xvEPA
United States
Environmental Protection
Agency
Environmental Monitoring
Systems Laboratory
PO Box 15027
Las Vegas NV 89114-5027
EPA-600/4-83-032
DOE/DP/0539-048
July 1983
Research and Development
Offsite Environmental
Monitoring Report
Radation monitoring around
United States nuclear test
areas, calendar year 1982
prepared for the
U.S. Department of Energy
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EPA-600/4-83-032
DOE/DP/00539-048
July 1983
OFFSITE ENVIRONMENTAL MONITORING REPORT
Radiation monitoring around United States
nuclear test areas, calendar year 1982
compiled by
S. C. Black, R. F. Grossman, A. A. Mullen,
G. D. Potter and D. D. Smith, 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
This report has been reviewed in accordance with the U.S. Environmental
Protection Agency's peer and administrative review policies and approved for
publication. Mention of trade names or commercial products does not
constitute endorsement or recommendation for use.
11
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PREFACE
The U.S. Atomic Energy Commission (AEC) used the Nevada Test Site (NTS)
from January 1951 through January 19, 1976, for conducting nuclear weapons
tests, nuclear rocket-engine development, nuclear medicine studies, and other
nuclear and non-nuclear experiments. Beginning January 19, 1976, these
activities 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 offsite 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.
Environmental Protection Agency (EPA) have provided an Offsite Radiological
Safety Program under an Interagency Agreement. The PHS or EPA has also
provided offsite 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. Offsite 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. To implement protective
actions, provide immediate radiation monitoring, and obtain environmental
samples rapidly after any release of radioactivity, personnel with mobile
monitoring equipment are placed in areas downwind from the test site prior to
each test. 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.
Prior to 1964 a report was published for each test series or test
project. Beginning in 1959 for reactor tests, and in 1962 for weapons and
plowshare tests, surveillance data were published for each test that released
significant radioactivity off site. From January 1964, through December
iii
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1970, semi-annual summaries of these reports for nuclear tests were also
published.
In 1971, the AEC implemented a requirement, now referred to as the DOE
Order 5484.1, that each contractor or agency involved in major nuclear
activities provide a comprehensive annual radiological monitoring report.
This is the eleventh annual report in this series; it summarizes the activities
of the EPA during CY 1982.
IV
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CONTENTS
Page
Preface i]]
Figures vii
Tables 1*
Abbreviations, Symbols and Conversions xi
Acknowledgement xiii
1. Summary 1
Purpose 1
Locations 1
Pathways Monitoring 1
External Exposure 2
Internal Exposure 2
Community Monitoring Stations 3
Dose Assessment 3
2. Introduction 4
3. Description of the Nevada Test Site 5
Site Location 5
Climate 5
Geology and Hydrology 7
Land use of NTS Environs 7
Population Distribution 8
Airborne Releases of Radioactivity at the NTS During 1982 ... 8
4. Quality Assurance 10
Goals 10
Sample Collection 10
Sample Analysis 10
External QA 10
Internal QA 11
Validation 11
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CONTENTS (Continued)
Page
5. Radiological Safety Activities 12
Special Test Support 12
Pathways Monitoring 13
Air Surveillance Network 13
Noble Gas and Tritium Surveillance Network 16
Long-Term Hydrological Monitoring Program 21
Milk Surveillance Network 26
Biomonitoring Program 28
External Exposure Monitoring 31
Thermoluminescent Dosimetry Network 31
Pressurized Ion Chamber Network 37
Internal Exposure Monitoring 37
Network Design 38
Methods 38
Results 40
Community Monitoring Stations 40
Claims Investigations 41
Public Information Program 41
Dose Assessment 42
6. References 44
Appendices
A. Site Data 47
B. Sample Analysis Procedures 58
C. Quality Assurance Procedures 60
D. Radiation Protection Standards for External and Internal
Exposure 67
E. Data Summary for Monitoring Networks 69
vi
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FIGURES
Number Page
1 Location of the Nevada Test Site 6
2 Air Surveillance Network stations (1982) 14
3 Standby Air Surveillance Network stations (1982) 15
4 Monthly Average Gross Beta in air, 1982 17
5 Noble Gas and Tritium Surveillance Network
sampling locations 18
6 Frequency distribution of krypton-85 concentration in
air, 1982 data 19
7 Trend in annual average krypton-85 concentration 21
8 LTHMP sampling locations on the NTS 23
9 LTHMP sampling locations near the NTS 24
10 Milk sampling locations within 300 km of the NTS 27
11 Strontium-90 concentration in Pasteurized Milk Network
samples 29
