&EPA
United States
Environmental Protection
Agency
Environmental Monitoring
Systems Laboratory
P.O. Box 93478
Las Vegas NV 89193-3478
EPA/600/4-87/017
DOE/DP/00539/058
May 1987
Research and Development
Off-Site
Environmental
Monitoring Report:
Radiation Monitoring
Around United States
Nuclear Test Areas,
Calendar Year
1986
prepared for the
United States Department of Energy
under Interagency Agreement
Number DE-AI08-76DP00539
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EPA-600/4-87-017
DOE/DP/00539-058
May 1987
OFF-SITE ENVIRONMENTAL MONITORING REPORT
Radiation Monitoring Around United States
Nuclear Test Areas, Calendar Year 1986
compiled by
R. G. Patzer, C. A. Fontana,
R. F. Grossman, S. C. Black, R. Ec Dye,
D. D. Smith, D. J. Thome', A. A. Mullen, and
Nuclear Radiation Assessment Division
prepared for the
U.S. Department of Energy
under Interagency Agreement
Number DE-AI08-76DP00539
ENVIRONMENTAL MONITORING SYSTEMS LABORATORY
OFFICE OF RESEARCH AND DEVELOPMENT
U.S. ENVIRONMENTAL PROTECTION AGENCY
LAS VEGAS, NEVADA 89114
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NOTICE
The information in this document has been funded wholly or in part by the
United States Environmental Protection Agency under IAG DE-AI08-76DP00539 to
the United States Department of Energy. It has been subject to the Agency's
peer and administrative review, and it has been approved for publication as
an EPA document. Mention of trade names or commercial products does no con-
stitute endorsement or recommendation for use.
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PREFACE
The U.S. Atomic Energy Commission (AEC) used the Nevada Test Site (NTS)
from January 1951 through January 19, 1975, for conducting nuclear weapons
tests, nuclear rocket-engine development, nuclear medicine studies, and other
nuclear and non-nuclear experiments. Beginning January 19, 1975, these activ-
ities became the responsibility of the newly formed U.S. Energy Research and
Development Administration (ERDA). On October 1, 1977 the ERDA was merged with
other energy-related agencies to form the U.S. Department of Energy (DOE).
Atmospheric nuclear tests were conducted periodically from January 27, 1951,
through October 30, 1958, after which a testing moratorium was in effect until
September 1, 1961. Since September 1, 1961, all nuclear detonations have been
conducted underground with the expectation of containment, except for four
slightly above-ground or shallow underground tests of Operation Dominic II in
1962 and five nuclear earth-cratering experiments conducted under the Plowshare
program between 1962 and 1968.
Prior to 1954, an off-site surveillance program was performed by the Los
Alamos Scientific Laboratory and the U.S. Army. From 1954 through 1970 the
U.S. Public Health Service (PHS), and from 1970 to the present the U.S. Envi-
ronmental Protection Agency (EPA) have provided an Off-Site Radiological Safety
Program under an Interagency Agreement. The PHS or EPA has also provided
off-site surveillance for U.S. nuclear explosive tests at places other than the
NTS.
Since 1954, an objective of this surveillance program has been to measure
levels and trends of radioactivity, if present, in the environment surrounding
testing areas to ascertain whether the testing is in compliance with existing
radiation protection standards. Off-site levels of radiation and radioactivity
are assessed by sampling milk, water, and air; by deploying dosimeters; and by
sampling food crops, soil, etc., as required. Personnel with mobile monitoring
equipment are placed in areas downwind from the test site prior to each test
in order to implement protective actions, provide immediate radiation monitoring,
and obtain environmental samples rapidly after any release of radioactivity.
Since 1962, aircraft have also been deployed to rapidly monitor and sample
releases of radioactivity during nuclear tests. Monitoring data obtained by
the aircraft crew immediately after a test are used to position mobile radiation
monitoring personnel on the ground. Data from airborne sampling are used to
quantify the amounts, diffusion, and transport of the radionuclides released.
Beginning with Operation Upshot-Knothole in 1953, a report was published
by the PHS summarizing the surveillance data for each test series. In 1959
for reactor tests, and in 1962 for weapons and Plowshare tests, such data were
published for those tests that released radioactivity detectable off the NTS.
n i
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The reporting interval was changed again in 1964 to semi-annual publication of
data for each 6-month period which also included the data from the individual
reports.
In 1971, the AEC implemented a requirement, now incorporated into DOE
Order 5484.1, that each contractor or agency involved in major nuclear act-
ivities provide a comprehensive annual radiological monitoring report. This is
the fifteenth annual report in this series; it summarizes the off-site
activities of the EPA during CY 1986.
IV
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CONTENTS
Preface. iii
Figures vii
Tables ix
Abbreviations, Symbols and Conversions xi
Prefixes, Conversions. ............... xii
1. Introduction ....... ......... 1
2. Summary 2
Purpose 2
Locations 2
Special Test Support 2
Pathways Monitoring 3
External Exposure 4
Internal Exposure 4
Community Monitoring Stations 4
Dose Assessment 4
3. Description of the Nevada Test Site 6
Site Location 6
Cl imate 6
Geology and Hydrology 8
Land use of NTS Environs 8
Population Distribution . . 9
Airborne Releases of Radioactivity at the NTS During 1986 ... 9
4. Quality Assurance. 11
Goals 11
Sample Collection .......... . 11
Sample Analysis 11
External QA. ........... .... 11
Internal QA 12
Validation 12
Audits 13
5. Radiological Safety Activities . 14
Special Test Support 14
Pathways Monitoring ..... 15
Air Surveillance Network 15
Noble Gas and Tritium Surveillance Network . 19
Long-Term Hydro!ogical Monitoring Program 24
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CONTENTS (Continued)
5. (Cont)
Milk Surveillance Network. 27
Biomonitoring Program . 31
External Exposure Monitoring 35
Thermo!uminescent Dosimetry Network. . 35
Pressurized Ion Chamber Network . 42
Internal Exposure Monitoring 43
Network Design 45
Methods. 46
Results 46
Community Monitoring Stations ....... .... 48
Claims Investigations 48
Public Information Program 49
Dose Assessment 51
Estimated Dose from NTS Activities . . 52
Estimated Dose from Tunnel Purging ............. 52
Estimated Dose from World-wide Fallout ..... . 52
Radioactivity in NTS Deer. ........... 53
Estimated Dose from Chernobyl 54
Background Radiation ...... 54
6. References ........... 60
Appendices
A. Site Data A-l
B. Sample Analysis Procedures B-l
C. Quality Assurance Procedures ................... C-l
D. Radiation Protection Standards for External and Internal
Exposure ............................ 0-1
E. Data Summary for the Monitoring Networks E-l
Addenda
1. REECO Nonradiological Supplement to the NTS Environmental
Monitoring Report Add-1
2. Environmental Permits, Orders, and Notices ....... Add-3
3. Environmental Impact Statements and Environmental Assessments. . . Add-12
VI
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FIGURES
Number Page
1 Location of the Nevada Test Site. ........... 7
2 Air Surveillance Network stations (1986) 16
3 Standby Air Surveillance Network stations (1986). . . . . 17
4 Monthly average gross beta in air samples, 1981-1986. . . 20
5 Noble Gas and Tritium Surveillance Network
sampling locations. . 21
6 Weekly average krypton-85 concentration in air, 1986 data ..... 23
7 Trend in annual average krypton-85 concentration 23
8 LTHMP sampling locations on the NTS 25
9 LTHMP sampling locations near the NTS 26
10 Milk sampling locations within 300 km of the NTS. 29
11 Standby milk surveillance network stations. . 30
12 Strontium-90 concentration in Pasteurized Milk Network
samples 32
13 Collection sites for bighorn sheep
deer and cattle samples 33
14 Average strontium-90 concentration in animal bone .......... 39
15 Locations monitored with TLD's 41
16 Average annual TLD exposure as a function of station
altitude 44
17 Location of families in the Off-Site Human Surveillance
Program 47
vn
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FIGURES (Continued)
Number
A-l Ground-water flow systems around the
Nevada Test Site A-4
A-2 General land use within 300 km of the
Nevada Test Site . A-5
A-3 Population of Arizona, California, Nevada, and Utah
Counties near the Nevada Test Site (1985) A-7
A-4 Distribution of family milk cows and goats,
by county (1986) A-8
A-5 Distribution of dairy cows, by county (1986) ........... A-9
A-6 Distribution of beef cattle, by county (1986). .... A-10
A-7 Distribution of sheep, by county (1986). A-ll
E-l Amchitka Island and background sampling locations
for the LTHMP. E-25
E-2 LTHMP sampling locations for Project Cannikin E-26
E-3 LTHMP sampling locations for Projects Mil row and Long Shot .... E-28
E-4 LTHMP sampling locations for Project Rio Blanco. ... E-30
E-5 LTHMP sampling locations for Project Rulison E-32
E-6 LTHMP sampling locations for Project Dribble -
towns and residences E-33
E-7 LTHMP sampling locations for Project Dribble - near GZ E-35
E-8 LTHMP sampling locations for Project Dribble -
near Salt Dome _ E-37
E-9 LTHMP sampling locations for Project Faultless . . E-39
E-10 LTHMP sampling locations for Project Shoal E-41
E-ll LTHMP sampling locations for Project Gasbuggy E-42
E-12 LTHMP sampling locations for Project Gnome E-43
vm
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TABLES
Number Page
1 Total Airborne Radionuclide Emissions at the NTS During 1986. ... 10
2 Annual Average Krypton-85 Concentrations in Air, 1976-1986 22
3 Water Sampling Locations Where Samples Contained
Man-made Radioactivity - 1986 28
4 Network Annual Average Concentrations of Tritium
and Strontium-90 in Milk, 1975-1986 31
5 Radionuclide Concentrations in Desert Bighorn Sheep
Samples - 1985 34
6 Radionuclide Concentrations in Tissues From Mule Deer
Collected on the Nevada Test Site, 1986 36
7 Dosimetry Network Summary for the Years 1971-1986 44
8 Pressurized Ion Chamber Readings, 1986. ... 45
9 Thyroid Inhalation Dose Equivalent,
May and June 1986 55
Appendices
A-l Characteristics of Climatic Types in Nevada ... A-2
B-l Sample Analysis Procedures B-l
C-l Samples and Analyses for Duplicate Sampling Program - 1986 C-2
C-2 Sampling and Analytical Precision - 1986 C-3
C-3 EPA Quality Assurance Intercomparison Results - 1986 C-4
C-4 Quality Assurance Results from DOE Program - 1986 -. . C-5
C-5 Quality Assurance Results for the Bioenvironmental Program - 1986 . C-7
C-6 Summary Results of the Eighth International
Intercomparison of Environmental Dosimeters C-9
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TABLES (Continued)
Number
D-l Routine Monitoring Frequency, Sample Size, MDC and
Concentration Guides D-2
E-l Summary of Analytical Results for Air Surveillance
Network Continuously Operating Stations - 1986 ........ E-l
E-2 Summary of Analytical Results for Air Surveillance Network
Standby Stations Operated 1 or 2 Weeks per Quarter - 1986. . . E-6
E-3 Summary of Gross Beta Analyses for
Air Surveillance Network - 1986. E-16
E-4 Plutonium-239 Concentration in Composited
Air Samples - 1986 ............ E-17
E-5 Summary of Analytical Results for the Noble Gas
and Tritium Surveillance Network - 1986. . . E-18
E-6 Summary of Tritium Results for the NTS Network
Long-Term Hydrological Monitoring Program - 1986 E-20
E-7 Tritium Results for the Long-term Hydrological
Monitoring Program - 1986 E-21
E-8 Summary of Analytical Results for the Milk
Surveillance Network - 1986. ........... . E-46
E-9 Analytical Results for the Standby Milk Surveillance
Network - 1986 E-50
E-10 Summary of Radiation Dose Equivalents from
TLD Data - 1986 E-56
E-ll Summary of Radiation Doses for Off-Site Residents - 1986 .... E-63
E-12 Noble Gas Samples Containing Detectable Concentrations
of Xenon-133 - 1986 E-66
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ABBREVIATIONS, SYMBOLS AND CONVERSIONS
ASN Air Surveillance Network
Bq Becquerel, one disintegration per second
CG Concentration Guide
Ci Curie
CP-1 Control Point One
CY Calendar Year
d day
DOE U.S. Department of Energy
DOE/NV Department of Energy, Nevada Operations Office
EMSL-LV Environmental Monitoring Systems Laboratory-, Las
EPA U.S. Environmental Protection Agency
eV electron volt
g gram
Gy Gray, equivalent to 100 rad (1 J/kg)
GZ Ground Zero
h hour
HTO tritiated water
L liter
LTHMP Long-Term Hydrological Monitoring Program
m meter
MDC Minimum Detectable Concentration
MSL Mean Sea Level
MSN Milk Surveillance Network
.NGTSN Noble Gas and Tritium Surveillance Network
NTS Nevada Test Site
Pa Pascal - unit of pressure
PIC Pressurized ion chamber
R Roentgen
rad unit of absorbed dose, 100 ergs/g
rem the rad adjusted for biological effect
Sv Si evert, equivalent to 100 rem
TLD thermoluminescent dosimeter
Vegas
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PREFIXES
a atto =
f femto =
p pi co =
n nano =
p micro =
m mi 1 1 i =
k kilo =
M mega =
CONVERSION
Multiply By
Concentration Guides
yCi/mL 109
yCi/mL 1012
SI Units
rad 10-2
rem 10"2
pCi 0.037
10-18
10-15
10-12
10-9
10-6
lO'3
103
106
4S
To Obtain
pCi/L
pC i /m3
Gray (Gy = 1
Si evert (Sv)
Becquerel
XI 1
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SECTION 1
INTRODUCTION
The EMSL-LV operates an Off-Site Radiological Safety Program around the
NTS and other sites as requested by the Department of Energy (DOE) under an
Interagency Agreement between DOE and EPA. This report, prepared in accordance
with DOE guidelines (DOE85), covers the program activities for calendar year
1986. It contains descriptions of pertinent features of the NTS and its en-
virons, summaries of the EMSL-LV- dosimetry and sampling methods, analytical
procedures, quality assurance, and the analytical results from environmental
measurements. Where applicable, dosimetry and sampling data are compared to
appropriate guides for external and internal exposures of humans to ionizing
radiation.
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SECTION 2
SUMMARY
Purpose
It is U.S. Environmental Protection Agency (EPA) policy to protect the
general public and the environment from pollution caused by human activities.
This includes radioactive contamination of the biosphere and concomitant
radiation exposure of the population. To this end and in concordance with U.S.
Department of Energy (DOE) policy of keeping radiation exposure of the general
public as low as reasonably achievable, the EPA's Environmental Monitoring
Systems Laboratory in Las Vegas (EMSL-LV) 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 principal activity at
the NTS is testing of nuclear devices, though other related projects are also
conducted.
The principal 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 are conducted to
document compliance with standards, to identify trends, and to provide informa-
tion to the public. This report summarizes these activities for CY 1986.
Locations
Most of the radiological safety effort is applied in the areas around the
Nevada Test Site (NTS) in south-central Nevada. This portion of Nevada is
sparsely settled, 0.5 person/km^, and has a continental arid climate. The
largest town in the near off-site area is Beatty, located about 65 km west of
the NTS with a population of about 1S000.
Underground tests have been conducted in several other States for various
purposes. At these sites in Alaska, Colorado, New Mexico, and Mississippi, a
long-term hydrological monitoring program is conducted to detect any possible
radioactive contamination of potable water and aquifers near these sites.
Special Test Support
During CY86, personnel were deployed in support of the 13 announced nu-
clear tests at the NTS. Twice radioactivity of NTS origin was detected off
site. Once was during the planned purging of T-tunnel following the Mighty
Oak test. Xenon-133 was detected at Penoyer Farms, Nevada, at concentrations
which could have led to a dose of 2.7 x 10~4 mrem (2.7 x 10'° mSv). The other
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was during a drillback operation when a xe-133 concentration of 84 pCi/m was
detected in the sample from Lathrop Wells the week ending March 31.
Pathways Monitoring
The pathways leading to human exposure to radionuclides (air, water, and
food) are monitored by networks of sampling stations. The networks are
designed not only to detect radiation from DOE/NV nuclear test areas but also
to measure population exposure from other sources. Some positive results were
obtained this year. These resulted from three incidents that occurred during
1986, namely: the tunnel purging following the Mighty Oak test, the accident
at the Chernobyl nuclear plant in the Soviet Union, and the drillback operation
on the NTS in March.
In 1986 the air surveillance network (ASN) consisted of 30 continuously
operating stations surrounding the NTS and 83 standby stations (operated 1 or 2
weeks each quarter) in all States west of the Mississippi River. Gamma-emitting
radionuclides were detected by the Air Surveillance Network. These included
beryllium-7, a naturally occurring nuclide, and several fresh fission products
(Tables E-l and E-12) that resulted from the Chernobyl accident. The concen-
trations were too low to have any health significance. The average of gross
beta results on selected air samples was higher during the Chernobyl fallout
period in early to mid-May.
The noble gas and tritium sampling network (NGTSN) consisted of 17 sta-
tions off site (off the NTS and exclusion areas) in 1986. Krypton-85 concen-
trations in the Noble Gas and Tritium Sampling Network averaged 25 pCi/m^
(0.9 Bq/m^), consistent with the levels determined since 1981 (Table 2).
Krypton-85 concentrations reported previously for 1984-86 have been changed
in this report to correct an error in the -calibration source. Xenon-133 was
found in 45 samples with a maximum of 730 pCi/nP (27 Bq/m^) which occurred at
Groom Lake, Nevada, during the purging of the tunnel in which the Mighty Oak
test was conducted. In about 32 of these samples the xenon-133 is attributed
to the air emissions from the Chernobyl reactor.
The long-term monitoring of wells and surface waters near sites of nuclear
tests showed only background radionuclide 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 consisted of 28 sampling locations within
300 km of the NTS and about 122 standby locations in the Western U.S. The
tritium concentration in milk was at background levels, and strontium-90 from
worldwide fallout continued the slow downward trend observed in recent years.
Fission products from the Chernobyl accident were not detected in milk samples
except for low concentrations of cesium-137 detected at Seattle, Washington and
Flensburg, Minnesota (Table E-9). In addition, trace amounts of iodine-131
were detected in one group of special milk and green-chop (cattle feed) samples
collected at Las Vegas. These were not part of the routine network samples.
Other foods analyzed have been mainly meat from domestic or game animals.
The radionuclide most frequently found in the edible portion of the sampled
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animals is cesium-137. However, its concentration has been near the MDC since
1968. Strontiuni-90 in samples of animal bone remain at very low levels as does
plutonium-239 in both bone and liver samples. Of the Chernobyl fission pro-
ducts, only radioiodine was detected in samples of cow thyroid.
External Exposure
External exposure is monitored by a network of TLD's at 129 fixed loca-
tions surrounding the NTS and by TLD's worn by 53 off-site residents. In a few
cases, small exposures of a few mR above the average for the person were meas-
ured. Except for several occupational exposures, all such net exposures were
very low and were not related to NTS activities. The range of exposures meas-
ured, varying with altitude and soil constituents, is similar to the range of
such exposures found in other areas of the U.S.
Internal Exposure
Internal exposure is assessed by whole-body counting supplemented by
phoswich and intrinsic detectors to measure lung burdens of radioactivity. In
1986S counts were made on 102 off-site residents, as well as on 106 other
individuals for occupational or other reasons. Natural potassium-40 was found,
as well as trace amounts of cesium-137 from the Chernobyl accident, but no
nuclear test related radioactivity was detected. In addition, physical
examinations of the off-site residents revealed a normally healthy population
consonant with the age and sex distribution of that population.
Community Monitoring Stations
The 15 Community Monitoring Stations became operational in 1982. Each
station is operated by a resident'of the community who is trained to collect
samples and interpret some of the data. Each station is an integral part of
the ASN, NGTSN and TLD networks and is also equipped with a pressurized ion
chamber system and recording barograph. Samples and data from the stations are
analyzed by EMSL-LV and are also interpreted and reported by the Desert Research
Institute, University of Nevada. Data from these stations are reported herein
as part of the networks in which they participate. No detectable increase in
the external gamma background was found when the low-level Chernobyl debris
arrived in the Western U.S.
Dose Assessment
Doses were calculated for an average adult living in Nevada based on the
Kr-85, Sr-90, HTO and Pu-239 measured in samples collected from the monitoring
networks. Using conservative assumptions, the estimated dose would have been
about 0.12 mrem/yr (1.2 ySv/yr), a small fraction of the variation of 10 mrem/
yr due to the natural radionuclide content of the body. The only NTS-related
radioactivity detected during 1986 was xenon-133 in a weekly sample from
Lathrop Wells and in 12 special samples collected during the tunnel purging
following the Mighty Oak test. The highest concentration could have caused a
dose of 0.27 urem (2.7 x 10~3 ySv) to a person outdoors for the entire purging
period. No other radioactivity originating on the NTS was detectable by the
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monitoring networks so no dose assessment could be made on the reported emis-
sions (Table 1). However, atmospheric dispersion calculations, based on those
emissions, indicate that the highest individual dose would have been 1.4 urem
(0.014 ySv), and the dose to the population within 80 km of CP-1 (on the NTS,
Figure 8) would have been 5.7 x 10"^ person-rem (5.7 x 10"^ person-Sv). Maxi-
mum annual dose equivalents to the infant thyroid (1-131) from Chernobyl
fallout were about 0.8 mrem (8 ySv); for the whole body they were about 0.06
mrem (0.6 ySv).
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SECTION 3
DESCRIPTION OF THE NEVADA TEST SITE
Historically, the major programs conducted at the NTS have been nuclear
weapons development, proof-testing and weapons safety and effects, testing
peaceful uses of nuclear explosives (Plowshare Program), reactor engine devel-
opment for nuclear rocket and ramjet applications (Projects Rover and Pluto),
high-energy nuclear physics research, seismic studies (Vela Uniform), and
studies of high-level waste storage. During 1986, nuclear weapons development,
proof-testing and weapons safety, nuclear physics programs, and studies of high-
level waste storage were continued at the NTS. Project Pluto was discontinued
in 1964; Project Rover was terminated in January 1973; Plowshare tests were
terminated in 1970; Vela Uniform studies ceased in 1973. All nuclear weapons
tests after 1962 have been conducted underground. More detail and pertinent
maps for the portions of this section are included in Appendix A. Only selected
information is presented in this Section.
SITE 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 Nell is 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 at the time of testing, 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 varia-
tions in altitude and its rugged terrain. Generally, the climate is referred
to as continental arid. Throughout the year, there is insufficient precipita-
tion to support the growth of common food crops without irrigation.
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Nellis AFB [J375
Range Complex^
-
N
0
3/87
Scale in Miles
50 100
b
^^MBW
50 100 150 200
Scale in Kilometers
Figure 1. Location of the Nevada Test Site (NTS).
7
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As Houghton et al. (Ho75) point out, 90 percent of Nevada's population
lives in areas with less than 25 cm of rainfall per year or in areas that would
be classified as mid-latitude steppe to low-latitude desert regions.
The wind direction, as measured on a 30 m tower at an observation station
about 9 km NNW of Yucca Lake near CP-1, is predominantly northerly except
during 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. Wind patterns are often quite
different at other locations on the NTS because of local terrain effects and
differences in elevation.
GEOLOGY AND HYDROLOGY
Geological and hydrological studies of the NTS have been in progress by
the U.S. Geological Survey and various other organizations since 1956. Because
of this continuing effort, the surface and underground geological and hydro-
logical characteristics for much of the NTS are known in considerable detail
(see Figure A-l). This is particularly true for those areas in which under-
ground experiments are conducted. A comprehensive summary of the geology and
hydrology of the NTS was published in 1975 (Wi75).
The aquifers underlying the NTS vary in depths from about 200 m beneath
the surface of valleys in the southeastern part of the site to more than 500 m
beneath the surface of highlands to the north. Although much of the valley
fill is saturated, downward movement of water is retarded by various tuffs and
is extremely slow. The primary aquifer in these formations consists of
Paleozoic carbonates that underlie the more recent tuffs and alluviums.
LAND USE OF NTS ENVIRONS
Industry within the immediate off-NTS area includes approximately 40
active mines and mills, oil fields in the Railroad Valley area, and several
industrial plants in Henderson, Nevada. The number of employees for these
operations may vary from one person at several of the small mines to several
hundred workers for the oil fields north of the NTS and the industrial plants
in Henderson. Most of the individual mining operations involve less than 10
workers per mine; however, a few operations employ 100 to 250 workers.
The major body of water close to the NTS is Lake Mead (120 km southeast,
Figure A-2), a manmade lake supplied by water from the Colorado River. Lake
Mead supplies about 60 percent of the water used for domestic, recreational,
and industrial purposes in the Las Vegas Valley. Some Lake Mead water is used
in Arizona, southern California, and Mexico. Smaller reservoirs and lakes
located in the area are used primarily for irrigation, for watering livestock,
and for wildlife refuges.
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Dairy farming is not extensive within 300 km of the NTS. As shown in
Figures A-4 and A-5 the family cows and goats are distributed in all direc-
tions around the NTS, whereas most dairy cows are located to the southeast
(along the Muddy and Virgin River valleys and in Las Vegas, Nevada), northeast
(Lund), and southwest (near Barstow, California).
Grazing is the most common land use within 300 km of the site. Approxi-
mately 500,000 cattle and 150,000 sheep are distributed within the area as
shown in Figures A-6 and A-7, respectively. The estimates are based on infor-
mation supplied by the California Crop and Livestock reporting service (CA85),
from 1985 agricultural statistics supplied by the Nevada Department of Agri-
culture (NV86) and 1985 estimates based on 1982 census information supplied by
the Utah Department of Agriculture (UT82).
POPULATION DISTRIBUTION
Excluding Clark County, the major population center (approximately 536,000
in 1984), the population density within a 150 km radius of CP-1 on 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 all of Nevada
in 1980 was 2.8 persons per square kilometer.
The off-site area within 80 km of the NTS (the area in which the dose
commitment must be determined for the purpose of this report) is predominantly
rural, Figure A-2. 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 750, 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 1,000 and is located approximately
65 km to the west of CP-1.
AIRBORNE RELEASES OF RADIOACTIVITY AT THE NTS DURING 1986
All nuclear detonations during 1986 were conducted underground and were
contained, although occasional releases of low-level radioactivity occurred
during re-entry drilling, seepage through fissures in the soil or purging of
tunnel areas. Table 1 shows the total quantities of radionuclides released
to the atmosphere, as reported by the DOE Nevada Operations Office (DOE87).
Because these releases occurred throughout the year and because of the dis-
tance from the points of releases to the nearest sampling station, only twice
was any radioactive material listed in this table detected off site. In both
cases only Xe-133 was detectable. Debris from the Chernobyl reactor arrived in
the Western U.S. after the tunnel purging following the Mighty Oak test.
-------
TABLE 1. TOTAL AIRBORNE RADIONUCLIDE EMISSIONS
AT THE NTS DURING 1986
Radionuclide
Tritium
Krypton-85
Xenon-133
Xenon-133m
Xenon-135
Iodine-131
Half -Life
(days)
4500
3990
5.24
2.2
0.38
8.07
Quantity Released
(Ci)
120.7
4.3
36,000
0.058
0.041
2.4
10
-------
SECTION 4
QUALITY ASSURANCE
GOALS
The goals of the EMSL-LV quality assurance program are to assure the col-
lection and analysis of environmental samples with the highest degree of
accuracy and precision obtainable with state-of-the-art instrumentation and to
achieve the best possible completeness and comparability given the extent and
type of networks from which samples are collected. To meet these goals, it is
necessary to devote strict attention to sample collection, sample analysis,
and quality assurance procedures.
SAMPLE COLLECTION
The collection of samples is governed by a detailed set of Standard Opera-
ting Procedures (SOP's). These SOP's prescribe the frequency and method of
collection, the type of collection media, sample containment and transport,
sample preservation, sample identification and labeling, and operating param-
eters for the instrumentation. Sample control is an important segment of these
activities as it enables tracking from collection to analysis for each sample
and governs the selection of duplicate samples for analysis and the samples
chosen for replicate analysis.
These procedures provide assurance that sample collection, labeling and
handling are standardized to minimize sample variability due to inconsistency
among these variables.
individual Quality Assur-
plans assure that the
be comparable to results
Plans are summarized in
SAMPLE ANALYSIS
All of the networks operated by the EMSL-LV have
ance Project Plans. The procedures required by these
results of analysis will be of known quality and will
obtained elsewhere with equivalent procedures. These
the following sections.
External QA
External QA provides the data from which the accuracy of analysis (a com-
bination of bias and precision) can be determined. Bias is assessed from the
results obtained on intercomparison study samples and on samples "spiked" with
known amounts of radionuclides. The Off-Site Radiological Safety Program
11
-------
participates in Intercomparison Study Programs that include environmental
sample analysis, TLD dosimetry, and whole-body counting. Also, samples which
are undisclosed to the analyst are spiked by adding known amounts of radio-
nuclides and then entered into the normal chain of analysis.
Data for precision are collected from duplicate and replicate analyses.
At least 10 percent of all samples are collected in duplicate. When analyzed,
the data indicate the precision of both sample collection and analysis. Repli-
cate counting of at least 10 percent of all samples yield data from which the
precision of counting can be determined.
If the bias and precision data are of sufficient quality (i.e., normalized
deviation in Table C-3 is less than 3), then comparability, i.e., comparison of
the data with those of other analytical laboratories, can be assessed witn con-
fidence. The results of external QA procedures are shown in Appendix C.
Internal QA
Internal QA consists of those procedures used by the analyst to assure
proper sample preparation and analysis. The principal procedures used are the
followi ng:
0 Instrument background counts
0 Blank and reagent analyses
0 Instrument calibration with known nuclides
0 Laboratory control standards analysis
0 Performance check-source analysis
0 Maintenance of control charts for background and check-source data
0 Scheduled instrument maintenance
These procedures ensure that the instrumentation is not contaminated, that
calibration is correct, and that standards carried through the total analytical
procedure are accurately analyzed.
VALIDATION
After the results are produced, supervisory personnel examine the data to
determine whether or not the analysis is valid. This includes checking all
procedures from sample receipt to analytical result with particular attention
to the internal QA data and comparison of the results
similar samples at the same location. Trend analysis
suggested a problem was occurring. Investigation led
new NBS standards were obtained, the old standard was
noble gas data from January 1984 on were then revised
included in this report.
with previous data from
of krypton-85 data
to the standard. Uhen
found to be faulty. All
the revised values are
Any variant result or failure to follow internal QA procedures during
sample analysis will trigger an internal audit of the analytical procedures
and/or a re-analysis of the sample or its duplicate.
12
-------
AUDITS
All analytical data are reviewed by personnel of the Dose Assessment
Branch for completeness and consistency. Investigations are conducted to
resolve any inconsistencies and corrective actions are taken if necessary.
SOP's and QA project plans are revised as needed following review of procedures
and methodology. The EMSL-LV QA Officer audits the operations periodically.
13
-------
SECTION 5
RADIOLOGICAL SAFETY ACTIVITIES
The radiological safety activities of the EMSL-LV are divided into two
major areas: special test support and routine environmental surveillance which
includes pathways monitoring and internal and external 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 following portions of this report.
SPECIAL TEST SUPPORT
Before each nuclear test, mobile monitoring personnel are positioned in
the off-site areas most likely to be affected should a release of radioactive
material occur. They ascertain the locations of residents, work crews and
animal herds and obtain information relative to controllability of residents
in communities and remote areas. These monitors, equipped with radiation
survey instruments, gamma exposure-rate recorders, thermoluminascent dosimeters
(TLD's), portable air samplers, and supplies for collecting environmental
samples, are prepared to conduct a monitoring program as directed from the NTS
Control Point (CP-1) via two-way radio communications.
