r/EPA
United States
Environmental Protection
Agency
Environmental Monitoring
Systems Laboratory
P.O. Box 93478
Las Vegas NV 89193-3478
EPA/600/4-89/019
DOE/DP/00539-061
May 1989
Research and Development
Off-Site Environmental
Monitoring Report
Radiation Monitoring
Around United States
Nuclear Test Areas,
Calendar Year 1988
-------
Available to DOE and DOE contractors from the
Office of Scientific and Technical Information
P.O. Box 62, Oak Ridge, TN 37831
prices available frorrH(615) 576-8401, FTS 625-8401
Available to the public from the
National Technical Information Service
U. S. Department of Commerce
5285 Port Royal Road, Springfield, VA 22161
Price Code: Printed Copy or Microfiche A01
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Department of Energy
Nevada Operations Office
R 0. Box 98518
Las Vegas, NV 89193-8518
OEI;:,81989
Recipient
ENVIRONMENTAL STA2US AT TBE NEVADA TEST SITE
The primary mission of the Nevada Operations Office (NV) is the underground
testing of nuclear devices. TJiare axe no major processing facilities
located at the site that would release emissions typical of conventional or
nuclear industrial operations * TMs "Off-Site Environmental Monitoring
Report" contains infonnat,ion alxwt and analysis of results from monitoring
programs dssigrtM to wssssxee :rel©ases of radioactive materials from
activities aqretueted for the U.S. Departasant of Energy (DOE) at the several
sites j^ags^t^by NW The results indicate that conditions at these sites
ccaply with the .standards and'requireients of the DOE, as well as other
federal and state regulations related to radiation.
In addition to,the information contained in this report, information on
monitoring and analysis related to nonradiological requirements on the
Nevada Test Site is being assembled into an additional report not yet
availably. In general, there have besn few noncompliancesf and those that
have beeh identified are being resolved with appropriate state agencies.
Howsver, thefts are important environffiaital, issues facing NV in terms of
nuclear ei^^r&Lated grqandwater contamination, possible National Priority
listing, lifting of the desert tortoise as an endangered species, possible
listing of "Astragalus beatleyea56 as an endangered plant species, and an
interagarssy agreeasnt with the state of Nevada for implementation of the
Environmental Survey Action Plan. These and other topics are discussed in
nor® detail in the attached summary assessment.
Questions related to environmental compliance issues should be identified
to tha Office of External Affairs on 702-295-3521.
Nick c. AquilinaI
EPD/EST:DRE Manager
Enc.losure:
Summazy Assessment
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CERCLA Reporting
Under CERCLA, releases of hazardous or extremely hazardous
materials above a reportable quantity must be reported to the
National Response Center (NRG). Nevada Operations Office (NV)
met with the Chief of Operations, state of Nevada Division of
Emergency Management, on October 25, 1989, to discuss reporting
procedures for underground nuclear tests conducted at the NIB.
NV has begun reporting underground tests to the State Emergency
Management Division; copies of reports that list unclassified
materials in typical tests will also be provided to the state.
This reporting is in addition to reporting to the NRC.
Endangered Species
The desert tortoise was listed under the Endangered Species Act
on August 4, 1989. All NV operations in desert tortoise
habitats, approximately 30 percent of the NTS, are being
evaluated to determine possible impacts. Preconstruction surveys
are under way and long-term monitoring is being implemented.
"Astragalus beatleyea" is also presently under consideration for
federal listing as an endangered plant species. A conservation
agreement developed with the U.S. Fish and Wildlife Service for
protection of the species includes preconstruction surveys and
long-term monitoring in potential "Astragalus beatleyea"
habitats. Should "Astragalus beatleyea" be listed as endangered,
additional activities may be required.
Interagency Agreement
NV is currently negotiating an agreement with the state to define
working relationships and responsibilities to implement the
Environmental Survey Action Plan (ESAP), the Environmental
Restoration and Waste Management Five-Year Plan, and other
regulatory requirements affecting the NTS.
Continuing Surveillance
NV recognizes the Importance of environmental audits, reviews,
surveillances, and inspections as tools to ensure compliance with
environmental regulations. Baseline information on audits is
being compiled and is to be included in subsequent reports.
Results of an Environmental Survey of the NTS conducted in the
summer of 1987 by Headquarters have been compiled in the ESAP.
Fifty-eight of the 105 findings in the report have been closed
and 11 data record sheets have been revised; corrective action is
ongoing for the remaining findings.
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SUMMARY ASSESSMENT
ENVIRONMENTAL COMPLIANCE ACTIVITY
U.S. DEPARTMENT OF ENERGY NEVADA TEST SITE
BACKGROUND
The Nevada Test Site (NTS) must operate in compliance with environmental
and other requirements established by a number of federal and state
statutes and regulations, Executive Orders, and the U. S. Department of
Energy. The following paragraphs summarize the NTS compliance status with
major environmental statutes:
Clean Air Act — The NTS has 26 air quality permits with the state
of Nevada and is in substantive compliance with permit limits.
Procedural violations have been resolved. NTS is assessing all
facilities to ensure that all release points have been identified
and permitted.
- clean Water Act. Safe Drink'' TXT Water Act— The NTS has nine public
water system and sewage treatment system permits with the state
of Nevada and is in substantive compliance with permit limits.
Procedural violations have been resolved. NTS is seeking permits
for new or modifications to existing systems as they are
identified.
Resource Conservation and Recovery Act — The NTS has submitted
four closure plans, two Part B permit applications, and will be
preparing three additional closure plans resulting in substantive
compliance with regulatory requirements. Procedural violations
have been resolved. The state of Nevada is reviewing the permit
applications.
Comprehensive Environmen^l Ttegponse,, Compensation and Liability
Act fCERdA) — The Preliminary Assessment/Site Investigation
reports have been provided to the Environmental Protection Agency
for their review. This action will determine the status
regarding the National Priority List and the NTS. Community
right-to-know reporting requirements are fully satisfied.
Current Issues and Actions
Groundwater
The past and present nuclear device testing program poses
significant environmental questions. Each test produces large
amounts of radioactivity and lesser amounts of hazardous
components, both of which are known to have contaminated
groundwater. Questions that must be addressed by ongoing
monitoring and research programs are the extent of contamination
and the potential for movement of contamination off site.
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EPA-600/4-89/019
DOE/DP/00539-061
May 1989
Off-Site Environmental
Monitoring Report
Radiation Monitoring Around United States
Nuclear Test Areas, Calendar Year 1988
contributors
C. A. Fontana, N. R. Sunderland
S. C. Black, B. B. Dicey, A. N. Jarvis,
K. S. Moroney, A. A. Mullen,
V. E. Niemann, D. D. Smith,
E. A. Thompson, and
Nuclear Radiation Assessment Division
I
V)
rv
x prepared for the
U.S. Department of Energy
under Interagency Agreement
Number DE-AI08-86NV1 0522
ENVIRONMENTAL MONITORING SYSTEMS LABORATORY
OFFICE OF RESEARCH AND DEVELOPMENT
U.S. ENVIRONMENTAL PROTECTION AGENCY
LAS VEGAS, NEVADA 89193-3478
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NOTICE
This report has been reviewed In accordance with the U.S. Environmental Protection Agency's peer and
administrative review policies and approved for publication. Mention of trade names or commercial
products does not constitute endorsement or recommendation for use.
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TABLE OF CONTENTS
Figures v
Tables vii
List of Abbreviations, Acronyms, and Conversions ix
1.0 Abstract 1
2.0 Introduction 3
3.0 Summary 5
4.0 Description of the Nevada Test Site 7
5.0 Radiological Safety Activities 19
5.1 Special Test Support 19
5.2 Routine Environmental Surveillance 20
5.2.1 Air Surveillance Network (ASM) 21
5.2.2 Noble Gas and Tritium Surveillance Network (NGTSN) . . . 24
5.2.3 Milk Surveillance Network (MSN) 44
5.2.4 Biomonitoring Program 44
5.2.5 Thermoluminescent Dosimetry (TLD) Network 60
5.2.6 Results of TLD Monitoring 61
5.2.6.1 Offsite Personnel 61
5.2.6.2 Offsite Stations 63
5.2.6.3 Comparison with Direct Exposure Measurements 67
5,2.7 Pressurized Ion Chamber (PIC) Network 77
5.2.8 Internal Exposure Monitoring 80
5.2.9 Long Term Hydrological Monitoring Program (LTHMP) ... 83
6.0 Public Information and Community Assistance Programs . m
7.0 Quality Assurance and Procedures 115
8.0 Dose Assessment 125
9.0 Sample Analysis Procedures 127
10.0 Radiation Protection Standards for External and Internal
Exposure 129
11.0 References 135
iii
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FIGURES
Number Page
1 Location of the Nevada Test Site (NTS) 8
2 Ground Water Flow Systems Around the Nevada Test Site 10
3 General Land Use Within 300 km of the Nevada Test Site ........ 11
4 Population of Arizona, California, Nevada, and Utah Counties
Near the Nevada Test Site (Based on 1986 Census Estimates) ... 13
5 Distribution of Family Milk Cows and Goats, by County (1988) 14
6 Distribution of Dairy Cows, by County (1988) 15
7 Distribution of Beef Cattle, by County (1988) 16
8 Distribution of Sheep, by County (1988) 17
9 Air Surveillance Network Stations (1988) 22
10 Standby Air Surveillance Network Stations (1988) 23
11 Noble Gas and Tritium Surveillance Network Sampling Locations 33
12 Weekly 85Kr Concentrations in Air by Station, 1988 Data 34
13 Network Weekly Average 85Kr Concentrations in Air, 1988 Data 42
14 Annual Network Average 85Kr Concentration 42
15 Milk Sampling Locations Within 300 Km of the NTS 45
16 Standby Milk Surveillance Network Stations 46
17 Strontium-90 Concentration in Pasteurized Milk Network Samples .... 46
18 Collection Sites for Animals Sampled, 1988 55
19 Average 90Sr Concentration in Animal Bone 56
20 Locations Monitored With TLDs 61
21 Personnel vs. Background TLD Results 62
22 Mean TLD Results: All Off Site Stations-1988 75
23 Mean TLD Results: Arizona Stations-1988 75
24 Mean TLD Results: California Stations-1988 75
25 Mean TLD Results: Nevada Stations -1988 76
26 Mean TLD Results: Utah Stations -1988 . . 76
27 Comparison of TLD and PIC Results-1988 76
28 Annual Exposure Rates as Measured by PICs -1988 79
29 Location of Families in the Off-site Human Surveillance Program 81
30 LTHMP Sampling Locations on the NTS 85
31 LTHMP Sampling Locations Near the NTS 86
32 Amchitka Island and Background Sampling Locations for the LTHMP . . 87
33 LTHMP Sampling Locations for Project Cannikin 88
34 LTHMP Sampling Locations for Projects Milrow and Long Shot 89
35 LTHMP Sampling Locations for Project Rio Blanco 90
36 LTHMP Sampling Locations for Project Rulison 91
37 LTHMP Sampling Locations for Project Dribble - Towns and
Residences 92
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FIGURES (Continued)
Number Page
38 LTHMP Sampling Locations for Project Dribble - Near GZ 93
39 LTHMP Sampling Locations for Project Dribble - Near Salt Dome 94
40 LTHMP Sampling Locations for Project Faultless 95
41 LTHMP Sampling Locations for Project Shoal 96
42 LTHMP Sampling Locations for Project Gasbuggy 97
43 LTHMP Sampling Locations for Project Gnome 98
vi
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TABLES
Number Page
1 Characteristics of Climatic Types in Nevada 9
2 Total Airborne Radionuclide Emissions at the Nevada Test Site
During 1988 20
3 Summary pf Analytical Results for Air Surveillance Network
Continuously Operating Stations -1988 25
4 Summary of Analytical Results for Air Surveillance Network
Standby Stations Operated 1 or 2 Weeks Per Quarter -1988 27
P^R 9*^Q
5 Concentrations of "°Pu and "03Pu in Composited Air
Samples -1988 29
6 Summary of Gross Beta Analysis for Air Surveillance Network -1988 .... 32
7 Summary of Analytical Results for the Noble Gas and
Tritium Surveillance Network -1988 39
8 Annual Average esKr Concentrations in Air, 1979-1988 41
9 Summary of Analytical Results for the Milk Surveillance
Network-1988 47
10 Analytical Results for the Standby Milk Surveillance Network-1988 ...... 51
11 Radionuclide Concentrations in Desert Bighorn Sheep Samples -1988 . . . 57
12 Radionuclide Concentration in Tissues From Mule Deer Collected
on the Nevada Test Site-1987/1988 59
13 Annual Summary TLD Results-Offsite Personnel-1988 64
14 Annual Summary TLD Results - Offsite Stations -1988 68
15 Pressurized Ion Chamber Readings -1988 78
16 LTHMP Tritium Results for the Monthly NTS Network for 1988 84
17 Water Sampling Locations Where Samples Contained Man-made
Radioactivity-1988 i 99
18 Tritium Results for the LTHMP-1988 101
19 Samples and Analyses for Duplicate Sampling Program-1988 116
20 Sampling and Analytical Precision -1988 117
21 EPA Quality Assurance Intercomparison Results-1988 118
22 Quality Assurance Results from DOE Program-1988 120
23 Quality Assurance Results for the Bioenvironmental Program-1988 ... 122
24 Summary of Analytical Procedures 127
25 Routine Monitoring Frequency, Sample Size, MDC and
Concentration Guides 130
vii
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LIST OF ABBREVIATIONS, ACRONYMS, AND CONVERSIONS
ABBREVIATIONS
A LARA
All
ASN
AVG
Bq
CFR
CG
Ci
CMS
CP-1
CY
d
DAC
DOE
DOE/NV
DQO
DRI
EML
EMSL-LV
EPA
eV
9
Gy
GZ
hr
HTO
L
LTHMP
m
mL
MDC
MSL
MSN
NIST
NGTSN
NNE
NNW
NRD
NTS
Pa
PIC
QA
QC
R
As Low as Reasonably Achievable
Annual Limits of Intake
Air Surveillance Network
Average
Becquerel, one disintegration per second
Code of Federal Regulations
Concentration Guide
Curie
Community Monitoring Station
Control Point One
Calendar Year
day
Derived Air Concentration
U.S. Department of Energy
Department of Energy, Nevada Operations Office
Data Quality Objectives
Desert Research Institute
Environmental Monitoring Laboratory
Environmental Monitoring Systems Laboratory, Las Vegas
U.S. Environmental Protection Agency
electron volt
gram
Gray, equivalent to 100 rad (1 J/kg)
Ground Zero
hour
tritiated water
liter
Long-Term Hydrological Monitoring Program
meter
milliliter
Minimum Detectable Concentration
Mean Sea Level
Milk Surveillance Network
National Institute of Standards and Technology
Noble Gas and Tritium Surveillance Network
North-Northeast
North-Northwest
Nuclear Radiation Assessment Division
Nevada Test Site
Pascal - unit of pressure
Pressurized ion chamber
Quality Assurance
Quality Control
Roentgen
continued
ix
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LIST OF ABBREVIATIONS, ACRONYMS AND CONVERSIONS
ABBREVIATIONS (Continued)
rad
rem
SD
SI
SOP
Sv
TLD
WHO
unit of absorbed dose, 100 ergs/g
dose equivalent, the rad adjusted for biological effect
Standard deviation
International System of Units
Standard Operating Procedure
Sievert, equivalent to 100 rem
thermoluminescent dosimeter
World Health Organization
PREFIXES
a
f
P
n
atto
femto =
pico =
nano =
10'18
ID'15
10'12
ID'9
f*
m
k
M
micro
mill!
kilo
mega
_
=
=
=
10'6
10'3
103
106
CONVERSIONS
Multiply
by
To Obtain
Concentration Guides
Ci/mL
Ci/mL
SI Units
rad
rem
pCl
10*
10
12
10
10
0.037
pCi/L
pCi/m3
Gray (Gy = 1 Joule/kg)
Sievert (Sv)
Becquerel (Bq)
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1.0 Abstract
This report describes the Off-Site Radiation Safety Program conducted during 1988 by the Environ-
mental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas
(EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region
surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, New Mexico,
and Mississippi. The surveillance program is designed to detect and document any changes in
radiation levels in the environs of nuclear test areas and to take the actions needed to protect the
health and well-being of the public in the event of any accidental release of radioactive con-
taminants. Information presented in this report includes the following results and interpretation of
data for 1988: the measurement of external exposure using thermoluminescent dosimeters (TLDs)
and pressurized ion chambers (PICs); air surveillance including radioactive particulates, noble and
reactive gases, and tritium; long-term hydrologlcal monitoring; milk surveillance; and the biological
monitoring of both animals and humans. Comparison of the measurements and sample analysis
results with background levels and with appropriate standards and regulations Indicated that no sig-
nificant radioactivity, of recent NTS origin, was detected off site by the various EPA monitoring net-
works and there was no significant exposure to the population living in the vicinity of the NTS. The
major contribution to population exposure came from naturally occurring background radiation
which yielded approximately 85 mrem/yr and worldwide fallout which accounted for about 0.14
mrem/yr.
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2.0 Introduction
The U.S. Atomic Energy Commission used the Nevada Test Site, between January 1951 and January
1975, for conducting nuclear weapons tests, nuclear rocket engine development, nuclear medicine
studies, and for other nuclear and non-nuclear experiments. Beginning in mid January 1975, these
activities became the responsibility of the U.S. Energy Research and Development Administration.
Two years later this organization was merged with other energy related agencies to form the U.S.
Department of Energy (DOE).
Atmospheric weapons tests were conducted
periodically at the Nevada Test Site from January
1951 through October 1958 followed by a test
moratorium which was in effect until September
1961. Since then all nuclear detonations at the NTS
have been conducted underground, with the
expectation of containment, except for the above
ground and shallow underground tests of Operation
Sunbeam and in cratering experiments conducted
under the Plowshare program between 1962 and
1968.
Prior to 1954, an off-site radiation surveillance
program was performed by personnel from the Los
Alamos Scientific Laboratory and the U.S. Army.
Beginning In 1954, and continuing through 1970,
this program was conducted by the U.S. Public
Health Service. Since 1970, the EPA has provided
an off-site Radiological Safety Program, both in
Nevada and at other nuclear test sites, under
interagency agreements with the DOE or its
predecessor agencies.
Since 1954, the objectives of the off-site radiation
surveillance program have included: the
measurement and documentation of the levels and
trends of any radiation or radioactive contaminants
in the environment in the vicinity of atomic testing
areas; and the determination as to whether the
testing is in compliance with radiation protection
standards, guidelines, and regulations. Off-site
levels of radiation and radioactivity are assessed by
sampling air and water; by measurements using
pressurized ion chambers and thermoluminescent
dosimeters; by sampling milk, food crops and other
vegetation, soil, and animals; and by biological
assay procedures.
Personnel with mobile monitoring equipment are
placed in areas downwind from the test site before
each test to provide immediate radiation
measurements; to obtain environmental samples;
and to initiate any action needed to protect the
public if radioactive contamination of the off-site
area should occur. Aircraft are also available to
rapidly monitor and sample any releases from a
test. Monitoring data obtained by the aircraft crew
Immediately after a test can be used to position
radiation monitors on the ground. Data from the
aircraft may also be used to estimate the amount of
activity released and the diffusion, dispersion, and
distribution of any airborne radioactive
contaminants.
Beginning with operation Upshot-Knothole in 1953,
a report, summarizing the monitoring data obtained
from each test series, was published by the U.S.
Public Health Service. For the reactor tests In 1959
and the weapons and Plowshare tests in 1962, data
were published only for the tests in which
detectable amounts of radioactivity were measured
in an off-site area. Publication of summary data for
each six-month period was initiated in 1964. In
1971, the Atomic Energy Commission implemented
a requirement, subsequently incorporated into
Department of Energy Order 5484.1 (DOE85), that
each agency or contractor Involved in major nuclear
activities provide an annual comprehensive
radiological monitoring report. Sixteen annual
reports were published by the Environmental
Protection Agency between 1971 and 1987. During
1988, Order 5481.1 was superseded by the General
Environmental Protection Program Requirements
(Order 5400.1) (DOE88) of the Department of
Energy. This is the first annual report prepared in
accordance with the new order. It summarizes the
radiation monitoring activities of the U.S.
Environmental Protection Agency in the vicinity of
the Nevada Test Site and at former nuclear testing
areas in the United States. Included in this report
are descriptions of the pertinent features of the
Nevada Test Site and its environs; summaries of the
dosimetry and sampling methods; a delineation of
analytical and quality control procedures; and the
results of environmental measurements. Where
applicable, dosimetry and analytical data are
compared with appropriate standards and
guidelines for the external and internal exposure of
humans to ionizing radiation.
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Although written to meet the terms of the federal, and local agencies Involved In protecting
interagency agreement between the Environmental the environment and the health and well-being of
Protection Agency and the Department of Energy the public; to Individuals and organizations
as well as the requirements of Order 5400.1, the concerned with environmental quality and the
data and information contained In this report also possible release of radioactive contaminants into
should be of interest and use to the citizens of the biosphere; and to scientists and students
Nevada, Utah and California who live in the Interested In the natural radiation environment,
downwind areas of the Nevada Test Site; to state, population dosimetry. or environmental monitoring.
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3.0 Summary
Purpose
"EPA is charged by Congress to protect the nation's land, air and water systems." (EPA89). This
policy applies to radioactive contamination of the biosphere and accompanying radiation exposure
of the population. To accomplish this and in agreement with the DOE policy of keeping radiation
exposure of the general public as low as reasonably achievable (ALARA), the EPA's Environmental
Monitoring Systems Laboratory in Las Vegas conducts an Off-Site Radiological Safety Program
around the DOE's Nevada Test Site. This program is conducted under an Interagency Agreement
between EPA and DOE. The main activity at the NTS is testing of nuclear devices, however, other
related projects are conducted as well.
The principle activities of the Off-Site Radiological
Safety Program are: routine environmental
monitoring for radioactive materials in various
media and for radiation in areas which may be
affected by nuclear tests, and protective actions in
support of the nuclear testing program. These
activities are conducted to document compliance
with standards, to Identify trends, and to provide
information to the public. This report summarizes
these activities for the calendar year of 1988.
In 1988 the Air Surveillance Network (ASM)
consisted of 31 continuously operating sampling
stations surrounding the NTS and 78 standby
stations (operated one or two weeks each quarter)
in all states west of the Mississippi River. During
1988, no airborne radioactivity related to current
nuclear testing at the NTS was detected on any
sample from the ASN. Other than naturally
occurring 7Be the only activity detected by this
network was 238Pu and 239Pu from worldwide
fallout.
The Noble Gas and Tritium Surveillance Network
(NGTSN) consisted of 18 stations off site (off the
NTS and exclusion areas) In 1988. No NTS-related
radioactivity was detected at any off-site station by
this network. As in previous years, radloxenon and
tritium levels in samples from the off-NTS stations
were generally below the minimum detectable
concentration (MDC).
The Long Term Hydrological Monitoring Program
(LTHMP) involves the analysis of ground and
surface water samples from sites of nuclear tests.
These wells and surface water showed only
background radlonuclide concentrations except for
those wells that had detectable activity in previous
years or those that had been spiked with
radionuclides for hydrological tests.
The Milk Surveillance Network (MSN) consisted of
29 locations within 300 kilometers of the NTS and
102 standby locations throughout the western
United States. StrontIum-89 above the minimum
detectable activity was found In one MSN sample.
One of the standby samples collected in Minnesota
had detectable Cs. Tritium concentrations in
milk were at background levels. Strontlum-90 from
worldwide fallout from atmospheric testing
continued the slow downward trend documented
over the past several years.
Other foods are analyzed regularly, most of which
are meat from domestic or game animals. The
radlonuclide most frequently found In the edible
portion of the sampled animals is 137Cs. However,
Its concentration has been near the MDC since
1968. Strontlum-90 in samples of animal bone
remain at very low levels as does 239Pu In both
bone and liver samples.
External Exposure
External exposure Is monitored by a network of
TLDs at 154 fixed locations surrounding the NTS
and by TLDs worn by 61 off-site residents. With
one exception, there were no exposures above
natural background when tests for statistical
significance of variation were applied. This net
exposure above natural background was at Warm
Springs, NV, and was determined to be due to
higher levels of naturally occurring radioactivity In
the ground water at that location (see Section
5.2.6). The range of background exposures
measured, varied with altitude and soil constituents,
is similar to the range of such exposures found In
other areas of the U.S.
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Dose Assessment
The maximum dose calculated for an adult living In
Nevada using the radionuclides measured in
samples collected by the monltorina networks
would have been about 0.1 ^wrem (10 mSv) for
1988. No radioactivity originating on the NTS was
detectable by the monitoring networks; therefore,
no dose assessment can be made. However,
based on the NTS releases reported in Table 2,
atmospheric dispersion calculations (AIRDOS/EPA)
indicate that the highest individual dose would have
been 0.01 ^rem (10"4 fiSv), and the,dose to the
population within 80 km of Control Point One (CP-1)
would have been 4.7 x 10"5 person-rem (4.7 x 10
person-Sv), The person receiving the highest dose
was also exposed to 138 mrem from natural
background radiation.
In the unlikely event that a certain mule deer had
been collected by a hunter rather than by EPA
personnel, that hunter could have received a dose
equivalent of 100 mrem (1.0 mSv) if he ate all the
liver and meat from the deer.
Internal Exposure
Internal exposure is assessed by whole body
counting, using a single germanium detector, lung
counting using semi-planar detectors and bioassay
using radiochemlcal procedures. In 1988, counts
were made on 188 Individuals from the following:
100 off-site areas around the Nevada Test Site,
EMSL-LV Laboratory, EG&G facilities throughout
the United States, five DOE contractors and
members of the general public concerned about
possible radiation exposure. No nuclear test related
radioactivity was detected. In addition, physical
examinations of the off-site residents revealed a
normally healthy population consistent with the age
and sex distribution of that population.
Community Monitoring Stations (CMS)
The Community Monitoring Stations are operated
for the Environmental Protection Agency,
Department of Energy and the Desert Research
Institute by local residents. Fifteen of the eighteen
CMS became operational in 1982, the sixteenth,
seventeenth and eighteenth in 1988. Each station is
an Integral part of the Air Surveillance Network
(ASN), Noble Gas and Tritium Surveillance Network
(NGTSN), and Thermoluminescent Doslmetry
(TLD) network, in addition they are equipped with a
Pressurized Ion Chamber (PIC) connected to a
gamma rate recorder, and a microbarograph.
Samples and data from these stations are analyzed
and reported by the EPA at EMSL-LV. Data is also
Interpreted and reported by Desert Research
Institute, University of Nevada. Data from these
stations are reported herein as a part of the
networks In which they participate. All
measurements for 1988 were within the normal
background range for the United States.
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4.0 Description of the Nevada Test Site
A. N. Jarvis
The principle activity at the Nevada Test Site (NTS) is the testing of nuclear devices to aid in the
development of nuclear weapons, proof testing of weapons, and weapons safety and effects
studies. Thus, the major activity of the EPA's Off-Site Radiological Safety Program is radiation
monitoring around the NTS. This section is included to provide readers with an overview of the
climate, geology and hydrology, as well as with land uses, in this generally arid and sparsely popu-
lated area of the southwest. The Information included should provide a better understanding of the
environment in which nuclear testing and monitoring activities take place, the reasons for the loca-
tion of instrumentation, the weather extremes to which both people and equipment are subject, and
the distances traveled by field monitors In collecting samples and maintaining equipment.
Location
The NTS is located in Nye County, Nevada, with its
southeast corner about 90 km northwest of Las
Vegas (Figure 1). It has an area of about 3,500
square km and varies from 40 to 56 km In width
(east-west) and from 64 to 88 km in length
(north-south). This area consists of large basins or
flats about 900 to 1,200 m above mean sea level
(MSL) surrounded by mountain ranges rising 1,800
to 2,300 m above MSL
The NTS is surrounded on three sides by exclusion
areas, collectively named the Nellis Air Force Base
Range Complex, which provide a buffer zone
between the test areas and public lands. This buffer
zone varies from 24 to 104 km between the test area
and land that Is open to the public. Depending
upon wind speed and direction, from 2 to more than
6 hours will elapse before any release of airborne
radioactivity could pass over public lands.
Climate
The climate of the NTS and surrounding area Is
variable, due to its wide range In altitude and its
rugged terrain. Generally, the climate is referred to
as continental arid. Throughout the year, there Is
insufficient water to support the growth of common
food crops without irrigation.
Climate may be classified by the types of vegetation
indigenous to an area. According to Houghton et
al. (H075), this method of classification of dry
condition, developed by Doppen, is further
subdivided on the basis of temperature and severity
of drought. Table 1 (H075) summarizes the
characteristics of climatic types for Nevada.
According to Quiring (QU68), the NTS average
annual precipitation ranges from about 10 cm at the
lower elevations to around 25 cm on the higher
elevations. During the winter months, the plateaus
may be snow-covered for a period of several days
or weeks. Snow is uncommon on the flats.
Temperatures vary considerably with elevation,
slope, and local air currents. The average dally high
(low) temperatures at the lower altitudes are around
SOT (25°F) in January and 95°F (55°F) in July, with
extremes of 120°F and -15°F. Corresponding
temperatures on the plateaus are 35°F (25°F) in
January and 80°F (65°F) in July with extremes of
115°Fand-306F.
The wind direction, as measured on a 30 m tower at
an observation station about 9 km NNW of Yucca
Lake, is predominantly northerly except during the
months of May through August when winds from
the south-southwest predominate (QU68). Because
of the prevalent mountain/valley winds in the basins,
south to southwest winds predominate during
daylight hours of most months. During the winter
months southerly winds have only a slight edge
over northerly winds for a few hours during the
warmest part of the day. These wind patterns may
be quite different at other locations on the NTS
because of local terrain effects and differences in
elevation.
Geology and Hydrology
Two major hydrologic systems shown in Figure 2
exist on the NTS (ERDA77). Ground water in the
northwestern part of the NTS or in the Pahute Mesa
area flows at a rate of 2 m to 180 m per year to the
south and southwest toward the Ash Meadows
Discharge Area in the Amargosa Desert. Ground
water to the east of the NTS moves from north to
south at a rate of not less than 2 m nor greater than
220 m per year. Carbon-14 analyses of this eastern
ground water indicate that the lower velocity is
-------
Figure 1. Location of the Nevada Test Site (NTS).
8
-------
Climate Type
Alpine
tundra
Humid
continental
Subhumid
continental
Mid-latitude
steppe
Mid-latitude
desert
Low-latitude
desert
Table 1.