12 Strontium-90 concentration trends in animal bone 31
13 Locations monitored with TLD's 34
14 Average annual TLD exposure as a function of station
altitude 36
15 Location of families participating in the Offsite Human
Surveillance Program 39
Appendix A
A-l Groundwater flow systems around the NTS 50
vn
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FIGURES (Continued)
Number Page
A-2 General land use within 300 km of the NTS 51
A-3 Population of Arizona, California, Nevada, and Utah
counties near the NTS 53
A-4 Distribution and number of family milk cows and goats,
by county 54
A-5 Distribution of dairy cows, by county 55
A-6 Distribution of beef cattle, by county 56
A-7 Distribution of sheep, by county 57
Appendix E
E-l Amchitka Island and Background sampling locations
for the LTHMP 86
E-2 LTHMP sampling locations for Project Cannikin 87
E-3 LTHMP sampling locations for Projects Milrow and Long Shot. . 89
E-4 LTHMP sampling locations for Project Rio Blanco 94
E-5 LTHMP sampling locations for Project Rulison 96
E-6 LTHMP sampling locations for Project Faultless 98
E-7 LTHMP sampling locations for Project Shoal 99
E-8 LTHMP sampling locations for Project Gasbuggy 101
E-9 LTHMP sampling locations for Project Gnome 103
E-10 LTHMP sampling locations for Project Dribble -
towns and residences 106
E-ll LTHMP sampling locations for Project Dribble - near GZ. . . . 110
E-12 LTHMP sampling locations for Project Dribble -
near salt dome Ill
viii
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TABLES
Number Page
1 Total Airborne Radionuclide Emissions at the NTS During 1982. . 9
2 Annual Average Krypton-85 Concentrations in Air, 1973-1982. . . 20
3 Water Sampling Locations Where Samples Contained
Man-made Radioactivity 25
4 Network Annual Average Concentrations of Tritium
and Strontium-90 in Milk, 1975-1982 28
5 Radionuclides in Animal Tissue Samples - 1982 30
6 Radionucl ides in Selected Vegetable Crops - 1982 32
7 Dosimetry Network Summary for the Years 1971-1982 36
8 Pressurized Ion Chamber Readings - yR/hr 37
Appendix A
A-l Characteristics of Climatic Types in Nevada 48
Appendix B
B-l Summary of Analytical Procedures 58
Appendix C
C-l Samples and Analyses for Duplicate Sampling Program 60
C-2 Sampling and Analytical Precision 62
C-3 1982 Quality Assurance Intercomparison Results 63
C-4 Summary Results of the Fifth International Intercomparison
of Environmental Dosimeters 64
C-5 Quality Assurance Results for the Bioenvironmental Program. . . 65
Appendix D
D-l DOE Concentration Guides 68
IX
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TABLES (Continued)
Number Page
Appendix E
E-l 1982 Summary of Analytical Results for ASN Continuously
Operating Stations 69
E-2 1982 Summary of Analytical Results for ASN Standby Stations
Operated 1 or 2 Weeks per Quarter 71
E-3 1982 Summary of Analytical Results for the Noble Gas
and Tritium Surveillance Network 75
E-4 1982 Summary of Gross Beta Analyses for Five ASN Stations ... 78
E-5 1982 Summary of Plutonium Concentrations at Selected
ASN Stations 79
E-6 1982 Summary of Tritium Results for the NTS Monthly
Long-term Hydrological Monitoring Program 81
E-7 Tritium Results for the NTS Long-term Hydrological
Monitoring Program, Semi-Annual Project 82
E-8 Tritium Results for the NTS Long-term Hydrological
Monitoring Program, Annual Project 85
E-9 1982 Tritium Results for the Off-NTS Long-term Hydrological
Monitoring Program (Annual Samples) 88
E-10 1982 Summary of Analytical Results for the Milk
Surveillance Network 113
E-ll 1982 Summary of Analytical Results for Standby Milk
Surveillance Network 116
E-12 1982 Summary of Radiation Doses for the Dosimetry Network . . . 124
E-13 1982 Summary of Radiation Doses for Offsite Residents 128
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ABBREVIATIONS, SYMBOLS AND CONVERSIONS
a annum (year)
ASN Air Surveillance Network
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 Vegas
EPA U.S. Environmental Protection Agency
eV electron volt
g gram
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
R Roentgen
rad unit of absorbed dose, 100 ergs/g
rem the rad adjusted for biological effect
TLD thermoluminescent dosimeter
XI
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PREFIXES
a
f
P
n
y
m
k
M
atto
femto
pi co
nano
micro
milli
kilo
Mega
- 10-18
= 10-15
= 10-12
= 10-9
= 10-6
= 10-3
= 103
= 106
CONVERSIONS
Multiply
To Obtain
Concentration Guides
pCi/mL
vCi/mL
SI Units
rad
rem
pCi
109
1012
10-2
10-2
0.037
pCi/L
pCi/nv*
Gray (Gy = 1
Sievert (Sv)
Becquerel
Joule/kg)
xn
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ACKNOWLEDGEMENT
Jaci L. Hopper, a health physicist for the Reynolds Electrical and
Engineering Co., performs the calibration and readout of the TLD's used in
the Dosimetry Network as described in Section 5 of this report. These
services plus a summary of the results and preliminary interpretation for
the TLD and Pressurized Ion Chamber networks are supplied under contract
to the Nuclear Radiation Assessment Division, EMSL-LV.