For those tests which might cause ground motion detectable off site, EPA
monitors are stationed at locations where hazardous situations might ensue. 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 case accidental releases 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 radiation monitors.
During CY 1986, EMSL personnel were deployed in support of the 13 announced
underground tests, none of which accidently released radioactivity win en could
be detected off site. However, following the Mighty Oak event, conducted on
April 10, radioactivity was detected in the tunnel leading to the test point,
14
-------
although containment measures prevented escape of the radioactivity to the
atmosphere. To gain entry to the tunnel and the instrumentation contained
therein, the tunnel was purged and the escaping gas passed through high effi-
ciency and charcoal filters. Special air samplers were installed at near
off-site locations during the purging. The sampler at the Penoyer Farms near
Rachel, Nevada, detected the highest xenon-133 integrated concentration,
11.5 nCi-hr/m^. An individual who remained outdoors during the 170 hours of
the collection period would have received an exposure of 0.27 yrem (2.7 x
10~3 pSv) to the skin or equivalent to 1-1/2 minutes exposure to background
at that location. A complete description of the monitoring for this event is
reported separately (EPA86). Prior to this, a small amount of xe-133 was
detected in the weekly noble gas sample collected March 31 from Lathrop Wells.
This was apparently due to seepage from a drillback operation.
PATHWAYS MONITORING
The off-site radiation monitoring program includes a pathways monitoring
system consisting of air, water and milk surveillance networks surrounding the
NTS and a limited animal sampling project. These are explained in detail
below.
Air Surveillance Network (ASN)
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 corrective 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 2). The coverage is
constrained to those locations having available electrical power and 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 3).
Methods--
During 1986 the ASN consisted of 30 continuously operating sampling sta-
tions and 83 standby stations. The air sampler at each station was equipped to
collect both particulate radionuclides and reactive gases.
Samples of airborne particulates were collected at each active station on
5-cm diameter glass-fiber filters at a flow rate of about 81 m3 per day until
April, when the flow rate was increased to about 122 m^ per day. Filters were
changed after sampler operation periods of 2 or 3 days (160 to 360 m3).
Activated charcoal cartridges placed directly behind the filters to collect
gaseous radioiodine were changed at the same time as the filters. The standby
network was activated for 1 to 2 weeks per quarter at most locations and for
several weeks following the Chernobyl accident on April 26, 1986, near Kiev,
Ukrainian Republic, USSR. The standby samplers are identical to those used in
the ASN and are operated by State and municipal health department personnel or
by local residents. All air filters and charcoal cartridges were analyzed at
the EMSL-LV.
15
-------
Ely
\ I Pyramid Lake
4 Sunnyside
Stone Cabin Rn. B|ue Eag|e Rn
Tonopah
O\ Nyala
^Nv Goldfield
~~ i Twin Springs Rn.
TTR
Salt Lake City
Delta
i Milford
Pioche
I
Cedar City |
Scotty's Jet.
Beatty
\
Lathrop Wells*
>
Furnace Creek par)
Death Valley Jet.
R
-o_^
k
levada
Test
Site
l \r"
\
umpi
achel Hiko
Alamo
Groom
Lake
.Indian Qve
Springs ft i
I . J/La
1
St. George 1
Arizona
Jrton
ce Mead
Shoshone
Community Monitoring Stations (15)
Other Locations (15)
3/87
Figure 2. Air Surveillance Network stations (1986).
16
-------
North Dakota Minnesota
A A
Anzona New
Scale in Miles
100 300 500
100 300 500 700
Scale in Kilometers
A Stand-by ASN Station
3/87
Figure 3. Standby Air Surveillance Network stations (1986).
17
-------
Results--
During 1986, no airborne radioactivity related to nuclear testing at the
NTS was detected on any sample from the ASN. However, naturally occurring
beryl!ium-7 was detected by gamma spectroscopy, as were fission products from
the Chernobyl accident. Appendix Tables E-l and E-2, summarize the data from
the ASN samples.
In addition to beryllium-7, the radionuclides listed in the table below
were detected. The presence of these fresh fission products is attributed to
the Chernobyl nuclear reactor accident. Gamma-emitting radionuclides from
Chernobyl were also detected in most samples collected by the standby stations,
which were activated following the accident. Although these radionuclides were
not detected on all days of the quarter, each average concentration was cal-
culated using the total sampling time as the collection period and assuming
zero concentration for the periods when the nuclide was not detected. This is
a time-weighted average so it is possible for the average concentration to be
less than the minimum reported concentration (Tables E-l and E-2). A complete
report on the Chernobyl fallout and its significance is being prepared for
publication.
The fresh fission products from the Chernobyl accident were first observed
in air samples collected on May 7 from Denver, Colorado, and from Delta,
Milford, and Vernal, Utah. No fission products were detected in air samples
after June, 1986. The locations where the samples had the highest concentra-
tions of each radionuclide detected were as follows:
Radionuclide
Nb-95
Ru-103
Ru-106
1-131
Te-132
Cs-134
Cs-136
Cs-137
Ba-140
La-140
Ce-141
Collection
Date
May 15*
May 11
May 18
May 11
May 11
May 11
May 13
May 11
May 12
May 12*
May 15*
(pCi/m3)
0.11
1.0
0.24
8.9
0.45
0.55
0.081
1.5
0.26
1.8
0.058
Sampling Location
Wendover, UT
Reno, NV
Furnace Creek,
Reno, NV
Reno, NV
Nampa, ID
Ridgecrest, CA
Grand Junction,
Currie, NV
Bishop, CA
Wendover, UT
CA
CO
*Samples collected over 3-day period; all other samples are for 1-day sampling.
Two additional analyses are performed on selected samples from the ASN: a
gross beta analysis of the filters from 5 stations, and plutonium-238 and
plutonium-239 analysis of composited filters from 15 states. The gross beta
analysis is used to detect trends in atmospheric radioactivity because this
analysis is more sensitive than gamma spectrometry for detecting low levels of
radioactivity. For this study, three stations north and east of the NTS, and
18
-------
two stations south and west of the NTS are used. The three filters per week
from each station are analyzed for gross beta activity after a 7-day delay to
decrease the contribution from radon and thoron daughter activity- The data
suggest little significant difference among stations, but show the influence of
low level fission products from the Chernobyl accident which arrived in the U.S.
during the spring of 1986 (Figure 4). The maximum concentration measured was
1.1 pCi/m3, the minimum was <0.001 pCi/m3, and the arithmetic average was 0.025
pCi/m3 (0.9 mBq/m3). The maximum and average values were about 5 and 1.6 times
the values for 1985, respectively. A summary of the data is shown in Appendix
Table E-3. The results from the plutonium-239 analyses, all less than the MDC,
are shown in Appendix Table E-4; plutonium-238 results were also
-------
,^
CO
E
0
a
i
< 10'?
CO
+»
CO
M
M
0
5
io-3.
B
*
*.. * .""'*:.'
* *
.
1981 I 1982 | 1983 I 1984 | 1985 I 1 986 |
Figure 4. Monthly average gross beta in air samples, 1981-86.
for 1984 through 1986. The new values are 1 to 3 pCi/m3 lower than reported
previously. The master database has also been corrected. This network average
concentration, as shown in Table 2, gradually increased since sampling began
in 1972 until 1981. This increase, observed at all stations, reflects the
worldwide increase in ambient concentrations resulting from the increased use
of nuclear technology. The increase in ambient krypton-85 concentration was
projected by Bernhardt, et al., (Be73). However, the measured network average
in 1986 is only about 10 percent of the 250 pCi/m3 (9 Bq/m3) predicted by
Bernhardt. Since nuclear fuel reprocessing is the primary source of krypton-85,
the decision of the United States to defer fuel reprocessing may be one reason
why krypton-85 levels have not increased as fast as predicted. The average
concentrations have remained relatively constant since 1981.
Using published data for krypton-85 concentrations in air (NCRP75) and the
data from our network (Table 2), the change over time was plotted as shown in
Figure 7. Linear correlation analysis indicates that the krypton concentration/
time relation is pCi/m3 = 6.4 + 0.76 t where t is number of years after I960.
The correlation coefficient, R, is 0.98.
20
-------
3/87
Figure 5. Noble Gas and Tritium Surveillance Network sampling locations,
21
-------
TABLE 2. ANNUAL AVERAGE KRYPTON-85 CONCENTRATIONS
Sampling
Locations
Alamo, NV
Austin, NV
Beatty, NV
Diablo and
Rachel , NV**
Ely, NV
Gold-field, NV
Hiko, NV*
Indian Springs,
NV
NTS, Mercury, NV*
NTS, Groom Lake, NV*
NTS, BJY, NV*
NTS, Area 12, NV*
Tonopah, NV
Las Vegas, NV
Death Valley Jet. ,
CA*
NTS, Area 15, NV*
NTS, Area 400, NV*
Lathrop Wells, NV
Pahrump, NV
Overton, Nev.
Cedar City, Ut.
St. George, Ut.
Salt Lake City, Ut.*
Shoshone, CA
NETWORK AVERAGE
IN AIR, 1976-1986***
Kr-85 Concentrations (pCi/m^)
1976
-_
20
19
__
17
20
19
20
20
20
19
18
20
__
--
--
--
19
1977
20
19
--
19
20
20
19
21
19
19
20
20
__
__
--
20
1978
__
20
20
-_
20
20
20
20
22
20
20
20
20
__
--
--
20
1979
__
19
19
__
19
19
19
19
21
19
18
19
19
18
19
--
--
__
19
1980
--
21
21
--
21
21
21
21
23
21
21
21
21
22
__
--
21
1981
27
24
24
--
24
24
23
24
26
24
25
24
25
23
24
23
26
--
--
24
1982
24
24
25
26
24
25
26
24
__
--
24
24
__
24
24
24
25
24
25
25
24
1983
25
25
24
24
25
24
25
__
__
25
24
26
24
25
24
25
25
25
25
1984
24
23
23
22
22
24
22
--
23
23
__
22
23
23
22
23
25
23
23
1985
24
25
25
24
24
24
24
__
__
25
25
__
24
25
24
24
24
25
24
24
1986
24
25
26
25
26
25
26
__
--
25
25
--
25
25
25
24
24
25
25
*Stations discontinued
**Station at Diablo was moved to Rachel in March 1979.
***Note changes in 1984 and 1985 values due to new calibration, see text.
22
-------
70-
65-
60-
55-
50-
45-
40-
35-
The measurement of precision expressed as the coefficient of variation for 1 986 was i 1 5%
30-
20-
15-
10-
5
U----"-:f-^--3z^- = -^U-W:tJr^-^----
ra.Kj^kffl^01^^ L^ifi±tr:±fl=e^=y^fi±HfliJ
5 is'zsls 'VsVsIs 'l5 25|5 Vs'zsls ISZsIs 152s|5 152s|s 1 5 2s| 5 152s|s 1525|5 152s|5 15251
Jan 1 Fob | Mar | Apr | May | Jun | Jul | Aug | Sept | Oct | Nov | Dec
1986
Figure 6. Weekly average krypton-85 concentration in air, 1986 data.
30-
o
Q,
§ 20-
o 15'
u
c
o
O
10-
IT)
00
Least Squares: pCi/m^-6.4 +
R = 0.98
1960 1965 1970 1975 1980 1985 1990
Time - Calendar Years
Figure 7. Trend in annual average krypton-85 concentration.
23
-------
Detectable levels of xenon-133 were found on three occasions: following
a drill back on the NTS in March, following the Mighty Oak tunnel purging in
late April, and following the April accident at Chernobyl in the USSR. Table
E-12 lists when and where each sample was collected, the xenon-133 concentra-
tion for each sample, and the percent of the concentration guide.
As in the past, tritium concentrations in atmospheric moisture samples
from the off-NTS stations were generally below the minimum detectable concen-
tration (MDC) of about 400 pCi/L water (Appendix Table E-5). -The tritium
concentrations observed at off-NTS stations were considered to be represent-
ative of environmental background. The mean of the tritium concentrations for
all off-site stations was 0.45 pCi/m3 (17 m Bq/m3) of air. Only 11 of the 870
collected samples were above the MDC.
Long-Term Hydrological Monitoring Program
Network Design--
A major pathway for the transport of radionuclides to individuals is via
potable water. This program monitors possible radioactive contamination of
potable water sources. The design is for a system to monitor the aquifers
underlying, and surface waters on or near, sites where nuclear explosions have
occurred. For aquifers, monitoring is limited by the availability of wells
that tap those sources. For the sites considered herein, a suitable number of
wells is present so that representative monitoring data are obtained.
The monitored locations for the NTS and nearby off-site areas are shown in
Figures 8 and 9. For Projects Cannikin, Long Shot and Mil row in Alaska; for
Projects Rio Blanco and Rulison in Colorado; for Project Dribble in Mississippi;
for Projects Faultless and Shoal in Nevada; and for Projects Gasbuggy and Gnome
in New Mexico, the sampling locations are shown in Figures E-l through E-12 in
Appendix E.
Methods--
At each sampling location, four samples are collected. Two samples are
collected in 500-mL glass bottles; one is used for tritium analysis and the
other stored for use as a duplicate sample or to replace the original sample if
it is lost in analysis. The remaining two samples are collected in 3.5-L
cubitainers; one for gamma spectrometry analysis and the other is stored. This
procedure was modified for the locations around the NTS which had been sampled
semi-annually and annually. At these locations, the sampling frequency was
changed to monthly and the above sampling procedure was used only twice a year.
During the other months, only a 3.5-L sample was collected for analysis by
gamma spectrometry.
The tritium and gamma spectrometric analyses are described in Appendix B.
If the tritium concentration detected by the conventional analysis is less than
700 pCi/L (26 Bq/L) then the sample is reanalyzed using the enrichment method.
Results-
Table 3 lists the locations at which water samples were found to contain
man-made radioactivity. Radioactivity in samples collected at these locations
has been reported in previous years. The data for all samples analyzed are
24
-------
WellUE18rA
4 / Test Well D
Strip
WellC
AWellC-1
4CP-1A
Nuclear Rocket
Development Station
Figure 8, LTHMP sampling locations on the NTS.
25
-------
Twin Springs Rn.
Tonopah
Nyala
Adaven Springs
TTR Well #6
Nellis AFB
Range Complex
V
^
Spicer
Springdale
Goss Springs
Nevada
Test Site
Beatty
v
\
^
Ecology
1dd
Younghans Ranch (2)
Specie Springs
NRDS Mercury
1
T
I
A *'
\-l
0 Tempiute
Penoyer 0 Hiko
O Crystal Springs
Alamo
sAF#2
U
Lathrop Wells
v
v Fairbanks Springs
Well 17S/SOE-14CAC0
X 9 Crystal Pool
Well 18S/§1E-7db *Ash Meadows
Death Valley Jet
Calvada Well #1
Indian Springs
Sewer Co. Well #1
« * v
N
Scale in Miles
0 10 20 30 40
0 10 20 30 40 50 60
3/87 Scale in Kilometers
Nevada
,Shoshone
Spring
Nevada Test Site &
Nellis AFB Range Complex
Location Map
_ Las Vegas
9 Wei! #28
Lake Mead(
Intake
Figure 9. LTHMP sampling locations near the NTS.
26
-------
compiled in Appendix Tables E-6 and E-7 together with the percent of the
relevant concentration guide listed in Appendix D. Radiochemical analyses of
water samples from 5 new stations indicate only normal concentrations of
uranium and radium.
None of the radionuclide concentrations found at the locations listed in
Table 3 are expected to result in measurable radiation exposures to residents
in the areas where the samples were collected. Well UE7NS and Test Well B are
located on the NTS, and are not used as sources of domestic water.
USGS Wells 4 and 8, which were contaminated with the reported nuclides
during tracer studies years ago, are on private land at the Project Gnome site
in New Mexico and are closed and locked to prevent their use. Well LRL-7 was
used for the disposal of contaminated soil and salt so this well is expected to
produce contaminated water.
The Project Dribble wells in Mississippi are about 1 mile from the nearest
residence and are not sources of drinking water.
The shallow wells at the Project Long Shot site on Amchitka Island in
Alaska are in an isolated location and are not sources of drinking water.
Milk Surveillance Network (MSN)
Network Design
An important pathway for transport of radionuclides to humans is the air-
forage-cow-milk chain. This pathway is monitored by EMSL-LV through analysis
of milk. The design of the network is based on collections from areas likely
to be affected by-accidental releases from the NTS as well as from areas un-
likely to be so affected. Additional considerations are: 1) a complete ring
of stations to cover any NTS release, and 2) samples from major milksheds as
well as from family cows. The availability of milk cows or goats sometimes
restricts sample collection in certain areas.
Methods--
The network consists of two major portions, the MSN at locations within
300 km of the NTS from which samples are collected monthly (Figure 10) and the
standby network (SMSN) at locations in all major milksheds west of the Miss-
issippi River (Figure 11) from which samples are collected annually. One
exception to the latter portion of the network is Texas; the State Health
Department performs the surveillance of the milksheds in that State.
The monthly raw milk samples are collected by EPA monitors in 4-liter
plastic containers (cubitainers) and preserved with formaldehyde. The annual
milk samples are also collected in cubitainers and preserved with formaldehyde
but they are collected by contacting State Food and Drug Administration Repre-
sentatives, after notification of the Regional EPA offices, who arrange for the
samples to be mailed to EMSL-LV.
All the milk samples are analyzed first for gamma-emitting nuclides by
high-resolution gamma spectrometry and periodically for strontium-89 and
strontium-90 by the methods outlined in Appendix B, after a portion of milk
27
-------
TABLE 3. WATER SAMPLING LOCATIONS WHERE SAMPLES CONTAINED MAN-MADE
RADIOACTIVITY - 1986
Sampling Location
Type of
Radioactivity
Concentration
(pCi/L)
NTS,
Test Well B
Well UE7NS
PROJECT GNOME, NM
USGS Well 4
USGS Well 8
Well LRL-7
PROJECT DRIBBLE, MS
Well HMH-1 through 11
Well HM-S
Well HM-L
REECo Pit Drainage-B
Half Moon Creek Overflow
PROJECT LONG SHOT, AK
Hydrogen-3
Hydrogen-3
Hydrogen-3
Strontium-90
Hydrogen-3
Strontium-90
Cesium-137
Hydrogen-3
Strontium-90
Cesium-137
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Well EPA-1
Well WL-2
Well GZ, No. 1
Well GZ, No. 2
Mud Pit No. 1
Mud Pit No. 2
Mud Pit No. 3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
130-320
2300-3200
220,000
13,000
160,000
10
62
16,000
10
210
22-18,000
14,000
1,400-1,800
2,800
800-840
270
320
2,300
150
310-540
410
590-870
is set aside for tritium analysis. Occasionally a milk sample will sour, thus
preventing its passage through the ion exchange column and its subsequent
strontium analysis; however, the other analyses can generally be performed
satisfactorily. For the SMSN, two locations in each State are selected for
tritium and strontium analyses.
Results
The analytical results from the 1986 MSN samples are summarized in Appen-
dix Table E-8 where the maximum, minimum, and average concentrations of tritium,
28
-------
o
SL
3=
Wells
Winnemucca
»Elko
a
99
a
0!
Larsen Rn I
McGill
Reno
Austin
Young Rn.
Ely
Burdick Rn. I
Round Mtn. _
Berg Rn.
Warm Springs
Twin Spgs. Rn.l
Tonopah
Manzonie Rn
Currant
Penoyer
Farms
Harbecke Rn.
Shoshone
I Lund
McKenzie Dairy
B Blue Eagle Rn.
I Nyala
Sharp's Rn.
Rachel
Darrel Hansen
Hiko Rn. ,1
I June Cox
Caliente
Alamo
Whipple Rn.
Scale in Miles
50
100
50 100 150
Scale in Kilometers
Lathrop Wells
John Deer
NTS
Moapa 9
Indian S*pgs. Decade Corp
Rn.
Cedar City
Western
General Dairy
_St. George
'Gentry Dairy
Ridgecrest
| Cedarsage Farm
Milk Sampling Locations
NOTE: When sampling location occured
in city or town, the sampling location
symbol was used for showing both town
and sampling location
3/87
Mesquite
SF and K Dairy
Knudsen Corp
Logandale
LDS Dairy Farm
Barstow
Bill Nelson Dairy
Hinkley
Figure 10. Milk sampling locations within 300 km of the NTS.
29
-------
3/87
Figure 11. Standby milk surveillance network stations.
strontium-89 and strontium-90 are shown for each sampling location. As shown in
Table 4, the average concentrations of tritium and strontium-90 for the whole
network are similar to the network averages for previous years. The results
obtained from the standby network are listed in Table E-9.
Other than naturally occurring potassium-40, only Cs-137 was detected
(2 samples, standby network) by gamma spectrometry in milk samples (Table E-9).
No radionuclides from the Chernobyl accident were detected in milk from the
networks. A trace amount of iodine was detected in a special milk sample
from Las Vegas.
30
-------
TABLE 4. NETWORK ANNUAL AVERAGE CONCENTRATIONS OF
TRITIUM AND STRONTIUM-90 IN MILK, 1975-1986
Average Concentrations - pCi/L
Year H-3 Sr-90
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<3
<2
<2
1.2
<3
<2
1.9
1.2
0.8
0.5
0.7
0.6
The tritium and strontium-90 concentrations for the whole milk network
were plotted versus probits. The tendency of the data to fit one straight line
indicates that the data represent a single source, which appears to be atmos-
pheric deposition. These results are consistent with the results obtained for
the Pasteurized Milk Network, operated by the Eastern Environmental Radiation
Facility in Montogmery, Alabama, shown in Figure 12. The consistently higher
results from New Orleans reflect the higher rainfall in that area.
Biomonitoring Program
Objective
The pathways for transport of radionuclides to man include air, water, and
food. Monitoring of air, water, and mil-k are discussed above. Locally raised
meat is a food component that may be a potential route 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
northeast of the NTS. These samples are analyzed for gamma-emitters, tritium,
strontium, and plutonium. Each November and December, bone and kidney samples
from desert bighorn sheep collected throughout southern Nevada (see Figure 13)
are donated by licensed hunters and are analyzed. These kinds of samples have
been collected and analyzed for up to 29 years to determine long term trends.
During 1986, following the Mighty Oak test, four NTS mule deer were collected
and sampled in the same manner as the cattle.
Results--
Analytical data from bones and kidneys collected from desert bighorn sheep
31
-------
.2
«
CJCL
S
E
3 U
V)
A New Orleans
Salt Lake City
Las Vegas
1960
t965
1970
1975
1980
1985
Figure 12. Strontium-90 concentration in Pasteurized Milk Network samples.
during the late Fall of 1985 are presented in Table 5. Tritium and gamma-
emitting radionuclides, other than the naturally occurring potassium-40, were
not detected in any of the kidneys. Strontium-90 levels in the bones (average
3.2 pCi/g ash, 118 Bq/kg) are consistent with those reported in recent years
(Figure 14). Counting errors exceeded the reported concentrations of plutdnium-
238 in all but five samples of: bone ash. These five values ranged from 2.1 to
4.1 fCi per gram of bone ash. Plutonium-239 concentrations in the ash ranged
from -1.7 to 6.7 fCi/g, however, seven values exceeded the MDC and ranged from
1.9 to 6.7 fCi/g ash.
Eight beef cattle were sampled during 1986; four from the D. Agee ranch
collected in May$ and four from the Steve Medlin ranch collected in October.
Iodine-131 (ranging from 1.5 to 27 pCi/g) was detected in the thyroids of all
four beef animals sampled in May. The source of this iodine was thought to be
the worldwide fallout associated with the Chernobyl reactor accident. The
only other gamma-emitting radionuclides detected in soft tissue was naturally
occurring potassium-40. Tritium was not detected in any of the blood samples.
The cattle bone ash samples averaged 1.2 pCi of strontium-90 per gram of ash.
None of the samples contained plutonium-238 concentrations that exceeded the
counting errors and only two samples exceeded the counting error for plutonium-
239 (14 ± 7 fCi/g ash and 4 ± 3.9 fCi/g ash). The cattle liver samples did
not contain detectable concentrations of either plutonium-238 or -239; all
were less than 0.06 pCi/kg wet weight.
Following the Mighty Oak test (April 10) it was decided to collect mule
deer that drank the waters draining from the T-tunnel complex in Area 12 of the
NTS. Deer were collected on June 17, September 9 and October 29. A control
deer (No. 3) was collected. October 23, in Area 17, well away from the Area 12
32
-------
V/Q.C.Smt.
1 ^T^
1 - -im] *
|v&
NellisAFB Coyote Smt.
Range Complex >!
.xv I
/
1,2,4
NTS
{~^\ Hancock Smt^ \Alamo
v L_ 1 .
v t,t. l*i
v ^S.^
^ ^. LathropV^fgf
_ X. Wells l l
Furnace . x
Creek T\ S
*4
I i
. Desert
1 National,. 12
« Wildlife M ^>
-*- Range «"
>2
*5
*ro
h VI I Vxduius-' ^T^s. 'Wfu~> r7r\
N^ \ \SpHngsVX ^(?W
\ ^\^v \ Springs \ 715
V DeatK^V Jpahrump \^*C 3*1^
Valley JctA V^v %/ *V r?^^
\ \ /^N^v Ve9a.s\S^
Ridgecrest
-*_ J
Shoshone^v 16
N Af
1986
Mule
Deer
1985
Bighorn
Sheep
1986
Cattle
^V T
Searchlight
V \
Figure 13. Collection sites for bighorn sheep, deer and cattle samples.
33
-------
TABLE 5. RADIONUCLIDE CONCENTRATIONS IN DESERT BIGHORN SHEEP SAMPLES - 1985
Bighorn Sheep Bone
(Collected 90 Sr
Winter 1985) (pCi/g Ash)
1 3.1 ± 0.1
2 1.6 ± 0.1
3 2.0 ± 0.1
4___
5 1.9 ± 0.1
6 2.4 ± 0.1
7 2.1 ± 0.1
8 2.1 ± 0.1
9 6.2 ± 0.1
10 2.1 ± 0.2
11 1.5 ± 0.1
12 2.8 ± 0.1
13 5.7 ± 0.1
14 1.4 ± 0.1
15 9.6 ± 0.1
Bone
238 Pu
(fCi/g Ash)
3.7 ± 3.3
2.1 ± 2.1
2.5 ± 2.3
Ach ^\^mnl o 1 net1.
4.1 ± 5.4**
8.7 ± 17-**
3.1 ± 18.**
2.3 ± 2.4**
2.7 ± 14.**
-4.7 ± 16.**
-2.3 ± 2.5**
1.1 ± 1.3**
2.7 ± 16**
4.1 ± 3.0
1.3 ± 2.1**
Bone
239 Pu
(fCi/g Ash)
6.7 ± 0.4
4.2 ± 1.0
1.9 ± 1.9**
1.3 ± 2.7**
0.3 ± 0.8**
0.31 ± 0.9**
0.7 ± 2.0**
2.9 ± 2.4
0.5 ± 1.3**
0.3 ± 1.7**
2.3 ± 1.9
0 ± 1.6**
2.7 ± 2.2
0.3 ± 1.1**
Kidney
K(g/kg)*
3H(pCi/l)T
4.1 ± 0.8
NA
3.8 ± 0.5
NA
4.0 ± 0.4
NA
3 Q + n &
o . o x u . H-
120 ± 440**
4.0 ± 0.8
-100 ± 430**
2.2 ± 0.9
-100 ± 430**
4.9 ± 0.7
490 ± 430
4.1 ± 0.5
NA
2.7 ± 0.1
170 ± 440**
3.7 ± 0.4
150 ± 440**
2.5 ± 0.5
230 ± 440**
4.5 ± 0.7
290 ± 440**
2.2 ± 0.5
0 ± 440**
4.7 ± 0.7
-140 ± 440**
2.6 ± 0.9
150 ± 440**
(continued)
34
-------
TABLE 5. Continued
Bighorn Sheep
(Collected
Winter 1985)
16
17
18
19
20
Median
Range
Bone
90 Sr
(pCi/g Ash)
2
5
1
6
1
2
1
.0 ±
.5 ±
.0 ±
.3 ±
.6 ±
.1
.0 -
0.
0.
0.
0.
0.
9.
2
1
1
1
1
6
Bone
238
(fCi/g
3
-4
3
-4
1
2
-4
.8 ±
.9 ±
.6 ±
.9 ±
.7 ±
.1
.9 -
Pu
Ash)
2.7
11**
18**
12**
3.9**
8.7
Bone
239
(fCi/g
4.5 ±
4.7 ±
0 ±
0 ±
-1.7 ±
2.9
-1.7 -
Pu
Ash)
2.8
2.7
2.8**
0.9**
1.8*
6.7
Kidney
K(g/kg)*
3H(pCi/l)*
2.9
290
2.9
260
2.6
-59
3.2
210
4.9
360
3.7
160
2.2
-140
± 0.5
± 440**
± 0.6
± 440**
± 0.1
± 440**
± 0.5
± 440**
± 0.8
± 440**
- 4.9
- 490
* Wet weight
**Counting error exceeds reported activity
^Aqueous portion of Kidney Tissue
All concentrations are expressed with either the 2 sigma counting error or, for
results less than the value in error term field, ± the MDC.
tunnels. A wide variety of fresh fission products (1-131, Ru-103 and -106,
Zr-95, Sr-89, etc.) was detected in the tissue and ingesta samples from the
deer drinking from the T-tunnel ponds. The data are presented in Table 6.
Iodine-131 was still detectable in the thyroids of deer No. 4, sampled on
September 9, some 172 days post-detonation.
EXTERNAL EXPOSURE MONITORING
Thermoluminescent Dosimetry Network
External radiation exposure of people is due primarily to medical sources
and to natural sources such as cosmic radiation and naturally occurring radio-
activity in soil. Radioactivity from fallout generated by past atmospheric
nuclear testing causes approximately 0.6 percent of a person's total contempor-
ary exposure. Until 1965, film badges were used to document external exposure,
35
-------
TABLE 6. RADIONUCLIDE CONCENTRATION IN TISSUES FROM MULE DEER COLLECTED ON THE NEVADA TEST SITE - 1986
Tissue
Thyroid
Kidney
Liver
Lung
Muscle
^ Blood
Rumenb
Contents
Bone
Thyroid
Kidneyd
Muscle6
Liver
131-1
(pCi/g)
2.0xl06
±3.2xl02
110±0.4
80±0.3
90±0.5
16±0.2
90±0.4
110±4.7
5300±19
0.18±0.04
NO
0.4±0.04
103-Ru
(pCi/g)
9±0.09
2.6±0.05
0.5±0.05
0.4±0.03
0.1±0.02
8±0.3
ND
1.8±0.04
0.3±0.02
0.9±0.03
137-Cs 106-Ru H3 239 Pu 238 Pu 90 Sr 89 Sr
(pCi/g) (pCi/g) (PCi/l)a fCi/g/ash fCi/g/ash pCi/g/ash pCi/g/ash
-- Mi ilp nppr Nn 1 fnl 1 prtpH fi/1 7/ftfi
0.8±0.04 130+0.3 -l±4f l±4f
0.4±0.3
0.3±0.04 24±7 2.4±40f
0.2±0.03
0.05±0.01 150±0.3 6±2 0±330f
0.2±0.03 1.2±0.4 36±7 9±3
-0.2±0.2f -2±2f 2.8±0.1
Mill P Rppr Nn 9 Pnl 1 prfprl Q/Q/ftfi -
ND
0.09±0.02 0.9±0.1
0.2±0.02 0.2±0.08 100±0.2
0.05±0.003
(continued)
-------
TABLE 6. (Continued)
Tissue
131-1 103-Ru 137-Cs 106-Ru H3 239 Pu 238 Pu 90 Sr 89 Sr
(pCi/g) (pCi/g) (pCi/g) (pCi/g) (uCi/l)a fCi/g/ash fCi/g/ash pCi/g/ash pCi/g/ash
Lung
0.04±0.02 0.08±0.01 0.02±0.007
Rumen0
Contents 0.1±0.03 0.7±0.02 0.03±0.01 0.4±0.09 90±0.2 0.3±l.lf -l±15f
Bone
-2±1.5 0.3±llf 1±0.4
21±0.3
Mule Deer No. 3 Collected 10/23/86
Thyroid
w Kidney
Liver
Lung
Muscle
Blood
Gamma Spectrum Negligible
Gamma Spectrum Negligible
Gamma Spectrum Negligible
Gamma Spectrum Negligible
Gamma Spectrum Negligible
Gamma Spectrum Negligible
Rumen
Contents Gamma Spectrum Negligible
Bone
0.0009±0.00006
-4±1.8f
5.5±4 0.6±0.1 0.1±0.6f
(continued)
-------
TABLE 6. (Continued)
131-1 103-Ru 137-Cs 106-Ru H3 239 Pu 238 Pu 90 Sr 89 Sr
Tissue (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/l)a fCi/g/ash fCi/g/ash pCi/g/ash pCi/g/ash
_ Mule Deer No. 4 Collected 10/29/86
Thyroid 12±1
Kidney Gamma Spectrum Negligible
Muscle 0.1±0.06 0.1±0.03
Liver9 0.7±0.1 0.04+0.02 1.0±0.3
Lung 0.3±0.1 0.06±0.04
U)Rumen'1
03 Contents 0.06±0.007 0.7±0.03 <0.4
Blood 180±0.3
Bone 1.0±2.7d 4.4±4.1 1.2±0.4 16±1.8
aAqueous portion of tissue sampled.
bRumen Contents from Mule deer 1 also contained 9$lr (3.6 ± 0.1 pCi/g) and
(0.14 ± 0.03 pCi/g).