Characteristics of Climatic Types In Nevada
(from Houghton et al. 1975)
Mean Temperature
°C
, (°F)
Winter Summer
-18" to -9°
(0° to 15°)
-12°tO-1°
(10° to 30")
-12°tO-1°
(10° to 30°)
-7° to 4°
(20° to 40°)
-7° to 4°
(20° to 40°)
-4° to 10"
(40° to 50°)
* Limits of annual precipitation overlap
4° to 10"
(40° to 50°)
10° to 21°
(50° to 70°)
10° to 21°
(50° to 70°;
18° to 27°
(65° to 80°)
18° to 27°
(65° to 80°)
27° to 32°
(80° to 90°)
Annual
Precipitation
cm
(Inches)
Total* Snowfall
38 to 114
(15 to 45)
6410114
(25 to 45)
30 to 64
(12 to 25)
15 to 38
(6 to 15)
8 to 20
(3 to 8)
5 to 25
(2 to 10)
Medium
to
heavy
Heavy
Moder-
ate
Light
to
moderate
Light
Neglig-
ible
Dominant
Vegetation
Alpine
meadows
Pine-fir
forest
Pine or
scrub
woodland
Sagebrush,
grass,
scrub
Grease-
wood,
shadscale
Creosote
bush
%
of
Area
-
1
15
57
20
7
because of variations in temperature which affect the water balance.
nearer the true value. At Mercury Valley in the
extreme southern part of the NTS, the eastern
ground water flow shifts south-westward toward the
Ash Meadows Discharge Area.
Land Use of NTS Environs
Figure 3 is a map of the off-NTS area showing a
wide variety of land uses, such as farming, mining,
grazing, camping, fishing, and hunting within a
300-km radius of the NTS. For example, west of the
NTS, elevations range from 85 m below MSL in
Death Valley to 4,420 m above MSL in the Sierra
Nevada Range. Parts of two major agricultural
valleys (the Owens and San Joaquin) are included.
The areas south of the NTS are more uniform since
the Mojave Desert ecosystem (mid-latitude desert)
comprises most of this portion of Nevada,
California, and Arizona. The areas east of the NTS
are primarily mid-latitude steppe with some of the
older river valleys, such as the Virgin River Valley
and Moapa Valley, supporting irrigation for
small-scale but intensive farming of a variety of
crops. Grazing is also common in this area,
particularly to the northeast. The area north of the
NTS is also mid-latitude steppe, where the major
agricultural activity is grazing of cattle and sheep.
Minor agriculture, primarily the growing of alfalfa
hay, is found in this portion of the State within 300
km of the NTS Control Point-1 (CP-1). Many of the
residents grow or have access to locally grown
fruits and vegetables.
Many recreational areas, in all directions around the
NTS (Figure 3) are used for such activities as
hunting, fishing, and camping. In general, the
camping and fishing sites to the northwest, north,
and northeast of the NTS are utilized throughout the
-------
\
\
Panute Mesa
Ground Water
System
Ash Meadows
Ground Water System
10 20 30
Scale in Kilometers
•>•—>• Flow Direction
— — Ground Water System Boundaries
, —.— Silent Canyon Caldera
Timber Mountain Caldera
5/89
Figure 2. Ground Water Flow Systems Around the Nevada Test Site
10
-------
Camping &
Recreational Areas
O Hunting
• Fishing
O Mines
A Oil Fields
JLAKE * King man
MOJAVE
!A
Lake Havasu
Figure 3. General Land t/se Within 300 km of the Nevada Tesf S/fe.
11
-------
year except for the winter months. Camping and
fishing locations to the southeast, south, and
southwest are utilized throughout the year. The
hunting season is from September through January.
Population Distribution
Figure 4 shows the current population of counties
surrounding the NTS based on 1986 Bureau of
Census estimates (DOC86). Excluding Clark
County, the major population center (approximately
569,500 in 1986), the population density within a
150 km radius of the NTS is about 0.5 persons per
square kilometer. For comparison, the 48
contiguous states (1980 census) had a population
density of approximately 29 persons per square
kilometer. The estimated average population
density for Nevada In 1980 was 2.8 persons per
square kilometer.
The off-site area within 80 km of CP-1 (the area In
which the dose commitment must be determined
for the purpose of this report) Is predominantly
rural. Several small communities are located in the
area, the largest being in the Pahrump Valley. This
growing rural community, with an estimated
population of about 6,000 is located about 72 km
south of the NTS CP-1. The Amargosa Farm Area,
which has a population of about 1,200, is located
about 50 km southwest of CP-1. The largest town in
the near off-site area is Beatty, which has a
population of about 2,000 and is located
approximately 65 km to the west of CP-1. A report
by Smith and Coogan (EPA84) was published in
1984 which summarized the population distribution
within selected rural areas out to 200 kilometers
from the Control Point on the NTS.
The Mojave Desert of California, which includes
Death Valley National Monument, lies along the
southwestern border of Nevada. The National Park
Service (NPS80) estimated that the population
within the Monument boundaries ranges from a
minimum of 200 permanent residents during the
summer months to as many as 5,000 tourists and
campers on any particular day during the major
holiday periods in the winter months, and as many
as 30,000 during "Death Valley Days" in the month
of November. The largest town and contiguous
populated area (about 40 square miles) In the
Mojave Desert Is Barstow, located 265 km
south-southwest of the NTS. with a 1986 population
of about 20,250. The next largest populated area is
the Ridgecrest-China Lake area, which has a
current population of about 25,000 and is located
about 190 km southwest of the NTS. The Owens
Valley, where numerous small towns are located,
lies about 50 km west of Death Valley. The largest
town in Owens Valley is Bishop, located 225 km
west-north-west of the NTS, with a population of
about 3,500.
The extreme southwestern region of Utah is more
developed than the adjacent part of Nevada. The
largest community is St. George, located 220 km
east of the NTS, with a population of 19,800. The
next largest town, Cedar City, with a population of
12,380, is located 280 km east northeast of the NTS.
The extreme northwestern region of Arizona is
mostly range land except for that portion in the Lake
Mead Recreation Area. In addition, several small
communities lie along the Colorado River. The
largest towns in the area are Bullhead City, 165 km
south-southeast of the NTS, with a 1986 population
estimate of 18,740 and Kingman, located 280 km
southeast of the NTS, with a population of about
10,760. Figures 5 through 8 show the domestic
animal populations in the counties near the NTS.
12
-------
Washoe
224,600 "*•
kk
Humboldt
10,600
1
Pershing jr
3,700 /
NEVADA •
1
Elko I
21 ,900 •
'
/ Lander
•i— y A 9nn
!
\ •
Fnrpkal *
UTAH
Box Elder
36,800
-^
Tooele
29,200
White Pine
7,600
Millard
14,200
Douglas
23,200
Beaver
5,100
Mono \Esmeralda
,200 V 1 ,300
^Washington K?"e
38,600
0 50 100 150
Scale in Kilometers
I
San Bernardino
1,139,100
Q%^, \ Mojave
•^l 76'600
*VV
5/89
Figure 4. Population of Arizona, California, Nevada and Utah Counties Near the Nevada Test Site
(Based on 1986 Census Estimates).
13
-------
Washoe
7(23)
Storey
0(4) _
Carson I
City
0(2)
Douglas
3(3)
Lyon
7(16)
Hum6oldt
50 (20)
Pershing )r
f 12(0) /
/Lan
- L / 16
I C
I, Churchill \
**f\ 28(26) /
NEVADA
Elko
135(6)
der
(0)
I
Eureka!
30(15))
( White Pine
/ 26 (8)
UTAH
Box Elder
30(12)
.**
Tooele
25(4)
Juab ,
•
Millard
Nye
48(115)
Mono ^/Esmeralda
8(4) * 8(4)
Lincoln
30(35)
•Washington
80 (8)
NELLIS
AFB RANGE
COMPLEX
50 100 150
Scale in Kilometers
San Bernardino
20 (290)
00 Cows
(00) Goats
5/89
Figure 5. Distribution of Family Milk Cows and Goats, by County (1988).
14
-------
Washoe
700
Douglas
2,'400
Lyon
1,800
Beaver
2,800
Mono \/tsmeralda
NELLIS
AFB RANGE —
COMPLEX
Washington
< 500
Scale in Miles
50 100
50 100 150
Scale in Kilometers
San Bernardino
193,000
Figure 6. Distribution of Dairy Cows, by County (1988).
15
-------
Washoe
27,600
Storey
100
Carson I
City
1,100
Douglas
15,000
Lyon
36,500
Kh.
Humboldt
58,000
\
Pershing K
NEVADA
Elko
1 56,400
21,000 /
/ Lander
-, / 25.000
\i Churchill \
£7l 47.000 /
/ \ L
\
\
Eureka I
21,800?
( White Pine
/ 25,500
I
•
1
1
1
•
1
1"
1
•
t
•
1
UTAH
Box Elder
28,300
-^
Tooele
1 5,000
Juab
8,400
Millard
17,100
Mono %/Esmeralda
*
0 50 100 150
Scale in Kilometers
San Bernardino
7,700
Figure 7. Distribution of Beef Cattle, by County (1988).
16
-------
Washoe
3,000
Churchill
4,900
White Pine
19,700
Millard
9,000
Douglas
6,000
Mineral
5,000
Mono \/Esmeralda
Lincoln
<500
7,500 «V <5oo
NELUS
AFB RANGE
COMPLEX
Washington
I 1,500
50 100 150
Scale in Kilometers
Kern
155,000
San Bernardino
10,600
Figure 8. Distribution of Sheep, by County (1988).
17
-------
5.0 Radiological Safety Activities
The radiological safety activities of the EMSL-LV are divided into two major areas: special test sup-
port and routine environmental surveillance that includes pathways monitoring, internal and exter-
nal exposure monitoring. Both of these activities are designed to detect any increase in
environmental radiation which might cause exposure to individuals or population groups so that
protective actions may be taken, to the extent feasible. These activities are described in the follow-
ing portions of this report.
5.1 Special Test Support
C. A. Fontana
During all nuclear tests mobile monitoring
teams are deployed around the NTS. They are
prepared to assist in directing protective ac-
tions for off-site residents should that become
necessary. Prior to the test they ascertain the
locations of residents, work crews and domestic
animal herds, and obtain information relative to
residents in communities and remote areas.
Monitors, equipped with radiation survey instru-
ments, gamma exposure-rate recorders, TLDs,
portable air samplers, and supplies for collect-
ing environmental samples, are prepared to con-
duct a monitoring program as directed from the
NTS CP-1 via two-way radio communications.
**•.,',•»'•"., ' - .*?
19
-------
If an underground nuclear test is expected to cause
ground motion detectable off site, then EPA
monitors are stationed at locations where
hazardous situations might occur, such as
underground mines. At these locations, occupants
are notified of potential hazards so they can take
precautionary measures.
Professional EPA personnel serve as members of
the Test Controller's Advisory Panel to provide
advice on possible public and environmental impact
of each test and on feasible protective actions in the
event that an accidental release of radioactivity
should occur.
An EG&G cloud sampling and tracking aircraft is
always flown over the NTS to obtain samples,
assess total cloud volume and provide long range
tracking in the event of a release of airborne
radioactivity. A second aircraft is also flown to
gather meteorological data and to perform cloud
tracking. Information from these aircraft can be
used in positioning the mobile radiation monitors.
During the calendar year of 1988, EMSL personnel
were deployed for all underground nuclear tests
conducted at the NTS, none of which released
radioactivity that could be detected off site.
5.2 Routine Environmental
Surveillance
Airborne Releases of Radioactivity at the NTS
During 1988
S. C. Black
All nuclear detonations during 1988 were con-
ducted underground and were contained.
Releases of low-level radioactivity occurred
during re-entry drilling, seepage through fis-
sures in the soil or purging of tunnel areas.
Table 2 shows the total quantities of
radionuclides released to the atmosphere, as
reported by the DOE Nevada Operations Office
(DOE89). Because these releases occurred
throughout the year and because of the distance
from the points of releases to the nearest off-site
sampling station, none of the radioactive
material listed in this table was detected off site.
To detect any radioactivity that might escape from
the NTS, including that listed in Table 2, a routine
surveillance program is conducted. This program
includes pathways monitoring that consists of air,
water, and milk surveillance networks surrounding
Table 2 Total Airborne Radionuclide Emissions at the NTS During 1988
Radionuclide
Half-Life (days)
Quantity Released (Ci)
dH
131 |
133 |
133Xe
133m
Xe
135
Xe
4511
8.04
0.86
5.24
2.19
0.38
68.2
3.2 X10'5
1.1X10"4
18.1
0.44
8.0
20
-------
the NTS and a limited animal sampling program. In
addition, external and internal exposures of off-site
populations are assessed using state-of-the-art
dosimetry equipment. The following portions of this
report detail the results of these surveillance
programs.
5.2.1 Air Surveillance Network (ASN)
V. E. Niemann
Network Design
The ASN monitors an important route of human
exposure to radionuclides, inhalation of airborne
materials. The concentration and the source
must both be determined if appropriate correc-
tive actions are to be taken. The ASN is
designed to monitor the areas within 350 km of
the NTS with some concentration of stations in
the prevailing downwind direction (Figure 9).
Station location is dependent upon the
availability of electrical power and, at stations
distant from the NTS, of a resident willing to
operate the equipment. This continuously
operating network is supplemented by a standby
network which covers the contiguous states
west of the Mississippi river (Figure 10).
Methods
During 1988, the ASN consisted of 31 continuously
operating sampling stations and 78 standby
stations. The air sampler at each station was
equipped to collect both paniculate radionuclides
on prefilters and reactive gases on charcoal
cartridges. The prefilters and charcoal cartridges
from all active stations were routinely analyzed. The
prefilters from the standby stations were routinely
21
-------
'#„
Lathrop Wells
Furnace Creek | *\
Death Valley Jet. |f\ m
X
Shoshone9
) Community Monitoring Stations (18)
I Other Air Sampling Stations (13)
B/89
VI
50 100
Seal* in Kilonwurt
Figure 9. Air Surveillance Network Stations (1988).
22
-------
North Dakota Minnesota
A A
Scale in Miles
0 100 300
500
100 300 500 700
Scale in Kilometers
A Stand-by ASN \
Stations (78) f
5/89
Figure 10. Standby Air Surveillance Network Stations (1988).
23
-------
analyzed; the charcoal cartridges from the standby
stations were not routinely analyzed.
Samples of airborne participates were collected at
each active station on 5-cm diameter glass-fiber
filters at a flow rate f 82 m3 per day. Filters were
changed after sampler operation periods of two to
three days (160 to 250 m3). Activated charcoal
cartridges placed directly behind the filters to collect
gaseous radloiodine were changed at the same
time as the filters. The standby network was
activated for one week per quarter at most
locations. The standby samplers were Identical to
those used at the active stations and were operated
by state and municipal health department personnel
or by other local residents. All analytical work was
done at the EMSL-LV.
Results
During 1988, no airborne radioactivity related to
current nuclear testing at the NTS was detected on
any sample from the ASN. Throughout the network,
7Be was the only nuclide detected by gamma
spectroscopy. The principal means of 7Be
production is from spallatlon of 160 and 14N by
cosmic rays In the atmosphere. Tables 3 and 4
summarize the data from the ASN samples. All
time-weighted averages ("Wt-Avg" in the tables) are
less than one percent of the Concentration Guide
(see Section 10) for exposure to the general public.
However, these guides do not apply to naturally
occurring radionuclides.
Two additional analyses are performed on the
samples from the ASN: a gross beta analysis of the
filters from five stations, and 238Pu and 239Pu
analysis of composited filters from fourteen Western
states.
Once each quarter, the prefilters from selected
stations are composited and analyzed for 238Pu and
239Pu. Those from the stations at Las Vegas,
Lathrop Wells, and Rachel, Nevada, and Salt Lake
City, Utah, are composited as monthly samples and
submitted quarterly for analysis. The other samples
consist of composited filters from two standby
stations in each of fourteen states. The results of the
238Pu and 239Pu analyses are shown in Table 5.
The January composite from Lathrop Wells,
Nevada, yielded a Pu result above the MDC (and
greater than the 2-sigma error). The June
composite from Rachel, Nevada, yielded results
above the MDC (and greater than the 2-sigma error)
for 238Pu and Pu. Because work done on the
Plutonium analytical procedure during the first
quarter of 1988 produced an Increased yield, an
improved (lower) MDC was achieved. These very
small amounts of plutonium may have been present
over time but, until improved sensitivity was
achieved, it was impossible to quantitate them.
The gross beta analysis Is used to detect trends In
atmospheric radioactivity since this analysis is more
sensitive than gamma spectrometry for this
purpose. For this study, five stations around the
NTS are used. The three filters per week from each
station are analyzed for gross beta activity after a
seven day delay to decrease the contribution from
naturally-occurring thoron daughter activity. The
data suggest little significant difference among
stations and Indicate a relatively stable
concentration compared to previous years. A
summary of the data is shown in Table 6.
5.2.2 Noble Gas and Tritium Surveillance Net-
work (NGTSN)
E. A. Thompson
Network Design
There are several sources for the radionuclides
monitored by this network. Noble gases are
emitted from nuclear power plants, propulsion
reactors, reprocessing facilities, and nuclear ex-
plosions. Tritium is emitted from the same sour-
ces and is also produced naturally. The
monitoring network will be affected by all these
sources, but must be able to detect NTS emis-
sions. As a part of the monitoring network,
samplers are located around the NTS, particular-
ly in drainage-wind channels leading from the
test areas. Others are located farther from the
test site and outside of drainage-wind channels
to provide more complete coverage, especially
for populated areas. In 1988 this network con-
sisted of 18 stations as shown in Figure 11. This
figure also shows the location of the temporary
station operated at Mammoth Lakes, CA, during
1987 and 1988.
Methods
Samples of air are collected by directly
compressing air into storage tanks. The equipment
continuously samples air over a 7-day period and
stores approximately 1 m3 of air in two tanks. The
tanks are exchanged weekly and returned to the
24
-------
TABLE 3. Summary of analytical results for Air Surveillance
CONTINUOUSLY OPERATING STATIONS - 1988
Sampling Location
Death Valley Jet CA
Furnace Creek CA
Shoshone CA
Alamo NV
Austin NV
Beatty NV
Caliente NV
Stone Cabin Ranch NV
Blue Eagle Ranch NV
ElyNV
Goldfield NV
Groom Lake NV
Hiko NV
Indian Springs NV
Las Vegas NV
Lathrop Wells NV
Overton NV
Pahrump NV
Pioche NV
Scotty's Jet NV
Sunnyside NV
Rachel NV
No. Days
Detected
/Sampled
37/335
47/353
13/348
7/346
28/349
18/352
9/303
8/342
10/345
8/350
5/349
26/357
9/349
6/351
9/352
26/341
6/348
20/343
11/340
22/329
12/343
10/354
Radio-
Nuclide
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
Network
Radioactivity Cone.
(pCi/m3)
Max
0.78
1.6
1.1
0.73
0.65
1.9
0.47
0.95
0.93
0.64
0.55
0.34
0.57
0.61
1.0
0.52
1.4
1.5
0.86
0.82
1.1
0.49
Min
0.16
0.15
0.18
0.26
0.17
0.29
0.17
0.39
0.33
0.37
0.26
0.058
0.24
0.23
0.14
0.099
0.26
0.22
0.24
0.20
0.43
0.24
WT-Avg*
0.047
0.079
0.020
0.0096
0.032
0.034
0.0098
0.013
0.014
0.010
0.0054
0.0082
0.011
0.0073
0.0088
0.018
0.011
0.036
0.015
0.030
0.022
0.010
(continued)
25
-------
TABLES. (Continued)
. Sampling Location
No. Days
Detected
/Sampled
Radio
Nuclide
Radioactivity Cone.
(pCi/m3)
Max
Min WT-Avg*
Tonopah NV
TTRNV
Fallinl's fTwn Spgs)
Ranch NV
Cedar City UT
Delta UT
Milford UT
St George UT
Salt Lake City UT
11/355
63/238
11/351
18/348
26/344
26/345
29/323
27/344
7Be
7Be
7Be
7Be
7Be
7Be
7Be
0.68
1.0
0.77
0.68
0.81
0.67
1.0
1.1
0.23
0.14
0.19
0.29
0.30
0.21
0.28
0.21
0.013
0.13
0.015
0.026
0.037
0.029
0.062
0.042
* Wt-Avg Is a Time-Weighted Average over the location's entire sampling period.
The following station had negligible gamma-spectra:
Nyala NV (sampled for 353 days.)
26
-------
TABLE 4. Summary
STANDBY STATIONS -
Sampling Location
Klngman AZ
Alturas CA
Bishop CA
Indio CA
Rldgecrest CA
Grand Jet CO
Great Falls MT
Currant NV -
Angleworm Ranch
Duckwater NV
Desert Oasis Resort NV
Round Mountain NV
Carlsbad NM
Shlprock NM
Williston ND
Burns OR
Rock Springs WY
of analytical
OPERATED
No. Days
Detected
/Sampled
6/28
2/28
3/28
2/26
3/14
5/24
3/28
3/35
26/26
5/7
2/24
2/21
3/21
4/22
3/28
3/28
results for Air Surveillance Network
1 OR 2 WEEKS PER QUARTER - 1988
Radio-
Nuclide
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
7Be
* Wt-Avg is a Time-Weighted Average over the location's entire
Radioactivity Cone.
(pCi/m3)
Max Min
0.41 0.23
0.42 0.42
0.45 0.45
0.035 0.035
0.22 0.22
0.24 0.24
0.24 0.24
0.64 0.64
0.74 0.30
0.21 0.21
1.1 1.1
0.80 0.80
0.69 0.69
0.39 0.39
0.59 0.59
0.43 0.43
sampling period.
WT-Avg*
0.069
0.030
0.048
0.0027
0.050
0.025
0.025
0.054
0.36
0.15
0.088
0.076
0.098
0.068
0.063
0.046
(continued)
27
-------
TABLE 4. (Continued)
The following stations had negligible gamma-spectra: () Is number of days operated.
Globe AZ (27 days)
Tucson AZ (30 days)
Winslow AZ (26 days)
Yuma AZ (27 days)
Little Rock AR (20 days)
Baker CA (20 days)
Chico CA (29 days)
Lone Pine CA (28 days)
Needles CA (22 days)
Santa Rosa CA (28 days)
Cortez CO (21 days)
Denver CO (27 days)
Mountain Home ID (21 days)
Boise ID (28 days)
Pocatello ID (28 days)
Fort Dodge IA (32 days)
Iowa City IA (29 days)
Dodge City KS (28 days)
Monroe LA (28 days)
Minneapolis MN (28 days)
Clayton MO (28 days)
Joplln MO (28 days)
Kalispell MT (29 days)
Miles City MT (28 days)
North Platte NE (20 days)
Battle Mountain NV (20 days)
Blue Jay NV (9 days)
Currle NV - Currie Maintenance Station (19 days)
Elko NV - Phillips 66 Truck Stop (21 days)
Eureka NV (26 days)
FallonNV(18days)
Lovelock NV (14 days)
Lund NV (23 days)
Mesquite NV (27 days)
Reno NV (21 days)
Uhalde's Ranch NV (58 days)
Wells NV (19 days)
Winnemucca NV (21 days)
Albuquerque NM (21 days)
Bismarck ND (28 days)
Fargo ND (19 days)
Muskogee OK (20 days)
Medford OR (32 days)
Rapid City SD (21 days)
AmarilloTX(21days)
Austin TX (21 days)
Midland TX (28 days)
Tyler TX (36 days)
Bryce Canyon UT (20 days)
Enterprise UT (35 days)
Garrison UT (16 days)
Logan UT (21 days)
Parowan UT (16 days)
Vernal UT (29 days)
Wendover UT (21 days)
Seattle WA (19 days)
Spokane WA (21 days)
Worland WY (26 days)
28
-------
Table 5. Concentrations of 238 Pu and 239 Pu-Composited Air Samples - 1988
COLLECTION
DATE
SAMPLING LOCATION 1988
AZ COMPOSITE (Winslow& Tucson)
03/09
06/22
07/27
11/02
CA COMPOSITE (Bishop & Rldgecrest)
02/24
06/17
07/29
10/31
CO COMPOSITE (Denver & Cortez) ............
02/29
06/22
07/29
12/12
ID COMPOSITE (Boise & Mountain Home)
03/14
06/29
07/29
10/31
MO COMPOSITE (Clayton & Joplln)
02/29
06/29
08/31
11/22
MT COMPOSITE (Great Falls & Miles Citv) ...
02/29
06/29
08/31
12/14
NV COMPOSITE (Las Veaas^
01/29
02/29
03/30
CONG. ±
238p
(aCI/m3)
-13 ± 25
-1.6 ± 13
-0.5 ± 6.5
-3.6 ± 39
5.3 ± 11
-4.3 ± 17
-7.5 ± 5.8
-38 ±42
-4.3 ± 16
-11 ± 29
-1.1 ± 14
-51 ± 36
0.5 ± 17
-12 ± 32
-7.5 ± 5.7
-26 ± 35
-6.1 ± 11
-19 ± 75
-8.9 ± 6.9
NOT ANALYZED
-4.6 ± 8.6
-8.7 ± 23
-0.8 ± 11
-3.3 ± 2.5
0.2 ± 8.7
LOST
-5.7 ± 15
2 SIGMA
239 pu
(aCI/m3)
-1.4 ± 7
0 ± 7.6
-5 ± 3.2
-10 ± 15
9.3 ± 10
2.1 ± 10
2.2 ± 19
-5.5 ± 1.9
-1.0 ± 11
-3.6 ± 16
-4.3 ± 14
-5.1 ± 17
-3.3 ± 12
0 ±19
-11 ± 7
-8.7 ± 12
LOST
9.3 ± 43
-13 ± 8
NOT ANALYZED
-1.7 ± 6.1
0 ±13
-8.2 ± 5.3
-4.6 ± 3
6.9 ± 7.5
LOST
0 ± 8.9
(continued)
29
-------
Tables. (Continued)
COLLECTION
DATE
SAMPLING LOCATION 1988
04/29
05/03
06/19
07/29
08/31
09/30
10/31
11/30
12/30
NV COMPOSITE (LATHROP WELLS)
01/30
02/29
03/30
04/29
05/24
06/29
07/28
08/31
09/19
10/28
11/30
12/30
NV COMPOSITE (RACHEL)
01/31
02/28
03/03
04/30
05/31
06/28
07/31
08/30
09/30
10/30-
11/29
12/30
NM COMPOSITE (Albuquerque & Carlsbad)
03/30
06/29
12/12
CONC. ±
238 p
(aCI/m3)
-1.5
-1.2
-4.3
-0.6
-0.2
6.2
-9.1
-8.5
-8.6
0
43
-4.7
-2.5
5.9
3.2
-3.3
0.9
1.4
-3.8
-1.9
-2.2
-21
5
-1.6
5.6
-2.9
12
5.9
2.1
-0.1
-2
-1.9
-10
-1.6
-3.1
-4.5
±
±
±
±
±
±
±
±
±
±
±
jh
±
±
±
±
;*;
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
12
9.9
11
8.5
2.9
12
10
11
11
14
72
18
10
12
8.6
2.5
3.0
4.9
6.4
1.4
1.7
40
8.5
6.3
11
12
11**
6.1*
4
1.5
1.6
1.4
14
14
25
3.4
2 SIGMA
239 p
u.
(aCi/m*)
4.4
i.2
0
1.3
-2.2
1.1
-1.3
0
-1.4
27
6.1
-1
1.3
7.4
0
-1.9
2.4
-2.8
-1.5
-1.1
-3.2
9
3.1
1.4
7
0
47
4.1
1.5
2.3
2.3
-2.7
0
-2.8
0
-6.4
±
±
±
Hh
±
±
Hh
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
6.9
5.7
6.7
12
1.4
10
4.5
5.7
5
15**
51
13
5.8
7.9
4.9
6.3
4.3
1.8
2.2
3.7
2
28
6
4.4
7.5
6.8
19**
5.6*
4.1
3.2*
6.3
1.7
6.9
9.9
14
4.1
(continued)
30
-------
Table 5. (Continued)
COLLECTION
DATE
SAMPLING LOCATION 1988
ND COMPOSITE (Bismarck & Fargo)
03/28
06/29
09/19
12/12
OR COMPOSITE (Burns & Medford)
03/21
09/21
12/12
TX COMPOSITE (Austin & Amarillo)
03/31
06/29
09/18
12/23
UT COMPOSITE (Logan & Vernal)
03/30
06/29
12/11
UT COMPOSITE (SALT LAKE CITY)
01/29
02/26
03/30
04/29
05/30
06/29
07/29
08/31
09/30
10/31
11/30
12/30
WA COMPOSITE (Seattle & Spokane) . . ...
03/30
06/27
12/12
CONC. ±
238 p
(aCI/m3)
-8.4 ± 16
-6.8 ± 27
-7.2 ± 5.5
-4.8 ± 3.6
5.3 ± 12
1.1 ± 5
-5.3 ± 4.1
-3.9 ±. 9.8
-98 ± 264
-13 ± 10
-8.6 ± 6.6
-2.2 ± 8.5
0.0 ± 32
-0.4 ± 5.4
0.2 ± 8.2
-8.5 ± 23
-2.7 ± 7.3
0.0 ± 7.2
3 ± 8
0.8 ± 6.3
-0.2 ± 3.3
-0.2 ± 2.7
-3.7 ± 2.9
-5.1 ± 11
-11 ± 18
-7.4 ± 16
2.2 ± 13
-8.7 ± 35
-0.6 ± 8.6
2 SIGMA
239 pu
(aCi/m3)
-0.9 ±11
3.4 ± 16
2.1 ± 19
-6.8 ± 4.4
-2.3 ± 8.4
-1.1 ± 3.8
-7.6 ± 4.9
-0.5 ± 6.9
-33 ±153
-18 ± 12
-12 ± 8
4.3 ± 6
0.0 ± 18
13 ± 14*
5.3 ± 5.8
-2.8 ± 13
0.9 ± 4.2
-0.9 ± 4.2
1.0 ± 4.6
0.0 ± 3.7
-2.5 ± 1.6
4.1 ± 5.7*
-5.3 ± 3.5
-1.3 ± 4.4
-4.5 ± 6.3
-1.8 ± 6.4
-0.7 ± 9.3
-4.3 ± 20
-6.5 ± 4.2
(continued)
31
-------
Tables. (Continued)
CONC. ± 2 SIGMA
COLLECTION
DATE 238 Pu 239 Pu
SAMPLING LOCATION 1988 (aCi/m3) (aCi/m3)
WY COMPOSITE (Worland& Rock Springs)
03/30 -6.1 ± 11 -2.3 ± 8
06/29 -29 ± 77 -9.5 ± 44
09/26 -25 ±19 -35 ± 24
12/09 -24 ± 20 -5.4 ± 7.7
All concentrations below the minimum detectable concentration (MDC) unless so noted.