xm
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SECTION 1
SUMMARY
PURPOSE
It is U.S. Environmental Protection Agency 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 policy of keeping radiation exposure of the general
public as low as reasonably achievable, the EMSL-LV conducts an Offsite
Radiological Safety Program centered on the DOE's Nevada Test Site. This
program is conducted under an Interagency Agreement between EPA and DOE.
A principal activity of the Offsite Radiological Safety Program is
routine environmental monitoring for radioactive materials in various media
and for radiation in areas which may be affected by nuclear tests. It is
conducted to document compliance with standards, to identify trends, and to
provide information to the public. This report summarizes these activities
for CY 1982.
Locations
Most of the radiological safety effort is applied in the areas
around the Nevada Test Site in south-central Nevada. The principal activity
at the NTS is testing of nuclear devices, though other related projects are
also conducted. This portion of Nevada is sparsely settled, 0.5 person/km2,
and has a continental arid climate. The largest town in the near offsite area
is Beatty, located about 65 km west of the NTS with a population of about 900.
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 (LTHMP) is conducted to detect any
possible contamination of potable water and aquifers near these sites.
Pathways Monitoring
The pathways leading to human exposure to radionuclides, namely 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 detect increases in population exposure from other sources.
In 1982 the air surveillance network (ASN) consisted of 29 continuously
operating stations surrounding the NTS and 92 standby stations (operated 1 or
1
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2 weeks each quarter) in all States west of the Mississippi. Other than
naturally occurring beryllium-7, the only activity detected by this network
was plutonium-239 from worldwide fallout.
The noble gas and tritium sampling network (NGTSN) consisted of 16
stations offsite (off the NTS and exclusion areas) in 1982. No NTS-related
radioactivity was detected at any offsite station. Tritium concentration
in air remained below MDC levels and krypton-85 concentration continued
the upward trend which started in 1960, reflecting the worldwide increase
in nuclear technology.
The long-term hydrological monitoring of wells and surface waters near
sites of nuclear tests showed only background tritium and other radionuclide
concentrations except for those wells that enter the test cavity or those
that were previously spiked with radionuclides for hydrological tests.
The milk surveillance network (MSN) consisted of 25 sampling locations
within 300 km of the NTS and about 140 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.
Other foods analyzed have been mainly meat from domestic or game animals
and garden vegetables. The radionuclide most frequently found in the edible
portion of the sampled animals is cesium-137. Its concentration has been
low since 1968. Meat from deer that reside on the NTS has not had markedly
higher concentrations of radionuclides than meat from deer that reside
in other areas of Nevada.
External Exposure
External exposure is monitored by a network of TLD's at 82 locations
surrounding the NTS and by TLD's worn by 48 offsite residents. In a few
cases, small exposures of a few mrem above the average for the person or
location were measured. Except for one case of occupational exposure, all
such net exposures were very low and were not related to NTS activities. The
range of exposures measured, 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 detectors to measure lung burdens of radioactivity. In 1982, counts
were made on 70 offsite residents and about 275 EPA and EG&G employees.
Natural potassium-40 was found as expected, but no nuclear test related
radioactivity was detected. In addition, physical examinations of the
offsite residents revealed only a normally healthy population consonant
with the age and sex distribution of that population.
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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 ASM, 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 sta-
tions are reported herein as part of the networks in which they participate.
Dose Assessment
Doses were calculated for an average adult living in Nevada based on the
Kr-85, Sr-90, Cs-137 and Pu-239 detected by the monitoring networks. Using
conservative assumptions, the estimated dose would have been less than 0.3
mrem per year, a small fraction of the variation of 10 mrem per year due to
the natural radionuclide content of the body. Since no radioactivity orig-
inating on the NTS was detectable offsite, no dose assessment related to
NTS activities could be made. However, atmospheric dispersion calculations,
based on known emissions from the NTS, indicate that the population dose
within 80 km of CP-1 was about 10~5 man-rem for 1982.