CRumen Contents from Mule deer 2 contained 22Na (0.03 ± 0.01).
dKidney from Mule deer 2 also contained 203Hg (0.09 ± 0.02 pCI/g) and 22Na (0.03 ± 0.02 pCi/g).
^Muscle from Mule deer 2 contained 203Hg 90.03 ± 0.01).
'Counting error exceeded reported activity.
Sliver from Mule deer 4 also contained 12^Sb (0.08 ± 0.04 pCI/g) and 125Sb (0.7 ± 0.07 pCi/g).
"Rumen Contents for Mule deer 4 also contained 124Sb (6 ± 0.2 pCi/g), 125Sb (0.6 ± 0.1 pCi/g)
and 95N (0<4 ± QA^
-------
Bighorn sheep
Deer
Numbers at top of columns indicate
the number of bone samples in each
category. Numbers prior to 1964
are unknown
56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86
Year(1956 -1986)
Figure 14. Average strontium-90 concentration in animal bone.
-------
but thermoluminascent dosimeters (TLD) gradually replaced film as the measure-
ment instrument because of their greater sensitivity and precision. From 1970
to 1974 the EMSL-LV used the TLD-12 dosimeter but changed to the TLD-200 in
1975. In 1987, a change will be made to use Panasonic TLD's instead of the
Harshaw model now used.
Network Design--
The TLD network is designed to measure environmental radiation exposure
at a location rather than to an individual because of the many uncertainties
associated with personnel monitoring. However, several individuals, some
residing within and some residing outside of estimated fallout zones from past
nuclear tests at the NTS, have been monitored so that any correlations that may
exist between personnel and environmental monitoring could be obtained. The
network consists of locations encircling the NTS with some concentration in the
area of the estimated fallout zones (Figure 15). This arrangement permits an
estimate of average background exposure; yet any increase due to NTS activities
can be detected.
Methods--
In 1986 the TLD Network consisted of 129 stations at both inhabited and
uninhabited locations within a 500-km radius of the CP-1. Each station was
equipped with three Harshaw TLD's to measure gamma exposures resulting from
environmental background as well as accidental releases of gamma-emitting
radioactivity. Within the area covered by the Network, 53 off-site residents
wore dosimeters during 1986. All environmental TLD's were exchanged quarterly,
and all personnel TLD's were exchanged monthly.
The Harshaw Model 2271-G2 (TLD-200) dosimeter consists of two small "chips"
of dysprosium-activated calcium fluoride mounted in a window of Teflon plastic
attached to a small aluminum card. An energy compensation shield of 1.2-mm
thick cadmium metal is placed over the card containing the chips, and the
shielded card is then sealed in an opaque plastic card holder. Three of these
dosimeters are placed in a secured, rugged, plastic housing one meter above
ground level at each station to standardize the exposure geometry. One dosim-
eter is issued to each of 53 off-site residents who are instructed in its
proper wearing.
After appropriate corrections were made for exposure accumulated during
shipment between the laboratory and the monitoring location, and for fading
and the response factor, the six TLD chip readings for each station were aver-
aged. The average value for each station was then compared to the values
obtained during the previous four quarters at that station to determine whether
the new value was statistically different from the previous values. The result
from each of the personnel dosimeters was compared to the average background
value measured at the nearest fixed station over the previous four quarters.
The smallest exposure above background radiation that can be determined
from these TLD readings depends primarily on the magnitude of variations in the
natural background exposure rate at the particular station. Typically, the
smallest net exposure detectable at the 99 percent confidence level for a
90-day exposure period would be 1 to 5 mR above background. Depending on
40
-------
Range ComplexTpN* kAlamo
Figure 15. Locations monitored with TLD's.
41
-------
location, the background ranges from 15 to 35 mR per quarter. The term "back-
ground," as used in this context, refers to naturally occurring radioactivity
and cosmic rays plus a contribution from residual manmade fission products,
such as worldwide fallout.
Results--
Appendix Table E-10 lists the maximum, minimum, and average dose equiva-
lent rate (mrem/day) and the annual adjusted dose equivalent rate (average in
mrem/day times the number of days in the year) measured at each station in the
Network during 1986. No allowance was made for the small additional exposure
due to the neutron component of the cosmic ray spectrum. No station exhibited
an exposure in excess of background during 1986.
Appendix Table E-ll lists the personnel number; associated background
station; the maximum, minimum, and average dose equivalent rate (mrem/d); and
the annual dose equivalent (mrem) measured for each off-site resident monitored
during 1986. Twelve dosimeters worn by residents exhibited exposures in excess
of background. These exposures are attributed to higher background levels in
the residence than at the background station location or to occupational ex-
posure (Nos. 45, 49, 57). Usually, the average dose equivalent rates of the
off-site residents is lower than their background stations due to the shielding
provided by their homes or places of work.
Table 7 shows that the average annual dose rate for the Dosimetry Network
is consistent with the Network average established in 1975. Annual doses
decreased from 1971 to 1975 with a leveling trend since 1975, except for a high
bias in the 1977 results attributed to mechanical readout problems. The trend
shown by the Network average is indicative of the trend exhibited by individual
stations, although this average is also affected by the mix of stations at
different altitudes (note Figure 16).
Because of the great range in the results, 40 to 135 mrem, an average for
the whole area monitored may be inappropriate for estimating individual exposure.
This would be particularly true if the exposure of a particular resident were
desired. Since environmental radiation exposure can vary markedly with both
altitude and the natural radioactivity in the soil, and since the altitude of
the TLD station location is relatively easy to obtain, the measured dose rates
for 1975 to 1986 were plotted as a function of altitude. As most of Nevada
lies between 2,000 and 6,000 feet above mean sea level, this range was split
into two sections for plotting purposes. The results, shown in Figure 16,
indicate that the average exposure at altitudes between 4,000 and 6,000 feet is
about 17 mrem/yr (0.17 mSv/yr) higher than that at altitudes between 2,000 and
4,000 feet, although both curves follow the same trend as the overall averages
listed in Table 7. Thus, if an individual does not live near a monitored
location, an estimate of exposure could be based on the altitude of his resi-
dence rather than on the average for the whole area monitored.
Pressurized Ion Chamber (PIC) Network
These gamma-ray ratemeters are located at the 15 Community Monitoring
Stations identified on Figure 2 plus stations at Complex I, Furnace Creek,
Nyala, Pioche, Stone Cabin Ranch, Tikaboo Valley, Twin Springs, and Lathrop
42
-------
Wells. The output of each PIC is displayed on both a paper tape and a digital
readout, so the station manager can observe the response. The data is also
stored on cassette tapes, which are read into a computer at EMSL-LV each week.
The computer output consists of tables containing hourly, daily, and weekly
summaries of the maximum, minimum, average, and standard deviation of the gamma
exposure rate.
The data for 1986 are displayed in Table 8 as the average yR/hr and annual
mR from each station. When these data are compared to the TLD results for the
same 23 stations, it is found that the PIC exposure is about 30% higher than
the TLD exposure. This is attributed, primarily, to the difference in energy
response of the two instruments. No increase in external gamma measurements
was found following the Chernobyl accident or the purging of the Mighty Oak
tunnel.
INTERNAL EXPOSURE MONITORING
Internal exposure is caused by ingested or inhaled radionuclides 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'bo'dy-burdens: whole-
body counting and urinalysis.
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 radio-
active materials which may have been inhaled or ingested. A single thallium-
activated sodium iodide crystal, 28 x 10 centimeters, is used to measure gamma
radiation having energies ranging from 0.1 to 2.5 MeV- Two phoswich detectors
are ava-iTable and can be placed on the chest to measure low-energy radiation -
for example, 17 KeV x-rays from plutonium-239. The most likely mode of intake
for most alpha-emitting radionuclides is inhalation, and the most important of
these radionuclides also emit low-energy x-rays which can be detected in the
lungs by the phoswich detectors. An additional phoswich detector is used to
determine low-energy radionuclide concentrations in bone, by moving the detec-
tor around the skul1.
To upgrade the facility, a single intrinsic coaxial detector has been
installed for use with an adjustable chair to achieve greater resolution and
lower background with greater patient comfort in whole-body counting. In
addition, two intrinsic planar detectors were installed in special holders
designed to allow them to be positioned in various attitudes to facilitate the
counting of areas other than the lungs and to allow additional detectors to be
mounted as they are obtained. The planars are specially designed for internal
dosimetry use and provide low background, high resolution analysis of low
energy gamma-emitting radionuclides. With the addition of specially designed
software, the ability to identify transuranic radionuclides will be greatly
increased.
A Micro-Vax-based gamma spectrometer was installed to process data from
both the old and the new detector systems. It facilitates manipulation of
data, gives greater storage capacity, and reliability of operation. The old
43
-------
TABLE 7. DOSIMETRY NETWORK SUMMARY FOR THE YEARS 1971 - 1986
Environmental Radiation Dose Rate (mrem/y)
Year Maximum Minimum Average
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
250
200
180
160
140
140
170
150
140
140
142
139
140
133
142
135
102
84
80
62
51
51
60
50
49
51
40
42
42
.35.
40
40
160
144
123
114
94
94
101
95
92
90
90
88
87
85
85
85
:=================
Station Altitude
4 - 6,000 ft.
75 76 77 78 79
80 81 82 83 84 85 86
Calendar Year 19--
Figure 16. Average annual TLD exposure as a function of station altitude,
44
-------
TABLE 8. PRESSURIZED ION CHAMBER READINGS - 1986
STATION LOCATION
ALAMO, NV
AUSTIN, NV
BEATTY, NV
CEDAR CITY, UT
COMPLEX 1, NV
ELY, NV
FURNACE CREEK, CA
GOLDFIELD, NV
INDIAN SPRINGS, NV
LAS VEGAS, NV (UNLV)
LATHROP WELLS, NV
NYALA, NV
OVERTON, NV
PAHRUMP, NV
PIOCHE, NV
RACHEL, NV
SALT LAKE CITY, UT
SHOSHONE, CA
ST. GEORGE, UT
STONE CABIN RNCH, NV
TIKABOO VALLEY, NV
TONOPAH, NV
TWIN SPRGS RANCH, NV
NO. OF
HOURLY
VALUES
8130
8174
8253
7146
7547
8072
7388
7721
8083
8072
7617
7383
8082
7596
7576
7723
7782
8017
8277
6471
7991
7882
5684
EXPOSURE RATE
MAX
16.61
27.42
24.23
14.51
22.33
17.27
16.20
21.16
14.66
10.51
17.92
17.74
11.82
13.99
17.83
20.53
23.24
14.71
11.98
20.98
22.46
22.40
22.42
MIN
12.39
15.40
10.80
9.82
15.60
11.85
9.20
15.20
8.39
6.06
13.28
12.30
8.00
7.36
12.12
16.08
7.63
10.87
7.86
15.88
15.30
16.65
15.83
, uR/H*
AVG + 1 SO
13.23 ± 0.36
19.97 ± 0.87
16.41 ± 1.05
10.63 ± 0.43
17.34 ± 0.58
12.57 ± 0.34
9.96 ± 0.44
15.93 ± 0.35
8.99 ± 0.27
6.44 ± 0.18
14.18 ± 0.27
13.07 ± 0.40
8.53 ± 0.33
7.81 ± 0.21
12.90 ± 0.34
17.13 ± 0.49
9.73 ± 2.86
11.67 ± 0.34
8.79 ± 0.46
17.74 ± 0.79
16.18 ± 0.30
17.63 ± 0.42
17.13 ± 0.56
MR/YR
116
175
144
93
151
110
87
140
78
56
124
114
75
68
113
150
85
102
77
155
142
154
150
*The MAX and MIN values are obtained from the instantaneous readings,
spectrometer is being retained until data accumulated in past years is con-
verted to the new format.
New quality assurance software obtained with the Micro Vax provides
statistical analysis and plots that in the past, required many tedious hours
to maintain. Dose calculation software provides organ specific analysis for
accurate internal monitoring. Software for internal dose calculation was
also obtained for use on a portable computer in the mobile counting van or
for other field use. This and two complete counting systems were readied for
deployment to areas affected by the Chernobyl accident.
Network Design
This activity consists of two portions, an Off-Site Human Surveillance
Program and a Radiological Safety Program. The design for the Off-Site Human
Surveillance Program is to measure radionuclide 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. A few families who reside in areas
not affected by such fallout were also selected for comparative study. The
45
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principal constraint to the program is the cooperation received from the people
in the area of study.
The Radiological Safety Program portion requires all employees who may be
exposed to radioactive materials in the course of their work to undergo a
periodic whole-body count. Some DOE contractor employees are also included in
this program.
Methods
The Off-Site Human Surveillance Program was initiated in December 1970 to
determine levels of radioactive nuclides 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 18 families added in recent years. The geographical locations of
the families which participated in 1986 are shown in Figure 17. Two additional
families were added to the program during 1986.
These persons travel to the EMSL-LV where a whole-body count of each
person is made to determine the body burden of gamma-emitting radionuclides. 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 urinalysis, 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 then be requested for use by
their family physician.
As reported in previous years, medical examination of the off-site fam-
ilies revealed a generally healthy population. In regard to the hematological
examinations and thyroid profiles, no abnormal results were observed which
could be attributed to past or present NTS testing operations.
In addition to the above off-site families, counts are performed routinely
on EPA and on contractor's employees as a part of the health monitoring pro-
grams. Counts on other individuals in the general population from Las Vegas
and other cities are used for comparison.
Results
During 1986, a total of 208 NaI(Tl)/Germanium, and 416 phoswich/planar
spectra were obtained from individuals, of whom 102 were participants on the
Off-Site Human Surveillance Program. Also, about 1,814 spectra for calibra-
tions and background were generated. Cesium-137 is generally the only fission
product detected. This year, following the Chernobyl accident, trace amounts
of cesium-137, and cobalt-60 were detected in a limited number of individuals,
mainly those contractor personnel flown in from California. Several ranchers
actively involved in farming also showed a trace of these radionuclides. Time
did not allow sufficient data to be collected to accurately quantitate the
amounts found. No fission products were detected from counts of individuals
46
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Ely
6
O Lund
° Nva'a Eagle Valley
o
O Adaven
Salt Lake City
.C
CO
Racl
&
Lathrop Wells
Elgin
O
Alamo
Tikaboo
Valley
BunkervilleO
Olndian
Springs
Cedar City
St. George
O Offsite Family
Community Monitoring Sta. Family
Arizona
,Overton
Lake Mead
3/87
Figure 17. Location of families in the Off-Site Human Surveillance Program.
47
-------
traveling or living in Europe during the Chernobyl accident when they were
counted some time after the incident. Prior to Chernobyl, the spectra were
representative of normal background for people and showed only naturally
occurring potassium-40. No transuranic nuclides were detected in any lung
counting data.
The concentration of tritium in urine samples from the off-site residents
varied from 0 to 3,200 pCi/L (118 Bq/L) with an average value of 158 pCi/L
(5.8 Bq/L). Nearly all the concentrations measured were in the range of
background levels measured in water and reflect only natural exposure. The
source for the high value (an Ely, Nevada resident) is unknown but is not
attributed to NTS activities. The tritium concentration in urines from EPA
employees had a range of 0 to 3,000 pCi/L (111 Bq/L) and an average of 316
pCi/L (11.7 Bq/L). Contractor personnel working at NTS showed tritium levels
above background but below maximum permissible body burdens.
COMMUNITY MONITORING STATIONS
In order to increase public knowledge about and participation in radio-
logical surveillance activities as conducted by DOE and EPA; the DOE, through
an Interagency Agreement with EPA and contracts with the Desert Research Insti-
tute (DRI) of the University of Nevada and the University of Utah, has estab-
lished a network of 15 Community Monitoring Stations in the off-NTS areas. Each
station is operated by a local resident, in most cases a science teacher, who
is trained in radiological surveillance methods by the University of Utah. The
stations are equipped and maintained, and samples are collected and analyzed by
EMSL-LV. DRI provides data interpretation to the communities involved and pays
the station operators for their services.
Each station 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.
All of the equipment is mounted on a stand at a convenient location in each
community so the residents are aware of the surveillance and, if interested,
can have ready access to the data. The station locations are those indicated
in Figure 2.
The data from these stations are included in the tables in Appendix E with
the other data from the appropriate networks. Table 8 contains a summary of
the PIC data.
CLAIMS 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 radio-
biology, investigates claims of radiation injury for domestic animals to
determine whether or not radiation exposure may be involved. In most cases
the injuries investigated have been due to common causes such as bacterial
48
-------
infections or unusual events such as feeding on halogeton, a poisonous plant.
No such claims were made in 1986.
PUBLIC INFORMATION PROGRAM
An important function of the Off-Site Program has been to create and main-
tain, to the extent possible, public confidence that all reasonable safeguards
are being employed to preserve public health and property from possible hazards
resulting from nuclear testing. Much of this responsibility is carried out
through personal contact with off-site residents by the radiation monitors who
advise the residents of program developments and answer questions about test
activities.
For any test where ground motion may be perceptible off site, monitors
visit remote locations and active mines beforehand to advise operators of pos-
sible problems. They also stand by on test day to advise of schedule changes.
Mine operators are reimbursed for time lost due to these activities. After the
test, monitors inform all their contacts that the test is over and whether or
not any radiation was detected off site. The community monitoring station
managers are informed by telephone of all announced test events and of their
completion.
In Jul-y-August 1986, the EMSL-LV participated with the DOE in a 1-week
refresher course for station managers arranged by the University of Utah and
the Desert Research Institute. No major changes in the program are antici-
pated.
The series of "town hall" meetings, initiated during Fiscal Year 1982 near
community monitoring stations was continued for CY 1986. The meetings were
organized to familiarize the local citizenry with the NTS nuclear testing and
related activities, to show how the surveillance networks function, and to
answer questions or expressed concerns of the attending public. During CY86,
meetings were held according to the following schedule:
Alamo, NV
Pioche, NV
Pahrump, NV
Dolan Springs,
Rachel, NV
Panguich, UT
Orderville, UT
AZ
January 21
January 22
January 23
March 23
May 14
June 11
June 12
Ely, NV
Lund, NV
Tonopah, NV
Beatty, NV
Indian Springs, NV
Mt. Charleston, NV
Venyo, UT
Santa Clara, UT
July 16
July 17
September 17
September 18
October 21
October 23
November 19
November 20
Personnel
listed below:
July 8, 1986
August 18, 1986
from the EMSL-LV addressed other citizen groups during CY86 as
Deer migration slides were shown to O.C.C. at NTS. Approx-
imately 30 people from various agencies attended.
A slide presentation of the communication aspects of
equipment used for the deer migration study was given
to
49
-------
the radio communication section in Mercury during their
monthly safety meeting.
August 19, 1986 Deer migration study slides were shown to personnel at
U.S. Ecology outside of Beatty, Nevada. A great deal of
interest had been generated because the manager had
killed a tagged deer from the NTS the previous fall.
Other activities included arranging NTS tours for businesses and community
leaders from Round Mountain, Rachel, Alamo, and Lincoln County- Nevada, and
from Kingman, Arizona.
With the continued population growth in the off-site area in recent years
and the continuing concern for keeping radiation exposures as low as reasonably
achievable, the EMSL-LV realized that it would need local government assistance
to implement all protective actions that could be needed to protect close-in
population centers should an underground nuclear test accidently vent. The
EMSL-LV staff discussed the kinds of assistance needed with the Nevada State
Division of Emergency Management, and obtained the State's concurrence with its
plan to work with County emergency management officials to develop modifica-
tions or additions to their adopted emergency response plans. These changes
would specify protective actions and procedures for implementing them and would
serve as formal agreements on Federal and local government responsibilities and
authorities.
During 1986, an Appendix to the Radiological Defense Annex of the Clark
County, Nevada and Inyo County, California emergency plans was prepared. The
County plans, with their new appendices, will be annexed to the master plan DOE
is developing for off-site emergency response for an accidental venting or
seepage at the Nevada Test Site. As part of these plans, 12,000 film badges
were distributed to 13 locations in Lincoln and Nye Counties with the objective
of providing personal dosimetry for at least one person per family or about
two-thirds of the total population in major population centers. Issue of
badges will be performed by county or state personnel in the unlikely event of
a significant release of radioactive material from the NTS. Film badge loca-
tions are being selected for Esmeralda and White Pine Counties (Nevada). It
is planned to replace the film badges with TLD's during FY 1987-
To improve it's services to communities in the environs of the Nevada Test
Site, to help dispel some of the misunderstanding concerning radiation, and to
provide students with some of the knowledge they need to participate in the
decision making processes, and to enable them to deal with the nuclear testing
and waste storage and disposal problems facing the citizens of Nevada, the NRD
staff developed a program of lectures and laboratory exercises for presentation
to students.
Beginning in mid-October, 1986, a NRD staff member began teaching basic
radiation concepts to students in high school biology, chemistry, physics and
general science classes. The instructor spends 4 or 5 days at each school.
During this time he presents lecture-demonstrations and conducts laboratory
exercises. Although the concepts presented at each school may differ somewhat
50
-------
due to teachers' requests and the grade-level of the students involved, the
lecturers deal with such topics as:
Introduction to Radiation ScienceAn Historical Perspective;
Radioactive Decay Processes;
Biological Effects of Ionizing Radiation;
Monitoring Radiation in the Environment, and
Nuclear Waste Problems.
Several laboratory exercises, designed to introduce students to radiation
measurement techniques are included during each school visit. The program was
approved by the school boards in both Lincoln and Nye counties, and has been
conducted at the schools listed below, the program will be continued at other
schools during 1987.
1. Pahrump High School, Pahrump, Nevada October 20-24
2. Gabbs High School, Gabbs, Nevada October 27-30
3. Lincoln County High School, Panaca, Nevada November 03-07
4. Pahranagat Valley High School, Alamo, Nevada December 01-05
DOSE ASSESSMENT
During calendar year 1986 there were five sources of possible radiation
exposure to the population of Nevada, all of which produced negligible exposure
possibilities and one of which was due to an accident in a foreign country. The
five sources were:
0 Normal seepage of radioactivity from the NTS,
0 Purging of radioactivity from the tunnel in which the Mighty Oak test
was conducted,
0 Radioactivity in migratory deer from drinking in contaminated ponds
on the NTS,
0 World-wide fallout of strontium in milk, of plutonium in cattle, and
krypton-85 in air, and
0 Airborne radioactivity from the reactor accident at Chernobyl, USSR.
The dose equivalent estimates from these sources for people living near
the Nevada Test Site are calculated separately in the following sections.
51
-------
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 1. Since no
significant activity of recent NTS origin was detectable off site by the air,
water, milk, TLD or biological monitoring networks, other than as described
for Mighty Oak, no significant exposure to the population around the NTS
would be expected. To confirm this, a simple atmospheric dispersion cal-
culation, using a gaussian plume model and cumulated meteorological data for
the NTS, was performed. The maximum individual dose equivalent was calculated
to be 1.4 urem (0.014 ySv) for the year, and the population dose equivalent to
the 6360 people living within 80 km of CP-1 was calculated to be 5.7 x 10~3
person-rem (5.7 x 10"^ person-Sv). When the Table 1 release quantities were
tested with the AIRDOS program, the maximum individual dose equivalent
became 2.4 yrem (0.024 ySv) and for the population 7.2 x 10~3 persom-rem
(7.2 x 10'5 person-Sv).
Estimated Dose from Tunnel Purging
The maximum integrated concentration of xenon-133 during the purging of
the tunnel following the Mighty Oak test was 11.5 nd-hr/m3 at the Penoyer
Farm near Rachel, Nevada. An individual who remained outdoors during the 170
hours of the collection period for the xenon-133 would have received an exposure
of 0.27 yrem (2.7 x 10'3 ySv).
Estimated Dose from World-wide Fallout
From the monitoring networks, the following concentrations of radionuclides
were found:
Pu-239 - <0.06 pCi/kg in beef liver
Sr-90 - 0.6 pCi/L (22 mBq/L) in milk
Kr-85 - 25 pCi/m3 (0.92 Bq/m3) in air
Tritium - 0.45 pCi/m3 (17 mBq/m3) in air
To estimate maximum individual dose equivalents from these findings,
the following assumptions (from ICRP-23) and dose conversion factors (from
ICRP-30) are used.
0 Adult breathing rate = 8400 m3/yr
0 Milk intake (10-year old) = 160 L/yr
0 Liver consumption = 1 Ib/wk = 23.6 kg/yr
0 Meat consumption = 248 g/day = 90.5 kg/yr
subtract liver consumption, balance is 66.9 kg/yr
0 Pu-239 - 2.1 x ID'6 Sv/Bq = 7.8 x 10~3 mrem/pCi
52
-------
0 Sr-90 - 1.9 x 1CT7 Sv/Bq = 7 x 1(T4 mrem/pCi
0 H-3 - 9.9 x 10'15 Sv/hr per Bq/m3 = 3.2 x 10'7 mrem/yr per pCi/m3
0 Kr-85 - 4.7 x 1CT11 Sv/hr per Bq/m3 = 1.5 x 1CT3 mrem/yr per pCi/m3
The dose equivalents can then be estimated by the following calculations:
Pu-239: (Assume concentration = detection limit)
0.06 pCi/kg x 23.6 kg/yr x 7.8 x 10'3 mrem/pCi = 0.011 mrem/yr
Sr-90: 0.6 pCi/L x 160 L/yr x 7 x 10~4 mrem/pCi = 0.067 mram/yr
Kr-85: 25 pCi/m3 x 1.5 x 10~3 = 0.038 mrem/yr
H-3: 0.45 pCi/m3 x 3.2 x 10'7 = 1.4 x 1Q-7 mrem/yr
These sum to 0.12 mrem/yr (1.2 ySv/yr) compared to the 0.0024 mrem (2.4 x
10'2 uSv) from NTS activities.
Radioactivity in NTS Deer
The tissues collected from the deer that had been drinking from the
T-tunnel drainage pond contained the radionuclides 1-131 and Cs-137 with the
concentrations listed in Table 6. To estimate an off-site exposure based on
those findings, some rather broad assumptions must ba used.
During the deer migration study at the NTS, it was estimated that 1500 to
2000 deer resided there. Because the herd migrated to lower altitudes after
the legal hunting season, few were collected by hunters. Of the deer that
were tagged (about 200 by EPA personnel) only 3 were shot by hunters over a
5-year period. This represents about 0.3% per year. Therefore, for the group
of 25 or so deer that use the T-tunnel drainage pond, less than one would be
collected by a hunter.
If one deer is collected, then a family of four persons would share the
3 Ib. of liver and 100 Ib. of meat for the year. Assuming the deer with the
highest concentration of iodine and cesium was collected, the dose equivalent
can be calculated. The dose conversion factors are:
1-131: 4.8 x 10'7 Sv/Bq = 1.8 x 10~6 rem/pCi to thyroid
Cs-137: 1.5 x lO"8 Sv/Bq = 5.6 x 10~8 rem/pCi to muscle
The intake would be 3 Ib. = 1.36 kg of liver and 100 Ib. = 45.3 kg of meat so
the dose to the thyroid would be 1.36 kg x 80 nCi/kg x 1.8 x 10"5 rem/pCi =
196 mrem plus 45.3 kg/365 days x 12 days (T-vq) x 16 nCi/kg x 1.8 x 10'5
rem/pCi = 43 mrem for a total of 240 mrem (thyroid) divided among four people.
The whole-body dose equivalent from Cs-137 would be (1.36 kg x 400 pCi/kg)
+ (45.3 kg x 200 pCi/kg) = 9600 pCi and 9600 pCi x 5.6 x lO'8 rem/pCi =
0.54 mrem. With the weighting factors recommended in ICRP-26, the effective
53
-------
dose equivalent would be 7.7 mrem if all was consumed by one person or only
1.9 mrem if shared equally among a family of four.
Estimated Dose from Chernobyl
Of the radionuclides detected by the ASN only 1-131 was in concentrations
high enough to warrent a dose calculation. Only 5 of the 113 air sampling
stations detected no radioiodine. Using the time-integrated concentrations of
1-131 at each station, an estimated dose equivalent for infants with a 2-gram
thyroid was calculated for each station location as shown in Table 9. With the
weighting factor recommended by the ICRP, the calculated effective dose equiv-
alents from Table 9 ranged from about 0.001 mrem to a maximum of slightly more
than 0.06 mrem.
Background Radiation
Background radiation in the off-site area is measured by two methods.
The TLD's (page 40) measure cumulative exposure, and the PIC's (page 45) meas-
ure exposure rate. Both measurement systems show a factor of 3 difference
(high vs. low) in dose equivalent depending on the location where the measure-
ment was made. In addition, at any location there can be variations of as
much as 1,5 to 2 jjrem/hr for 3 to 4 hours when atmospheric low-pressure
troughs move through the area. The low pressure allows more of the natural
radioactivity to diffuse from the soil to temporarily increase the background
radiation. This occurs 5 to 6 times per year at the PIC stations with an
excursion up to 2 yR/hr and a duration of 3 to 4 hours. Since the graph of
these excursions appears sinusoidal, the exposure delivered by these events
can be 5 to 6 urem each.
Therefore, to put the dose equivalents calculated for NTS activities,
world-wide fallout and Chernobyl into perspective, they may be compared to up
to 100 mrem/yr dose acquired merely by moving from one location to another or
to the 25 to 30 yrem/year added dose of one location due to meteorological
effects.
