1
5/5
5/5
A-66
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Ra-224
Ra-228
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
Min
ND
ND
ND
ND
ND
ND
ND
1.1
ND
ND
ND
ND
ND
ND
0.6
ND
ND
ND
ND
4.5
ND
0.9
0.44
ND
Median
ND
ND
ND
ND
ND
ND
ND
1.1
ND
ND
ND
ND
0.7
1.2
0.8
0.78
0.85
0.56
1.3
4.5
0.84
0.9
0.6
0.7
95th P
0.7
2.3
1
ND
1
ND
0.9
1.1
ND
ND
ND
ND
1.9
12
8
1.6
3
3.1
12
4.5
1.6
0.9
2.5
1.1
Max
1.1
12
1
0.4
2.7
0.4
3
1.1
0.2
ND
ND
ND
5
38
8
2.8
6
4.8
13
4.5
2.3
0.9
2.5
1.1
No. Detects/
No. Analyses
16/106
15/84
1/3
1/11
8/48
1/13
3/17
1/1
1/17
0/1
0/5
0/5
92/106
76/84
3/3
9/11
37/48
11/13
16/17
1/1
16/17
1/1
5/5
4/5
Radionuclide Group: Thorium-232 Decay Series
Th-228
Th-232
A
B
C
D
AB
AC
BC
ABC
A
B
C
D
AB
AC
BC
ABC
0.23
0.19
2.6
0.36
0.07
1.7
0.42
0.19
0.13
0.07
0.37
0.13
0.02
0.44
0.08
0.09
0.53
0.8
2.6
0.5
0.495
1.7
1.65
0.27
0.315
0.2
0.37
0.24
0.205
0.44
0.105
0.1
1.3
6.8
2.6
1.8
0.8
1.7
4.1
0.57
0.9
0.46
0.37
1.6
0.4
0.44
0.31
0.27
1.4
9
2.6
1.8
2.4
1.7
4.1
0.57
1.1
0.6
0.37
1.6
0.4
0.44
0.31
0.27
24/24
38/38
1/1
3/3
12/12
1/1
8/8
5/5
24/24
38/38
1/1
3/3
12/12
1/1
8/8
5/5
A-67
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
TI-208
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
Min
ND
ND
0.23
ND
ND
ND
ND
0.37
ND
0.11
ND
ND
Median
0.08
0.09
0.53
ND
ND
ND
0.07
0.37
0.05
0.11
0.06
0.11
95th P
0.69
2.4
2.7
1.4
0.6
0.2
1.1
0.37
0.17
0.11
2.3
0.15
Max
0.99
4.8
2.7
1.8
1.44
0.23
1.9
0.37
0.27
0.11
2.3
0.15
No. Detects/
No. Analyses
62/106
52/84
3/3
5/11
22/48
6/13
10/17
1/1
11/17
1/1
3/5
4/5
Radionuclide Group: Medical Isotopes
1-125
1-131
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.11
0.04
2
0.17
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2.35
1.3
0.59
4.1
1.65
0.56
0.2
0.11
4.2
2
11.3
2.2
0.8
ND
0.3
ND
ND
ND
ND
ND
ND
ND
ND
ND
60.5
42
2.2
51
105
23
4.2
0.11
19
2
65
34
40
0.9
0.3
0.5
0.7
4
ND
ND
ND
ND
ND
ND
280
220
2.2
73
840
106
39
0.11
36
2
65
34
6/106
1/84
1/3
1/11
1/48
1/13
0/17
0/1
0/17
0/1
0/5
0/5
88/106
65/84
2/3
9/11
36/48
9/13
9/17
1/1
17/17
1/1
5/5
4/5
A-68
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
ln-111
TI-201
TI-202
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
3.7
ND
56
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.14
ND
1.16
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.9
ND
0.49
3.5
ND
0.34
ND
3.7
2.3
56
10.2
ND
ND
ND
ND
ND
ND
ND
ND
0.14
ND
1.16
ND
ND
95th P
0.04
ND
0.05
ND
ND
ND
0.044
ND
3
ND
ND
ND
45
34
0.7
11.6
110
16
7.3
3.7
19
56
31
13
0.51
0.66
ND
ND
0.4
0.19
0.09
0.14
0.54
1.16
0.59
0.14
Max
3.6
0.17
0.05
ND
0.12
0.04
0.4
ND
3.5
ND
ND
ND
207
138
0.7
16
241
189
19
3.7
51
56
31
13
0.92
0.95
ND
0.11
0.85
0.19
0.55
0.14
0.54
1.16
0.59
0.14
No. Detects/
No. Analyses
8/106
2/84
1/3
0/11
1/48
1/13
2/17
0/1
4/17
0/1
0/5
0/5
59/106
31/84
2/3
6/11
20/48
7/13
6/17
1/1
13/17
1/1
4/5
1/5
25/106
19/84
0/3
1/11
8/48
3/13
3/17
1/1
8/17
1/1
2/5
2/5
A-69
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
ND
ND
0.7
0.2
ND
ND
ND
1.5
0.4
1.8
0.11
ND
ND
ND
3.2
2.3
ND
1.1
1.4
3
0.9
1.9
2.5
2.1
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1.8
0.57
1.2
2
0.8
1.4
0.6
1.5
1.9
1.8
1.4
1.5
4.35
4
3.6
4.5
3.25
5.1
3.6
3
3.5
1.9
4.8
3
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
11
4
2.9
8
4.9
14.9
5.5
1.5
6.6
1.8
4.1
1.6
12
13
5.4
22
12
10
6
3
8.7
1.9
6.7
4
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
22
8
2.9
9
8.7
17
8.6
1.5
10.7
1.8
4.1
1.6
15.4
22
5.4
26
25
10
6
3
9
1.9
6.7
4
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
95/106
64/84
3/3
11/11
38/48
12/13
12/17
1/1
17/17
1/1
5/5
4/5
105/106
83/84
3/3
11/11
47/48
13/13
17/17
1/1
17/17
1/1
5/5
5/5
0/106
0/84
0/3
0/11
0/48
0/13
0/17
0/1
0/17
0/1
0/5
1/5
A-70
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
ABC
A
B
C
D
AB
AC
BC
ABC
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.19
ND
ND
ND
ND
ND
ND
ND
0.11
ND
ND
0.00
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.01
0.01
0.19
0.01
0.01
ND
0.01
0.01
0.0035
0.002
0.11
0.004
0.0035
0.004
0.01
0.003
ND
0
0.12
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
0.05
0.19
0.01
0.03
ND
0.1
0.02
0.07
0.03
0.11
0.009
0.04
0.004
0.12
0.01
0.3
2.5
0.12
ND
ND
ND
0.1
ND
ND
ND
ND
ND
0.14
0.1
0.19
0.01
0.03
ND
0.1
0.02
0.1
0.03
0.11
0.009
0.04
0.004
0.12
0.01
3/106
5/84
1/3
0/11
0/48
0/13
1/17
0/1
0/17
0/1
0/5
0/5
22/24
30/38
1/1
2/3
10/12
0/1
6/8
4/5
17/24
26/38
1/1
2/3
11/12
1/1
6/8
4/5
A-71
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
ABC
ABCD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
0.1
ND
0.04
0.07
ND
0.2
0.02
ND
ND
0.09
ND
ND
ND
0.06
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.1
0.5
ND
0.04
0.1
ND
0.2
0.04
ND
ND
1/106
0/84
0/3
0/11
1/48
0/13
0/17
0/1
0/17
0/1
0/5
0/5
0/106
0/84
0/3
0/11
0/48
0/13
0/17
0/1
0/17
0/1
0/5
0/5
7/65
22/62
0/2
2/10
10/33
0/7
5/13
3/11
0/3
0/1
A-72
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
U-235
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.3
ND
ND
Median
ND
ND-0
0.06
ND
ND
ND
0.01
ND
ND
0.3
ND
ND
95th P
0.42
0.5
0.17
0.07
0.46
0.15
0.28
ND
0.1
0.3
ND
ND
Max
0.61
1.3
0.17
1.3
3.1
0.31
0.7
ND
0.7
0.3
ND
ND
No. Detects/
No. Analyses
31/106
42/84
2/3
3/11
16/48
3/13
9/17
0/1
5/17
1/1
0/5
0/5
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.06
ND
ND
ND
ND
0.016
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.05
ND
ND
0.26
ND
ND
ND
0.06
ND
ND
ND
0/106
1/84
0/3
0/11
0/48
0/13
0/17
0/1
0/17
0/1
0/5
0/5
0/106
2/84
0/3
0/11
1/48
0/13
0/17
0/1
3/17
0/1
0/5
0/5
A-73
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Co-60
Cr-51
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
95th P
ND
ND
ND
ND
ND
ND
ND
ND
0.04
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.6
ND
ND
ND
Max
0.1
1.16
ND
ND
5.1
ND
0.07
ND
0.08
ND
ND
ND
2.8
ND
ND
ND
3.5
ND
ND
ND
0.8
ND
ND
ND
No. Detects/
No. Analyses
3/106
4/84
0/3
0/11
2/48
0/13
1/17
0/1
3/17
0/1
0/5
0/5
3/106
0/84
0/3
0/11
1/48
0/13
0/17
0/1
2/17
0/1
0/5
0/5
Radionuclide Group: Fission and Activation Products
Cs-134
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.04
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0/106
1/84
0/3
0/11
0/48
0/13
0/17
0/1
0/17
0/1
0/5
0/5
A-74
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Cs-137
Eu-154
Fe-59
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
0.02
ND
0.03
ND
ND
ND
ND
ND
0.014
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
95th P
0.19
0.08
0.07
0.1
0.11
0.05
0.1
ND
0.06
ND
0.05
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Max
1.5
3.6
0.07
0.3
1.1
0.07
0.11
ND
0.11
ND
0.05
ND
21
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.4
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
No. Detects/
No. Analyses
63/106
25/84
2/3
4/11
16/48
5/13
6/17
0/1
11/17
0/1
1/5
0/5
1/106
0/84
0/3
0/11
0/48
0/13
0/17
0/1
0/17
0/1
0/5
0/5
0/106
1/84
0/3
0/11
0/48
0/13
0/17
0/1
0/17
0/1
0/5
0/5
A-75
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Fission and Activation Products
Sm-153
Sr-89
Sr-90
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
A
B
C
D
AB
AC
BC
ABC
A
B
C
D
AB
AC
BC
ABC
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2
ND
ND
1
ND
ND
ND
ND
ND
ND
ND
1
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.15
1
2
ND-0
0.3
1
1
3
0.1
0.1
ND
0.15
0.05
1
0.1
ND-0.1
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2
20
2
2
20
1
7
30
9
0.4
ND
0.4
0.3
1
0.4
0.3
ND
ND
ND
ND
27
ND
ND
ND
ND
ND
ND
ND
10
70
2
2
40
1
7
30
9.4
2
ND
0.4
0.7
1
0.4
0.3
0/106
0/84
0/3
0/11
1/48
0/13
0/17
0/1
0/17
0/1
0/5
0/5
18/26
25/35
1/1
3/6
11/16
1/1
4/7
5/6
19/26
23/35
0/1
4/6
9/16
1/1
5/7
3/6
A-76
-------
Table A.7 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Zn-65
Response
A
B
C
D
AB
AC
BC
CD
ABC
BCD
ABCD
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
95th P
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Max
ND
ND
ND
ND
0.06
ND
ND
ND
ND
ND
ND
ND
No. Detects/
No. Analyses
0/106
0/84
0/3
0/11
1/48
0/13
0/17
0/1
0/17
0/1
0/5
0/5
* Indicates concentrations for this radionuclide are exoressed in oCi/a wet.
A-77
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
ND
1.3
1.06
0.72
2.8
0.64
2.2
ND
ND
1.1
ND
2
2
2
ND
ND
ND
ND
ND
ND
ND
0.61
1.32
1.17
0.74
3.1
0.69
2.4
ND
ND
2.2
0
9.5
1.1
4
2.15
4.65
1.28
9.9
2.8
0.64
2.2
4
3
7
6
2
2
2
2.7
4.45
ND
ND
ND
ND
ND
2.3
5.1
1.35
11.1
3.1
0.69
2.4
2.9
4.05
2.5
16.7
9.5
1.1
4
9
16
2.8
14.1
2.8
0.64
2.2
7
77
11
11
2
2
2
8.5
8.9
ND
1.8
ND
ND
ND
10
16.4
3
15.1
3.1
0.69
2.4
17
15
6.6
22
9.5
1.1
4
13.7
16
2.8
14.1
2.8
0.64
2.2
10
77
11
11
2
2
2
12.3
8.9
ND
1.8
ND
ND
ND
14.8
16.4
3
15.1
3.1
0.69
2.4
18
15
6.6
22
9.5
1.1
4
19/20
4/4
3/3
5/5
1/1
1/1
1/1
17/20
3/4
3/3
4/5
1/1
1/1
1/1
12/20
3/4
0/3
1/5
0/1
0/1
0/1
20/20
4/4
3/3
5/5
1/1
1/1
1/1
19/20
3/4
3/3
5/5
1/1
1/1
1/1
A-78
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Th-230
Response
A
B
D
AB
AC
ACD
Min
ND
0.64
0.3
0.55
0.6
0.4
Median
1
0.95
0.45
0.7
0.6
0.4
95th P
2.3
1
0.6
1.3
0.6
0.4
Max
2.6
1
0.6
1.3
0.6
0.4
No. Detects/
No. Analyses
14/15
4/4
2/2
5/5
1/1
1/1
Radionuclide Group: Uranium-238 Decay Series
Th-234
U-234
U-238
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
A
B
D
AB
AC
ACD
ND
1.1
ND
ND
ND
1.7
1.1
1.3
1.2
12
6.9
1.9
2.7
0.8
1.1
6.2
3.3
1.7
2.5
3.6
11.4
4.9
4.2
ND
1.7
1.1
5.1
1.95
12.5
7.3
1.9
2.7
3.1
1.65
7.6
5.1
1.7
2.5
7.2
80
10
11
ND
1.7
1.1
18
91
13
19
1.9
2.7
6.4
74
9
15
1.7
2.5
7.3
80
10
11
ND
1.7
1.1
49
91
13
19
1.9
2.7
35
74
9
15
1.7
2.5
19/20
4/4
2/3
4/5
0/1
1/1
1/1
15/15
4/4
2/2
5/5
1/1
1/1
15/15
4/4
2/2
5/5
1/1
1/1
Radionuclide Group: C-14 and H-3
C-14*
H-3*
A
B
AB
A
B
AB
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
1
ND
3
4
ND
1
1
ND
8
4
ND
4/13
1/3
0/2
6/13
1/3
0/2
A-79
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ND
ND
0.6
ND
2.1
0.3
0.9
0.73
1.3
0.74
1
2.4
0.36
1.14
ND
ND
0.4
ND
0.4
ND
0.6
0.68
2.2
0.71
1.8
5.7
0.65
2.4
ND
0.7
0.9
0.68
1.7
0.4
1.25
3.45
0.9
ND
2.1
0.3
0.9
1.5
4.55
0.99
1.5
2.4
0.36
1.14
ND
ND
0.8
ND
0.4
ND
0.6
2.45
15.15
1.46
7.8
5.7
0.65
2.4
1.3
4.1
1.4
1.7
1.7
0.4
2.4
15.7
1.5
1.6
2.1
0.3
0.9
2.6
15
1.7
1.6
2.4
0.36
1.14
2
4.9
1.8
1.3
0.4
ND
0.6
9.6
30
3.2
9.9
5.7
0.65
2.4
3.4
14
1.9
2.4
1.7
0.4
3.5
15.7
1.5
1.6
2.1
0.3
0.9
3.3
15
1.7
1.6
2.4
0.36
1.14
2.4
4.9
1.8
1.3
0.4
ND
0.6
17
30
3.2
9.9
5.7
0.65
2.4
3.7
14
1.9
2.4
1.7
0.4
14/20
3/4
3/3
2/5
1/1
1/1
1/1
20/20
4/4
3/3
5/5
1/1
1/1
1/1
7/20
1/4
3/3
2/5
1/1
0/1
1/1
20/20
4/4
3/3
5/5
1/1
1/1
1/1
14/15
4/4
2/2
5/5
1/1
1/1
A-80
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Th-232
TI-208
Response
A
B
D
AB
AC
ACD
A
B
D
AB
AC
ACD
ABCD
Min
ND
0.4
0.5
0.39
0.5
0.22
ND
1.16
0.23
ND
0.73
0.11
0.34
Median
0.8
0.475
0.6
0.5
0.5
0.22
0.89
2
0.3
0.47
0.73
0.11
0.34
95th P
1
0.9
0.7
0.8
0.5
0.22
2.3
13.5
0.55
1.05
0.73
0.11
0.34
Max
1.7
0.9
0.7
0.8
0.5
0.22
3.1
13.5
0.55
1.05
0.73
0.11
0.34
No. Detects/
No. Analyses
14/15
4/4
2/2
5/5
1/1
1/1
19/20
4/4
3/3
3/5
1/1
1/1
1/1
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1.14
7.4
0.61
ND
ND
ND
ND
ND
ND
ND
ND
ND-0.8
ND
ND
ND
ND
ND
0.22
0.815
ND
0.05
1.14
7.4
0.61
ND
ND
ND
ND
ND
ND
ND
ND
1
ND
0.3
ND
ND
ND
4.3
46
ND
81
1.14
7.4
0.61
ND
ND
ND
ND
ND
ND
ND
0.4
1
ND
0.3
ND
ND
ND
20
46
ND
81
1.14
7.4
0.61
ND
ND
ND
ND
ND
ND
ND
1/20
2/4
0/3
1/5
0/1
0/1
0/1
14/20
3/4
0/3
3/5
1/1
1/1
1/1
0/20
0/4
0/3
0/5
0/1
0/1
0/1
A-81
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
TI-201
TI-202
Response
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
Min
ND
3.3
ND
ND
93
26
11
ND
ND
ND
ND
1.53
0.77
0.99
Median
0.49
46
ND
ND
93
26
11
ND
ND
ND
ND
1.53
0.77
0.99
95th P
35
105
ND
73
93
26
11
0.14
ND
ND
0.1
1.53
0.77
0.99
Max
48
105
ND
73
93
26
11
1.1
ND
ND
0.1
1.53
0.77
0.99
No. Detects/
No. Analyses
11/20
4/4
0/3
1/5
1/1
1/1
1/1
3/20
0/4
0/3
1/5
1/1
1/1
1/1
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
0.14
2.2
ND
0.5
4.3
1.9
12.5
7.4
8.4
9.7
10.8
9.4
15
16
ND
ND
ND
ND
ND
ND
ND
7.65
3.3
1.2
3.6
4.3
1.9
12.5
15.9
14.75
12
13
9.4
15
16
ND
ND
ND
ND
ND
ND
ND
27
15
2.2
5.3
4.3
1.9
12.5
22
19.8
12.7
14.2
9.4
15
16
ND
ND
ND
ND
ND
ND
ND
30
15
2.2
5.3
4.3
1.9
12.5
22.4
19.8
12.7
14.2
9.4
15
16
ND
ND
ND
ND
ND
ND
ND
20/20
4/4
2/3
5/5
1/1
1/1
1/1
20/20
4/4
3/3
5/5
1/1
1/1
1/1
0/20
0/4
0/3
0/5
0/1
0/1
0/1
A-82
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
A
B
D
AB
AC
ACD
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
ND
ND
ND
0.01
0
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.03
0
ND-0.01
0.02
ND
ND
0.01
0.009
0.02
0.01
ND
ND
ND
0.04
ND
ND
ND
ND
ND
0.1
0.02
0.01
0.08
ND
ND
0.06
0.02
0.03
0.05
ND
ND
0.21
0.04
ND
ND
ND
ND
ND
0.1
0.02
0.01
0.08
ND
ND
0.17
0.02
0.03
0.05
ND
ND
1/20
1/4
0/3
0/5
0/1
0/1
0/1
11/15
3/4
1/2
5/5
0/1
0/1
11/15
3/4
2/2
5/5
0/1
0/1
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.2
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.2
ND
ND
0.5
ND
0.2
0.1
ND
ND
ND
0.2
ND
ND
ND
0.2
ND
ND
0.8
ND
0.2
0.1
ND
ND
ND
0.4
ND
ND
ND
0.2
ND
ND
2/20
0/4
1/3
1/5
0/1
0/1
0/1
2/20
0/4
0/3
0/5
1/1
0/1
0/1
A-83
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Th-227
U-235
Response
A
B
D
AB
AC
ACD
A
B
D
AB
AC
ACD
ABCD
Min
ND
ND
0.02
ND
0.1
0.04
ND
0.06
0.15
0.14
0.03
0.18
0.11
Median
ND
ND
0.11
ND
0.1
0.04
0.14
0.08
0.4
0.4
0.03
0.18
0.11
95th P
0.3
0.6
0.2
0.2
0.1
0.04
0.7
3.4
0.5
0.7
0.03
0.18
0.11
Max
1.1
0.6
0.2
0.2
0.1
0.04
1.7
3.4
0.5
0.7
0.03
0.18
0.11
No. Detects/
No. Analyses
7/20
1/4
2/2
2/5
1/1
1/1
15/20
4/4
3/3
5/5
1/1
1/1
1/1
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.038
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.17
ND
ND
ND
ND
ND
ND
3.46
ND
ND
ND
ND
ND
ND
0/20
0/4
0/3
0/5
0/1
0/1
0/1
1/20
0/4
0/3
0/5
0/1
0/1
0/1
2/20
0/4
0/3
0/5
0/1
0/1
0/1
A-84
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Cr-51
Cs-134
Cs-137
Response
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
Min
ND
ND
ND
ND
ND
0.3
0.8
ND
ND
ND
ND
ND
ND
ND
ND
0.03
0.03
0.04
0.04
0.02
0.08
Median
ND
ND
ND
ND
ND
0.3
0.8
ND
ND
ND
ND
ND
ND
ND
0.085
0.05
0.05
0.05
0.04
0.02
0.08
95th P
ND
ND
ND
35
ND
0.3
0.8
ND
ND
ND
ND
ND
ND
ND
0.27
0.08
0.11
0.08
0.04
0.02
0.08
Max
0.2
ND
ND
35
ND
0.3
0.8
ND
ND
ND
ND
ND
ND
ND
0.37
0.08
0.11
0.08
0.04
0.02
0.08
No. Detects/
No. Analyses
1/20
0/4
0/3
2/5
0/1
1/1
1/1
0/20
0/4
0/3
0/5
0/1
0/1
0/1
19/20
4/4
3/3
5/5
1/1
1/1
1/1
Radionuclide Group: Fission and Activation Products
Eu-154
Fe-59
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
ABCD
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0/20
0/4
0/3
0/5
0/1
0/1
0/1
0/20
0/4
0/3
0/5
0/1
0/1
0/1
A-85
-------
Table A.8 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What are the primary sources of drinking water for your community?"