* Concentration above the MDC but smaller than the 2-slgma error term.
** Concentration above the MDC and greater than the 2-slgma error term.
TABLE 6. Summary of Gross Beta Analyses
for Air Surveillance Network- 1 988
Sampling Location
Shoshone CA
Las Vegas NV
Delta UT
Milford UT
St George UT
No. Days
Sampled
351.0
356.4
353.9
357.6
328.7 *
Radioactivity Cone.
(pCi/m3)
Max Min
0.056 0.0010
0.055 -0.0036
0.10 -0.0017
0.088 0.0013
0.072 0.001 1
Avg
0.020
0.021
0.022
0.026
0.022
* This station was out of service during May, 1988.
32
-------
NEVADA J
O PYRAMID
Austin •
1 Ely*
\
\
ty ^V Tonopah^
>. . , PiocheA
» ,,,...... 1 H Rachel
•^ Goldfield* 1 1— — ,«
^ UNELLISAFB ^* Calientn*
V ? RANGE COMPLEX 1 i-anentew
• Mammoth ^ e_ x-v >,
Lakes \ S rC-X— 1 • Alamo
\ ^^s. \ NEVAOA
^^ Beattv i TEST
\^ I
Lathrop WellMr""\J"TJ ' Oyerton
* Q ^f^ v_i
\ Indian Springs W
UTAH
j SALT V.
\A /^A
>^ Salt
Lake
City
• Cedar City
• St. George
T ARIZONA
1
Pahrmnp • , _ ^J/LAKE^IEAD 1
Shoshone. \ *»* <5**T J
S ; N
*V • Scale in Milas
• Both Noble Gas and Tritium T» • o so 100
A Tritium (H-3) only S | ^==^^^===^o
5/89 ^1 Seal* in Kilom«ter>
F/0ure 11. Noble Gas and Tritium Surveillance Network Sampling Locations.
33
-------
EMSL-LV where their contents are analyzed.
Analysis starts by condensing the samples at liquid
nitrogen temperature and using gas
chromatography to separate the gases. The
separate fractions of radloxenon and radlokrypton
are dissolved In scintillation cocktail and counted In
a liquid scintillation counter (see Section 9.0 Sample
Analysis Procedures).
For tritium sampling, a molecular sieve column is
used to collect water from air after it passes through
a paniculate filter. Up to 10 m3 of air are passed
through the column over a 7-day sampling period.
Water adsorbed on the molecular sieve Is
recovered, and the concentration of tritium in the
water, as tritlated water (HTO), Is determined by
liquid scintillation counting (see Section 9.0 Sample
Analysis Procedures). This result can then be used
to calculate the concentration of tritium In air by
knowing the volume of air that passed through the
sieve.
Results
Figure 12 contains plots showing the results for all
the ^Kr analyses for each station, with the error
bars representing the two-sigma counting error.
The results all fell within the limits expected from
statistical variation.
A summary of the results from the samples
collected by the NGTSN Is shown In Table 7. This
summary consists of the maximum, minimum and
average concentration for each station. The
number of samples analyzed Is typically less than
the expected number (fifty-two) since samples are
occasionally lost in the analysis procedure, or
Insufficient volume Is collected, or no sample Is
collected due to equipment problems. Caliente and
Mammoth Lakes have particularly low counts for the
number of samples analyzed because their noble
gas systems were not installed and operational for
the entire year. At Caliente, the noble gas sampler
was not Installed until late April, then it was not
functional during the last two months of the year
due to equipment problems. The sampler at
Mammoth Lakes was removed about half way
through the year because the study It was
supporting was completed. The low number of
samples analyzed for St. George was due to a
combination of two factors. The first of these was a
series of samples with low volume, and the second
was a problem with the equipment which caused It
to be out of operation for several weeks. Network
weekly averages of 85Kr concentrations (with
two-sigma error bars) measured in 1988 are shown
in Figure 13. The measured ^Kr concentrations
ranged from 18.0 to 34.8 pCI/m3 (0.67 to 1.3
Bq/m3).
A paper presented by Bernhardt et al., (BE73) In a
1973 symposium contained a curve predicting 85Kr
concentration for the future. In recent years,
measured levels have not reached those predicted;
but Instead seem to have reached a plateau. Two
reasons for this may be the decision by the United
States to defer fuel reprocessing which is the step In
the fuel cycle where the majority of the krypton Is
*r
45 T~
40--
35--T
30- £
25--
20--
15--
10--
5--
Mammoth Lakea, CA
+
+
+
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
Figure 12. Weekly KKr Concentrations In Air by Station, 1988 Data.
34
-------
45
5«t
SM--
c 30--
{.25.-
| 20--
8 15--
^ 10--
5--
Shoahon*. CA
H - 1 - 1 - 1
1
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
45
§ *0
3 35
^ 30
I 25
| 20
8 15
t
10 +
5
0
Alamo, NV
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
45
*°
35
30
25
20
15
10
5
>
\i
5 10--
S
Austin, NV
1
h
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
45
§40f
U -.c
o. 35 -f
>~*
c 30
l25^
I 20--
I 15--
5--
Beatty. NV
+
—i ^_
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
Figure 12. (Continued)
35
-------
45
40--
30--
20--
15--
8
Callanta, NV
H 1-
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
45
c 30
•| 25
| 20
8 15--
8?
{
Oy, NV
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
45 T
£ 4°-'
^T 30 ••
I 25--
£ 20--
8 15--
C
510 • •
u 5-f
a^ o
Goldflold, NV
H 1 1 1 h
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
^45
S 40--
S 35-.
^30-.
| 20--
j 15--
5--
Indian Springs, NV
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
Figure 12. (Continued).
36
-------
"V45
40 -
la* Vegas, NV
8 15--
<§ 1°v
S
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
V. 40--
B»f
20--
8 15--
<§ 10"
L. 5 " "
Lathrop Walla, NV
s
H h
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
^45
S 40
& 35
^ 30
•| 25
| 20
8 15
§ 10
5--
S
Overton, NV
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
45
£ 40
" 35
Tj°
'"§ Z5
-| 20
8 15
o 10
" 5
Pahrump, NV
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
Figure 12. (Continued).
37
-------
40
35
30
Q" W"
g 35-.;
20
15
S
Rachel, W
H 1 1 1-
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
45
£«+
S»»
c 30--
•| 25--
| 20--
10--
3
Tonopah, NV
_, , , 1 ,_
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
S
40--
35--
§ 30
'-8 25 +•
8 15--
5 10-
i 5-
3
Cadar City, UT
H 1 1 1 h
+
H H
1 1 1_
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
"?
!
45
40-4-
35--
c 30--
» 25--
20--
15--
10--
5--
U
J
SL Gaorge, UT
+
H 1 1-
H h
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
Figure 12. (Continued).
38
-------
TABLE 7. Summary of analytical results for the Noble
Gas and Tritium Surveillance Network - 1988
SAMPLING
LOCATION
MAMMOTH LAKES,
CA
SHOSHONE,
CA
ALAMO,
NV
AUSTIN,
NV
BEATTY,
NV
CALIENTE,
NV
ELY,
NV
'
GOLDFIELD,
NV
INDIAN SPRINGS,
NV
LAS VEGAS,
NV
NUMBER
SAMPLES
ANALYZED
26
27
43
46
49
49
49
52
50
50
42
43
51
51
44
45
50
50
23
23
48
48
45
46
50
50
46
46
50
50
41
41
48
48
49
50
51
51
RADIONUCLIDE
85Kr
133Xe
85Kr
, 133Xe
3H in atm. m.*
3H as HTO in air
85Kr
^33Xe
3H In atm. m.*
3H as HTO in air
85Kr
133Xe
3H in atm. m.*
3H as HTO in air
85Kr
133Xe
3H in atm. m.*
3H as HTO in air
85Kr
133v«
e
3H in atm. m.*
3H as HTO In air
85Kr
133v**
®
3H in atm. m.*
3H as HTO in air
85Kr
' 133Xe
3H in atm. m.*
3H as HTO in air
ssKr
133Xe
3H in atm. m.*
3H as HTO in air
85Kr
133Xe
3H in atm. m.*
3H as HTO in air
RADIOACTIVITY CONG.
(pCi/m3)* I
MAX
31
12
30
8.8
0.53
6.9
29
20
0.52
5.3
30
11
0.74
3.0
32
17
0.50
4.6
28
14
0.50
6.5
35
11
1.1
7-7
32
15
0.80
8.3
30
7.1
0.75
3.5
31
8.8
0.60
5.2
MIN
22
-8.2
21
-9.3
-0.73
-8.4
20
-9.7
-1.3
-6.8
21
-12
-0.89
-5.9
20
-11
-0.64
-7.5
20
-20
-0.53
-2!3
20
-16
-1.3
-4.8
20
-21
-0.64
-6.2
20
-7.9
-1.1
-3.0
22
-11
-0.90
-8.1
AVG
25
2.1
25
0.17
-0.0027
-0.17
25
0.58
0.023'
0.26
25
-0.95
0.019
-0.0061
26
1.4
0.044
0.27
24
-3.8
0.014
0.42
26
0.51
0.034
0.36
25
0.32
-0.0019
-0.063
25
-0.54
0.038
0.41
26
0.93
0.033
0.39
PERCENT
CONC.
GUIDE**
< 0.01
< 0.01
< 0.01
< 0.01
...
<0.01
< 0.01
< 0.01
..
< 0.01
< 0.01
< 0.01
..
< 0.01
< 0.01
< 0.01
—
< 0.01
< 0.01
< 0.01
—
< 0.01
< 0.01
< 0.01
—
<0.01
<0.01
< 0.01
—
< 0.01
< 0.01
< 0.01
—
<0.01
< 0.01
< 0.01
-
< 0.01
(Continued)
39
-------
TABLET. (Continued)
NUMBER
SAMPLING SAMPLES
LOCATION ANALYZED RADIONUCLIDE
LATHROP WELLS,
NV
•
i
OVERTON,
NV
PAHRUMP,
NV
PIOCHE,
NV
RACHEL,
NV
TONOPAH,
NV
FALLINI'S (TWIN
SPRINGS) RANCH.NV
CEDAR CITY,
UT
ST GEORGE,
UT
SALT LAKE CITY,
UT
47
47
48
48
48
51
50
50
44
44
50
50
51
51
43
48
51
50
43
43
51
51
1
1
39
42
50
49
35
39
45
45
50
50
"Kr
133Xe
3H In atm. m.*
3H as HTO In air
*5Kr
133Xe
3H In atm. m.*
3H as HTO in air
85Kr
133Xe
3Hinatm. m.*
3H as HTO In air
3Hinatm.m.*
3H as HTO ln;alr
/
Kr
133Xe
3H In atm. m.*
3H as HTO In air
85Kr
133Xe
3H in atm. m.*
3H as HTO In air
85Kr
133\/—
xe
iS*
133Xe
3H in atm. m.*
3H as HTO In air
85Kr
133Xe
3H In atm. m.*
3H as HTO In air
3H in atm. m.*
3H as HTO In air
RADIOACTIVITY CONC.
(pCI/m3)* PERCENT
nr»M/^
MAX
30
8.6
0.71
6.3
32
8.2
0.74
15
30
10
0.69
6.7
0.55
4.7
32
12
0.61
5.0
30
16
0.74
8.5
24
9.2
31
13
0.67
3.8
32
9.6
0.50
4.9
0.55
4.9
MIN
18
-14
-1.0
-12
20
-10
-0.60
-3.8
21
-11
-0.90
-8.1
-0.75
-5.1
21
-17
-0.76
-5.0
21
-12
-0.67
-6.0
24
9.2
21
-9.0
-0.73
-4.2
21
-13
-0.95
-8.3
-0.70
-6.2
AVG GUIDE**
26
-0.032
0.082
0.53
26
1.1
0.070
0.68
25
0.67
0.0051
0.18
0.035
0.27
26
0.41
0.055
0.34
25
1.0
0.022
0.10
+
•f
25
2.5
0.053
0.22
26
-0.047
0.015
0.010
0.010
0.33
< 0.01
< 0.01
.,
<0.01
< 0.01
< 0.01
..
< 0.01
< 0.01
< 0.01
._
<0.01
..
< 0.01
< 0.01
< 0.01
..
< 0.01
<0.01
< 0.01
..
< 0.01
+
+
< 0.01
< 0.01
..
< 0.01
< 0.01
< 0.01
..
< 0.01
•-
< 0.01
* Concentrations of Tritium in atmospheric moisture (atm. m.) are expressed as Cl per mL of water collected.
** Concentration Guides used are for exposure to a suitable sample of the population In an uncontrolled area.
+ Insufficient data to calculate an average.
40
-------
TABLE 8. Annual average ^Kr concentrations in air, 1979-1988
^Kr Concentrations (pCI/m3)
Sampling
Locations
Death Valley Jet., CA*
Mammoth Lakes, CA*
Shoshone, CA
Alamo, NV
Austin, NV
Beatty, NV
Caliente, NV
Ely, NV
Goldfield, NV
Hiko, NV*
Indian Springs, NV
Las Vegas, NV
Lathrop Wells, NV
NTS, Mercury, NV*
NTS, Groom Lake, NV*
NTS, BJY, NV*
NTS, Area 12, NV*
NTS, Area 15, NV*
NTS, Area 400, NV*
Overton, NV
Pahrump, NV
1979
19
—
-
.
-
19
-
..
~
19
19
—
19
19
19
21
19
19
18
„
-
Rachel and Diablo, NV** 19
Tonopah, NV
Cedar City, UT
St. George, UT
Salt Lake City, UT*
NETWORK AVERAGE
* Stations discontinued
** Station at Diablo was
18
—
—
-
19
1980
«
—
-
..
™
21
~
..
-
21
21
22
21
21
23
21
21
21
„
~
21
21
-
-
-
21
moved to Rachel
1981
-
-------
O
Q.
x_x
C
o
0 23 - -
c
to
o
c
o
CJ
IO
00
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC
Network Weekly Averages for 1988
Figure 13. Network Weekly Average B5Kr Concentrations in Air, 1988 Data.
40--
"E 35--
Sx 30--
c
•2 25 +
o
c 20 +
v
o
o 15 +
o
IT)
00
10--
5--
1970
Annual Network Average
o o
o o
o o
00
°°
+
1975 1980
Time in Years
1985
1990
Figure 14. Annual Network Average 85Kr Concentration.
42
-------
actually released and the failure of the nuclear
power industry to grow at predicted rates.
An historical summary of data for this network
shows its trends over time. Network average
krypton results for the past ten years are shown in
Table 8, while results for the period 1972-1988 have
been plotted in Figure 14.
The concentration over the whole network showed
a mean of 25.4 pCi/m3 (0.94 Bq/m3). This network
average concentration, as shown in Figure 14 has
gradually increased from the time sampling began
in 1972 to the present. This increase, observed at
all stations, reflects the worldwide increase in
ambient concentrations resulting from the increased
use of nuclear technology as projected by
Bernhardt et al., (BE73). There is no evidence in the
^Kr results to indicate that the radioactive material
detected was from tests conducted at the NTS.
The analytical results for the 734 xenon samples
counted were all below the MDC which varied, but
was generally around 10 pCi/m3.
As in the past, tritium concentrations in atmospheric
moisture samples from the off-NTS stations were
generally below the MDC of about 400 pCi/L of
water (see Section 9.0 Sample Analysis
Procedures). Due to the statistical nature of
counting radioactive samples, some samples may
yield negative results or results below the MDC.
Results below the MDC are not necessarily real but
are below the sensitivity of the method. The tritium
concentrations observed at off-NTS stations were
considered to be representative of environmental
background. The mean of the tritium concentrations
for all off-site stations was 0.25 pCi/m3 (9.3
mBq/m3) of air. Only one of the 891 samples
analyzed was above the MDC and the
concentration measured for that sample was only
slightly above the MDC. That sample was collected
in Ely, and although there was a detectable amount
of 3H in the atmospheric moisture, the calculated
concentration of H in air was less than the
calculated MDC for that sample.
In conclusion, no NTS releases were detected by
this monitoring network during 1988.
43
-------
5.2.3 Milk Surveillance Network
K. S. Moroney
One important possible means of intake of
radlonuclides by humans is through airborne
deposition of radioactivity on forage crops eaten
by dairy cattle, with subsequent transmission to
milk. This pathway is monitored by EMSL-LV
through an extensive sampling and surveillance
system. The system is designed to produce
data from areas adjacent to the NTS which could
be affected by a release of airborne radioactivity,
as well as from areas unlikely to be so affected.
In 1988, the Milk Surveillance Network (MSN)
consisted of 29 locations within 300 km. of the NTS
(Figure 15) from which samples were collected
monthly by EPA monitors. The raw milk Is collected
in four-liter cubitalners and preserved with
formaldehyde.
In addition, all major milksheds west of the
Mississippi River, represented by 102 locations in
1988 (Figure 16), are sampled on an annual basis
as a part of the Standby Milk Surveillance Network
(SMSN). The annual activation of the SMSN helps
maintain readiness and highlights any trends of
increasing radionucllde concentrations in western
states. One exception to the latter portion of the
network Is Texas; the State Health Department
performs the surveillance of the milksheds in that
state. SMSN samples are supplied by cooperating
State Food and Drug Administration personnel
upon the request of the Regional EPA offices.
These samples, also preserved with formaldehyde
In four liter cubitainers, are mailed to EMSL-LV.
All samples are analyzed by high resolution gamma
spectroscopy to detect gamma emitting
radionuclldes. One sample per quarter for each
location In the MSN, and samples from two
locations In each western state in the SMSN, are
subjected to radiochemical analytical evaluations.
These samples are analyzed for tritium (3H) by
liquid scintillation counting, and for 89Sr and ^Sr by
an ion exchange method, as outlined in Section 9.0
Sample Analysis Procedures.
Although all the samples collected for the MSN
were analyzed for gamma-emitting nuclides, only
naturally occurring K was detected. For those
MSN samples analyzed for tritium and
radiostrontiums, the results are displayed In Table 9.
Two MSN samples with ^Sr slightly above the
minimum detectable activity were noted at
Mesquite, Nevada, and St. George, Utah. With
those exceptions, no 89Sr or ^Sr, or significant
levels of tritium, were detected by radiochemical
analysis In the laboratory.
Results for SMSN are presented In Table 10. One
SMSN sample from Flensberg, Minnesota,
contained detectable 137Cs (result = 65 ± 9
plcocuries per liter). No other radionuclide aside
from naturally occurring 40K was Identified for the
SMSN. The SMSN had six samples from high
rainfall states with detectable ^Sr.
These results are expected, and data from both
networks are consistent with data from previous
years. These results are also consistent with the
results shown In Figure 17 for the Pasteurized Milk
Network operated by the EPA's Eastern
Environmental Radiation Facility In Montgomery,
Alabama. No result was available for Salt Lake City.
Results from the New Orleans samples have been
consistently higher over the years, and reflect the
higher rainfall In that area. Data overall shows a
trend of slowly decreasing levels of ^Sr over the
past several years (EPA88).
5.2.4 Biomonitoring Program
D. D. Smith
The pathways for transport of radionuclides to
humans include air, water, and food. Monitoring
of air, water, and milk are discussed elsewhere
In this report. Meat from local animals and lo-
cally grown fruit and vegetables are food com-
ponents that may be potential routes of
exposure to off-site residents.
Methods
Samples of muscle, lung, liver, kidney, blood, and
bone are collected periodically from cattle
purchased from commercial herds that graze areas
adjacent to the NTS. The soft tissues are analyzed
for gamma-emitters. Bone and liver are analyzed
for strontium and plutonium and blood/urine or soft
tissue is analyzed for tritium. Each -November and
December, bone and kidney samples which are
donated by licensed hunters from desert bighorn
sheep killed in southern Nevada (Figure 18) are
analyzed for strontium, plutonium and tritium.
These kinds of samples have been collected and
analyzed for up to 31 years to determine long-term
trends. During 1988, four NTS mule deer were
collected and sampled in the same manner as the
cattle.
44
-------
Winnemucca^
Wells*
Elko»
PYRAMID
LAKE
NEVADA IUTAH
•
I
•
|
I
Reno
• Austin
• Young Rn.
Larsen Rn.B
• McGill
• Ely
McKay Rn.B
Round Mtn.
Berg Rn.
_
Tonopah
• Herbecke Rn.
• Shosnone
.
Lemon Rn.
Dyer*
T*
I. Brown Rn.
Bishop •
Goldfield
B
V Fayne Rn.
>Scott Rn.'
\
Manzonie Rn. • Lund
I Currant • Peacock Rn/ •
, , , _ _ McKenzie Dairy I
Blue Eagle Rn.B *
• Jay Springs Rn. |
Warm,- BNyala •
Springs T". Sharp's Rn. |
Springs
DO Darrel
! nil. QaoKal . .
Hansen
. _ BRn.
•RANGE COMPLEX [p-enover
Farms
• Town Locations
• Milk Sampling Locations
NOTE: When sampling location occurred
in city or town, the sampling location
symbol was used for showing both town
and sampling location
5/89
Cedar City
I Brent Jones
Dairy
Springdale»
Lathrop Wells
John Deerfl
^*
Moapa
_ •
RockviewB
Indian Dairies
Springs fj |
Pahrumpjt i ac^BIPS Dairy Farm
Vegas
St. George
Cannon Farm/
B Gentry Dairy —1 —
,. l—"™ ™' AR'IZONA
Mesquite
-
• Speda Brothers
Knudsen Corf/L. Marshall Rn.
jLogandale
• Ridgecrest
• Cedarsage Farm
V!
• Hinkley
• Bill Nelson Oairy/
Desert View Dairy
100
50 100
Seal* in Kilomete
150
Figure 15. Milk Sampling Locations Within 300 km of the NTS.
45
-------
Figure 16. Standby Milk Surveillance Network Stations.
New Orleans
Salt Lake City*
Las Vegas
*No sample reported for 1988
1965
1970
1975
1980
1985
1990
Figure 17. Strontium-90 Concentration in Pasteurized Milk Network Samples.
46
-------
TABLE 9. Summary of Analytical
Results for the Milk
COLLECTION
DATE
SAMPLING LOCATION 1988
BENTON CA
Irene Brown Ranch
HINKLEY CA
Bill Nelson Dairy
Desert View Dairy (Alt for B.
RIDGECREST CA
Cedarsage Farm
ALAMO NV
Courtney Dahl Ranch
AUSTIN NV
Young's Ranch
BLUE JAY NV
Blue Jay Sprgs-Jim Bias
CURRANT NV
Blue Eagle Ranch
Manzonie Ranch
01/21
04/13
12/01
01/21
04/13
04/13
Nelson)
10/04
01/21
04/13
07/14
10/04
03/02
06/01
09/01
12/01
01/13
04/12
06/07
10/19
08/16
11/02
01/05
04/06
07/12
12/07
01/05
04/06
07/12
10/12
NO
580
210
430
320
340
521
181
93
864
245
243
129
70
659
NO
183
-162
122
232
72
NO
210
118
398
3H
(pCi/L)
SAMPLE **
± 240
± 240
±
±
±
±
±
±
±
±
±
**
±
240
380*
250
243
369*
234*
235
386*
386*
238*
241*
241
SAMPLE **
+
+
±
**
±
±
239*
238*
234*
366*
246*
SAMPLE **
**
±
±
±
378*
244*
246
Surveillance Network- 1988
CONC ± 2 SIGMA
(pCi/L) (pCi/L)
GOATS DRY **
-2.4 ± 3.7*
-2.0 ±14*
-0.8
2.1
OUT OF
-2.3
-2.7
-2.7
-4.3
0.6
2.2
1.4
-0.4
-1.4
1.6
1.4
±10* 0.8
± 2.7* 0.3
BUSINESS
**
± 4.4*
± 4.9*
± 3.2*
± 10.2*
± 5.2*
± 2.4*
**
± 5*
± 6.2*
± 3.6*
1.3
1.4
1.3
1.0
0.0
-0.0
-0.3
-0.2
1.0
1.5
COW DRY **
-2.3
-2.5
-3.2
-4.1
1.6
-3.3
COW
1.0
2.3
-0.7
-0.1
± 7*
± 20.5*
±11*
± 1.2*
± 3*
± 10.7*
DRY**
± 3.7*
± 4.8*
± 2.6*
± 5.8*
1.8
1.1
1.6
2.6
1.1
2.7
0.2
0.2
0.5
1.1
**
**
±
±
±
±
±
±
±
±
±
•±
**
±
±
±
+
±
±
**
±
±
±
±
1.6*
2.3*
6.5*
1.2*
2.8*
2.1*
1.7*
1.2*
2.0*
1.4*
2.5*
1.2
3.6*
1.6*
1.6*
1.8*
1.7*
6.2*
1.2*
6.9*
2.0*
1.9*
1.4*
1.2*
(continued)
47
-------
TABLE 9. (Continued)
SAMPLING LOCATION
DYER NV
Ozel Lemon
ELY NV
McKay, Robert and Caria
GOLDFIELD NV
Frayne Ranch
Susie Scott Ranch
LAS VEGAS NV
LDS Dairy Farms
LATHROP WELLS NV
John Deer Ranch
LOGANDALE NV
Leonard Marshall
Knudsen Dairy
LUND NV
Rue Peacock
COLLECTION
DATE 3H
1988 (pCi/L)
01/12
04/15
07/12
10/19
**
423 33 236
188 as 241*
NO SAMPLE **
(Alt. for W. Burdic)
12/01 117 ae 236*
01/13
07/28
10/19
12/14
06/17
09/16
10/19
12/15
02/08
05/06
08/01
11/01
01/12
04/15
08/08
12/15
03/01
05/02
07/01
08/04
10/02
11/01
02/01
07/12
08/02
11/02
NO SAMPLE **
190 as 244*
NO SAMPLE **
NO SAMPLE **
6.7 ae 370*
-54 as 240*
NO SAMPLE **
NO SAMPLE **
94 33 368*
398 33 227
94 ae 247*
303 33 236
NO SAMPLE **
326 33 383*
-32 33 231*
NO SAMPLE **
**
308 33 367*
160 33 240*
170 33 247*
457 33 245
237 33 232*
509 33 235
-68 33 232*
107 33 235
161 33 231
CONC ± 2 SIGMA
89Sr
(pCI/L)
6.2 33 6.4*
3.6 33 7.3*
-2.0 33 4.1*
COW DRY **
-1.2 33 5.7*
GOAT DRY **
-0.1 33 2.0*
GOAT DRY **
GOATS DRY **
1.1 33 7.0*
GOATS DRY **
GOATS DRY **
1.4 33 8.0*
1.2 ae 2.3*
-4.4 3327.4*
0.8 33 4.9*
GOATS DRY **
-2.9 33 7.8*
7.3 3330.6*
GOATS DRY **
**
-1.2 33 7.8*
-0.4 33 9.7*
**
-3.1 33 7.0*
1.0 33 8.2*
-4.4 3310.6*
2.7 33 4.5*
-4.2 3316.8*
0.1 33 8.4*
90Sr
(pCi/L)
-0.4 33 3.7*
0.6 33 3.2*
0.8 33 2.0*
**
0.8 33 1.3
**
1.3 33 1.3*
**
**
-0.1 33 4.1*
**0.7 33 2.1*
**
**
0.7 33 2.2*
0.5 33 1.8*
1.0 332.0*
0.0 33 1.1*
**
1.2 332.7*
-1.1 33 2.4*
**
ALTERNATE
1.0 33 2.7*
1.5 335.4*
-0.8 33 1.3*
1.2 33 1.3*
-0.1 33 1.3*
1.2 332.6*
1.0 333.0*
0.9 33 1.3*
0.6 33 1.7*
(continued)
48
-------
TABLE 9. (continued)
COLLECTION
SAMPLING LOCATION
LUND NV
McKenzie Dairy
MCGILL NV
Larsen Ranch
MESQUITE NV
Speda Brothers Dairy
MOAPA NV
Rockview Dairies Inc.
NYALA NV
Sharp's Ranch
CALIENTE NV
June Cox Ranch
ROUND MT NV
Berg's Ranch
SHOSHONE NV
Harbecke Ranch
DATE
1988
02/01
05/04
01/05
02/01
04/04
05/02
08/09
09/12
11/01
02/01
05/02
07/01
07/01
08/11
10/03
11/01
02/02
05/05
08/09
11/01
01/06
04/04
07/11
10/03
03/10
09/15
12/14
01/05
03/01
06/07
09/01
12/01
3H
(pCi/L)
309 38 378*
SOLD OUT **
NO SAMPLE **
333 33 380*
365 33 370*
155 39 371*
243 33 255
**
268 33 244
400 33 230
294 33 371*
98 33 236*
(HIGH Sr ABOVE
-20 33 252*
39 33 234*
36 33 249*
378 33 399*
164 33 376*
71 33 253*
159 33 235*
**
300 33 385*
-12 33 252*
200 33 250*
NO SAMPLE **
NO SAMPLE **
-16 33 242*
**
428 33 238
583 33 246
201 33 239*
51 33 226*
CONC ± 2 SIGMA
^Sr
(PCi/L)
-2.7 33 6.*
**
SOLD COW **
-0.7 33 7.2*
-9.8 33 6.9*
-6.9 33 7.9*
**
**
2.0 33 9.9*
-1.8 33 6.6*
-1.5 33 5.4*
-3.1 3322.6*
MDA)
-9.7 3323.1*
0.1 3315.9*
**
-4.8 3310.3*
1.6 33 7*
2.9 3316.2*
0.9 3313.4*
LOST
4.2 33 4.6*
1.1 33 5.1*
-0.6 33 6.4*
COW DRY **
COW DRY **
**
1.5 33 4.1*
7.9 3324.6*
-0.1 33 2.1*
**
3.7 33 6.2*
^Sr
(PCi/L)
**
**
**
0.7 ae 1.8*
2.3 ae 2.6*
1.6 ae 0.9
0.4 33 3.0
0.5 331.4*
0.1 33 1.6*
1.2 33 1.7*
1.1 33 1.7*
1.3 3313.5*
2.1 33 2.0
0.7 33 2.8*
0.3 33 1.4*
1.5 33 2.6*
1.0 333.1*
0.4 ae 1.3*
0.6 33 1.4*
LOST
-0.2 33 1.8*
0.3 33 3.3*
0.5 33 1.2*
**
**
1.0 33 1.6*
2.0 33 2.2*
1.3 3314*
0.0 33 1.3*
3.2 33 3.2*
0.25 33 1.4*
(continued)
49
-------
TABLE 9. (Continued)
COLLECTION
SAMPLING LOCATION
RACHEL NV
Penoyer Farm
C. Castleton
WARM SPRINGS NV
Twin Springs Ranch
CEDAR CITY UT
Brent Jones Dairy
ST GEORGE UT
Gentry Dairy
Truman Cannon
DATE
1988
02/02
05/04
08/02
12/06
01/04
03/01
06/06
07/01
09/12
12/01
01/04
03/01
06/06
09/12
12/01
* CONCENTRATION IS LESS THAN THE MINIMUM
** SAMPLES NOT ANALYZED.
3H
(pCI/L)
130 as 372*
NO SAMPLE **
NO SAMPLE **
130 33 249*
295 33 384*
318 33 353*
315 33 375*
140 33 234*
40 33 239*
148 33 243*
253 33 390*
199 33 374*
448 33 239
155 33 155*
293 33 244
CONC ± 2 SIGMA
^Sr
(pCi/L)
6.6 33 7.2*
COW DRY **
COW DRY **
**
-2.1 33 5.4*
-1.9 33 6.4*
0.3 33 2.7*
-0.5 33 3.8*
**
-0.2 33 5.1*
-3.3 33 1.3*
6.0 33 9.1*
-0.4 33 2.4*
**
2.4 33 6.4*
*°Sr
(pCi/L)
0.1 33 1.8*
**
**
0.8 33 1.9*
1.6 332.8*
1.7 332.3*
0.2 33 1.7*
0.9 33 1.7*
1.1 33 1.0*
0.8 33 1.2*
1.3 334.8*
0.2 33 2.1*
1.3 33 1.4*
1.3 33 1.1
-0.4 33 1.4*
DETECTABLE CONCENTRATION (MDC).