54
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TABLE 9. THYROID INHALATION DOSE EQUIVALENT, MAY AND JUNE 1986
STATION
GLOBE AZ
KINGMAN AZ
TUCSON AZ
WINSLOW AZ
YUMA AZ
LITTLE ROCK AR
ALTURAS CA
BAKER CA
BISHOP CA
CHI CO CA
DEATH VALLEY JCT CA
FURNACE CREEK CA
INDIO CA
LONE PINE CA
NEEDLES CA
RIDGECREST CA
SANTA ROSA CA
SHOSHONE CA
CORTEZ CO
DENVER CO
GRAND JUNCTION CO
MOUNTAIN HOME ID
NAMPA ID
INFANT THYROID DOSE
MREM**
0.31
0.35
0.34
0.25
0.14
0.0032
0.21
0.34
0.49
0.31
0.58
0.61
0.21
0.066
0.33
0.50
0.14
0.38
0.17
0.070
0.20
0.30
0.33
ADULT THYROID DOSE
MREM**
0.19
0.21
0.20
0.15
0.084
0.0019
0.12
0.20
0.29
0.18
0.34
0.36
0.13
0.039
0.20
0.30
0.085
0.23
0.10
0.042
0.12
0.18
0.20
(CONTINUED)
55
-------
TABLE 9. CONTINUED
STATION
POCATELLO ID
FORT DODGE IA
IOWA CITY IA
DODGE CITY KS
MINNEAPOLIS MN
JOPLIN MO
ST JOSEPH MO
GREAT FALLS MT
KALISPELL MT
MILES CITY MT
NORTH PLATTE NE
ALAMO NV
AUSTIN NV
BATTLE MOUNTAIN NV
BEATTY NV
CALIENTE NV
STONE CABIN RANCH NV
CURRANT NV - BLUE EAGLE RANCH
CURRANT NV - ANGLE WORM RANCH
CURRIE NV
DUCKWATER NV
ELKO NV
ELY NV
INFANT THYROID DOSE
MREM**
0.31
0.031
0.030
0.035
0.074
0.016
0.032
0.16
0.18
0.075
0.050
0.39
0.55
0.31
0.66
0.39
0.39
0.51
0.40
0.58
0.28
0.41
0.58
ADULT THYROID DOSE
MREM**
0.19
0.018
0.018
0.021
0.044
0.0096
0.019
0.094
0.11
0.044
0.030
0.23
0.32
0.18
0.39
0.23
0.23
0.30
0.24
0.35
0.17
0.24
0.34
(CONTINUED)
56
-------
TABLE 9. CONTINUED
INFANT
STATION
EUREKA NV
FALLON NV
FRENCHMAN STATION NV
GEYSER RANCH NV
GOLDFIELD NV
GROOM LAKE NV
HIKO NV
INDIAN SPRINGS NV
LAS VEGAS NV
LATHROP WELLS NV
LOVELOCK NV
LUND NV
MESQUITE NV
NYALA NV
OVERTON NV
PAHRUMP NV
PIOCHE NV
RENO NV
ROUND MOUNTAIN NV
SCOTTY'S JCT NV
SUNNYSIDE NV
RACHEL NV - ROBINSON TRAILER PARK
RACHEL NV - PENOYER FARM CRIS CASTLETON
THYROID DOSE
MREM**
0.37
0.36
0.57
0.27
0.80
0.67
0.32
0.53
0.54
0.50
0.43
0.44
0.24
0.16
0.40
0.60
0.41
0.60
0.69
0.69
0.36
0.37
0.012
ADULT THYROID DOSE
MREM**
0.22
0.21
0.34
0.16
0.48
0.40
0.19
0.31
0.32
0.30
0.25
0.26
0.14
0.097
0.24
0.36
0.25
0.36
0.41
0.41
0.22
0.22
0.0070
(CONTINUED)
57
-------
TABLE 9. CONTINUED
STATION
TONOPAH NV
TTR NV
FALLINI'S (TWIN SPGS) RANCH NV
WELLS NV
WINNEMUCCA NV
ALBUQUERQUE NM
CARLSBAD NM
SHIPROCK NM
BISMARK ND
FARGO ND
WILLISTON ND
MUSKOGEE OK
MEDFORD OR
BURNS OR
RAPID CITY SD
AMARILLO TX
MIDLAND TX
BRYCE CANYON UT
CEDAR CITY UT
DELTA UT
ENTERPRISE UT
GARRISON UT
LOGAN UT
INFANT THYROID DOSE
MREM**
0.73
0.66
0.55
0.46
0.30
0.062
0.17
0.20
0.13
0.15
0.12
0.0094
0.16
0.34
0.040
0.022
0.0093
0.23
0.24
0.29
0.28
0.22
0.19
ADULT THYROID DOSE
MREM**
0.44
0.40
0.33
0.28
0.18
0.037
0.10
0.12
0.077
0.088
0.074
0.0056
0.094
0.20
0.024 '
0.013
0.0055
0.14
0.14
0.17
0.17
0.13
0.11
(CONTINUED)
58
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TABLE 9. CONTINUED
STATION
MILFORD UT
PAROWAN UT
ST GEORGE UT
SALT LAKE CITY UT
VERNAL UT
WENDOVER UT
SEATTLE WA
SPOKANE WA
ROCK SPRINGS WY
NORLAND WY
INFANT THYROID DOSE
MREM**
0.31
0.16
0.30
0.32
0.17
Ocl3
0.061
0.20
0.27
0.17
ADULT THYROID DOSE
MREM**
0.18
0.098
0.18
0.19
0.10
0.075
0.036
0.12
0.16
0.10
*NO RADIOIODINE WAS DETECTED IN SAMPLES COLLECTED AT MONROE, LA, MINNEAPOLIS,
MM, ADAVEN, NV, MEDLIN RANCH, NV, AND TYLER, TX.
**CALCULATED FROM RADIOIODINE ON PARTICULATE FILTERS ONLY.
REFERENCE
ICRP-23 FOR BREATHING RATES.
ICRP-30 FOR DOSE CONVERSION FACTORS AND EFFECTIVE ENERGY PER DISINTEGRATION.
BNWL-1754, FEBRUARY, 1974. FOR EFFECTIVE ENERGY PER DISINTEGRATION FOR
2-YEAR-OLD.
59
-------
SECTION 6
REFERENCES
ANSI75 American National Standards Institute, Inc., 1975, "American National
Standard Performance Testing and Procedural Specifications for Thermolumi-
nescent Dosimetry (Environmental Applications)." ANSI N545-1975.
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.
B184 Black, S. C. and D. D. Smith, 1984, "Nevada Test Site Experimental
Farm Summary Report 1963-1981". EPA 600/4-84-066, DOE/DP/0539-052. U.S.
Environmental Protection Agency, Environmental Monitoring Systems Labor-
atory, Las Vegas, Nevada.
CA85 California, 1985, Personal communication from California county agents.
DOE85a U.S. Department of Energys 1985, Amendment to DOE Order 5480.1A, Radia-
tion Standards for Protection of the Public in the Vicinity of DOE
Facilities.
DOE85 U.S. Department of Energy, 1985, Environmental Protection, Safety, and
Health Protection Information Reporting Requirements. Order DOE 5484.1.
DOE87 U.S. Department of Energy, 1987, Personal communication from Health Physics
Division, DOE/NV, Las Vegas, NV.
EPA81 U.S. Environmental Protection Agency, 1981, "Environmental Radioactivity
Laboratory Intercomparison Studies Program 1978-1979." EPA-600/4-81-004.
Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
(Available from U.S. Department of Commerce, NTIS, Springfield, VA 22161.)
EPA86 U.S. Environmental Protection Agency, 1986, "Off-Site Monitoring for the
Mighty Oak Nuclear Test." EPA 600/4-86-030. Environmental Monitoring
Systems Laboratory, Las Vegas, Nevada. (Available from the U.S. Environ-
mental Protection Agency.)
ERDA77 U.S. Energy Research and Development Administration, 1977, "Final Environ-
mental 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.)
60
-------
6179 Giles, K. R., 1979, "A Summer Trapping Method for Mule Deer." EMSL-LV-0539-27-
U.S. Environmental Protection Agency, Environmental Monitoring and Support
Laboratory, Las Vegas, Nevada.
Gi85 Giles, K. R. and J. Cooper, 1985, "Characteristics and Migration Patterns of
Mule Deer on the Nevada Test Site," U.S. Environmental Protection Agency,
Environmental Monitoring Systems Laboratory Report EPA-60/4-85-030 (DOE/OP/
00539-054).
Ho75 Houghton, J. G., C. M. Sakamoto, and R. 0. Gifford, 1975, "Nevada's Weather
and Climate." Special Publication 2. Nevada Bureau of Mines and Geology,
Mackay School of Mines, University of Nevada, Reno, Nevada, pp. 69-74.
ICRP75 International Commission in Radiological Protection, 1975, Report of the
Task Group on Reference Man, Report ICRP-23.
ICRP77 International Commission in Radiological Protection, 1977, Recommendations
of the ICRP, Report ICRP-26.
ICRP79 International Commission in Radiological Protection, 1979, Radionuclide
Releases to the Environment: Assessment of Dose to Man, Report ICRP-24.
ICRP79 International Commission in Radiological Protection, 1979, Limits for
Intake of Radionuclides by Workers, Report ICRP-30, 3 parts.
Ja81 Jarvis, A. N. and L. Siu, 1981, Environmental Radioactivity Laboratory
Intercomparison Studies Program - FY 1981-82, EPA-600/4-81-004, U.S. EPA,
Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
NPS80 National Park Service, 1980, Personal Communication with Chief Ranger R.
Rainer, Death Valley National Monument, Death Valley, California.
NCRP71 National Council on Radiation Protection and Measurements, 1971, Basic
Radiation Protection Criteria. NCRP Report No. 39.
NCRP75 National Council on Radiation Protection and Measurements, 1975, Natural
Background Radiation in the United States. NCRP Report No. 45.
NV86 Nevada Department of Agriculture, 1986, "Nevada Agricultural Statistics 1985."
Nevada Crop and Livestock Reporting Service, Reno, Nevada.
Pi82 Patzer, R. G. and M. E. Kaye, 1982, "Results of a Human Surveillance
Program in the Off-site Area Surrounding the Nevada Test Site." Health
Phys. 43:791-801.
Qu68 Quiring, R. E., 1968, "Climatological Data, Nevada Test Site, Nuclear Rocket
Development Station (NRDS)." ERLTM-ARL-7. ESSA Research Laboratories,
Las Vegas, Nevada.
61
-------
Sm81 Smith, D. D. and V. E. Andrews, 1981, Selected Radioisotopes in Animal
Tissues: 90Sr and 137Cs Measurements from 1956 to 1977. U.S. Environmental
Protection Agency Report EPA-600/3-81-027 (DOE/DP/00539-040). Las Vegas,
Nevada.
Sm84 Smith, D. D. and S. C. Black, 1984, Animal Investigation Program for the
Nevada Test Site 1957-1981, U.S. Environmental Protection Agency,
Environmental Monitoring Systems Laboratory Report EPA 600/6-84-020,
Las Vegas, Nevada.
UT82 Utah Department of Agriculture, 1982, "Utah Agricultural Statistics, 1982."
State of Utah Department of Agriculture, Salt Lake City, Utah.
Wi75 Winograd, I. J. and W. Thordarson, 1975, Hydrogeologic and hydrochemical
framework, south-central Great Basin, Nevada-California, with special
reference to the Nevada Test Site, USGS Professional Paper 712-C, Denver,
Colorado.
62
-------
APPENDIX A
SITE DATA
SITE DESCRIPTION
A summary of the uses of the NTS and its immediate environs is included
in Section 3 of this report. More detailed data and descriptive maps are
contained in this Appendix.
Location
The NTS is located in Nye County, Nevada, with its southeast corner about
90 km northwest of Las Vegas (Figure 1 in main report). 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 Range, 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 air-
borne radioactivity could pass over public lands.
Climate
The Climate of the NTS and surrounding area is variable, due to its varia-
tions 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. (Ho75), this method of classification of
dry condition, developed by Doppen, is further subdivided on the basis of
temperature and severity of drought. Table A-l (Ho75) summarizes the charac-
teristics 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 eleva-
tions. 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
daily high (low) temperatures at the lower altitudes are around 50°F (25°F) in
A-l
-------
TABLE A-l. CHARACTERISTICS OF CLIMATIC TYPES IN NEVADA
(from Houghton et al. 1975)
Climate Type
Mean Temperature
Winter
Summer
Annual
Precipitation
cm Percent
(inches) Dominant of
Total* Snowfall Vegetation Area
Alpine -18° to -9° 4° to 10° 38 to 114 Medium
tundra ( 0° to 15°) (40° to 50°) (15 to 45) to
heavy
Humid -12° to -1° 10° to 21° 64 to 114 Heavy
continental (10° to 30°) (50° to 70°) (25 to 45)
Alpine
meadows
Pine-fir
forest
Subhumid -12° to -1° 10° to 21° 30 to 64 Moder-
continental (10° to 30°) (50° to 70°) (12 to 25) ate
Mid-latitude -7° to 4° 18° to 27° 15 to 38 Light
steppe (20° to 40°) (65° to 80°) ( 6 to 15) to
moderate
Mid-latitude -7° to 4° 18° to 27° 8 to 20 Light
desert (20° to 40°) (65° to 80°) ( 3 to 8)
Low-latitude -4° to 10° 27° to 32° 5 to 25 Neglig-
desert (40° to 50°) (80° to 90°) ( 2 to 10) ible
Pine or
scrub
woodland
Sagebrush,
grass,
scrub
Grease-
wood,
shadscale
Creosote
bush
15
57
20
*Limits of annual precipitation overlap because of variations in temperature
'which affect the water balance.
January and 95°F (55°F) in July, with extremes of 120°F and -15°F. Correspond-
ing temperatures on the plateaus are 35°F (25°F) in January and 80°F (65°F) in
July with extremes of 115°F and -30°F-
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.
A-2
-------
Geology and Hydrology
Two major hydro!ogic systems shown in Figure A-l 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 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 A-2 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 agricul-
tural 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 A-2) 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 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.
A-3
-------
Pahute Mesa
Ground Water
System
Ash Meadows
Ground Water System
Indian Springs
10 20 30 40
Scale in Kilometers
» » Flow Direction
^ Ground Water System Boundaries
__<.«__ Silent Canyon Caldera
Timber Mountain Caldera
Figure A-l. Ground-water flow systems around the Nevada Test Site.
A-4
-------
DAIRIES
A
FARMS \-^s
Haiwee Res / O\O
FARMS
,0
Moiave Desert
0 50 100 150
3/87 Scale in Kilometers
A Camping & Recreational
Areas
D Hunting
Fishing
OMines
A Oil Fields
JA
Lake Havasu
Figure A-2. General land use within 300 km of the Nevada Test Site.
A-5
-------
Population Distribution
Figure A-3 shows the current population of counties surrounding the NTS
based on 1980 census figures. Excluding Clark County, the major population
center (approximately 536,000 in 1984), 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 the NTS (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 5,500, is located about 72 km south of the NTS CP-1. The Amargosa
Farm Area, which has a population of about 1S200, is located about 50 km south-
west of CP-1. The largest town in the near-offsite area is Beatty, which has a
population of about 900 and is located approximately 65 km to the west of CP-1.
A report by Smith and Coogan was published in 1984 which summarizes the popula-
tion 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 hol-
iday 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 1983 population of about 36,000. 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 5,300 including contiguous populated
areas.
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 11,300. The next largest town, Cedar City, with
a population of 10,900, 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 com-
munities lie along the Colorado River. The largest town in the area is Kingman,
located 280 km southeast of the NTS, with a population of about 9,300. Figures
A-4 through A-7 show the domestic animal populations in the counties near the
NTS.
A-6
-------
Storey
1,800
Humboldt
10,900
Pershing
3,600
WashoeT
211,500'
Lander
4,400
Carson
City
35,400
Douglas
21,000
Elko
20,300
Box. Elder
36,900
CD C
< I £ Tooele
Q.
03
Eureka
1,300
White Pine
28,700
8,200-
^x.
Millard
12,800
r
Beaver ^*
5,100
I
19,800
Washington
33,100
Nellis AFB
Range Complex
San Bernardino
1,033,700
0 50 100 150
Scale in Kilometers
Juab
6,100
Figure A-3. Population of Arizona, California, Nevada, and Utah
Counties near the Nevada Test Site (1985).
A-7
-------
Nellis AFB
Range Complex
San Bernardino
21(297)
50 100 150
Scale in Kilometers
XX Cows
(XX) Goats
Figure A-4. Distribution of fanrrily milk cows and goats, by county (1986),
A-8
-------
Nellis AFB
Range Complex
50 100 150
Scale in Kilometers
Figure A-5. Distribution of dairy cows, by county (1986).
A-9
-------
Storey-
100
Carson
City
1,200
Nellis AFB
Range Complex
0 50 100 150
3/87Scale m Kilometers
Figure A-6. Distribution of beef cattle, by county (1986).
A-10
-------
Nellis AFB
Range Complex
San Bernardino
12,100
50 100 150
Scale m Kilometers
Figure A-7. Distribution of sheep, by county (1986).
A-ll
-------
APPENDIX B
SAMPLE ANALYSIS PROCEDURES
ANALYTICAL PROCEDURES
The procedures for analyzing samples collected for offsite surveillance are
described by Johns et al. in "Radiochemical Analytical Procedures for Analyses
of Environmental Samples" (EMSL-LV-0539-17, 1979) and are summarized in Table
B-l.
TABLE B-l. SUMMARY OF ANALYTICAL PROCEDURES
Type of
Analysis
IG Ge(L1)
Gamna
Spec
tpometry**
Analytical
Equipment
IG or Ge(Li)
detector cali-
brated at 0.5 keV/
channel (0.04
to 2 MeV range)
Individual detec-
tor efficiencies
ranging from
15S to 351.
Counting
Period
(min)
Air charcoal
cartridges
and individual
air filters,
30 min; air
filter com-
posites, 1200
min. 100 nin
for milk.
water, sus-
pended solids.
Analytical
Procedures
Radionucl ide
concentration
quantified
from gamma
spectral data
by on-1 ine
computer pro-
gram. Radio-
nucl ides in air
filter composite
samples are
identified only.
Sample
Size
120-370 m3
for air
filters;
and char-
coal car-
tridges;
3-1/2
liters for
milk and
water.
Approximate
Detection
Limit*
For routine milk
and water general ly ,
5 pCI/L for most
cannon fallout
radionuclides 1n a
simple spectrum.
Filters for LTHMP
suspended solids,
6 pCi/L. Air
filters and char-
coal cartridges,
0.04 pd/m3.
Gross beta
on air
filters
Low-level end
window, gas
flow proportional
counter with a
12.7 cm diameter
window (80 w9/cm2)
30
Samples are
counted after
decay of
naturally-
occuring
radionuclides
and, 1f neces-
sary, extrapo-
lated to mid-
point of col-
lection in
accordance with
t.-1.2 decay or
an experiment-
ally-derived
decay.
120-370 m3 0.5 pCI/sample.
(continued)
B-l
-------
TABLE B-l. (Continued)
Type of Analytical
Analysis Equipment
Sr-89-90 tow-bade ground
thin-window.
gas-flow pro-
portional
counter.
Counting
Period Analytical
(mln) Procedures
50 Chemical separa-
tion by 1on ex-
change. Separated
sample counted
successively; ac-
tivity calculated
by simultaneous
solution of equa-
tions.
Approximate
Sample Detection
Size Limit*
1.0 liter Sr-89 5 pCIA,
for milk Sr-90 « 2 pCI/L.
or water.
0.1-1 kg
for tissue.
H-3
H-3
Enrichment
(Leng-Term
Hydro-
logical
Samples)
Pu-238,239
Automatic
liquid
scintillation
counter with
output printer.
Automatic
scintillation
counter with
output printer.
Alpha spectro-
neter with 450
mm, 300-um
depletion depth,
silicon surface
barrier detectors
operated In
vacuum chambers.
200
200
1000-1400
Sample pre-
pared by
distillation.
Sample concen-
trated by
electrolysis
followed by
distillation.
Water sample or
acid-digested
filter or tissue
samples separated
by ion exchange,
electro-plated on
stainless steel
planchet.
4 ml
for water
2SO ml
fer water
1.0 liter
for water;
0.1-1 kg
for tissue;
s.ooo-
10,000 m3
for air.
400 pCI/L.
10 pCI/l.
Pu-238 0.08 pCI/L
Pu-239 0.04 pCI/L
for water. For
tissue samples,
0.04 pCi per total
sample for all
Isotopes; 5-10 aCi/m3
for plutonium on air
filters.
Kr-85,
Xe-133,
Xe-135
Automatic 200
liquid scintil-
lation counter
with output
printer.
Separation by
gas chromatogra-
phy. dl solved in
toluene "cocktail"
for counting
0.4-1.0 m-
for air
5 Kr-85. Xe-133,
4 PC1/m3.
Xe-135
The detection limit is defined as 3.29 sigma where sigms equals the counting error of the sample
and Type 1 error « Type II error 5 percent. (J. P. Corley, 0. H. Denham, R. E. Jaquish, 0. E~
Hichels, A. R. Olsen, 0. 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, 0. C.)
**Gamma Spectrometry using either an intrinsic germanium (16), or lithium-drifted germanium diode
(Ge(LD) detector.
B-2
-------
APPENDIX C
QUALITY ASSURANCE PROCEDURES
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 by the EMSL-LV.
The program consists of the analysis of duplicate or replicate samples
from the ASN, the N6TSN, the LTHMP, and the Dosimetry Network. As the radio-
activity concentration in samples collected from the LTHMP and the MSN are
below detection levels, most duplicate samples for these networks are prepared
from spiked solutions. The NGTSN samples are generally split for analysis.
At least 30 duplicate samples from each network are normally collected and
analyzed over the report period. Since three TLD cards consisting of two TLD
chips each are used at each station of the Dosimetry Network, no additional
samples were necessary. Table C-l summarizes the sampling information for each
surveillance network.
To estimate the precision of a methodology, the standard deviation of
replicate results is needed. Thus, for example, the variance, $2, of each set
of replicate TLD results (n=6) was estimated from the results by the standard
expression,
s2 = s (xi - x)2/ (k - 1)
where k = number of sets of replicates.
Since duplicate samples were collected for all other sample types, the
variances, sS for these types were calculated from s^ = (0.886R)S where R is
the absolute difference between the duplicate sample results. For small sample
sizes, this estimate of the variance is statistically efficient* and certainly
more convenient to calculate than the standard expression. The standard devia-
tion is obtained by taking the square root.
*Snedecor, G. W., and W. G. Cochran. Statistical Methods. The Iowa State
University Press, Ames, Iowa, 6th Ed. 1967, pp. 39-47-
C-l
-------
TABLE C-l. SAMPLES AND ANALYSES FOR DUPLICATE SAMPLING PROGRAM - 1986
Survei 1 lance
Network
ASN
NGTSN
Dosimetry
MSN
LTHMP
Sets of
Number of Samples Duplicate
Sampling Collected Samples Number
Locations This Year Collected Per Set
113 6,791
17 880 (NG)
870 (H3)
146 604
26 260
196 342
159 2
107 2
97
604 4-6
42 2
149 2
Sample
Analysis
Gross beta,
Y Spectrometry
Kr-85, H-3,
H20, HTO
Effective dose
from gamma
K-40, Sr-89,
Sr-90, H-3
H-3
The principle that the variances of random samples collected from a normal
population follow a chi-square distribution (x2) was then used to estimate the
expected population standard deviation for each type of sample analysis. The
expression used is as follows:*
s =
1)
1/2
where
j-1 = the degrees of freedom for n samples collected for the ith
replicate sample
2
s-j = the expected variance of the ith replicate sample
s = the best estimate of sample standard deviation derived from the
variance estimates of all replicate samples (the expected value
of s2 is a2)*
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 C-2 for those analyses for which there were adequate data.
To estimate the precision of counting, approximately 10 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 preci-
sion data in Table C-2 represents errors principally in analysis.
*Freund, J. E. Mathematical Statistics. Prentice Hall, Englewood, New Jersey,
1962, pp 189-235.
C-2
-------
TABLE C-2. SAMPLING AND ANALYTICAL PRECISION - 1986
Surveillance
Network
ASN
NGTSN
Dosimetry
Analysis
Gross 8
Ru-103
1-131
Cs-137
Kr-85
HTO
H20
TLD
Sets of
Replicate
Samples
Evaluated
Coefficient
of Variation
28
29
8
19
50
*
53
387
32
27
57
29
15
50
49
6.0
MSN
LTHMP
K-40
Sr-89 (1985)
Sr-90
H-3
H-3+
31
33
22
35
51
11
17
15
11
80
*E'stimate of precision was calculated from the errors in the H-3 conventional
analysis and the measurement of atmospheric moisture
ACCURACY OF ANALYSIS
Data from the analysis of intercomparison samples are statistically anal-
yzed and compared to known values and values obtained from other participating
laboratories. A summary of the statistical analysis is given in Table C-3,
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 separately (Ja81). If the value of this parameter (in multiples of
standard normal deviate, unitless) lies between control limits of -3 and +3,
the precision or accuracy of the analysis is within normal statistical varia-
tion. However, if the parameters exceed these limits, one must suspect that
there is some cause other than normal statistical variations that contributed
to the difference between the measured values and the known value. As shown by
this table, all of the analyses were within the control limit.
The analytical methods were further checked on by Laboratory participation
in the semiannual Department of Energy Quality Assessment Program conducted by
the Environmental Measurements Laboratory, New York, N.Y. The results from
these tests (Table C-4) indicate that this Laboratory's results were of accept-
able qual ity.
C-3
-------
TABLE C-3. EPA QUALITY ASSURANCE INTERCOMPARISON RESULTS - 1986
Analysis
H-3
in water
H-3
in urine
Pu-239
in water
Sr-90
in milk
Sr-89
in milk
1-131
in milk
1-131
in water
Cs-137
in milk
Cr-51
in water
Co-60
in water
Zn-65
in water
Ru-106
in water
Cs-134
in water
Cs-137
in water
Month
February
June
October
April
November
January
August
June
October
June
October
February
June
October
April
August
June
October
June
October
June
October
June
October
June
October
June
October
June
October
Mean of
Replicate
Analyses
(pCi/L)
5077
2837
5775
4538
5295
6.5
9.4
14.3
<2
<5
9
9.8
45.0
52.3
10.0
44.0
36.0
44.0
0.0
57.7
65.0
32.0
81.3
87.3
50.3
71.7
44.0
27.7
11.0
45.3
Known Value
(pCi/L)
5227
3125
5973
4423
5257
7.1
10.1
16
0
0
9
9.0
41.0
49.0
9.0
45.0
31.0
39.0
0.0
59.0
66.0
31.0
86.0
85.0
50.0
74.0
49.0
28.0
10.0
44.0
Normalized
Deviation from
Known Concentration
-0.4
-1.3
-0.5
0.4
0.1
-1.3
-1.1
-1.9
N/A
N/A
0.0
0.2
1.1
0.9
1.9
-0.2
1.7
1.7
0.0
-0.5
-0.3
0.3
-1.6
0.8
0.1
0.8
-1.7
-0.1
0.3
0.5
C-4
-------
TABLE C-4. QUALITY ASSURANCE RESULTS FROM DOE PROGRAM - 1986
Analysis
K-40
in soil
Cs-137
in soil
Pu-239
in soil
K-40
in tissue
K-40
in vegetation
Cs-137
in vegetation
Pu-239
in vegetation
H-3
in water
Mn-54
in water
Co-60
in water
Sr-90
in water
Cs-137
in water
Pu-239
in water
Month
June
June
June
June
June
June
June
June
June
June
June
June
June
EMSL-LV
Results
27.1
1.02
.0111
1.99
11.4
1.71
.0219
21.5
2.35
2.32
.312
2.44
.0559
EML
Results
20.4
.810
.0100
2.10
9.80
1.39
.0170
21.8
2.30
2.30
.430
2.43
.0560
Ratio
EPA/ EML
1.33
1.26
1.11
0.95
1.16
1.23
1.29
0.99
1.02
1.01
0.73
1.00
1.00
C-5
-------
To measure the performance of the contractor laboratory for analysis
of animal tissues, a known amount of activity was added to several samples.
The reported activity is compared to the known amount in Table C-5. The aver-
age bias for Sr-90 was -57 percent and for Pu-239 was -26 percent. The pre-
cision was 65 percent for Pu-239 and 11 percent for Sr-90 analyses.
In addition to calibration of the TLD's with a Cs-137 source traceable to
NBS, the accuracy of the results obtained from the Dosimetry Network is af-
firmed by participation in the International Intercomparison of Environmental
Dosimeters Program operated by the Idaho Operations Office of the DOE. The
results of the eighth such comparison study are given in Table C-6.
For personal dosimeters, this Laboratory was accredited in 1985 under the
National Voluntary Laboratory Accreditation Program operated by the National
Bureau of Standards. For both personal and environmental dosimeters, the
TLD measurements are performed according to standards proposed by the American
National Standards Institute (ANSI75).
C-6
-------
TABLE C-5. QUALITY ASSURANCE RESULTS FOR THE BIOENVIRONMENTAL PROGRAM - 1986
Sample Type
and
Shi pment
Number
Bone Ash
Ash 1
72
Ash 2
72
Ash 3
72
Ash 4
72
Ash F
73
Ash G
73
Ash H
73
Ash I
73
Duplicate Samples
Bov-1
Bov-1 Dup
Bov-2
Bov-2 Dup
Nuclide
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
Activity Added
pCi/g Bone Ash
Spiked Samples
0
10.4
0.18
0
0
0
0
0
0.073
10.1
0.073
10.1
0
0
0
0
Activity Reported
pCi/g Bone Ash
0**
8.8
0.13
2.5
0.0008**
2.3
-0.0003**
2.3
0.05
12
0.06
4.8
0.002**
2.5
0**
2.3
-0.004**
2.5
-0.002**
2.5
0.0005**
2.5
-0.0004**
2.7
% Bias+
or
Precision^
-38
-28
-32
-5
-18
-75
0.59
0
0.59
0
0.20
0.07
0.20
0.07
(continued)
C-7
-------
TABLE C-5. CONTINUED
Sample Type
and
Shipment
Number
Nuclide
Activity Added
pCi/g Bone Ash
Activity Reported
pCi/g Bone Ash
% Bias+
or
Precision^
Spiked Samples
Duplicate Samples
Bov-5
239Pu
90Sr
239Pu
90Sr
Bov-5 Dup
Bov-6
Bov-6 Dup
+ Bias (B) = Recovery -1; where recovery is
239Pu
90Sr
239Pu
90Sr
0.002**
0.5
0.003**
0.5
0.01
0.2
0.001**
0.3
0.35
0
0.35
0
1.45
0.35
1.45
0.35
and X]_ = net activity reported
u = activity added
Precision (CJ = 2
xl - X2
1
xl + X2
**Counting error exceeds reported activity
x where
1.128
= first value
= second value
-------
TABLE C-6.
Quantity
SUMMARY RESULTS OF THE EIGHTH INTERNATIONAL INTERCOMPARISON
OF ENVIRONMENTAL DOSIMETERS
Mean
Standard
Deviation
Summary of Field Site No. 1
Results (mR):
EMSL-LV dosimeters 23.1
ALL dosimeters 28.9
Calculated exposure 29.7
Summary of Field Site No. 2
Results (mR):
EMSL-LV dosimeters 7.8
ALL dosimeters 10.1
Calculated exposure 10.4
Summary of Laboratory
Results (mR):
EMSL-LV dosimeters 14.1
ALL dosimeters 16.2
Calculated exposure 17.2
1.9
6.2
1.5
0.8
4.5
0.5
1.1
3.4
0.9
Comments
EMSL-LV results 20% lower
than all domimeters and
22% lower than the
calculated exposure.
EMSL-LV results 23% lower
than all domimeters and
25% lower than the
calculated exposure.
EMSL-LV results 13% lower
than all domimeters and
18% lower than the
calculated exposure.