A=Municipal/Surface, B=Municipal/Ground, C=Private Wells, D=Private/Surface
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Sm-153
Sr-89
Sr-90
Zn-65
Response
A
B
D
AB
AC
ACD
ABCD
A
B
D
AB
AC
ACD
A
B
D
AB
AC
ACD
A
B
D
AB
AC
ACD
ABCD
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
12
30
ND
ND
ND
ND
0.1
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
1
ND- 1
ND-20
0.4
12
30
0.1
0.2
ND-0.7
0.3
0.1
ND
ND
ND
ND
ND
ND
ND
ND
95th P
ND
ND
ND
ND
ND
ND
ND
5
2
20
300
12
30
1
1
0.7
6
0.1
ND
ND
ND
ND
ND
ND
ND
ND
Max
ND
ND
ND
ND
ND
ND
ND
60
2
20
300
12
30
1
1
0.7
6
0.1
ND
0.06
ND
ND
ND
ND
ND
ND
No. Detects/
No. Analyses
0/20
0/4
0/3
0/5
0/1
0/1
0/1
11/17
2/4
1/2
4/5
1/1
1/1
15/17
3/4
1/2
4/5
1/1
0/1
1/20
0/4
0/3
0/5
0/1
0/1
0/1
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-86
-------
Table A.9 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Does your wastewater collection system receive discharges of
drinking water treatment residuals?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
Yes
No
NR
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.2
0.14
0.09
ND
ND
0.1
0.39
0.18
0.18
0.19
0.3
0.295
ND-0.23
ND
ND
ND-2
ND
ND
ND-0.4
0.33
0.3
0.2
2
2
0.5
0.39
0.325
0.5
0.65
1.25
1.85
2.1
1.4
1.4
1.9
3
0.27
10
7
6
4.2
4
0.6
2
3.1
0.31
10
15
2.4
1.6
0.8
5
7
6.8
17
17
12.5
12
16
16
0.27
22
27
6
5.6
13
0.6
17
17
0.31
47
30
2.4
1.7
1.7
16
23
6.8
20
44
16
26
85/105
151/202
2/4
29/105
49/202
2/4
41/105
92/202
2/4
93/105
157/202
3/4
100/105
185/202
4/4
30/30
62/62
62/105
125/202
4/4
30/30
62/62
30/30
62/62
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
1
0
ND
ND-0
0.4
0.2
2
1
1
0
3
5
3
2
3
0
8
7
3
26/49
35/107
1/2
35/49
74/107
2/2
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Yes
No
NR
ND
ND
ND
ND
ND
ND-0.4
1.4
1.1
0.5
13
6.8
0.5
36/105
63/202
2/4
A-87
-------
Table A.9 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Does your wastewater collection system receive discharges of
drinking water treatment residuals?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Response
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
Yes
No
Yes
No
NR
Min
ND
ND
0.09
ND
ND
ND
ND
ND
ND
0.19
0.07
0.08
0.02
ND
ND
ND
Median
0.5
0.435
0.23
ND
ND
ND
0.9
0.81
0.275
0.75
0.6
0.23
0.195
0.09
0.04
ND-0.1
95th P
1.9
1.9
0.49
0.9
1
ND
4
6.7
0.53
4.6
4.1
1.1
0.52
1.4
0.9
0.15
Max
15
5.4
0.49
12
5
ND
20
38
0.53
9
9
1.6
0.7
4.1
4.8
0.15
No. Detects/
No. Analyses
104/105
195/202
4/4
17/105
30/202
0/4
97/105
171/202
3/4
30/30
62/62
30/30
62/62
70/105
108/202
2/4
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2.9
1.45
ND-0.56
ND
ND
ND
0.3
ND
ND
ND
ND
ND
ND
ND
ND
42
60.5
0.67
0.044
0.03
0.04
45
48
3.1
0.4
0.56
0.01
0.7
40
ND
840
280
0.67
3.6
3.5
0.04
176
241
3.1
0.93
1.16
0.01
1/105
1 0/202
0/4
90/105
154/202
2/4
7/105
11/202
1/4
53/105
97/202
1/4
24/105
48/202
1/4
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
Yes
No
NR
Yes
No
NR
ND
ND
0.1
ND
ND
2.7
1.2
1.2
0.48
4
3.9
4.1
9.9
7.2
14.9
12
13
5.7
22
17
14.9
22
26
5.7
90/105
169/202
4/4
104/105
200/202
4/4
A-88
-------
Table A.9 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Does your wastewater collection system receive discharges of
drinking water treatment residuals?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
La-138
Response
Yes
No
NR
Min
ND
ND
ND
Median
ND
ND
ND
95th P
ND
ND
ND
Max
ND
0.07
ND
No. Detects/
No. Analyses
0/105
1/202
0/4
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
NR
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.01
0.01
0.0045
0.002
ND
ND
ND
0.1
0.05
0.05
0.04
0.1
2.5
ND
0.14
0.19
0.07
0.12
4/105
6/202
0/4
26/30
49/62
24/30
44/62
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND-0.15
ND
ND
ND
ND
ND
ND
0.1
0.09
ND
0.42
0.5
0.31
0.09
ND
ND
ND
ND
ND
0.5
0.5
ND
1.1
3.1
0.31
2/105
0/202
0/4
0/105
0/202
0/4
18/67
31/138
0/2
37/105
73/202
2/4
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Cr-51
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.016
ND
ND
0.26
0.06
ND
0.08
5.1
ND
3.5
0.8
ND
1/105
0/202
0/4
1/105
5/202
0/4
5/105
8/202
0/4
3/105
3/202
0/4
A-89
-------
Table A.9 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Does your wastewater collection system receive discharges of
drinking water treatment residuals?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
Yes
No
Yes
No
NR
Min
ND
ND
ND
ND
ND
0.01
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
0.02
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.6
0.3
0.1
0.1
ND
ND
ND
95th P
ND
ND
ND
0.11
0.11
0.04
ND
ND
ND
ND
ND
ND
ND
ND
ND
20
20
0.4
1
ND
ND
ND
Max
ND
0.04
ND
0.4
3.6
0.04
ND
21
ND
ND
0.4
ND
ND
27
ND
70
30
2
9.4
ND
0.06
ND
No. Detects/
No. Analyses
0/105
1/202
0/4
49/105
80/202
4/4
0/105
1/202
0/4
0/105
1/202
0/4
0/105
1/202
0/4
25/33
43/65
20/33
44/65
0/105
1/202
0/4
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-90
-------
Table A.10 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Does your wastewater collection system receive discharges of
drinking water treatment residuals?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
0.62
ND
ND
ND
ND
ND
0.61
0.69
ND
ND
0.6
ND
1
ND
1.3
1.2
0.8
1.1
2.15
3
5
3
3.75
ND
2.3
3.2
2.4
3.4
1.1
0.64
3.7
2.7
6.05
5.55
3.65
3.3
13.7
14
11
9
8.9
4.4
14.8
14.6
17
18
2.6
1.4
10
11
91
13
74
6.4
14.1
16
77
11
12.3
5.3
15.1
16.4
22
18
2.6
2.2
80
21
91
19
74
15
16/16
18/19
14/16
16/19
10/16
6/19
16/16
19/19
15/16
18/19
10/10
17/18
16/16
15/19
10/10
18/18
10/10
18/18
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
0.7
ND
1
0
8
0.5
1
0
8
0.5
3/10
2/8
6/10
1/8
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
0.85
0.36
ND
ND
0.68
0.65
0.7
ND
0.49
ND
0.34
ND
1.4
0.8
1.5
1.42
ND
ND
2.45
2.9
2.05
1.45
0.8
0.49
1.095
0.47
2.4
5.5
2.6
6.6
1.8
2
9.6
24
3.4
6.7
1.7
0.9
2.3
2
3.5
15.7
3.3
15
2.4
4.9
9.9
30
3.4
14
1.7
1
3.1
13.5
13/16
12/19
16/16
19/19
6/16
9/19
16/16
19/19
10/10
17/18
10/10
17/18
16/16
16/19
A-91
-------
Table A.10 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Does your wastewater collection system receive discharges of
drinking water treatment residuals?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.09
0.37
ND
ND
ND-0.36
1.3
ND
ND
ND
0.4
1.17
46
ND
ND
48
93
0.99
0.77
1
0.8
20
81
ND
ND
61
105
1.1
1.53
1/16
3/19
10/16
13/19
0/16
0/19
8/16
11/19
3/16
4/19
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
Yes
No
Yes
No
Yes
No
0.14
ND
7.4
7.9
ND
ND
7.85
4.3
15.8
14
ND
ND
27
13
20.9
19.8
ND
ND
30
15
22.4
22
ND
ND
16/16
18/19
16/16
19/19
0/16
0/19
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.015
0.015
0.005
0.01
ND
0.04
0.1
0.09
0.17
0.04
ND
0.21
0.1
0.1
0.17
0.05
0/16
2/19
7/10
13/18
8/10
13/18
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
0.03
ND
ND
ND
ND
ND
ND-0.02
0.11
0.18
0.2
0.1
ND
0.2
0.2
0.3
1.7
0.6
0.8
0.5
0.4
0.2
1.1
0.6
3.4
0.7
2/16
2/19
1/16
2/19
5/15
9/18
11/16
19/19
Radionuclide Group: Fission and Activation Products
Ce-141
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0/16
0/19
A-92
-------
Table A.10 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Does your wastewater collection system receive discharges of
drinking water treatment residuals?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg)
Radionuclide
Co-57
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
0.095
0.05
ND
ND
ND
ND
ND
ND
0.65
1
0.1
0.3
ND
ND
95th P
ND
ND
ND
ND
0.3
0.3
ND
ND
0.27
0.08
ND
ND
ND
ND
ND
ND
60
20
1
1
ND
ND
Max
0.17
ND
3.46
0.038
0.8
35
ND
ND
0.37
0.09
ND
ND
ND
ND
ND
ND
300
30
6
1
ND
0.06
No. Detects/
No. Analyses
1/16
0/19
1/16
1/19
2/16
3/19
0/16
0/19
15/16
19/19
0/16
0/19
0/16
0/19
0/16
0/19
7/12
13/18
10/12
14/18
0/16
1/19
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-93
-------
Table A.11 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Does your waste water collection system include
combined sanitary and storm water sewers?"
(All concentration are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.14
0.09
ND
ND
0.18
0.39
0.19
0.18
0.31
0.275
ND
ND
ND
ND
0.37
0.3
2.2
2
0.415
0.32
0.6
0.75
1.45
2.1
1.1
1.4
1.9
2.9
4
9
5.6
3
2
3
10
14
1.7
0.8
3
7.8
7.3
17
6.6
12
16
16
22
27
11
13
17
17
47
30
1.7
1.6
16
23
20
44
16
26
73/95
165/216
26/95
54/216
43/95
92/216
80/95
173/216
88/95
201/216
22/22
70/70
57/95
134/216
22/22
70/70
22/22
70/70
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
0.4
0.3
1
1
6
4
3
2
8
7
20/49
42/109
39/49
72/109
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.19
0.07
0.08
0.02
ND
ND
ND
ND
0.5
0.4
ND
ND
0.8
0.83
0.7
0.6
0.255
0.185
0.08
0.06
1.3
1.1
1.9
1.9
0.7
1
4
7.9
6.7
4.1
0.9
0.5
1.8
0.9
13
6.8
15
5.4
12
4
20
38
9
9
1.6
1.1
4.1
4.8
34/95
67/216
92/95
211/216
15/95
32/216
83/95
188/216
22/22
70/70
22/22
70/70
57/95
123/216
A-94
-------
Table A.11 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Does your waste water collection system include
combined sanitary and storm water sewers?"
(All concentration are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2.6
1.55
ND
ND
1.2
ND
ND
ND
ND
ND
82
44
0.033
0.04
36
48
0.4
0.54
1.5
40
280
840
1.19
3.6
241
207
0.82
1.16
2/95
9/216
78/95
168/216
7/95
12/216
59/95
92/216
25/95
48/216
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
Yes
No
Yes
No
Yes
No
ND
ND
1.6
ND
ND
ND
3.5
0.9
5
3.5
ND
ND
13.5
3
13
12
ND
ND
22
6
26
25
ND
0.07
88/95
175/216
95/95
213/216
0/95
1/216
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.01
0.01
0.004
0.002
ND
ND
0.07
0.07
0.04
0.05
0.1
2.5
0.14
0.19
0.07
0.12
1/95
9/216
17/22
58/70
18/22
50/70
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
0.1
0.29
0.5
0.06
0.09
ND
ND
0.5
0.5
0.7
3.1
1/95
1/216
0/95
0/216
11/60
38/147
28/95
84/216
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.016
ND
0.04
0.26
1/95
0/216
1/95
5/216
A-95
-------
Table A.11 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Does your waste water collection system include
combined sanitary and storm water sewers?"
(All concentration are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.)
Radionuclide
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
0.029
ND
ND
ND
ND
ND
ND
ND
0.3
0.8
0.1
0.1
ND
ND
95th P
ND
ND
ND
ND
ND
ND
0.11
0.11
ND
ND
ND
ND
ND
ND
5
20
0.5
1
ND
ND
Max
0.3
5.1
3.5
2.8
ND
0.04
0.3
3.6
ND
21
0.4
ND
ND
27
70
40
0.6
9.4
ND
0.06
No. Detects/
No. Analyses
4/95
9/216
3/95
3/216
0/95
1/216
58/95
75/216
0/95
1/216
1/95
0/216
0/95
1/216
18/28
50/70
17/28
47/70
0/95
1/216
* Indicates concentrations for this radionuclide are expressed in pCi/a wet.
A-96
-------
Table A.12 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Does your waste water collection system include
combined sanitary and storm water sewers?"
(All concentration are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
1.06
ND
ND
ND
ND
ND
1.17
0.61
ND
ND
0.6
ND
ND
ND
2.1
1.2
1.9
0.8
2.2
2.9
5
3
ND
ND-1.8
2.4
3.15
2.5
3.7
1.3
0.64
3.7
2.15
5.3
6
4.3
3.1
3.8
14.1
10
11
8.5
5.3
4.1
15.1
9.4
18
2.6
1.5
7.5
21
49
19
35
15
13.7
16
11
77
12.3
8.9
14.8
16.4
17
22
2.6
2.3
10
80
49
91
35
74
15/15
19/20
14/15
16/20
6/15
10/20
15/15
20/20
14/15
19/20
9/9
18/19
14/15
17/20
9/9
19/19
9/9
19/19
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
0.4
ND
1
0
8
2
1
1
8
4
2/7
3/11
4/7
3/11
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
0.74
0.36
ND
ND
0.71
0.65
0.9
ND
0.7
ND
ND
ND
1.3
1.2
1.5
1.55
0.4
ND
2.3
4.45
1.7
1.5
0.8
0.49
0.55
0.74
1.8
5.5
2.1
6.6
1.8
2
3.7
24
3.4
6.7
1
0.9
1.6
3.1
2.4
15.7
2.6
15
2.4
4.9
4.7
30
3.4
14
1
1.7
2.3
13.5
12/15
13/20
15/15
20/20
8/15
7/20
15/15
20/20
9/9
18/19
9/9
18/19
14/15
18/20
A-97
-------
Table A.12 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Does your waste water collection system include
combined sanitary and storm water sewers?"
(All concentration are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.525
ND
ND
ND
5.05
ND
ND
ND
0.8
3.8
46
ND
ND
11
93
0.07
1.1
ND
1
4.3
81
ND
ND
35
105
0.99
1.53
0/15
4/20
7/15
16/20
0/15
0/20
5/15
14/20
2/15
5/20
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
Yes
No
Yes
No
Yes
No
0.14
ND
9.7
7.4
ND
ND
8.2
4.3
16
13.6
ND
ND
27
15
20.9
19.8
ND
ND
30
15.4
22.4
22
ND
ND
15/15
19/20
15/15
20/20
0/15
0/20
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.02
0.01
0.01
0.009
ND
0.04
0.1
0.09
0.06
0.05
ND
0.21
0.1
0.1
0.06
0.17
0/15
2/20
6/9
14/19
7/9
14/19
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.15
0.145
0.2
ND
ND
0.2
0.2
0.3
0.6
0.7
0.8
0.5
0.4
0.2
1.1
0.6
1.7
3.4
3/15
1/20
1/15
2/20
6/13
8/20
11/15
19/20
A-98
-------
Table A.12 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Does your waste water collection system include
combined sanitary and storm water sewers?"
(All concentration are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.03
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.09
0.05
ND
ND
ND
ND
ND
ND
ND-0.6
1
0.5
0.1
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.3
ND
ND
0.23
0.1
ND
ND
ND
ND
ND
ND
60
30
1
1
ND
ND
ND
ND
0.17
ND
0.038
3.46
0.8
35
ND
ND
0.27
0.37
ND
ND
ND
ND
ND
ND
60
300
1
6
0.06
ND
0/15
0/20
1/15
0/20
1/15
1/20
1/15
4/20
0/15
0/20
15/15
19/20
0/15
0/20
0/15
0/20
0/15
0/20
5/10
15/20
8/10
16/20
1/15
0/20
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-99
-------
Table A.13 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Do you receive sludge from other wastewater treatment facilities for
processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.09
0.09
ND
ND
0.18
0.39
0.19
0.18
0.25
0.3
ND
ND
ND
ND
0.29
0.33
2
2
0.22
0.4
0.5
0.75
2.1
1.9
1.25
1.4
1.5
2.4
7
7
3
4.7
1.5
3
10.1
13
0.8
1.2
5
6.7
15.4
20
12
12
6
16
17
27
4.3
13
5.8
17
26
47
1.6
1.7
12
23
17
44
12.5
26
59/75
1 79/236
15/75
65/236
29/75
1 06/236
61/75
1 92/236
70/75
219/236
24/24
68/68
43/75
148/236
24/24
68/68
24/24
68/68
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
0.3
0.35
1
1
2
5
2
3
6
8
15/34
48/124
26/34
85/124
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.38
0.475
ND
ND
0.8
1.4
1.2
2
0.6
1
3.7
13
4.2
15
5
12
23/75
78/236
74/75
229/236
11/75
36/236
A-100
-------
Table A.13 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Do you receive sludge from other wastewater treatment facilities for
processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Ra-228
Th-228
Th-232
TI-208
Response
Yes
No
Yes
No
Yes
No
Yes
No
Min
ND
ND
0.16
0.07
0.06
0.02
ND
ND
Median
0.7
0.9
0.39
0.685
0.17
0.205
0.07
0.07
95th P
4
6.7
3.1
4.6
0.5
0.65
0.8
0.99
Max
38
24
9
9
1.1
1.6
1.9
4.8
No. Detects/
No. Analyses
68/75
203/236
24/24
68/68
24/24
68/68
47/75
1 33/236
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
3.8
1.35
ND
ND
0.6
ND
ND
ND
ND
ND
60.5
44
0.033
0.04
43
48
0.7
0.45
0.9
40
220
840
1.19
3.6
80
241
0.93
1.16
2/75
9/236
65/75
181/236
6/75
13/236
43/75
1 08/236
24/75
49/236
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
Yes
No
Yes
No
Yes
No
ND
ND
0.3
ND
ND
ND
1.1
1.2
3.8
4
ND
ND
9.1
8.6
10.5
13
ND
ND
13.5
22
22
26
ND
0.07
65/75
1 98/236
75/75
233/236
0/75
1/236
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.01
0.01
0.0025
0.004
ND
ND
0.04
0.1
0.04
0.05
2.5
0.3
0.05
0.19
0.1
0.12
4/75
6/236
19/24
56/68
20/24
48/68
A-101
-------
Table A.13 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Do you receive sludge from other wastewater treatment facilities for
processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.1
0.09
0.58
0.42
ND
0.09
ND
ND
0.5
0.5
1.3
3.1
0/75
2/236
0/75
0/236
14/48
35/1 59
27/75
85/236
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.2
0.4
0.1
0.1
ND
ND
ND
ND
ND
ND
0.03
ND
ND
ND
ND
ND
0.11
0.11
ND
ND
ND
ND
ND
ND
10
20
0.3
1
ND
ND
ND
0.016
0.26
0.06
1.16
5.1
0.3
3.5
0.04
ND
3.6
1.5
ND
21
ND
0.4
ND
27
40
70
0.4
9.4
0.06
ND
0/75
1/236
1/75
5/236
5/75
8/236
1/75
5/236
1/75
0/236
34/75
99/236
0/75
1/236
0/75
1/236
0/75
1/236
15/23
53/75
17/23
47/75
1/75
0/236
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-102
-------
Table A.14 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you receive sludge from other w a stew ate r treatment facilities for
processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
0.62
ND
ND
ND
ND
ND
0.61
0.69
ND
0
0.3
ND
ND
ND
1.5
1.2
1.4
0.8
2.7
2.25
4
3
ND
2.2
3
2.55
2.9
3.2
0.95
0.64
3.8
2.15
6.35
3.9
4.05
2.65
14
13.7
9
11
6.4
8.9
14.6
14.8
18
17
2.2
1.5
10
11
12
49
6.4
35
14.1
16
11
77
8.5
12.3
15.1
16.4
22
18
2.6
2.3
21
80
13
91
9
74
21/21
13/14
18/21
12/14
7/21
9/14
21/21
14/14
19/21
14/14
14/14
13/14
19/21
12/14
14/14
14/14
14/14
14/14
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
1
1
8
4
1
1
8
4
3/9
2/9
3/9
4/9
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
0.74
0.36
ND
ND
0.68
0.65
0.9
ND
0.4
ND
ND
0.11
0.9
1.5
1.42
1.85
0.4
ND
2.4
3.35
1.7
1.3
0.7
0.475
0.47
1.105
1.8
3.5
2.5
3.3
1.8
2
9.9
17
3.4
3.7
0.9
0.9
2
3.1
5.5
15.7
6.6
15
4.9
2.4
24
30
6.7
14
1
1.7
2
13.5
14/21
11/14
21/21
14/14
11/21
4/14
21/21
14/14
14/14
13/14
14/14
13/14
18/21
14/14
A-103
-------
Table A.14 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you receive sludge from other w a stew ate r treatment facilities for
processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.13
0.305
ND
ND
ND
5.05
ND
ND
ND
0.8
4.3
20
ND
ND
48
73
0.1
1.1
0.3
1
46
81
ND
ND
105
93
0.99
1.53
1/21
3/14
12/21
11/14
0/21
0/14
8/21
11/14
3/21
4/14
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
Yes
No
Yes
No
Yes
No
ND
0.14
8.4
7.4
ND
ND
4.3
4.3
15
13.6
ND
ND
27
8.1
22
17.9
ND
ND
30
8.3
22.4
19.8
ND
ND
20/21
14/14
21/21
14/14
0/21
0/14
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.02
0
0.015
0
ND
0.04
0.08
0.09
0.04
0.05
ND
0.21
0.1
0.1
0.06
0.17
0/21
2/14
12/14
8/14
12/14
9/14
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
0.03
ND
ND
ND
ND
ND
ND
0.15
0.145
0.1
0.5
ND
0.2
0.2
0.3
0.5
1.7
0.2
0.8
ND
0.4
0.6
1.1
0.6
3.4
2/21
2/14
0/21
3/14
9/19
5/14
16/21
14/14
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.17
ND
0/21
0/14
1/21
0/14
A-104
-------
Table A.14 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you receive sludge from other w a stew ate r treatment facilities for
processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1pCi/g=37 Bq/kg.)
Radionuclide
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Min
ND
ND
ND
ND
ND
ND
0.03
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
0.08
0.06
ND
ND
ND
ND
ND
ND
0.3
1.65
0.5
0
ND
ND
95th P
ND
ND
0.3
0.3
ND
ND
0.23
0.18
ND
ND
ND
ND
ND
ND
20
30
1
1
ND
ND
Max
0.038
3.46
0.8
35
ND
ND
0.27
0.37
ND
ND
ND
ND
ND
ND
300
60
6
1
0.06
ND
No. Detects/
No. Analyses
1/21
1/14
3/21
2/14
0/21
0/14
21/21
13/14
0/21
0/14
0/21
0/14
0/21
0/14
9/16
11/14
14/16
10/14
1/21
0/14
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-105
-------
Table A.15 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Do you receive septage for processing at your facility?