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SECTION 2
INTRODUCTION
The EMSL-LV operates an Offsite 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 the guidelines in DOE/EP-0023 (DOE 1981), covers the program
activities for calendar year 1982. It contains descriptions of pertinent
features of the NTS and its environs, summaries of the EMSL-LV dosimetry and
sampling methods, analytical procedures, 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 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
development for nuclear rocket and ramjet applications (Projects Pluto and
Rover), high-energy nuclear physics research, seismic studies (Vela Uniform),
and studies of high-level waste storage. During 1982, 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 since 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 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 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
variations in altitude and its rugged terrain. Generally, the climate is
referred to as continental arid. Throughout the year, there is insufficient
precipitation to support the growth of common food crops without irrigation.
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3 81
0 50 100 150 200
Scale in Kilometers
Figure 1. Location of the Nevada Test Site (NTS).
6
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As Houghton et al. (1975) 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
(Quiring 1968). 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 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, including subsurface studies of numerous
boreholes, the surface and underground geological and hydrological
characteristics for much of the NTS are known in considerable detail (see
Figure A-l). This is particularly true for those areas in which underground
experiments are conducted. A comprehensive summary of the geology and
hydrology of the NTS by Winograd and Thordarson was published in 1975.
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. A survey of
milk cows during the summer of 1981 showed 11,800 dairy cows, 920 family milk
cows and 530 family milk goats in the area (Figures A-4 and A-5). The family
cows and goats are distributed in all directions around the NTS, whereas most
dairy cows are located to the southeast (Moapa River, Nevada; Virgin River
Valley, Nevada; and 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 280,000 cattle and 180,000 sheep are distributed within the area as
shown in Appendix Figures A-6 and A-7, respectively. The estimates are based
on information supplied by the California county agents during 1982, from 1982
agricultural statistics supplied by the Nevada Department of Agriculture and
from 1982 census information supplied by the Utah Department of Agriculture.
POPULATION DISTRIBUTION
Excluding Clark County, the major population center (approximately
462,000 in 1980), 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 offsite 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-3. 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 3,600, is located about 72 km south-southwest of
the NTS CP-1. The Amargosa Farm Area, which has a population of about 1,600,
is located about 50 km southwest 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.
AIRBORNE RELEASES OF RADIOACTIVITY AT THE NTS DURING 1982
All nuclear detonations during 1982 were conducted underground and were
contained, although occasional releases of low-level radioactivity occurred
during re-entry drilling. Table 1 shows the total quantities of radionuclides
released to the atmosphere, as reported by the DOE Nevada Operations Office
(1983). Because these releases occurred throughout the year, and because
of the distance from the points of releases to the nearest sampling station,
none of the radioactive nuclides listed in this table were detected offsite.
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TABLE 1. TOTAL AIRBORNE RADIONUCLIDE EMMISIONS
AT THE NTS DURING 1982
Half-Life Quantity Released
Radionuclide (days) (Ci)
Tritium 4,500 165
Iodine-131 8.04 0.0001
Xenon-133 5.29 74
Xenon-133m 2.33 2.5
Xenon-135 0.38 4.2
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SECTION 4
QUALITY ASSURANCE
GOALS
The goals of the EMSL-LV quality assurance program are to assure the
collection 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 both the sample collection and sample
analysis procedures.
SAMPLE COLLECTION
The collection of samples is governed by a detailed set of Standard
Operating 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
parameters 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.
SAMPLE ANALYSIS
All of the networks operated by the EMSL-LV have individual Quality
Assurance Project Plans that assure the results of analysis will be of high
accuracy and precision and will be comparable to results obtained elsewhere
with equivalent procedures. These Plans are summarized in the following
sections.
External QA
External QA provides the data from which the accuracy of analysis (a
combination 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 Offsite Radiological
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Safety Program participates in Intercomparison Study Programs that include
environmental sample analysis, TLD dosimetry, and whole-body counting.
Also, samples unknown to the analyst are spiked by adding known amounts of
radionuclides and 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.
Replicate counting of at least 10 percent of all samples yield data from which
the precision of counting can be determined.
If the accuracy and precision data are of sufficient quality (i.e.,
normalized deviation in Table C-3 is less than 2), then comparability,
i.e., comparison of the data with those of other analytical laboratories,
can be assessed with confidence. 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
following:
Instrument background counts
Blank reagent analyses
Instrument calibration with known nuclides
Laboratory control standards analysis
Performance check-source analysis
Maintenance of control charts for background and check-source data
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 with previous data from
similar samples at the same location.