C-9
-------
APPENDIX D
RADIATION PROTECTION STANDARDS FOR EXTERNAL AND INTERNAL EXPOSURE
DOE EQUIVALENT COMMITMENT
For stochastic effects in members of the public, the following limits are
used:
Effective Dose Equivalent*
mrem/yr mSv/yr
Occasional annual exposures** 500 5
Prolonged period of exposure 100 1
*Includes both effective dose equivalent from external radiation and
committed effective dose equivalent from ingested and inhaled
radionuclides. I
**0ccasional exposure implies exposure over a few years with the proviso
that over a lifetime the average exposure does not exceed 100 mrem
(1 mSv) per year (ICRP-39).
CONCENTRATION GUIDES
ICRP-30 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 (CG's) in Table D-l 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 the EPA set allowable concentrations for continuous con-
trolled 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 strontium is
8 pCi/L (0.3 Bq/L).
D-l
-------
TABLE D-l. ROUTINE MONITORING FREQUENCY, SAMPLE SIZE, MDC AND CONCENTRATION GUIDES
Nucl ide
Air Surveillance
Be-7
Zr-95
Nb-.95
Mo-99
Ru-103
1-131
Te-132
Cs-137
Ba-140
La-140
Ce-141
Ce-144
Pu-239
Gross Beta
Sampl i ng
Frequency
Network
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
3/wk
Locations
all
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
160-240
Count
Time
minutes
30
30
30
30
30
30
30
30
30
30
30
30
1000
30
Concentration
Bq/m3 n
2000
20
100
100
60
4
18
10
100
100
50
1
9E-4
2E-2
Guide*
Ci/m3
50
0.6
3
3
2
0.1
0.5
0.4
3
3
1
0.03
2E-5
0.4E-4
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
0.11
MDC as
% CG
8E-4
2E-2
2E-3
2E-3
3E-3
4E-2
1E-2
2E-2
5E-3
3E-3
6E-3
1.2
2E-1
6E-1
(conti nued)
-------
TABLE D-l. Continued
o
Sampling Sample
Nuclide Frequency Locations Size
Noble Gas Tritium
H-3
Kr-85
Xe-133
Xe-135
Water Surveillance
H-3
H-3 (Enrich)
Sr-89
Sr-90
Cs-137
Ra-226
U-234
U-235
U-238
Pu-238
in
1/wk
1/wk
1/wk
1/wk
Air
17
17
17
17
Network (LTHMP)
I/ mo
1/rno
1st
1st
1/mo
1st
1st
1st
1st
1st
all
all
time all
time all
all
time all
t i rne all
time all
t i me all
time all
m3
5
0.4
0.4
0.4
Liters
1
0.1
1
1
1
1
1
1
1
1
Count
Time Concentration Guide* MDC
Minutes
200
200
200
200
Minutes
200
200
50
50
100
1000
1000
1000
1000
1000
Bq/m3
7000
1E5
2E4
2E3
j^/L
7E2
7E2
600
0.3
160
5
20
20
20
10
nCi/m3
190
3000
480
60
pCi/L
2E4
2E4
2E4
8
3E3
100
500
600
600
400
rriBq/m3
148
148
148
148
BSL/L
12
0.37
0.18
0.074
0.33
NA
NA
NA
NA
0.003
MDC as
% CG
2E-3
2E-4
7E-4
7E-3
1.7
5E-2
0.03
25
0.3
0.03
(continued)
-------
TABLE D-l. Continued
o
Sampling
Nuclide Frequency
Water Surveillance
Pu-239
Gamma
Milk Surveillance
H-3
Cs-137
Sr-89
Sr-90
Gamma
Dosimetry Network
TLD (Personnel)
TLD (Station)
Ion Chamber
Network
1st time
1/mq
Network
1/mo
1/mo
1/mo
1/mo
1/mo
1/mo
1/qtr
weekly
Locations
(LTHMP)
all
all
all
all
all
all
all
50
130
23
Sample
Size
Liters
1
3.5
3.5
3.5
3.5
3.5
3.5
Number
2
6
2016
Count
Time Concentration Guide*
Minutes Bq/L pCi/L
1000 10 300
30
200 8E4 2E6
100 100 3E3
50 600 2E4
50 40 1E3
50
Exposure
Guide
lOOmR
__
MDC as
MDC % CG
Bq/L
0.002 0.02
0.18 <0.2
12 2E-2
0.33 0.3
0.18 3E-2
0.074 0.2
0.18 <0.2
MDA
2mR 2
2mR
2pR/hr
Na - Not Available
*ALI and DAC 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).
-------
APPENDIX E
DATA SUMMARY FOR THE MONITORING NETWORKS
TABLE E-l. SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
CONTINUOUSLY OPERATING STATIONS - 1986
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
DEATH VALLEY JCT CA
FURNACE CREEK CA
SHOSHONE CA
ALAMO NV
AUSTIN NV
LJL. 1 l_U 1 I_L>
/SAMPLED
26.7/300.1
14.0/300.1
14.8/300.1
3.0/300.1
5.0/300.1
8.8/300.1
30.7/355.0
13.1/355.0
1.0/355.0
16.6/355.0
8.7/355.0
11.5/355.0
1.0/355.0
62.5/353.7
12.2/353.7
14.6/353.7
4.3/353.7
9.4/353.7
32.8/358.9
16.1/358.9
13.3/358.9
4.2/358.9
8.2/358.9
27.7/364.7
16.9/364.7
17.9/364.7
1.1/364.7
NUCLIDE
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1Q6RU
1311
134CS
137CS
140LA
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
MAX
0.71
0.81
4.6
0.97
0.18
0.49
0.97
0.45
0.24
1.9
0.22
0.43
0.61
0.65
0.37
2.2
0.12
0.27
0.72
0.45
2.3
0.13
0.29
0.45
0.94
4.1
0.47
MIN
0.20
0.021
0.045
0.14
0.083
0.088
0.26
0.11
0.24
0.15
0.045
0.055
0.61
0.16
0.10
0.14
0.072
0.11
0.23
0.089
0.24
0.11
0.057
0.19
0.056
0.071
0.47
AVG*
0.033
0.011
0.043
0.0042
0.0023
0.0063
0.033
0.011
0.00064
0.040
0.0029
0.0069
0.0016
0.051
0.0075
0.031
0.0012
0.0043
0.036
0.0097
0.040
0.0015
0.0045
0.021
0.012
0,061
0.0014
(continued)
E-l
-------
TABLE E-l. Continued
SAMPLING LOCATION
AUSTIN NV (CONT)
BEATTY NV
STONE CABIN RANCH NV
CURRANT NV - BLUE EAGLE RANCH
ELY NV
GOLDFIELD NV
GROOM LAKE NV
NO. DAYS
DETECTED
/SAMPLED
12.9/364.7
15.0/364.7
31.9/366.0
10.9/366.0
18.1/366.0
2.1/366.0
9.2/366.0
12.1/366.0
14.0/348.4
10.0/350.4
12.0/350.4
1.0/350.4
4.0/350.4
5.0/350.4
7.0/352.3
13.0/352.3
14.0/352.3
4.0/352.3
9.0/352.3
10.2/357.1
15.0/357.1
19.0/357.1
8:2/357.1
12.0/357.1
24.8/360.8
13.5/360.8
17.3/360.8
1.0/360.8
4.1/360.8
13.4/360.8
21.0/333.8
15.0/333.8
19.0/333.8
1.0/333.8
1.0/333.8
3.0/333.8
RAD 10-
NUCLIDE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
RADIOACTIVITY
(PCI/M3)
MAX
0.35
0.52
0.36
0.42
3.0
0.37
0.29
0.44
0.50
0.48
3.3
0.21
0.20
0.29
0.56
0.62
2.6
0.20
0.44
0.53
0.66
4.2
0.22
0.62
0.96
0.83
4.8
0.33
0.42
0.69
0.45
0.61
1.5
0.13
0.24
0.40
MIN
0.012
0.029
0.21
0.074
0.082
0.14
0.022
0.040
0.19
0.12
0.089
0.21
0.10
0.091
0.21
0.012
0.080
0.13
0.066
0.27
0.047
0.065
0.012
0.026
0.13
0.064
0.14
0,33
0.097
0.048
0.22
0.037
0.069
0.13
0.24
0.20
CONC.
AVG*
0.0033
0.0065
0.026
0.0082
0.043
0.0015
0.0027
0.0078
0.012
0.0079
0.033
0.00059
0.0017
0.0029
0.0073
0.011
0.037
0.0019
0.0059
0.011
0.011
0.061
0.0026
0.0068
0.027
0.011
0.053
0.00093
0.0026
0.0083
0.020
0.0061
0.022
0.00039
0.00072
0.0024
(continued)
E-2
-------
TABLE E-l. Continued
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
HIKO NV
INDIAN SPRINGS NV
LAS VEGAS NV
LATHROP WELLS NV
NY ALA NV
OVERTON NV
PAHRUMP NV
\J L_ 1 l_O 1 UU
/SAMPLED
38.1/356.9
6.0/356.9
12.0/356.9
5.0/356.9
35.2/363.2
14.2/363.2
16.8/363.2
2.2/363.2
2.4/363.2
12.0/363.2
25.1/357.9
13.3/361.0
16.1/361.0
4.1/361.0
2.0/361.0
7.1/361.0
7.8/355.5
11.1/355.5
14.0/355.5
1.1/355.5
3.0/355.5
8.3/355.5
43.0/362.9
8.0/362.9
7.0/362.9
3.0/362.9
5.0/362.9
5.0/362.9
31.8/350.3
8.1/353.3
11.8/353.3
6.2/353.3
10.9/353.3
43.0/351.7
17.0/351.7
17.8/351.7
NUCLIDE
7BE
103RU
1311
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
MAX
0.82
0.33
0.85
0.22
0.58
0.64
2.3
0.20
0.17
0.46
1.1
0.47
2.8
0.18
0.17
0.22
0.47
0.58
2.8
0.24
0.22
0.28
0.60
0.25
2.0
0.070
0.095
0.17
0.48
0.38
4.0
0.14
0.30
0.51
0.51
2.6
MIN
0.22
0.078
0.11
0.090
0.19
0.097
0.14
0.18
0.14
0.053
0.20
0.085
0.094
0.085
0.10
0.099
0.23
0.064
0.18
0.24
0.12
0.052
0.21
0.037
0.094
0.070
0.078
0.13
0.25
0.20
0.39
0.12
0.12
0.25
0.057
0.13
AVG*
0.039
0.0032
0.0099
0.0018
0.032
0.0091
0.038
0.0011
0.0010
0.0055
0.025
0.0091
0.044
0.0015
0.00076
0.0033
0.0067
0.0076
0.039
0.00072
0.0016
0.0038
0.042
0.0035
0.020
0.00058
0.0012
0.0020
0.033
0.0065
0.037
0.0022
0.0059
0.049
0.010
0.044
(continued)
E-3
-------
TABLE E-l. Continued
SAMPLING LOCATION
PAHRUMP NV (CONT)
PIOCHE NV
SCOTTY'S JCT NV
SUNNYSIDE NV
RACHEL NV - ROBINSON
TRAILER PARK
TONOPAH NV
TTR NV
NO. DAYS
DETECTED
/SAMPLED
3.1/351.7
10.1/351.7
49.1/362.8
13.0/362.8
16.0/362.8
6.4/362.8
9.7/362.8
21.0/355.4
17.0/358.4
17.0/358.4
4.0/358.4
7.0/358.4
12.0/358.4
4.0/358.4
40.4/346.9
15.1/346.9
15.1/346.9
3.8/346.9
9.7/346.9
27.2/361.4
13.7/361.4
15.7/361.4
6.3/361.4
8.6/361.4
23.1/365.7
13.1/365.7
14.8/365.7
.8/365.7
7.8/365.7
7.0/365.7
104.2/328.3
23.7/328.3
25.0/328.3
3.8/328.3
12.8/328.3
23.7/328.3
3.8/328.3
RAD 10-
NUCLIDE
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
140LA
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
140LA
RADIOACTIVITY CONC.
(PCI/M3)
MAX
0.19
0.38
0.61
0,57
3.6
0.14
0.33
0.60
0.55
3.3
0.13
0.26
0.45
0.32
0.70
0.65
2.4
0.22
0.37
0.41
0.52
1.5
0.37
0.34
0.42
0.91
5.1
0.46
0.34
0.61
0.47
0.75
1.9
0.18
0.26
0.44
0.53
MIN
0.10
0.050
0.24
0.081
0.074
0.034
0.049
0.20
0.077
0.12
0.13
0.15
0.085
0.32
0.17
0.055
0.091
0.10
0.034
0.22
0.061
0.086
0.030
0.095
0.19
0.078
0.11
0.46
0.033
0.070
0.044
0.0081
0.0063
0.18
0.065
0.0062
0.53
AVG*
0.0012
0.0061
0.053
0.0085
0.035
0.0011
0.0038
0.023
0.014
0.048
0.0014
0.0034
0.0084
0.0036
0.040
0.0083
0.035 ,
0.0015
0.0045
0.024
0.0078
0.025
0.0026
0.0046
0.020
0.011
0.047
0.0010
0.0032
0.0053
0.066
0.015
0.040
0.0021
0.0050
0.0097
0.0061
(continued)
E-4
-------
TABLE E-l. Continued
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
FALLINI'S (TWIN SPGS) RANCH NV
CEDAR CITY UT
DELTA UT
MILFORD UT
ST GEORGE UT
SALT LAKE CITY UT
U L. 1 I_O I L.U
/SAMPLED
35.5/362.4
14.0/362.4
16.0/362.4
3.0/362.4
11.0/362.4
13.2/354.8
11.0/358.8
15.0/358.8
5.8/358.8
7.0/358.8
16.6/298.2
8.7/302.3
17.6/302.3
3.2/302.3
6.1/302.3
1.1/302.3
41.8/359.1
10.9/359.1
17..5/359.1
4.9/359.1
5.9/359.1
19.0/364.1
9.0/364.1
12.0/364.1
5.0/364.1
71.8/360.1
15.4/360.1
16.5/360.1
1.0/360.1
11.4/360.1
9.4/360.1
f\nu i\j-
NUCLIDE
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
140LA
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
137CS
7BE
103RU
1311
132TE
134CS
137CS
MAX
0.52
0.59
5.2
0.24
0.39
0.44
0.29
1.4
0.10
0.20
0.40
0.36
1.7
0.16
0.27
0.47
0.67
0.71
1.2
0.47
0.67
0.52
0.33
1.5
0.27
0.60
0.61
3.1
0.24
0.20
0.59
MIN
0.17
0.056
0.12
0.18
0.072
0.23
0.085
0.17
0.046
0.15
0.22
0.12
0.074
0.096
0.094
0.47
0.17
0,093
0.085
0.052
0.058
0.32
0.095
0.15
0.12
0.16
0.074
0.19
0.24
0.024
0.099
AVG*
0.032
0.0083
0.034
0.0017
0.0054
0.010
0.0057
0.025
0.00097
0.0033
0.017
0.0065
0.028
0.0012
0.0035
0.0018
0.035
0.0069
0.017
0.0024
0.0036
0.021
0.0046
0.022
0.0022
0.056
0.0087
0.027
0.00068
0.0024
0.0054
*AVG MEANS TIME-WEIGHTED AVERAGE OVER THE SAMPLING TIME.
NOTE: ALL RADIOISOTOPES, OTHER THAN 7BE, WERE DETECTED AS THE DEBRIS FROM
CHERNOBYL ENTERED THE U.S.
E-5
-------
TABLE E-2. SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
STANDBY STATIONS OPERATED 1 OR 2 WEEKS PER QUARTER - 1986
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
GLOBE AZ
KINGMAN AZ
TUCSON AZ
WINSLOW AZ
YUMA AZ
LITTLE ROCK AR
ALTURAS CA
BAKER CA
UC. 1 C.U 1 LU
/SAMPLED
5.0/52.2
12.8/52.2
16.1/52.2
2.9/52.2
10.9/52.2
5.0/56.2
13.1/56.2
14.1/56.2
1.0/56.2
5.0/56.2
6.7/57.3
16.8/57.3
21.0/57.3
7.0/57.3
5.0/58.0
5.0/58.0
11.0/58.0
3.0/65.6
11.3/65.6
14.1/65.6
6.5/65.6
6.9/52.8
3.0/52.8
1.0/52.8
10.0/56.5
12.0/56.5
1.0/56.5
8.6/56.5
3.1/44.4
11.0/44.4
14.9/44.4
4.1/44.4
11.1/44.4
2.1/44.4
t\nu lu-
NUCLIOE
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
137CS
7BE
103RU
1311
7BE
103RU
1311
137CS
7BE
103RU
1311
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
140LA
MAX
0.36
0.34
1.6
0.11
0.89
0.25
0.46
1.9
0.10
0.31
0.28
0.26
0.99
0.12
0.65
0.30
0.95
0.33
0.88
1.5
0.24
0.23
0.026
0.062
0.28
1.1
0.19
0.41
0.40
0.35
2.4
0.25
0.35
1.1
MIN
0.22
0.034
0.071
0.066
0.025
0.19
0.050
0.086
0.10
0.054
0.27
0.019
0.046
0.070
0.22
0.11
0.071
0.33
0.089
0.13
0.050
0.18
0.026
0.062
0.067
0.091
0.19
0.039
0.40
0.031
0.049
0.12
0.023
1.1
AVG*
0.026
0.027
0.11
0.0045
0.032
0.019
0.037
'0.12
0.0019
0.011
0.032
0.033
0.11
0.011
0.029
0.016
0.094
0.015
0.040
0.11
0.012
0.027
0.0015
0.0012
0.018
0.071
0.0034
0.022
0.028
0.041
0.27
0.017
0.035
0.052
(continued)
E-6
-------
TABLE E-2. Continued
SAMPLING LOCATION
BISHOP CA
CHICO CA
INDIO CA
LONE PINE CA
NEEDLES CA
RIDGECREST CA
SANTA ROSA CA
:==================
NO. DAYS
DETECTFD
\J L. 1 L_ \j I (_ U
/SAMPLED
9.0/58.0
16.0/58.0
18.0/58.0
7.0/58.0
17.0/58.0
3.0/58.0
16.0/58.0
18.0/58.0
1.0/58.0
8.0/58.0
17.0/58.0
4.0/51.4
15.9/51.4
13.9/51.4
3.9/51.4
11.9/51.4
7.1/56.8
4.9/56.8
7.9/56.8
13.0/61.0
15.0/61.0
15.0/61.0
3.0/61.0
12.0/61.0
16.9/54.5
16.9/54.5
18.8/54.5
3.0/54.5
8.0/54.5
13.0/54.5
8.9/51.9
9.1/51.9
5.1/51.9
7.1/51.9
:==========
RADIO-
r\r\u l \J
NUCLIDE
7BE
103RU
1311
134CS
137CS
140LA
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
103RU
1311
134CS
137CS
RAD I
MAX
0.74
0.71
1.9
0.19
0.42
1.8
0.52
4.2
0.16
0.24
0.53
0.40
0.61
7.7
0.29
0.41
0.46
0.13
0.33
0.51
0.40
1.5
0.21
0.28
0.31
0.75
5.8
0.35
0.27
0.49
0.37
3.1
0.36
0.68
OACTIVITY
(PCI/M3)
MIN
0.42
0.092
0.095
0.075
0.062
1.8
0.097
0.010
0.16
0.068
0.048
0.29
0.044
0.062
0.081
0.036
0.20
0.066
0.13
0.24
0.079
0.16
0.090
0.056
0.22
0.037
0.10
0.22
0.055
0.049
0.098
0.11
0.080
0.091
CONC.
AVG*
0.090
0.078
0.22
0.017
0.052
0.092
0.058
0.24
0.0028
0.017
0.044
0.027
0.048
0.26
0.012
0.035
0.036
0.0078
0.028
0.073
0.046
0.18
0.0067
0.027
0.088
0.082
0.39
0.017
0.022
0.052
0.042
0.15
0.017
0.036
(continued)
E-7
-------
TABLE E-2. Continued
SAMPLING LOCATION
CORTEZ CO
DENVER CO
GRAND JUNCTION CO
MOUNTAIN HOME ID
NAMPA ID
POCATELLO ID
FORT DODGE IA
NO. DAYS
DETECTED
/SAMPLED
7.0/58.4
10.0/58.4
13.9/58.4
3.0/58.4
7.1/58.4
3.0/57.1
6.0/57.1
10.0/57.1
1.0/57.1
5.0/57.1
15.0/46.7
11.0/46.7
17.9/46.7
2.3/46.7
5.2/46.7
3.2/60.7
10.4/60.7
14.6/60.7
2.0/60.7
9.4/60.7
12.0/57.3
19.0/57.3
18.9/57.3
2.0/57.3
9.1/57.3
12.1/57.3
8.6/57.2
15.0/57.2
17.0/57.2
3.0/57.2
13.6/57.2
8.0/50.1
7.0/50.1
3.0/50.1
RAD 10-
NUCLIDE
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
134CS
137CS
103RU
1311
137CS
RADIOACTIVITY
(PCI/M3)
MAX
0.36
0.19
1.3
0.087
0.13
0.40
0.26
0.33
0.050
0.13
0.39
0.39
1.6
0.11
1.5
0.37
0.55
4.6
0.41
1.0
0.42
0.64
4.2
0.43
0.55
0.24
0.37
0.34
3.1
0.13
0.47
0.20
1.5
0.23
MIN
0.28
0.060
0.10
0.023
0.035
0.20
0.054
0.059
0.050
0.053
0.27
0.063
0.17
0.10
0.088
0.37
0.087
0.098
0.20
0.045
0.27
0.025
0.039
0.17
0.013
0.022
0.25
0.085
0.080
0.11
0.030
0.027
0.045
0.11
CONC.
AVG*
0.040
0.018
0.10
0.0022
0.0088
0.017
0.013
0.033
0.00087
0.0074
0.10
0.033
0.20
0.0051
0.042
0.019
0.036
0.18
0.010
0.036
0.073
0.049
0.22
0.011
0.017
0.024
0.046
0.049
0.29
0.0062
0.038
0.015
0.080
0.010
(continued)
E-8
-------
TABLE E-2. Continued
SAMPLING LOCATION
IOWA CITY IA
DODGE CITY KS
MINNEAPOLIS MN
NO. DAYS
DETECTED
/SAMPLED
3.7/61.0
4.9/61.0
8.0/61.0
3.9/61.0
9.0/58.0
8.0/58.0
3.0/58.0
5.0/57.5
12.7/57.5
2.0/57.5
9.9/57.5
.7/57.5
3.7/57.5
5.7/57.5
RAD 10-
NUCLIDE
7BE
103RU
1311
137CS
103RU
1311
137CS
7BE
103RU
106RU
1311
132TE
134CS
137CS
RADIOACTIVITY
(PCI/M3)
MAX
0.18
0.24
0.20
0.10
0.26
0.29
0.19
0.33
0.33
0.15
2.3
0.043
0.11
0.30
MIN
0.18
0.11
0.075
0.080
0.040
0.13
0.12
0.22
0.025
0.15
0.10 '
0.043
0.067
0.11
CONC.
AVG*
0.011
0.016
0.019
0.0058
0.014
0.023
0.0076
0.023
0.033
0.0050
0.088
0.00055
0.0056
0.018
CLAYTON MO
JOPLIN MO
ST JOSEPH MO
GREAT FALLS MT
KALISPELL MT
2.0/50.0 103RU
0.099
0.099 0.0039
4.0/51.0
1.0/51.0
1.0/51.0
3.0/51.0
4.6/51.5
10.9/51.5
11.3/51.5
.9/51.5
4.8/51.5
7.0/39.0
8.0/39.0
2.0/39.0
5.0/39.0
3.0/52.5
13.2/52.5
14.2/52.5
5.3/52.5
13.2/52.5
7BE
103RU
1311
137CS
7BE
103RU
1311
134CS
137CS
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
0.21
0.17
0.31
0.043
0.20
0.20
1.5
0.11
0.22
0.41
2.9
0.15
0.34
0.28
0.44
4.2
0.30
0.70
0.066
0.17
0.31
0.043
0.091
0.024
0.045
0.11
0.014
0.096
0.093
0.092
0.10
0.28
0.030
0.0092
0.018
0.0086
0.011
0.0034
0.0061
0.0025
0.014
0,014
0.046
0.0019
0.0085
0.036
0.19
0.0062
0.031
0.016
0.038
0.15
0.011
0.034
(continued)
E-9
-------
TABLE E-2. Continued
SAMPLING LOCATION
MILES CITY MT
NORTH PLATTE NE
NO. DAYS
DETECTED
/SAMPLED
9.0/49.0
10.0/49.0
2.0/49.0
2.0/49.0
5.5/41.1
6.5/41.1
1.5/41.1
4.5/41.1
RADIO-
NUCLIDE
103RU
1311
134CS
137CS
103RU
1311
134CS
137CS
RADIOACTIVITY
(PCI/M3)
MAX
0.37
1.2
0.15
0.28
0.14
1.3
0.060
0.15
MIN
0.022
0.074
0.080
0.15
0.12
0.13
0.060
0.089
CONC.
AVG*
0.020
0.083
0.0046
0.0088
0.017
0.075
0.0022
0.012
ADAVEN (CANFIELD'S RANCH) NV
BATTLE MOUNTAIN NV
CALIENTE NV
CURRANT NV - ANGLE WORM RANCH
CURRIE NV
DUCKWATER NV
5.8/53.9
7BE
0.28
0.23
0.028
606/43.9
13.7/43.9
14.6/43.9
'2.0/43.9
4.9/43.9
12.6/43.9
2.0/43.9
14.0/51.0
23.9/51.0
1.1/51.0
3.1/51.0
12.0/51.0
8.0/50.4
12.0/50.4
16.9/50.4
1.0/50.4
3,9/50.4
10.9/50.4
4.1/57.9
14.1/57.9
17.0/57.9
4.0/57.9
6.0/57.9
12.1/57..9
2.0/25.6
9.8/25.6
10.9/25.6
7BE
103RU
1311
132TE
134CS
137CS
140LA
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
0.19
0.52
4.0
0.15
0.15
0.33
0.61
0.89
2.0
0.34
0.22
0.45
0.34
0.50
3.1
0.16
0.20
0.34
0.33
0.87
3.9
0.36
0.29
0.48
0.36
0.46
4.4
' 0.16
0.049
0.043
0.15
0.051
0.038
0.61
0.066
0.040
0.34
0.12
0.053
0.28
0.076
0.052
0.16
0.060
0.039
0.30
0.074
0.077
0.19
0.093
0.049
0.36
0.046
0.15
0.028
0.061
0.30
0.0068
0.013
0.042
0.027
0.067
0.23
0.0069
0.0095
0.037
0.049
0.045
0.24
0.0030
0.011
0.038
0.023
0.074
0.28
0.017
0.019
0.039
0.028
0.075
0.93
(continued)
E-10
-------
TABLE E-2. Continued
SAMPLING LOCATION
DUCKWATER NV (CONT)
ELKO NV
EUREKA NV
FALLON NV
FRENCHMAN STATION NV
GEYSER RANCH NV
LOVELOCK NV
NO. DAYS
DETECTED
/SAMPLED
1.4/25.6
2.5/25.6
5.5/25.6
9.0/29.0
10.0/29.0
2.0/29.0
6.0/29.0
7.0/29.0
2.0/44.3
9.1/44.3
11.1/44.3
2.2/44.3
4.3/44.3
8.6/44.3
2.2/44.3
14.5/43.6
15.5/43.6
4.0/43.6
8.0/43.6
7.0/29.0
10.0/29.0
1.0/29.0
5.0/29.0
7.0/29.0
6.0/49.8
10.0/49.8
17.9/49.8
2.0/49.8
8.0/49.8
4.0/38.4
15.0/40.5
16.0/40.5
.9/40.5
8.0/40.5
9.1/40.5
RADIO-
NUCLIDE
132TE
134CS
137CS
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
140LA
103RU
1311
134CS
137CS
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
RADIOACTIVITY CONC.
(PCI/M3)
MAX
0.16
0.18
0.39
0.92
1.8
0.22
0.30
0.71
0.28
0.59
1.1
0.14
0.16
0.33
0.87
0.50
3,6
0.20
0.45
0.75
5.1
0.41
0.40
0.62
0.26
0.38
1.4
0.15
0.21
1.1
0.75
3.1
0.23
0.30
0.54
WIN
0.16
0.13
0.042
0.13
0.11
0.16
0.10
0.17
0.28
0.12
0.32
0.14
0.15
0.070
0.87
0.038
0.055
0.093
0.074
0.085
0.21
0.41
0.16
0.13
0.15
0.054
0.0051
0.033
0.031
0.35
0.045
0.076
0.23
0.025
0.043
AVG*
0.0084
0.015
0.042
0.13
0.31
0.013
0.039
0.084
0.012
0.063
0.19
0.0069
0.015
0.040
0.043
0.062
0.21
0.014
0.036
0.12
0.67
0,015
0.040
0.095
0.026
0.032
0.14
0.0036
0.014
0.074
0.074
0.26
0.0050
0.023
0.050
(continued)
E-ll
-------
TABLE E-2. Continued
SAMPLING LOCATION
LUND NV
MESQUITE NV
RENO NV
ROUND MOUNTAIN NV
WELLS NV
WINNEMUCCA NV
ALBUQUERQUE NM
NO. DAYS
DETECTED
/SAMPLED
3.0/47.7
11.9/47.7
11.9/47.7
2.0/47.7
3.0/47.7
9.9/47.7
2.0/52.4
13.0/52.4
14.0/52.4
1.0/52.4
11.0/52.4
10.0/36.2
17.2/36.2
17.2/36.2
4.0/36.2
5.1/36.2
15.2/36.2
3.0/49.0
15.0/49.0
18.0/49.0
1.0/49.0
5.2/49.0
12.0/49.0
15.2/51.7
17.0/51.7
6.0/51.7
8.0/51.7
4.2/45.7
17.0/45.7
18.0/45.7
2.9/45.7
14.0/45.7
14.1/45.7
3.2/51.2
1.8/51.2
5.0/51.2
RAD 10-
NUCLIDE
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
RADIOACTIVITY
(PCI/M3)
MAX
0.39
0.64
3.5
0.35
0.24
0.47
0.28
0.48
2.3
0.12
0.20
0.81
1.0
8.9
0.45
0.46
0.96
0.30
0.79
3.6
0.19
0.26
0.56
0.80
3.9
0.25
0.44
0.37
0.35
1.8
0.093
0.17
0.32
0.18
0.058
0.88
MIN
0.39
0.10
0.11
0.30
0.085
0.046
0.28
0.019
0.016
0.12
0.021
0.41
0.030
0.17
0.21
0.095
0.055
0.30
0.12
0.044
0.19
0.12
0.049
0.026
0.10
0.094
0.14
0.37
0.056
0.080
0.093
0.019
0.040
0.18
0.058
0.16
COIMC.
AVG*
0.025
0.072
0.23
0.014
0.011
0.040
0.011
0.040
0.18
0.0022
0.020
0.16
0.14
0.55
0.035
0.040
0.11
0.019
0.084
0.29
0.0038
0.018
0.048
0.070
0.25
0.021
0.042
0.034
0.065
0.16
0.0060
0.024
0.050
0.011
0.0021
0.035
(continued)
E-12
-------
TABLE E-2. Continued
SAMPLING LOCATION
CARLSBAD NM
SHIPROCK NM
BISMARK ND
FARGO ND
WILLISTON ND
MUSKOGEE OK
MEDFORD OR
NO. DAYS
DETECTED
/SAMPLED
8.1/50.3
6.7/50.3
15.0/50.3
3.0/50.3
7.1/50.3
6.9/50.9
14.0/50.9
16.9/50.9
2.9/50.9
14.0/50.9
8.4/51.9
14.5/51.9
15.6/51.9
3.0/51.9
16.3/51.9
6.0/45.0
10.0/45.0
2.0/45.0
7.0/45.0
10.0/53.9
16.0/53.9
12.0/53.9
2.0/53.9
.9/53.9
12.1/53.9
8.0/66.0
11.0/66.0
5.0/66.0
4.0/66.0
8.0/66.0
3.0/48.8
4.0/48.8
6.0/48.8
1.0/48.8
2.0/48.8
3.0/48.8
: = := = = = = :== = :
RAD 10-
NUCLIDE
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
RADIOACTIVITY CONC.