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g= 37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
1.8
0.09
0.09
0.19
ND
ND
ND
0.18
0.4
0.8
0.18
0.37
0.7
0.27
0.305
0.335
ND
ND
2
ND
ND
ND
0.3
0.35
0.32
2
2.1
2.85
0.31
0.36
0.54
0.5
0.75
1.45
2.1
1.6
1.6
1.4
1.4
1.4
2
3
1.37
6
7
11
4
4.2
1
2.4
3.1
1.42
10.4
17
10.1
0.8
1.2
1
5.7
5
12
17
25
15.4
9
12
12.5
16
16
1.37
22
27
11
12
13
1
17
17
1.42
47
30
10.1
1.6
1.7
1
19
23
12
20
44
15.4
16
26
12.5
137/177
92/124
9/10
46/177
28/124
6/10
84/177
50/124
1/10
146/177
98/124
9/10
166/177
113/124
10/10
48/48
35/35
9/9
107/177
76/124
8/10
48/48
35/35
9/9
48/48
35/35
9/9
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
0.6
0.3
0.5
1
1
1
1
5
4
1.7
3
2
1
7
8
1.7
42/94
16/59
5/5
66/94
41/59
4/5
A-106
-------
Table A.15 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Do you receive septage for processing at your facility?
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g= 37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
0.15
ND
ND
ND
ND
ND
0.6
0.07
0.2
0.2
0.02
0.06
0.1
ND
ND
ND
ND
ND
ND-0.5
0.48
0.4
0.615
ND
ND
ND
0.8
0.9
1
0.605
0.7
0.49
0.23
0.16
0.4
0.06
0.07
ND-0.11
1
2
0.8
1.9
1.9
1.55
1
0.7
0.7
5.1
7.8
1.9
3.1
4.6
1.4
0.65
0.52
0.9
0.96
1.1
0.26
13
6.8
0.8
15
5.4
1.55
12
3
0.7
38
24
1.9
9
6.8
1.4
1.1
1.6
0.9
4.1
4.8
0.26
52/177
44/124
5/10
174/177
119/124
10/10
28/177
16/124
3/10
155/177
106/124
10/10
48/48
35/35
9/9
48/48
35/35
9/9
100/177
75/124
5/10
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2.6
1.29
0.425
ND
ND
ND
0.45
ND
ND
ND
ND
ND
ND
73
42
39
0.03
0.09
ND
43
56
24
0.32
5.9
40
ND
280
840
39
1.9
3.6
ND
176
241
24
0.93
9/177
2/124
0/10
146/177
93/124
7/10
10/177
9/124
0/10
93/177
55/124
3/10
41/177
A-107
-------
Table A.15 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Do you receive septage for processing at your facility?
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g= 37 Bq/kg.)
Radionuclide
Response
No
NR
Min
ND
ND
Median
ND
ND
95th P
0.56
ND
Max
1.16
ND
No. Detects/
No. Analyses
32/124
0/10
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
2.5
ND
ND
ND
1.2
1.1
1.15
4
3.9
4.05
ND
ND
ND
8.7
8.6
22
13
10
7.3
ND
ND
ND
15.3
17
22
26
16
7.3
ND
0.07
ND
155/177
100/124
8/10
176/177
122/124
10/10
0/177
1/124
0/10
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
ND
ND
0.01
0.01
0.01
0.002
0.004
0.01
ND
ND
ND
0.07
0.03
0.14
0.04
0.04
0.07
2.5
0.14
ND
0.19
0.1
0.14
0.11
0.12
0.07
8/177
2/124
0/10
39/48
28/35
8/9
37/48
22/35
9/9
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND-0.01
ND
ND
0.16
ND
ND
ND
ND
ND
ND
0.09
0.1
0.1
0.41
0.5
0.6
0.09
ND
ND
ND
ND
ND
0.5
0.2
0.1
1.3
3.1
0.6
2/177
0/124
0/10
0/177
0/124
0/10
22/116
22/81
5/10
60/177
43/124
9/10
A-108
-------
Table A.15 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question:
Do you receive septage for processing at your facility?
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g= 37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.02
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.4
0.15
0.3
0.04
0.1
0.1
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.1
0.12
0.19
ND
ND
ND
ND
ND
ND
ND
ND
ND
6
30
10
1
0.6
0.4
ND
ND
ND
ND
0.016
ND
0.26
0.06
ND
1.16
5.1
ND
3.5
2.8
ND
0.04
ND
ND
3.6
1.5
0.19
ND
21
ND
ND
0.4
ND
27
ND
ND
40
70
10
9
9.4
0.4
0.06
ND
ND
0/177
1/124
0/10
2/177
4/124
0/10
8/177
5/124
0/10
3/177
3/124
0/10
1/177
0/124
0/10
76/177
51/124
6/10
0/177
1/124
0/10
0/177
1/124
0/10
1/177
0/124
0/10
37/51
24/38
7/9
30/51
28/38
6/9
1/177
0/124
0/10
** Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-109
-------
A-110
-------
Table A.16 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you receive septage for processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
0.62
ND
2.1
ND
ND
ND
ND
1.9
ND
0.61
0.92
2.2
ND
1
2.9
0.3
ND
0.55
ND
1.1
ND
1.3
1.2
5
0.8
1.1
3.3
2.4
1.9
6.5
4
3
3
ND
3.5
ND
2.9
2.05
7.25
2.5
2.95
13.05
0.85
0.605
0.85
3.6
2.15
3.95
4.1
5.55
6.55
3.55
2.95
3.55
13.7
16
14
11
77
6
8.5
8.9
ND
14.8
16.4
14.6
18
15
18
1.5
2.3
2.2
11
80
5.1
19
91
7.6
15
74
4.7
14.1
16
14
11
77
6
12.3
8.9
ND
15.1
16.4
14.6
22
15
18
2.6
2.3
2.2
21
80
5.1
49
91
7.6
35
74
4.7
25/25
5/6
4/4
22/25
5/6
3/4
10/25
6/6
0/4
25/25
6/6
4/4
23/25
6/6
4/4
18/18
5/6
4/4
22/25
6/6
3/4
18/18
6/6
4/4
18/18
6/6
4/4
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND-0
ND
ND-0. 5
ND
1
1
0
8
4
ND
1
1
0
8
4
ND
2/10
2/6
1/2
4/10
3/6
0/2
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Yes
No
NR
ND
ND
ND
1.3
1.6
ND
3.5
15.7
0.8
5.5
15.7
0.8
20/25
4/6
1/4
A-110
-------
Table A.16 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you receive septage for processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Response
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Min
0.36
0.73
0.91
ND
ND
ND
0.65
1.8
1.6
0.4
ND
0.9
0.22
ND
0.48
0.11
0.63
ND
Median
1.5
1.7
1.21
0.4
ND
ND
2.4
2.95
4.8
1.7
0.9
1.4
0.75
0.46
0.6
0.66
1.5
ND
95th P
3.3
15
1.6
2.4
ND
0.5
17
30
8.2
3.7
14
2.4
0.9
0.51
1
2.3
13.5
0.29
Max
6.6
15
1.6
4.9
ND
0.5
24
30
8.2
6.7
14
2.4
1.7
0.51
1
3.1
13.5
0.29
No. Detects/
No. Analyses
25/25
6/6
4/4
14/25
0/6
1/4
25/25
6/6
4/4
18/18
5/6
4/4
18/18
5/6
4/4
25/25
6/6
1/4
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.62
ND
ND
ND
ND
ND
ND-0.4
ND
0.22
0.185
2.185
ND
ND
ND
0.36
7.85
ND
ND
ND
ND
ND
1
0.3
46
1.2
4.3
ND
ND
ND
93
61
ND
1.1
ND
ND
ND
1
0.3
81
1.2
4.3
ND
ND
ND
105
61
ND
1.53
ND
ND
0/25
3/6
1/4
15/25
5/6
3/4
0/25
0/6
0/4
13/25
6/6
0/4
7/25
0/6
0/4
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
Yes
No
NR
ND
2.3
4.2
3.6
5.2
4.8
27
7.6
13
30
7.6
13
24/25
6/6
4/4
A-111
-------
Table A.16 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you receive septage for processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
K-40
La-138
Response
Yes
No
NR
Yes
No
NR
Min
7.4
7.9
14
ND
ND
ND
Median
14.1
14.95
14.6
ND
ND
ND
95th P
22
19.8
15
ND
ND
ND
Max
22.4
19.8
15
ND
ND
ND
No. Detects/
No. Analyses
25/25
6/6
4/4
0/25
0/6
0/4
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
0.01
ND
ND
0.00
ND
ND
ND
0.015
ND-0
0.05
0.01
ND-0
0.03
ND
0.21
ND
0.06
0.1
0.1
0.06
0.01
0.04
ND
0.21
ND
0.09
0.1
0.1
0.17
0.01
0.04
0/25
2/6
0/4
13/18
3/6
4/4
14/18
3/6
4/4
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
0.14
ND
ND
ND
ND
ND
ND
0.04
ND
ND
0.11
0.145
0.18
0.5
ND
ND
0.2
ND
ND
0.6
ND
0.2
0.7
3.4
0.4
0.8
ND
ND
0.4
ND
ND
1.1
ND
0.2
1.7
3.4
0.4
4/25
0/6
0/4
3/25
0/6
0/4
13/23
0/6
1/4
20/25
6/6
4/4
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Yes
No
NR
Yes
No
NR
Yes
No
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.038
ND
ND
ND
ND
ND
0.17
ND
ND
3.46
ND
ND
0/25
0/6
0/4
1/25
0/6
0/4
2/25
0/6
0/4
A-112
-------
Table A.16 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you receive septage for processing at your facility?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Yes
No
NR
Min
ND
ND
ND
ND
ND
ND
ND
0
0.04
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
0.08
0.06
0.045
ND
ND
ND
ND
ND
ND
ND
ND
ND
1
ND-0
0.8
0.4
0
0.2
ND
ND
ND
95th P
0.8
ND
ND
ND
ND
ND
0.27
0.08
0.08
ND
ND
ND
ND
ND
ND
ND
ND
ND
60
5
3
1
1
0.3
ND
ND
ND
Max
35
ND
ND
ND
ND
ND
0.37
0.08
0.08
ND
ND
ND
ND
ND
ND
ND
ND
ND
300
5
3
6
1
0.3
0.06
ND
ND
No. Detects/
No. Analyses
5/25
0/6
0/4
0/25
0/6
0/4
24/25
6/6
4/4
0/25
0/6
0/4
0/25
0/6
0/4
0/25
0/6
0/4
13/20
3/6
4/4
16/20
5/6
3/4
1/25
0/6
0/4
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-113
-------
Table A.17 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question,
"What percentage of the annual average daily total flow rate is industrial flow?"
(All concentrations are expressed in pCi/g dry, unless noted;1 pCi/g=37 Bq/kg)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.09
0.32
0.12
ND
ND
ND
0.18
0.9
0.43
0.18
0.7
0.37
0.295
0.36
0.22
ND
ND
ND
ND
ND
0.2
0.305
0.4
0.245
2
1
1.55
0.355
0.8
0.21
0.8
ND
0.65
1.95
1
3.1
1.4
0.9
2.2
2.9
0.56
2
8
3
ND
4.2
0.7
3.4
3
0.61
2.1
14
3
4.6
1
1.2
0.24
7
0.8
4.9
17
2.3
5.1
12
2.1
3.7
16
0.75
2.3
27
4
3
13
4
6
17
0.8
2.4
47
4.3
5
1.7
1.2
0.24
23
2
5
44
2.3
5.1
26
2.1
3.7
218/284
12/15
8/12
75/284
4/15
1/12
123/284
5/15
7/12
232/284
12/15
9/12
265/284
14/15
10/12
86/86
3/3
3/3
179/284
4/15
8/12
86/86
3/3
3/3
86/86
3/3
3/3
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
ND
ND
ND
0
ND
0.3
0.5
0.15
1
1
0
5
0.7
3
3
1
0
8
0.7
3
58/145
3/5
2/8
102/145
4/5
5/8
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Less than 50%
50% or More
NR
ND
ND
ND
ND
0.3
ND
1.4
0.8
1
13
0.9
3.3
90/284
8/15
3/12
A-114
-------
Table A.17 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question,
"What percentage of the annual average daily total flow rate is industrial flow?"
(All concentrations are expressed in pCi/g dry, unless noted;1 pCi/g=37 Bq/kg)
Radionuclide
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Response
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Min
ND
0.03
0.03
ND
ND
ND
ND
ND
ND
0.07
0.16
0.38
0.02
0.1
0.08
ND
ND
ND
Median
0.435
0.4
0.515
ND
ND
ND
0.9
0.56
0.64
0.655
0.5
0.38
0.2
0.35
0.21
0.07
0.08
ND
95th P
1.9
0.67
1.1
1
0.6
ND
6.7
1
1.7
4.6
0.7
0.5
0.65
0.52
0.28
0.99
0.28
0.46
Max
15
0.82
3.3
12
0.7
1
38
1.02
3.5
9
0.7
0.5
1.6
0.52
0.28
4.8
0.6
3.1
No. Detects/
No. Analyses
276/284
15/15
12/12
41/284
5/15
1/12
251/284
11/15
9/12
86/86
3/3
3/3
86/86
3/3
3/3
164/284
11/15
5/12
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
2.2
0.03
1.45
ND
ND
ND
0.375
ND
ND
ND
ND
ND
ND
ND
ND
60.5
0.8
10.3
0.04
ND
ND
48
0.3
3.5
0.54
0.09
ND
40
1.1
0.5
840
3.6
98
3.6
ND
1.19
241
34
71
1.16
0.49
0.88
9/284
1/15
1/12
229/284
8/15
9/12
1 8/284
0/15
1/12
145/284
2/15
4/12
69/284
3/15
1/12
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
Less than 50%
50% or More
NR
ND
ND
ND
1.3
0.5
1
8.7
2.5
9.1
22
10.7
9.9
244/284
10/15
9/12
A-115
-------
Table A.17 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question,
"What percentage of the annual average daily total flow rate is industrial flow?"
(All concentrations are expressed in pCi/g dry, unless noted;1 pCi/g=37 Bq/kg)
Radionuclide
K-40
La-138
Response
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Min
ND
0.8
0.3
ND
ND
ND
Median
4
2.8
4
ND
ND
ND
95th P
13
5.8
8
ND
ND
ND
Max
26
8
9
ND
0.07
ND
No. Detects/
No. Analyses
281/284
15/15
12/12
0/284
1/15
0/12
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
0
0.00
ND
ND
0.00
ND
ND
ND
0.01
0
0.006
0.0035
ND
0.003
ND
ND
ND
0.07
0.01
0.01
0.05
0.001
0.01
2.5
ND
ND
0.19
0.01
0.01
0.12
0.001
0.01
1 0/284
0/15
0/12
69/86
3/3
3/3
64/86
1/3
3/3
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.1
0.07
0.05
0.5
0.18
0.15
0.09
ND
ND
ND
ND
ND
0.5
0.07
0.05
3.1
0.26
0.2
2/284
0/15
0/12
0/284
0/15
0/12
46/191
2/7
1/9
104/284
5/15
3/12
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Co-60
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.016
ND
ND
0.26
ND
ND
5.1
ND
ND
1/284
0/15
0/12
6/284
0/15
0/12
1 3/284
0/15
0/12
A-116
-------
Table A.17 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question,
"What percentage of the annual average daily total flow rate is industrial flow?"
(All concentrations are expressed in pCi/g dry, unless noted;1 pCi/g=37 Bq/kg)
Radionuclide
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
20
ND
0.2
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
0.011
ND-0.01
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.35
ND
20
0.1
0.2
ND
ND
ND
ND
95th P
ND
ND
ND
ND
ND
ND
0.11
0.07
0.05
ND
ND
ND
ND
ND
ND
ND
ND
ND
20
3
20
0.7
1
ND
ND
ND
ND
Max
3.5
ND
ND
0.04
ND
ND
3.6
0.11
0.12
21
ND
ND
0.4
ND
ND
27
ND
ND
70
3
20
9.4
1
ND
ND
0.06
ND
No. Detects/
No. Analyses
6/284
0/15
0/12
1/284
0/15
0/12
1 1 8/284
9/15
6/12
1/284
0/15
0/12
1/284
0/15
0/12
1/284
0/15
0/12
66/94
1/3
1/1
61/94
3/3
0/1
0/284
1/15
0/12
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-117
-------
Table A.18 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What percentage of the annual average daily total flow rate is industrial flow?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g= 37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Uranium-238 Decay Series
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
0.62
1.6
ND
ND
5
ND
2.9
ND
0.69
0.61
1.7
ND
1.1
1.9
0.3
ND
0.7
ND
1
4.7
1.2
7.1
9
0.8
6.1
6.4
2.55
2.01
1.7
3
ND-7
5
ND
3.65
4.1
2.95
2.205
1.9
3.4
2.05
2
0.85
ND
0.7
3.15
3.25
5.1
5.2
7.1
9
3.2
6.1
6.4
14.1
3.4
3
11
7
5
8.9
4.4
5
15.1
3.8
3.2
18
3
5.5
2.3
ND
0.7
21
5.5
7.2
49
7.1
9
35
6.1
6.4
16
3.4
3
77
7
5
12.3
4.4
5
16.4
3.8
3.2
22
3
5.5
2.6
ND
0.7
80
5.5
7.2
91
7.1
9
74
6.1
6.4
29/30
2/2
3/3
26/30
1/2
3/3
12/30
2/2
2/3
30/30
2/2
3/3
28/30
2/2
3/3
26/26
0/1
1/1
26/30
2/2
3/3
26/26
1/1
1/1
26/26
1/1
1/1
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
0
ND
ND
ND
3
ND
0
ND-1
ND
ND
5.5
0
0
1
2
ND
8
1
0
1
4
ND
8
2/14
2/2
1/2
5/14
0/2
2/2
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Less than 50%
50% or More
NR
ND
ND
1.2
1.05
ND-1. 8
1.6
5.5
1.8
1.8
15.7
1.8
1.8
21/30
1/2
3/3
A-118
-------
Table A.18 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What percentage of the annual average daily total flow rate is industrial flow?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g= 37 Bq/kg.)
Radionuclide
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Response
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Min
0.36
0.85
1.3
ND
ND
ND
0.65
0.68
2.2
0.4
ND
1.7
0.22
ND
0.8
ND
0.75
0.4
Median
1.5
1.375
1.5
ND
ND
ND
2.8
1.24
2.4
1.6
ND
1.7
0.505
ND
0.8
0.62
1.205
1.36
95th P
6.6
1.9
1.7
2.4
ND
0.5
24
1.8
3.4
6.7
ND
1.7
1
ND
0.8
3.1
1.66
1.48
Max
15
1.9
1.7
4.9
ND
0.5
30
1.8
3.4
14
ND
1.7
1.7
ND
0.8
13.5
1.66
1.48
No. Detects/
No. Analyses
30/30
2/2
3/3
14/30
0/2
1/3
30/30
2/2
3/3
26/26
0/1
1/1
26/26
0/1
1/1
27/30
2/2
3/3
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
0.24
ND
ND
ND
ND
ND
12.4
ND
ND
ND
ND
ND
ND
ND
0.22
0.705
ND
ND
ND
ND
0.795
30.2
ND
ND
ND
ND
0.8
ND
ND
46
1.17
ND
ND
ND
ND
93
48
ND
1.1
ND
ND
1
ND
ND
81
1.17
ND
ND
ND
ND
105
48
ND
1.53
ND
ND
4/30
0/2
0/3
21/30
2/2
0/3
0/30
0/2
0/3
17/30
2/2
0/3
7/30
0/2
0/3
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
Less than 50%
50% or More
NR
ND
7.5
0.8
4.3
11.45
0.8
27
15.4
1.2
30
15.4
1.2
29/30
2/2
3/3
A-119
-------
Table A.18 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What percentage of the annual average daily total flow rate is industrial flow?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g= 37 Bq/kg.)
Radionuclide
K-40
La-138
Response
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Min
7.4
14.1
17.4
ND
ND
ND
Median
13.85
15.15
19.3
ND
ND
ND
95th P
20.9
16.2
22
ND
ND
ND
Max
22.4
16.2
22
ND
ND
ND
No. Detects/
No. Analyses
30/30
2/2
3/3
0/30
0/2
0/3
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
ND
0.05
ND
ND
0.02
ND
ND
ND
0.015
ND
0.05
0.01
ND
0.02
0.04
ND
ND
0.1
ND
0.05
0.06
ND
0.02
0.21
ND
ND
0.1
ND
0.05
0.17
ND
0.02
2/30
0/2
0/3
19/26
0/1
1/1
20/26
0/1
1/1
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.15
ND-
0.31
ND
0.5
ND
ND
0.2
ND
ND
0.6
ND
0.1
1.7
0.31
0.3
0.8
ND
ND
0.4
ND
ND
1.1
ND
0.1
3.4
0.31
0.3
4/30
0/2
0/3
3/30
0/2
0/3
13/28
0/2
1/3
28/30
1/2
1/3
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.17
ND
ND
0/30
0/2
0/3
1/30
0/2
0/3
A-120
-------
Table A.18 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"What percentage of the annual average daily total flow rate is industrial flow?"
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g= 37 Bq/kg.)
Radionuclide
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Less than 50%
50% or More
NR
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
0.06
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.1
1
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.07
0.085
0.09
ND
ND
ND
ND
ND
ND
ND
ND
ND
1
ND-2
ND
0.1
0.55
1
ND
ND
ND
95th P
0.038
ND
ND
0.8
ND
0.2
ND
ND
ND
0.27
0.1
0.09
ND
ND
ND
ND
ND
ND
ND
ND
ND
60
2
ND
1
1
1
ND
ND
ND
Max
3.46
ND
ND
35
ND
0.2
ND
ND
ND
0.37
0.1
0.09
ND
ND
ND
ND
ND
ND
ND
ND
ND
300
2
ND
6
1
1
0.06
ND
ND
No. Detects/
No. Analyses
2/30
0/2
0/3
4/30
0/2
1/3
0/30
0/2
0/3
29/30
2/2
3/3
0/30
0/2
0/3
0/30
0/2
0/3
0/30
0/2
0/3
19/26
1/2
0/2
20/26
2/2
2/2
1/30
0/2
0/3
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-121
-------
Table A.19 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Do you have more than one final sewage sludge production facility location?"
(All concentrations are expressed in pCi/g dry, unless notes; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Radionuclide Group: Uranium-238 Deca^
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.17
0.09
ND
ND
0.5
0.18
0.5
0.18
Median
95th P
Max
No. Detects/
No. Analyses
i Series
0.21
0.3
ND
ND
ND
ND
0.225
0.31
2
2
0.305
0.34
0.5
0.7
1.45
2
1.05
1.4
2
2.3
4
8
2.2
4
2.1
2.6
10.6
13
0.5
1.2
3.1
6.8
2.5
17
2
12
6
16
5
27
12
13
4
17
19
47
0.5
1.7
19
23
2.5
44
2
26
24/32
214/279
6/32
74/279
12/32
123/279
26/32
227/279
31/32
258/279
6/6
86/86
19/32
172/279
6/6
86/86
6/6
86/86
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
0.1
0.35
2
1
1
5
3
2
2
8
6/14
57/144
10/14
101/144
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.19
0.07
0.07
0.02
ND
ND
ND
ND
0.365
0.47
ND
ND
0.79
0.84
0.645
0.605
0.15
0.2
0.055
0.08
0.9
1.4
1.1
2
0.5
0.9
3
6.7
1.6
4.6
0.31
0.65
0.36
0.99
2
13
1.9
15
1
12
6
38
1.6
9
0.31
1.6
1.1
4.8
10/32
91/279
31/32
272/279
3/32
44/279
28/32
243/279
6/6
86/86
6/6
86/86
18/32
162/279
A-122
-------
Table A.19 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Do you have more than one final sewage sludge production facility location?"