50
-------
TABLE 10. Analytical results for the Standby Milk Surveillance Network 1988
COLLECTION CONC. ± 2 SIGMA
DATE ^H ^Sr
SAMPLING LOCATION 1988 (pCi/L) (pCi/L)
Taylor AZ Sunrise Dairy
Tucson AZ Shamrock Dairy (Pima Co)
Little Rock AR Bordens
Russellville AR Arkansas Tech Univ
Bakersfield CA Carnation Dairy
Weed CA Medo-Bel Creamery
Willows CA Foremost Foods Company
Grand Junction CO
Colorado West Dairies
Pueblo CO Hyde Park Dairy Co
Boise ID Meadow Gold Dairies
Burlington IA MS Valley Milk Pro
Dubuque IA MS Valley Milk Assn
Ellis KS Mid-America Dairy
Sabetha KS Mid-America Dairy
Manhattan KS Kansas State University
Ellis KS Mid-America Dairy
Sabetha KS Mid-America Dairy
Manhattan MS Kansas City University
Monroe LA Borden's
Flensburg MN Flensburg Co-op Cmry
(Sobieski Dairy)
Fosston MN Land O'Lakes Inc
07/07
07/11
07/11
07/17
08/08
08/16
08/15
06/29
08/29
08/23
06/24
06/16
07/18
07/20
07/20
07/18
07/20
07/20
08/02
08/01
08/02
160 ±380*
83 ±240*
140 ±230*
244 ±241*
142 ±230*
-11 ±233*
107 ±236*
177 ±233*
243 ±236***
117 ±241*
140 ±241*
353 ±240***
116 ±234*
-147 ±230*
56 ±241*
116 ±234*
-147 ±230*
56 ±241*
248 ±250*
66 ±235*
33 ±229*
3.6 ±5.0*
1.5 ±4.5*
-1.3 ±5.3*
-2.1 ±5.2*
-0.9 ±2.3*
-1.1 ±1.8*
-1.0 ±1.2*
0.9 ±5.6*
**
**
5.2 ±9.6*
1.4 ±7.2*
-8.9 ±5.7*
1.1 d35*
-4.8 ±6.6*
-8.9 ±5.7*
1.1 d34.9*
-4.8 ±6.6*
**
**
-1.7 ±1.8*
^Sr
(pCi/L)
-1.9± 3.7*
-1.0± 3.5*
2.8± 4.1*
2.9 ± 4.4*
0.8 ± 1.8*
0.8 ± 1.6*
0.8± 1.1
-0.05 ±3.7*
1.5± 1.9*
1.3 ± 1.6*
-1.0± 5.0*
1.6± 4.0*
***
5.5 ± 3.0
-3.0 ±29*
2.5 ± 5.7*
***
5.5 ± 3.0
-3.0 ±29*
2.5 ± 5.7*
1.9 ± 3.0*
1.4 ± 2.4*
***
2.0 ± 1.0
(continued)
51
-------
TABLE 10. (Continued)
COLLECTION CONC. ± 2 SIGMA
DATE ^H ^Sr
SAMPLING LOCATION 1988 (pCi/L) (pCi/L)
Rochester MN Rochester Dairy Co-op
Aurora MO Mid-America Dairy Inc
Jackson MO Mid-America Dairymen Inc
Billings MT Beatrice Foods Co
Havre Mt Vita-Rich Dairy
Norfolk NE Gillette Dairy
North Platte NE Mid America Dairymen
Superior NE Mid-Amer Dairymn-D Fritz
Albuquerque NM Borden's Valley Gold
La Plata NM Rothlisberger Dairy
Bismarck ND Bridgemens Creamery
Grand Forks ND Minnesota Dairy
Enid OK AMPI Goldspot Division
McAlester OK OK State Penitentiary
Corvallis OR Sunny Brook Dairy
Medford OR Dairygold Farms
Tillamook OR Tillamook Co Crmy
Sioux Falls SD Land O'Lakes Inc
Volga SD Land O'Lakes Inc
Provo UT BYU Dairy Products Lab
Moses Lake WA Safeway Stores Inc
Seattle WA Consolidated Dairy Prod
08/02
08/29
06/27
06/15
08/18
07/21
07/11
07/21
06/29
07/05
07/27
07/07
09/06
09/26
07/25
07/26
07/28
06/17
06/20
07/15
09/01
08/11
161 ±235*
304 ±241*"
31 ±230*
43 ±230*
305 ±250***
25 ±232*
131 ±238*
135 ±236*
123 ±231*
21 ±241*
245 ±234*
143 ±239*
163 ±240*
142 ±244*
61 ±234*
88 ±239*
138 ±239*
97 ±233*
129 ±234*
20 ±232*
311 ±253***
319 ±265***
-5.1 ±5.9*
**
-0.1 ±3.0*
1.4 ±11*
**
-0.38 ±1.7*
-2.1 ±2.6*
-0.9 ±3.7*
-3.4 ±15*
15 ±17*
1.0 ±2.6*
-2.3 ±4.0*
**
**
-4.4 ±6.1*
-1.4 ±3.3*
-0.5 ±3.4*
3.0 ±5.2*
1.9 ±15*
-0.2 ±2.0*
**
-3.7 ±17.2*
^Sr
(PCi/L)
3.4 ± 4.1*
***
4.9 ± 2.6
1.7± 2.1*
1.5± 6.1*
-0.6 ± 3.0*
***
2.4 ± 1.2
***
3.7 ± 1.5
2.2 ± 3.4*
0.0 ± 9.9*
-5.0 ±12*
0.9 ± 1.6*
2.3 ± 3.4*
0.0 ± 2.2*
1.5 ± 2.0*
1.6± 5.7*
1.1± 2.1*
1.5± 2.3*
0.6 ± 3.0*
0.5 ± 8.7*
0.7 ± 1.8*
**
1.9±13.1*
(continued)
52
-------
TABLE 10. (Continued)
SAMPLING LOCATION
COLLECTION
DATE
1988
H
(pCi/L)
CONC. ± 2 SIGMA
89,
Sr
(pCi/L)
90,
'Sr
(pCi/L)
Spokane WA Consolidated Dairy
Powell WY Cream of the Valley Dairy
09/01
07/23
324 ±250
384 ±235
-6.3 ± 4.4*
2.4 ± 2.2
**
***
Concentration is less than the minimum detectable concentration (MDC).
Samples not analyzed.
Concentration is greater than the minimum detectable concentration (MDC).
SAMPLES FROM THE FOLLOWING LOCATIONS WERE ANALYZED BY GAMMA
SPECTROSCOPY ONLY:
In all cases gamma spectroscopy results were negligible.
SAMPLING LOCATION
COLLECTION
DATE
1988
SAMPLING LOCATION
COLLECTION
DATE
1988
Joseph City AZ
Midway Dairy 07/11
Tempe AZ
United Dairyman of AZ 07/11
YumaAZ
Golden West Dairy 07/12
Batesville AR
Hills Valley Foods 09/19
Fayetteville AR
University of AR 07/20
Helendale CA
Osterkamp Dairy No 2 08/08
Chino CA
CA Inst for Men 08/09
Holtville CA
Schaffner & Son Dairy 08/08
Manteca CA
Dejager Dairy #2 North 08/10
Oxnard CA
Chase Bros Dairy 08/09
Redding CA
McColl's Dairy Prod 08/15
San Jose CA
Marques Bros Mexican Impo 08/02
San Luis Obispo CA
Cal State Poly 08/08
Smith River CA
Country Maid Dairy 08/01
Soledad CA
CTF Dairy 08/04
Tracy CA
DeuelVoclnst 08/15
Colorado Springs CO
Sinton Dairy Co 07/05
Delta CO
Arden Meadow Gold Dairy 08/18
Lewiston ID
Golden Grain Dairy Prod 06/16
Pocatello ID
Rowland's Dairy 08/17
Twin Falls ID
Associated Dairy Inc 08/17
Kimballton IA
AMPI Receiving Sta 06/21
Lake Mills IA
Lake Mills Coop Crmy 07/11
Lemars IA
Wells Dairy 07/12
Hammond LA
Southeastern LA College 08/03
Dalton MN
Dalton Co-op Creamery 07/28
(continued)
53
-------
TABLE 10. (continued)
SAMPLING LOCATION
COLLECTION
DATE
1988
SAMPLING LOCATION
COLLECTION
DATE
1988
Saugus CA
Wayside Honor Ranch 08/08
SebastopoICA
WM Miller Dairy 08/16
Jefferson City MO
Central Dairy Co 07/19
Boseman MT
Darlgold Farms 06/15
Great Fall MT
Meadow Gold Dairy 06/17
Mtssoula MT
Community Creamery 08/22
Caldwell ID
DCA Receiving Sta 06/15
Chapped NE
Leprino Foods 07/25
Fallen NV
Creamland Dairy 07/25
Logandale NV
Knudsen Dairy 07/24
Reno NV
Model Dairy 07/26
YeringtonNV
Valley Dairy 07/25
Devils Lake ND
Lake View Dairy 07/05
Fargo ND
Cassclay Creamery 07/29
AtokaOK
Mungle Dairy 09/07
Claremore OK
Swan Bros Dairy 09/08
Myrtle Point OR
Safeway Stores Inc 07/26
Nicollet MN
Nicollet County Dairy 08/01
Chillicothe MO
Mid-America Dairymen 06/15
Eugene OR
Echo Springs Dairy 07/25
Grants Pass OR
Valley of Rogue Dairy 07/25
Klamath Falls OR
Medo Bel Creamery 08/17
Union OR
Gram-Bell Dairy 07/25
Omaha NE
Roberts Dairy-Marshall Gro 07/11
Redmond OR
Eberhard's Creamery Inc 07/25
Mitchell SD
Culhanes Dairy 08/17
Rapid City SD
Brown Swiss Dairy 06/21
Beaver UT
Cache Valley Dairy 08/24
North Ogden UT
Western General Dairy 07/08
Richfield UT
Ideal Dairy 07/05
Smithfield UT
Cache Valley Dairy 07/13
Cheyenne WY
Dairy Gold Foods 06/10
Laramie WY
Univ of WY (Dairy Farm) 09/14
Riverton WY
Albertson's Plant 06/10
54
-------
• Nyala
.C. Smt.
Tempi ute
Smt.
Handcock Smt.
NELLIS AFB
RANGE COMPLEX
DESERT
NATIONAL
WILDLIFE
RANGE
'/NEVADA'••:": "
"-..TEST '.I-'"
'•''• 'SITE'/''"/,
Furnace
Creek
Tf Searchlight
O Bighorn Sheep
D Mule Deer
A Cattle
5/89
Symbol numbers represent the
animal identification numbers
Figure 18. Collection Sites for Animals Sampled, 1988.
55
-------
Results
Analytical data from bones and kidneys collected
from desert bighorn sheep during the late fall of
1987 are presented In Table 11. Tritium
concentrations reported from the kidneys ranged
from 100 pCi/L to 970 pCi/L with a median value of
510 pCi/L Kidney tissue concentration Ira eight
animals exceeded the minimum detectable activity
of 560 pCi/L The naturally occurring ^K was the
only gamma-emitting radionuclide detected In the
kidneys of the sheep. Strontium-90 levels In the
bones (average 2.3 pCi/g ash) are consistent with
those reported in recent years (Figure 19).
Plutonium concentration In tissues from the desert
bighorn sheep were also similar to those reported in
previous years. Counting errors exceeded the
reported concentrations in the majority of bone
samples. Plutonium-238 concentrations in bone
ash ranged from 0.02 fCI/g to 8.2 fCI/g ash with a
median of 2.95 fCi/g ash. The 239Pu concentrations
ranged from -0.07 fCi/g ash to 17 fCi/g ash with a
median value of 2.6 fCi/g ash.
Eight beef cattle were sampled during 1988, four in
May and four in October. All eight animals were
purchased from G. L Coffer of Beatty, Nevada, and
grazed the Beatty Wash adjacent to Yucca
Mountain and Area 30 of NTS (Figure 18). Tritium
concentrations In blood did not exceed the
minimum detectable activity in any of the eight
animals. The only gamma-emitting radionuclides
detected other than naturally occurring 40K, was
137Cs (15 ± 7 pCI/kg) in the muscle from an aged
cow. Strontlum-90 concentration in bone ash
samples from the 1988 cattle ranged from 0.2 pCi/g
of ash to 0.8 pCI/g ash with an average of 0.6 pCi/g
of ash (Figure 19). Strontium-90 concentrations in
bones from four cattle from the Steve Medlin Ranch
30-|
11 12
H Bighorn Sheep
I I Deer
133 Cattle
Numbers at top of columns indicate
the number of bone samples in each
category. (Numbers prior to 1964
are unknown)
iq
70 75
Year (1956-1987)
,80
Figure 19. Average Sr Concentrations in Animal Bone.
56
-------
Table 11. Radionuclide concentrations in desert bighorn sheep samples - 1987
Bighorn Sheep Bone
(collected ^Sr
Winter 1987) (pCi/g Ash)
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
Median
Range
1.9
2.2
2.9
2.1
6.4
1.6
2.4
2.3
1.2
1.7
1.0
3.6
6.7
1.3
2.3
1.0
0.9
0.5
1.0
1.0
1.8
0.5
±
+
±
+
+
±
±
±
±
±
±
±
±
±
±
+
±
jr
+
j;
-
0.1
0.1
0.1
0.1
1.0
0.1
0.1
0.1
0.1
0.1
0.1
0.2
0.7
0.2
0.2
0.1
0.07
0.06
0.07
0.08
6.7
Bone
238pu
(fCi/gAsh)
4.8
1.2
1.8
2.4
5.6
2.8
5.1
2.2
1.2
1.1
2.2
0.02
3.1
3.1
8.2
5.4
4.9
3.2
1.1
4.2
2.95
0.02
±4.5
± 4.0**
±3.1**
± 3.6**
±3.5
± 3.6**
±3.2
±3.1
± 4.2**
± 3.9**
± 4.3**
± 0.03**
±3.1
±3.1
±4.0
±3.6
±3.2
± 3.6**
±3.5
±3.4
- 8.2
Bone
239pu
(fCi/g Ash)
17
4.7
1.5
2.2
0.1
3.2
6.6
2.7
2.9
-0.07
2.9
-0.2
0.5
1.0
6.1
4.2
0.8
1.0
2.4
7.0
2.55
-0.2
±
±
±
+
+
+
+
±
±
±
±
±
Hh
±
±
+
±
±
+
±
4.7
2.7
1.9**
2.3**
1.4**
2.5
2.8
1.6
2.4
1.4**
2.2
0.8**
1.1**
1.7**
2.9
5.3**
1.5**
1.9**
2.1
3.0
- 17.0
Kidney
3H(pCi/L)*
460
570
760
100
470
120
480
180
370
380
810
710
970
760
680
340
540
580
260
510
510
100
±
±
±
±
+
±
jt
+
±
+
4;
±
±
±
+
+
±
±
±
H;
-
350
350
350
320**
350
340**
350
340**
340
340
350
350
550
350
350
350**
350
350
340**
350
970
* Aqueous portion of kidney tissue, MDA is 560 pCI/L
** Counting error exceeds reported activity
57
-------
sampled In October 1987 averaged 1.2 pCI/g of ash
(analyses were not completed In time for data to be
Included In the 1987 annual report).
Concentrations of 238Pu did not exceed the
counting errors In any of the bone and liver samples
collected from cattle during October 1987, or 1988.
Liver concentrations of 239Pu exceeded the
counting error In all samples. Concentrations
ranged from 6.3 to 28 fCI/g ash (median of 11 fCi/g
ash) for the Medlln cattle and from 6 to 31 fCI/g ash
(median 12 fCI/g ash) for liver samples from the
Coffer cattle. Plutonlum-239 concentrations in
cattle bone samples exceeded the counting error In
only one of the Medlln animals (20 ± 13 fCI/g ash)
and one of the 1988 cows (4.8 ± 2.5 fCi/g ash).
Whole body concentrations of plutonlum In two fetl
from the 1988 October cattle were similar to those
found In their dams, i.e., 238Pu concentration did
not exceed its counting error and 239Pu
concentrations were 1.1 ±1.7 and 6.1 ± 3 fCI/g of
ash.
During 1988, four NTS mule deer were sampled.
Analytical data from these animals plus those from
the last two mule deer sampled in 1987 (data from
these animals was not available for 1987 annual
report) are presented In Table 12.
Other than the naturally occurring ^K, the only
gamma-emitting radionuclldes detected were 137Cs
In the soft tissues of deer #4 (1987) and deer #3
(1988) and 106Ru and 125Sb In the rumen contents
of the same animals. The 106Ru values in rumen
contents were 50 and 54 pCI/kg, respectively, and
the 125Sb values were 1500 and 110 pCi/kg,
respectively: the kidneys of deer #3 (1988) also
contained 220 pCi/kg of 106Ru.
Strontium-90 values In the 1988 deer ranged from
0.5 to 2.2 pCi/g of bone ash with an average value
of 1.2 pCI/g of ash (Figure 19). The ^Sr values In
the two 1987 deer were 1.3 and 1.7 pCi/g of bone
ash (average for all 1987 deer were 1.0 pCI/g of
bone ash). Bone levels of 238Pu and 239Pu did not
exceed the counting error In any of the deer. Soft
tissue concentrations of 239Pu, which exceeded the
counting errors, ranged from 1.3 fCI/g of ash (lung
1988 No. 3) to 52 fCi/g of ash (muscle 1988 No. 1).
Soft tissue concentration of 23^Pu, which exceeded
the counting errors, occurred In muscle samples
from three of the 1988 deer and ranged from 0.1
fCi/g of ash to 6.9 fCi/g of ash.
Detectable tritium concentrations found in the
kidneys of two 1988 deer were quite elevated In the
kidneys of two deer (No. 1,1.5 //Ci/L of tissue water
and No. 3, 39 /iCi/L of tissue water). Both of these
animals and No. 4 from 1987 were collected in close
proximity to the tunnel area of Area 12 and probably
were drinking from the drainage waters in this area.
These unfenced drainage waters continue to be a
potential source of exposure to the off-site
population which may consume meat from mule
deer or migratory fowl which travel off the NTS.
Dose estimates from consumption of NTS deer are
presented in the dose assessment section.
Two migratory ducks from the Overton Wildlife
Refuge were collected through the cooperation of
the Nevada Department of Wildlife. Other than 40K,
no gamma-emitting radionuclides were detected.
Strontium-90 concentrations in bones were 0.2
pCI/g of ash in both ducks. Plutonium-238
concentrations exceeded the counting errors in the
muscle of duck No. 1 (21 ± 4.4 fCi/g ash).
Plutonium-239 levels exceeded the counting error in
the muscle of duck No. 1 (53 ± 14 fCi/g ash) and
Internal organs of duck No. 2 (12 ± 5 fCi/g ash).
Certain radionuclide analyses of composited tissue
from two NTS chukars collected during 1987 were
not completed prior to publishing the 1987 annual
report. Therefore, that data Is summarized as
follows: the ^Sr value of the bones was 0.04 ±
0.03 pCi/g of bone ash. Plutonlum-238 values that
exceeded the counting error were 100 ± 17 fCi/g
bone ash and 18 ± 6 fCi/g of ash from internal
organs. Plutonlum-239 values that exceeded the
counting error were 930 ± 130 fCI/g of bone ash, 40
± 15 fCi/g of ash from muscle and 170 ± 20 fCi/g
ash from the internal organs.
During the summer of 1988, samples of produce
were collected from the Fallis and Penoyer Farm
gardens In Rachel, Nevada. All of these samples
(turnips, turnip greens, potatoes, squash, and
cucumbers) were submitted for gamma analysis,
the spectra were negligible for all samples
collected.
58
-------
Table 12. Radionuclide Concentration in Tissues From Mule Deer
Collected on the Nevada Test Site - 1988
Tissue
Thyroid
Kidney
Muscle
Liver
Lung
Rumen
Contents
Blood
Bone
Liver
Lung
Rumen
Contents
Blood
Bone
Kidney
Lung
Muscle
Rumen
Contents
Bone
Liver
Muscle
Rumen
Contents
Bone
137Cs
(pCI/Kg)
ND
270 ± 40
90 ±20
90 ±20
120 ± 30
830 ± 40
NA
NA
ND
ND
ND
NA
NA
ND
ND
ND
ND
NA
ND
ND
ND
NA
3H
(uCi/L)
Mule Deer No. 4
NA
NA
NA
NA
NA
NA
41 .4 ±0.08
NA
Mule Deer No. 5
NA
NA
NA
0.23 ± 0.02
NA
Mule Deer No. 1
1.5 ±0.004
NA
NA
NA
ND
Mule Deer No. 2
NA
NA
NA
NA
-•
238pu
fCi/g/ash
Collected 07/28/87
NA
NA
ND*
NA
ND*
53 ±11
NA
ND*
Collected 11/02/87
ND*
ND*
ND*
NA
ND*
Collected 03/1 1/88
ND*
ND*
0.1 ± 0.07
9.5 ± 68
ND*
Collected 05/23/88
ND
ND*
ND*
ND*
239pu
fCi/g/ash
NA
NA
ND*
NA
ND*
205 ± 27
NA
ND*
11 ±9
8.9 ± 3.6
39 ±17
NA
ND*
ND*
4.6 ± 3.9
52 ± 14
24 ± 7.8
ND*
6.7 ± 4.6
6.3 ± 3.1
3.1 ± 7.3
ND*
90Sr
fCi/g/ash
NA
NA
NA
NA
NA
NA
NA
1.7 ±0.1
NA
NA
NA
NA
1.3 ±0.1
NA
NA
NA
NA
2.2 ± 1.3
NA
NA
NA
1.1 ±0.1
(continued)
59
-------
Table 12. Continued
Tissue
Kidney
Liver
Lung
Muscle
Rumen
137C3
(pCi/Kg)
60 ± 14
35 ±2
ND
50 ±17
Contents
Bone
Muscle
Liver
Lung
Rumen
NA
ND
ND
ND
Contents ND
Bone
ND =
ND* -
NA «.
NA
Not Detected
Counting error exceeds
Not Analyzed
3H
(uCi/L)
Mule Deer No.
39 ± 0^002
NA
NA
NA
ND
NA
Mule Deer No.
NA
NA
NA
NA
NA
reported activity
238PU
fCi/g/ash
3 Collected 09/13/88
NA
ND*
ND*
6.9 ± 54
NA
ND*
4 Collected 10/24/88
ND*
ND*
6.3 ± 5.9
9.9 ± 8.5
ND*
239pu
fCi/g/ash
NA
5.8 ± 3.3
1.3 ±0.6
7.6 ± 3.8
ND
ND*
4.2 ± 2.0
ND*
8.6 ± 4.4
11 ±8
ND*
90Sr
fCi/g/ash
NA
NA
NA
NA
30 ± 13
1 ±0.1
NA
NA
NA
NA
0.5 ± 0.05
5.2.5 Thermolumlnescent Dosimetry Network
B. B. Dicey
EPA's primary method of measuring external
radiation exposures is the thermoluminescent
dosimeter (TLD). Calendar year 1988 repre-
sented the first full year of operations using the
Panasonic TLD system. This system, installed
in 1987, provides greater sensitivity and
precision than was possible using film or the
previous TLD system. There is an added ad-
vantage In that the dosimeters used are more
nearly tissue-equivalent. This facilitates correlat-
ing individual measured exposures with the ab-
sorbed biological dose equivalent.
Network Design
The TLD network is designed to measure total
ambient gamma exposures at specified locations
rather than exposures to specific individuals. This
method is generally preferred because of multiple
uncontrollable variables associated with personnel
monitoring. Measuring environmental ambient
gamma exposures In fixed locations provides a
reproducible Index which can then be easily
correlated to the maximum exposure an individual
would have received were he continuously present
at that location. In addition to the fixed locations,
several Individuals residing within and outside
estimated fallout zones from past nuclear tests at
the NTS have been monitored. These individuals
are monitored both to determine individual
exposures and to confirm the validity of correlating
fixed-site ambient gamma measurements to
projected Individual exposures.
A network of environmental stations and monitored
personnel has been established In locations
encircling the NTS. Monitoring locations are as
shown on Figure 20. This arrangement permits
both an estimate of average background exposures
and prompt detection of any increase due to NTS
activities.
Net exposure to an individual is determined by
comparing the results of each dosimeter issued to
that individual with the results obtained from the
previous four dosimeters located at the associated
reference background location established for that
individual. The reference background dosimeters
measure ambient gamma radiation exposure. An
associated reference background dosimeter
reading that varies by greater than a statistically
determined amount from the historical mean is not
used in calculating net exposures to individuals
because this variation could represent an anomaly
or a contribution from NTS activities.
60
-------
Monitoring of off-site personnel is accomplished
with the Panasonic UD-802 dosimeter. This
dosimeter contains two elements of Li2B4O/:Cu and
two of CaS04:Tm phosphors. The four elements
are behind 14, 300,300, and 1000 mg/cm2 filtration,
respectively. Monitoring of off-site environmental
stations is accomplished with the Panasonic
UD-814 dosimeter. This dosimeter contains a single
element of Li2B4Or:Cu and three replicate
CaS04:Tm elements. The first element is filtered by
14 mg/cm2 of plastic and the remaining three are
filtered by 1000 mg/cm2 of plastic and lead. The
three replicate phosphors are used to provide
Improved statistics and extended response range.
5.2.6 Results of TLD Monitoring
5.2.6.1 Off-Site Personnel
During 1988 a total of 61 individuals living in
areas surrounding the Nevada Test Site were
provided with personnel TLD dosimeters. All
measured exposures are presumed to be due
to gamma radiation and hence are numeri-
cally equivalent to absorbed dose.
Of the 61 individuals monitored, 57 showed
zero detectable exposure above that measured
at the associated reference background loca-
tion. One individual did not return the
dosimeter for processing. Three apparent in-
dividual exposures were slightly greater than
the associated reference background. These
ranged from 3.6 to 10.0 mrem for the year.
Each of these represented total exposures ob-
tained from several dosimeters worn during the
year. Apparent exposures to an individual
dosimeter of less than three times the as-
sociated reference background are considered
to be within the range of normal variation for the
Panasonic TLD system. Therefore, none of the
three apparent net individual exposures are
considered to represent an abnormal occur-
rence. Figure 21 illustrates that the TLD
monitoring results for off-site personnel were all
well within the range of the associated refer-
ence background values. Table 13 lists the
results of off-site personnel TLD monitoring for
1988.
50 100 150
Scale in Kilometers
Figure 20. Locations Monitored with TLDs.
61
-------
PERSONNEL vs BACKGROUND TLD RESULTS
Alamo — Corn Cr«*k Station*
Alamo Austin Bvatty Blu* Cagl* Calient* Cadar City Compl«K I Corn Cr««k
a TLD R««ult. °C °r°^I « Mean «»f. Bkg.
M? ?,?„?„
Coyote Crystal
a TLD Results
D. Valley Delta
3X Mean Pel
Ely
Geldfl«ld
a TLD R«
Hlko Met Cr««k Ind Spring Koy»n'»
Background Location
UNLV USDI — LV Lovado*
Figure 21. Personnel vs. Background TLD Results.
62
-------
mR/m
Res
S
o
Mllford — Round Mountain Station*
U
o
1
*.
o
1
20
a o
fiW
V
tDa
Mllford Mlna
II M HIM 11 M 11 Ml 11 M 1111 11 I Ml
Nyolo Overton Pa hrumpPenoyer Ploche
Rach«l
n i mi nun i mi nm
Round Ml
60
Background Location
TLD Rexult* 3X Mean Ref. Bkg.
Shoshone — Twin Spring* Station*
30 -
ao-
an
co
a a
a-i n a
Sho*hone Sliver Pk. Stone Cab.
O TLD Reeult*
St. G«orgo
Tonopah
Twin Sprg*
Background Location
3X Mean Ref. Bkg.
Figure 21. (Continued).
5.2.6.2 Off-Site Stations
During 1988 a total of 154 off-site stations
were monitored to determine background
ambient gamma radiation levels. The annual
adjusted dose equivalent (mrem/year) was
calculated by multiplying the average daily
rate for each station by 365.
During 1988 the maximum apparent net annual
exposure to an off-site station was measured to
be 225 mrem. This exposure, at Warm Springs,
NV, was felt to be due to high levels of naturally
occurring radioactive material in a stream.
During the first two quarters of 1988 the TLD
was located adjacent to the stream. Average
ambient gamma radiation readings measured
by TLDs were 0.85 mR/day. The TLD was
moved away from the stream for the second
half of 1988. Average readings with the TLD lo-
cated away from the stream were 0.38 mR/day.