(PCI/M3)
MAX
0.40
0.12
1.1
0.0083
0.12
0.48
0.22
0.73
. 0.029
0.14
0.30
0.32
1.1
0.094
0.31
0.52
1.5
0.18
0.34
0.18
0.35
0.83
0.10
0.24
0.31
0.21
0.15
0.89
0.0030
0.098
0.20
0.29
2.4
0.20
0.21
0.53
MIN
0.16
0.022
0.0068
0.0083
0.014
0.33
0.062
0.15
0.029
0.034
0.22
0.040
0.085
0.067
0.019
0.18
0.18
0.17
0.14
0.15
0.029
0.12
0.10
0.24
0.026
0.14
0.013
0.18
0.0030
0.0090
0.20
0.071
0.20
0.20
0.17
0.064
AVG*
0.037
0.0077
0.089
0.00050
0.0059
0.053
0.028
0.14
0.0016
0.016
0.044
0.036
0.087
0.0044
0.037
0.042
0.097
0.0078
0.035
0.030
0.034
0.072
0.0039
0.0041
0.031
0.021
0.0074
0.057
0.00018
0.0059
0.012
0.016
0.083
0.0041
0.0076
0.017
(continued)
E-13
-------
TABLE E-2. Continued
SAMPLING LOCATION
BURNS OR
RAPID CITY SD
AMARILLO TX
AUSTIN TX
MIDLAND TX
TYLER TX
BRYCE CANYON UT
ENTERPRISE UT
GARRISON UT
NO. DAYS
DETECTED
/SAMPLED
4.9/49.9
13.9/49.9
16.9/49.9
3.9/49.9
8.9/49.9
6.0/50.6
5.0/50.6
2.0/50.6
3.7/49.5
5.7/49.5
3.7/49.5
1.0/47.0
1.1/47.0
2.2/51.2
1.1/51.2
2.2/51.2
8.9/41.9
10.9/48.2
13.8/48.2
14.7/46.2
2.8/48.2
5.8/48.2
8.0/58.0
15.0/58.0
15.0/58.0
1.0/58.0
2.0/58.0
10.0/58.0
11.3/54.5
15.2/54.5
15.0/54.5
1.8/54.5
11.8/54.5
13.0/54.5
RAD 10-
NUCLIDE
7BE
103RU
1311
134CS
137CS
103RU
1311
137CS
103RU
1311
137CS
1311
137CS
103RU
1311
137CS
103RU
7BE
103RU
1311
'134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
RADIOACTIVITY
(PCI/M3)
MAX
0.28
0.38
2.5
0.37
0.56
0.16
1.1
0.095
0.078
0.17
0.092
1.6
0.065
0.027
0.16
0.038
0.11
0.33
0.35
0.76
0.16
0.21
0.69
0.29
1.9
0.10
0.16
0.33
0.29
0.32
2.7
0.13
0.12
0.27
MIN
0.26
0.067
0.063
0.017
0.030
0.022
0.12
0.095
0.078
0.047
0.092
1.6
0.065
0.027
0.16
0.038
0.018
0.19
0.038
0.067
0.046
0.093
0.27
0.084
0.086
0.10
0.088
0.035
0.16
0.092
0.096
0.13
0.026
0.073
CONC.
AVG*
0.027
0.053
0.20
0.0099
0.028
0.0056
0.037
0.0037
0.0058
0.0085
0.0069
0.033
0.0015
0.0011
0.0035
0.0016
0.0083
0.050
0.037
0.095
0.0050
0.016
0.065
0.042
0.13
0.0017
0.0043
0.021
0.041
0.040
0.14
0.0043
0.011
0.028
E-14
(continued)
-------
TABLE E-2. Continued
SAMPLING LOCATION
LOGAN UT
PAROWAN UT
VERNAL UT
WENDOVER UT
SEATTLE WA
SPOKANE WA
ROCK SPRINGS WY
NO. DAYS
DETECTED
/SAMPLED
8.4/51.4
13.6/51.4
3.0/51.4
11.2/51.4
3.0/41.1
9.0/41.1
10.0/41.1
4.0/41.1
6.0/41.1
3.1/43.6
9.4/43.6
14.1/43.6
3.5/43.6
4.5/43.6
2.0/28.0
5.0/28.0
7.0/28.0
3.0/28.0
6.0/28.0
2.0/28.0
3.9/53.9
5.0/53.9
1.0/53.9
6.9/53.9
5.0/50.0
10.0/50.0
11.0/50.0
2.0/50.0
3.0/50.0
10.0/50.0
8.0/51.0
10.0/51.0
2.0/51.0
6.0/51.0
RAD 10-
NUCLIDE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
7BE
103RU
1311
134CS
137CS
95NB
103RU
1311
134CS
137CS
141CE
103RU
1311
134CS
137CS
7BE
103RU
1311
132TE
134CS
137CS
103RU
1311
134CS
137CS
RADIOACTIVITY
(PCI/M3)
MAX
0.33
3.2
0.15
0.32
0.47
0.35
0.85
0.10
0.23
0.30
0.23
1.7
0.090
0.37
0.11
0.62
2.3
0.16
0.47
0.058
0.56
0.97
0.097
0.19
0.25
0.39
2.4
0.28
0.27
0.64
0.59
1.3
0.28
0.54
MIN
0.060
0.028
0.13
0.044
0.25
0.044
0.073
0.019
0.047
0.30
0.050
0.091
0.068
0.081
0.11
0.15
0.40
0.049
0.075
0.058
0.089
0.12
0.097
0.090
0.22
0.031
0.12
0.14
0.13
0.028
0.080
0.17
0.12
0.12
CONC.
AVG*
0.025
0.18
0.0080
0.033
0.029
0.037
0.087
0.0068
0.018
0.021
0.029
0.17
0.0066
0.021
0.0077
0.053
0.21
0.0092
0.039
0.0042
0.015
0.046
0.0018
0.017
0.024
0.034
0.14
0.0084
0.011
0.032
0.038
0.16
0.0079
0.027
(continued)
E-15
-------
TABLE E-2. Continued
SAMPLING LOCATION
WORLAND WY
NO. DAYS
nFTFfTFD
/SAMPLED
8.0/57.7
10.0/57.7
13.0/57.7
5.0/57.7
9.0/57.7
RADIOACTIVITY
(PCI/M3)
RADIO-
NUCLIDE
7BE
103RU
1311
134CS
137CS
MAX
0.37
0.32
3.1
0.16
0.25
MIN
0.18
0.034
0.081
0.056
0.043
CONC.
AVG*
0.035
0.024
0.13
0.0082
0.020
*AVG MEANS TIME-WEIGHTED AVERAGE OVER THE SAMPLING TIME.
NOTE: ALL RADIOISOTOPES OTHER THAN 7BE, WERE DETECTED AS THE DEBRIS FROM
CHERNOBYL ENTERED THE U.S.
THE FOLLOWING STATIONS HAD NEGLIGIBLE GAMMA-SPECTRA:
MONROE LA
BLUE JAY NV
DESERT OASIS RESORT NV
TABLE E-3. SUMMARY OF GROSS BETA ANALYSES FOR AIR SURVEILLANCE NETWORK - 1986
RADIOACTIVITY CONC.
NO. (PCI/M3)
SAMPLING LOCATION
SHOSHONE CA
LAS VEGAS NV
DELTA UT
MILFORD UT
ST GEORGE UT
L/n i o
SAMPLED
352.9
358.8
302.3
359.1
364.1
MAX
0.70
0.73
1.1
0.83
0.62
MIN
-0.0057
0.0013
0.0
0.0014
0.0018
AVG
0.022
0.026
0.029
0.025
0.021
E-16
-------
TABLE E-4. PLUTONIUM-239 CONCENTRATION IN COMPOSITED AIR SAMPLES* - 1986
SAMPLING LOCATION
WINSLOW/TUCSON, AZ
BISHOP/RIDGECREST, CA
DENVER AND CORTEZ, CO
MT HOME/NAMPA, ID
JOPLIN/CLAYTON, MO
GREAT FALLS/MILES CITY, MT
LAS VEGAS, NV
LATHROP WELLS, NV
RACHEL, NV
BISMARCK/ FARGO, NO
ALBUQUERQUE/CARLSBAD, NM
MEDFORD/BURNS, OR
AUSTIN/ AMARILLO, TX
VERNAL/LOGAN, UT
SALT LAKE CITY, UT
SEATTLE/SPOKANE, WA
WORLAND/ROCK SPRINGS, WY
FIRST
QUARTER
-96
-3.4
370
5.1
-49
160
4.1
4
7.7
46
-
6.5
1.4
-8.4
8.9
7.8
12
SECOND THIRD
QUARTER QUARTER
-2.2
-0.91
2.1
-0.47
-2.1
-1.5
3.7 -21
2.4 78
6.8 -51
-1.6
0.17
-16
-
-2.7
2.5 -3.3
-0.91
-1.8
FOURTH
QUARTER
_
1.4
-
-6.1
-26
140
2.8
2.9
-27
1.2
-
13
-4.1
5.2
2.4
-11
11
ANNUAL
AVERAGE
-63
-.31
170
-1.5
-16
40
-2.6
18
-8.5
4.8
.17
-6.0
-1.9
-1.5
3.2
-.89
9.5
*ALL DATA ARE EXPRESSED IN ACI/M3 AND ARE LESS THAN THE MDC WHICH VARIED FROM
2 TO 500 ACI/M3. ALL PLUTONIUM-238 RESULTS WERE ALSO LESS THAN MDC.
E-17
-------
TABLE E-5. SUMMARY OF ANALYTICAL RESULTS FOR THE NOBLE GAS AND TRITIUM
SURVEILLANCE NETWORK - 1986
NUMBER
SAMPLES
SAMPLING ANALYZED/
LOCATION LOST RADIONUCLIDE
SHOSHONE,
CALIF.
ALAMO,
NEV.
0
AUSTIN,
NEV.
BEATTY,
NEV.
ELY,
NEV.
GOLDFIELD,
NEV.
INDIAN SPRINGS,
NEV.
LAS VEGAS,
NEV.
43/9
44/8
51/0
51/0
49/2
47/4
52/0
52/0
51/1
48/4
52/0
52/0
41/10
37/14
52/0
52/0
52/0
52/0
52/0
52/0
49/2
44/7
51/1
51/1
44/7
46/5
50/2
50/2
46/5
46/5
50/1
50/1
85KR
133XE
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
133XE
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
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
RADIOACTIVITY CONC.
(PCI/M3)*
MAX
33
29
0.69
4.2
31
40
0.63
5.6
30
54
0.74
4.1
37
52
0.77
9.6
31
36
0.59
7.5
31
45
0.62
1.7
30
43
0.49
2.9
33
67
2.3
21
MIN
17
-4.5
-0.57
-4.1
16
-8.7
-0.56
-5.1
20
-5.8
-0.68
-3.7
19
-6.9
-0.78
-4.7
19
-7.7
-0.51
-3.7
17
-13
-0.72
-1.4
21
-14
-0.60
-2.9
18
-15
-0.65
-8.1
AVG
25
3.0
0.070
0.29
24
3.5
0.022
0.074
25
3.7
0.024
0.26
26
6.4
0.083
0.51
25
3.2
-0.0041
0.11
25
3.4
0,0080
0.11
26
3.3
0.054
0.37
25
3.3
0.22
2.3
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
(continued)
E-18
-------
TABLE E-5. Continued
SAMPLING
LOCATION
LATHROP WELLS,
NEV.
OVERTON,
NEV.
PAHRUMP,
NEV.
PIOCHE,
NEV.
RACHEL,
NEV.
TONOPAH,
NEV.
CEDAR CITY,
UTAH
ST GEORGE,
UTAH
NUMBER
SAMPLES
POSITIVE/
NEGATIVE
51/1
48/4
51/0
51/0
49/3
47/5
50/2
50/2
48/4
47/5
51/0
51/0
13/1
12/2
52/0
52/0
50/2
48/4
52/0
52/0
48/4
47/5
52/0
52/0
44/8
39/13
52/0
52/0
40/12
41/11
50/2
50/2
RADIOACTIVITY CONC.
(PCI/M3)*
RADIONUCLIDE
85KR
133XE
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
133XE
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
133XE .
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
MAX
32
84
1.5
18
32
31
0.63
5.3
30
24
0.68
5.9
30
9.4
0.68
2.7
31
45
1.0
14
30
57
0.57
4.4
30
33
0.99
5.9
30
16
0.43
7.2
MIN
19
-5.8
-0.44
-4.3
17
-11
-0.69
-5.2
19
-9.2
-0.57
-4.7
21
-3.2
-0.74
-6.4
19
-7.6
-0.38
-1.9
18
-5.6
-0.78
-4.5
19
-4.9
-0.47
-5.9
19
-16
-0.58
-10
AVG
25
5.3
0.22
1.5
25
2.4
0.025
0.17
25
2.2
0.041
0.28
26
2.4
-0.059
-0.57
25
3.5
0.14
1.3
25
4.4
0.010
0.032
24
3.9
0.034
0.16
24
2.9
-0.0083
-0.18
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
(continued)
E-19
-------
TABLE E-5. Continued
SAMPLING
LOCATION
SALT LAKE CITY,
UTAH
NUMBER
SAMPLES
POSITIVE/
NEGATIVE
50/2
50/2
RADIONUCLIDE
3H IN ATM. M.*
3H AS HTO IN AIR
RADIOACTIVITY CONC.
(PCI/M3)*
MAX
0.91
8.7
MIN
-0.28
-3.2
AVG
0.14
1.0
PERCENT
CONC.
GUIDE+
<0.01
* CONCENTRATIONS OF TRITIUM IN ATMOSPHERIC MOISTURE (ATM. M.) ARE EXPRESSED AS
PCI PER ML OF WATER COLLECTED.
+ CONCENTRATION GUIDES USED ARE FOR EXPOSURE TO A SUITABLE SAMPLE OF THE
POPULATION IN AN UNCONTROLLED AREA.
TABLE E-6. SUMMARY OF TRITIUM RESULTS FOR THE NTS NETWORK LONG-TERM
HYDROLOGICAL MONITORING PROGRAM - 1986
SAMPLING
LOCATION
NO.
SAMPLES
TRITIUM CONCENTRATION
(PCI/L)
MAX
MIN
AVG
PERCENT
CONC.
GUIDE
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
1 ARMY
2
3
4
4 CP-1
5C
8
20
A
B TEST
C
J-13
U19C
UE7NS
UE18R
12
12
11
11
9
11
12
11
11
.10
11
11
12
4
3.7
150
7.4
7.8
7.0
4.3
160
6.1
19
320
58
5.5
5.8
3200
23
-3.5
-7.1
-4.9
-28
-3.5
-5.8
-6.4
-7.4
4.1
130
0.13
-8.5
-7.4
2300
-1.0
-0.99
12
0.99
-4.8
-0.54
-0.94
14
1.2
11
160
25
-1.7
-0.54
2500
5.8
<0.01
0.06
<0.01
<0.01
<0.01
<0.01
0.07
<0.01
0.06
0.8
0.1
<0.01
<0.01
10
0.03
E-20
-------
TABLE E-7- TRITIUM RESULTS FOR THE LONG-TERM HYDROLOGICAL MONITORING
PROGRAM - 1986
SAMPLING LOCATION
NEVADA TEST SITE NETWORK
SHOSHONE CA
SHOSHONE SPRING
ADAVEN NV
ADAVEN SPRING
ALAMO NV
WELL 4 CITY
ASH MEADOWS NV
CRYSTAL POOL
FAIRBANKS SPRINGS
WELL 17S-50E-14CAC
WELL 18S-51E-7DB
BEATTY NV
SPECIE SPRINGS
TOLICHA PEAK
USECOLOGY
WELL 11S-48-1DD COFFERS
WELL 12S-47E-7DBD CITY
COLLECTION
DATE
1985
01/15
06/03
05/02
10/07
04/01
09/09
02/04
07/02
03/12
08/06
02/04
07/02
02/04
07/02
08/06
01/09
02/03
03/13
02/10
07/01
01/15
06/09
02/05
07/01
03/12
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
-86 ± 200*
9.7 ± 8.1*
39 ± 8
12 ± 250*
9.3 ± 7.5*
-75 ± 140*
7.5 ± 8.5*
22 ± 230*
0.11 ± 7.9*
-22 ± 140*
0.93 ± 8.6*
110 ± 230*
6.5 ± 8.5*
110 ± 230*
39 ± 140*
49 ± 8
40 ± 7
35 ± 6
-5.0 ± 8.8*
-0.57 ± 8.3*
-9.9 ± 8.1*
2.4 ± 200*
-2.8 ± 8.5*
22 ± 230*
9.0 ± 7.6*
PCT OF
CONC.
GUIDE
<0.01
0.05
0.2
0.06
0.05
<0.01
0.04
0.1
<0.01
<0.01
<0.01
0.5
0.03
0.5
0.2
0.2 (1)
0.2
0.2
<0.01
<0.01
<0.01
0.01
<0.01
0.1
0.04
(continued)
E-21
-------
TABLE E-7. Continued
SAMPLING LOCATION
BEATTY NV
WELL ROAD D SPICERS
YOUNGHANS RCH (COW CAMP)
YOUNGHANS RCH (HOUSE WE)
YOUNGHANS RCH (LOWER PO)
YOUNGHANS RCH (UPPER PO)
BOULDER CITY NV
LAKE MEAD INTAKE
CLARK STATION NV
WELL 6 TTR
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
CITY 15S-50E-18CDC
NYALA NV
SHARP'S RANCH
COLLECTION
DATE
1985
02/06
07/01
08/06
08/06
08/06
08/06
03/10
08/11
05/01
10/07
04/01
08/12
09/09
01/17
06/09
01/14
06/09
02/07
06/06
01/14
06/03
04/01
09/10
CONC.
i
-4.2
3.6
-46
62
-29
-79
110
79
-1.7
-46
12
-62
35
-6.2
-170
3.5
210
-9.3
2.7
-0.83
-2.4
6.7
-42
± 2 SIGMA
FRITIUM
(PCI/L)
± 8.6*
± 7.9*
± 140*
± 140*
± 140*
± 85*
± 7
± 140*
± 8.8*
± 250*
± 7
± 140*
± 140*
± 7.9*
± 200*
± 7.9*
± 200*
± 200*
± 7.9*
± 7.9*
± 200*
± 7.6*
± 140*
PCT OF
CONC.
GUIDE
<0.01
0.02
<0.01
0.3
<0.01
<0.01
0.6
0.4
<0.01
<0.01
0.06
<0.01
0.2
<0.01
<0.01
0.02
1
<0.01
0.01
<0.01
<0.01
0.03
<0.01
(2)
(3)
(4)
(5)
(continued)
E-22
-------
TABLE E-7. Continued
SAMPLING LOCATION
OASIS VALLEY NV
GOSS SPRINGS
PAHRUMP NV
WELL 3 CALVADA
RACHEL NV
WELLS 7 AND 8 PENOYER
WELL 13 PENOYER
WELL PENOYER CULINARY
UNION CARBIDE WELL
TONOPAH NV
CITY WELL
WARM SPRINGS NV
TWIN SPRINGS RANCH
NTS NV
WELL 58
WELL C-l
WELL D TEST
WELL U16D
WELL UE1C
WELL UE5C
COLLECTION
DATE
1985
03/11
05/01
10/21
02/03
04/03
09/08
04/03
09/08
01/15
06/02
05/01
10/07
04/01
09/10
02/05
07/03
02/04
07/02
03/03
02/04
07/02
03/03
02/05
06/03
07/03
CONG. ± 2 SIGMA
TRITIUM
(PCI/L)
4.5 ± 7.6*
-4.3 ± 9.2*
-120 ± 250*
-13 ± 9*
-0.71 ± 7.5*
-18 ± 140*
4.4 ± 7.7*
-42 ± 140*
-48 ± 200*
1.3 ± 8.0*
-6.8 ± 9.3*
-120 ± 250*
2.5 ± 3.0*
24 ± 140*
5.8 ± 8.3*
8.5 ± 11*
-150 ± 200*
6.3 ± 8.2*
120 ± 200*
-86 ± 200*
1.0 ± 7.9*
200 ± 200*
-130 ± 200*
83 ± 7
0.13 ± 7.9*
PCT OF
CONC.
GUIDE
0.02
<0.01
<0.01
<0.01
<0.01
<0.01
0.02
<0.01
<0.01
<0.01
<0.01
<0.01
0.01
0.1
0.03
0.04
<0.01
0.03
0.6
<0.01
<0.01
1
<0.01
0.4
<0.01
(continued)
E-23
-------
TABLE E-7. Continued
(
SAMPLING LOCATION
NTS NV
WELL UE15D
BACKGROUND SAMPLES - AMCHITKA, AK
CONSTANTINE SPRING
DUCK COVE CREEK
JONES LAKE
SITE D HYDRO EXPLORE HOLE
WELL ARMY 1
WELL ARMY 2
WELL ARMY 4
PROJECT CANNIKIN - AMCHITKA, AK
CANNIKIN LAKE (NORTH END)
CANNIKIN LAKE (SOUTH END)
DK-45 LAKE
ICE BOX LAKE
PIT SOUTH OF CANNIKIN G
WELL HTH-3
WHITE ALICE CREEK
:OLLECTION
DATE
1985
01/08
08/29
08/29
08/29
08/28
08/28
08/29
08/29
08/29
08/29
08/30
08/29
08/29
08/29
08/29
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
88 ± 200*
65 ± 8
40 ± 8
30 ± 7
75 ± 6
45 ± 6
25 + 6
63 ± 6
36 ± 7
47 ± 7
49 ± 8
39 ± 7
28 ± 6
50 ± 7
49 ± 8
PCT OF
CONC.
GUIDE
0.4
0.3
0.2
0.2
0.4
0.2
0.1
0.3
0.2
0.2
0.2
0.2
0.1
0.2
0.2
E-24
(continued)
-------
=Constantme Harbor
Scale in Miles
5 10
'Duck Cove Cr.
0 5 10
3/83 Scale in Kilometers
: Base Camp Area
Surface Ground Zero
Sampling Locations
= Bermg Sea
Constantme Harbor2S:
lnfentry Road
Mason Lakeo
Constantine Spring
Clevenger Lake
South Hangar
Maintenance Building
0 1
Scale in Kilometers
Sampling Locations
Pacific Ocean
Figure E-l. Amchitka Island and background sampling locations for the LTHMP.
E-25
-------
0 1
3-'84 Scale in Kilometers
Surface Ground Zero
Sampling Locations
Figure E-2. LTHMP sampling locations for Project Cannikin.
E-26
-------
TABLE E-7. Continued
SAMPLING LOCATION
PROJECT LONGSHOT - AMCHITKA, AK
LONG SHOT POND 1
LONG SHOT POND 2
LONG SHOT POND 3
MUD PIT NO.l
MUD PIT NO. 2
MUD PIT NO. 3
REED POND
WELL EPA-1
WELL GZ NO.l
WELL GZ NO. 2
WELL WL-1
WELL WL-2
PROJECT MILROW - AMCHITKA, AK
CLEVENGER CREEK
HEART LAKE
WELL W-2
WELL W-3
WELL W-4
WELL W-7
WELL W-8
COLLECTION
DATE
1985
08/30
08/30
08/30
06/10
08/30
08/30
06/10
08/30
08/30
08/30
08/30
08/30
08/30
08/30
08/28
08/28
08/28
08/28
08/28
08/28
08/28
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
33 ± 8
37 ± 7
38 ± 9
540 ± 190
310 ± 1
410 ± 9
870 ± 190
590 ± 9
37 ± 7
270 ± 9
2300 ± 230
150 ± 8
41 ± 7
320 ± 9
44 ± 8
31 ± 7
28 ± 8
28 ± 8
31 ± 8
35 ± 7
41 ± 1
PCT OF
CONC.
GUIDE
0.2
0.2
0.2
3
2
2
4
3
0.2
1
10
0.8
0.2
2
0.2
0.2
0.1
0.1
0.2
0.2
0.2
(continued)
E-27
-------
Surface Ground Zero
Sampling Locations
Long Shot
Pond #3
Surface Ground Zero
Sampling Locations
Figure E-3. LTHMP sampling locations for Projects Milrow and Long Shot,
E-28
-------
TABLE E-7. Continued
COLLECTION
DATE
SAMPLING LOCATION 1985
PROJECT MILROW - AMCHITKA, AK (CONT)
WELL W-10
WELL W-ll
WELL W-13
WELL W-14
WELL W-15
WELL W-17
WELL W-18
PROJECT RIO BLANCO - COLORADO
B-l EQUITY CAMP
BRENNAN WINDMILL
CER NO.l BLACK SULPHUR
CER NO. 4 BLACK SULPHUR
FAWN CREEK 1
FAWN CREEK 3 (sp cond 350, pH .6)
FAWN CREEK 6800FT UPSTR
(sp cond 190, ph. 4)
FAWN CREEK 500FT UPSTRE
(sp cond pH.O)
FAWN CREEK 500FT DOWNST
FAWN CREEK 8400FT DOWNS
WELL JOHNSON ARTESIAN
WELL RB-D-01
08/28
08/28
08/28
08/28
08/28
08/28
08/28
06/17
06/16
06/17
06/17
06/16
06/16
06/16
06/16
06/16
06/16
06/17
06/17
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
35 ± 1
87 ± 8
42 ± 7
33 ± 7
28 ± 7
30 ± 8
52 ± 7
100 ± 8
71 ± 7
100 ± 7
100 ± 8
58 ± 7
64 ± 7
59 ± 7
69 ± 8
63 ± 7
49 ± 8
57 ± 7
25 ± 7
PCT OF
CONC.
GUIDE
0.2
0.4
0.2
0.2
0.1
0.1
0.3
0.5
0.4
0.5
0.5
0.3
0.3
0.3
0.3
0.3
0.2
0.3
0.1
(continued)
E-29
-------
Johnson
Artesian
CER-1 AjfFawrt Cr. No. 1
Fawn Cr.
8400' Downstream
Fawn Cr. 500 Downstream
R8-D-01
SGZ
awn Cr. 500' Upstream
Fawn Cr. No. 3
Fawn Cr 6800'
Upstream
Rio Blanco County
Garfield County
Rio Blanco County
Scale in Kilometers
Surface Ground Zero Q Water Well
Artesian Well A Spring
O Windmill ' Stream
Location Maps
Figure E-4. LTHMP sampling locations for Project Rio Blanco.
E-30
-------
TABLE E-7. Continued
SAMPLING LOCATION
PROJECT RULISON - COLORADO
GRAND VALLEY CO
BATTLEMENT CREEK
CITY SPRINGS
ALBERT GARDNER RANCH
WELL CER TEST (3H lost)
RULISON CO
LEE HAYUARD RANCH
POTTER RANCH
ROBERT SEARCY RANCH (SC)
FELIX SEFCOVIC RANCH
PROJECT DRIBBLE - MISSISSIPPI
BAXTERVILLE MS
HALF MOON CREEK
HALF MOON CREEK OVRFLW
LOWER LITTLE CREEK
POND WEST OF GZ
REECO PIT DRAINAGE-A
REECO PIT DRAINAGE-B
REECO PIT DRAINAGE-C
SALT DOME TIMBER CO.
COLLECTION
DATE
1985
06/15
06/15
06/15
06/15
06/15
06/16
06/15
06/15
06/16
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/04
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
100 ± 3
28 ± 8
190 ± 9
NA
260 ± 12
140 ± 8
90 ± 9
98 ± 3
190 ± 8
36 ± 7
3.6 ± 8.9*
800 ± 12
840 ± 12
16 ± 8
21 ± 9
11 ± 9*
14 ± 8
62 ± 9
2800 ± 200
36 ± 9
30 ± 9
PCT OF
CONC.
GUIDE
0.5
0.1
1
1
0.7
0.5
0.5
1
0.2
0.02
4
4
0.08
0.1
0.06
0.07
0.3
10
0.2
0.2
(continued)
E-31
-------
G. Schwab ' Potter
Rn.
Grand Valley ,,--.-
City Water\ \*£
irSefcovic Rn.
Hayward Rn.
Grand Valley
Rifle
Gardner
Rn.
Battlement Creek
NCER Test Well
Sprin'gS) SGZ
Scale in Miles
0 5
0 8
Scale in Kilometers
N
Surface Ground Zero
Water Sampling Locations
Colorado
Garfield
County
3/86
Location Maps
Figure E-5. LTHMP sampling locations for Project Rulison.
E-32
-------
B. Chamblissa
T. Speights
M.
Baxterville
Well Ascot 2
98) \«49
Lower Little Creek
Salt Dome Timber Co.j
. Anderson /fi)
B.R. Anderson//
R.L. Anderson
W. Daniels Jr. if Purvis
R. Ready
Lumberton
Scale in Miles
5 10
15
5 10 15 20
Scale in Kilometers
j, Missi:
IN
Mississippi / /
3/86
Surface Ground Zero
Water Sampling Locations
Lamar
County
SGZ
Location Maps
Figure E-6. LTHMP sampling locations for Project Dribble
towns and residences.
E-33
-------
TABLE E-7. Continued
SAMPLING LOCATION
BAXTERVILLE MS
HALF MOON CREEK
HALF MOON CREEK OVRFLW
LOWER LITTLE CREEK
POND WEST OF GZ
REECO PIT DRAINAGE-A
REECO PIT DRAINAGE-B
REECO PIT DRAINAGE-C
SALT DOME TIMBER CO.
ANDERSON, B. R.
ANDERSON, H.
ANDERSON, R. L.
CHAMBLISS, B.
DANIELS, W. JR.
KELLY, G.
LEE, P. T.
MILLS, A. C.
MILLS, R.
READY, R.
WELL ASCOT 2
COLLECTION
DATE
1985
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/04
04/04
04/04
04/03
04/03
04/03
04/03
04/03
04/04
04/03
04/03
04/03
04/05
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
36 ± 7
3.6 ± 8.9*
800 ± 12
840 ± 12
16 ± 8
21 ± 9
11 ± 9*
14 ± 8
62 ± 9
2800 ± 200
36 ± 9
30 + 9
42 ± 7
27 ± 7
34 ± 8
42 ± 9
-3.6 ± 8.4*
36 ± 8
-6.9 ± 11*
35 ± 9
-0.38 ± 8.1*
26 ± 8
59 ± 9
-23 ± 10*
PCT OF
CONC.
GUIDE
0.2
0.02
4
4
0.08
0.1
0,06
0.07
0.3
10
0.2
. 0.2
0.2
0.1
0.2
0.2
<0.01
0.2
<0.01
0.2
<0.01
0.1
0.3
<0.01
(continued)
E-34
-------
HMH-6 HMH-5 \
HMH-4 x
HMH-1 0
HMH-1
.
Half-Moon ^f
Creek /
Overflow /
SGZ
IHMH-2
1 BHMH-9
HMH-11
\
HMH-8I
HMH-7I
Scale in Feet
0 100 200 300
0 50 100
Scale in Meters
I
N
\
La mar
County
© Surface Ground Zero
Water Sampling Locations
3/86
Mississippi
Location Maps
Figure E-7. LTHMP sampling locations for Project Dribble - near GZ.