(All concentrations are expressed in pCi/g dry, unless notes; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
3.25
1.5
ND
ND
0.595
ND
ND
ND
ND
ND
82
44
0.18
ND
40
48
0.4
0.54
5.9
40
153
840
3.6
3.5
80
241
0.92
1.16
1/32
1 0/279
27/32
219/279
6/32
1 3/279
18/32
133/279
10/32
63/279
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
Yes
No
Yes
No
Yes
No
ND
ND
1.4
ND
ND
ND
1.45
1.1
3.6
4
ND
ND
4
9.1
8.3
12
ND
ND
9.9
22
25
26
ND
0.07
27/32
236/279
32/32
276/279
0/32
1/279
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.01
0.01
0.0035
0.003
ND
ND
0.04
0.07
0.12
0.04
2.5
0.14
0.04
0.19
0.12
0.11
2/32
8/279
5/6
70/86
5/6
63/86
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.04
0.1
0.13
0.5
ND
0.09
ND
ND
0.05
0.5
0.3
3.1
0/32
2/279
0/32
0/279
3/17
46/190
9/32
103/279
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.016
0.26
0.06
0/32
1/279
1/32
5/279
A-123
-------
Table A.19 Concentrations of Radionuclides in Sludge
Summarized by Response to the POTW Questionnaire Question
"Do you have more than one final sewage sludge production facility location?"
(All concentrations are expressed in pCi/g dry, unless notes; 1 pCi/g=37 Bq/kg.)
Radionuclide
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Min
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
ND
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
5
0.3
ND
0.1
ND
ND
95th P
ND
ND
ND
ND
ND
ND
0.06
0.11
ND
ND
ND
ND
ND
ND
40
20
0.2
1
ND
ND
Max
0.07
5.1
ND
3.5
ND
0.04
0.11
3.6
ND
21
ND
0.4
ND
27
40
70
0.2
9.4
ND
0.06
No. Detects/
No. Analyses
1/32
12/279
0/32
6/279
0/32
1/279
7/32
126/279
0/32
1/279
0/32
1/279
0/32
1/279
7/7
61/91
2/7
62/91
0/32
1/279
* Indicates concentrations for this radionuclide are expressed in pCi/q wet.
A-124
-------
Table A.20 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you have more than one final sewage sludge production facility location?
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Radionuclide Group: Uranium-238 Deca^
Bi-214
Pa-234m
Pb-210
Pb-214
Ra-226
Th-230
Th-234
U-234
U-238
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
1.4
ND
ND
ND
ND
ND
1.6
0.61
ND
ND
0.7
ND
1.7
ND
2.1
1.2
1.9
0.8
Median
95th P
Max
No. Detects/
No. Analyses
i Series
3.25
2.2
5
3
ND
ND
3.6
2.4
5.5
3
1.1
0.7
3.7
3.6
4.9
5.55
4
3.3
14.1
13.7
9
11
5
8.5
15.1
14.6
22
17
2.6
2.2
7.5
11
7
49
6.2
35
14.1
16
9
77
5
12.3
15.1
16.4
22
18
2.6
2.3
7.5
80
7
91
6.2
74
4/4
30/31
3/4
27/31
1/4
15/31
4/4
31/31
3/4
30/31
4/4
23/24
4/4
27/31
4/4
24/24
4/4
24/24
Radionuclide Group: C-14 and H-3
C-14*
H-3*
Yes
No
Yes
No
ND
ND
1
ND
ND
ND
1
ND
ND
1
1
4
ND
1
1
8
0/1
5/17
1/1
6/17
Radionuclide Group: Thorium-232 Decay Series
Bi-212
Pb-212
Ra-224
Ra-228
Th-228
Th-232
TI-208
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
1.3
0.36
ND
ND
1.7
0.65
1.1
ND
0.5
ND
0.38
ND
1.3
1.2
1.5
1.5
1.1
ND
2.25
2.7
2
1.45
0.8
0.5
0.475
0.73
1.6
3.5
1.6
3.3
1.3
2
9.9
17
3.4
6.7
0.9
1
1.38
2.3
1.6
15.7
1.6
15
1.3
4.9
9.9
30
3.4
14
0.9
1.7
1.38
13.5
3/4
22/31
4/4
31/31
3/4
12/31
4/4
31/31
4/4
23/24
4/4
23/24
4/4
28/31
A-125
-------
Table A.20 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you have more than one final sewage sludge production facility location?
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Response
Min
Median
95th P
Max
No. Detects/
No. Analyses
Radionuclide Group: Medical Isotopes
1-125
1-131
ln-111
TI-201
TI-202
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND-0.05
0.22
ND
ND
ND
1
ND
ND
ND
0.4
0.39
20
ND
ND
0.36
73
0.1
0.99
ND
1
0.39
81
ND
ND
0.36
105
0.1
1.53
0/4
4/31
2/4
21/31
0/4
0/31
1/4
18/31
1/4
6/31
Radionuclide Group: NORM other than Thorium/Uranium
Be-7
K-40
La-138
Yes
No
Yes
No
Yes
No
0.5
ND
11
7.4
ND
ND
5.85
4.3
16.5
14.2
ND
ND
11.3
15.4
22.4
19.8
ND
ND
11.3
30
22.4
22
ND
ND
4/4
30/31
4/4
31/31
0/4
0/31
Radionuclide Group: Transuranics
Am-241
Pu-238
Pu-239
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
0.015
0.015
0.005
0.01
ND
ND
0.06
0.1
0.06
0.05
ND
0.21
0.06
0.1
0.06
0.17
0/4
2/31
3/4
17/24
3/4
18/24
Radionuclide Group: Actinium (U-235) Decay Series
Ra-223
Rn-219
Th-227
U-235
Yes
No
Yes
No
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
0.11
ND
ND
ND
ND
ND
0.135
ND
0.275
0.14
0.1
0.2
ND
0.2
0.2
0.6
0.6
0.7
0.1
0.8
ND
0.4
0.2
1.1
0.6
3.4
1/4
3/31
0/4
3/31
3/4
11/29
4/4
26/31
Radionuclide Group: Fission and Activation Products
Ce-141
Co-57
Yes
No
Yes
No
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
0.17
ND
ND
ND
0.17
ND
0/4
0/31
1/4
0/31
A-126
-------
Table A.20 Concentrations of Radionuclides in Ash
Summarized by Response to the POTW Questionnaire Question
"Do you have more than one final sewage sludge production facility location?
(All concentrations are expressed in pCi/g dry, unless noted; 1 pCi/g=37 Bq/kg.)
Radionuclide
Co-60
Cr-51
Cs-134
Cs-137
Eu-154
Fe-59
Sm-153
Sr-89
Sr-90
Zn-65
Response
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Yes
No
Min
ND
ND
ND
ND
ND
ND
0.06
ND
ND
ND
ND
ND
ND
ND
ND
ND
0
ND
ND
ND
Median
ND
ND
ND
ND
ND
ND
0.075
0.07
ND
ND
ND
ND
ND
ND
ND
1
0.95
0.1
ND
ND
95th P
ND
ND
0.3
0.3
ND
ND
0.11
0.23
ND
ND
ND
ND
ND
ND
300
30
6
1
ND
ND
Max
ND
3.46
0.3
35
ND
ND
0.11
0.37
ND
ND
ND
ND
ND
ND
300
60
6
1
ND
0.06
No. Detects/
No. Analyses
0/4
2/31
1/4
4/31
0/4
0/31
4/4
30/31
0/4
0/31
0/4
0/31
0/4
0/31
1/4
19/26
4/4
20/26
0/4
1/31
* Indicates concentrations for this radionuclide are expressed in pCi/g wet.
A-127
-------
APPENDIX B
OMB SUPPORTING STATEMENT
FOR
JOINT NRC/EPA SURVEY OF SEWAGE SLUDGE/ASH
-------
APPENDIX B
DECEMBER 2, 1997
OMB SUPPORTING STATEMENT
FOR
JOINT NRC/EPA SURVEY OF SEWAGE SLUDGE/ASH
Description of the Information Collection
The U.S. Nuclear Regulatory Commission and the U.S. Environmental Protection Agency (EPA)
are sponsoring a joint effort to characterize radioactive materials in sewage sludge and ash
from publicly owned treatment works (POTWs). Sanitary sewer disposal of radioactive material
and sludge reconcentration became issues in the 1980s with the discovery of elevated levels in
sewage sludge or incinerator ash at several POTWs. Although the NRC expected that
compliance with revisions in its sewer disposal criteria would prevent future reconcentration
problems, NRC and EPA have continued to work together to ensure a coordinated regulatory
review effort concerning sewage treatment with respect to radioactive material. EPA had
planned to include analysis of radioactivity in sewage sludge and incinerator ash in its second
National Sewage Sludge Survey during 1996-97. (The first national survey conducted in the
late 1980s did not include analysis of radioactive material.) Based on the current budget
situation, EPA did not move forward with a second national survey. As a result, NRC and EPA
will perform a joint survey of radioactivity in sewage sludge and ash at POTWs.
Because existing information is not adequate, NRC is requesting Office of Management and
Budget (OMB) approval to conduct the survey to obtain this information. The survey will sample
radioactive materials in sewage sludge and ash at POTWs in all regions of the country. For the
planned NRC/EPA survey, we will send questionnaires to the POTWs associated with types of
NRC licensees that have the highest potential to discharge radioactive material to the sewer
system and POTWs in all geographic areas of the United States. Using the information from
the questionnaires, NRC and EPA will identify approximately 300 POTWs to be sampled. NRC
and EPA tested the survey methods and procedures on nine POTWs. The results of the full
survey will be published as a joint NRC/EPA report for use by Federal agencies, States,
POTWs, local POTW officials, and other interested parties.
A. JUSTIFICATION
1. Need for and Practical Utility of the Collection of Information
The objectives of this joint NRC/EPA sewage sludge/incinerator ash survey are to
(1) obtain national estimates of high probability occurrences of elevated levels of
radioactive materials in sludge and ash at POTWs, (2) estimate the extent to which
radioactive contamination comes from either NRC/Agreement State licensees or
naturally occurring radioactivity, and (3) support rulemaking decisions by NRC and EPA.
Specific amounts and concentrations of radioactive material are legally authorized to be
disposed into the sanitary sewer system by Federal or State law. In 1994 NRC revised
its sewer disposal criteria partially in response to evidence that certain radioactive
B-1
-------
materials were reconcentrating in sewage sludge or incinerator ash. Regulations in
10 CFR 20.2003 currently permit disposal into a sanitary sewer of specific quantities of
soluble material. The EPA standard for the use and disposal of sewage sludge in
40 CFR Part 503 does not include radionuclides.
This survey also responds to a recommendation in the General Accounting Office
(GAO) report, "Actions Needed to Control Radioactive Contamination at Sewage
Treatment Plants," published in May 1994. That report recommended that NRC
determine the extent of elevated levels of radionuclides at POTWs and establish
acceptable limits for radioactive materials in sewage sludge and ash.
2. Agency Use of Information
This is a new collection of information.
The information could lead to additional NRC rulemaking for licensees disposing
material into sanitary sewer systems or to EPA rulemaking for the use or disposal of
sewage sludge. EPA will determine, based on the results of this survey, whether
additional random sampling will be necessary to support its own rulemaking, if
warranted.
This information will be used in developing joint NRC/EPA guidance for POTWs. This
guidance would provide information to help POTW operators determine sources of
radioactive materials at POTWs, describe sampling and analysis procedures, and
advise whether a response is needed to the presence of radioactive material in sludge.
POTWs, local sewer district officials, and EPA have requested this guidance.
3. Reduction of Burden through Information Technology
POTWs will respond to a short questionnaire and send sewage samples to an NRC or
EPA lab for analysis. There will not be an electronic collection of information because
the information will be collected on a one-time-basis. Two letters co-signed by NRC and
EPA will be mailed to each POTW - the first letter with the questionnaire and the second
with the sample collection package. The questionnaire is attached.
4. Effort to Identify Duplication and Use Similar Information
There is no similar information available. The only previous national sewage survey, the
1988-1989 National Sewage Sludge Survey, did not include analysis of radionuclides.
Recently, the Association of Metropolitan Sewerage Agencies (AMSA) conducted a
voluntary survey of radionuclide concentrations in some of its members' POTW sewage
sludge and ash. However, the AMSA survey did not identify the facilities tested, and
thus it is not possible to assess regional background levels of radionuclides or the
effects of licensees that dispose of radioactive material into sanitary sewers. (See
further discussion of the AMSA survey in Item 8.)
B-2
-------
5. Effort to Reduce Small Business Burden
This survey does not directly involve small entities. However, because the information
needs are the same for both large and small POTWs, it is not possible to reduce the
burden on small entities.
6. Consequences to Federal Program or Policy Activities if the Collection is Not
Conducted or is Conducted Less Frequently
If the collection is not conducted at all, NRC and EPA will not be responsive to the
recommendation in the GAO report to determine the extent of elevated levels of
radionuclides at POTWs. NRC and EPA will also not be able to obtain information
providing a basis for developing potential future rulemakings and quantitative guidance
for the proposed joint NRC/EPA guidance for POTWs. This is a one-time collection.
There are no technical or legal obstacles to conducting this data collection.
7. Circumstances Which Justify Variation from OMB Guidelines
There is no variation from OMB guidelines. The POTWs will have 30 days to respond.
8. Consultations Outside the NRC
In an October 11, 1994 letter, NRC and EPA notified the water and radiological officials
of all States of the potential for reconcentration of radioisotopes in sanitary sewer
systems. This letter mentioned the planned EPA national survey and the guidance
document.
On March 6, 1996, EPA and NRC staff were briefed by AMSA and the Water
Environment Federation (WEF) on the preliminary results of a voluntary (but
anonymous) AMSA survey of radionuclide concentrations in sewage sludge and ash at
POTWs (see also discussion in Item 4). To date, sewage sludge and ash samples from
55 wastewater plants in 17 states have been analyzed. These plants were distributed
across the country and range in size from small to among the largest POTWs in the
United States. Because of limitations in the AMSA survey, including the fact that the
POTWs were anonymous, the possibility of a more extensive NRC/EPA jointly funded
survey of sludge and ash to assess the need for NRC rulemaking was considered. The
industry representatives stated their continued interest in a joint NRC/EPA guidance
document addressing reconcentration of radioactive material at POTWs. NRC and EPA
have met with the WEF Radioactivity Task Force to discuss the status of the NRC/EPA
survey and the contents of the joint guidance. During the survey, NRC and EPA will
continue to meet with representatives of industry.
The sewage sludge/ash survey is being coordinated by a subcommittee of the
Interagency Steering Committee on Radiation Standards (ISCORS). ISCORS was
formed in 1995 to coordinate resolution of interagency issues. The ISCORS Sewage
Subcommittee is assisting NRC and EPA in the development of the survey, including
sample collection and analysis procedures and the selection of facilities to sample.
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The NRC contractor, the U.S. Department of Energy's Oak Ridge Institute for Science
and Education (ORISE), in Oak Ridge, Tennessee and EPA's National Air and Radiation
Environmental Laboratory (NAREL) in Montgomery, Alabama will analyze the sewage
sludge and ash samples. These labs have also provided input on the survey design.
For example, ORISE and NAREL collaborated to ensure that the analytical laboratory
procedures and quality assurance programs that both labs will use will produce
consistent, accurate, and reliable measurements.
An opportunity to comment on the information collection requirements in this survey was
provided in the January 6, 1997 Federal Register notice on this clearance request. NRC
received comments from five members of the public. The only change to the survey
that resulted from the public comments was that one question was added to the
questionnaire to determine if a previous analysis of radioactive materials was
performed. If there is a question about the survey results at a specific POTW and an
earlier analysis is available, we may compare the earlier analysis to the survey results.
There were no changes in the cost or hourly burden as a result of the public comments.
Some of the public comments did not address the survey, and therefore, their resolution
will have no impact on it. For example, some commenters asked the NRC to survey and
sample its licensees, not POTWs. Several commenters noted the nearly complete
absence of data in the NRC's possession regarding the licensees' discharges to the
sewers. Some commenters also asked what the NRC would do for POTWs if they are
found to have a contamination problem.
Some of the commenters objected to the survey. All the comments have been
analyzed, and an analysis of the comments is attached.
9. Payment or Gift to Respondents
The POTWs will not receive payments or gifts; however, they will receive the results of
the NRC/EPA analysis of sewage sludge and ash samples from their POTWs.
Assuming an average of two samples analyzed per POTW, the analysis for each POTW
is worth about two thousand dollars. The results will be provided to the POTWs in a
joint NRC/EPA report.
10. Confidentiality of the Information
Each POTW will be assigned a code number to ensure confidentiality. Only NRC
individuals with a need to know will be given access to the identity of a POTW if an NRC
or Agreement State licensee is likely responsible for elevated levels of radioactive
materials at a POTW and follow-up testing becomes desirable. At the conclusion of the
survey, an industry organization such as AMSA will receive the code book with the
identity of the POTW code numbers.
11. Justification for Sensitive Questions
There will be no survey questions of a sensitive nature.
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12. Estimated Burden and Burden Hour Cost
About 600 POTWs will be asked to complete the survey questionnaire. Because the
survey is voluntary (and thus not all POTWs will respond to the questionnaire),
additional POTWs may have to be surveyed to find enough appropriate facilities to be
sent sample collection packages. The estimated time to complete the questionnaire is
hour. For 600 POTWs, the estimated burden would be 600 hours.
The survey was tested at nine POTWs to assess the questionnaire and sampling and
analysis procedures. The test cases also gave a better basis for estimating the actual
burden cost. Most of the POTW test cases took 20 minutes or less to complete the
questionnaire; larger facilities required two hours to develop a list of zip codes for their
collection system. Our original estimate of the time needed to complete the
questionnaire was 2 hours; however, based on the results of the test cases, the revised
estimated time to complete the questionnaire is 1 hour. For 600 POTWs, the estimated
burden to respond to the questionnaire is 600 hours.
The questionnaire to the POTWs will ask for the zip codes for its collection system so
that we can identify the licensees associated with each POTW. NRC will request from
each Agreement State (depending on its information retrieval capabilities) (a) a list of
licensees by zip code or (2) the list of all licensees (so that NRC can determine the
licensees in the zip codes for the POTW collection systems). For 30 Agreement States
at 8 hours per State, the estimated burden would be 240 hours.
Based on the method discussed in Items B.1 and B.2, about 300 POTWs will be sent
sample collection packages. Each POTW will collect an average of two samples (one
for each disposal practice). The estimated time for each POTW to collect and return the
two samples is 6 hours. For 300 POTWs, the estimated burden is 1800 hours.
Total estimated burden = 600 + 240 + 1800 hours = 2640 hours
Estimated cost = 2640 hours x $120/hour = $316,800
13. Estimate of Other Additional Costs
There will be no additional cost burdens (beyond the cost of the hour burden discussed
above) to the POTWs. There is no need to purchase additional equipment or laboratory
support. For respondents to this survey, it is most likely that purchases of equipment
and services were made (1) prior to October 1, 1995, (2) to achieve regulatory
compliance with requirements not associated with the information collection, (3) for
reasons other than to provide information or keep records for the government, or (4) as
part of customary and usual business or private practices.
14. Estimated Cost to the Federal and State Governments
The cost to the Federal Government for this one-time-only survey includes costs for
contractor support for the radioanalytical analysis, NRC and EPA Headquarters staffs,
and Agreement State support.
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Cost for Radioanalytical Support
Radioanalytical support will be provided by NRC's contractor, ORISE and EPA's
NAREL. ORISE will assemble and distribute sample collection packages to about 300
POTWs. ORISE and NAREL will each analyze half the samples to determine the
activity of radionuclides. No purchase of computers, software, or monitoring or testing
equipment is needed. Monthly letter reports will be prepared containing the results of
the analysis.
Tasks
Assist NRC and EPA in development of the
survey, including test cases
Phone calls to POTWs, mailing sample
collection packages, and providing return
postage
Analyze samples
Report preparation
Sample disposition
Subtotal
ORISE Cost
50,000
25,500
146,400
16,100
0
238,000
EPA/NAREL Cost
12,000
0
110,550
9,750
5,000
137,300
Federal Government Cost
NRC Headquarters staff will coordinate the development of the survey and analyze the
survey results. NRC, EPA, ORISE, and NAREL staff will write and publish the results as
a joint NRC/EPA report. There will also be costs incurred by NRC and EPA for contract
management and general oversight of the work scope.
2 FTE x 2080 hours x $120/hour = $499,200
The cost for a statistical consultant to support the analysis is about $100,000.
Total estimated survey cost for the Federal government
Lab costs + Federal costs + statistical consultant =
$238,000 + $137,300 + $499,200 + $100,000 = $974,500
Agreement State Cost
See Item 12, Estimated Burden and Burden Hour Cost, above.
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15. Reasons for Changes in Burden or Cost
This is a new collection. There are no changes in burden or cost.
16. Publication for Statistical Use
NRC, EPA, ORISE, and NAREL will jointly write a report summarizing the survey results.
The database in the report will include, at a minimum, lists of radionuclide
concentrations for each POTW (coded to disguise the names of the facilities),
geographic region, and disposal practice.
The project is to be completed within two years of approval by OMB. Questionnaires will
be sent to the POTWs within two months of OMB approval, sample collection will take
place over a one-year period, from 6 to 18 months after OMB approval, and the final
report will be published two years after OMB approval.
17. Reason for Not Displaying the Expiration Date
Not applicable. The expiration date will be displayed.
18. Exceptions to the Certification Statement
There are no exceptions.
B. COLLECTIONS OF INFORMATION EMPLOYING STATISTICAL METHODS
The desire is to provide a national survey of high probability occurrences of elevated
levels of radioactive materials in sewage sludge and ash. Even though this is a
voluntary survey and may lack the number of samples needed to generate a
comprehensive national profile, the survey will sample POTWs in all regions of the
country and for a variety of NRC/Agreement State licensees. The collection of
information will employ statistical methods.
1. There are approximately 11,000 POTWs in the United States that use at least
secondary waste water treatment and are not simple pond treatment systems with only
periodic solids cleanout. For the 1980s national survey, EPA developed categories
based on flow rate and sewage sludge use and disposal practice. For the planned
NRC/EPA survey, questionnaires will be sent to (1) POTWs associated with types of
NRC licensees that have the highest potential to discharge radioactive material into the
sewer system, (2) many of the POTWs with incinerators (these will be more heavily
sampled because concentrations of radioactive material are expected to be higher in
ash than in sludge), (3) POTWs in all geographic areas of the contiguous United States,
and (4) POTWs requested by States and ISCORS agencies.
The survey questionnaire will ask the POTW operator to list the zip codes served by its
collection system. Using this information, NRC will identify those licensees associated
with each POTW that have the potential to dispose of radioactive material into its
collection system.