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.
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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.
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 offsite 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, thermoluminescent 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 offsite, EPA
monitors were stationed at locations where hazardous situations might ensue.
At these locations, e.g., mines and specific buildings, occupants are notified
of potential hazard 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 feasible protective actions in case accidental releases
of radioactivity should occur.
An EG&G cloud sampling and tracking aircraft is 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 EG&G aircraft
is flown to gather meteorological data and to perform cloud tracking. Infor-
mation from these aircraft can be used in positioning the radiation monitors.
During CY 1982 none of the tests conducted at the NTS released
radioactivity that was detected offsite.
12
-------
PATHWAYS MONITORING
The offsite radiation monitoring program includes pathways monitoring
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. Not only the concentration but also the
source must be determined if appropriate corrective actions are to be taken.
Thus the ASN is designed to circumscribe the NTS with a 200 km circle, is
limited only by the availability of electric power and a resident for opera-
tion, and has a slight concentration of sampling stations in the prevailing
downwind direction as shown in Figure 2. This continuously operating network
is reinforced by a standby network which covers the contiguous States west of
the Mississippi River, Figure 3.
Methods—
During 1982 the ASN consisted of 29 continuously operating sampling
stations and 92 standby stations. Each sampler was equipped to collect both
particulate and gaseous radionuclides.
Samples of airborne particulates were collected at each active station
on 4-cm diameter glass-fiber filters at a flow rate of 'about 81 m^ per day.
Filters were changed after sampler operation periods of 2 or 3 days (160 to
240 m^). 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. The samplers
use 10-cm Microsorban filters and charcoal cartridges. They sample air at
about 350 m-* per day. The stations were operated by State and municipal
health department personnel or by local residents. All air filters and
charcoal cartridges were analyzed by the EMSL-LV.
Results--
Throughout the network, beryllium-7 was the only nuclide detected
by gamma spectroscopy. The principal means of beryllium-7 production is
from spallation of oxygen-16 and nitrogen-14 in the atmosphere by cosmic
rays. Appendix Tables E-l and E-2 summarize the data from the ASN samples.
All time-weighted averages (Avg in the tables) are less than 1 percent of
the Concentration Guide (Appendix D) for exposure to the general public.
These guides do not apply to naturally-occurring radionuclides.
During 1982, no airborne radioactivity related to nuclear testing at the
NTS was detected on any sample from the ASN.
A plot of the logarithm of the individual concentrations for all stations
during the year versus probits indicates that the air data are approximately
lognormally distributed. The distribution for the individual nuclide that
13
-------
s
1
N
IT
Nevada
JL
\J Pyramid Lake
• Austin Cl
Ely
'
v a • Sunnyside
\ Stone Cab'n Rn Blue Eagle Rn.
X Tonopah •
OX • Nyala
9$X Goldfield
^O\ • •Twin Springs Rn.
'Vx 0TTR
V ^V B »
Scotty'^Jct. "^fhel . Alamo
^ *, . rw Groom
Beatty • Nevadal
\ ISite 1 Sherri's Rn.
Lathrop Wells m1— \T
\. • Indian _ -.
X _ . ".Ove
X Springs A i
Furnace Creek • PahrumpB m ^J(Lak
Death Valley Jet. • X Las ^K*^'^'
%|
1
1
• l
Salt Lake City f
•c
CO 1
+- 1
D
1
1
Delta • I
1
• Milford |
I
• Cedar City |
1
• St. George I
1
Arizona
"ton
e Mead
ou • X Ve9as
Shoshone X 1
• Community Monitoring Stations (15)
• Other Locations (14)
Figure 2. Air Surveillance Network stations (1982).
14
-------
North Dakota \ Minnesota
A Stand-by ASN Station (92)
Figure 3. Standby Air Surveillance Network stations (1982).
15
-------
was detected indicated that there was a single source, assumed to be world-
wide, because all stations were affected similarly.
Two special studies are performed on the 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 17 States.
The gross beta analysis is used to detect trends in atmospheric radio-
activity more quickly than is possible with gamma spectrometry. For this
study, three stations north and east of the NTS, and 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 daughter activity. The data suggest little signif-
icant difference among stations and show the normal trend of decreased
activity to be expected after the rainout which occurs each spring (Figure 4).
The maximum concentration measured was 0.09 pCi/rn^. the minimum was <0.002
pCi/m^, and the arithmetic average was 0.011 pCi/m^. A summary of the
data is shown in Appendix Table E-4.