If the TLD had been located away from the
stream for the entire year, the adjusted dose
63
-------
Table 13. Annual Summary TLO Results - Off site Personnel - 1988
ASSOCIATED REFERENCE
BACKGROUND STATION RESIDENT
LOCATION No.
(See Table 14)
*** CALIFORNIA ***
DEATH VALLEY JCT.CA
DEATH VALLEY JCT, CA
SHOSHONE, CA
*** NEVADA ***
ALAMO, NV
AUSTIN, NV
BEATTY.NV
BEATTY, NV
BLUE EAGLE RANCH, NV
CALJENTE, NV
CAUENTE, NV
COMPLEX 1.NV
COMPLEX 1.NV
CORN CREEK, NV
CORN CREEK, NV
CORN CREEK, NV
COYOTE SUMMIT, NV
COYOTE SUMMIT, NV
CRYSTAL, NV
ELY, NV
ELY, NV
GABBS, NV
GABBS, NV
OLDFIELD, NV
304
331
60
22
329
38
21
9
2
336
10
11
25
56
223
15
14
301
47
233
302
305
7
MEASUREMENT PERIOD
START END
DATE DATE
01/07/88 01/06/89
01/07/88 01/05/89
01/04/88 01/04/89
01/05/88 01/04/89
01/13/88 01/12/89
01/05/88 01/06/89
01/06/88 01/06/89
01/05/88 01/04/89
01/05/88 01/04/89
02/03/88 01/04/89
01/06/88 01/05/89
01/06/88 01/05/89
01/04/88 01/03/89
01/04/88 01/03/89
01/04/88 01/03/89
01/05/88 01/04/89
01/05/88 01/04/89
01/04/88 01/04/89
01/05/88 01/11/89
01/04/88 01/11/89
01/14/88 01/10/89
01/14/88 03/11/88
01/14/88 01/11/89
DOSE
EQUIV. RATE
(mrem/day)
MAX.
0.57
0.18
0.21
0.22
0.41
0.43
0.20
0.18
0.39
0.44
0.32
0.37
0.10
0.17
0.23
0.32
0.27
0.17
0.27
0.28
0.32
0.28
0.49
MIN.
0.05
0.07
0.02
0.04
0.08
0.09
0.03
0.02
0.09
0.08
0.05
0.08
0.02
0.05
0.01
0.03
0.09
-1.16
0.04
0.05
0.03
0.17
0.04
AVG.
0.22
0.15
0.10
0.13
0.20
0.23
0.13
0.11
0.22
0.16
0.19
0.22
0.06
0.11
0.08
0.17
0.16
0.01
0.15
0.15
0.12
0.23
0.20
NET
ANNUAL COMMENTS
DOSE
(mrem)*
10.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
(continued)
-------
Table 13. (Continued)
ASSOCIATED REFERENCE
BACKGROUND STATION RESIDENT
LOCATION
(See Table 14)
OLDFIELD, NV
GOLDFIELD, NV
HIKO, NV
HOT CK RNCH, NV
INDIAN SPRINGS, NV
INDIAN SPRINGS, NV
IONE, NV
IONE, NV
KOYEN'S RANCH, NV
LAS VEGAS (UNLV),NV
LAS VEGAS (UNLV), NV
LAS VEGAS (USDI).NV
LAS VEGAS (USDI), NV
LAVADA'S MARKET. NV
LAVADA'S MARKET, NV
MINA, NV
MON SYS LAB ROOM 22
NYALA, NV
OVERTON, NV
OVERTON, NV
PAHRUMP, NV
PENOYER FARMS, NV
PIOCHE, NV
RACHEL, NV
RACHEL, NV
RACHEL, NV
ROUND MT, NV
SILVER PEAK, NV
No.
19
40
232
3
37
6
333
343
300
49
335
326
297
332
342
307
339
18
348
57
36
248
293
264
54
334
299
341
MEASUREMENT PERIOD
START END
DATE DATE
01/05/88 01/11/89
01/06/88 01/11/89
01/04/88 01/04/89
01/06/88 01/05/89
01/04/88 01/03/89
01/04/88 01/03/89
02/09/88 10/18/88
10/18/88 01/10/89
01/11/88 01/12/89
01/04/88 01/03/89
01/15/88 10/04/88
01/04/88 01/03/89
01/04/88 01/03/89
01/05/88 10/04/88
10/04/88 01/04/89
01/14/88 01/10/89
09/15/88 01/11/89
01/05/88 01/04/89
12/01/88 01/03/89
01/05/88 11/28/88
01/04/88 01/04/89
01/05/88 01/05/89
01/05/88 01/04/89
01/11/88 01/05/89
01/06/88 01/03/89
01/11/88 01/05/89
01/13/88 01/12/89
10/08/88 01/11/89
DOSE
EQUIV. RATE
(mrem/dav)
MAX.
0.56
0.48
0.24
0.28
0.14
0.16
0.55
0.19
0.26
0.22
0.24
0.18
0.13
0.25
0.19
0.36
0.27
0.19
0.28
0.17
0.30
0.39
0.35
0.25
0.33
0.47
0.11
MIN.
0.03
0.04
0.05
0.07
0.04
0.00
0.08
0.15
0.03
0.03
0.03
0.03
0.02
0.08
0.01
0.03
0.13
0.04
0.04
0.02
0.04
0.10
0.09
0.04
0.08
0.07
0.10
AVG.
0.16
0.15
0.14
0.17
0.08
0.07
0.25
0.17
0.14
0.13
0.11
0.08
0.06
0.14
0.11
0.14
0.19
0.12
0.14
0.07
0.18
0.20
0.18
0.12
0.19
0.19
0.10
NET
ANNUAL COMMENTS
DOSE
(mrem)*
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
TLD NOT RETURNED
3.60
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0.00
(continued)
-------
.8
Table 13. (Continued)
ASSOCIATED REFERENCE
BACKGROUND STATION
LOCATION
(Sea Table 14)
STONE CABIN RNCH, NV
TONOPAH, NV
TTR. NV
TWIN SPRGS RNCH, NV
*** UTAH ***
CEDAR CITY, UT
DELTA, UT
.DELTA. UT
MILFORD, UT
MILFORD. UT
ST. GEORGE, UT
DOSE
MEASUREMENT PERIOD EQUIV. RATE
RESIDENT imrem/davl
No.
29
42
52
8
44
345
344
347
346
45
$TABT END
DATE DATE MAX. MIN.
01/05/88 01/04/89 0.33 0.08
01/06/88 01/13/89 0.60 0.05
01/04/88 01/04/89 0.36 0.05
01/05/88 01/04/89 0.31 0.08
01/05/88 01/04/89 0.29 0.04
11/03/88 01/06/89 0.15 0.08
11/03/88 01/06/89 0.16 0.12
11/03/88 01/06/89 0.28 0.19
11/03/88 01/06/89 0.20 O.I 8
01/08/88 01/06/89 0.26 0.04
* Net annual dose = (Average Gross mR/day * 365.25) - (Adjusted Annual Dose Equivalent for Ref. Bkg.
Apparent net annual dose values < =
# of People Monitored
Ave. Max mrem/day
Ave. Min mrem/day
Ave. Mean mrem/day
61
0.29
0.04
0.15
2 mrem are reported as zero.
Min. Net Annual Dose (mrem)
Max. Net Annual Dose (mrem)
Mean Net Annual Dose (mrem)
AVG.
0.21
0.18
0.21
0.21
0.16
0.12
0.14
0.23
0.19
0.11
Station)
NET
ANNUAL COMMENTS
DOSE
(mrem)*
0.00
0.00
4.60
0.00
0.00
0.00
0.00
0.00
0.00
0.00
0
10
0.30
-------
equivalent for that station would have been ap-
proximately 139 mrem.
The minimum net annual exposure to an off-site
station was measured to be 23 mrem, noted at
several sites. The mean net annual exposure
for all off-site stations of 72 mrem represented a
slight decrease from that reported in previous
years. A major factor contributing to this
decrease was that, for most of 1988, associated
reference background readings no longer re-
quired adjustment to account for differing sen-
sitivities of the Panasonic and the former
Harshaw TLD systems.
Table 14 summarizes the results of off-site sta-
tion TLD monitoring for 1988.
Preliminary information gathered during 1988
indicates the possibility that some TLD readings
may be slightly lowered due to self-annealing of
the phosphors during the hottest portion of the
year. This phenomenon will be studied in
greater detail during the coming year.
Because of the great range in the results, an
average for all off-site station TLDs is not an ap-
propriate tool for estimating individual ex-
posures. Environmental ambient radiation
levels vary markedly with natural radioactivity in
the soil, with altitude, and other factors. If en-
vironmental TLD data is to be used in estimating
the background radiation exposure of an in-
dividual, the dose equivalent for the station
location closest to that individual would be the
most appropriate reference point.
Figures 22 - 26 provide a general summary of
mean annual background radiation levels at es-
tablished off-site locations in Arizona, California,
Nevada, and Utah, as well as a mean of all
monitored locations.
5.2.6.3 Comparison with Direct Exposure
Measurements
When TLD results are compared with results
of co-located Pressurized lonization Cham-
bers (PICs), an average difference of ap-
proximately 38% is noted. The range of
differences was 24 to 55%. A uniform over-
response of PIC vs TLD continues to be ob-
served. This difference is attributed to
several factors: (1) The PIC measures
ionization in air (the Roentgen) while the TLD
measures energy deposited in matter (the
rad). Results of the two methods are not ad-
justed to account for this difference; (2) The
PIC is an exposure rate measuring device,
sampling every five seconds, while the TLD
as an integrating dosimeter is analyzed ap-
proximately once each quarter. Some reduc-
tion in TLD results may be due to a small
amount of loss due to normal fading (studies
by Panasonic have shown this loss to be
minimal over the sampling period used); (3)
PICs are more sensitive to lower energy
gamma radiation than are the TLDs. A
review of manufacturer's specifications for
the PIC and TLD systems shows their
responses to be close to linear above ap-
proximately 80 and above approximately 150
keV, respectively; and (4) The PIC units are
calibrated by the manufacturer against 60Co,
while the TLDs are calibrated using 137Cs.
No adjustment is made to account for the dif-
fering energies at which the two systems are
calibrated. Figure 27 correlates PIC and TLD
results for 1988.
67
-------
Table 14. Annual Summary TLO Results - Off site Stations - 1988
REFERENCE BACKGROUND
STATION LOCATIONS
*** ARIZONA***
COLORADO CITY, AZ
JACOB'S LAKE, AZ
PAGE, AZ
*** CALIFORNIA***
BAKER, CA
BARSTOW, CA
BISHOP, CA
DEATH VALLEY JCT, CA
FURNACE CREEK, CA
INDEPENDENCE, CA
LONE PINE, CA
MAMMOTH GEOTHERMAL
MAMMOTH LAKES, CA
OLANCHA. CA
RIDGECREST, CA
SHOSHONE.CA
VALLEY CREST, CA
*** NEVADA ***
ALAMO, NV
AMERICAN BORATE, NV
ATLANTA MINE, NV
AUSTIN, NV
YEAR
STATION
ESTAB-
LISHED
1985
1985
1985
1971
1971
1971
1971
1971
1971
1971
1972
1972
1971
1971
1971
1980
1971
1977
1985
1971
MEASUREMENT PERIOD
START END
DATE DATE
10/27/87 11/01/88
10/27/87 11/01/88
10/28/87 11/01/88
11/03/87 11/02/88
11/03/87 11/02/88
11/04/87 11/02/88
01/07/88 01/06/89
01/07/88 01/06/89
11/04/87 11/02/88
11/04/87 11/02/88
11/04/87 11/02/88
11/05/87 11/02/88
11/04/87 11/02/88
11/03/87 11/02/88
11/03/87 11/01/88
01/07/88 01/06/89
10/30/87 11/03/88
01/07/88 01/04/89
12/07/87 12/01/88
02/03/88 11/22/88
DOSE
EQUIVALENT RATE
(mR/day)
MAX.
0.19
0.29
0.19
0.23
0.27
0.38
0.29
0.21
0.23
0.25
0.29
0.34
0.23
0.22
0.18
0.15
0.24
0.34
0.20
0.42
MIN.
0.11
0.14
0.10
0.19
0.24
0.23
0.18
0.15
0.20
0.22
0.25
0.20
0.19
0.14
0.15
0.08
0.13
0.24
0.13
0.27
AVG.
0.15
0.23
0.14
0.22
0.25
0.28
0.23
0.18
0.22
0.24
0.27
0.27
0.21
0.18
0.17
0.12
0.19
0.28
0.18
0.34
ADJUSTED
DOSE
EQUIVALENT
(mR/year)
56
85
51
80
92
101
85
65
81
87
100
97
76
67
62
43
69
104
65
124
COMMENTS
No data 1973 -1975
No data 1973 -1975
No data 1974 - 1980
No data 1973 -1976
(continued)
-------
Table 14. (Continued)
REFERENCE BACKGROUND
STATION LOCATIONS
BATTLE MOUNTAIN, NV
BEATTY, NV
BLUE EAGLE RANCH, NV
BLUE JAY, NV
CACTUS SPRINGS, NV
CALJENTE, NV
CARP, NV
CHERRY CREEK, NV
CLARK STATION, NV
COALDALE, NV
COMPLEX 1.NV
CORN CREEK, NV
CORTEZ RD/HWY 278.NV
COYOTE SUMMIT, NV
CRESCENT VALLEY, NV
CRYSTAL, NV
CURRANT, NV
CURRIE, NV
DIABLO MAINT STA, NV
DUCKWATER, NV
ELGIN, NV
ELKO, NV
ELY. NV
EUREKA, NV
FALLON, NV
FLYING DIAMND CP, NV
GABBS, NV
GEYSER RANCH, NV
YEAR
STATION
ESTAB-
LISHED
1985
1971
1971
1971
1971
1971
1977
1985
1971
1983
1977
1971
1985
1971
1985
1983
1971
1971
1971
1971
1971
1971
1971
1971
1985
1985
1983
1971
MEASUREMENT PERIOD
START END
DATE DATE
12/15/87 11/29/88
01/05/88 01/04/89
01/05/88 01/04/89
01/06/88 01/05/89
11/02/87 11/01/88
10/27/87 11/01/88
10/27/87 11/03/88
12/10/87 12/01/88
01/04/88 01/04/89
02/09/88 11/08/88
10/28/87 11/02/88
11/02/87 11/01/88
12/15/87 11/29/88
10/28/87 11/03/88
12/16/87 11/29/88
11/05/87 11/01/88
01/06/88 01/05/89
12/10/87 12/01/88
01/04/88 01/06/89
01/06/88 01/05/89
10/27/87 11/03/88
12/15/87 11/29/88
12/09/87 12/01/88
01/06/88 01/06/89
12/14/87 12/01/88
10/30/87 11/02/88
02/09/88 11/16/88
12/07/87 12/01/88
DOSE
EQUIVALENT RATE
(mR/day)
MAX.
0.21
0.40
0.19
0.42
0.16
0.25
0.22
0.25
0.36
0.26
0.29
0.13
0.26
0.31
0.25
0.19
0.34
0.27
0.41
0.31
0.32
0.20
0.20
0.33
0.19
0.20
0.17
0.26
MIN.
0.11
0.25
0.12
0.27
0.09
0.15
0.11
0.17
0.24
0.22
0.16
0.07
0.16
0.17
0.11
0.15
0.21
0.17
0.28
0.21
0.19
0.10
0.12
0.22
0.09
0.10
0.13
0.17
AVG.
0.16
0.31
0.16
0.34
0.13
0.20
0.17
0.22
0.30
0.24
0.23
0.09
0.21
0.27
0.18
0.17
0.26
0.23
0.33
0.25
0.27
0.16
0.17
0.27
0.15
0.15
0.15
0.22
ADJUSTED
DOSE
EQUIVALENT
(mR/year)
60
113
57
125
47
73
61
81
109
89
84
34
78
98
65
61
97
86
120
91
97
57
63
98
54
56
56
82
COMMENTS
No data 1972 -1984
No data 1973
Formerly Desert Game
No data 1972 -1984
No data 1972 -1984
No data 1987
No data 1973 -1976
(continued)
-------
Table 14. (Continued)
YEAR
REFERENCE BACKGROUND STATION
STATION LOCATIONS
GOLDFIELD, NV
GROOM LAKE, NV
HALLOWAY RANCH. NV
HANCOCK SUMMIT.NV
HIKO, NV
HOT CREEK RANCH, NV
INDIAN SPRINGS, NV
IONE, NV
KIRKEBY RANCH, NV
KOYEN'S RANCH, NV
LAS VEGAS (UNLV), NV
LAS VEGAS (USDI).NV
LASVEGAS(AIRPRT),NV
LATHROP WELLS, NV
LAVADA'S MARKET, NV
UDA, NV
LOVELOCK, NV
LUND.NV
MANHATTAN, NV
MEDUN'S RANCH, NV
MESQUITE, NV
MINA, NV
MOAPA, NV
MTN MEADOWS RNCH, NV
NASH RANCH, NV
NYALA, NV
OVERTON, NV
PAHRUMP, NV
ESTAB-
LISHED
1971
1971
1971
1971
1971
1971
1971
1971
1973
1971
1981
1971
1972
1971
1981
1971
1985
1971
1971
1982
1971
1983
1983
1971
1985
1971
1982
1971
MEASUREMENT PERIOD
START END
DATE DATE
02/08/88 11/07/88
11/05/87 11/08/88
01/06/88 01/05/89
10/29/87 11/03/88
10/29/87 11/03/88
01/06/88 01/05/89
11/02/87 11/01/88
02/09/88 11/16/88
12/07/87 12/01/88
10/28/87 11/03/88
01/04/88 01/03/89
01/04/88 01/03/89
01/04/88 01/03/89
01/05/88 01/04/89
01/05/88 01/04/89
02/11/88 11/08/88
12/15/87 11/30/88
12/09/87 12/01/88
02/03/88 11/17/88
10/28/87 11/01/88
10/30/87 11/01/88
02/09/88 11/16/88
10/27/87 11/01/88
10/06/87 01/04/89
10/30/87 11/03/88
01/05/88 01/04/89
10/27/87 11/01/88
11/03/87 11/01/88
DOSE
EQUIVALENT RATE
(mR/day)
MAX.
0.21
0.22
0.38
0.37
0.18
0.28
0.15
0.24
0.19
0.23
0.13
0.19
0.16
0.27
0.29
0.22
0.20
0.21
0.32
0.30
0.17
0.22
0.21
0.21
0.21
0.25
0.17
0.22
MIN.
0.20
0.18
0.24
0.24
0.10
0.18
0.08
0.22
0.11
0.14
0.05
0.11
0.08
0.03
0.19
0.21
0.09
0.14
0.28
0.18
0.09
0.21
0.10
0.12
0.10
0.15
0.06
0.08
AVG.
0.21
0.20
0.30
0.32
0.14
0.22
0.11
0.23
0.16
0.18
0.08
0.14
0.11
0.18
0.23
0.22
0.15
0.19
0.30
0.24
0.13
0.21
0.15
0.16
0.16
0.21
0.11
0.13
ADJUSTED
DOSE
EQUIVALENT
(mR/year)
75
72
108
116
49
82
41
85
57
67
29
49
39
66
85
79
56
69
111
87
48
78
56
60
59
75
40
46
COMMENTS
— • . .
BLM Office
Formerly Tikaboo
Formerly Casey's
(continued)
-------
Table 14. (Continued)
YEAR
REFERENCE BACKGROUND STATION
STATION LOCATIONS
PENOYER FARMS, NV
PINE CREEK RANCH, NV
PIOCHE, NV
QUEEN CITY SMT, NV
RACHEL, NV
REED RANCH, NV
RENO, NV
ROUND MT, NV
RUBY VALLEY, NV
S DESERT COR CTR, NV
SCHURZ, NV
SHERI'S RANCH, NV
SILVER PEAK, NV
SPRINGDALE, NV
STEWARD RANCH, NV
STONE CABIN RNCH, NV
SUNNYSIDE, NV
TEMPIUTE, NV
TONOPAH, NV
TONOPAH TEST RNG, NV
TWIN SPRGS RNCH, NV
UHALDE'S RNCH, NV
US ECOLOGY, NV #2
WARM SPRINGS, NV
WELLS, NV
WINNEMUCCA, NV
YOUNG'S RANCH, NV
YUCCA - AMARGOSA CMS
ESTAB-
LISHED
1971
1971
1971
1971
1977
1971
1987
1971
1971
1983
1985
1971
1987
1971
1987
1977
1971
1971
1971
1972
1971
1971
1971
1971
1971
1985
1973
1988
MEASUREMENT PERIOD
START END
DATE DATE
10/28/87 11/02/88
10/28/87 11/03/88
10/27/87 11/01/88
01/04/88 01/06/89
10/28/87 11/03/88
01/04/88 01/06/89
12/14/87 11/30/88
02/03/88 11/17/88
12/17/87 11/29/88
11/02/87 11/01/88
12/14/87 12/01/88
10/30/87 05/03/88
02/09/88 11/16/88
01/06/88 01/05/89
12/08/87 12/01/88
01/05/88 01/04/89
12/07/87 12/01/88
10/29/87 11/02/88
02/09/88 11/08/88
02/10/88 11/15/88
01/05/88 01/04/89
10/28/87 11/02/88
01/06/88 01/04/89
01/04/88 01/04/89
12/16/87 11/29/88
12/15/87 11/29/88
02/03/88 11/17/88
10/20/88 01/18/89
DOSE
EQUIVALENT RATE
(mR/day)
MAX.
0.31
0.31
0.20
0.45
0.29
0.39
0.20
0.28
0.27
0.13
0.26
0.26
0.18
0.40
0.28
0.40
0.24
0.29
0.27
0.26
0.36
0.29
0.40
0.88
0.21
0.23
0.20
0.15
MIN.
0.19
0.20
0.12
0.28
0.17
0.24
0.09
0.26
0.16
0.08
0.15
0.26
0.15
0.24
0.21
0.22
0.08
0.19
0.26
0.25
0.22
0.18
0.24
0.35
0.13
0.12
0.19
0.15
AVG.
0.25
0.26
0.16
0.35
0.24
0.30
0.15
0.27
0.23
0.11
0.22
0.26
0.17
0.31
0.25
0.30
0.16
0.23
0.26
0.25
0.29
0.24
0.31
0.62
0.17
0.18
0.20
0.15
ADJUSTED
DOSE
EQUIVALENT
(mR/year)
90
95
60
127
86
108
56
98
84
39
80
95
60
112
93
110
57
86
96
92
106
86
113
225**
62
65
73
53
COMMENTS
No data 1972 -1984
No data 1972 -1984
(continued)
-------
Table 14. (Continued)
REFERENCE BACKGROUND
STATION LOCATIONS
YUCCA -BRIGHT RES.
YUCCA -CL1 03
YUCCA -CL108
YUCCA -CL1 13
YUCCA -CL1 17
YUCCA -CL128
YUCCA -CL98
YUCCA - HALE RANCH
YUCCA- MILE 47
YUCCA - NY1
YUCCA -NY11
YUCCA-NY16
YUCCA - NY21
YUCCA -NY26
YUCCA -NY36
YUCCA -NY41
YUCCA - NY46
YUCCA - NY51
YUCCA -NY56
YUCCA - NY6
YUCCA-NICKELL QUIK-S
*** UTAH ***
BOULDER, UT
BRYCE CANYON, UT
CEDAR CITY, UT
DELTA, UT
YEAR
STATION
ESTAB-
LISHED
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1988
1985
1985
1971
1985
MEASUREMENT PERIOD
START END
DATE DATE
10/12/88 01/18/89
08/29/88 01/19/89
08/29/88 01/19/89
08/29/88 01/19/89
08/29/88 01/19/89
08/29/88 01/18/89
08/29/88 01/19/89
10/12/88 01/19/89
10/11/88 01/18/89
08/29/88 01/18/89
08/29/88 01/18/89
08/29/88 01/18/89
09/01/88 01/18/89
09/01/88 01/18/89
09/01/88 01/18/89
09/02/88 01/18/89
09/02/88 01/18/89
09/02/88 01/18/89
09/02/88 01/18/89
08/31/88 01/18/89
10/12/88 01/18/89
12/08/87 09/13/88
12/08/87 09/13/88
12/07/87 09/12/88
01/05/88 01/06/89
DOSE
EQUIVALENT RATE
(mR/day)
MAX.
0.22
0.08
0.09
0.08
0.08
0.12
0.08
0.13
0.25
0.12
0.13
0.09
0.13
0.19
0.28
0.30
0.20
0.28
0.18
0.15
0.20
0.21
0.18
0.17
0.24
MIN.
0.22
0.05
0.04
0.04
0.05
0.08
0.07
0.13
0.25
0.08
0.12
0.06
0.11
0.19
0.27
0.28
0.20
0.25
0.17
0.15
0.20
0.11
0.08
0.06
0.14
AVG.
0.22
0.06
0.07
0.06
0.06
0.10
0.08
0.13
0.25
0.10
0.13
0.08
0.12
0.19
0.28
0.29
0.20
0.26
0.17
0.15
0.20
0.17
0.15
0.13
0.20
ADJUSTED
DOSE COMMENTS
EQUIVALENT
(mR/year)
79
23
25
23
23
36
28
46
90
37
47
28
43
69
101
106
72
96
64
55
74
63
54
46
73
(continued)
-------
Table 14. (Continued)
YEAR
REFERENCE BACKGROUND STATION
STATION LOCATIONS
DUCHESNE, UT
ENTERPRISE, UT
PERRON, UT
GARRISON, UT
GRANTSVILLE, UT
GREEN RIVER, UT
GUNNISON, UT
IBAPAH, UT
KANAB. UT
LOA.UT
LOGAN, UT
LUND, UT
MILFORD, UT
MONTICELLO, UT
NEPHI, UT
PAROWAN, UT
PRICE, UT
PROVO, UT
SALT LAKE CITY, UT
ST. GEORGE, UT
TROUT CREEK, UT
VERNAL, UT
VERNON, UT
WENDOVER, UT
WILLOW SPRGS LDGE, UT
ESTAB-
LISHED
1985
1973
1985
1971
1985
1985
1985
1985
1985
1985
1985
1985
1972
1985
1985
1985
1985
1985
1982
1971
1985
1985
1985
1971
1985
MEASUREMENT PERIOD
START END
DATE DATE
01/07/88 01/04/89
12/07/87 09/15/88
10/29/87 01/04/89
12/08/87 12/01/88
01/06/88 01/05/89
10/28/87 11/02/88
12/08/87 09/14/88
12/07/87 12/01/88
10/27/87 11/01/88
12/08/87 09/13/88
01/05/88 01/03/89
12/07/87 09/12/88
12/09/87 09/14/88
10/28/87 11/02/88
01/05/88 01/06/89
12/07/87 09/14/88
10/29/87 01/04/89
01/05/88 01/05/89
01/04/88 01/04/89
12/09/87 09/12/88
12/09/87 12/01/88
01/07/88 01/04/89
01/06/88 01/05/89
12/16/87 11/28/88
01/06/88 01/05/89
DOSE
EQUIVALENT RATE
(mR/day)
MAX.
0.21
0.28
0.19
0.18
0.23
0.22
0.17
0.25
0.16
0.31
0.19
0.24
0.22
0.24
0.18
0.19
0.19
0.21
0.23
0.15
0.19
0.22
0.22
0.21
0.19
MIN.
0.12
0.15
0.10
0.10
0.14
0.11
0.06
0.18
0.10
0.16
0.14
0.20
0.15
0.16
0.11
0.12
0.11
0.12
0.16
0.07
0.12
0.12
0.15
0.09
0.12
AVG.
0.17
0.23
0.14
0.15
0.18
0.17
0.13
0.23
0.12
0.25
0.16
0.22
0.19
0.20
0.15
0.16
0.15
0.15
0.19
0.12
0.16
0.18
0.18
0.16
0.16
ADJUSTED
DOSE
EQUIVALENT
(mR/year)
61
84
52
54
67
63
46
83
45
91
60
81
70
74
54
57
54
56
68
42
57
65
66
59
58
COMMENTS
No data 1973 -1976
No data 1973 -1984
No data 1972 -1984
(continued)
-------
Table 14. (Continued)
No. of Stations Monitored
Avg. Max mR/day
Avg. Min mR/day
Avg. Mean mR/day
Max. Net Annual Exposure
Min. Net Annual Exposure
Mean Net Annual Exposure
157
0.24
0.16
0.20
225
23
72.3
Statistics of
•let Otr
2nd Qtr.
3rd Qtr:
4th Qtr:
YEAR
1988 Offsite Station TLD Results:
#
C.V.
OH43
0.085
0.074
0.062
0.066
Best
Std. Dev.
Onm
0.016
0.014
0.012
0.013
#
REPS
fiPQ
786
876
870
3231
#
RECORDS
131
148
145
542
#
STATS
117
131
147
143
147
NOTE TO WARM SPRINGS, NV, TLD RESULTS:
Anomalous high reading due to TLD located adjacent to stream containing high amount of Radium/Radon. TLD relocated away
from stream 3rd and 4th quarters.
Average results with TLD near stream = 0.85 mR/day.
Average results with TLD located away from stream = 0.38 mR/day.
If TLD had been located away from stream for entire year, adjusted dose equivalent would be approximately 139 mrem.
-------
7O
6O
SO
4O
3O
2O
1O
1OO
90
ao
70
6O
SO
4O
30
2O
1O
0
MEAN TLD RESULTS: ALL OFF —SITE STATIONS
1971 - 198S
Figure 22.
I
X
X
1971 1973 1975 1977
1979
Imar
19S1 19S3 1985
ISO
I4O
130
1 2O
1 1O
1 OO
9O
8O
70
6O
SO
4O
30
2O
1O
O
MEAN TLD RESULTS - ARIZONA STATIONS
1971 — 1 988
X
Figure 23.
x:
x.
1973 1975 1 977
1979 1981
Y.ar
1983 1 985 1987
1 SO
1 4O
ISO
1 2O
1 1O
1 OO
90
so
7O
6O
30
4O
3O
2O
1 O
O
MEAN TLD RESULTS — CALIFORNIA STATIONS
1971 - 1968
Figure 24.
i
X P1
I
i
I
I
1973 197S 1977
1979
Y«or
1981 1983 198S 1987
Figures 22 - 24. Mean TLD Results -1988.
75
-------
BO -
70 -
60 -
50 -
AO -
SO -
20 -
1 O -
00 -
90 -
80 -
7O -
6O -
50 -
AO -
30 -
20 -
1 O -
O -
MEAN TLD RESULTS — NEVADA STATIONS
1971 — 1988
X
Figure 25.