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There are currently approximately 7,000 NRC licensees and 15,000 Agreement State
licensees in the United States (including Alaska and Hawaii, the District of Columbia and
Puerto Rico). About half of these facilities use radioactive materials in the form of
sealed sources (i.e., contained within a metal or other material casing); radioactive
material in sealed sources cannot be disposed into the sewer system. Facilities that use
material in unsealed form are predominantly hospitals, clinics, radiopharmacies,
research and academic facilities, fuel cycle facilities, and research reactors. Nuclear
power plants are not allowed to discharge to sewer systems.
2. The selection of the 300 POTWs to sample will be based on the results of the
questionnaire survey. The questionnaire responses will be grouped into several
categories and a random sample will be selected from each category. The categories
we expect are:
Types of NRC licensees (e.g., industrial, academic, medical)
Geographic area, especially areas of high background radioactive
material
Sludge use or disposal practice (e.g., incinerator ash, landfill)
Potential problems include a low response rate because the survey is voluntary and
difficulty in finding sufficient sample respondents for each category.
3. The following actions should lead to improved response rates:
A short and easy to complete questionnaire
A cover letter clearly stating the objectives of the data collection effort
Development of a program to follow up on non-respondents
4. A pilot survey of nine POTWs was executed to test the questionnaire and the
sampling and laboratory analysis procedures. As a result of the pilot survey, several
changes were made to the questionnaire. For example, a question was added on
whether the POTW had previously sampled for radioactive material. If there is a
question about the survey results at a specific POTW, and an earlier analysis is
available, it may be advisable to compare the two analyses.
As a result of the pilot survey, several changes were made to the sample analysis. For
example, the list of radionuclides to be analyzed was refined, and the need for analysis
of some samples by both labs was dropped due to the similarity of the test site results at
the two labs.
5. Statistician consulted for the statistical aspects of the survey design:
Lee Abramson
U.S. Nuclear Regulatory Commission
301-415-6180
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APPENDIX C
SEWAGE SLUDGE QUESTIONNAIRE
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APPENDIX C
SEWAGE SLUDGE QUESTIONNAIRE
1. GENERAL INSTRUCTIONS
1.1 Introduction
The U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental Protection
Agency (EPA) request your participation in a joint national survey of the concentrations of
radioactive material in sewage sludge (biosolids), ash, and related byproducts.
NRC regulations in 10 CFR 20.2003 currently permit licensee disposal of certain specific
quantities of soluble or readily dispersible biological radioactive material into a sanitary sewer
system. The EPA regulation that addresses the use or disposal of sewage sludge (40 CFR
Part 503) currently does not address radionuclides.
This survey will help determine the adequacy of the present NRC and EPA regulations
addressing the discharge of radioactive material to the sanitary sewer system. It will also
respond to a recommendation from the General Accounting Office (GAO) to determine the
extent to which radioactive contamination in sewage sludge, ash, and related byproducts is
occurring (GAO report, "Actions Needed to Control Radioactive Contamination at Sewage
Treatment Plants," May 1994).
1.2 When and Where to File
Please return the completed questionnaire within 30 days of date of receipt to the address
below:
U.S. Nuclear Regulatory Commission
Attn: Mary Thomas
Mail Stop T-9C24
Washington, DC 20555
1.3 Reporting Period
Please report information for the last 12 months or the last calendar year.
1.4 Further Information
If you require assistance in completing this questionnaire, call Robert Bastian, EPA, at
202-260-7378, (email: bastian.robert@.epa.gov) or Mary Thomas, NRC, at
1-800-368-5642-extension 6230 (email: mltKajnrc.gov).
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2. GLOSSARY OF TERMS
End-products are the materials that leave the sewage treatment facility or are disposed of
onsite after all
processing is completed (e.g., ash from incineration, digested liquid or dewatered cake, dried
pellets, compost).
Incineration is the combustion of matter in sewage sludge by high temperatures in an enclosed
device.
Land application is the application of sewage sludge to land to either condition the soil or
fertilize crops or other vegetation.
Monofills are landfills where only sewage sludge is disposed. Monofills include trenches and
area fills.
Municipal solid waste landfill is a landfill that receives household waste, and that is not a land
application unit, surface impoundment, injection well, or waste pile. Such a landfill may be
publicly or privately owned.
Sewage sludge is solid, semi-solid, or liquid residue generated during the treatment of domestic
sewage in a treatment works. Sewage sludge includes, but is not limited to: domestic septage;
scum or solids removed in primary, secondary, or advanced wastewater treatment processes;
and material derived from sewage sludge. Sewage sludge does not include ash generated
during the incineration of sewage sludge or grit and screenings generated during preliminary
treatment of domestic sewage in a treatment works.
Surface disposal is the placement of sewage sludge on an area of land for final disposal. It
includes monofills, surface impoundments, lagoons, waste piles, and dedicated disposal sites.
It does not include treatment and storage of sewage sludge, although placement on land for
longer than 2 years is considered surface disposal unless the site owner/operator retains
written records demonstrating that the operation constitutes a treatment or temporary storage
site.
Treatment works is either a Federally-owned, publicly-owned, or privately-owned device or
system used to treat (including recycle and reclaim) either domestic sewage or a combination of
domestic sewage and industrial waste of a liquid nature.
Use or disposal includes: land application of bulk sewage sludge, land application of sewage
sludge sold or given away in a bag or other container, surface disposal, disposal in a municipal
solid waste landfill unit, incineration, or any other use or disposal practice (e.g., vitrification, use
in asphalt or brick production).
SECTION I. TREATMENT WORKS IDENTIFICATION INFORMATION
Mailing Label
Name of the treatment works and physical location (which may differ from the mailing address):
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Mailing address of the treatment works (if different):
Name, title, and telephone number of the person who should be contacted regarding
information on this questionnaire:
Name, title, address, and telephone number of the person who should be sent the sample
collection package:
SECTION II. GENERAL TREATMENT WORKS INFORMATION
1. Indicate below the level(s) of wastewater treatment achieved by this treatment works.
(Mark X for all that apply.
D a. Primary treatment
D b. Secondary treatment
D c. Advanced treatment
2. Provide the annual average daily total flow rate for the last 12 months or the last
calendar year (the total volume of wastewater treated by the treatment works in one
year divided by 365). Use Gallons per Day (GPD) if your total daily flow rate is less than
10,000 GPD, or use Million Gallons per Day (MGD), but not both.
GPDorMGD
(Circle one) over the last 12 months or last calendar year (circle one)
3. List the zip codes served by the collection system for this treatment works. This
information is needed so NRC can identify licensees that can potentially discharge to
your collection system. A list of these licensees will be sent to you in return for providing
this information.
4. Identify the sewage sludge treatment process(es) used at your treatment works. (Mark
X for all that apply.)
D a. Treatment works did not process sewage sludge in the last 12 months or
the last calendar year. Explain:
D b. Thickening
D c. Mechanical dewatering by
(Please fill in process(es) used.
D d. Heat treatment/wet air oxidation
D e. Aerobic digestion
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D f. Anaerobic digestion
D g. Composting
D h. Lime stabilization (Class B)
D i. Alkaline Stabilization (Class A)
D j. Air drying beds
D k. Heat drying/Pelletizing
D I. Sewage sludge treatment/storage lagoon(s)
D m. Sewage sludge storage bins or piles
D n. Incineration
D o. Other sewage sludge treatment processes
(Please specify.)
5. Check the boxes below to indicate the sewage sludge use or disposal practice
employed at your facility or by others using/disposing of your sewage sludge or ash.
Also describe the product as one of the following: slurry, dewatered cake, compost,
pellets, ash, effluent, grit, or other. Note if the product is stored onsite before ultimately
being disposed offsite; and if the product is stored onsite, the time stored onsite.
D a. Land application. Product description:
D b. Surface disposal (permanent piles, lagoons, sludge or ash monofills).
Product description:
D c. Disposal in municipal solid waste landfill.
Product description:
D d. Transfer of your sewage sludge or ash to another facility for use or
disposal.
Product description:
Identify the facility (type, location):
D e. Other use or disposal practice.
Product description:
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Describe practice:
6. What are the primary sources of drinking water for your community? Check more than
one, if applicable.
D a. Municipal water supply from surface water source(s)
D b. Municipal water supply from groundwater well(s)
D c. Private wells
D d. Private water supply from surface water source(s)
7. Does your wastewater collection system receive discharges of drinking water treatment
residuals?
Yes No
8. Does your wastewater collection system include combined sanitary and storm water
sewers?
Yes No
9. Do you receive sludge from other wastewater treatment facilities for processing at your
facility?
Yes No
10. Do you receive septage for processing at your facility?
Yes No
11. What percentage of the annual average daily total flow rate (response to question 3) is
industrial flow?
Percent
12. Have you ever tested for radioactive materials in your sewage sludge?
Yes No
13. Do you have more than one final sewage sludge production facility location?
Yes No
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APPENDIX D
QUALITY ASSURANCE PROJECT PLAN
EPA/NRC SEWAGE SLUDGE SURVEY
IAG/QAPP-2
Revision 1
October 2001
Prepared by:
U.S. Environmental Protection Agency
Office of Radiation and Indoor Air
National Air and Radiation Environmental Laboratory
540 South Morris Avenue
Montgomery, AL 36115-2601
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This Quality Assurance Project Plan has been prepared in accordance with requirements
described in EPA QA/R-5, »EPA Requirements for Quality Assurance Project Plans for
Environmental Data Operations," United States Environmental Protection Agency, Quality
Assurance Management Staff (now Quality Assurance Division), Draft Interim Final, August
1994.
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Quality Assurance Project Plan
EPA/NRC Sewage Survey
Revision History
Rev. Responsible Official Date
0 Mary Wisdom 10/27/99
1 Andrea R. Jones 10/31/01
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TABLE OF CONTENTS
Revision History D-2
Table of Contents D-3
1.0 Project Description D-5
2.0 Project Organization and Responsibilities D-5
3.0 Project Quality Objectives D-6
4.0 Procurement and Acceptance Requirements D-12
5.0 Instruments and Equipment D-13
5.1 Field and Sampling Instruments and Equipment D-13
5.2 Laboratory Instruments and Equipment D-13
6.0 Documentation and Records D-14
6.1 Document Control System D-14
6.2 Laboratory Operating Documents D-14
6.3 Project Documentation D-15
6.4 Project Data Package Deliverables D-16
6.5 Records Archiving and Retention Policies D-18
7.0 Sampling Process Design D-18
8.0 Sampling Procedures D-18
8.1 Sampling Procedures and Equipment D-18
8.2 Collection of Samples D-18
8.3 Sample Custody, Shipping, and Notification D-18
8.4 Corrective Actions D-22
9.0 Laboratory Sample Receipt D-22
10.0 Laboratory Sample Preparation Procedures D-23
11.0 Analytical Procedures D-23
11.1 Analytical Methods D-23
11.2 Analytical Quality Assurance D-23
11.3 Quality Control Samples D-23
11.4 Sample Batching D-28
11.5 Waste Disposal D-28
12.0 Laboratory Data Management D-28
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13.0 Reports to Management D-32
13.1 Frequency and Distribution of Reports D-32
13.2 Direct Reports to Management D-32
13.3 Reports of Audit Findings D-33
13.4 Performance Evaluation Results D-33
13.5 Project Reportsforthe Sludge Survey D-33
14.0 Assessments and Responses D-33
14.1 Performance Evaluation and Cross-Check Samples D-33
14.2 QAC Laboratory Audits D-34
14.3 Corrective Actions and Nonconformance Reports D-34
15.0 RISSAD Data Management Quality Assurance Project Plan D-36
15.1 Environmental Health Associates D-36
15.2 Data Acceptance Criteria D-36
15.3 Computer and Computer Software D-36
15.4 Record Keeping D-37
15.5 Data Management Path D-38
15.6 Document and File Tracking Systems and Change Control Systems D-38
15.7 Data Security: Transference, Storage, Recovery and Retrieval D-38
15.8 Final Quality Assurance of Database D-39
16.0 Implementation of the QAPP D-39
16.1 Implementation Schedule D-39
16.2 Flexibility D-39
16.3 Review and Approval for the Sludge Project D-39
Table D.1 Format of Monthly Data Report D-16
Table D.2 Minimum Detectable Concentrations for Selected Gamma Emitters D-20
Table D.3 Minimum Detectable Concentrations for Selected Radionuclides D-21
Table D.4 NAREL Data Handling Equipment D-31
Table D.5 ORISE Data Handling Equipment D-32
Figure D.1 Alpha Analysis Decision Tree D-8
Figure D.2 Beta Analysis Decision Tree D-9
Figure D.3 Gamma Analysis Decision Tree D-10
Figure D.4 Comparison of Critical Level to Detection Limit D-11
Figure D.5 Data Flow Process D-29
Figure D.6 RISSAD Data Handling Process D-37
Appendix A Sampling Kit and Sample Collection Information Sent to POTWs D-40
Appendix B Method and Reference SOPsforthe Survey D-43
Glossary D-45
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1.0 PROJECT DESCRIPTION
This Plan applies to the joint survey sponsored by the U.S. Nuclear Regulatory Commission
(NRC) and the U.S. Environmental Protection Agency (EPA) to collect information concerning
radioactivity in sewage sludge and ash from sewage treatment plants (referred to in the industry
as publicly owned treatment works (POTWs) which was conducted from 1998 through 2000.
The U.S. Department of Energy's Oak Ridge Institute for Science and Education (ORISE), in
Oak Ridge, Tennessee and EPA's National Air and Radiation Environmental Laboratory
(NAREL) in Montgomery, Alabama analyzed the sewage sludge and ash samples. NAREL and
ORISE will each analyzed half the samples. Samples were collected over a 12-month period to
ensure an even flow of samples into the laboratories and to allow adjustments to the analyses
as needed.
Pilot Study
In order to evaluate sampling procedures, laboratory procedures, and laboratory comparability,
nine POTWs were selected as test cases. The samples from the test cases were collected,
shipped, analyzed, and reported undercurrent requirements of the Quality Assurance Manual
for the Energy/Environment Systems Division, Environmental Survey and Site Assessment
Program (EESAP) of ORISE, and The Quality Assurance Plan for the National Air and Radiation
Environmental Laboratory and written NAREL and ORISE QA/QC policies for radionuclide
analysis. Split samples from the nine test POTWs were analyzed by both ORISE and NAREL.
Results were studied to ensure comparability, consistency in sample handling, and validity of
analytical methods. The results of this study indicated that in general the laboratories had good
agreement between gamma analyses. Thus, the final survey did not require that split samples
be analyzed by both laboratories. The gross alpha and beta analyses did not provide as good
agreement due to differences in calibration and/or analysis procedures at the two laboratories.
Although gross alpha and beta measurements are useful as screening tools, their accuracy
should not be assumed to be better than about one order of magnitude. Therefore, the general
magnitude of the results should be evaluated rather than detailed comparisons between
individual measurements.
2.0 PROJECT ORGANIZATION AND RESPONSIBILITIES
At ORISE, the Program Director and Assistant Program Director have overall responsibility for
ESSAP quality assurance. Specifically, they establish program policies and procedures;
monitor training operations; monitor data collection, development, and management; host and, if
necessary, initiate external audits; review final survey reports and approve for release; and
authorize exceptions to the requirements of the ESSAP Manual. The Quality Assurance
Manager provides independent oversight for QA/QC pertaining to projects and laboratory
activities and provides input directly to the Program Director; maintains the tracking system of
audit findings and nonconformances, and then follows their resolution and closure; reviews all
final reports prior to release; oversees maintenance of ESSAP training and certification records;
oversees ESSAP performance evaluation activities; and coordinates vendor/provider
assessments as deemed necessary by the Program Director.
According to the NAREL Quality Management Plan, the Director of the Office of Radiation and
Indoor Air (ORIA) is responsible for ensuring that measurements performed within ORIA meet
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established Data Quality Objectives (DQOs). The Office Director has delegated the
responsibility for overseeing quality assurance to the ORIA Quality Assurance Manager and has
further delegated to the NAREL Director the primary responsibility for quality assurance on
measurements in that facility. The NAREL Director has appointed a Quality Assurance
Coordinator (QAC) to direct and oversee the laboratory's Quality Assurance Program. In
addition, the Quality Assurance Forum (QAF) has been formed to focus on all pertinent QA
issues. The QAF meets quarterly, includes all interested laboratory personnel, and uses open
forums and work groups to recommend procedures that will effectively and efficiently resolve an
identified problem.
The two laboratories will provide the analytical work, quality control and quality assurance, and
data review and internal evaluation for the project. NAREL and ORISE will cooperate fully
toward reaching agreement and closure on any issues which arise.
NAREL and ORISE staff are knowledgeable, well-trained, and experienced. Staff are trained,
qualified, and certified according to requirements in the two laboratories' QA plans. Laboratory
staffs routinely perform radiochemical analysis and data evaluation and interpretation.
Laboratory analysts must be trained and certified for the analytical procedures they conduct.
At ORISE, staff receives appropriate training in health and safety, first aid, and CPR as deemed
necessary by program management. The Quality Assurance manager ensures completion of
training. The Office of Human Resources schedules and tracks ORISE mandatory training and
assists with developmental training. The Office of Safety and Environmental Assurance
provides training for radiation workers as required by federal regulations, and other safety related
training as needs are identified. At NAREL, the Safety, Health, and Environmental Manager
(SHEM) and the Radiation Safety Officer (RSO) with assistance from the Branch Chiefs and the
Laboratory Director, annually assess individual needs for training in health and safety and in
radiological safety for each employee. Specific job responsibilities dictate the type, complexity,
and frequency of such training. Once an employee is identified as requiring health and safety
training, whether initial or refresher training, attendance at, and completion of, the training are
mandatory.
3.0 PROJECT QUALITY OBJECTIVES
Data quality objectives for the laboratory analysis of project samples are the normal analytical
procedures and quality control acceptance criteria routinely followed by each of the laboratories.
Section 11 of this QAPP provides a complete description of the analytical DQOs, their
acceptance criteria, and corrective action required if criteria are not met.
ORISE will supply the sample collection packages to the POTWs. Samples will be collected,
preserved, packaged, and shipped to the ORISE or NAREL laboratory by regular POTW
workers using information and sampling supplies furnished by the laboratories. See Appendix A
for sampling instructions and lists of sampling materials to be sent to POTWs.
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Samples collected each month will be screened by the laboratories using their standard
procedures for gross alpha and beta analysis and gamma scanning. A decision tree will be
used for the alpha, beta, and gamma screening analyses to determine if, and what, nuclide
specific analyses are indicated. Figures 1, 2, and 3 show the three decision trees. These trees
will be used to identify samples for nuclide-specific analyses from the samples sent to the
laboratories by the POTWs.
D-7
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Figure D.1
Alpha Analysis Decision Tree
Perform gross alpha
analysis on sludge or ash
samples.
Is gross alpha activity
present ?
Report no activity
detected, with the MDC
value provided.
c
Stop
yes
Pool samples until end
of calendar month.
re the positiv
samples in the top 10%
of activities detected this
calendar month for
each matrix?
Report activity (at 95%
confidence).
Compare samples with gamma
spectra. If presence is
confirmed, perform specific
radiochemical analyses for
U, Th, Pu, Am as indicated.
Is activity detected
for a specific nuclide?
Report no activity
detected, with the MDC
value provided, for
each nuclide.
Stop
Report activity (at 95%
confidence) of the specific
nuclide(s).
C
Stop
D-8
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Figure D.2
Beta Analysis Decision Tree
Perform gross beta
analysis on sludge or asl
samples.
Is gross beta activity
present ?
Pool samples until end
of calendar month.
re the posi
mples in the top 1
of activities detected this
calendar month for
ach matrix
Report no activity
detected, with the MD(
value provided.
Stop
Report activity (at 95°X
confidence).
yes
Perform specific radiochemica
analyses for Sr.
Is activity detected
fora Sr?
Report no activity
detected, with the MDC
value provided, for
each nuclide.
Stop
yes
Report activity (at 95%
confidence) of Sr.
f Stop J
D-9
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Figure D.3
Gamma Analysis Decision Tree
Perform gamma spectroscopy
on sludge crash samples
using standard 1000 minute
counting time.
Report no activity detected,
with the MDC value
provided.
Stop
yes
Report activity (at 95%
confidence) of nuclides
detected.
Stop
D-10
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Each laboratory will report the minimum detectable concentration (MDC) for all nuclides of
interest which are not detected in a sample. The instrument signal is compared to a critical level
(Lc) which is the value of the net signal (e.g., count rate) that has a 5% probability of being
exceeded when a blank sample is analyzed. It is used as a threshold value for deciding whether
a sample contains the analyte of interest.
The minimum detectable concentration in a sample (MDC) is the smallest concentration of
analyte (expressed in this study as pCi/g of sludge or ash) that has a 95% probability of
producing a net detection-level signal (Ld) greater than the critical-level signal (Lc). It is thus the
statistically smallest concentration with a 95% probability of being detected. Figure D.4
illustrates this concept.
Figure D.4 Comparison of Critical Level to Detection Limit
File Contains Data for
PostScript Printers Only
Analytical results will be reported as activity ± 2s uncertainty. At NAREL, the uncertainty for all
alpha spec results includes counting error, nonzero uncertainties for the sample volume, tracer
concentration, and tracer volume, and an uncertainty in the counting efficiency, although this
uncertainty affects only thorium results and yields for other analyses. For Ra-226 analyses,
NAREL uses counting uncertainty and an uncertainty in the counting efficiency. For all other
analyses, only counting uncertainty is computed. NAREL made an administrative decision to
change the uncertainty reported for all of its gamma analyses in April 2000. The decision was to
change from reporting only counting uncertainty, to reporting an uncertainty number which
represents our best estimate of total uncertainty. The contractor who maintained the sewage
survey database applied this total uncertainty correction algorithm retroactively to the counting
uncertainties previously reported by NAREL. This makes all uncertainty numbers in the sewage
survey database (for both NAREL and ORISE) nominally equivalent 'total uncertainty.
At ORISE, uncertainties for alpha and gamma spec include anything that has an uncertainty
associated with it, including balances, pipettes, volumes, standards, tracers, and counting error.
Uncertainty does not include any uncertainty related to the field sampling procedure.
NAREL reports uncertainty to two significant figures. Associated activity numbers are reported
with their least significant digit being the same as the least significant digit of the uncertainty,
e.g., if the least significant digit of the uncertainty is the tenths digit, that of the activity will also be
tenths.
Of all the sludge/ash samples in which gross alpha or gross beta activity is detected, 10% will
be chosen each calendar month from both ash and sludge matrices, and submitted for nuclide-
specific analysis. They constitute a population, or sample pool, from which special samples will
be selected for nuclide-specific analyses. The number of monthly samples should not exceed,
for routine analyses, about 35 samples per month for each laboratory (400 samples/lab/12
months for routine analyses consisting of gross beta, gross alpha and gamma analyses). For
D-11
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nuclide-specific analyses, no more than 3 to 4 samples per month per laboratory (10% special
samples from the 400 samples/lab/12 months) should be analyzed; and for quality control
samples, about 5 per laboratory per month (60 QC samples/12 months in addition to the 300
routine samples).
It should be understood that samples which are received in a calendar month during the survey
will be analyzed in batches as soon as is practicable. All samples for which gross alpha, gross
beta, and gamma analyses are performed during a calendar month will be stored until the end of
the month at which time decisions will be made about which samples of that month's pool will be
subjected to nuclide-specific analyses. These nuclide-specific analyses will be conducted
during the following 60 days.