The plutonium study uses the filters from 32 standby ASN stations
distant from the NTS, and from three ASN stations near the NTS. The filters
from two standby stations in each State (operated 1 or 2 weeks per quarter)
are composited quarterly, and those from the ASN stations are composited
monthly. The composites are analyzed radiochemically as indicated in
Appendix B.
The peak plutonium concentrations occurred in the spring and summer,
as they did in 1981. The weighted annual average for the standby stations
was 23 aCi/m^, and for all stations was 30 aCi/m^. This latter average is
0.15% of the CG for an individual in the general population.
Noble Gas and Tritium Surveillance Network
Network Design--
There are several sources of the radionuclides monitored by this network.
Noble gases are emitted from nuclear power plants, propulsion reactors,
reprocessing facilities and nuclear explosions. Tritium is emitted from the
same sources and is also produced naturally. The monitoring network will be
affected by all these sources, but must be able to detect NTS emissions. For
this purpose some of the samplers are located close to the NTS and particu-
larly in drainage-wind channels leading from the test areas. In 1982 this
network consisted of 16 stations as shown in Figure 5.
Methodology--
Samples of air are collected by either of two methods; by directly
compressing or by liquefying air using cryogenic techniques. Either type of
equipment continuously samples air over a 7-day period and stores approximately
1 cubic meter of air in pressure tanks. The tanks are exchanged weekly and
returned to the EMSL-LV where their contents are analyzed. Analysis starts
16
-------
10-1-]
o
a
10-2-
10-3-
Jan ' Feb I Mar I Apr I May I June ' July I Aug I Sept I Oct I Nov I Dec I
Month - 1982
Figure 4. Monthly average gross beta in air samples, 1982.
by condensing the samples at liquid nitrogen temperature and using fractional
distillation to separate the gases. The separate fractions of radioxenon
and radiokrypton are dissolved in scintillation cocktails and counted in a
liquid scintillation counter (see Appendix B).
For tritium sampling, a molecular sieve column is used to collect water
from air. A prefilter is used to remove particles before air passes through
the molecular sieve column. Up to 10 cubic meters of air are passed through
each column over a 7-day sampling period. Water absorbed on the molecular
sieve column is recovered, and the concentration of tritium in the water (HTO)
is determined by liquid scintillation counting techniques (see Appendix B).
Results--
All results are shown in Appendix Table E-3 as the maximum, minimum and
average concentration for each station. These data indicate that no radio-
activity from NTS tests was detected offsite by the Noble Gas and Tritium
Surveillance Network during 1982. The average concentrations at all network
stations ranged from 24 to 26 pCi/m3. Additional samples were collected at
Canfield's Ranch (Adaven), Reveille Project (near Warm Springs), Twin Springs
Ranch, and Hiko to monitor a deliberate release of gaseous radioactivity
from a tunnel experiment on the NTS on September 24, 1982. However, no
radioactivity was detected.
As shown in Figure 6, the concentrations of krypton-85 within the whole
network appeared to have a skewed distribution. The lognormal distribution
had a geometric mean of 24 pCi/m3 and a geometric standard deviation of 1.15.
17
-------
Ely
Rachel
Beatty • Nevada!
•J |Test
Lathrop Wells
Pahrump
l Alamo
Salt Lake City
(O
i Cedar City
I St. George
Arizona
Shoshone
.Overton
Lake Mead
Figure 5. Noble Gas and Tritium Surveillance Network sampling locations.
18
-------
a>
o
I
3
u
u
O
u
c
100-
80-
60-1
I 40-
20-
15
20
25
86Kr -pCi/m3
30
I
35
Figure 6. Frequency distribution of krypton-85 conentration
in air, 1982 data.
As shown in Table 2 and Figure 7, the average concentration of krypton-
85 for the whole network has gradually increased since sampling began in
1972. This increase, observed at all stations, reflects the worldwide
increase in ambient concentrations resulting from the increased use of the
nuclear technology. The increase in ambient krypton-85 concentration was
projected by Bernhardt, et al., (1973). However, the measured network average
in 1982 is only about 25 percent of the 99 pCi/nH 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.
Using published data for krypton-85 concentration in air (NCRP 1975) 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 concen-
tration/time relation is pCi/m3 = 5.7 + 0.82t where t is number of years after
1960. The correlation coefficient, R, was 0.98.
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-3). The tritium
19
-------
TABLE 2. ANNUAL AVERAGE KRYPTON-85 CONCENTRATIONS
Sampling
Locations
Alamo, Nevt
Austin, Nev.t
Beatty, Nev.
Diablo and
Rachel , Nev.*
Ely, Nev.t
Goldfield, Nev.t
Hiko, Nev.
Indian Springs,
Nev.
NTS, Mercury, Nev.