E-35
-------
TABLE E-7. Continued
SAMPLING LOCATION
BAXTERVILLE MS
WELL CITY
WELL E-7
WELL HM-1
WELL HM-2A
WELL HM-2B
WELL HM-3
WELL HM-L
WELL HM-L2
WELL HM-S
WELL HMH-1
WELL HMH-2
WELL HMH-3
WELL HMH-4
WELL'HMH-5
WELL HMH-6
WELL HMH-7
WELL HMH-8
WELL HMH-9
COLLECTION
DATE
1985
04/03
04/04
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
04/03
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
21 ± 8
-7.0 ± 12*
-14 ± 9*
-7.8 ± 9.4*
-12 ± 9*
-13 ± 9*
-12 ± 10*
-16 ± 10*
-11 ± 10*
-19 ± 10*
1800 ± 180
1400 ± 180
-21 ± 10*
66 ± 180*
14000 ± 270
14000 ± 270
18000 ± 300
13000 ± 270
81 ± 7
28 ± 7
1800 ± 200
99 ± 8
260 ± 10
34 ± 7
22 ± 7
PCT OF
CONC.
GUIDE
0.1
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
9
7
<0.01
0.3
70
70
90
70
0.4
0.1
9
0.5
1
0.2
0.1
(continued)
E-36
-------
&
-------
TABLE E-7. Continued
SAMPLING LOCATION
BAXTERVILLE MS
WELL HMH-10
WELL HMH-11
WELL HT-2C
WELL HT-4
WELL HT-5
WELL PS-3
COLUMBIA MS-
WELL 64B .CITY
LUMBERTON MS
WELL 2 CITY
PURVIS MS
CITY SUPPLY
PROJECT FAULTLESS - NEVADA
BLUE JAY NV
HOT CREEK RANCH SPRING
MAINTENANCE STATION
WELL BIAS
"WELL HTH-1
WELL HTH-2
COLLECTION
DATE
1985
04/03
04/03
04/04
04/04
04/04
04/05
04/04
04/04
04/03
07/22
07/22
07/22
07/21
07/21
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
25 ± 7
1100 ± 190
-4.6 ± 8.8*
-17 ± 9*
-27 ± 11*
20 ± 8
-5.0 ± 9.3*
-12 ± 10*
-17 ± 10*
15 ± 8
-4.6 ± 9.3*
5.4 ± 9.2*
2.0 ± 9.2*
6.8 ± 9.0*
PCT OF
CONC.
GUIDE
0.1
6
<0.01
<0.01
<0.01
0.1
<0.01
<0.01
<0.01
0.07
<0.01
0.03
0.01
0.03
E-38
(continued)
-------
SGZ
/
HTH 2
HTH 1
Hot Creek T
Ranch
xx /
,' I
Six-Mile
I Jim Bias Well
(Blue Jay Springs)
N
0 5 10
3/85 Scale in Kilometers
(Surface Ground Zero
Water Sampling Locations
I Blue Jay
Mamt Sta
Location Maps
Figure L-9. LTHMP sampling locations for Project Faultless.
E-39
-------
TABLE E-7. Continued
SAMPLING LOCATION
PROJECT SHOAL - NEVADA
FRENCHMAN STATION NV
HUNT'S STATION
WELL FLOWING
FRENCHMAN STATION
WELL H-3
WELL HS-1
PROJECT GASBUGGY - NEW MEXICO
GOBERNADOR NM
ARNOLD RANCH
BIXLER RANCH
BUBBLING SPRINGS
CAVE SPRINGS
LA JARA CREEK
LOWER BURRO CANYON
WELL EPNG 10-36
WELL JICARILLA 1
WELL 30.3.32.343 (NORTH)
COLLECTION
DATE
1985
02/19
02/19
02/19
02/19
02/19
06/11
06/13
06/11
06/12
06/11
06/12
06/13
06/12
06/12
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
1.7 ± 3.7*
-0.36 ± 8.3*
0.87 ± 8.7*
-2.7 ± 8.7*
8.8 ± 8.8*
54 ± 8
20 ± 8
120 ± 9
120 ± 9
69 ± 9
120 ± 8
320 ± 11
68 ± 7
96 ± 8
PCT OF
CONC.
GUIDE
<0.01
<0.01
<0.01
<0.01
0.04
0.3
0.1
0.6
0.6
0.3
0.6
2
0.3
0.5
E-40
(continued)
-------
I Spring
Windmill Frenchman
HS-1
Churchill County
Mineral County
Scale in Miles
5
10
0 5 10 15
3/86 Scale in Kilometers
I
N
Surface Ground Zero
Water Sampling Locations
Churchill
County
Location Maps
Figure E-10. LTHMP sampling locations for Project Shoal.
E-41
-------
To Dulce
Bixler Rn.
To Blanco &
Gobernador
Bubbling
Spring
EPNGWell 10-36
La Jara Creek
Windmill #2
SGZ
Jicarillaj
Well#1
Cave Spring!
Arnold Rn.B
Lower Burro I
Canyon
Scale in Kilometers
0 8
0 5
Scale in Miles
N
3/86
Surface Ground Zero
Water Sampling Locations
New
Mexico
[ ©SGZ)
Rio Arriba
County
Location Maps
Figure E-ll. LTHMP sampling locations for Project Gasbuggy.
E-42
-------
Carlsbad
Carlsbad City
Well #7
Loving
N
USGS 4 8
Wells AAADD-1
1A ALRL-7
PHS Well #6
PHS Well #9|
PHS Well #10r
Loving City
Well #2
Scale in Miles
5 10
0 5 10 15
Scale in Kilometers
PHS Well #8
Pecos River
Pumping Station
Well #1
Eddy County
Surface Ground Zero
A On-Site Water Sampling Locations
Off-Site Water Sampling Locations
3/86
Location Maps
Figure E-1Z. LTHMP sampling locations for Project Gnome,
E-43
-------
TABLE E-7. Continued
SAMPLING LOCATION
PROJECT GNOME - NEW MEXICO
CARLSBAD NM
WELL 7 CITY
LOVING NM
WELL 2 CITY
MALAGA NM
WELL 1 PECOS PUMPING ST
WELL LRL-7
WELL PHS 6
WELL PHS 8
WELL PHS 9
WELL PHS 10
WELL USGS 1
WELL USGS 4
MALAGA NM
WELL USGS 8
COLLECTION
DATE
1985
03/20
03/20
03/19
03/21
03/19
03/19
03/19
03/19
03/19
03/21
03/21
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
5.2 ±
5.1 ±
1.1 ±
16000 ±
66 ±
26 ±
3.3 ±
4.0 ±
1.3 ±
220000 ±
160000 ±
7.6*
7.5*
8.8*
310
7
7
7.8*
7.7*
7.9*
670
780
PCT OF
CONC.
GUIDE
0.03
0.03
<0.01
80
0.3
0.1
0.02
0.02
<0.01
1000
800
(6)
(7)
(8)
(9)
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC)
NOTES
ANALYSIS RESULT 2SIGMA UNITS
(1) 226RA
234U
235U
238U
(2) 226RA
234U
235U
238U
0.095
0.53
0.014
0.23
0.060
6.0
0.13
2.3
0.057
0.07
0.014*
0.05
0.040
Oo4
0.04
0.2
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
E-44
-------
TABLE E-7. Continued
SAMPLING LOCATION
(3)
(4)
(5)
(6)
(7)
(8)
(9)
Analysis
226RA
234U
235U
238U
226RA
234U
235U
238U
226RA
234U
235U
238U
238PU
239PU
90SR
137CS
23SPU
239PU
90SR
238PU
239PU
90SR
137CS
238PU
239PU
Result
6.14
17
0.27
6.0
0.030
6.7
0.090
2.6
0.10
5.4
0.059
2.1
-0.80
-0.40
10
210
-1.3
-0.92
13000
-0.0063
-0.0032
5640
62
-0.49
-0.028
2 Sigma
0.05
1
0.05
0.3
0.025*
0.5
0.051
0.2
0.05
0.4
0.029
0.2
2.1*
1.5*
7
16
2.7*
1.9*
750
0.033*
0.023*
392
9
2.2*
1.5*
COLLECTION CONC. ± 2 SIGMA PCT OF
DATE TRITIUM CONC.
1985 (PCI/L) GUIDE
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
E-45
-------
TABLE E-8. SUMMARY OF ANALYTICAL RESULTS FOR THE MILK SURVEILLANCE
NETWORK - 1986
SAMPLING
LOCATION
BENTON CA -
IRENE BROWN RANCH
BENTON CA -
PAUL ALLRED
HINKLEY CA -
BILL NELSON DAIRY
RIDGECREST CA -
CEDARSAGE FARM
AUSTIN NV -
YOUNG'S RANCH
CURRANT NV -
MANZONIE RANCH
DYER NV -
OZEL LEMON
SAMPLE NO. OF
TYPE SAMPLES
10 8
3
3
3
13 1
1
1
1
12 12
4
4
4
10 11
4
4
4
13 10
4
4
4
13 12
5
4
4
13 12
3
3
3
RAD 10-
NUCLIDE
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
RADIOACTIVITY CONC.
(PCI/L)
MAX
2.3
69
0.70
0.66
1.4
11
-0.031
0.23
1.8
180
1.1
0.89
2.3
240
0.69
0.88
1.8
470
1.8
0.83
2.2
530
1.2
0.63
1.7
730
0.50
1.1
MIN
1.4
-49
-0.15
0.51
1.4
11
-0.031
0.23
1.3
99
0.068
0.21
1.6
-240
-0.50
0.15
1.3
31
-0.98
-0.018
0.32
50
-0.90
-0.51
1.2
-130
-0.015
0.098
AVG
2.1
11
0.25
0.58
1.4
11
-0.03
0,23
1.6
130
0.66
0.55
2.0
57
0.03
0.49
1.5
240
0.45
0.37
1.3
190
0.36
0.12
1.4
230
0.30
0.68
E-46
(continued)
-------
TABLE E-8. Continued
SAMPLING SAMPLE
LOCATION TYPE
GOLDFIELD NV -
FRAYNE RANCH 10
LAS VEGAS NV -
HEIN HETTINGA DRY (LDS) 12
LATHROP WELLS NV -
JOHN DEER RANCH 10
LOGANDALE NV -
KNUDSEN DAIRY 12
LUND NV -
MCKENZIE DAIRY 12
MCGILL NV -
LARSEN RANCH 13
MESQUITE NV -
SF AND K DAIRY 12
NO. OF
SAMPLES
7
2
2
2
11
5
5
5
7
2
2
2
12
5
5
5
12
4
4
4
11
5
4
4
12
5
5
5
RAD 10-
NUCLIDE
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
RADIOACTIVITY CONC.
(PCI/L)
MAX
2.1
260
-1.7
2.4
2.0
550
0.48
1.2
2.3
130
2.5
0.86
1.8
210
0.94
1.1
1.8
340
-0.21
0.76
1.9
450
0.92
1.0
1.7
280
0.58
1.6
MIN
1.7
200
-1.8
1.6
0.49
140
-5.6
0.024
1.7
-43
-5.4
0.46
0.44
7.6
-8.2
0.24
0.45
-72
-1.1
0.49
1.0
240
-3.9
-0.27
0.41
120
-2.9
0.67
AVG
2.0
230
-1.7
2.0
1.5
280
-1.2
0.54
2.0
44
-1.4
0.66
1.4
130
-1.6
0.60
1.4
130
-0.72
0.61
1.5
360
-0.71
0.18
1.5
200
-0.96
1.0
(continued)
E-47
-------
TABLE E-8. Continued
CAMDI T MG
OHI'lr Li INu
LOCATION
RADIOACTIVITY CONC.
(PCI/L)
cAMpiC Nin OF RAHTO- .
TYPE SAMPLES NUCLIDE MAX MIN AVG
MOAPA NV -
ROCKVIEW DAIRIES, INC 12
NYALA NV -
SHARP'S RANCH 13
CALIENTE NV -
JUNE COX RANCH 10
ROUND MT NV -
BERG'S RANCH 13
SHOSHONE NV -
HARBECKE RANCH 13
RACHEL NV -
JAMES MOODY 13
RACHEL NV -
PENOYER FARM 13
CRIS CASTLETON
12
5
5
5
12
3
4
4
11
5
6
6
7
2
2
2
12
3
4
4
11
3
4
4
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
K
3H
89SR
90SR
1.7
190
2.1
1.3
2.0
340
0.73
1.3
2.2
350
0.67
0.91
1.7
180
1.5
1.9
1.8.
660
1.6
2.0
1.4
-57
2.0
130
0.13
1.2
0.43
-77
-4.8
-0.054
0.41
-10
-3.9
0.62
0.48
-52
-1.0
-0.36
1.2
160
-0.29
1.4
0.42
94
0.043
0.78
1.4
-57
1.3
53
-2.4
0.19
1.4
52
-0.71
0.61
1.5
150
-0.70
0.96
1.4'
140
-0.22
0.35
1.5
170
0.59
1.6
1.4
300
0.85
1.2
1.4
-57
1.6
87
-0.54
0.56
(continued)
E-48
-------
TABLE E-8. Continued
SAMPLING
LOCATION
SAMPLE
TYPE
NO. OF
SAMPLES
RAD 10-
NUCLIDE
RADIOACTIVITY CONC.
(PCI/L)
MAX
MIN
AVG
CEDAR CITY UT -
BRENT JONES DAIRY
13
CEDAR CITY UT -
WESTERN GEN DAIRIES
12
ST GEORGE UT -
GENTRY DAIRY
12
3
1
2
2
9
2
2
2
10
3
4
4
K
3H
89SR
90SR
K
3H
89SR
90SR
K
3H
89SR
90SR
1.8
91
4.7
0.91
1.7
220
2.3
0.96
1.8
210
0.97
0.64
1.4
91
0.49
-0.98
0.48
36
-1.8
0.84
0.37
-120
-1.3
-0.19
1.7
91
2.6
-0.03
1.4
130
0.27
0.90
1.5
51
0.07
0.15
ST GEORGE UT -
TRUMAN CANNON
13
K
3H
89SR
90SR
1.7
340
-1.3
0.97
1.5
340-
-1.3
0.97
1.6
340
-1.3
0.97
E-49
-------
TABLE E-9. ANALYTICAL RESULTS FOR THE STANDBY MILK SURVEILLANCE NETWORK
1986
SAMPLING LOCATION
COLLECTION CONG. ± 2 SIGMA
DATE 3H 89SR 90SR
1986 (PCI/L) (PCI/L) (PCI/L)
TAYLOR AZ
SUNRISE DAIRY
GAMMA SPECTROMETRY AND RADIOCHEMICAL ANALYSES
08/11 190 ± 280* -1.0 ± 1.5*
TUCSON AZ
SHAMROCK DAIRY (PIMA CO 08/11 180 ± 270* 0.58 ± 0.98*
FAYETTEVILLE AR
UNIVERSITY OF ARK
RUSSELLVILLE AR
ARKANSAS TECH UNIV
BAKERSFIELD CA
CARNATION DAIRY
MODESTO CA
FOSTER FARMS DAIRY
WEED CA
MEDO-BEL CREAMERY
08/18 300 ± 270*
NA
08/18 160 ± 280* -1.5 ± 1.1*
08/12 NA
08/19 240 ± 280*
0.24 ± 0.94*
NA
08/11 230 ± 270* 1.3 ± 1.3*
WILLOWS CA
FOREMOST FOODS COMPANY 08/11 350 ± 290* -1.1 ± 1.1*
COLORADO SPGS CO
SINTON DAIRY CO
FT COLLINS CO
POUDRE VALLEY DAIRY
GRAND JCT CO
COLORADO WEST DAIRIES
PUEBLO CO
HYDE PARK DAIRY CO
BURLINGTON IA
MISS VALLEY MILK PRO
07/22 380 ± 280*
07/22 350 ± 260*
07/24
07/30
NA
NA
07/29 290 ± 260*
NA
NA
0.98 ± 1.2*
4.3 ± 12*
-11 ± 1*
DAVENPORT IA
SWISS VALLEY FARMS CO 07/28 110 ± 260* 0.63 ± 1.8*
0.89 ± 0.97*
0.18 ± 0.66*
NA
2.3 ± 1.6*
0.59 ± 0.60*
NA
0.55 ± 0.52*
0.83 ± 0.66*
NA
NA
0.33 ± 0.58*
0.11 ± 1.2*
3.7 ± 2.2
1.8 ± 1.1
E-50
-------
TABLE E-9. Continued
SAMPLING LOCATION
GAMMA
GARDEN CITY KS
MYERS MILK PROD
COLLECTION
DATE
1986
SPECTROMETRY
07/24
07/28
MANHATTAN KS
KANSAS STATE UNIVERSITY 08/04
BATON ROUGE LA
LA STATE UNIV
LAFAYETTE LA
UNIV SOUTHWESTERN LA
MONROE LA
BORDEN'S
RUSTON LA
TECH UNIV DAIRY
FOSSTON MN
LAND 0' LAKES INC
ROCHESTER MN
ASSC MILK PRODUCERS
AURORA MO
MID-AMERICA DAIRY INC
CHILLICOTHE MO
MID-AMERICA DAIRYMEN
BOZEMAN MT
DARIGOLD FARMS
HAVRE MT
VITA-RICH DAIRY
NORFOLK NE
GILLETTE DAIRY
08/18
08/18
08/18
08/18
07/30
07/28
07/28
07/22
07/24
07/21
07/28
07/31
CONC. ± 2 SIGMA
3H 89SR 90SR
(PCI/L) (PCI/L) (PCI/L)
AND RADIOCHEMICAL ANALYSES
130 ±
180 ±
170 ±
100 ±
84 ±
140 ±
110 ±
260 ±
NA
220 ±
250 ±
300 ±
170 ±
NA
270*
280*
270*
270*
270*
270*
SAMPLE
270*
270*
290*
270*
280*
270*
1.5 ± 1.4*
NA
0.33 ± 2.1*
0.18 ± 1.2*
NA
NA
DESTROYED IN
-1.6 ± 1.3*
2.5 ± 2.5*
-0.43 ± 1.5*
3.3 ± 2.6*
NA
2.1 ± 1.5*
-0.53 ± 1.8*
-0.70 ± 1.1*
1.5 ±
NA
1.7 ±
NA
NA
NA
MAIL
3.4 ±
1.5 ±
2.6 ±
2.0 ±
NA
1.4 ±
3.3 ±
2.5 ±
0.8
1.2*
0.8
0.8
1.0
0.7
1.5*
1.0
0.7
(continued)
E-51
-------
TABLE E-9. Continued
/>
U
SAMPLING LOCATION
OLLECTION
DATE
1986
GAMMA SPECTROMETRY
OMAHA NE
ROBERTS DAIRY-MARSHALL
LAS VEGAS NV
ANDERSON DAIRY
RENO NV
MODEL DAIRY
ALBUQUERQUE NM
BORDEN'S VALLEY GOLD
LA PLATA NM
ROTHLISBERGER DAIRY
DEVILS LAKE ND
LAKE VIEW DAIRY
FARGO ND
CASSCLAY CREAMERY
CLAREMORE OK
SWAN BROS DAIRY
ENID OK
AMPI GOLDSPOT DIVISION
MCALESTER OK
OK STATE PENITENTIARY
STILLWATER OK
OSU DAIRY
CORVALLIS OR
SUNNY BROOK DAIRY
MEDFORD OR
DAIRYGOLD FARMS
TILLAMOOK OR
TILLAMOOK CO CRMY
07/29
08/11
08/11
08/18
08/19
08/18
08/05
08/18
08/25
08/19
08/18
08/25
08/26
08/25
3H
(PCI/L)
CONC. ± 2 SIGMA
89SR
(PCI/L)
90SR
(PCI/L)
AND RADIOCHEMICAL ANALYSES
180 ± 270*
410 ± 240
430 ± 250
310 ± 290*
530 ± 250
280 ± 280*
210 ± 270*
130 ± 280*
170 ± 270*
46 ± 290*
330 ± 280*
140 ± 300*
89 ± 270*
130 ± 260*
NA
NA
NA
0.29 ± 1.4*
0.46 ± 0.86*
NA
NA
NA
0.0049 ± 0.79*
-0.83 ± 0.89*
NA
-0.47 ± 0.74*
NA
0.97 ± 1.6*
NA
NA
NA
1.1 ± 0.9*
0.74 ± 0.60*
NA
NA
NA
1.9 ± 0.7
1.7 ± 0.7
NA
1.3 ± 0.6
NA
1.4 ± 0.6
(continued)
E-52
-------
TABLE E-9. Continued
SAMPLING LOCATION
COLLECTION CONC. ± 2 SIGMA
DATE 3H 89SR 90SR
1986 (PCI/L) (PCI/L) (PCI/L)
BEAVER UT
CACHE VALLEY DAIRY
GAMMA SPECTROMETRY AND RADIOCHEMICAL ANALYSES
07/18 160 ± 270* NA
PROVO UT
BYU DAIRY PRODUCTS LAB 07/21 360 ± 260* 0.46 ± 1.9*
CEDAR CITY UT
WESTERN GEN DAIRIES 07/29
NA
0.43 ± 1.2*
SEATTLE WA
CONSOLIDATED DAIRY PROD 08/25(1) 220 ± 270* -0.033 ± 1.4*
SPOKANE WA
CONSOLIDATED DAIRY
LARAMIE WY
UNIV OF WYO (DAIRY)
RIVERTON WY
ALBERTSON'S PLANT
08/25 230 ± 280* -0.22 ± 0.98*
08/01 350 ± 260* NA
07/30 240 ± 270* NA
NA
1.3 ± 0.9*
0.83 ± 0.66*
1.1 ± 0.8*
1.2 ± 0.8
NA
NA
COLLECTION
DATE
SAMPLING LOCATION 1986
GAMMA SPECTRAL
PIMA AZ
SMITH HUNT DAIRY 08/11
YUMA AZ
GOLDEN WEST DAIRY 08/11
LITTLE ROCK AR
BORDENS 08/18
FRESNO CA
STATE UNIV CREAMERY 08/14
COLLECTION
DATE
SAMPLING LOCATION 1986
ANALYSES ONLY**
MANTECA CA
DEJAGER DAIRY NO 2 NORTH
REDDING CA
MCCOLL'S DAIRY PROD
SAN LUIS OBISPO CA
CAL STATE POLY
SEBASTOPOL CA
WM MILLER DAIRY
(conti
08/11
08/11
08/12
08/11
nued)
E-53
-------
TABLE E-9. Continued
COLLECTION
DATE
SAMPLING LOCATION 1986
COLLECTION
DATE
SAMPLING LOCATION 1986
GAMMA SPECTRAL ANALYSES ONLY**
SMITH RIVER CA
COUNTRY MAID DAIRY
TRACY CA
DEUEL VOC INST
WILLITS CA
RIDGEWOOD RANCH DAIRY
DELTA CO
ARDEN MEADOW GOLD DAIRY
LAKE MILLS IA
LAKE MILLS COOP CRMY
LEMARS IA
WELLS DAIRY
DALTON MN
DALTON CO-OP CREAMERY
FLENSBURG MN
FLENSBURG CO-OP CMRY
NICOLLET MN
WALTER SCHULTZ FARM
JACKSON MO
MID-AMERICA DAIRYMEN IN
JEFFERSON CITY MO
CENTRAL DAIRY CO
BILLINGS MT
MEADOW GOLD DAIRY
08/12
08/11
08/13
08/04
07/30
07/29
08/06
08/08 (2)
08/15
07/29
07/22
07/28
GREAT FALLS MT
MEADOW GOLD DAIRY
MISSOULA MT
BEATRICE DAIRY PRODUCTS
GERING NE
4-STATES DAIRY-D SCHILL
GD ISLAND NE
MID-AMER DAIRYMN-JIM SA
SUPERIOR NE
MID-AMER DAIRYMN-D FRIT
FALLON NV
CREAMLAND DAIRY
YERINGTON NV
VALLEY DAIRY
EUGENE OR
ECHO SPRINGS DAIRY
GRANTS PASS OR
VALLEY OF ROGUE DAIRY
KLAMATH FALLS OR
NEDO BEL CREAMERY
MILTON-FREEWATER OR
PARENTS DAIRY
MYRTLE POINT OR
SAFEWAY STORES INC
07/23
07/29
07/31
07/30
07/29
08/11
08/10
08/25
08/25
08/25
08/25
08/25
E-54
(continued)
-------
SAMPLING LOCATION
TABLE E-9. Continued
COLLECTION
DATE
1986
SAMPLING LOCATION
COLLECTION
DATE
1986
GAMMA SPECTRAL ANALYSES ONLY**
REDMOND OR
EBERHARD'S CREAMERY INC
NORTH OGDEN UT
WESTERN GENERAL DAIRY
SMITHFIELD UT
CACHE VALLEY DAIRY
08/26
07/17
07/17, 07/21
MOSES LAKE WA
SAFEWAY STORES INC
CHEYENNE WY
DAIRY GOLD FOODS
08/25
08/06
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
** POTASSIUM-40 WAS THE ONLY GAMMA EMITTER DETECTED EXCEPT FOR THE TWO SAMPLES
LISTED BELOW.
NOTES
ANALYSIS RESULT 2SIGMA UNITS
(1) 137CS 13 7 PCI/L
(2) 137CS 31 13 PCI/L
SAMPLING LOCATION
Seattle, WA
Flensburg, MN
E-55
-------
TABLE E-10. SUMMARY OF RADIATION DOSE EQUIVALENTS FROM TLD DATA - 1986
STATION
LOCATION
Alamo, NV
American Borate, NV
Atlanta Mine, NV
Austin, NV
Baker, CA
Barstow, CA
Battle Mountain, NV
Beatty, NV
Bishop, CA
Blue Eagle Ranch, NV
Blue Jay, NV
Boulder, UT
Bryce Canyon, UT
Cactus Springs, NV
Caliente, NV
Carp, NV
Cedar City, UT
Cherry Creek, NV
Clark Station, NV
Coaldale, NV
Colorado City, AZ
MEASUREMENT PERIOD
ISSUE
11/07/85
11/07/85
12/09/85
01/08/86
12/13/85
12/12/85
12/11/85
11/07/85
12/11/85
12/10/85
01/15/86
12/10/85
12/10/85
11/04/85
11/06/85
11/06/85
11/05/85
12/10/85
01/13/86
12/11/85
11/05/85
COLLECT
11/06/86
11/06/86
12/01/86
01/15/87
12/01/86
12/01/86
12/03/86
11/04/86
12/02/86
12/02/86
01/15/87
12/09/86
12/09/86
11/03/86
11/06/86
11/06/86
11/05/86
12/02/86
01/14/87
12/04/86
11/04/86
DOSE
EQUIVALENT
(MREM/D)
MAX.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
25
27
24
40
23
27
23
29
28
19
32
25
23
17
29
30
20
30
30
29
19
MIN.
0.
22
0.^3
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.'
0.
20
31
19
23
19
25
25
16
29
22
21
14
26.
27
19
0.25
0.
0.
o:
28
24
12
RATE
AVG.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
24
26
22
36
21
25
21
27
26
17
31
23
22
16
27
28
19
27
29
27
17
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
88
95
80
131
77
91
77
99
95
62
113
84
8Q
58
99
102
69
99
106
99
62
(continued)
E-56
-------
TABLE E-10. Continued
STATION
LOCATION
Complex 1, NV
Corn Creek, NV
Cortez Rd./HWY 278, NV
Coyote Summit, NV
Crescent Valley, NV
Crystal , NV
Currant, NV
Currie, NV
Death Valley JCT. , CA
Delta, UT
Diablo Maint. Sta. , NV
Duchesne, UT
Duckwater, NV
Elgin, NV
Elko, NV
Ely, NV
Enterprise, UT
Eureka, NV
Fall on, NV
Perron, UT
Flying Diamond CP, NV
MEASUREMENT PERIOD
ISSUE
12/10/85
11/08/85
12/11/85
01/13/86
12/11/85
11/08/85
12/11/85
12/10/85
11/07/85
01/13/86
01/13/86
01/15/86
12/11/85
11/06/85
12/10/85
12/11/85
11/05/85
01/07/86
12/11/85
11/06/85
12/12/85
COLLECT
12/03/86
11/03/86
12/03/86
01/12/87
12/03/86
11/06/86
12/02/86
12/02/86
11/06/86
01/08/87
01/13/87
01/06/87
12/02/86
11/06/86
12/02/86
12/02/86
11/05/86
01/15/87
12/03/86
11/06/86
12/04/86
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
31
12
31
32
24
19
29
31
20
21
33
20
27
35
25
23
34
31
22
20
23
MIN.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
27
10
27
30
20
17
25
26
17
18
30
18
23
24
19
20
30
24
18
.13
19
AVG.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
29
11
28
31
22
18
26
28
19
19
32
19
25
30
22
21
32
28
20
,18
,21
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
106
40
102
113
80
66
95
102
69
69
117
69
91
110
80
77
117
102
73
66
77
(continued)
E-57
-------
TABLE E-10. Continued
STATION
LOCATION
Furnace Creek, CA
Gabbs, NV
Garrison, UT
Geyser Ranch, NV
Goldfield, NV
Grantsville, UT
Green River, UT
Groom Lake-NTS, NV
Gunnison, UT
Hancock Summit, NV
Hiko, NV
Hot Ck. Ranch, NV
Ibapah, UT
Independence, CA
Indian Springs, NV
Jacob's Lake, AZ
Kanab, UT
Kirkeby Ranch, NV
Koyens Ranch, NV
Las Vegas (Airport) , NV
Las Vegas (Placak), NV
MEASUREMENT PERIOD
ISSUE
11/06/85
12/11/85
12/09/85
12/09/85
01/06/86
01/14/86
11/05/85
01/07/86
11/06/85
01/13/86
11/07/85
01/15/86
12/09/85
12/11/85
11/04/85
11/04/85
11/04/85
12/09/85
01/15/86
12/31/85
12/31/85
COLLECT
11/06/86
12/04/86
12/01/86
12/01/86
01/12/87
01/08/87
11/06/86
01/12/87
11/06/86
01/12/87
11/06/86
01/15/87
12/01/86
12/02/86
11/03/86
11/04/86
11/04/86
12/01/86
01/13/87
12/31/86
12/31/86
DOSE
EQUIVALENT
(MREM/D)
MAX.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
17
21
21
28
26
21
21
20
20
39
22
24
32
24
14
29
18
22
24
15
15
MIN.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
13
17
18
24
20
18
13
17
12
35
18
22
25
22
0.12
0.
0.
0.
0.
0.
0.
17
12
19
22
13
12
RATE
AVG.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
16
19
19
26
24
19
18
18
17
37
20
23
28
23
13
25
16
20
23
14
14
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
58
69
69
95
88
69
66
66
62
135
73
' 84
102
84
47
91
58
73
84
51
51
(continued)
E-58
-------
TABLE E-10. Continued
STATION
LOCATION
Las Vegas (UNLV) , NV
Las Vegas (USDI), NV .