Except for preparation of tritium samples at ORISE, no special or extraordinary sample
concentration or analytical procedures will be employed for analysis of the sludge samples. For
tritium analysis, ORISE will add two steps to its routine preparation procedure:
1. All samples will be double distilled to reduce or eliminate as many interferences as
possible.
2. The chemiluminescence monitor for the instrument will be turned on and monitored.
Both laboratories will use currently approved analytical procedures for routine environmental
samples. MDCs for samples will be those usually cited by each laboratory for environmental
samples.
There are no established guidelines or regulations, in the ranges of results expected in these
studies, which would dictate distinct actions at certain levels. Thus, any actions which might be
recommended, or any indication of the need for further regulatory decisions, cannot be
established until the results of the survey are complete. In the absence of applicable guidelines
or regulations, recommended actions will be based on professional judgement.
The Data Quality Objectives (DQOs) for these studies have been developed using a process
outlined in the guidance document EPA QA/G-4, Guidelines for the Data Quality Objective
Process. Generally, DQOs for such specific criteria as accuracy, precision, comparability, and
completeness will correspond to those routinely cited by the two laboratory quality assurance
manuals as part of the laboratories' overall quality assurance and quality control program.
Specific quantitative criteria for laboratory procedures are discussed within Section 11 of this
QAPP.
4.0 PROCUREMENT AND ACCEPTANCE REQUIREMENTS
For ORISE, the Quality Assurance Manual for the Energy/Environment Systems Division,
Environmental Survey and Site Assessment Program (ESSAP) identifies items or services to
be procured by description of the item or service required along with all specifications, health
and safety considerations, and quality requirements. The ORISE Financial Operations Division
is responsible for procurement processing and compliance with all applicable regulations.
ESSAP is responsible for assessment/inspection of items or services and payment approval.
D-12
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The authority to commit and/or obligate funds by purchasing and contracting has been delegated
to the NAREL Program Management Officer (PMO) and the NAREL Support Services Specialist.
These persons and the bank card holders are the only employees authorized to handle
procurement transactions with vendors. The technical or analytical staff is responsible for
requesting supplies, reagents, and materials of adequate purity and reliability to ensure that there
will be no adverse effect on the technical or analytical data produced. Procurement officials
must not change orders for reagents or for technical supplies or services without approval from
the original requestor. Upon receipt of purchased items, it is the responsibility of the requestor to
verify that the correct items, of the expected grade and quality have been received.
5.0 INSTRUMENTS AND EQUIPMENT
5.1 FIELD AND SAMPLING INSTRUMENTS AND EQUIPMENT
For sample collection, only new containers are to be used.
No laboratory-supplied field sampling equipment or instruments, other than sample containers,
will be used as part of this survey. Each POTW will use its own system and equipment to
collect the appropriate samples. POTW workers are experienced in collecting samples for
various analyses.
5.2 LABORATORY INSTRUMENTS AND EQUIPMENT
Laboratory instruments and equipment at each laboratory are used, calibrated, and maintained
according to accepted good laboratory practices, each laboratory's written policies, and each
laboratory's SOPs.
Regular efficiency checks (NAREL) and instrument reproducibility checks (ORISE) are
performed on every detector in use at the laboratory according to each laboratory's standard
operating procedures and written policies. Criteria and corrective actions are in place in both
laboratories which dictate procedures when checks fail.
Regular background measurements are required for all detectors by both labs. At NAREL,
backgrounds are measured daily for proportional counters, twice a month for alpha
spectrometers, monthly for germanium detectors, and immediately before a sample is counted
on a scintillation counter. ORISE measures backgrounds daily for proportional counters and a
scintillation counter. Weekly background counts are performed for the alpha and gamma
detectors.
Each gross radiation detector has an acceptable range for background levels. Background
measurements are evaluated statistically to determine whether the true level is outside the
acceptable range. There are warning limits and rejection limits for the test. If the most recent
background level is outside the rejection limit, the detector is not used to analyze samples.
All radioactive standard solutions used for calibrations at NAREL and ORISE are NIST traceable
whenever possible. Standard reference materials are purchased directly from NIST when they
are available. If NIST traceable solutions are not available, industry accepted standards are
used.
D-13
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6.0 DOCUMENTATION AND RECORDS
6.1 DOCUMENT CONTROL SYSTEM
At ORISE, the Quality Assurance Manual and procedures manuals are controlled documents.
They are distributed to all ESSAP personnel who must use the information to perform or review
work. Agency representatives may also receive controlled documents on request. The QA
Manager ensures document control is maintained according to QA Manual procedures.
NAREL operates under a formal document control system, described in the NAREL SOP for
Document Control, which presents the policies and procedures for the production, review,
revision, storage, and distribution of documents. Document control policies apply to all printed
internal documents that are maintained by or for NAREL personnel on a continuing basis for a
period longer than one year. Controlled documents include, but are not limited to, the NAREL
Quality Management Plan (QMP), Quality Assurance Manuals (QAMs), Quality Assurance
Project Plans (QAPPs), SOPs, technical documentation, and forms. The Document Control
Officer maintains the NAREL Document Control Logbook, maintains current copies of all
controlled documents in hard copy and electronic forms, approves any new or revised
documents in the system, and has primary responsibility for the NAREL SOP for Document
Control.
6.2 LABORATORY OPERATING DOCUMENTS
At ORISE, procedures used in the ESSAP activities are documented in the following manuals
prepared specifically for ESSAP applications: Laboratory Procedures Manual, which presents
the procedures used in handling, preparation, and analysis of samples for radioactive
constituents; Survey Procedures Manual, which presents the procedures used for radiation
measurements and sampling; and the Quality Assurance Manual. These manuals are
controlled documents.
The NAREL Quality Management Plan (QMP) describes the Quality System at NAREL in terms
of the organizational structure, functional responsibilities of management and staff, lines of
authority, and processes for planning, implementing, documenting, and assessing activities.
The QMP is the umbrella document for management policies, goals, and processes which
incorporate quality assurance and quality control into all aspects of work. The QMP describes
how NAREL implements its quality system and educates its staff about QA and QC processes.
A Quality Assurance Manual (QAM), formerly called a Quality Assurance Plan (QAP), presents
technical criteria for analytical and administrative tasks to ensure that all data produced will be of
known and desired quality, and that all measurements performed at NAREL are valid,
scientifically defensible, and of known precision and accuracy. The QAM addresses all phases
of the quality control, quality assurance, and quality assessment processes. A Quality
Assurance Project Plan (QAPP) describes in detail the necessary QA, QC, and other technical
activities that must be implemented to ensure that the work performed on a specific project will
satisfy the required performance criteria. Each project conducted by or for NAREL requires a
QAPP. This includes projects supported by contract, interagency agreement, or grant.
D-14
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Standard Operating Procedures (SOPs) contain specific details and procedures which ensure
that data generated by their use will be of known and adequate quality. An SOP details the
method for an operation, analysis, or action, with thoroughly described techniques and steps.
6.3 PROJECT DOCUMENTATION
This QAPP describes the necessary QA, QC, and other technical activities that will be
implemented during the Sewer Sludge Survey project. The QAPP is written in accordance with
requirements described in EPA QA/R-5, »EPA Requirements for Quality Assurance Project
Plans for Environmental Data Operations," United States Environmental Protection Agency,
Quality Assurance Management Staff (now Quality Assurance Division), Draft Interim Final,
August 1994. The QAPP also incorporates specific points of agreement between EPA, NRC,
ORISE, and NAREL. It references specific documents, including SOPs, which will guide the
procedures used during this survey.
6.3.1 GAMMA ANALYSIS
The activity and 2-sigma uncertainty for radionuclides measured by gamma spectrometry are
reported only if the nuclide is detected. Nuclides that are not detected do not appear in the
report, with the exception of Co-60, Cs-137, 1-131, K-40, Ra-226 and Ra-228. If one of these six
nuclides is undetected, it is reported as »Not Detected" or »ND", and a sample-specific estimate
of the MDC is provided.
Due to potential spectral interferences and other possible problems associated with the
determination of the activity of certain radionuclides, the activities for Th-234, Pa-234m, Ra-226,
and U-235 are subject to greater possible uncertainty than other commonly reported
radionuclides. It should be noted that this potential uncertainty is not included in the two-sigma
counting uncertainty which is reported with each activity. Although the calculated activities for
these radionuclides are reported, it is recommended that the results be used only as a
qualitative means of indicating the presence of these radionuclides and not as a quantitative
measure of their concentration. The results for these nuclides are not used in the evaluation of
quality control samples. Furthermore, because of mutual interference between Ra-226 and
U-235, NAREL's gamma analysis software tends to overestimate the amounts of these
nuclides whenever both are present in a sample. Lower estimates for Ra-226 activities can be
obtained from the reported activities of its decay products, Pb-214 and Bi-214, which are likely to
be somewhat less than the Ra-226 activity because of the potential escape of radon gas.
NAREL's gamma spectrometry software corrects activities and MDCs for decay between
collection and analysis, but only up to a limit of ten half-lives. So, if the decay time for a sample
is more than ten half-lives of a radionuclide, that nuclide will almost always be undetected and
the reported MDC will be meaningless. This is usually a problem only for short-lived
radionuclides, such as 1-131, when there is a long delay between collection and analysis.
ORISE uses extrapolated efficiencies for radionuclides with energies below 59 keV, e.g., 1-125
and Pb-210. The reported concentrations and MDCs for any radionuclide below 59 keV are
approximations and are reported as qualified data. At both laboratories, all preparation, survey,
sampling, analytical, reporting, and disposal activities are completely documented throughout the
life of a project.
D-15
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6.3.2 GROSS ALPHA AND BETA ANALYSIS
In comparison to the methods employed to determine radionuclide-specific activities, the method
employed by NAREL to determine gross alpha and beta activity has the potential for greater
analytical bias. This is especially true for solid samples. It should be noted that this potential
analytical uncertainty is not included in the two-sigma counting uncertainty term. Therefore,
gross alpha and beta results should be used as gross approximations of the alpha and beta
activity present.
6.4 PROJECT DATA PACKAGE DELIVERABLES
Each month, the laboratories will prepare data packages for each batch of samples which has
been completed during that calendar month. The data for each completed analysis batch will be
correlated on sample summary sheets. See Table 6.1 for an example of the format and content
of the data summary sheet. Copies of the data packages and summary sheet will be sent to
project managers for EPA and NRC by the 10th day of the month following the end of the month
being summarized. Review of the monthly reports will provide a continuing input of information
about nuclides and activities seen at the POTWs in the survey and, most importantly, will allow
the reviewers and the project team to note problems and unusual results. Monthly data reports
will allow the project team to correct any problems noted, change action limits for nuclide-
specific analyses if necessary, and add data to the databases to be used for analysis of survey
results.
Table D.1
Laboratory:
Sample ID:
Collection Date and Time:
Monthly Data Report for EPA/NRC National Radiological Sewage Survey
Data Summary Sheets
Page of
Other ID:
Matrix:
Analysis
Gamma
Gamma
Gamma
Gamma
Gamma
Gamma
Gamma
Gamma
Gamma
Gamma
Gamma
Nuclide
Pb-212
Pb-214
Bi-214
1-131
Ra-226
Ra-228
Bi-212
Be-7
TI-208
K-40
Cs-137
Activity
2s Uncertainty
Units
% solids
MDC
D-16
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Analysis
Gamma
Gamma
Alpha
Beta
LSC
LSC
a Spec
a Spec
a Spec
a Spec
a Spec
a Spec
a Spec
a Spec
a Spec
a Spec
a Spec
Prop. Ctr.
Prop. Ctr.
Nuclide
Co-60
1-125
Gross
Gross
C-14
H-3
U-234
U-235
U-238
Th-227
Th-228
Th-230
Th-232
Pu-238
Pu-239
Pu-242
Am-241
Sr-89
Sr-90
Activity
2s Uncertainty
Units
% solids
MDC
Both labs analyze samples in analytical batches; no information will be reported about a sample
or an analysis until the entire batch data package has been completed, reviewed, verified, and
approved for release from the lab according to the lab's quality assurance and data review
policies.
For each analytical batch of samples analyzed at the laboratory, a data package will be provided
for each type of analysis. This package will include:
tabulated sample information for the analytical batch: sample ID, client sample ID, matrix,
date collected, date received, and date analyzed.
documentation exceptions
holding time information if applicable
sample preparation exceptions
sample analytical exceptions
general information unique to the sample batch, the analytical method, or reporting
conventions
individual report forms for each sample which provide
D-17
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sample identification information
analytical method
detector identification
sample weight information
activity units
nuclides, activity, 2s uncertainty, and MDC
Instrument printouts including spectra and other raw data, calibration data, and quality control
results are compiled and maintained in the laboratory for each sample batch. Raw data will not
be included in the monthly data reports, but will be maintained by the labs and will be available to
reviewers on request.
6.5 RECORDS ARCHIVING AND RETENTION POLICIES
All records pertaining to environmentally related measurements will be archived, retained, and
disposed of according to the pertinent EPA records schedule, with concurrence of EPA and
NRC. No documents at either laboratory are disposed of without specific approval from the
client or data-user for the project.
7.0 SAMPLING PROCESS DESIGN
Owners and operators of the selected POTWs will collect and ship the samples following
guidelines provided by ORISE and NAREL.
All samples collected will be analyzed for gross alpha and beta emissions and gamma-emitting
nuclides and, if indicated by the decision tree process, (See Figures 1, 2, and 3) for uranium,
thorium, plutonium, radium-226, americium, and strontium. All samples received at ORISE will
be analyzed for carbon-14 and tritium. The NAREL and ORISE Minimum Detectable
Concentrations (MDC) for these nuclides are listed in Tables 7.1. and 7.2.
8.0 SAMPLING PROCEDURES
8.1 SAMPLING PROCEDURES AND EQUIPMENT
Procedures and equipment for field collection of samples are described in the instructions for
collection found in Appendix A of this QAPP.
8.2 COLLECTION OF SAMPLES
Container identification labels will be filled out completely in indelible ink. Labels are glued to
containers and then covered with clear waterproof tape for protection. Containers will be filled,
closed, and rinsed with water to minimize cross-contamination. Samples will be described and
identified on the appropriate Sampling Data Form and are packed for shipment to the laboratory.
Samples must be collected and returned to the laboratory within one week of receipt of the
sampling kit at the POTW.
8.3 SAMPLE CUSTODY, SHIPPING, AND NOTIFICATION
ORISE will send appropriate sampling containers, chain-of-custody forms (COCs), and sample
collection and handling instructions to each POTW in the survey and will notify NAREL when kits
D-18
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are sent and to which facilities. Copies of the COC and the collection instructions are found in
Appendix A of this QAPP. POTW operators will collect the samples, ensure that the samples
are properly labeled with the name of the facility, type of material sampled, location or source of
the sample, the name of the person taking the sample, and the date and time of sample
collection. The COC form will then be completed to include the name of the facility, the location
or source of the sample, the name of the person taking the sample, and the date and time of
sample collection.
The samples will be placed in a shipping container and security seals placed across the top and
bottom of the shipping container. Samples will be shipped priority overnight by Federal Express
for next-morning delivery to the designated laboratory. No samples should be shipped to
laboratories on Friday or the day before a holiday. ORISE will track delivery of all samples
shipped by the POTWs. NAREL will notify ORISE of shipments received.
D-19
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Table D.2 Minimum Detectable Concentration (MDC) for Selected Gamma Emitters Using Gamma
Spectrometry with Ge Detector
Selected Gamma
Emitters
Am-241
Cd-109
Th-234
U-235
Ra-226
Th-229
Pb-212
Ra-224
Ra-223
Pb-214
1-131
Rn-219
1-125
Be-7
Ba-140
TI-208
Cs-134
Bi-214
Cs-137
Bi-212
Pb-21 1
Mn-54
Ra-228
Pa-234m
Co-60
Na-22
K-40
NAREL MDC
(pCi/L)
forl L of Water
Counted for 1000
min
17.7
83.0
52.5
56.7
86.1
65.6
8.45
91.0
26.7
11.4
5.84
69.6
100
45.4
22.2
6.42
6.67
13.1
7.26
89.4
188
7.03
24.4
950
10.3
9.38
99.3
NAREL
MDC (pCi/gwet)
for 1 00 g of Sediment
Counted for 1000 min
0.0842
0.424
0.270
0.294
0.446
0.340
0.0439
0.473
0.139
0.0601
0.0307
0.367
0.15
0.241
0.119
0.0344
0.0357
0.0704
0.0391
0.483
1.02
0.0382
0.133
5.20
0.0566
0.0519
0.552
ORISE
MDC (pCi/L)
forl L of Water
Counted for 1000
min
4.88
64
68.7
14.4
61.0
38.0
5.41
59.8
16.0
8.02
3.04
39
10
26.6
11.4
3.95
4.11
8.29
4.18
28.7
117
3.52
21
687
4.33
4.17
59.4
ORISE
MDC (pCi/gwet)
for 1 00 g of Sediment
Counted for 1000 min
0.01
0.6
0.10
0.02
0.6
0.05
0.01
0.08
0.01
0.01
0.01
0.3
0.2
0.04
0.02
0.01
0.01
0.01
0.01
0.04
0.17
0.01
0.2
0.67
0.01
0.01
0.10
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NOTE: MDCs will vary depending on activity in the sample, density of sample matrix, efficiency of detector, and other counting
parameters. The above MDCs were calculated based on a 1000-min count of a 1.0-L Marinelli of deionized water.
Table D.3 Minimum Detectable Concentration (MDC) for Selected Radionuclides Using Various Radiochemical Analyses
Radionuclide
Gross Alpha
Gross Beta
Radium-226
Radium-228
lodine-131
Uranium-234, 235,
238 Thorium-230,
232
Plutonium-238, 239
Sr-89
Sr-90
Thorium-227
Thorium-228
H-3
C-14
Matrix
Water
Solids
Water
Solids
Water
Solids
Water
Solids
Water
Water
Solids
Water
Solids
Water
Solids
Water
Solids
Water
Solids
Wet
N/A
NAREL
Typical
Aliquot Size
250 ml
250 ml
1 L
0.5 g
1 L
0.5 g
2L
1L
0.5 g
2L
0.5 g
2L
0.5 g
1L
0.5 g
1L
0.5 g
N/A
N/A
Count
Time (min)
100
100
1000
1000
100
100
1000
1000
1000
100x3
100x3
100x3
100x3
1000
1000
1000
1000
N/A
N/A
Method
GFP
GFP
SC
SC
GFP
GFP
GFP
AS
AS
CS-PC
CS-PC
CS-PC
CS-PC
AS
AS
AS
AS
N/A
N/A
MDC
6 pCi/L
3 pCi/L
0.02 pCi/L
0.04 pCi/g
1 pCi/L
2 pCi/g
0.7pCi/L
0.1 pCi/L
0.2 pCi/g
1
4
1
4
0.2 pCi/L
0.35 pCi/g
0.15 pCi/L
0.3 pCi/g
N/A
N/A
ORISE
Typical Aliquot
Size
250 ml
250 ml
1 L
700g
1 L
700 g
1 L
0.25L
ig
0.25 L
5g.
0.25 L
5g.
0.25 L
1.0g
0.25 L
1.0g
60 g wet
0.5 g wet
Count Time
(min)
200
200
240
60
60
60
1000
1000
1000
60
60
60
60
1000
1000
1000
1000
60
60
Method
GFP
GFP
AS
GS
GFP
GS
GS
AS
AS
GFP
GFP
GFP
GFP
AS
AS
AS
AS
LSC
LSC
MDC
3 pCi/L
2 pCi/L
0.1 pCi/L
1 .0 pCi/g
2 pCi/L
1 PCi/g
3.2 pCi/L
0.4 pCi/L
0.1 pCi/g
5.0
0.5
5.0
0.5
0.4 pCi/L
0.1 pCi/g
0.4 pCi/L
0.1 pCi/g
1 .0 pCi/g
3.0 pCi/g
AS Alpha Spectrometry
GFP Gas-Flow Proportional Counting
GS Gamma Spectrometry
LS Liquid Scintillation Counting
SC Scintillation Counting
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8.4 CORRECTIVE ACTIONS
Each laboratory will receive and survey samples according to approved laboratory procedures
and policies. Discrepancies in labeling, COC information, or other documentation will be noted
on the COC for the samples and, when the discrepancy has the potential to affect sample
integrity, it will be reported to the POTW samplers and the EPA and NRC project managers. All
discrepancies and their resolution must be fully documented. Additional information about
corrective action is provided in Section 14.3 of this QAPP. Specific information regarding
corrective actions and the personnel responsible for them are documented in the QA manuals
for each laboratory.
9.0 LABORATORY SAMPLE RECEIPT
Similar procedures are used at both NAREL and ORISE to ensure complete control of samples
and clear, concise documentation of the steps in the sample chain-of-custody form.
The POTW staff initiates the chain-of-custody form for survey samples. When sample custody
is transferred (relinquished) to the laboratory, the container and its contents are inspected by the
individual accepting custody to assure that tampering has not occurred and custody has
therefore been maintained.
Samples received at ORISE will be surveyed for radioactive contamination and recorded in the
electronic sample database according to Laboratory Procedures Manual requirements. The
Laboratory Supervisor will maintain sample custody until the sample is disposed of, consumed,
transferred, or destroyed. Sample disposal must be authorized by the Program Director or
Assistant Program Director at the direction of the customer. During analysis, the samples will
remain in a locked building during working hours and in a locked room in the building during non-
working hours. Disposition information is entered into the electronic database. Archived
samples are sealed and stored in a locked building.
Environmental samples received at NAREL are surveyed for radioactive contamination, logged-
in, and stored in accordance with the NAREL SOP for Sample Receipt, Log-in, and Storage. All
samples are received by the Sample Preparation Manager (SPM) or her designee. Sample
packages are stored in a secure area until they are surveyed for radioactive contamination. The
results of the survey are recorded on the chain-of-custody. The SPM compares the samples
received to the chain-of-custody. Any discrepancies must be resolved and documented on the
COC before sample analysis begins. The samples are then logged-in to the Sample
Preparation Logbook and into the NAREL Radioanalytical Database.
After samples are logged-in and numbered, and all documentation is complete, samples are
stored at various locations at NAREL, depending on the matrix, analyses requested, and project,
until the analyses are performed. Samples are always stored in a secure area to which only
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laboratory personnel have access. Access to NAREL is restricted. Outside entrances,
laboratories, the counting room, and the sample preparation area require a key-card for entry.
Visitors must sign in at the reception area and are escorted while in the laboratory.
10.0 LABORATORY SAMPLE PREPARATION PROCEDURES
Sample preparation procedures and required documentation are described in the specific
NAREL SOPs and the ORISE procedures manuals for each analytical method. Exceptions to
an approved procedure must be documented and explained fully in accordance with the
laboratories' QA manuals. Corrective actions must be initiated and documented when required.
Appendix B of this QAPP lists specific references to methods and procedures.
11.0 ANALYTICAL PROCEDURES
11.1 ANALYTICAL METHODS
All analytical methods used for this survey at either the NAREL or ORISE laboratories have been
approved internally and are based on industry standard procedures with proven precision and
accuracy. Methods are described and techniques outlined in the individual method SOPs
and procedures manuals for the two laboratories. Appendix B of this QAPP provides a list of
methods and procedures for each laboratory.
11.2 ANALYTICAL QUALITY ASSURANCE
Quality control testing is performed for laboratory activities to provide an ongoing assessment of
equipment and procedures. Quality control samples are prepared using standards traceable to
NIST or to industry accepted reference materials if NIST traceability is not possible. Chemicals
used for reagent preparation are reagent grade or higher depending on specific method
requirements.