I Kx -V Kx
173
X
XI Kxl
xl -XI Kxl Kxl KX
1971 1973 1975 1977
1979
Y«ar
1981 1983 1985 1987
150
140 -
130 -
120 -
110-
1OO -
90
80
70 -
60 -
50 -
*O —
30 -
2O -
1O -
MEAN TLD RESULTS — UTAH STATIONS
1971 — 1988
Figure 26.
Xl KXI r XI K XI KX
XI KX
x:
XI K X
XI r x
1971 1973 1975 1977
1 979
Y«ar
1981 1983 1985 1987
COMPARISON OF TLD AND PIC RESULTS
1 988
Figures 25 - 27. Mean TLD Results and Comparison of TLD and PIC Results -1988.
76
-------
5.2.7 Pressurized Ion Chamber (PIC) Network
C. A. Fontana
The Pressurized Ion Chamber is a spherical
shell filled with argon gas to 25 times atmos-
pheric pressure. Inside the chamber is a spheri-
cal electrode with a charge opposite to the outer
shell. When gamma radiation penetrates the
sphere, ionization of the gas occurs and the ions
are collected by the electrode, the current is
measured and the intensity of the radiation field
is determined.
There are 28 PICs deployed around the Nevada
Test Site, of these, 18 are at Community Monitoring
Stations described in Section 6.1. In addition, there
are ten other PIC locations. Data are collected
weekly in the form of magnetic tapes, paper tapes,
and via a satellite telemetry system. Data are
displayed in ^R/hr on a digital readout display at
each location for easy access by the public.
Computer analysis of the data is accomplished on a
weekly basis at EMSL-LV. Trends are noted and
compared to previous years. During 1988, as in
previous years background levels dropped in the
higher elevation locations during the winter. This
drop is attributed to snow cover shielding the PIC
from low energy gamma radiation coming from the
ground.
For an 11 hour period during the week of August
22-29, 1988, the PIC located at Lathrop Wells
showed elevated readings which were
approximately twice the level normally expected.
Upon further investigation these elevated readings
were determined to be due to the presence of a
shipment of low-level radioactive waste which was
en route to the U.S. Ecology low level radioactive
waste disposal site in nearby Beatty, Nevada.
This finding contributed to a decision to expand the
scope of monitoring adjacent to the disposal site.
Through a cooperative agreement with the Nevada
State Health Division, additional equipment Is being
installed. It is anticipated that the expanded
monitoring adjacent to the disposal site will be fully
operational in 1989.
77
-------
Data for 1988 is displayed in Table 15 as the
average /iR/hr and annual mR/yr from each station.
Figure 28 shows annual averages for each location
in mR/yr as compared to the maximum and
minimum United States background (BEIR80). The
U.S. background maximum and minimum values
shown represent the highest and lowest values
respectfully, of the combined terrestrial ahd cosmic
components of environmental gamma radiation
nationwide. When these data are compared to TLD
results for the same 28 stations, it Is found that the
PIC exposure Is approximately 38% higher than the
TLD exposure. This has been attributed primarily to
the differences in energy response of the two
systems. Since PICs have a greater sensitivity to
lower energy gamma radiation, they normally
record higher apparent exposure rates than do the
TLDs.
The 1988 PIC data is consistent with previous year
trends. No prolonged unexplained deviations from
background levels occurred during 1988.
Table 15. Pressurized Ion Chamber Readings -1988
Station
Alamo, NV
Austin, NV
Beatty, NV
Caliente, NV
Cedar City, UT
Complex I, NV
Delta, UT
Ely, NV
Furnace Creek, CA
Goldfield, NV
Indian Springs, NV
Las Vegas, NV
Lathrop Wells, NV
Mammoth Lakes, CA
Medlins' Ranch, NV
Milford, UT
Nyala, NV
Overton, NV
Pahrump, NV
Pioche, NV
Rachel, NV
St. George, UT
Shoshone, CA
Salt Lake City, UT
Stone Cabin Ranch, NV
Tonopah, NV
Twin Springs Ranch, NV
Uhaldes Ranch, NV
No. of
Weekly
Values
50
49
50
49
52
49
9
51
50
47
49
50
49
24
52
10
45
52
51
52
46
51
45
45
41
46
45
51
Exposure Rate (uR/hr)*
Minimum
12.9
13.7
16.4
13.1
9.7
14.0
11.6
11.4
9.5
14.6
8.5
6.0
13.9
14.6
14.2
16.9
11.6
9.0
7.6
11.2
13.5
8.8
9.7
11.0
14.2
16.3
15.7
14.1
Maximum
13.5
20.6
17.5
15.2
10.8
16.5
12.1
12.7
10.5
16.2
9.4
6.4
14.6
17.8
16.2
18.4
13.1
10.5
8.0
13.4
17.0
9.6
11.3
12.4
18.4
17.8
18.7
18.5
Average ± S.D.
13.1 ± 0.2
19.2 ± 1.6
16.9 ±0.3
14.6 ± 0.4
10.3 ± 0.2
15.8 ± 0.5
11.9 ±0.1
12.2 ± 0.2
10.0 ± 0.3
15.7 ± 0.3
9.1 ± 0.1
6.2 ± 0.9
14.2 ± 0.2
16.9 ± 0.9
15.8 ± 0.3
17.9 ± 0.4
12.6 ± 0.3
9.5 ± 0.3
7.7 ± 0.1
12.7 ± 0.4
15.9 ± 0.8
9.1 ± 0.2
10.5 ±0.5
11.6 ±0.3
16.7 ± 0.9
16.8 ± 0.3
16.9 ± 0.5
17.0 ± 0.9
mR/yr
115
168
148
128
90
138
104
107
88
137
80
54
124
148
138
157
110
83
67
111
139
80
92
102
146
147
148
149
* Weekly Averages
78
-------
Alamo -
Austin -
Beatty -
Caliente -
Cedar City -
Complex I -
Delta -
Ely-
Furnace Creek -
Goldfield-
Indian Springs -
Las Vegas -
Lathrop Wells -
Mammoth Lakes -
Medlin's Ranch -
Milford-
Nyala -
Overton -
Pahrump -
Pioche -
Rachel -
St. George -
Shoshone -
Salt Lake -
Stone Cabin Ranch -
Tonopah -
Twins Springs Ranch
Uhaldes Ranch -
U.S. Background
300
Milliroentgens Per Year
Figure 28. Annual Exposure Rates as Measured by PICs -1988.
79
-------
5.2.8 Internal Exposure Monitoring
A. A. Mullen
Internal exposure Is caused by ingested or in-
haled radlonuclldes that remain in the body
either temporarily or for longer times because of
storage In tissues. At EMSL-LV two methods are
used to detect such body burdens: whole-body
counting and urinalysls.
The whole-body counting facility has been
maintained at EMSL-LV since 1966 and Is equipped
to determine the identity and quantity of
gamma-emitting radlonuclldes which may have
been Inhaled or ingested. Routine examination
consists of a 2000 second count in each of two
shielded examination vaults. In one vault a single
intrinsic germanium coaxial detector positioned
over an adjustable chair allows detection of gamma
radiation with energies ranging from 60 KeV to 2.5
MeV In the whole body. The other vault contains an
adjustable chair with two germanium detectors
mounted above the chest area; two intrinsic
germanium semi-planar detectors were used until
the latter part of the year when four additional
semi-planar detectors were added. The semi-planar
array is designed for detection of gamma emitting
radlonuclides with energy ranges from ten to
300 KeV. Specially designed software was obtained
to allow individual detector spectra to be analyzed
to obtain a summation of left-or right-lung arrays
and the total lung area. This provides much greater
sensitivity for the transuranic radionuclides but
maintains the ability to pinpoint "hot spots."
Specially designed detector mounts were also
Installed to allow maximum flexibility for the
placement of detectors In various configurations for
skull, knee, ankle, or other geometries.
Network Design
This activity consists of two portions, an Off-Site
Human Surveillance Program and a Radiological
Safety Program. The Off-Site Human Surveillance
Program is designed (1) to measure radlonuclide
body burdens in a representative number of families
who reside in areas that were subjected to fallout
during the early years of nuclear weapons tests, and
(2) to act as a biological monitoring system for
present nuclear testing activities. A few families
who reside In areas not affected by such fallout
were also selected for comparative study.
Methods
The Off-Site Human Surveillance Program was
Initiated in December 1970, to determine levels of
radionuclides In some of the families residing in
communities and ranches surrounding the NTS.
Biannual counting is performed In the spring and
fall. This program started with 34 families (142
Individuals). In 1986, 16 of these families (37
Individuals) were still active In the program together
with 7 families added in recent years. When the
Community Monitoring Station Network was started
in 1982, the families of the station managers were
added to the program. These families are counted
In the winter and summer of each year. The
geographical locations of the families which
participated in 1988 are shown in Figure 29.
These persons travel to the EMSL-LV where a
whole-body count and a lung count of each person
Is made to determine the body burden of
gamma-emitting radlonuclldes. A urine sample is
collected for tritium analysis. Results of the
whole-body count are available before the families
leave the facility and are discussed with the
subjects. At 18-month intervals a physical exam,
health history and the following are performed: a
urinalysls, complete blood count, serology, chest
x-ray (3-year intervals), sight screening, audiogram,
vital capacity, EKG (over 40 years old), and thyroid
panel. The individual Is then examined by a
physician. The results of the examination can be
requested for use by their family physician.
Analysis for internally deposited radionuclides is
also performed for EPA employees, the DOE
contractor employees, and for other workers who
may be occupatlonally exposed as well as for
concerned members of the general public. Results
of counts on Individuals from Las Vegas and other
cities are used for comparison.
The QC Program utilizes daily equipment checks
and calibrations with NBS traceable radionuclides.
Calibration phantoms are exchanged among this
facility and other whole-body counting facilities
across the nation for intercomparison studies.
Results
During 1988, a total of 600 gamma spectra were
obtained from 188 individuals, of whom 100 were
participants In the Off-Site Human Surveillance
Program. Also, 1825 spectra for calibrations and
background were generated. Cesium-137 is
80
-------
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r '"*' ™" ' "™ ' ""ARIZONA
Pahrumpjb . a I(IAKEMEAO I
Shoshone. \ v«8as ^<^J kj
\ i
V Z Scale in Milei
V • 0 50 1
^ ^nmmi initii HMjtnitnrinn Qta Cdm!K< ^^ _ • ^i™^^™!!^^^^^^^^^^^*^"™^!^^™^
Scale In Kilonuters
Figure 29. Location of Families In the Off-Site Human Surveillance Program.
81
-------
generally the only fission product detected. As a
result of worldwide fallout following the Chernobyl
accident, trace amounts of 137Cs and 134Cs were
detected in a limited number of individuals, mainly
those contractor personnel flown in from California,
and people stationed in or visiting Europe. In
general, the spectra were representative of normal
background for people and showed only naturally
occurring ^K. No transuranic radionuclides were
detected in any lung counting data.
Bioassay results for the Off-Site Human Surveillance
Program showed that the concentration of tritium in
urine samples from the off-site residents varied from
0 to 1300 pCi/L (0 to 48 Bq/L) with an average value
of 140 pCi/L (5.19 Bq/L). Nearly all the
concentrations measured were in the range of
background levels measured in water and reflect
only natural exposure. The 3H concentrations in
urine samples from EPA employees had a range of
0 to 1200 pCi/L (44 Bq/L) with an average value of
210pCi/L(7.7Bq/L).
As reported in previous years, medical
examinations of the off-site families revealed a
generally healthy population. The blood
examinations and thyroid profiles showed no
abnormal results which could be attributed to past
or present NTS testing operations. Two deaths
occurred in the Off-Site Human Surveillance
Program participants of causes unrelated to NTS
testing.
EG&G personnel participating in the Joint
Verification Experiment, Shagan Event, in the USSR
were counted upon their return. Those people who
visited Germany, Scandinavia, England and Ireland
were found to have very small amounts of 137Cs;
while those persons who travelled directly to and
from the Russian Test Site did not pick up this
radionuclide.
One EG&G employee from California was also
found to have a very small body burden of 134Cs
and 137Cs. This individual had been eating large
quantities of imported cheeses. A limited survey of
imported cheese available in local stores was
82
-------
conducted and only one, a goat cheese from
Norway, was found to have 134Cs and 137Cs.
Four members of the general public were counted.
Two of these were: a man who had travelled in Italy
and was concerned about possible uptake of fission
products from the Chernobyl-4 accident; and a
woman travelling around the U.S. Nothing over
natural background was detected in either person.
Additionally, a photographer from the National
Geographic Magazine requested a count as she
had been in Sweden for a week and had eaten a
small amount of reindeer meat, mushrooms,
vegetables and cheese while photographing the
Laplanders. Cesium 134 and Cs were detected.
A visiting scientist from Poland also requested a
count. Her 134Cs and 137Cs values were about
twice those found in the photographer.
5.2.9 Long-Term Hydrological Monitoring
Program
S.C. Black
Tritium and gamma-spectral analysis were done
on samples taken from 193 wells, springs, and
other sources of water at locations where under-
ground nuclear explosives tests have been con-
ducted. Gamma radioactivity was found in only
one sampled location where 137Cs had been
used in a hydrologic study. The tritium con-
centrations found during this sampling year
were consistent with the levels found in previous
years, except for a slight upward trend in one
NTS well. In only three samples were the tritium
concentrations greater than the Drinking Water
Standards, and those samples were from wells
not accessible to the general public.
Background
Surface- and ground-water sampling and analysis
from water sources around the NTS have been
performed for many years. When underground
nuclear tests occurred in other states, water
sampling programs were instituted. Finally, in 1972,
all of the water sampling programs were combined
to constitute the Long-Term Hydrological
Monitoring Program (LTHMP). At each of the sites
of underground nuclear tests, water sampling points
were established by the U.S. Geological Survey so
that any migration of radioactivity from the test
83
-------
cavities to potable water sources could be detected
by radioanalysis.
The 23 wells on the NTS and the 32 wells in areas
around the NTS which are part of this program are
shown In Figures 30 and 31, respectively. The
locations of the sampling points at other than NTS
locations in Nevada, and at locations In Alaska,
Colorado, Mississippi, and New Mexico are shown
In Figures 32 through 43.
Methods
At nearly all locations, the standard operating
procedure is to collect four samples. Two samples
are collected In 500-mL glass bottles to be analyzed
for tritium. The results from analysis of one of these
is reported while the other sample serves as a
backup in case of loss, or If the tritium Is at
detectable concentration, as a duplicate sample.
The remaining two samples are collected In 4 L
plastic containers (cubitainers). One of these is
analyzed by gamma spectrometry and the other is
stored as a backup or for duplicate analysis. For
wells with operating pumps, the samples are
collected at the nearest convenient outlet. If the
well has no pump, a truck-mounted sampling rig is
used. With this rig it is possible to collect 3-liter
samples from wells as deep as 1800 meters. The
pH, conductivity, and temperature of the water are
measured when the sample is collected.
The tritium and gamma spectrometric analyses are
described In Section 9.0 Sample Analysis
Procedures. For those samples in which the tritium
concentration Is less than 700 pCi/L (26 Bq/L), an
enrichment procedure is performed which reduces
the MDC from about 600 to about 10 pCi/L (from 22
to 0.4 Bq/L). Also, the first time a water source is
sampled the sample is analyzed for 89Sr and 90Sr,
226Ra, uranium isotopes, 238Pu and 239Pu.
For those operations conducted in other states,
samples for the LTHMP are collected annually. For
the locations on the NTS listed in Table 16, the
samples are collected monthly, when possible, and
analyzed by gamma spectrometry as well as for
tritium. For a few NTS wells and for all the water
sources around the NTS a sample for tritium
analysis is collected twice per year at about a
6-month interval. One of the semi-annual samples
Is analyzed for tritium by the conventional method,
the other by the enrichment method. During the
other 10 months, only a cubitainer of water Is
collected for analysis by gamma spectrometry.
Since all gamma spectra were negligible only the
tritium results are shown in Table 16.
Table 16. LTHMP Tritium Results for the Monthly NTS Network for 1988
Sampling
Location
Well 1 Army
Well 2
Well 3
Well 4
Well4CP-1
Well 5C
Well 8
Well 20
Well A
Well B Test
Well C
WellJ-13
Well U19C
Well UE18R
No.
Samples
12
12
11
11
12
12
11
12
10
9
12
12
12
7
Tritium Concentration
(PCI/L)
Max
14
11
16
18
3.7
9.0
4.4
4.4
52
156
76
5.9
8.9
.. 110
Min
-19
-16
-16
-16
-19
-18
-23
-21
14
120
5.9
-26
-18
-4.2
Avg
1.6
0.63
0.33
-0.17
-2.4
-1.8
-2.1
-2.3
37
140
29
-0.27
-0.47
17
Percent
Cone.
Guide
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
0.19
0.70
0.14
< 0.01
< 0.01
0.10
84
-------
•Well 3
RAINIER 12
MESA
jWellUE15d
WellUE18r
BUCKBOARD
MESA
NUCLEAR ROCKET
DEVELOPMENT STATION
-r
Well UE5c
WelJ 58
Well 5c
A
WellJ-13
0 5 10
Scale in Kilometers
Figure 30. LTHMP Sampling Locations on the NTS.
85
-------
Twin Springs Rn.
Tonopah
Adaven Springs
TTR Well #6
NELLIS AFB
RANGE COMPLEX
L Springdale«
«> Goss Springs 4
*\ Beatty 4
NEVADA
SITE
vounghans Ranch (2)
^US Ecology 0 Specie Springs
N • Nickells
Lathrop Wei Is
Mercury
~U
•USAF
^*> £ Fairbanks Springs
Well 17S/50E-14CaC^
^ ^^ Crystal Pool
Well 18S-51 E-7db 0 • Ash Meadows
Death Valley Jet. • *V
Tempi ute
Penoyer(3)
Crystal Springs
Alamo
Springs
Sewer Co. Well # 1
Calvada Well #1
Las Vegas
28
Scale in Miles
.0 20 X .
NEVADA
0 10 20 30 40 50 60
Scale in Kilometers 5/89
NEVADA TEST SITE &
NELLIS AFB RANGE COMPLEX
<
N^J
Lake Mead I
Intake
LOCATION MAP
Figure 31. LTHMP Sampling Locations Near the NTS.
86
-------
BERING
SEA
\ Surface Ground Zero
i Sampling Locations
Scats in Miles
5 10
._,
Long Snot
CONSTANTS
HARBOR
Duck Cove Civ
Milrow
0 5 10
Scale in Kilometers
N
BASE CAMP AREA
I
Kirilof Point
BERING
SEA
BAKER RUNWAY
South Hanger
5/89
Figure 32. Amchitka Island and Background Sampling Locations for the LTHMP
87
-------
BERING
S£A
Banjo Point
Surface Ground Zero
Water Sampling Locations
\
Scale in Miles
0 1
Scale in Kilometers
5/89
Figure 33. LTHMP Sampling Locations for Project Cannikin.
88
-------
/ /
/COLLAPSE .
/' BOUNDARY \
>\
W-15
©Surface Ground Zero
Sampling Locations
Scale in Feet
0 600 1200
N
400
Scale in Kilometers
MILROW
5/89
Scale in Feet
0 300
V
LONG SHOT
Long Shot
Pond #3
o 100
Scale in Kilometers
© Surface Ground Zero
• Sampling Locations
Figure 34. LTHMP Sampling Locations for Projects Milrow and Long Shot.
89
-------
Johnson
Artesian
Fawn Cr. No. 1
Fawn Cr
8400' Downstream
Fawn Cr. 500' Downstream
RB-D-01
SGZ
Fawn Cr. 500'
Upstream
Fawn Cr. 6800
Upstream
Fawn Cr. No 3
RIO BLANCO COUNTY
GARFIELD COUNTY
Scale in Miles
-© Surface Ground Zero
£ Artesian Well
O Windmill
D Water Well
A Spring
I Stream
COLORADO
RIO BLANCO
COUNTY
LOCATION MAP
5/89
Figure 35. LTHMP Sampling Locations for Project Rio Blanco.
90
-------
Schwab Rn. Potter
Grand Valley
City Water'
Grand Valley
Gardner UJ
Rn.
Test Well
Rulison
_ __ __ .^ • Sefcovic Rn.
Hayward Rn.
Battlement Creek
4
CER •>
Spring
(SGZ
Surface Ground Zero
Water Sampling Locations
N
GARFIELD
g>SGZ| COUNTY
0 8
Scale in Kilometers
LOCATION MAPS
5/89
Figure 36. LTHMP Sampling Locations for Project Rulison.
91
-------
Lower Little Creek
Salt Dome Timber Co.
Anderson
King
B.R. Anderson
t Hunt Club
R.L. Anderson
W. Daniels Jr.
Baxterville
Well Ascot 21
Lumberton
1 Surface Ground Zero
Water Sampling Locations
Scale in Miles
5
0 5 10 15
Scale in Kilometers
LAMAR
COUNTY
LOCATION MAPS
5/89
Figure 37. LTHMP Sampling Locations for Project Dribble - Towns and Residences.
92
-------
\
•
HMH-5\
*
HMH-10
\
A Half Moon )
1 I \ Creek /
I \\ Overflow /
HMH-7
V
SGZ
IHMH-2 ]
^ BHMH-9
HMH-11
I Surface Ground Zero
Water Sampling Locations
N
Scale in Miles
0 100 200 300
0 50 100
Scale in Kilometers
LAMAR
COUNTY
LOCATION MAPS
5/89
Figure 38. LTHMP Sampling Locations for Project Dribble - Near GZ.
93
-------
A •*
«^
#••'
/•'*
\V
^>/
v •
/••'
.^/ HM-L2
-------
h
\
Hot Creek i
Ranch !
SGZi
Six-Mile Well
Jim Bias Well
(Blue Jay Springs)
Blue Jay
Maint Station
1 Surface Ground Zero
Water Sampling Locations
aNYE
)UNTY
LOCATION MAPS
5/89
Figure 40. LTHMP Sampling Locations for Project Faultless.
95
-------
Fallen
Flowing Well
H-31
Hunts I
Station
SGZ
• HS-1
Smith/James
Spring
CHURCHILL COUNTY
MINERAL COUNTY
) Surface Ground Zero
I Water Sampling Locations
Scale in Miles
5
5 10
Scale in Kilometers
CHURCHILL
COUNTY
LOCATION MAPS
5/89
Figure 41. LTHMP Sampling Locations for Project Shoal.
96
-------
Bixler Rn.
To Blanco &
Gobernador
I Bubbling
Spring
La Jara Creek
•
Windmill #2
EPNG Well 10-36
Cedar Spring •
Cave Spring •
Jicarilla
Well #1
SGZ
Arnold RN.
Lower Burro I
Canyon
I Well 28.3.33.233
© Surface Ground Zero
• Water Sampling Locations
Scale in Miles
0 5
0 8
Scale in Kilometers
RIO
ARRIBA
COUNTY
LOCATION MAPS
5/89
Figure 42. LTHMP Sampling Locations for Project Gasbuggy.
97
-------
Carlsbad
Carlsbad
City •
Well #7
Loving City
Well #2
LRL-7
PHS Well #6 •
PHS Well #9 •
PHS Well #10
PHS
Well #8
Pecos River
Pumping Station
Well #1
Scale in Miles
0 5 10
©Surface Ground Zero
• On-Site Water Sampling Locations
A Off-Site Water Sampling Locations 6 5 10
Scale in Kilometers
* N
EDDY
COUNTY
LOCATION MAPS
5/89
Figure 43. LTHMP Sampling Locations for Project Gnome.
98
-------
The tritium concentration in samples from Well A highest tritium concentration obtained on multiple
were plotted as a running average to minimize the sampling is reported in Table 18 on the assumption
variability in the data. The plot indicated an it is representative of formation water.
increase in concentration was occurring that had
started in early 1988. Although the maximum (50
pCi/L) was only 0.25 percent of the Drinking Water Results
Regulation, the DOE removed the well from ... , 4l „ ., . t.
industrial and culinary water production. There The '°catlonf ,at which *he water sfmPIes uwere
were no other trends noted for these wells. ouTndK ° °°ntal n man^e radl°actfy arf sh°wn
in Table 17 along with the analytical results. For
Because of the variability noted in samples obtained tritium concentrations, only those samples In which
at the shallow monitoring wells at the Project the concentration exceeded 0.01 of the Drinking
Dribble site, these wells were pumped extensively Water Standard (i.e., 200 pCi/L) are shown. The
during the 1988 sample collection trip. Some of the radioactivity in the samples collected from those
shallow wells were pumped and sampled up to locations has been reported in earlier reports.
eight times and others less frequently. Only the Several samples were analyzed for plutonium and
TABLE 17. Water sampling locations where samples contained
man-made radioactivity - 1988
Sampling Location Type
PROJECT GNOME, NM
USGS Well 4
USGS Well 8
Well LRL-7
PROJECT RULISON, CO
Hayward Ranch
PROJECT DRIBBLE, MS
Half Moon Creek Overflow
Well HMH-1 through 11
Well HM-S
Well HM-L
REECo Pit Dralnage-A
PROJECT LONGSHOT, AK
Stream E of GZ
Well GZ, No. 1
Mud Pit No. 1
Mud Pit No. 2
Mud Pit No. 3
of Radioactivity
3H
^Sr
3H
^Sr
3H
137Cs
3H
3H
3H
3H
3H
3H
3H
3H
3H
3H
3H
Cone. (pCi/L)
190,000
3,600
150,000
2,300
16,000
200
250
1,400
24-35,000
11,000
1,300
230
530
2,100
250
280
420
99
-------
two from the Gnome site In New Mexico were
analyzed for ^Sr to confirm results obtained
previously.
The results of analysis for all collected samples are
shown In Table 18 together with the percent of the
relevant concentration guide that Is listed in Table
25.
Discussion
i
The NTS network presently consists of 24 wells that
are sampled periodically. However, there are
another 31 wells that have never been monitored.
These are being added to the NTS network as time
permits. They will be sampled and analyzed
semiannually.
Although some positive results, that Is detectable
amounts of man-made radionuclldes, are shown for
some of the water samples, none of them are
expected to give measurable radiation exposures to
residents in the areas where the samples were
collected. Specifically, these were:
Project Gnome - Wells USGS 4 and 8 were used for
a hydrologlcal tracer study many years ago so the
radionuclides detected were consistent with
previous results. These wells are capped and
locked to prevent use. Well LRL-7 is expected to
show elevated levels of radionuclides as it was used
for disposal of contaminated soil and salt. It is also
guarded to prevent access.
Project Dribble -- Wells at this location are on
private land, about one mile from the nearest
resident and are not sources for drinking water.
Project Alaska - The shallow wells at Project
Longshot on Amchitka Island are In an isolated
location and are not sources of drinking water.
100
-------
Table 18.
Tritium
Results for the LTHMP - 1988
COLLECTION CONC. ± 2 SIGMA
DATE TRITIUM
SAMPLING LOCATION 1988 (pCi/L)
CARLSBAD NM
WELL 7 CITY
LOVING NM
WELL 2 CITY
MALAGA NM
WELL 1 PECOS PUMPING STAT
WELL LRL-7
WELL PHS 6
WELL PHS 8
WELL PHS 9
WELL PHS 10
WELL USGS 1
WELLUSGS4
WELL USGS 8
FRENCHMAN STATION NV
FRENCHMAN STATION
04/25
04/25
04/25
04/26
04/24
04/26
04/24
04/24
04/24
04/26
04/26
02/22
9 ±15*
17±10
10 ±15*
16000 ± 460
57 ± 10
21 ± 10
-9 ± 15*
-5 ± 16*
0.4 ± 15*
1 90,000 ± 1100
150,000 ± 1000
**
PCTOF
CONC.
GUIDE
0.05
0.08
0.05
82.0
0.29
0.10
< 0.01
< 0.01
< 0.01
955.
735.
( 1)
( 2)
( 3)
( 4)
( 5)
( 6)
( 7)
( 8)
( 9)
( 10)
( 11)
PUMP REMOVED SITE CLOSED
HUNT'S STATION
SMITH/JAMES SPRGS
SPRING WINDMILL
WELL FLOWING
WELLH-3
WELL HS-1
BAXTERVILLE MS
HALF MOON CREEK
HALF MOON CREEK OVRFLW
LOWER LITTLE CREEK
POND WEST OF GZ
ANDERSON POND
REECO PIT DRAINAGE-A
REECO PIT DRAINAGE-B
REECO PIT DRAINAGE-C
02/23
02/24
06/15
02/23
02/23
02/24
02/24
04/18
04/18
04/18
04/18
04/18
04/18
04/18
04/20
04/19
04/19
04/19
1 ± 15*
83 ±10
58 ± 10
**
NO SAMPLE WINDMILL OUT
-4± 16*
**
NOT SAMPLED
-6 ±18*
31 ± 10
36 ±9
1400 ± 390
1200 ± 380
49 ±10
28 ± 10
15 ±16*
13 ± 15*
230 ± 1 1
120 ± 10
200 ± 11
< 0.01
0.42
0.29
< 0.01
< 0.01
0.15
0,18
6.80
6.20
0.24
0.14
0.08
0.07
1.14
0.59
0.98
( 12)
(continued)
101
-------
SAMPLING LOCATION
BAXTERVILLE MS (Cont)
SALT DOME HUNTING CLUB
SALT DOME TIMBER CO.
ANDERSON, B. R.
ANDERSON, H.
ANDERSON, R. L
CHAMBLISS, B.
DANIELS, W. JR.
KELLY, G.
KING, RHONDA
LEE, P. T.
LOWE, M.
MILLS, A. C.
MILLS, R.
READY, R.
SAUCIER, T. S.
SPEIGHTS, T.
WELL ASCOT 2
WELL CITY
WELL E-7
WELL HM-1
WELLHM-2A
WELL HM-2B
WELL HM-3
WELL HM-L
WELL HM-L2
WELLHM-S
WELLHMH-1
WELL HMH-2
WELL HMH-3
WELLHMH-4
WELLHMH-5
WELLHMH-6
WELLHMH-7
WELLHMH-8
WELLHMH-9
WELLHMH-10
WELLHMH-11
WELLHT-2C
Table
18. (continued)
COLLECTION CONIC. ± 2 SIGMA
DATE TRITIUM
1988 (pCi/L)
,
04/19
04/18
04/19
04/19
04/18
04/18
04/18
04/18
04/19
04/19
04/18
04/18
04/18
04/18
04/18
04/18
04/19
04/18
04/19
04/18
04/18
04/18
04/18
04/18
04/18
04/18
04/19
04/19
04/17
04/17
04/17
04/17
04/17
04/17
04/17
04/17
04/17
04/19
42 ± 10
46 ±10
23 ±11
27 ±11
36 ±11
-3 ±17*
40±10
-8 ± 16*
36 ± 10
51 ±9
**
NOT SAMPLED
4 ±16*
35 ±10
80±11
46 ±9
**
NOT SAMPLED
46 ± 10
46±9
15 ±9
11 ±15*
11 ± 16*
15 ± 15*
5 ±15*
1300 ± 390
6 ±16*
11 000 ±470
35000 ± 620
17000 ±510
51 ±10
24 ±9
5400 ± 420
100 ± 10
180± 11
43 ±9
73 ±11
24 ±11
78 ± 11
**
NOT SAMPLED
PCTOF
CONC.