NTS, Area 51, Nev.
NTS, BJY, Nev.*
NTS, Area 12, Nev.
Tonopah, Nev.
Las Vegas, Nev.
Death Valley Oct.,
Calif.*
NTS, Area 15, Nev.
NTS, Area 400, Nev
Lathrop Wells, Nev
Pahrump, Nev.
Overton, Nev.
Cedar City, Ut.t
St. George, Ut.t
Salt Lake City, Ut
Network Average
Kr-85 Concentrations
1973
--
16
16
--
16
* 16
* 16
18
* 16
16
16
15
*
*
.
. ~ ~
--
--
.t-
16
1974
—
17
17
--
17
18
17
19
18
18
17
18
--
—
--
18
1975
— —
19
18
--
17
20
18
18
19
18
17
18
17
--
-_
--
18
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
IN AIR, 1973-1982
(pCi/m3)
1979
•m «
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
24
*Stations discontinued
"fNew stations
^Station at Diablo was moved to Rachel in March 1979.
20
-------
concentrations observed at off-NTS stations were considered to be representa-
tive of environmental background. The geometric mean of the tritium concen-
trations for all offsite stations was evaluated as 0.051 pCi/mL of moisture,
which is below the minimum detectable concentration of about 0.4 pCi/mL.
The geometric standard deviation for the mean was determined to be 1.45.
30-,
\ 25-
Least Squares Line: pCi/m3 = 5.7 + 0.82t
R = 0.98
O
a
a
o
c
o
O
20-
1960
1965
1970 1975 1980
Time - Calendar Years
Figure 7. Trend in annual average krypton-85 concentration.
Long-term Hydrological Monitoring Program
Network Design—
A major pathway for 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 sufficient monitoring data are obtained.
21
-------
The monitored locations for the NTS and nearby offsite areas are shown in
Figures 8 and 9. For Projects Cannikin, Longshot and Mi Trow in Alaska; for
Projects Rio Blanco and Rulison in Colorado; for Projects Dribble and Miracle
Play 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. Two 3.5-L samples are filtered through 10 cm
diameter membrane filters into cubitainers and acidified with HN03. One
sample and the filter are gamma-scanned, the other sample is stored for
duplicate analysis or for reanalysis as required.
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, 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
compiled in Appendix Tables E-6 through E-9 together with the percent of the
relevant CG listed in Appendix D.
None of the radionuclide concentrations found at the locations listed in
Table 3 are expected to result in radiation exposures to residents in the
areas where the samples were collected. Well UE7NS is located on the NTS, and
it is not used as a source 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 DD-1
enters the Gnome cavity, to which Well LRL-7 is connected by a shaft used
for the disposal of contaminated soil and salt. As a result, both of these
wells are 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.
No man-made gamma-emitting radionuclides were detected in any of the
other water samples analyzed. The Cs-137 in the sample from USGS Well 4
reported last year is attributed to contamination of the sampling gear; it
has never been detected in samples collected in the past and was not detected
in the sample collected this year.
22
-------
Nuclear Rocket
Development Station
Desert Game
Range
AMonthly (12)
• Semi-Annual (6)
7/83
4fe
'°<"V
Figure 8. LTHMP sampling locations on the NTS.
23
-------
\
N
c
c
3/i
•
Twin Springs Rn £
Tonopah 0Adaven Springs
^TTR Well #6
Nellis
J? Air Force
.1 Range
\ \
Sprmgdale* S,
Goss SpringsH • £o
^^ Beatty™ 1 1 !
V^ Neco
\
• Hiko
^Crystal Springs
s — \ ^
1 •*""
I Nevada
Test Site
fer's
5/48-1dd
NRDS Mercury
^ Blndian Springs AFB
V ^Fairbanks Springs Sewer Co Well #1
Well 17S/50E-14CACTI
X tCrystal Poo!
Well 18S/51E-7dbli«Ash Meadows
Death Valley Jet * ~v ^ Las Vegas
N^ ^Calvada Well #3 Well #28
"^.^b- Lake MeadH
°^ v Intake
*\
^Shoshone v
Scale in Miles
10 20 30 4
~~r^^T~~~^^i~~^^i
10 20 30 40 50 60
33 Scale in Kilometers
Annual Samples (11)
Semi-Annual Samples (12)
— bprmg
1 Nevada
Nevada Test Site &^fc
Nellis Air l-orce Hange-^p
Location Map \J
Figure 9. LTHMP sampling locations near the NTS.
24
-------
TABLE 3. WATER SAMPLING LOCATIONS WHERE SAMPLES CONTAINED
MAN-MADE RADIOACTIVITY*
Sampling Location
Type of
Radioactivity
Concentration
(pCi/L)
NTS (Nev.)