11.3 QUALITY CONTROL SAMPLES
Laboratory quality control (QC) samples will be included in the analytical scheme in accordance
with the Quality Assurance Manual for the Energy/Environment Systems Division,
Environmental Survey and Site Assessment Program (ESSAP) of ORISE, and The Quality
Assurance Plan for the National Air and Radiation Environmental Laboratory and written ORISE
and NAREL QA/QC policies for radionuclide analysis. Four types of internal quality control
samples are analyzed routinely in the NAREL and ORISE radiochemistry QA programs. The
QC analyses and their frequency are:
duplicate analyses (NAREL - one per analysis batch, ORISE - based on client request.);
matrix spikes, containing a known quantity of each analyte of interest added to an existing
sample (NAREL - one per analysis batch, ORISE based on client request);
performance evaluation (PE) samples consisting of the radionuclide of interest in either
an interference free matrix (usually deionized water) or standard reference material
(SRM) that will simulate soil or ashed samples; and
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reagent blanks, which contain only the radioactive tracer, if appropriate, and reagents
used in the analysis (one per analysis batch).
For both labs, a batch can contain 20 samples plus appropriate QC samples.
The batch QC requirements listed above do not apply to gamma analyses. Duplicate gamma
analyses are performed on every twentieth sample through the laboratory, and performance
evaluation samples consisting of a variety of gamma emitters and matrices are submitted to the
radioanalysis laboratory at least once a month.
The result of a quality control check is a quality indicator, whose numerical value must be judged
either acceptable or unacceptable. The acceptance criteria for a quality indicator must be based
on sound statistical principles and should be formulated in terms of the estimated uncertainties
and analytical errors (standard deviations) of the quantities used to compute the value of the
indicator.
A quality indicator may have both control limits and warning limits. When an indicator value falls
in the warning region, the Project Coordinator must initiate an investigation. When the value is
outside the control limits, the Project Coordinator must report the problem to the Quality
Assurance Coordinator, who will issue a corrective action memorandum .
11.3.1 Duplicate Analyses
Duplicates are two aliquots taken from the same homogenized sample.
When precision is assessed by duplicate analyses, including matrix spike duplicates, the quality
indicator is given by
where
ST = First of two measurements
S2 = Second of two measurements
L/i = Estimated 1-sigma total random error associated with S.,
1/2 = Estimated 1-sigma total random error associated with S2
When requested by the Subcommittee, NAREL will compute and report the 'relative percent
difference," or RPD, of the two measurements, which is defined by the equation
v-v
RPD x 100%.
(Sl S2)/2
Acceptance criteria based on the RPD generally require spiked activities significantly above
environmental levels and therefore are usually applicable only to matrix spike duplicates.
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If the total uncertainties U, for the measured concentrations S, are unknown, they may be
estimated. When duplicate analyses are performed, the total uncertainties may be estimated as
follows:
where
E, = Estimated 1-sigma counting error
? = Maximum acceptable 1-sigma total random error, excluding
counting error, expressed as a fraction of the concentration
The result of a duplicate analysis is acceptable if \Zd\ 2. An investigation is necessary if
< \Zd\ 3. Corrective action is required whenever \Zd\ > 3.
11.3.2 Spiked Samples
An aliquot of a sample is spiked (fortified) with known quantities of specific compounds and
subjected to the entire analytical procedure.
In the case of a matrix spike, the accuracy indicator is defined as
S-B-K
zr
uk2
where
S = Measured concentration in spiked aliquot
6 = Measured concentration in unspiked aliquot
K = Known concentration of spike added
Us = Estimated 1-sigma total random error associated with S
Ub = Estimated 1-sigma total random error associated with 6
Uk = Estimated 1-sigma total uncertainty associated with K
The total random uncertainties Us and Ub may be estimated as follows:
U2 E2-!2S\
S
where
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Es = Estimated 1-sigma counting error for S
Eb = Estimated 1-sigma counting error for 6
? = Maximum acceptable 1-sigma total random error, excluding
counting error, expressed as a fraction of the concentration
The accuracy indicator for performance spikes and standard reference materials is defined as
S'K
Z
where
S = Measured concentration of reference material
K = Known concentration of reference material
Us = Estimated 1-sigma total error associated with S
Uk = Estimated 1-sigma total uncertainty associated with K
The total random uncertainty Us may be estimated as follows:
U2 E2
S S
where
Es = Estimated 1 -sigma counting error for S
? = Maximum acceptable 1 -sigma total random error, excluding
counting error, expressed as a fraction of the concentration
It is permissible to use a fixed percentage of K, not to exceed 5%, for Uk. If the uncertainty in K
is assumed to be negligible, then Uk may be set equal to zero.
The indicator is acceptable if \Z\ 2. An investigation is necessary if 2 < \Zr\ 3. Corrective
action is required if |Zr| > 3.
When requested by the Subcommittee, NAREL will compute and report the ^percent recovery,"
or %R, which is given by
%R . J_ x 100%
K
for matrix spikes and by
%R . . x 100%
K
for performance spikes and standard reference materials. Meaningful acceptance criteria for
%R generally require spiked activities significantly higher than environmental levels.
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11.3.3 Reagent Blanks
A reagent blank, or method blank, is an analytical control, consisting of all reagents and internal
standards or tracers, that is carried through the entire analytical procedure. The blank is used to
define the level of laboratory background and reagent contamination.
Control charts are maintained for each analysis type. The initial set-up and all subsequent
updates of a control chart should be based on_a sample of at least 20 reagent blank results,
which are used to determine a sample mean x and standard deviation s.
The blank values used to compute the mean and standard deviation must first be judged
acceptable. For this purpose, any reagent blank measurement whose value differs from zero by
less than the 2-sigma counting error of the measurement is acceptable. Professional judgment
is required to accept any value that differs from zero by more than the 2-sigma counting error.
The mean and standard deviation are computed as follows:
1
x -. x ,
n
I- (V
^ w 1
x) . x nx
9
where n denotes the number of measurements.
A reagent blank value is judged acceptable if it lies within two standard deviations of the mean.
An investigation is required if the blank value is more than two but no more than three standard
deviations from the mean. The value is unacceptable if it is more than three standard deviations
from the mean.
When a reagent blank is unacceptable, the samples in the batch may have to be reanalyzed.
Any sample whose measured activity is greater than the associated 2-sigma counting error and
whose total activity is less than a predetermined multiple k (generally 5) of the total blank activity
must be reanalyzed.
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11.3.4 Completeness (statistical)
Completeness is assessed by the following indicator:
%C 100%
where
%C = Percent completeness
V = Number of measurements judged valid
n = Total number of measurements performed.
The requirements for judging measurements as valid and the total number of measurements
necessary to achieve the desired statistical level of confidence depend on the study objectives
and, thus, are specified by the QAPP. For this project, designed as a survey study, statistical
completeness is not an indicator of concern.
11.4 SAMPLE BATCHING
Analytical batches consist of a number of samples of the same matrix to be analyzed by the
same procedure for a common set of parameters. Batches may range in size from 1 to 20
samples. At NAREL and at ORISE, a batch may contain 20 samples plus the additional QC
samples. For this survey, reports and data packages will reference analytical batches of
samples as defined by each laboratory.
11.5 WASTE DISPOSAL
All radioactive and chemical wastes from samples and reagents are properly characterized,
stored, and disposed of in full compliance with all applicable federal and state regulations and
with internal NAREL and ORISE policies. Storage and disposal of hazardous and radioactive
waste is fully documented. No samples are disposed of without specific concurrence of the
laboratory client.
12.0 DATA MANAGEMENT
A flow diagram of the general data management scheme is shown in Figure D.5. The data
collection is initiated when ORISE sends sampling kits to POTW operators. Complete
documentation is required for each step in the sampling, shipping, receipt, storage, analysis,
data production and review, and sample disposal processes.
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Figure D.5
Data Flow Process
ORISE Sends Sampling
Kits to POTWs
Field Sample Collection
| Sample Preparation/Preservation in Field
Prepare Samples for Shipping
(with Chain-of-Custody)
I
Ship Samples to NAREL or ORISE |
I
I Sample Receipt at NAREL or ORISE I
I
Radiation Screening of Shipping Containers
Verification of Samples Received and
Chain-of-Custody Documentation
Sample Log-in and Identification Assignment
[Alpha/Beta Screen]
I Sample Preparation I
Distribute to Analysts
Gamma Screen
Specific Analyses
J Data Acquisition r
I
Specific Analyses
I Double Verification I
I
Data Package Preparation
Data Packane Review
r
Finalize Data Package
Permanent Electronic
Data Storage
Data Interpretation I
Compare Concentration of
Nuclidesto PRDL
Preparation of Monthly
Summary Reports
FPA/NRC HO Review and Comment
Preparation of Final Project Report
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A sample identification code is assigned to each sample. Sample preparation activities are
performed and the samples are distributed to analysts. Samples are subjected to appropriate
analyses (alpha/beta screening, gamma spectrometry, radiochemistry/ specific nuclides
analysis), and the resulting data are subjected to review and verification. NAREL analytical data
will be reviewed according to the NAREL Standard Operating Procedure for the Review of
Radioanalysis Data (Draft, June 14, 1996). ORISE analytical data will be reviewed according to
the ESSAP QA Manual. Following verification, the data are available for inclusion in a data
package or other report formats. All data packages and reports are peer-reviewed internally and
reviewed by the laboratory's QA staff before being sent to the data-user.
Review of the prepared reports includes verification of documentation for the following:
sample receipt and preparation,
laboratory data handling (using the Laboratory Information Management System (LIMS),
or other electronic systems,
instrumentation calibrations and efficiency checks,
types of sample analyses performed (individual detailed procedures are available for
each type),
data review, error detection and other problem determinations, including requirements for
recounting or reanalysis of samples,
involvement of the project quality assurance officers for the two labs.
Record keeping will be in the form of laboratory logbooks and information and data storage in the
laboratory LIMS system (which includes a large database of storage of all data produced in the
radioanalytical laboratory). Both NAREL and ORISE have formal document control systems
which allow for documents to be either controlled or uncontrolled. Data storage and retrieval is
via the LIMS system for NAREL and the relational database for ORISE.
Methods used by the laboratories in data management activities including verification of samples
with chain-of-custody records, instrument calibration and background checks, and extensive
review of counting room data including checks by at least four persons before release. Systems
backups are performed on a routine basis. For NAREL, the backups are daily, with archival to
optical disks. ORISE performs incremental backups every 2 days with a monthly full system
backup to tape. Any calculations requiring the data extract a copy from the database, leaving the
original electronic record intact. The only chance for temporary data loss is in case of a power
failure during sample counting or hardware failure. In those instances, the sample is still
available and is simply recounted.
Data handling equipment includes radioanalytical instrumentation, PCs dedicated to counting
room applications, and the local area network or other database systems. All of this equipment
has been thoroughly tested for these applications and proven to be stable and reliable.
Commercial software programs used by the two radioanalytical laboratories are listed in
Table D.4 and D.5.
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Table D.4 NAREL Data Handling Equipment
Program Analysis System
LB4000 Tennelec LB4000 Gas-Flow Proportional Counters (raw data)
GDR High-purity Germanium Detectors (raw and reduced data)
OASIS Alpha Spectrometers (raw and reduced data)
G3000 Gamma Products G3000 Automatic Germanium Counting System
(control software)
G5000 Gamma Products G5000 Automatic Alpha/Beta Counting System (control
software)
In-house software includes the following:
Data Entry and Instrument Control
Program Analysis System
1131 Tennelec LB4000 lodine-131
GROSS Tennelec LB4000 Gross alpha and beta
SR Tennelec LB4000 Strontium-89 and 90
RA228 Tennelec LB4000 Radium-228
TH234 Tennelec LB4000 Thorium beta tracer
GET4, GET12 Germanium counters
Calculation and Data Review
Program Analysis System
GAMMARVW Gamma spectrometry
ALPHARVW Alpha spectrometry (Am,U,Pu,Th)
I131RVW LB4000 lodine-131
GROSSRVW LB4000 Gross alpha and beta
SRRVW LB4000 strontium-89 and 90
RA226 Radium-226 by the radon emanation method
Data Management
CAA NAREL database system
RPT Interactive database queries
NARSS Counting Room analysis scheduling
DATAPKG Data package production
The calculations performed by all in-house analysis software are documented in the software
user manuals. Only one NAREL employee is authorized to modify in-house analysis software
and electronic and written records of software modifications are maintained. After each
modification of an analysis software system, the calculations are checked using a calculator
program, which reads equations from a text file in a form similar to that shown in the user's
manual. The results generated by the analysis software are checked against the results given
by the calculator.
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Table D.5 ORISE Data Handling Equipment
Program Analysis Program
Alpha spectrometry
Gamma spectrometry
Gross alpha/beta
GAMMA
AMS
ECLIPSE
Alpha Management System by Canberra
Genie Spectroscopy by Canberra
In-house Excel spreadsheet
High Purity Germanium Detectors (raw and
reduced data)
Alpha Spectrometers (raw and reduced
data)
Tennelec LB5100W (control software)
In-house software includes the following:
Data Entry, Calculation, and Data Review
Program
GROSS
SR
GAMTAB
AMS
Strontium-90
Strontium-89,90
Radium-228
Carbon-14
Tritium
Tech neti urn
Analysis Program
GAB EXCEL SPREADSHEET
SRB EXCEL SPREADSHEET
GAMMA TABLES EXCEL SPREADSHEET
VAX REDUCED DATA
In-house Excel spreadsheet
In-house Excel spreadsheet
In-house Excel spreadsheet
In-house Excel spreadsheet
In-house Excel spreadsheet
In-house Excel spreadsheet
13.0 REPORTS TO MANAGEMENT
13.1 FREQUENCY AND DISTRIBUTION OF REPORTS
The QA staffs at NAREL and ORISE make routine reports to management on the status of the
QA program, results of evaluations, and problems. In addition, project-specific reports may be
required.
13.2 DIRECT REPORTS TO MANAGEMENT
The NAREL QAC and the ORISE QM report to staff and management on QA or QC issues
routinely. Reports on audits and results of audits, performance evaluation results, and other QA
and QC issues which need to be brought to the attention of managers are performed in a timely
manner to ensure issue resolution.
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13.3 REPORTS OF AUDIT FINDINGS
Written reports of the audit findings and recommendations from internal and external audits are
submitted to the Laboratory Director, the Associate Director, and the Branch Chiefs as
applicable to each lab, by the NAREL QAC or ORISE QM. Responsible parties are expected to
investigate and correct deficiencies noted, and to submit a written audit response to the QAC or
QM.
13.4 PERFORMANCE EVALUATION RESULTS
QA staff distributes results of performance evaluation studies to the Branch Chief, the
Laboratory Director, the Associate Director, and the analysts, as the results are evaluated. At
NAREL, unacceptable results require that the Branch Chief or a designee investigate, initiate
corrective action, and submit a written Corrective Action Report (CAR) to the QAC. At ORISE,
unacceptable results require that a nonconformance report (NCR) be initiated, including a
corrective action plan. The QM tracks the NCR through completion.
13.5 PROJECT REPORTS FOR THE SLUDGE SURVEY
Each month, a report will be submitted by each of the laboratories to the NRC and EPA.
Reports will include results from sample analyses and information on problems and corrective
actions for that month. See Section 6.4 for a complete list of what a report will contain.
14.0 ASSESSMENTS AND RESPONSES
Technical assessments, audits, and inspections are part of the overall quality system and are
intended to provide guidance for quality improvement, to identify problems and deficiencies, and
to acknowledge what is being done well. Audits are management tools for assessment and
improvement, and are not to be viewed as punitive. The technical assessments help staff
evaluate how well expectations are being met and offer recognition for good practices and
effective work.
14.1 PERFORMANCE EVALUATION AND CROSS-CHECK SAMPLES
A performance evaluation (PE) or cross-check sample examines the ability of the laboratory to
perform analytical procedures and obtain data of known and required precision and accuracy.
Performance evaluation and cross-check samples are analyzed throughout the year as
continual checks on accuracy and precision for all analyses. The NAREL QA staff is also
expected to provide internally prepared single-blind PE samples on a regular schedule for
analytes and matrices of interest. Successful analysis of known reference materials is required
annually for analysts by both labs for the analytes for which he or she is certified to perform
analyses.
PE and cross-check samples must be analyzed and reviewed in the same manner as regular
analytical samples. PE or cross-check programs conducted by external agencies must be
coordinated through the QAC and the appropriate Branch Chief for NAREL and the QM for
ORISE. All results must be reviewed and approved by the QA staff before submitting data to any
outside PE program. Results and scores received from an outside program must be reported
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by the outside program directly to the QA staff at NAREL. The QAC or a designee compiles the
results, conducts a statistical test for acceptability, and reports the results to the analysts, the
Branch Chief, the Associate Director, and the Laboratory Director. Unacceptable results require
an investigation, and written documentation of findings and corrective actions must be submitted
to the QAC. The QA staff monitors trends in PE and cross-check results and provides a
quarterly graphical summary of PE results to management. The ORISE QAM compiles PE
results, enters them into a database, and reports results to laboratory staff, other managers, and
Program Directors. Results found to be outside the defined PE Program criteria are entered into
the nonconformance system and tracked through resolution by the QAM.
14.2 QAC LABORATORY AUDITS
The NAREL QAC conducts at least one complete systems audit during each fiscal year. The
audit must cover all aspects of NAREL's mission. The audit allows the QA staff to assess and
document facilities, equipment, systems, procurement, record keeping, data validation,
operations, maintenance, calibration procedures, software control, reporting requirements, and
QC procedures. The audit must assess adherence to the QMP, QAM, and SOPs, generally
accepted Good Laboratory Practices (GLP), and written policies for NAREL operations.
An audit of data quality should be performed each year either in conjunction with the systems
audit or at a different time. This audit will assess the methods used to collect, interpret, and
report the information required to characterize data quality. Such an audit requires detailed
review of recording and transfer of raw data, calculations, documentation procedures, and data
quality indicators. Audits may be either announced or unannounced.
The QAC or a designee is required to provide documentation of the audit findings, deficiencies,
and recommendations to management within one month after completion of an audit. Findings
and deficiencies require investigation and implementation of corrective actions by the
appropriate personnel, and require a written response to the QAC within one month of the audit
report.
The ORISE QM performs assessments of 25% of all projects. Assessments evaluate all critical
activities pertinent to the particular project for procedural compliance as well as good laboratory
practice. Results are documented and provided to the management team. The appropriate
manager ensures that corrective actions are successfully carried out. At ORISE, biennial audits
providing an external independent evaluation of all systems and work practices are also required.
14.3 CORRECTIVE ACTIONS AND NONCONFORMANCE REPORTS
Corrective action is required whenever the results of a quality assessment are unacceptable, as
when quality indicators fall outside predetermined rejection limits, or when an audit reveals
deficiencies in any portion of the QA program.
The primary responsibility for corrective action belongs to management. A Branch Chief or
Supervisor who delegates responsibilities to subordinates is still responsible for monitoring the
actions of those subordinates and for ensuring that the results are satisfactory. The Quality
Assurance Coordinator and Quality Manager also take active roles in resolving serious problems
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and all problems affecting more than one branch. He or she has the authority to require
corrective action and to halt operations in the event of a serious circumstance.
14.3.1 Initiation of Corrective Actions
The first person who discovers a problem should initiate the corrective action process by
reporting the problem to the laboratory's quality assurance staff. Corrective actions must be
initiated when:
There is a variation to or a deviation from an SOP, QAPP, QAM, or the QMP
There is a method, protocol, or work plan violation.
When samples or extracts are lost or otherwise cannot be handled by the usual
procedure or protocol.
When quality control criteria are exceeded and control cannot be re-established by
means defined in an SOP.
When there is suspect data for any reason.
When data are found to be flawed, of questionable validity, or in violation of good
laboratory practices.
In any other circumstances when an analyst, manager, or other staff deems it
appropriate to request investigation of a circumstance impacting on data quality.
14.3.2 Corrective Action Initiated by the QAC and QAM
At NAREL, the QAC may initiate corrective action by issuing a corrective action memorandum,
addressed to the appropriate Branch Chief, the Laboratory Director, and other concerned
parties, which describes the problem and provides a deadline for a formal response. The
Branch Chief, or a subordinate with delegated responsibility, investigates the problem, identifies
probable causes, and takes corrective action. The responsible party must report to the QAC the
steps taken to solve the problem. The QAC evaluates this corrective action report and may
accept it or require testing to prove that the problem has been solved. The QAC tracks the
progress of the corrective action until the problem has been resolved. The QAC must maintain
documentation of each corrective action. The file includes all related memoranda, paper copies
of electronic mail messages, and any computer printouts of related data.
Corrective action should generally be taken immediately. When immediate action is not
possible or required, the responsible party must issue a corrective action request, in the form of
a memorandum, to facilitate the tracking of the progress of the corrective action. The
memorandum will include:
description of the problem;
date of detection/identification;
name of the person identifying the problem;
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name of the person assigned to the corrective action;
target date for the solution;
periodic reporting status;
nature and date of solution; and
documented feedback to the initiator.
When the QAC performs an audit, he or she must summarize the results in a memorandum
addressed to the Laboratory Director and the key staff members involved in the audit. If the
QAC finds that corrective action is required, the audit report has the effect of a corrective action
memorandum and requires formal written responses.
At ORISE, the QAM discusses formal audit findings with the Program Directors and Manager
and assists with the determination of corrective action plans. The cognizant Manager performs
an investigation, identifies probable cause, and recommends corrective action to the Program
Directors and the QAM. Once the corrective action plan is approved, status of the item is
tracked by the QAM through completion. Quarterly nonconformance reports are submitted to
Directors and Managers.
15.0 RADIONUCLIDES IN SEWAGE SLUDGE AND ASH DATABASE (RISSAD) DATA
MANAGEMENT QUALITY ASSURANCE PROJECT PLAN
15.1 ENVIRONMENTAL HEALTH ASSOCIATES (EHA)
Personnel working on the database have received a copy of the RISSAD Data Quality
Management Plan. This section outlines EHA team member responsibilities and the interactions
required to implement evaluation of data quality, corrective actions, and reporting activities that
ensure data quality.
15.2 DATA ACCEPTANCE CRITERIA
Dual electronic and hard copy versions of the same data sent by ORISE or NAREL will be
compared for sameness. If the data points on both copies are the same, data will be accepted.
If not the same, the sender will be contacted for corrective action (See Figure D.6).
15.3 COMPUTER AND COMPUTER SOFTWARE
Software is obtained through purchase of commercial packages. Computer hardware is
obtained through purchase of commercial brands.
Acceptability of hardware/software configuration: The RISSADatabase is designed,
because of intents and purposes, to be portable and compatible with the most commonly
used and easily accessible computer operating systems, database and data analysis
software and computer hardware.
Original development of the database is in Microsoft Access 1997. Updates to newer
versions will be at the request of the subcommittee with agreement of NRC to support
such efforts.
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15.4 RECORD KEEPING
Quality assurance documentation is made at critical control points in the form of e-mail
communication and dated logs kept by each EHA team member. All stages of the RISSAD Data
Handling Process (see flow chart) are logged for completion. Task descriptions, task
delegations, task completion details, data/file transfers, data integrity issues, error
determinations and error correction measures implemented, resource needs, and
data/database alterations are logged. The logs are consolidated by the database manager for
compilation.