GUIDE
0.21
0.23
0.11
0.13
0.18
< 0.01
0.20
< 0.01
0.18
0.25
0.02
0.17
0.40
0.23
0.23
0.23
0.08
0.06
0.06
0.08
0.02
6.65
0.03
55.0
173.
85.5
0.25
0.12
27.1
0.52
0.91
0.22
0.36
0.12
0.39
(continued)
102
-------
Table 18.
COLLECTION
DATE
SAMPLING LOCATION 1988
BAXTERVILLE MS (Cont)
WELL HT-4
WELL HT-5
COLUMBIA MS
WELL 64B CITY
LUMBERTON MS
WELL 2 CITY
PURVIS MS
CITY SUPPLY
GOBERNADOR NM
ARNOLD RANCH
BIXLER RANCH
BUBBLING SPRINGS
CAVE SPRINGS
CEDAR SPRINGS
LA JARA CREEK
LOWER BURRO CANYON
RESAMPLE OF WINDMILL
POND N WELL 30.3.32.343
WELL EPNG 10-36
RESAMPLE OF WELL
WELLJICARILLA1
WELL 28.3.33.233 (SOUTH)
WELL 30.3.32.343 (NORTH)
WINDMILL 2
GRAND VALLEY CO
BATTLEMENT CREEK
CITY SPRINGS
ALBERT GARDNER RANCH
SPRING 300 YRD N OF GZ
WELL CER TEST
RULISON CO
LEE HAYWARD RANCH
POTTER RANCH
ROBERT SEARCY RN (SCHWAB)
04/19
04/19
04/18
04/18
04/18
06/22
06/21
06/21
06/22
06/21
06/21
06/22
06/21
06/23
06/22
06/21
NO
06/21
NO
06/22
06/25
06/25
06/25
06/25
06/25
06/25
06/27
06/25
(continued)
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
16 ±9
3± 15*
26 ±9
7 ±15*
2± 15*
7.5 ± 9.2
15 ±9
69 ± 10
25 ±9
83 ±10
73 ±10
12 ±9
580 ±13
750 ± 15
5 ±9.3
**
SAMPLE-WELL OUT
**
SAMPLE-WELL OUT
5.1 ± 9.5
140 ±11
-2 ± 16*
170 ± 12
84± 11
160 ±12
250 ± 12
140 ± 11
150 ±11
PCTOF
CONC.
GUIDE
0.08
0.02
0.13
0.04
0.01
0.04
0.08
0.35
0.13
0.42
0.36
0.06
2.91
3.77
0.03
0.03
0.70
<0.01
0.86
0.42
0.79
1.24
0.71
0.76
(continued)
103
-------
Table
18. (continued)
COLLECTION CONG. ± 2 SIGMA
DATE TRITIUM
SAMPLING LOCATION 1988 (pCi/L)
RULISON CO (continued)
FELIX SEFCOVIC RANCH
RIO BLANCO CO
B-1 EQUITY CAMP
BRENNAN WINDMILL
CER NO.1 BLACK SULPHUR
CER NO.4 BLACK SULPHUR
FAWN CREEK 1
FAWN CREEK 3
FAWN CREEK 6800FT UPSTRM
FAWN CREEK 500FT UPSTRM
FAWN CREEK 500FT DWNSTRM
FAWN CREEK 8400FT DWNSTR
WELL JOHNSON ARTESIAN
WELL RB-D-01
WELLRB-D-03
WELL RB-S-03
BLUE JAY NV
HOT CREEK RANCH SPRING
MAINTENANCE STATION
WELL BIAS
WELL HTH-1
WELL HTH-2
WELL SIX MILE
AMCHITKA AK
CLEVENGER LAKE
CONSTANTINE SPRING
DUCK COVE CREEK
JONES LAKE
RAIN SAMPLE
SITE D HYDRO EXPLORE HOLE
WELL ARMY 1
WELL ARMY 2
WELL 4 ARMY
CANNIKIN LAKE (NORTH END)
CANNIKIN LAKE (SOUTH END)
DK-45 LAKE
ICE BOX LAKE
PIT SOUTH OF CANNIKIN GZ
p6/25
06/26
06/27
06/26
06/26
06/27
06/27
06/27
06/27
06/27
06/27
06/27
06/27
06/27
06/27
07/20
07/21
07/20
07/21
07/21
07/20
09/07
09/07
09/07
09/07
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
160± 11
92 ±10
46 ±11
87 ±10
73 ± 10
46 ± 11
60 ±10
62 ± 10
57 ±9
53 ±10
45 ± 11
-7 ± 10*
7.9 ± 9.2*
4.8 ± 9.2*
1.2 ±9.1*
**
NOT SAMPLED
7 ±10*
0.8 ± 9.2*
-8.4 ±9.1*
-5.5 ± 9.2*
**
NOT SAMPLED
47 ± 10
53 ± 10
36 ±10
34 ±10
27 ± 10
72 ±10
48 ±10
34 ± 10
43± 11
34 ±10
44±11
36 ±9
46 ±10
38 ±10
PCTOF
CONC.
GUIDE
0.82
0.46
0.23
0.43
0.36
0.23
0.30
0.31
0.29
0.26
0.22
< 0.01
0.04
0.02
< 0.01
0.03
< 0.01
<0.01
< 0.01
0.24
0.26
0.18
0.17
0.13
0.36
0.24
0.17
0.22
0.17
0.22
0.18
0.23
0.19
(continued)
104
-------
SAMPLING LOCATION
AMCHITKA AK (continued)
WELL HTH-3
WHITE ALICE CREEK
LONG SHOT POND 1
LONG SHOT POND 2
LONG SHOT POND 3
MUD PIT N0.1
MUD PIT NO.2
MUD PIT N0.3
REED POND
Table
18. (continued)
COLLECTION CONG. ± 2 SIGMA
DATE TRITIUM
1988 (pCI/L)
09/08
09/08
09/07
09/07
09/07
09/07
09/07
09/07
09/07
STREAM EAST OF LONGSHOT 09/07
WELLEPA-1
WELLGZNO.1
WELL GZ NO.2
WELLWL-1
WELLWL-2
CLEVENGER CREEK
HEART LAKE
WELLW-2
WELLW-3
WELLW-4
WELLW-5
WELLW-6
WELLW-7
WELLW-8
WELLW-9
WELLW-10
WELLW-11
WELLW-12
WELLW-13
WELLW-14
WELLW-15
WELLW-16
WELLW-17
WELLW-18
WELLW-19
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
09/08
40 ± 10
19 ±9
38 ± 10
38 ±11
56 ±11
250 ± 12
280 ± 12
420 ± 13
28 ± 10
530 ± 14
54 ±10
21 00 ±379
81 ±10
28 ±10
180± 11
46 ± 10
31 ±9
29 ±9
23 ±9
**
NOT SAMPLED
**
NOT SAMPLED
**
NOT SAMPLED
40 ±11
32 ±10
**
NOT SAMPLED
34 ± 12
69±12
**
NOT SAMPLED
51 ±11
**
NOT SAMPLED
36 ±10
**
NOT SAMPLED
28 ± 11
50 ± 12
**
NOT SAMPLED - WELL DRY
PCTOF
CONC.
GUIDE
0.20
0.09
0.19
0.19
0.28
1.23
1.38
2.13
0.14
2.64
0.27
10.3
0.40
0.14
0.92
0.23 (13)
0.15
0.15
0.11
0.20
0.16
0.17
0.35
0.25
0.18
0.14
0.25
(continued)
105
-------
Table 18. (continued)
SAMPLING LOCATION
SHOSHONE CA
SHOSHONE SPRING
ADAVEN NV
ADAVEN SPRING
ALAMO NV
WELL 4 CITY
ASH MEADOWS NV
CRYSTAL POOL
FAIRBANKS SPRINGS
WELL17S-50E-14CAC
WELL18S-51E-7DB
BEATTY NV
SPECIE SPRINGS
TOLICHA PEAK
US ECOLOGY WELL (NECO)
WELL 1 1 S-48-1 DD COFFERS
WELL 12S-47E-7DBD CITY
WELL ROAD DSPICERS
YOUNGHANS RCH WELL
COLLECTION
DATE
1988
Ofl/04
06/07
05/05
09/01
10/04
04/14
09/21
02/11
07/12
03/03
08/01
02/11
07/12
02/11
07/12
03/03
08/04
02/04
07/07
NOT
01/06
06/08
02/04
07/07
03/04
08/04
07/07
02/04
11 Samples:
CONG. ± 2 SIGMA
TRITIUM
(pCI/L)
170 ±330*
0.4 ± 16*
41 ±10
150 ± 610*
95 ± 360*
-11 ±16*
60 ±610*
10 ± 13*
-53 ± 600*
7 ±13*
-33 ±610*
13 ±13*
69 ± 600*
2.4 ± 14*
-90 ± 600*
250 ± 550*
48 ±11
5 ±14*
0±600*
SAMPLED
6± 14*
-26 ± 500*
4 ±13*
16 ± 600*
5 ±13*
38 ±610*
250 ± 600*
-3 ±14*
Max. 20 ± 8*
Min. -7 ±17*
Avg. 3 ± 12*
PCTOF
CONC.
GUIDE
0.87
< 0.01
0.21
0.74
0.47
< 0.01
0.30
0.05
< 0.01
0.03
< 0.01
0.07
0.35
0.01
<0.01
1.23
0.24
0.02
0.03
< 0.01
0.02
0.08
0.03
0.19
1.24
< 0.01
(continued)
106
-------
SAMPLING LOCATION
BOULDER CITY NV
LAKE MEAD INTAKE
CLARK STATION NV
WELL6TTR
NOT SAMPLED
HIKO NV
CRYSTAL SPRINGS
INDIAN SPRINGS NV
WELL 1 SEWER COMPANY
WELL 2 US AIR FORCE
LAS VEGAS NV
WELL 28 WATER DISTRICT
LATHROP WELLS NV
CITY15S-50E-18CDC
NYALA NV
SHARP'S RANCH
OASIS VALLEY NV
GOSS SPRINGS
PAHRUMP NV
WELL3CALVADA
RACHEL NV
WELLS7AND8PENOYER
WELL13PENOYER
Table 18.
COLLECTION
DATE
1988
03/11
08/11
06/01
10/06
04/14
09/02
01/04
06/07
01/04
06/07
01/08
06/09
01/05
06/08
04/05
09/01
03/02
08/04
05/03
10/04
04/13
09/01
05/10
09/01
(continued)
CONC. ± 2 SIGMA
TRITIUM
(pCI/L)
99±9
110 ±610*
-2 ± 15*
180 ±360*
-16 ±15*
170 ±610*
11 ± 14*
-70 ± 500*
24 ±9
-52 ± 500*
-3 ± 330*
0± 16*
6 ±14*
-180 ±500*
-14 ±16*
38 ± 610*
13 ± 14*
-210 ± 610*
-2 ± 15*
-100 ±360*
-1 ± 15*
60 ± 610*
6± 15*
5 ± 610*
PCTOF
CONC.
GUIDE
0.50
0.57
< 0.01
0.92
< 0.01
0.84
0.06
< 0.01
0.12
< 0.01
< 0.01
0.03
< 0.01
< 0.01
0.19
0.07
< 0.01
< 0.01
< 0.01
< 0.01
0.30
0.03
0.03
(continued)
107
-------
SAMPLING LOCATION
RACHEL NV (continued)
WELL PENOYER CULINARY
TEMPIUTE NV
UNION CARBIDE WELL
TONOPAH NV
CITY WELL
WARM SPRINGS NV
TWIN SPRINGS RANCH
NTSNV
WELL5B
WELLC-1
WELL D TEST
WELLUE1C
WELL UE5C
WELLUE15D
WELLUE16D
Table 18.
COLLECTION
DATE
1988
02/02
67/12
01/06
06/02
06/01
10/06
04/05
09/01
02/04
07/19
02/03
07/19
04/04
08/09
03/03
08/08
02/04
07/19
01/06
06/07
02/03
07/19
(continued)
CONG. ± 2 SIGMA
TRITIUM
(pCi/L)
51 ± 330*
53 ± 600*
59 ± 330*
5 ±16*
-6 ±16*
42 ±360
-18± 16*
-120 ± 610*
140 ± 330*
-4 ±10*
5 ± 330*
9 ±10*
-230 ± 560*
9 ±9.4
-120 ± 550*
-0.2 ± 9.4*
140 ± 330*
-2 ± 10*
140 ±330*
103 ± 10
13 ± 330*
-6.3 ± 9.9*
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION
** SAMPLES NOT ANALYZED.
PCTOF
CONC.
GUIDE
0.25
0.26
0.29
0.03
<0.01
0.21
< 0.01
< 0.01
0.70
< 0.01
0.03
0.04
<0.01
0.05
< 0.01
< 0.01
0.70
< 0.01
0.70
0.51
0.07
< 0.01
(MDC).
FOOTNOTES
ANALYSIS
(1) 239Pu
RESULT
2.2E-03
2 SIGMA
1.8E-02*
UNITS
pCi/L
(continued)
108
-------
Table 18. FOOTNOTES (continued)
ANALYSIS
(2)
(3)
(4)
(5)
(6)
(7)
(8)
(9)
(10)
(11)
(12)
(13)
*
+
238pu
239pu
90 Sr
238pu
239pu
90 Sr
137Cs
239pu
90 Sr
238Pu
239Pu
90 Sr
238pu
239pu
90 Sr
238pu
239pu
238pu
239pu
90 Sr
238pu
239pu
238pu
239pu
90 Sr
239pu
90 Sr
238pu
239pu
90 Sr
234 u
235 y
238U
7 Be
RESULT
9.5E - 03
-1.2E-03
1.0E-01
-3.4E - 03
-2.7E - 03
3.0E - 01
2.0E + 02
2.9E - 03
-1.2E + 00
9.2E-04
-6.4E - 03
4.7E - 01
4.6E - 04
3.6E - 03
-2.5E + 00
5.3E - 03
1.4E-03
1.4E-02
1.6E-03
3.2E+00
9.0E - 03
-4.0E - 03
-2.2E - 03
-3.9E-03
3.6E + 03
-3.7E - 03
2.3E+03
-1.2E-02
-1.1E-02
4.9E+00
2.8E - 02
7.5E - 03
1.3E-02
7.2E-01
2 SIGMA
2.1 E- 02*
1.5E-02*
1.2E+00*
1.4E-02*
9.6E - 03*
1.5E + 00*
1.7E+01
1.0E-02*
1.9E+00*
3.2E - 02*
2.3E - 02*
1.6E+00*
1.6E-02*
1.1E-02*
4.6E+00*
1.7E-02*
1.2E-02*
1.9E-02*
1.3E-02*
4.5E + 00*
2.0E - 02*
1.4E-02*
2.0E-02*
1.4E-02*
3.6E+01
1.3E-02*
5.6E + 01
5.7E - 02*
4.1 E- 02*
2.3E+00
2.3E - 02
9.0E - 03*
1.5E-02*
UNITS
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
cpm
Concentrations of Tritium in atmospheric moisture (atm. m.) are expressed as pCi/mL of water collected.
Concentration Guides used are for 25 mrem annual exposure.
109
-------
6.0 Public Information and Community Assistance Programs
A. N. Jarvis
In addition to its many monitoring and data analysis activities, the Nuclear Radiation Division (NRD)
provides a comprehensive program designed to provide information and assistance to individual
citizens, organizations, and local government agencies in communities in the environs of the NTS.
During 1988 activities included: participation in public hearings; "town hall" meetings; a school
radiation science program; continued support of Community Monitoring Stations; and a variety of
tours, lectures, and presentations.
Public Hearings
A workshop on monitoring radioactivity In the
environment was held by the Congressional Office
of Technology Assessment in Las Vegas, Nevada,
on September 25 and 26,1988. Presentations were
given by two NRD staff members. They described
the criteria that must be met prior to testing a
nuclear device as well as the extensive monitoring,
surveillance, and analytical activities carried out by
the EMSL-LV to ensure that any accidental releases
of radioactivity from the NTS will be detected and
reported.
Town Hall Meetings
The "town hall" meetings, which have been
conducted since 1982, were continued in 1988.
These meetings provide an opportunity for
attendees to meet directly with EPA, DOE, and DPI
personnel, ask questions, and express their
concerns regarding nuclear testing. During a
typical meeting, the procedures used and the
safeguards taken during any test are described, the
monitoring and surveillance networks are explained,
and for meetings in Nevada the proposed High
Level Waste Repository at Yucca Mountain
discussed. During 1988, meetings were held in the
communities listed below. Attendance varied from
4 to 35 with an average of 15 participants per
meeting.
Town Hall Meetings
February 16
February 17
March 22
March 23
May 18
May 19
June 22
June 23
Enterprise, UT
Mllford, UT
LeeViningCA
Furnace Creek CA
Delta UT
Beaver Dam AZ
Tropic UT
Escalante UT
September 21
September 22
November 15
November 16
Gabbs NV
Fish Lake/DyerNV
Laughlin NV
Needles CA
Animal Investigations
One of the public service functions of the EMSL-LV
is to Investigate claims of Injury allegedly due to
radiation originating from NTS activities. A
veterinarian, qualified by education and experience
in the field of radiobiology, investigates problems
with domestic animals and wildlife to determine
whether or not radiation exposure may be involved.
No animal investigations were requested during
1988.
NTS Tours
To complement the 'town-hall" meetings and to
familiarize Nevada citizens with both the DOE
testing program at the NTS and the Environmental
Monitoring Program conducted by the EPA, tours
are arranged for business and community leaders
from towns In the environs of the NTS, as well as for
government employees and the news media.
Between January and December 1988, the following
tours were sponsored by the EPA:
Employees of Gold Bar Mine,
Scotty's Castle and Beatty Residents February 24
Teachers, Round Mountain, NV April 4-5
Public Officials and
Residents of Kingman, AZ May 9-10
Attendees, 34th Annual Conference
on Bioassay, Analytical and
Environmental Radiochemistry
October 21
111
-------
School Science Program
The Introduction to Radiation Science Program was
conceived by the NRD staff In 1986, to provide a
service to schools In communities In the environs of
the NTS. The aim of this program being to
supplement school program with an activity
Involving the Interaction between students, teachers
and NRD personnel. Following the reactor accident
at Chernobyl, USSR, In April 1986, the need for such
a program became obvious as Indicated by
recurring Indications of misunderstanding of
Ionizing radiation by both the media and the public.
In response, the NRD staff developed a program
designed to help students better understand
radiation and radioactivity and to provide them with
some of the basic knowledge required to make
sound decisions concerning the many societal
Issues arising from the use and disposal of
radioactive materials.
Beginning in October 1986, and continuing through
1988, an NRD staff member has been teaching
radiation concepts to students. The Instructor
spends from one to five days in each school.
During this time he presents lecture-demonstrations
and conducts laboratory exercises. During 1988,
the program was presented in the schools listed
below:
Virgin Valley High School, Mesqulte, NV
Moapa Valley High School, Overton, NV
Amargosa School, Amargosa, NV
C.V.T. Gilbert School, Las Vegas, NV
Emergency Response
As a result of continued population growth in the
off-site communities, there is an Increasing need for
assistance from and coordination with both state
and local agencies in order to implement the
protective actions that may be needed if an
underground nuclear test accidentally released
radioactive contaminants Into the environment.
Therefore, during 1988, there has been a continuing
dialogue between the EMSL-LV staff and the State
of Nevada's Division of Emergency Management as
well as with the local and county officials
responsible for emergency planning.
In a continuing effort to provide and Improve
personal dosimetry to citizens living In communities
In the environs of the Nevada Test Site, plans were
developed in 1988 to replace film badge caches
with thermoluminescent dosimeters. Three
thousand TLDs were received and calibrated during
1988 and are awaiting distribution to communities In
California, Nevada, and Utah. The dosimeters will
be issued by county or state personnel in the
unlikely event of a significant release of radioactive
materials from the NTS.
Community Monitoring Stations
Beginning in 1981 DOE and EPA established a
network of Community Monitoring Stations In the
off-site areas In order to increase public awareness
of radiation monitoring activities. The DOE, through
an Interagency agreement with EPA, sponsors the
program and contracts with the Desert Research
Institute (DRI) to manage the stations, and the
University of Utah to train station managers. Each
station is operated by a local resident, in most
cases a science teacher, who is trained in radiation
monitoring methods by the University of Utah.
These stations continued to be maintained by the
NRD personnel during 1988. Samples were
collected and analyzed at the EMSL-LV. The DRI
provides data interpretation to the communities
involved and pays the station operators for their
services.
During 1988, new stations were Installed at Callente,
NV, and at Milford and Delta, Utah. Each of the 18
stations contains one of the samplers for the ASN,
NGTSN and Dosimetry networks discussed earlier,
plus a pressurized Ion chamber (PIC) and recorder
for immediate readout of external gamma exposure,
and a recording barograph. The new stations at
Milford and Delta are complete except for noble gas
samplers, which will be added when the equipment
becomes available. All of the equipment is mounted
on a stand at a prominent location In each
community so the residents are aware of the
surveillance and, If interested, can have ready
access to the data. The data from these stations
are included in the tables in Section 5 with the other
data from the appropriate networks. Table 15
contains a summary of the PIC data.
New computer generated reports for each station
were developed. These reports, Issued weekly,
indicate the current weekly PIC average, the
previous week and previous year averages, and
show the maximum and minimum backgrounds in
the U.S. In addition to being posted at each station,
copies are sent to newspapers in Nevada and Utah
112
-------
and provided to appropriate federal and state fully operational. With this equipment, gamma
personnel In California, Nevada and Utah. exposure measurements acquired by the
BBS Z 5JSS fflLKK =SH
during 1987, was completed In 1988. All of the EMSL-LV by telephone line.
community monitoring stations are equipped with
transmitting equipment and the telemetry system Is
113
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7.0 Quality Assurance and Procedures
K. S. Moroney and C. A. Fontana
Policy
One of the major goals of the Agency Is to ensure that all EPA decisions which are dependent on en-
vironmental data are supported by data of known quality. Consequently, agency policy requires that
all EPA laboratories participate in a centrally managed and locally implemented Quality Assurance
(QA) Program.
EMSL-LV's QA policies and requirements are
summarized in EPA/600/X-87/241, Quality
Assurance Program Plan (EPA87), and are fully
adhered to by the Nuclear Radiation Assessment
Division (NRD).
Standard Operating Procedures
Elements of the QA program include local Standard
Operating Procedures (SOPs) which define
methods of sample collection, handling, sample
control, analysis, data validation, trending and
reporting. These SOPs support the goal of the QA
program in maintaining the quality of results within
established limits of acceptance.
completeness of data Is attained, those which are
used to test the internal comparability within a given
data set, and procedures for comparing data sets
with historical data and other data sets.
Completeness Is the amount of data successfully
collected with respect to that amount intended in
the design, and comparability refers to the degree
of similarity of data from different sources included
in a single data set. All data is reviewed by
supervisory personnel to ensure that sufficient data
have been collected and the conclusions are based
upon valid data. Completeness Is an Important part
of quality, since missing data may reduce the
precision of estimates, introduce bias, and thus
lower the level of confidence in the conclusions.
Data Quality Objectives
In addition, the EPA as an Agency requires all
projects Involving environmentally related
measurements to develop data quality objectives
(DQOs). DQOs must clearly define the level of
uncertainty that a decision maker is willing to accept
In results derived from environmental data. DQOs
contain quantitative statements relating to the
decision to be made, how environmental
measurements will be used, time and resource
constraints on data collection, descriptions of the
data or measurements to be made, specifications of
which portions of the physical systems from which
samples will be collected, and the calculations that
will be performed on the data in order to arrive at a
result.
Data Validation
An essential element of QA is the validation of data.
Four categories of data validation methods are
employed by NRD: procedures which are applied
routinely to ensure adherence of acceptable
analytical methods, those that ensure that
Quality Control
The quality control (QC) portion of the NRD QA
program consists of routine use of methods and
procedures designed to achieve and maintain the
specified level of quality for the given measurement
system. Accuracy of analysis Is achieved through
the regular determination of bias and precision of
the results.
Bias is defined as the difference between the data
set mean value (or sample average for statistical
purposes) and the true or reference value (EPA87).
The NRD laboratory participates in EPA,
DOE/Environmental Measurements Laboratory
(EML), and World Health Organization (WHO)
laboratory intercomparison crosscheck studies.
The results of the EPA intercomparison study are
discussed later in this section. Blank samples and
samples "spiked" with known quantities of
radionuclides are also routinely run. Internal "blind
spiked" samples, (that is, samples spiked with
known amounts of radionuclides but unknown to
the analyst) are also entered into the normal chain
of analysis.
115
-------
Precision Is the degree of mutual agreement among
Individual measurements made under prescribed
conditions (EPA87). As a minimum, 10 percent of
all samples are collected and analyzed in duplicate,
and results compared.
In addition, Instruments are calibrated with
standards directly or indirectly traceable to National
Institute for Standards and Technology (NIST;
formerly National Bureau of Standards) or
NIST-approved EPA generated 'sources,
performance checks are routinely accomplished,
control charts of background and check source
data are maintained, and preventive maintenance
on equipment is scheduled and performed.
Health Physics Oversight
All analytical results receive a final review by the
health physics staff of the Dose Assessment Branch
for completeness and comparability. Trends of
Increasing or decreasing amounts of radionuclides
in the environment are identified, and potential risks
to humans and the environment are determined
based on the data.
Precision of Analysis
The duplicate sampling program was Initiated for
the purpose of routinely assessing the errors due to
sampling, analysis, and counting of samples
obtained from the surveillance networks maintained
bytheEMSL-LV.
The program consists of the analysis of duplicate or
replicate samples from the ASN, the NGTSN, the
MSN, and LTHMP, and the Dosimetry Network. As
the radioactivity concentration In samples collected
from the LTHMP and the MSN are usually below
detection levels, most duplicate samples for these
networks are prepared from spiked solutions. The
noble gas samples are generally split for analysis,
and duplicate samples are collected In the ASN.
Since two TLD cards consisting of three TLD
phosphors each are used at each station of the
Dosimetry Network, no additional samples were
necessary.
At least 30 duplicate samples from each network
are normally collected and analyzed over the report
period. Since duplicate samples were collected for
all other sample types, the variances, s2, for these
types were calculated from s2 = (0.886R)2 where R
is the range of the results. For small sample sizes,
this estimate of the variance is statistically efficient
(SNE67) and certainly more convenient to calculate
than the standard expression. The standard
deviation Is obtained by taking the square root of
the variance. Table 19 summarizes the sampling
Information for each surveillance network.
TABLE 19. Samples and analyses
Surveillance
Network
ASN
NGTSN
Dosimetry
MSN
LTHMP
Number of
Sampling
Locations
109
18
156
29
193
Samples
Collected
This Year
9,807
710(85Kr)
734(133Xe)
542
380
746
for Duplicate Sampling Program - 1988
Sets of
Duplicate
Samples Number
Collected Per Set
745 2
54 2
542 4-6
150 2
416 2
Sample
Analysis
Gross beta,
y Spectrometry
85Kr, 3H, HaO,
HTO, 133Xe
Effective dose
from gamma
^Sr, 3H
3H
116
-------
The variance, s2, of each set of replicate results was
estimated by the standard expression,
=2 „
n
i = 1
where n = number of sets of replicates.
The principle that the variances of random samples
collected from a normal population follow a
chi-square distribution fc2) was then used to
estimate the expected population standard
deviation for each type of sample analysis. The
expression used is a follows: (FRE62)
where m-1 = the degrees of freedom for ni
samples collected for the ith
replicate sample
si2 = the expected variance of the ith
replicate sample
s = the pooled estimate of sample
standard deviation derived from the
variance estimates of all replicate
samples (the expected value
of s2 iso2).
For expressing the precision of measurement In
common units, the coefficient of variation (s/x) was
calculated for each sample type. These are
displayed in Table 20 for those analyses for which
there were adequate data.
To estimate the precision of counting,
approximately ten percent of all samples are
counted a second time. These are unknown to the
analyst. Since all such replicate counting gave
results within the counting error, the precision data
In Table 20 represents errors principally In analysis.
Accuracy of Analysis
Data from the analysis of intercomparison samples
are statistically analyzed and compared to known
values and values obtained from other participating
laboratories. A summary of the statistical analysis is
given in Table 21, which compares the mean of
three replicate analyses with the known value. The
normalized deviation is a measure of the accuracy
of the analysis when compared to the known
concentration. The determination of this parameter
is explained in detail In the reference (JA81). If the
value of this parameter (in multiples of standard
normal deviate, unitless) lies between control limits
Surveillance
Network
ASN
NGTSN
Dosimetry
MSN
LTHMP
TABLE 20. Sampling
Analysis
7Be
^Kr
HaO*
TLD
40K
^Sr
3H
3H +
and Analytical Precision - 1988
Sets of
Replicate
Samples
Evaluated
6
53
90
542
70
12
65
67
Coefficient
of Variation
59
7.4
3.8
6.6
10
11
18
24
* Measurement of Atmospheric Moisture
117
-------
TABLE 21. EPA Quality Assurance Intercomparison Results - 1988
Analysis
Water Studies:
3H
51Cr
6000
65Zn
89Sr
^Sr
106RU
131,
134Cs
137Cs
Mean of
Replicate
Analyses
Month (pCi/L)
June
October
June
October
February
June
October
February
June
October
April
April
February
June
October
August
December
February
June
October
February
June
October
:
6042
2575
298.7
259.7
69.0
16.0
26.3
97.3
104.0
160.0
4.0
4.7
98.0
186.3
140.0
24.7
117.0
57.0
19.7
24.0
92.3
25.0
15.0
Normalized
Deviation from
Known Value Known Concentration
5565
2316
302.0
251.0
69.0
15.0
25.0
94.0
101.0
151.0
5.0
5.0
105.0
202.0
152.0
26.0
115.0
64.0
20.0
25.0
94.0
25.0
15.0
1.5
1.3
-0.2
0.6
0.0
0.3
0.5
0.6
0.5
1.0
-0.3
-0.4
-1.2
-1.4
-1.4
-0.3
0.3
-2.4
-0.1
-0.3
-0.6
0.0
0.0
(continued)
118
-------
TABLE 21. EPA Quality Assurance Intercomparison Results -1988
Analysis
Month
Mean of
Replicate
Analyses
(pCI/L)
Known Value
Normalized
Deviation from
Known Concentration
Milk Studies:
89,
'Sr
K
Urine Studies:
3H
Air Filter Studies:
Gross Alpha
Gross Beta
June
June
October
June
October
June
October
123.7*
6.7*
50.3
103.0
90.7
1189mg/L**
1600 mg/L
April 6028
November 2861
March
March
13.3 pCi
(total)
25.7* pCi
(total)
40.0
60
60
94.0
91.0
1600 mg/L
1600 mg/L
6202
3025
20.0
(total)
50.0
(total)
29.0
-30.8
-5.0
1.7
-0.1
-8.9
1.3
-0.5
-0.8
-2.3
8.0
* Normalized deviation from the known value exceeds three sigma due to computational errors.