Lathrop Wells, NV
Lavada's Market, NV
Li da, NV
Loa, UT
Logan, UT
Lone Pine, CA
Lovelock, NV
Lund, NV
Lund, UT
Mammoth Lakes, CA (1)
Manhattan, NV
Mesquite, NV
Milford, UT
Mina, NV
Moapa, NV
Monti cello, UT
Mtn. Meadows
Ranch, NV (2)
Nash Ranch, NV
Nephi , UT
MEASUREMENT PERIOD
ISSUE
12/31/35
12/31/85
11/04/85
11/08/85
01/07/86
12/10/85
01/06/86
12/11/85
12/11/85
12/10/85
12/11/85
12/11/85
01/08/86
11/04/85
12/09/85
12/11/85
11/04/85
11/05/85
01/15/86
12/12/85
01/13/86
COLLECT
12/31/86
12/31/86
11/03/86
11/07/86
01/14/87
12/09/86
01/06/87
12/02/86
12/03/86
12/02/86
12/01/86
12/02/86
01/15/87
11/04/86
12/01/86
12/04/86
11/04/86
11/05/86
01/14/87
12/04/36
01/05/87
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
12
17
24
24
29
35
21
23
22
24
32
31
40
18
27
28
20
26
20
24
20
MIN.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
10
15
21
19
22
32
16
18
18
19
26
23
32
15
22
22
17
18
18
21
17
AVG.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
11
16
23
21
26
33
19
21
20
22
28
28
36
16
24
25
18
23
19
22
.18
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
40
58
84
77
95
120
69
77
73
80
102
102
131
58
38
91
66
84
69
80
66
(continued)
E-59
-------
TABLE E-10. Continued
STATION
LOCATION
Nyala, NV
Olancha, NV ^
Overton, NV
Page, AZ
Pahrump, NV
Parowan, UT
Penoyer Farms , NV
Pine Creek Ranch, NV
Pioche, NV
Price, UT
Provo, UT
Queen City Smt. , NV
Rachel , NV
Reed Ranch, NV
Ridgecrest, CA
Rose Ranch, *NV
Round Mt., NV
Ruby Valley, NV
S. Desert Cor. Ctr. , NV
Salt Lake City, UT
Schurz, NV
MEASUREMENT PERIOD
ISSUE
01/15/86
12/12/85
11/04/85
11/05/85
11/07/85
12/10/85
01/13/86
12/10/85
12/09/85
01/16/86
01/14/86
01/13/86
01/15/86
01/13/86
12/12/85
12/09/85
01/08/86
12/10/85
11/08/85
11/08/85
12/11/85
COLLECT
01/14/87
12/01/86
11/04/86
11/05/86
11/06/86
12/02/86
01/15/87
12/03/86
12/04/86
01/06/87
01/06/87
01/13/87
01/12/87
01/13/87
12/01/86
12/01/86
01/15/87
12/02/86
11/03/86
11/06/86
12/04/86
DOSE
EQUIVALENT
(MREM/D)
MAX.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0 =
0.
0.
0.
0.
0.
0.
0.
0.
23
24
17
18
14
23
31
33
24
21
21
35
30
30
23
32
35
32
14
29
28
MIN.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
21
21
13
10
11
19
27
29
20
18
17
31
27
27
18
26
28
25
10
25
25
RATE
AVG.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
22
23
15
16
13
21
29
31
22
19
19
34
28
29
20
29
32
28
13
26
27
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
80
84
55
58
47
77
106
113
80
69
69
124
102
106
73
106
117
102
47
95
99
(continued)
E-60
-------
TABLE E-10. Continued
STATION
LOCATION
Scotty's OCT., NV
Sheri 's Ranch, NV
Shoshone, CA
Springdale, NV
St. George, UT
Stone Cabin Ranch, NV
Sunnyside, NV
Tempiute, NV
Tikaboo Valley, NV
Tonopah Test Rng. , NV
Tonopha, NV
Trout Creek, UT
Twin Springs Ranch, NV
Uhalde's Ranch, NV (3)
US Ecology, NV
Valley Crast, CA
Vernal , UT
Vernon, UT
Warm Springs, NV
Wells, NV
Wendover, UT
MEASUREMENT PERIOD
ISSUE
01/06/86
11/07/85
11/07/85
11/06/85
11/05/85
01/14/86
12/12/85
01/15/86
01/13/86
01/07/86
01/07/86
12/09/85
01/14/86
12/10/85
11/07/85
11/07/85
01/15/86
01/14/86
01/13/86
12/10/85
12/09/85
COLLECT
01/12/87
11/07/86
11/06/86
11/05/86
11/05/86
01/14/87
12/04/86
01/13/87
01/12/87
01/14/87
01/15/87
12/01/86
01/14/87
12/03/86
11/07/86
11/06/86
01/06/87
01/08/87
01/14/87
12/02/86
12/01/86
DOSE
EQUIVALENT RATE
(MREM/0)
MAX.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
31
28
20
30
17
31
17
30
29
30
35
24
31
32
30
24
23
23
36
25
21
MIN.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
23
23
15
26
14
26
14
27
25
24
30
21
28
25
26
13
19
20
32
22
,16
AVG.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
29
25
18
28
15
29
15
28
27
28
32
22
29
28
29
17
21
21
34
23
0.19
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
106
91
66
102
55
106
55
102
99
102
117
80
106
102
106
62
77
77
124
84
69
(continued)
E-61
-------
TABLE E-10. Continued
STATION
LOCATION
DOSE
EQUIVALENT RATE
MEASUREMENT PERIOD (MREM/D)
ISSUE
COLLECT MAX. MIN. AVG.
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
Willow Springs
Lodge, UT
Winnemucca, NV
Young's Ranch, NV
Footnotes
(1) Previously called Mammoth Mtn., CA
(2) Previously called Casey's Ranch, NV
(3) Previously called Adaven, NV
01/14/86 01/08/87 0.20 0.17 0.18
12/11/85 12/03/86 0.24 0.20 0.22
01/08/36 01/15/87 0.33 0.22 0.27
66
80
99
E-62
-------
TABLE E-ll. SUMMARY OF RADIATION DOSES FOR OFFSITE RESIDENTS - 1986
Background
RESIDENT Station
NO. Location
2
3
6
7
8
9
10
11
13
14
15
18
19
21
22
24
25
29
33
34
Call ante, NV
Blue Jay, NV
Indian Springs, NV
Goldfield, NV
Twin Springs
Ranch, NV
Blue Eagle
Ranch, NV
Complex 1, NV
Complex 1, NV
Koyens Ranch, NV
Tikaboo Valley, NV
Tikaboo Valley, NV
Nyala, NV
Goldfield, NV
Beatty, NV
Alamo, NV
Corn Creek, NV
Corn Creek, NV
Stone Cabin
Ranch, NV
Lathrop Wells, NV
Furnace Creek, CA
Measure-
ment
Issue
01/08/86
08/07/36
01/17/86
01/06/86
01/14/86
01/07/86
01/08/86
01/08/86
01/15/86
01/13/86
01/13/86
01/15/86
01/06/86
01/16/86
01/08/86
12/31/85
12/31/85
01/14/86
01/15/86
01/14/86
Period
Collect
01/13/87
01/15/87
01/07/87
01/12/87
01/12/87
01/06/87
01/07/87
01/07/87
01/12/87
01/12/87
01/12/87
01/12/37
01/12/87
01/06/87
01/14/87
09/02/86
12/31/86
01/12/87
01/09/87
01/08/87
Dose
Equivalent Rate
(MREM/D)
i
Max.
0.31
0.27
0.17
0.24
0.28
0.19
0.29
0.30
0.20
0.24
0.23
0.23
0.24
0.26
0.20
0.14
0.16
0.34
0.24
0.20
Min.
0.27
0.20
0.15
0.20
0.25
0.16
0.27
0.27
0.10
0.18
0.20
0.17
0.19
0.23
0.17
0.11
0.14
0.23
0.22
0.17
Avg.
0.30
0.23
0.16
0.22
0.26
0.17
0.28
0.29
0.16
0.21
0.22
0.19
0.21
0.25
0.19
0.13
0.15
0.27
0.23
0.18
Net
Exposure
(MREM)
2.6
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
6.6
0.0
0.0
3.6
(continued)
E-63
-------
TABLE E-ll. (Continued)
Resident
No.
36
37
38
40
42
44
45
47
49
51
52
54
55
56
57
60
223
232
233
Background
Station
Location
Pahrump, NV
Indian Springs, NV
Beatty, NV
Goldfield, NV
Tonopah, NV
Cedar City, UT
St. George, UT
Ely, NV
Las Vegas
(UNLV), NV
Tonapah, NV
Salt Lake City, UT
Rachel , NV
Rachel , NV
Corn Creek, NV
Overton, NV
Shoshone, CA
Corn Creek, NV
Hiko, NV
Ely, NV
Measure-
ment
Issue
01/15/86
01/17/86
01/16/86
01/06/86
01/07/86
01/07/86
01/06/86
01/07/86
12/31/85
01/08/86
01/03/86
01/15/86
01/15/86
12/31/85
01/06/86
01/14/86
12/31/85
01/08/86
01/06/86
Period
Collect
01/07/87
01/07/87
01/06/87
01/12/87
01/13/87
01/13/87
01/13/87
01/06/87
12/31/86
01/12/87
01/06/87
01/13/87
01/13/87
12/31/86
01/12/87
01/07/87
12/31/86
01/14/87
01/06/87
Dose
Equivalent
(MREM/D)
Max.
0.17
0.18
0.33
0.25
0.27
0.24
0.18
0.23
0.21
0.33
0.25
0.26
0.26
0.21
0.22
0.20
0.16
0.24
0.21
Min.'
0.13
0.14
0.30
0.20
0.24
0.21
0.14
0.19
0.19
0.30
0.24
0.18
0.22
0.14
0.15
0.18
0.11
0.21
0.19
Rate
Avg.
0.14
0.16
0.32
0.22 '
0.26
0.23
0.16
0.22
0.19
0.32
0.24
0.23
0.25
0.17
0.19
0.19
0.13
0.23
0.20
Net
Exposure
(MREM)
0.0
0.0
3.5
0.0
0.0
11.9
8.9
0.0
28.1
0.0
0.0
0.0
0.0
17.4
12.7
0.0
3.9
11.1
0.0
E-64
(continued)
-------
TABLE E-ll. (Continued)
Resident
No.
239
247
248
249
258
263
264
275
280
281
283
292
293
295
Background
Station
Location
Hot Creek
Ranch, NV
Caliente, NV
Penoyer Farms, NV
Austin, NV
Pioche, NV
Death Valley
Jet. , CA
Rachel , NV
Corn Creek, NV
Pine Creek
Ranch, NV
Currant, NV
Pioche, NV
Death Valley
Jet., CA
Pioche, NV
Currant, NV
Measure-
ment
Issue
01/15/86
01/08/86
01/13/86
01/08/86
01/06/86
01/14/86
01/15/86
01/31/86
06/03/86
06/10/86
08/27/86
10/21/86
12/01/86
12/02/86
Period
Collect
07/02/87
10/07/86
01/13/87
01/15/87
07/28/86
08/06/86
01/13/87
04/01/86
\
01/07/87
12/02/86
11/24/86
01/09/87
01/05/87
01/06/87
Dose
Equi val ent
(MREM/D)
Max.
0.27
0.20
0.27
0.27
0.24
0.21
0.28
0.15
0.29
0.21
0.20
0.20
0.21
0.20
Min.
0.25
0.18
0.21
0.21
0.21
0.15
0.24
0.15
0.21
0.11
0.20
0.20
0.21
0,20
Rate
Avg.
0.26
0.19
0.23
0.24
0.23
0.18
0.26
0.15
0.26
0.18
0.20
0.20
0.21
0.20
Net
Exposure
(MREM)
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
5.4
0.0
0.0
0.0
0.0
0.0
E-65
-------
TABLE E-12. NOBLE GAS SAMPLES CONTAINING DETECTABLE CONCENTRATIONS
OF XENON-133
SAMPLING LOCATION
SHOSHONE CA
ALAMO NV
AUSTIN NV
BEATTY NV
DIABLO NV-1MI TWO REED RA
ELY NV
GOLDFIELD NV
GROOM LAKE NV
HIKO NV
INDIAN SPRINGS NV
LAS VEGAS NV
LATHROP WELLS NV
OVERTON NV
PAHRUMP NV
COLLECTION
DATE
1986
05/05-05/12
05/16-05/19
04/23-04/30
05/07-05/14
05/14-05/21
05/06-05/13
05/13-05/20
05/05-05/12
05/12-05/19
04/22-04/23
05/06-05/13
05/13-05/20
05/05-05/12
05/12-05/19
04/25-04/26
0(4/ 29-04/30
05/09-05/16
04/25-04/26
04/28-04/30
05/05-05/12
05/12-05/19
05/06-05/13
05/13-05/20
03/24-03/31
05/05-05/12
05/12-05/19
05/06-05/13
05/15-05/20
05/15-05/19
05/19-05/27
CONC. ± 2 SIGMA
(PCI/M3)
24 ± 6
29 ± 5
30 ± 5
40 ± 5
18 ± 6
54 ± 11
25 ± 9
39 ± 11
52 ± 20
64 ± 10
36 ± 7
30 ± 8
45 ± 7
31 ± 10
330 ± 10
730 ± 15
52 ± 9
220 ± 7
92 ± 20
43 ± 6
37 ± 8
67 ± 11
25 + 8
84 ± 7
37 ± 15
37 ± 9
31 ± 9
21 ± 7
24 ± 4
12 ± 6
PCT OF
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
0.07
0.01
0.01
0.04
0.02
<0.01
<0.01
0.01
<0.01
0.02
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
Continued
E-66
-------
TABLE E-12. Continued
SAMPLING LOCATION
PIOCHE NV
RACHEL NV
ROBINSON TRAILER PARK
PENOYER FARM CRIS CASTL
MEDLIN RANCH
TONOPAH NV
FALLINI'S (TWIN SPGS) RAN
CEDAR CITY UT
CONCENTRATION IS LESS THAN
COLLECTION
DATE
1986
05/22-05/27
04/23-04/30
04/30-05/07
05/07-05/14
05/14-05/21
05/21-05/29
04/22-04/23
04/28-04/30
04/30-05/05
04/25-04/26
04/28-04/30
05/05-05/12
05/12-05/19
04/30-05/05
05/13-05/20
CONC. ± 2 SIGMA
(PCI/M3)
9.4 ± 5.4
29 ± 5
20 ± 6
45 ± 6
17 ± 7
9o6 ± 5.8
18 ± 5
160 ± 7
29 ± 7
430 ± 15
94 ± 6
57 ± 15
35 ± 9
92 ± 9
33 ± 12
THE MINIMUM DETECTABLE CONCENTRATION
PCT OF
CONC.
GUIDE
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.03
<0.01
0.09
0.02
0.01
<0.01
0.02
<0.01
(MDC).
E-67
-------
ADDENDUM 1
NONRADIOLOGICAL SUPPLEMENT TO THE NTS ENVIRONMENTAL MONITORING REPORT
Prepared by:
Industrial Hygiene
Reynolds Electrical and Engineering Co., Inc.
Report Period:
Calendar Year 1986
INTRODUCTION:
Environmental compliance activities which are the subject of this report are
regulated under Chapter 445 of the State of Nevada Administrative Codes.
Chapters 445.131, 445.361, and 445.401 respectively address water pollution
control, public water systems, and air pollution. There were a total of 23
facilities which had State of Nevada operating permits or approval in 1986.
For common information including site description, geology, land use, etc.,
reference the EPA Annual Report.
SUMMARY:
Water Pollution
No effluent monitoring is required.
Air Pollution
There was no State inspection in CY86 of the 23 facilities which had operating
permits or registration certificates. A State inspection conducted January
14 and 15, 1987, found no violations for permitted facilities operating in
CY86.
No effluent monitoring is required and none was performed. The allowable
emissions are established by State-determined operating constraints which were
not exceeded,
Ground-water Monitoring
Composite quarterly samples were taken from two wells to monitor changes in
nitrate concentration.
Add-1
-------
MONITORING DATA COLLECTION, ANALYSIS, AND EVALUATION:
Air Pollution Control
a. Area 1 Shaker Plant - Operating restrictions to Permits 922 and 923 were
not violated during this period. The facilities were not operated in excess
of the allowable hours and an annual production report was transmitted to
the State by April 15, 1987.
b. Area 12 Concrete Batch Plant - The plant did not exceed the permit restric-
tion of 8 hours per day, nor more than 296 hours per year. An annual
report was transmitted to the State by April 15, 1987.
c. Area 3 Aggregate Plant - The restrictions to Operating Permit 919 were not
exceeded. The plant did not operate in excess of 8 hours per day. nor
more than 280 hours per year. An annual production report was submitted
to the State by April 15, 1987.
d. Area 1 Aggregate Plant - The restrictions to Operating Permit 1287 were not
exceeded. The plant did not operate in excess of 9 hours per day, nor more
than 1125 hours per year. An annual production report was be submitted by
April 15, 1987.
e. Area 5 Surface Area Disturbance - The restrictions to Permit 921 were not
exceeded. A final fugitive dust control plan will be submitted at least
six months prior to abandonment of the site.
f. Are-a 2 Stemming Systems - The restrictions to Operating Permits 957 and 958
were not exceeded.
g. NTS 4,000,000 BTU/hour or Greater Boiler Permits - The restrictions to
Permits 1035, 1036 and 925 were not exceeded. The boilers were not operated
in excess of 8,400 hours per year. All boilers used Number 2 fuel oil.
An annual analysis of fuel for sulfur and BTU content was submitted on
September 26, 1986.
h. Area 3 Portable Stemming System - The restrictions to Operating Permit
1089 were satisfied in the annual report sent to the State by April 15,
1987.
i. Area 1 Concrete Batch Plant - The plant did not exceed Operating Permit
1082 restriction of 500 operating hours per year.
j. low Portable Crusher - The crusher did not exceed Operating Permit 1217
restriction of not operating in excess of 8 hours per day nor more than 650
hours at any one location.
Ground-Water Monitoring
Monthly ground water samples were collected from Wells Ue5C and Ue5B and com-
posited into calendar year quarterly samples to monitor changes in nitrate
concentration. The CY86 fourth quarter result from Well Ue5B was 67.0
Add-2
-------
milligrams of nitrates per liter (mg/1) and the sample from Well Ue5C was 75.9
mg/1.
Add-3
-------
ADDENDUM 2
Part A
ENVIRONMENTAL PERMITS, ORDERS, AND NOTICES
Part A of this Addendum pertains to EG&G activities at the locations shown.
EG&G Operations
Santa Barbara
Operation
(Robin Hill
Facility)
(The "226"
BuiIding)
Kirtland Oper.
(Craddock Fac.)
Los Alamos
Washington Aerial
Measurements
San Ramon Oper.
(San Ramon
Facility)
(Pleasanton
Faci1ity)
(San Ramon
Facility)
Woburn Oper.
Permit/Notification Issue
Type Date
Notification of Hazardous Feb. 1985
Waste Activity EPA ID
#CAD980813224
Industrial Waste Control 1973
Permit #11-202
Industrial Waste Control Jan. 1987
Permit (application)
Notification of Hazardous Dec. 1985
Waste Activity
EPA ID #NMD049986896
No Notifications or Permits
requi red
No Notifications or Permits
requi red
Notification of Hazardous May 1983
Waste Activity EPA ID
#CAD056196900
Wastewater Discharge Nov. 1985
Permit #3672-101
Wastewater Discharge Jan. 1985
Permit (no number)
Notification of Hazardous Jan. 1982
Waste Activity EPA ID
#MAD980578983
Wastewater Permit Oct. 1984
#43005732-0
Issuing
Agency
State of
Cali fornia
Goleta Sanitary
Dist. California
Goleta Sanitary
Dist. California
State of New
Mexico
State of
Cal i form'a
Dublin/San Ramon
Sanitary Dist.
Cal i form'a
Central Contra
Costa Sanitary
Dist. California
State of
Massachusetts
State of
Massachusetts
Add-4
-------
ADDENDUM 2
Part A (Continued)
EG&G Operations
Las Vegas Oper.
(North Las Vegas)
(Sunset &
Escondido)
Permit/Notification Issue
Type Date
Notification of Hazardous Aug. 1980
Waste Activity EPA ID
#NVD097868731
PCB Notification Feb. 1986
NVT-PCB-137
Extremely Hazardous Waste Jan. 1987
Disposal Permit #3-9886
Wastewater Contribution Aug. 1985
Permit #85-1
Industrial Wastewater March 1986
Permit CCSD-012
Air Pollution Control Operation*
Permits
A06501
A06502
A06504
A06505
A06503
A06506
A06507
A06509
A06510
A06511
A06512
A06503
A06504
*Renewed annually
Issuing
Agency
State of Nevada
State of Nevada
State of
California
City of North
Las Vegas
Clark County
Clark County
Nov.
Nov.
Aug.
Oct.
Nov.
May
May
May
May
May
Feb.
May
May
1981
1981
1976
1976
1981
1984
1984
1984
1984
1984
1985
1984
1984
Clark
Clark
Clark
Clark
Clark
Clark
Clark
Clark
Clark
Clark
Clark
Clark
Clark
County
County
County
County
County
County
County
County
County
County
County
County
County
Add-5
-------
ADDENDUM 2
Part B (Continued)
STATUS OF THE ENVIRONMENTALLY RELATED FACILITIES AT THE NTS,
ADMINISTERED THROUGH THE REYNOLDS ELECTRICAL CO., INC. (REECO)
CLEAN AIR ACT
The State of Nevada Air Quality Regulations require a registration certificate
before starting construction, modification, or alterations of an air contaminant
emission source. An operating permit is required before initial operation of
the emission source. A registration certificate or operating permit is required
before the surface disturbance of 20 acres or more accumulative total of land.
PERMIT
NO.
OP918
OP919
OP921
OP922
LOCATION/FACILITY
Area 6
Area 3 Protec
Aggregate Hopper
Area 5 Aggregate
Plant
Area 1 Shaker Plant
OP923 Area 1 Shaker PLant
OP925 Area 23, Bldg. 753
OP928 Area 12 Concrete
Batch Plant
OP957 Area 2 LLNL Port-
able Stemming
System
ISSUE
DATE
11/21/84
12/03/84
12/03/84
12/03/84
ITEM(S)
Concrete Batch
Plant
Bacon-Western
Dust Filters
Surface Dis-
turbance
Simp!icity
Screen
Pioneer Screen
Cedarapids Screen
Conveyors
Baghouse
Bins
CMI Rotary Dryer 12/03/84
Baghouse
Bins
Ajax Boiler #83- 12/03/84
35651
Ideal Mfg. Co. 12/03/84
EXPIRATION
DATE
11/29/89
12/03/89
12/03/89
12/03/89
12/03/89
12/03/89
12/03/89
PERMITTEE
F&S
DOE
DOE
DOE
Barber-Greene
Conveyor
Atlas Conveyors (s)
12/03/84 12/03/89
DOE
DOE
DOE
DOE
Add-6
-------
ADDENDUM 2
Part B (Continued;
CLEAN AIR ACT (Continued)
PERMIT
NO.
OP958
LOCATION/FACILITY ITEM(S)
ISSUE
DATE
EXPIRATION
DATE
Area 2 LLNL Porta-
ble Stemming System
Barber-Greene
Conveyor
Atlas Converyor
Nordberg Converyor
12/03/84 12/03/89
OP1035 Portable Boiler
OP1036
Area 6 Decon
Facility
Superior #2
Bioler Serial
#1342-1576
York-Shipley
Boiler
Serial #82-14857
10/20/85 10/20/90
10/20/85 10/20/90
Area 1 Concrete
Batch Plant
OP1082
OP1084 Area 1 Shaker Plant
Rex Lo-Go Plant 1/30/86
Surface Dis-
turbance
1/30/86
OP1085
OP1086
OP1087
OP1089
OP1090
OP1217
OP1287
Area 6 Diesel Tank
Mercury Gasoline
Tank
105,000 gallons 2/25/86
420,000 gallons 2/25/86
Mercury Diesel Tank 420,000 gallons 2/25/86
Area 3 Portable
Stemming System
Area 6 Gasoline
Tank
Area 1 Portable
Aggregate Plant
Area 1 Aggregate
Plant
4 Double Hoppers 2/25/86
1 Conveyor Belt
42,000 gallons 2/25/86
Iowa Crusher
12/03/84
Portec Crusher 2/12/87
Screens, Screws
and Conveyors
PERMITTEE
DOE
REECo
REECo
1/30/91
1/30/91
2/25/91
2/25/91
2/25/91
2/26/91
2/25/91
12/03/89
2/12/92
REECo
REECo
REECo
REECo
REECo
REECo
REECo
REECo
REECo
Add-7
-------
ADDENDUM 2
Part B (Continued)
CLEAN AIR ACT (Continued)
PERMIT
NO.
RC974
RC1367
LOCATION/FACILITY
Area 6 DAF
Nevad Test Site
ITEM(S)
Surface
Disturbance
Surface
Disturbance
ISSUE
DATE
4/19/85
3/17/87
EXPIRATION
DATE PERMITTEE
DOE
REECo
87-5 Open Burning
87-37 Tank Burn Test
Fire Dept. and 8/27/86 8/31/87
Env. Sci. Training
Open Burning 3/31/87 7/31/87
REECo
REECo
Add-8
-------
ADDENDUM 2
PART B (continued)
WATER POLLUTION
State of Nevada Water Pollution Control Regulations require a permit for con-
struction, installation, or significant modification of sewage collection and
treatment facilities and review of plans and specifications for sewage treat-
ment works.
The State of Nevada inspected the sewage treatment systems (lagoons) in Areas
6, 12 and 23 in November, 1985. Applications for permits will be made after
completion of final design.
The Area 30 Exploratory Shaft Sanitary Waste System Plan was reviewed by the
State, and approved 3/2/84.
CLEAN WATER
State of Nevada water supply regulations require review and approval of plans
and specifications for construction of public (potable) water systems and for
any substantial addition to or alteration of existing systems and periodic
sampling for bacteriological, chemical, and radiological analyses.
Permits Received:
System
& 12
NTS
NTS
NTS
NTS
NTS
NTS
- Area 23
- Area 1
- area 2
- Area 6
- Area 3
- Area 25
Permit No.
NY-360-12C
NY-5024-12NC
NY-4099-12C
NY-5000-12NC
NY-4097-12NC
NY-4098-12NC
Expiration Date
9/30/87
9/30/87
9/30/87
9/30/87
9/30/87
9/30/87
Permittee
REECo
REECo
REECo
REECo
REECo
REECo
Periodic sampling for bacteriological, chemical, and radiological analyses is
being done.
SOLID WASTE
State of Nevada Regulations governing
of solid waste management plans.
solid waste require review and approval
There is a salvage yard in Area 23; sanitary landfills in Areas 6, 10, and 23;
and construction landfills in Areas 3, 19, and 25. DOE/NV instructed REECo on
4/8/85 to obtain the necessary State permits or approvals for these facilities,
Add-9
-------
ADDENDUM 2
PART B (Continued;
RCRA HASTE
REECo has an EPA Identification Number, NV3890090001, for hazardous waste
activities. A Part B Permit application for the Radioactive Waste Management
Site Landfill in Area 5 was submitted to EPA Region IX by DOE/NV November,
1985. A report must be sent to the State by March 1, of each year providing
information on hazardous wastes shipped offsite the previous calendar year.
PCBS
REECo has been issued PCB Generator I.D. No. NVG-PCB-006 by the State.
An annual report must be sent to the State by July 1, covering the previous
calendar year.
Add-10
-------
ADDENDUM 2
PART C
STATUS OF THE ENVIRONMENTALLY RELATED FACILITIES AT THE TTR,
ADMINISTERED THROUGH REECO
CLEAN AIR ACT
1. REECo was issued Operating Permit #1083 for the Ross Concrete Batch Plant
on 1/30/86. This permit expires 1/30/91.
2. REECo was issued Operating Permit #1081 for the C. S. Johnson Batch Plant
on 1/30/86. This permit expires 1/30/91.
3. A permit for Open Burning at the Fire Department Training Facility in the
TTR was issued 9/17/86. This permit (#87-8) expires 9/17/87.
4. REECo was issued operating Permits #1311 - #1315 for the one diesel and
four JP-4 storage tanks respectively on 3/26/87. The permits expire
3/26/92.
5. REECo was issued Operating Permit #1316 on 3/26/87 for an incinerator.
This permit requires calendar year reporting of throughput and operating
hours by April 15, each year. The permit expires on 3/26/92.
6. REECo was issued Registration Certificate #1379 on 3/27/87 to construct
an additional diesel storage tank.
WATER POLLUTION
1. The sewage lagoon system is complete and in operation, replacing the
100,000 and 50,000 gpd Sewage Treatment Package Plants. Information is
currently being gathered for DOE to obtain a permit for this lagoon
system.
2. Plans for the Sewage Treatment Package Plant to be installed at Site 4
were submitted to the State for review and approval on 10/31/85. Approval
is expected after State receipt of additional requested information. A
permit will not be issued (less than 10,000 gpd inflow).
CLEAN WATER
1. Public Water Supply Operating Permits:
Add-11
-------
ADDENDUM 2
PART C (Continued)
Permits Received:
System
TTR-Sandia-
Area 6
TTR-Site 3A
TTR-Site O&M
TRR-Site 1A
Permit No.
NY-3014-12NC
NY-5001-12NC
NY-5002-12NC
NY-4068-12C
Expiration Date
9/30/87
9/30/87
9/30/87
9/30/87
Permittee
REECo
REECo
REECo
REECo
SOLID WASTE
Operation and maintenance plan for the sanitary landfill was submitted to the
State on December 19, 1981.
RCRA WASTE
TTR has an EPA Identification Number, NV 3570090016, for hazardous waste
activities.
Add-12
-------
ADDENDUM 3
ENVIRONMENTAL IMPACT STATEMENTS AND ENVIRONMENTAL ASSESSMENTS
The following Environmental Assessments were completed in CY 1986.
1. United States Geological Survey (USGS) Soil Studies near Beatty, Nevada
2. USGS drill holes near Lathrop Wells, Nevada
3. The Liquid Gas Fuel Spill Test Facility at Frenchmen Flat, Nevada Test Site
No Environmental Impact Statements were written in CY 1986.
Add-13
-------
TECHNICAL REPORT DATA
(Please read Instructions on the reverse before completing)
1. REPORT NO.
DOE/DP/00539-058
3. RECIPIENT'S ACCESSION NO.
4. TITLE AND SUBTITLE
5. REPORT DATE
OFFSITE ENVIRONMENTAL MONITORING REPORT
Radiation Monitoring Around U.S. Nuclear Test Area,
Calendar Year 1986
6. PERFORMING ORGANIZATION CODE
7.AUTHORIS) R.G, Patzer, C.A. Fontana, R.F. Grossman,
S.C. Black, R.E. Dye, A.A. Mullen, D.J. Thome', and
D.D. Smith
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
Las Vegas, NV 89114
10. PROGRAM ELEMENT NO.
XLUK10
11. CONTRACT/GRANT NO.
IAG DE-AI08-76DP00539
12. SPONSORING AGENCY NAME AND ADDRESS
U.S. Department of Energy
Nevada Operations Office
P.O. Box 14100
Las Vegas, NV 89114
13. TYPE OF REPORT AND PERIOD COVERED
Response - 1985
14. SPONSORING AGENCY CODE
EPA 600/07
15. SUPPLEMENTARY NOTES
Prepared for the U.S. Department of Energy under Interagency Agreement No.
DE-AI08-76DP00539
16. 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 document compliance with standards, to identify trends in environ-
mental radiation, and to provide such information to the public. It summarizes
activities for calendar year 1986. An addendum covers non-radiological activities
and facilities on the Nevada Test Site. Low levels of xenon-133 attributable to
NTS activities were detectable off site twice. In addition, debris from the Cher-
nobyl reactor accident was detectable throughout the Western U.S. for several weeks.
All measured radiation levels were very low and calculated maximum radiation doses,
based on conservative assumptions are: From NTS activities: 1.4 urem for an in-
dividual and 5.7x10 person-rem to the population within 80 km of the NTS. From
Chernobyl fallout: (only 1-131 was significant) an effective dose equivalent of
1 to 60 urem was calculated for infant thyroids at sampling stations West of the
Mississippi. The maximum dose from world-wide fallout (from Kr-85, Sr-90 and
Pu-239) was estimated to be 120 urem, or about one-thousandth of natural background
radiation exposures.
KEY WORDS AND DOCUMENT ANALYSIS
DESCRIPTORS
b. IDENTIFIERS/OPEN ENDED TERMS
c. COSATI Field/Group
RELEASE TO THE PUBLIC
19. SECURITY CLASS (This Report/
UNCLASSIFIED
21. NO. OF PAGES
20. SECURITY CLASS (THis page}
UNCLASSIFIED
22. PRICE
EPA Form 2220-1 (Re». 4-77) PREVIOUS EDITION IS OBSOLETE
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