Figure D.6
RISSAD Data Handling Process
ORISE or NAERL e-mail an electronic copy of laboratory analytical data and send at the same time, by U.S. Postal Service,
a duplicate copy of the paper (hard) copy of the same data.
Both data set versions (electronic and hard) are compared for sameness, data point by data point.
If the two data versions are the same, the laboratory is notified that data integrity is fine and this fact is recorded. If the two data versions
are different (errors), the laboratory is notified of the disparity, the process for correcting errors is initiated and logged.
When data integrity is established, the electronic version is re-arranged in form to allow importation into RISSAD. I
No content modifications are made to any data points. I
Data are imported into RISSAD. I
The data are compared for sameness, data point by data point, with the original hard copy version. I
Source of any errors is determined. Errors are corrected. Errors and error correction process is logged. I
Data are merged. I
Data are compared with original import, data point by data point. I
Errors are corrected. Errors and error correction process is logged. I
Version tracking numbers are updated. I
Duplicate (backup) copies of RISSAD are regularly made and any changes to the data base are logged. I
I Database and raw data are stored on removable media (Zip disks/CD-RW) and paper and are locked up when not in use. I
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15.5 DATA MANAGEMENT PATH
Task delegation: Database manager will contact EHA team members with descriptions
of assigned tasks and transfer the appropriate data/materials to each team member.
Each EHA team member will acknowledge receipt of data/materials and understanding
of task. Team member will provide completed task product to database manager and
database manager will acknowledge receipt of task product. Database manager will
quality check product and then provide feedback to team member as to task product
quality. Any potential improvements will be discussed, decided on, and implemented.
EHA team members will quality check any products developed by the database
manager, and any potential improvements will be discussed, decided on, and
implemented.
Error correction and reporting: Each EHA team member will report any errors and
problems with data integrity, data/file transfer, database function and structure, and task
assignment to the database manager. Database manager and team member(s) will
then discuss problems, resolve as necessary, and implement corrective actions. Each
team member will enter each issue and subsequent solution implemented into his/her
project log.
Task completion resources: Each EHA team members will notify the database manager
of any questions and resources needed to complete task at any time.
15.6 DOCUMENT AND FILE TRACKING SYSTEMS AND CHANGE CONTROL SYSTEMS
Paper documents are filed and kept in a locked metal storage cabinet. Electronic files are
named clearly with the most recent date of alteration, alterations/changes are logged, and each
file is backed up. All electronic files are stored on and accessed from removable media (Zip
disks/CD-RW). Removable media are locked in a metal storage cabinet when not in use.
15.7 DATA SECURITY: TRANSFERENCE, STORAGE, RECOVERY AND RETRIEVAL
Transference: All electronic files that have data considered 'sensitive' or potentially
sensitive and that are transferred by Internet or sent by regular mail are encrypted.
Storage: All documents and electronic files that have data considered 'sensitive' or
potentially sensitive are kept under lock and key when not in use.
Supervision, Recovery and Retrieval: All documents and electronic files that have data
considered 'sensitive' or potentially sensitive are always under the active supervision of
the EHA team members using the data. EHA team members are responsible for locking
up all data after use. All 'sensitive' electronic files are stored on, accessed and
manipulated from removable media (Zip disks/CD-RW).
Security: Database manager will make decisions on sensitivity of data and on security
protocols for use within EHA, Inc. Security decisions will be based on Los Alamos
National Laboratory security protocols and any additional protocols required by EHA, Inc.
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EHA team members will follow all data management/security protocols. EHA team
members will discuss data management/security issues with database manager before
implementing any self-generated alterations of data management/security protocols.
15.8 FINAL QUALITY ASSURANCE OF DATABASE
When all data sets have been entered into the RISSAD database and point comparisons with
laboratory data sets have been completed, completeness of data against the original sample
selection list is performed. Discrepancies in sample numbers, duplicate data, and missing data
will be addressed by comparing laboratory codes with POTW IDs and resolving discrepancies
with appropriate subcommittee or laboratory personnel.
Finally, summary statistics will be calculated and reviewed for any suspicious data points
(outliers) which will then be followed up to ensure they represent valid data.
16.0 IMPLEMENTATION OF QAPP
16.1 IMPLEMENTATION SCHEDULE
Under EPA policy, no environmental data operations may begin to collect data before the QAPP
has been approved by authorized EPA personnel or other persons to whom this authority has
been specifically delegated. This applies to work performed intramurally by EPA staff and
extramurally by contractors and assistance agreement holders. For the purposes of this survey,
analytical data acquired from the original nine test sites may be used as part of the project data
since these data were acquired, reviewed, and reported under requirements of the quality
manuals for each laboratory.
16.2 FLEXIBILITY
The approved QAPP must be implemented as approved. However, when conditions or
requirements change during environmental data operations, the QAPP must be revised and then
reviewed and approved in the same manner as the original QAPP.
16.3 REVIEW AND APPROVAL FOR THE SLUDGE PROJECT
The signature page of this QAPP lists the required approvals from the two laboratories for the
original QAPP and for any subsequent revisions to this document. In addition, Revision 0 of the
QAPP was formally agreed to by all members of the ISCORS Subcommittee during its
conference call on November 9, 1999.
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Appendix A
Sampling Kit and Sample Collection Information Sent to POTWs in the Survey
ORISE/ESSAP
P.O. BOX 117
OAK RIDGE, TN 37830
Site (Name of plant & city)
CHAIN-OF-CUSTODY
RECORD
EMERGENCY CONTACTS
(423) 576-3561
(423)241-3242
_Sample Type (List type of samples)
Samplers (List personnel who took samples)
Note: If more than one name is listed, circle the sample custodian.
ESSAP
SAMPLE
NUMBER
(Leave this
column blank)
Sample Information
(List specific sample identification,
i.e. digestor#, tank if, filter press
cake, etc. This must correlate to
information on the sample
container)
Collected
D
a
t
e
Time
Date and time
of sample
collection
Remarks
(Leave this column blank unless
conditions existed which may
compromise sample integrity)
Chain-of-Custody Form Directions - April 1997
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essap\forms\c-o-c.dir
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Transport Method (Federal Express) Seal No. (Shiooina container seal
numbers)
1. Relinquished by:
(Initial custody relinquished by sampler)
2. Relinquished by:
3. Relinquished by:
4. Relinquished by:
(Date and
time of
sample
transfer)
Date
Date
Date
Time
Time
Time
'Received in good condition by:
(Note custody transfer until received by
courier)
'Received in good condition by:
'Received in good condition by:
'Received in good condition by:
*For sample received in unacceptable condition explain in Remarks" column.
Distribution: Original to individual having custody
Copy filed in field data
COLLECTION OF SEWAGE TREATMENT PLANT SAMPLES
Following is a list of the equipment and supplies, in the attached sample collection package, needed to
collect your sample(s):
For liquid samples, one 1 -liter translucent plastic bottle for each sample
For de-watered or dried samples, one wide-mouth white plastic jar per sample
One Chain-of-Custody form (for all samples)
One return shipping container
Return shipping labels with pre-paid shipping
Two security seals for the shipping container closure
Collect one sample from each solids waste stream produced at your facility. This may include
sludge, dewatered sludge, filter press cake, ash compost, etc. See 'Sampling Instructions" on next
page.
Instructions for return shipment of samples:
1. Ensure that the sample(s) are properly labeled with the type of material sampled, location or
source of the sample, the name of the person taking the sample, and the sample date and
time. Your facility code, for confidentiality purposes, is already on the sample
label(s).
2. Complete the enclosed Chain-of-Custody form with the location or source of the sample,
the name of the person taking the sample, and the sample date and time. Your facility has
been given a code which already appears on the Chain-of-Custody
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3. Place the sample(s) in the shipping container. The person taking the sample must sign the
completed Chain-of-Custody form as 'Relinquished by" and enclose the form with the
sample(s).
4. Reseal the shipping container and place the security seals across the top and bottom of the
shipping container.
5. Place the enclosed return shipping labels on the shipping container. The return shipping
label has your facility code and ORISE's mailing address or NAREL's mailing
address to help maintain confidentially.
6. Please return the sample(s) as quickly as possible after collection. Do not ship for
Saturday delivery.
If you have any questions or need assistance, please contact Dale Condra at ORISE (423) 241-3242
or Susan Baker at NAREL (334) 270-7052.
Sampling Instructions
If a sample is well-mixed, then a representative sample can be easily obtained. If a sample is not
well-mixed, then incremental aliquots must be collected and composited, to obtain a representative
sample. The collection date and time should be close to the date that the sewage treatment stream
leaves the plant for transport to a landfill or for land application.
For example, the sample might be collected from a digester, filter press or drying bed, truck, tank, or
pile. A liquid or slurry sample from a digester or tank should be from an outlet stream. The outlet or
sample port should be opened and allowed to flow until a representative sample is available. A
sample collected from a filter press should be a composite of several small samples collected at
different locations across the press or within the filter cake. A sample collected from a drying bed,
truck or pile should be scoops from various areas and levels of the drying bed, truck, or pile. A
sample of incinerator ash should be from the location where it is collected or stored.
A large-mouth plastic jug is sufficient for liquid and slurry samples. If a sample of the total stream
cannot be collected, then the stream should be cut across for equal time periods until the sample
container is full. If the sample is collected from a tank, the tank should be well-mixed; and the line
should be flushed before collecting the sample. If the sample is a slurry, the sampling procedure
could involve obtaining a representative sample from a lagoon, pond, tank, or other vessel. The
sample should be representative of the typical amount of solids and liquids in the material being
sampled. If not collected from a liquid or slurry stream, incremental aliquots should be collected that
are representative of the solids and liquid present. For some sampling, such as from lagoons, ponds,
tanks, and other vessels, grab samples of the liquid and solids may have to be collected as separate
samples (not composited).
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Appendix B
Method and Reference SOPs for the Suvery
Method and SOP References for NAREL
The Quality Assurance Plan for the National Air and Radiation Environmental Laboratory.
NAREL Radiochemistry Quality Assurance Manual
QA/SOP-1
QA/SOP-2
MAS/SOP-1
MAS/SOP-2
MAS/SOP-3
MAS/SOP-4
MAS/SOP-5
MAS/SOP-6
MAS/SOP-7
MAS/SOP-8
MAS/SOP-9
MAS/SOP-10
MAS/SOP-11
MAS/SOP-12
MAS/SOP-13
MAS/SOP-14
MAS/SOP-15
MAS/SOP-16
MAS/SOP-17
MAS/SOP-18
NAREL Standard Operating Procedure for Document Control
NAREL Standard Operating Procedure for Writing Standard Operating Procedures
NAREL SOP for Chain of Custody
NAREL SOP for Calibration of Balances
NAREL SOP for Cleaning Laboratory Glassware and Planchets
NAREL SOP for Operating and Maintaining Fume Hoods
NAREL SOP for Use and Maintenance of Laboratory Logbooks
NAREL SOP for Standardization ofpH Meters
NAREL SOP for Labeling Chemical Containers
NAREL SOP for Storing Chemicals and Solutions
NAREL SOP for Transporting Chemicals
NAREL SOP for Training and Certification of Laboratory Personnel
NAREL SOP for Preparing Alpha Spectrometry Efficiency Standards
NAREL SOP for Preparing Thorium-234 Tracer Solution
NAREL SOP for Preparing Uranium-232 Tracer Solution
NAREL SOP for Receipt, Log-in, and Storage of Environmental Samples
NAREL SOP for the Preparation of Environmental Samples for Radiochemical
Analysis
NAREL SOP for Calibration, Use, and Maintenance of Pi pets
NAREL SOP for the Use of Control Charts
NAREL SOP for the Review of Radiochemistry Data
RAL/SOP-1 NAREL SOP for Calibration and Use of High-purity Germanium Gamma Detectors
RAL/SOP-2 NAREL SOP for the Handling of P-10 Gas
RAL/SOP-3 NAREL SOP for the Use of the Tennelec LB4000 Multi-detector Counting System
RAL/SOP-4 NAREL SOP for Use of the OASIS Alpha Spectrometry System
RAL/SOP-5 NAREL SOP for the Handling of Liquid Nitrogen
RAL/SOP-6 NAREL SOP for Calibration and Use of the Random SC-5 Scintillation Counter
RAL/SOP-7 NAREL SOP for the Calibration and Use of the Gamma Products G-3000 Automatic
Gamma Counting System
RAL/SOP-8 NAREL SOP for Automated Gross Beta Analysis Using the G5000 Series
Alpha/Beta/Gamma Counting System
RAL/SOP-9 NAREL SOP for Calibration and Use of the G5400 Auto-Quad Alpha/Beta Counting
System
RAL/SOP-10 NAREL SOP for Calibration and Use of the G542 Alpha/Beta Counting System
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Method and SOP References for ORISE
Quality Assurance Manual for the Environmental Survey and Site Assessment Program
Laboratory Manual for the Environmental Survey and Site Assessment Program
1 Introduction
Organization and Responsibilities
3 Procedure for Evaluating Operational Performance of Laboratory Instruments and
Equipment
4 Quality Control
4 (1) Training and Certification
4 (2) Balance Quality Control
4 (3) Procedure for the Preparation, Control and Traceability of Standards
4 (4) Procedure for Control of Laboratory Logbooks
4 (5) Analytical Quality Control and Sample Flow
4 (6) Radiochemical Contamination Control
4 (7) Automatic Pipet Quality Control
5 Sample Receipt and Preparation
5 (1) Sample Log-in
5 (2) Electronic Calibration of Bicron Analyst Ratemeters
5 (3) Screening Samples for Laboratory Contamination Control
6 Gross Alpha and Beta Screening for Various Matrices
7 (1) Determination of Tritium Utilizing Gas Permeable Membrane Distillation
7 (2) Determination of Tritium Using Glass Distillation
8 Determination of lodine-131 in Milk and Water
9 Determination of lodine-125 in Environmental Samples
10 Analysis of Polonium-210 in Water Soil, and Air Filters
11 Radium-226 in Water and Soil using Alpha Spectrometry
12 Radium-226 and-228 in Water
13 (1) Determination of Strontium-90 and -89 in Milk, Water, and Solid Samples Other than
Soil and Sediment
13 (2) Determination of Strontium-90 and -89 in Soil and Sediment
14 Determination of Technetium-99
15 Isotopic Determination of Americium, Plutonium, Uranium, Neptunium, and Thorium in Soil,
Water, Air Filters, and Biotic Material
16(1) Gamma Spectrometry
16 (2) Direct Ratio Gamma Counting Method, Single Energy Method
16 (3) Direct Ratio Gamma Counting Method, Two Energy Method
17 Neutron Activation of Soil for Th-232, U-238, and Other Metals
18 Determination of Carbon-14 and Tritium Using the Biological Material Oxidizer
19 Determination of Nickel-63
20 Determination of Mercury by X-Ray Fluorescence
21 Mercury Analysis by the Vapor Atomic Absorption (VAA) Method
22 Alpha Spectrometry
23 Analysis of Carbon-14 in Soil, Sediment, and Water
24 Radiochemical Determination of Phosphorus-32
25 Liquid Scintillation
26 Low Background Alpha/Beta Counter
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27 Analysis for Sulfur-35 in Organic Material
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GLOSSARY
Acceptance criteria - Specified limits placed on characteristics of an item, process, or service
defined in requirements documents. (ASQC definitions.)
Accuracy- A measure of the closeness of an individual measurement or the average of a
number of measurements to the true value. Accuracy includes a combination of random error
(precision) and systematic error (bias) components which are due to sampling and analytical
operations.
Agreement state - A state which has signed an agreement with the NRC allowing the state to
regulate the use of radioactive material within that state.
AMSA- Association of Metropolitan Sewerage Agencies.
Assessment - The evaluation process used to measure the performance or effectiveness of a
system and its elements. Assessment is an all-inclusive term used to denote audit,
performance evaluation, management systems review, peer review, inspection, or surveillance.
Audit (quality) - A systematic and independent examination to determine whether quality
activities and related results comply with planned arrangements and whether these
arrangements are implemented effectively and are suitable to achieve objectives.
Bias - Systematic or persistent distortion of a measurement process which causes errors in
one direction.
Blank (reagent blank) - A sample which is used to monitor contamination during sampling,
transport, storage, or analysis. The blank is subjected to the complete analytical or
measurement process to establish a zero baseline or background value.
Calibration - Comparison of a measurement standard, instrument, or item with a standard or
instrument of higher accuracy to detect and quantify inaccuracies and to report or eliminate
those inaccuracies by adjustments.
Chain of custody- An unbroken trail of accountability that ensures the physical security of
samples, data, and records.
Comparability- A measure of the confidence with which one data set or method can be
compared to another.
Completeness - A measure of the amount of valid data obtained from a measurement system
compared to the amount that was expected to be obtained under correct, normal conditions.
Corrective action - Measures taken to rectify conditions adverse to quality and, where
possible, to preclude their recurrence.
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Data of known quality- Data that have the qualitative and quantitative components associated
with their derivation documented appropriately for their intended use, and when such
documentation is verifiable and defensible.
Data quality indicators - Quantitative statistics and qualitative descriptors that are used to
interpret the degree of acceptability or utility of data to the user. The principal data quality
indicators are bias, precision, accuracy (bias and precision are preferred), comparability,
completeness, representativeness, and statistical confidence.
Data Quality Objectives (DQO's) - Qualitative and quantitative statements derived from the
DQO process that clarify study technical and quality objectives, define the appropriate type of
data, and specify tolerable levels of potential decision errors that will be used as the basis for
establishing the quality and quantity of data needed to support decisions.
Duplicate samples - Two samples taken from and representative of the same population and
carried through all steps of the sampling and analytical procedure in an identical manner.
Duplicate samples are used to assess variance of the total method including sampling and
analysis.
Environmental data - Any parameters or pieces of information collected or produced from
measurements, analyses, or models of environmental processes, conditions, and effects of
pollutants on human health and the ecology, including results from laboratory analyses or from
experimental systems representing such processes and conditions.
Holding time - The period a sample may be stored prior to its required analysis. While
exceeding the holding time does not necessarily negate the veracity of analytical results, it
causes the qualifying or "flagging" of the data for not meeting all of the specified acceptance
criteria.
Incineration - the combustion of organic matter and inorganic matter in sewage sludge by high
temperatures in an enclosed devise.
ISCORS - Interagency Steering Committee on Radiation Standards. NRC and WPA formed
ISCORS to expedite the resolution and coordination of regulatory issues associated with
radiation standards. This committee was formed in response to October 27, 1994, letters from
Senator John Glenn to NRC, EPA and the Office of Science and Technology Policy (OSTP).
The objectives of the committee include the following: (1) facilitate a consensus on acceptable
levels of radiation risk to the public and workers, (2) promote consistent risk assessment and
risk management approaches in setting and implementing standards for occupational and public
protection from ionizing radiation, (3) promote completeness and coherence of Federal
standards for radiation protection, and (4) identify interagency issues and coordinate their
resolution. In addition to NRC and EPA, ISCORS membership also includes senior managers
from the Department of Defense, the Department of Energy, the Department of Labor's
Occupational Safety and Health Administration, the Department of Transportation, and the
Department of Health and Human Services. Representatives of the Office of Management and
Budget (OMB), OSTP and the States are observers at meetings. The ISCORS Sewage
Subcommittee is assisting in the development of an NRC/EPA sewage survey and a sewage
guidance document.
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Laboratory split sample - Two or more representative portions taken from the same sample
and analyzed by different laboratories to estimate the interlaboratory precision or variability and
data comparability.
Land application - spraying or spreading of sewage sludge onto the land surface; the injection
of sewage sludge below the land surface; the incorporation of sewage sludge into the land so
that the sewage sludge can either condition the soil or fertilize crops or vegetation grown in the
soil.
Matrix spike - A sample prepared by adding a known mass of target analyte to a specified
amount of matrix sample for which an independent estimate of target analyte concentration is
available.
Spiked samples are used, for example, to determine the effect of the matrix on a method's
recovery efficiency.
Municipal solid waste landfill - a land or excavation that receives household waste, and that is
not a land application unit, surface impoundment, injection well, or waste pile. Such a landfill
may be publicly or privately owned.
Peer review- A documented critical review of work generally beyond the state of the art or
characterized by the existence of potential uncertainty. The peer review is conducted by
qualified individuals (or organization) who are independent of those who performed the work, but
are collectively equivalent in technical expertise (i.e., peers) to those who performed the original
work. The peer review is conducted to ensure that activities are technically adequate,
competently performed, properly documented, and satisfy established technical and quality
requirements. The peer review is an in-depth assessment of the assumptions, calculations,
extrapolations, alternate interpretations, methodology, acceptance criteria, and conclusions
pertaining to specific work and of the documentation that supports them. Peer reviews provide
an evaluation of a subject where quantitative methods of analysis or measures of success are
unavailable or undefined, such as in research and development.
Performance evaluation (PE) - A type of audit in which the quantitative data generated in
a measurement system are obtained independently and compared with routinely obtained data
to evaluate the proficiency of an analyst or laboratory.
POTW- Publicly owned treatment works.
Precision - A measure of mutual agreement among individual measurements of the same
property, usually under prescribed similar conditions expressed generally in terms of variance.
Quality - The totality of features and characteristics of a product or service that bear on its ability
to meet the stated or implied needs and expectations of the user.
Quality assurance (QA) - An integrated system of management activities involving planning,
implementation, assessment, reporting, and quality improvement to ensure that a process, item,
or service is of the type and quality needed and expected by the client.
Quality control (QC) - The overall system of technical activities that measures the attributes
and performance of a process, item, or service against defined standards to verify that they
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meet the stated requirements established by the customer; operational techniques and activities
that are used to fulfill requirements for quality.
Reporting limit - The lowest concentration or amount of the target analyte required to be
reported from a data collection project. Reporting limits are generally greater than detection
limits and are usually not associated with a probability level.
Representativeness - A measure of the degree to which data accurately ad precisely
represent a characteristic of a population, parameter variation at a sampling point, a process
condition, or an environmental condition.
Reproducibility- The precision, usually expressed as variance, that measures the variability
among the results of measurements of the same sample at different laboratories.
Sewage sludge - solid, semi-solid, or liquid residue generated during the treatment of domestic
sewage in a treatment works. Sewage sludge includes, but is not limited to, domestic septage;
scum or solids removed in primary, secondary, or advanced wastewater treatment processes;
and material derived from sewage sludge. Sewage sludge does not include ash generated
during the incineration of sewage sludge or grit and screenings generated during preliminary
treatment of domestic sewage in a treatment works.
Spike - A known quantity of a chemical that is added to a sample for the purpose of determining
(1) the concentration of an analyte by the method of standard additions, or (2) analytical recovery
efficiency, based on sample matrix effects and analytical methodology.
Standard operating procedure (SOP) - A written document that details the method for an
operation, analysis, or action with thoroughly prescribed techniques and steps, and that is
officially approved as the method for performing certain routine or repetitive tasks.
Traceability- The ability to trace the history, application, or location of an entity by means of
recorded identifications. In a calibration sense, traceability relates measuring equipment to
national or international standards, primary standards, basic physical constants or properties, or
reference materials. In a data collection sense, it relates calculations and data generated
throughout the project back to the requirements for the quality of the project.
Treatment works - either a federally owned, publicly owned, or privately owned device or
system used to treat (including recycle and reclaim) either domestic sewage or a combination of
domestic sewage and industrial waste of a liquid nature.
Use or disposal - includes land application of bulk sewage sludge, land application of sewage
sludge sold or given away in a bag or other container, surface disposal, disposal in a municipal
solid waste landfill unit, incineration, or any other use or disposal practice.
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