** Normalized deviation from the known value exceeds three sigma due to inadequate counting time.
of -3 and +3, the precision or accuracy of the
analysis Is within normal statistical variation.
However, If the parameters exceed these limits, one
must suspect that there Is some other than normal
statistical variation that contributed to the difference
between the measured values and the known value.
As shown by Table 21, all but three analyses were
within the control limit, the three analyses which
exceed three sigma are footnoted.
The analytical methods were further checked on by
Laboratory participation in the semiannual
Department of Energy Quality Assurance Program
conducted by the Environmental Measurements
Laboratory, New York, New York. The results from
these tests (Table 22) Indicate that this Laboratory's
results were of acceptable quality.
119
-------
TABLE 22. Quality Assurance results
Analysis
7Be
In air
MMn
In air
57Co
In air
^Co
in air
134Cs
In air
137Cs
in air
137Cs
in soil
239pu
In soil
40|<
In soil
40|<
In vegetation
137Cs
In air
137Cs
in soil
239pu
in soil
40K
In soil
40K
In vegetation
Month
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
Sept.
March
Sept.
EPA
EMSL-LV
Results
5.09E03
.2.33E03
i
3.98E02
2.08E02
1.65E02
4.16E02
2.96E02
3.74E02
3.68E02
1.96E02
2.38E02
7.47E02
0.41 3EOO
1.16EOO
5.99E-02
3.55E-01
8.90EOO
4.05E01
1.10E01
2.38E02
7.47E02
0.41 3EOO
1.16EOO
5.99E-02
3.55E-01
8.90EOO
4.05E01
1.10E01
from DOE Program - 1988
EML
Results
4.73E03
2.16E03
3.63E02
1.85E02
1.62E02
3.94E02
2.82E02
3.74E02
3.81 E02
1.91E02
2.11E02
2.45E02
0.400EOO
9.10E-01
0.410E-02
3.80E-01
7.48EOO
3.60E01
1.05E01
2.11E02
2.45E02
0.400EOO
9.10E-01
0.410E-02
3.80E-01
7.48EOO
3.60E01
1.05E01
Ratio
EPA/EML
1.08
1.08
1.10
1.12
1.02
1.06
1.05
1.00
0.97
1.03
1.13
3.05
1.03
1.27
1.46
0.93
1.19
1.13
1.05
1.13
3.05
1.03
1.27
1.46
0.93
1.19
1.13
1.05
(continued)
120
-------
TABLE 22. Continued
Analysis
137Cs
in vegetation
239pu
in vegetation
3H
In water
Mn
in water
57Co
in water
«fc>
In water
^Sr
In water
134Cs
in water
137Cs
in water
239pu
in water
* Low result was caused
Month
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
March
Sept.
Sept.
EPA
EMSL-LV
Results
5.18EOO
1.63EOO
6.10E-02
2.46E-02
2.18E01
1.13E01
6.97EOO
1.59EOO
1.85EOO
3.65EOO
1.82EOO
3.86EOO
1.15E-01
8.79E-01
3.03EOO
1.08EOO
1.68EOO
2.05EOO
5.39E-03
by an arithmetic error.Our corrected result is
EML
Results
4.62EOO
1.52EOO
4.50E-02
2.10E-02
2.07E01
1.06E01
6.80EOO
1.52EOO
2.06EOO
3.36EOO
2.03EOO
3.68EOO
5.30E-01
9.30E-01
3.56EOO
9.70E-01
1.84EOO
1.95EOO
5.40E-03
Ratio
EPA/EML
1.12
1.07
1.36
1.17
1.05
1.07
1.02
1.05
0.90
1.09
0.90
1.05
0.22*
0.95
0.85
1.11
0.91
1.05
1.00
0.607 pCi/m L and the ratio of reported to EML is 1 . 1 5.
To measure the performance of the contractor
laboratory that analyzed the animal tissues, a
known amount of activity was added to several sets
of bone ash samples. The reported activity Is
compared to the known amount in Table 23
together with the calculated bias and precision. The
average bias for 239Pu was -16 percent and the
average bias for ^Sr was -22. The average
precision determined from three sets of duplicate
ash samples was 79 percent for 239Pu and 17
percent for ^Sr at background levels but was
5.4 percent and 0.4 percent, respectively, for a
duplicate spiked sample.
121
-------
TABLE 23. Quality Assurance results for the Bioenvironmental Program • 1988
Sample ID
and
Shipment
Number
Bone Ash
Ash A
75
Ash B
75
Ash C
75
Ash D
75
Ash-1
76
Ash-2
76
Ash-3
76
Ash-4
76
Ash A
77
Ash B
77
Nuclide
239pu
^Sr
239pu
^Sr
239pu
^Sr
239pu
9°sr
239pu
^Sr
239pu
^Sr
239pu
^Sr
239pu
9°sr
239pu
^Sr
239pu
9°sr
Activity Added
pCi/g Bone Ash
0.0822
11.08
0.0765
10.31
0
0
0
0
0
0
0
0
0.03245
8.60
0.0325
8.63
0.0778
10.3
0.0778
11.9
Activity Reported
pCi/g Bone Ash
0.065
11.3
0.095
11.7
-0.002
2.9
-0.002
2.9
0.009
2.7
0.001
2.9
0.014
9.5
0.035
9.6
0.063
9.9
0.067
11.5
±0.013
±0.3
± 0.021
±0.3
± 0.003
±0.13
± 0.004
±0.12
± 0.003
±0.11
± 0.0015
±0.11
± 0.007
±0.2
± 0.007
±0.2
± 0.009
±0.3
± 0.001
±0.3
%Bias*
or
Precision**
-23*
-22*
+ 20*
-13*
0.0**
0.0**
141**
0.06**
-61.0*
-21.0*
-3.4*
-20.0*
-21.0*
-30.0*
-16.0*
-26.0*
(continued)
122
-------
TABLE 23. Continued
Sample ID
and
Shipment
Number
Ash C
77
Ash D
77
Activity Added
Nuclide pCi/g Bone Ash
239Pu 0
90gr Q
Pu 0
^Sr 0
%Bias*
Activity Reported or
pCi/g Bone Ash Precision**
0.002 ± 0.0015 ~~|
2.4 ± 0.14
0.0006± 0.0015
2.4 ± 0.15 _
0.95**
0.0**
* Bias (B) = Recovery -1; where recovery is xi/u
and xi = net activity reported
u = activity added
**
Precision (Cv) = 2
where xi = first value
xa = second value
123
-------
8.0 Dose Assessment
S. C. Black
Estimated Dose from NTS Activities
The estimate of dose equivalent due to NTS activities is based on the total release of radioactivity
from the site as listed in Table 2. Since no significant radioactivity of recent NTS origin was detec-
table off site by the various monitoring networks, no significant exposure to the population living
around the NTS would be expected. To confirm this expectation, a calculation of estimated dose
was performed using EPA's AIRDOS/RADRISK program. The individuals exposed were considered
to be all of those living within a radius of 80 km of CP-1 on the NTS, a total of 8,000 individuals. The
individual with the maximum exposure from airborne NTS radioactivity would have been living at
Medlin's Ranch which is NNE from the NTS. That maximum dose was 0.01 /irem (1 x lO^/iSv). The
population dose within 80 km would have been 47 pers-//rem (4.7 x 10"7 person-Sv).
During calendar year 1988 there were four sources
for possible radiation exposure to the population of
Nevada, all of which produced negligible
exposures. The four sources were:
Operational releases of radioactivity from
the NTS, including that from drillback and
purging activities;
Radioactivity in migratory animals that was
accumulated during residence on the NTS;
World-wide distributions such as ^Sr in
milk, 85Kr in air, etc.; and
Background radiation due to natural
sources such as cosmic radiation, natural
radioactivity in soil, and 7Be in air.
The estimated dose equivalent exposures from
these sources to people living near the NTS are
calculated separately In the following subsections.
Estimated Dose from Worldwide Fallout
From the monitoring networks described in
previous sections of this report, the following
concentrations of radioactivity were found:
Tritium (0.25 pCI/m3 of air [9 mBq/m3])
85Kr (26 pCi/m3 of air [0.9 Bq/m3])
90Sr (1.5 pCi/L in milk [55 mBq/L])
137Cs (15 pCi/kg beef muscle [0.6 Bq/kg])
239Pu (140 fCi/kg beef liver [5.2 fBq/kg])
The dose Is estimated from these findings by using
the assumptions and dose conversion factors as
follows:
Adult breathing rate is 8400 nr/yr,
Milk intake (10-yr old) is 160 L/yr,
Liver consumption is 0.5 Ib/week = 11.8 kg/yr,
Meat consumption 248 g/day, when liver
consumption is subtracted this is 78.7 kg/yr.
The dose conversion factors are based on the ALI
divided by 5000 to convert to becquerels/mrem,
then converted to mrem/pCI:
mrem/pCI)
3H(6.2x10-l
90o_, /4 A w 41
137Cs (4.5 x 10'5 mrem/pCi)
239Pu(9x10"4mrem/pCi)
85
133
Kr (1.6 x 10" mrem/yr per pCi/m)
'Xe (2 x 10"4 mrem/yr per pCi/m3)
As an example calculation, the following is the result
for tritium:
0.25 pCi/m3 x 8400 m3/yr x 6.2 x 10'8
mrem/pCi x I03j
-------
Estimated Dose from Radioactivity In NTS Deer
The highest measured concentrations of
radionuclides In mule deer tissues occurred in deer
collected on the NTS. The average values were:
Tissue
137,
Cs
239
'PU
Liver (pCI/kg)
Muscle (pCI/kg)
2x107
2x107
47
70
0.094
i 0.21
In the unlikely event that one such deer was
collected by a hunter in off-site areas, his intake
could be calculated. Assuming 3 pounds of liver
and 100 pounds of meat and the radionuclide
concentrations listed above, the dose equivalents
could be:
Liver: 1.36 kg x [(2 x 107 x 6.2 x 10"8) +
(47 X 4.5 x 10'5) + (0.094 x 9 X 10"4)]
= 1.7 mrem
Muscle: 78.7 kg x [(2 x 107 x 6.2 x 10*8) +
(70 X 4.5 X 10'5) + (0.21 X 9 X 10"4)]
= 97.8 mrem
Thus, approximately 100 mrem would be delivered
to one Individual consuming the stated quantity of
meat and assuming no radioactivity was lost in food
preparation. About 99.85 percent of this dose
equivalent is caused by the tritium content of the
meat.
Dose from Background Radiation
In addition to external radiation exposure due to
cosmic rays and that due to the gamma radiation
from naturally occurring radionuclides in soil C°K,
uranium and thorium daughters, etc.), there Is a
contribution from 7Be that is formed in the
atmosphere by cosmic ray Interactions with oxygen
and nitrogen. The annual average Be
concentration measured by our air surveillance
network was 0.5 pCi/m3. With a dose conversion
factor for inhalation of 2.6 x 10"7 mrem/pCi, this
equates to 1.1 /*rem, a negligible quantity when
compared with the PIC measurements that vary
from 56 to 172 mrem, depending on location.
Summary
For an Individual with the highest exposure to NTS
effluent, that Is someone living at the Medlln's
Ranch, the NTS exposure, plus that due to
world-wide fallout plus background would add to:
(1 x 10"5 + 0.1 + 138)mrem = 138 mrem
(1.4 mSv). Both the NTS and worldwide
distributions contribute a negligible amount of
exposure compared to natural background. If that
same individual used the NTS deer meat without
sharing it with someone else, the exposure would
increase to 138 + 100 = 238 mrem (2.38 mSv).
126
-------
9.0 Sample Analysis Procedures
Analytical procedures
The procedures for analyzing samples collected for offsite surveillance are described by Johns et al.
(EMSL79) and are summarized in Table 24.
Table
Type of Analytical
Analysis Equipment
IG Ge(U) Gamma IG or GE(U)
Spectrometry** detector
calibrated at 0.5
keV/channel
(0.04 to 2 MeV
range) individual
detector
efficiencies
ranging from
15% to 35%.
Gross beta Low-level end
on air filters window, gas flow
proportional
counter with a
12.7 cm diameter
window
(SO^g/cm2).
80Sr, ^Sr Low-background
thin-window,
gas-flow,
proportional
counter.
24. Summary of
Counting
Period (min)
Air charcoal
cartridges and
Individual air
filters, 30 min; air
filter composites,
1200 min. 100
min for milk,
water,
suspended solids.
30
50
Analytical Procedures
Analytical
Procedures
Radionucllde
concentration
quantified from
gamma spectral
data by on-line
computer
program.
Radionuclides In
air filter
composite
samples are
identified only.
Samples are
counted after
decay of
naturally
occurring
radionuclides
and, if necessary,
extrapolated to
midpoint of
collection In
accordance with
t-"1-2 decay or an
experimentally
derived decay.
Chemical
separation by ion
exchange.
Separated
sample counted
successively;
activity
calculated by
simultaneous
solution of
equations.
Sample
Size
1 20-370 m3 for
air filters; and
charcoal
cartridges; 3-1/2
liters for milk and
water.
1 20-370 m3
1.0 liter for milk
or water. 0.1 to 1
kg for tissue.
Approximate
Detection Limit*
For routine milk
and water
generally, 5 pCi/L
for most
common fallout
radionuclides in a
simple spectrum.
Filters for LTHMP
suspended
solids, 6pCi/L
Air filters and
char- coal
cartridges, 0.04
pCi/m3
0.5 pCi/sample.
89Sr = 5pCI/L
MSr = 2 pCi/L
(continued)
127
-------
Table 24. (Continued)
Type of Analytical
Analysis Equipment
3H Automatic liquid
scintillation
counter with
output printer.
3H Enrichment Automatic
(Long Term scintillation
Hydroiogical counter with
Samples) output printer.
238pUi 238pu A|pha
spectrometer
with silicon
surface barrier
detectors
operated in
vacuum
chambers.
MKr, 133Xe, 13S Xe Automatic liquid
scintillation
counter with
output printer
Counting Analytical
Period (min) Procedures
300 Sample prepared
by distillation.
•'
i
300 Sample
concentrated by
electrolysis
followed by
distillation.
1000 - 4000 Water sample or
acid-digested
filter or tissue
samples
separated by ion
exchange,
electroplated on
stainless steel
planchet.
200 Separation by
gas
chromatography;
dissolved in
toluene "cock-
tail" for counting.
Sample Approximate
Size Detection Limit*
4 ml for water. 400 pCi/L
250 ml for water. 10pCi/L
1 .0 liter for water; 238Pu = 0.08
0.1 to 1 kg for pCI/L ^Pu =
tissue; 5000 to 0.04 pCI/L for
10,000m3 for air. water. For tissue
samples,
0.04 pCI per total
sample for all
isotopes; 5 to
10aCI/m3for
Plutonium on air
filters.
0.4 to 1.0m3 for MKr, 133Xe, 135Xe
air. - 4 pCI/m3
* The detection limit is defined as 3.29 slgma, where slgma equals the counting error of the sample and Type I error =
Type II error « 5 percent (DOE81).
** Gamma Spectrometry using either an Intrinsic germanium (IG), or lithium-drifted germanium diode (Ge(LI)) detector.
128
-------
10.0 Radiation Protection Standards for External and Internal
Exposure
Dose Equivalent Commitment
For stochastic effects in members of the public, the following limits are used:
Effective Dose Equivalent*
Occasional annual exposures**
Prolonged period of exposure
mrem/yrmSv/yr
500 5
100 1
includes both effective dose equivalent from external radiation and committed
effective dose equivalent from ingested and inhaled radionuclides.
**0ccasional exposure implies exposure over a few years with the provision that over a lifetime
the average exposure does not exceed 100 mrem (1 mSv) per year (ICRP83).
Concentration Guides
ICRP-30 (ICRP79) lists Derived Air Concentrations
(DAC) and Annual Limits of Intake (ALI). The ALI is
the secondary limit and can be used with assumed
breathing rates and Ingested volumes to calculate
concentration guides. The concentration guides
(CGs) In Table 25 were derived In this manner and
yield the committed effective dose equivalent (50
year) of 100 mrem/yr for members of the public.
EPA Drinking Water Guide
In 40 CFR 141 (CFR88) the EPA set allowable
concentrations for continuous controlled releases of
radionuclides to drinking water sources. Any single
or combination of beta and gamma emitters should
not lead to exposures exceeding 4 mrem/yr. For
tritium this is 20,000 pCI/L (740 Bq/L) and for
8 pCI/L (0.3 Bq/L).
90
'Srls
129
-------
TABLE 25. Routine Monitoring Frequency, sample size,
Nuclide
Sampling
Frequency
Locations
Air Surveillance Network
7Be
*Zr
^Nb
"MO
103Ru
131,
132Te
137Cs
140Ba
140La
141Ce
144Ce
" »Pu
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
all
all
all
all
all
all
all
all
all
all
all
all
all
Sample
Size
m3
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
1120
Count
Time
Minutes
30
30
30
30
30
30
30
30
30
30
30
30
1000
MDC and concentration guides
Concentrations Guide*
Bq/m3
1700
12
110
110
58
4
17
12
120
120
52
1.2
5E-4
nCi/m3
47
0.3
3
3
1.5
0.1
0.5
0.3
3
3
1.4
0.03
1E-5
MDC
mBq/m3
17
4.1
1.8
1.5
1.8
1.8
1.8
1.8
4.8
2.6
3.0
12
1.48E-3
MDC
%CG
1E-3
4E-2
2E-3
2E-3
3E-3
4E-2
1E-2
2E-2
4E-3
2E-3
6E-3
1.0
0.32
(continued)
-------
Sampling
Nuclide Frequency
Locations
Noble Gas & Tritium in Air
Gross Beta
3H
^Kr
133Xe
135Xe
3/wk
1/wk
1/wk
1/wk
1/wk
Water Surveillance Network
3H
3H +
"fer
^Sr
137Cs
^Ra
Ru
1/mo
1/mo
1st time
1st time
1/mo
1st time
1st time
all
17
17
17
17
(LTHMP)**
all
all
all
all
all
all
all
Sample
Size
m3
160-240
5
0.4
0.4
0.4
Liters
1
0.1
1
1
1
1
1
TABLE 25.
Count
Time
Minutes
30
150
200
200
200
Minutes
200
200
50
50
100
1000
1000
(Continued)
Concentrations Guide*
Bq/m3
2E-2
46E2
22E3
18E3
2300
Bq/L
740
740
16
0.8
3.3
1.4
8.2
nCi/m3
5E-4
125
620
490
62
pCi/L
2E4
2E4
440
22
88
39
220
MDC
mBq/m3
0.11
148
148
370
370
Bq/L
12
0.37
0.18
0.074
0.33
NA
NA
MDC
%CG
6E-1
3E-3
6E-4
2E-3
2E-2
1.6
5E-2
1.1
9.2
10
(continued)
-------
TABLE 25. ROUTINE MONITORING FREQUENCY, SAMPLE SIZE, MDC AND CONCENTRATION GUIDES
Sampling
Nuclide Frequency
Water Surveillance Network
^U 1st time
^U 1st time
238Pu 1st time
^Pu 1st time
Gamma 1/mo
Milk Surveillance Network
3H 1/mo
131I 1/mo
137Cs 1/mo
^Sr 1/mo
^Sr 1/mo
Gamma 1/mo
Sample
Locations Size
(LTHMP)
all
all
all
all
all
all
all
all
all
all
all
Liters
1
1
1
1
3.5
3.5
3.5
3.5
3.5
3.5
3.5
Count
Time Concentrations Guide*
Minutes Bq/L pCi/L
1000 10 280
1000 10 280
1000 6.2 170
1000 4.1 110
30
200 12E4 3E6
100 41 1E3
100 160 4E3
50 820 2E4
50 40 1E3
50 -
MDC
Bq/L
MA
NA
0.003
0.002
0.18
12
0.18
0.33
0.18
0.074
0.18
MDC
%CG
0.05
0.05
<0.2
0.01
0.44
0.2
0.02
0.18
<0.2
(continued)
-------
TABLE 25. ROUTINE MONITORING FREQUENCY, SAMPLE SIZE, MOC AND CONCENTRATION GUIDES
Sampling
Nuclide Frequency Locations
Dosimetry Network
TLD (Personnel) 1/mo 61
TLD (Station) 1/qtr 154
PIC weekly 28
Sample Count
Size Time
Number
1 —
6
2016
MDC
Concentrations Guide* MDC % CG
Exposure
Guide MDA
100mR 2mR 2
2mR
3«R/hr
NA- Not Available
* AU and OAC values from ICRP-30 modified to 1 mSv annual effective dose equivalent for continuous exposure Te and I data corrected to 2 g thyroid, greater milk intake,
and smaller volume of air breathed annually (1 year-old infant).
** For tritium, Sr and Cs the concentration guide is based on Drinking Water Regs. (4 mrem/yr).
-------
11.0 References
BEIR80 The Effects on Populations of Exposure to
Low Levels of Ionizing Radiation: 1980, Committee
on the Biological Effects of Ionizing Radiations.
(Available from National Academy Press, 2101
Constitution Ave, N.W., Washington, DC 20418.)
BE73 Bernhardt, D. E., A. A. Moghissi and
J. A. Cochran, 1973, Atmospheric Concentrations of
Fission Product Noble Gases, pp. 4-19, in Noble
Gases, CONF-730915.
CA85 California, 1985, personal communication
from California county agents.
CFR88 Title 40 Code of Federal Regulations
Section - 141, Drinking Water Regulations, Federal
Register, Volume 41,1988.
DOC86 1986 Population and 1985 Per Capita
Income Estimates for Counties and Incorporated
Places, U.S. Department of Commerce, Bureau of
the Census, Publication P-26.
DOE81 J. P. Corley, D. H. Denham, R. E. Jaquish,
D. E. Michels, A. R. Olsen, D. A. Waite, A Guide for
Environmental Radiological Surveillance at U.S.
Dept of Energy Installations, July 1981, Office of
Operational Safety Report, DOE/EP-0023, U.S.
DOE, Washington, D.C.
DOE85 U.S. Department of Energy, 1985,
Environmental Protection, Safety, and Health
Protection Information Reporting Requirements.
Order DOE 5484.1, November 6,1987.
DOE89 U.S. Department of Energy, 1989, personal
communication from Health Physics Division,
DOE/NV, Las Vegas, NV.
DOE88 U.S. Department of Energy, 1988, General
Environmental Protection Program, DOE Order
5400.1, November 9,1988.
EMSL79 "Radlochemical and Analytical Procedures
for Analysis of Environmental Samples"
(EMSL-LV-0539-17-1979).
EPA80 U.S. Environmental Protection Agency,
1980, Upgrading Environmental Radiation Data,
Health Physics Society Committee Report HPSR-1,
EPA 520/1-80-012, U.S. Environmental Protection
Agency, Washington, DC.
EPA84 U.S. Environmental Protection Agency,
1984, Donald D. Smith and J. S. Coogan,
Population Distribution Around the Nevada Test
Site, EPA-600/4-84-067, DOE/DP/00539-053, U.S.
Environmental Protection Agency, Washington, D.C.
EPA87 U.S. Environmental Protection Agency,
1987, Quality Assurance Program Plan,
EPA/600/X-87/241, EMSL-LV, P.O. Box 93478, Las
Vegas, NV 89193-3478.
EPA88 Environmental Radiation Data, Draft Report
55, U.S. EPA, Office of Radiation Programs Eastern
Environmental Radiation Facility, Montgomery
Alabama, 1988.
EPA89 EPA Journal, United States Environmental
Protection Agency, Office of Public Affairs (A-107),
Washington, D.C. 20460.
ERDA77 U.S. Energy Research and Development
Administration, 1977, "Final Environmental Impact
Statement, Nye County, Nevada." Nevada
Operations Office, Las Vegas, NV, Report
ERDA-1551. (Available from U.S. Department of
Commerce, NTIS, Springfield, VA 22161.)
FRE62 Freund, J. E. Mathematical Statistics.
Prentice Hall, Englewood, New Jersey, 1962, pp.
189-235.
HO75 Houghton, J. G., C. M. Sakamoto, and R. O.
Gifford, 1975, "Nevada Weather and Climate."
Special Publication 2. Nevada Bureau of Mines and
Geology, Mackay School of Mines, University of
Nevada, Reno, Nevada, pp. 69-74.
ICRP79 International Commission in Radiological
Protection, Limits for Intake of Radionuclides by
Workers, ICRP-30,3 parts, 1979.
ICRP83 Annual Limits on Intakes (ALI) and Derived
Air Concentrations (DAC) for Members of the
Public, ICRP-39,1983.
JA81 Jarvis, A. N. and L Siu, 1981, Environmental
Radioactivity Laboratory Intercomparison Studies
Program - FY1981-82, EPA-600/4-81-004, U.S. EPA,
Environmental Monitoring Systems Laboratory, Las
Vegas, Nevada.
J. Qual. Tech. Z (1),
NEL75 Nelson, Loyd S.
January (1975).
NPS80 National Park Service, 1980, personal
communication with Chief Ranger R. Rainer, Death
Valley National Monument, Death Valley, California.
135
-------
NV86 Nevada Department of Agriculture, 1986, UT87 Utah Department of Agriculture, 1987, "Utah
"Nevada Agricultural Statistics 1985." Nevada Crop Agricultural Statistics, 1987." State of Utah
and Livestock Reporting Service, Reno, Nevada. Department of Agriculture, Salt Lake City, Utah.
QU68 Quiring, R. E., 1968, "Climatological Data, WI75 Winograd, I. J. and W. Thordarson, 1975,
Nevada Test Site, Nuclear Rocket Development Hydrogeologic and hydrochemical framework,
Station (NRDS)." ERLTM-ARL-7. ESSA Research south-central Great Basin, Nevada-California, with
Laboratories, Las Vegas, Nevada. special reference to the Nevada Test Site, USGS
SNE67 Snedecor, G. W., and W. G. Cochran. Professional Paper 712-C, Denver, Colorado.
Statistical Methods. The Iowa State University
Press, Ames, Iowa, 6th Ed. 1967, pp. 39-47.
* U.S. GOVERNMENT PRINTING OFFICE: 1989-680-704
-------
TECHNICAL REPORT DATA
(Please read Instructions on the reverse before completing)
i. REPORT NO.
DOE/DP/0539-061
2- EPA/600/4-89/019
May 1989
3. RECIPIENT'S ACCESSION NO.
4. TITLE AND SUBTITLE
OFFSITE ENVIRONMENTAL MONITORING REPORT:
Radiation Monitoring Around U.S. Nuclear Test Areas,
Calendar Year 1988
5. REPORT DATE
6. PERFORMING ORGANIZATION CODE
c.A. Fontana, N.R. Sunderland, S.C. Black,
B.B Dicey, A.N. Jarvis, K.S. Moroney, A.A. Mullen,
V.E. Niemann, P.P. Smith. E.A. Thompson
8. PERFORMING ORGANIZATION REPORT NO.
9. PERFORMING ORGANIZATION NAME AND ADDRESS
Environmental Monitoring Systems Laboratory
Office of Research and Development
U.S Environmental Protection Agency, P.O. Box 93478
Las Vegas, NV 89193-8518
10. PROGRAM ELEMENT NO.
XLUF10
11. CONTRACT/GRANT NO.
IAG DE-A108-86NV10522
12. SPONSORING AGENCY NAME AND ADDRESS
U.S. Department of Energy
Nevada Operations Office
P.O. Box 98518
Las Vegas, NV 89193-8518
13. TYPE OF REPORT AND PERIOD COVERED
Response - 1988
14. SPONSORING AGENCY CODE
EPA 600/07
15. SUPPLEMENTARY NOTES
Prepared for the U.S. Department of Energy under Interagency Agreement No.
DE-A108-86NV10522
6. ABSTRACT
This report covers the routine radiation monitoring activities conducted by the
Environmental Monitoring Systems Laboratory-Las Vegas in areas which may be affected by
nuclear testing programs of the Department of Energy. This monitoring is conducted to
locument compliance with standards, to identify trends in environmental radiation, and
to provide such information to the public. It summarizes these activities for calendar
ear 1988.
b radioactivity attributable to NTS activities was detectable offsite by the monitoring
letworks. Using recorded wind data and Pasquill stability categories, atmospheric dis-
ersion calculations based on reported radionuclides releases yield an estimated dose of
.7xlO"5 person-rem to the population within 80 km of the Nevada Test Site during 1988.
forld-wide levels of 85Kr, 9DSr, 137Cs, and 23?pu detected by the monitoring networks
rould cause maximum exposure to an individual of less than 0.27mrem per year. The in-
rease in ^Kr air concentration continued at a lower rate. Cesium and strontium in
Ilk were near their detection limits. An occasional net exposure to offsite residents
as been detected by the TLD network. On investigation, the cause of such net exposures
as been due to personal habits or occupational activities, not to NTS activities.
KEY WORDS AND DOCUMENT ANALYSIS
b.IDENTIFIERS/OPEN ENDED TERMS C. COSATI Field/Group
DESCRIPTORS
3. DISTRIBUTION STATEMENT
RELEASE TO THE PUBLIC
19. SECURITY CLASS (This Rrpoi
UNCLAS SIFTED
130
20. SECURITY CLASS (Thispage)
UNCLASSIFIED
22. PRICE
EPA Form 2220-1 (R«v. 4-77) PREVIOUS EDITION IS OBSOLETE
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^VM? '"•*'••- xx -
*- * '.^ • ;*. k S Xj
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