Well UE7NS
PROJECT GNOME (N. Mex.)
Hydrogen-3
1400-1500
USGS Well 4
USGS Well 8
Well LRL-7
Well DD-1
PROJECT DRIBBLE (Miss.)
Well HMH-1 through 11
Well HM-S
Well HM-L
REECo Pit Drainage-B
REECo Pit Drainage-C
PROJECT LONG SHOT (Alaska)
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
Strontium-90
Hydrogen-3
Strontium-90
Cesium-137
Hydrogen-3
Strontium-90
Cesium-137
Hydrogen-3
Strontium-90
Cesium-137
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
===3===—================
360,000
8,500
290,000
6,900
18
22,000
10
250
15 x 107
Lost
970,000
29-10,000
24,000
2,000
1,400
1,200
310
3,800
210
690
850
1,000
*Water not available for domestic use.
25
-------
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 unlikely to be so affected. Additional considerations are: 1) a
complete ring of stations to cover any eventuality, 2) samples from major
mi Ik sheds as well as from family cows, and 3) availability of milk cows.
Methods—
The network consists of two major portions, the MSN at locations
within 300 km of the NTS from which samples are collected quarterly (Figure
10) and the standby network (SMSN) at locations in all major milksheds west
of the Mississippi River 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 quarterly 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 formal-
dehyde but they are collected by contacting State Food and Drug Administration
Representatives, after notification of the Regional EPA offices by telephone,
and mailed to EMSL-LV for analysis.
All the milk samples are analyzed first for gamma-emitting nuclides by
high-resolution gamma spectrometry and then for strontium-89 and strontium-90
by the methods outlined in Appendix B, after a portion is removed for tritium
analysis. Occasionally a milk sample will turn sour thus preventing the
strontium analysis, but the other analyses can generally be performed.
Results—
The analytical results from the 1982 milk samples are summarized in
Appendix Table E-10 and Table E-ll where the maximum, minimum, and average
concentrations of tritium, 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. However, from the results of intercomparison
samples used for quality assurance, the strontium results for 1982 are
considered to be low by about 15 to 30 percent.
Other than naturally occurring potassium-40, radionuclides were not
detected by gamma spectrometry in any of the samples from the MSN. One SMSN
sample, from Flensburg, Minn., contained 16 ± 8 pCi/L of cesium-137. This
radionuclide is attributed to past atmospheric fallout and has a concentration
that is comparable to what has been observed previously.
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
26
-------
DWmnemucca
• Reno
• Austin
| Young Rn
Round Mtn M
Berg Rn •
Warm Springs •
Twin ^prings Rn |
Tonopah^
Larsen Rn
•
• McGill
• Ely
Manzome Rn
Currant^
• Blue Eagle Rn
Nyala
Sharp's Rn
| Harbecke Rn
• Shoshone
• Lund
•McKenzie Dairy
Caliente*"June
Alamo
Buckhorn Rn
Cox Rn
Cedar City
Western
General Dairy
_St George
^ Droubay Dairy
Indian Spgs Decade Corp
3/83
50 100 150
Scale in Kilometers
Pahrump^
B Ridgecrest Oxborrow Rn ~
Cedar Sage Farm
«Mesquite
SFand K Dairy
• Knudsen Corp
Logandale
IDS Dairy Farm
• Milk Sampling Locations
NOTE When sampling location occurred
in city or town, the sampling location
symbol was used for showing both town
and sampling location
• •Barstow
Bill Nelson Dairy
Hmkley
Figure 10. Milk sampling locations within 300 km of the NTS.
27
-------
TABLE 4. NETWORK ANNUAL AVERAGE CONCENTRATIONS OF
TRITIUM AND STRONTIUM-90 IN MILK, 1975 - 1982
Average Concentrations - pCi/L
Year H-3 Sr-90
1975
1976
1977
1978
1979
1980
1981
1982
<400
<400
<400
<400
<400
<400
<400
<400
<3
<2
<2
1.2
<3
<2
1.9
1.2
be atmospheric deposition. These results are consistent with the results
obtained for the Pasteurized Milk Network shown in Figure 11. This network
is operated by the Eastern Environmental Radiation Laboratory in Montgomery,
Alabama.
Biomonitoring Program
Objective—
This program began about 1957 and most recently was known as the Animal
Investigation Program (AIP). The program had two major objectives: to measure
the tissue concentration of radionuclides in beef cattle maintained life-long
in an area used for above-ground nuclear tests and to measure radionuclides in
the tissues of game animals (deer, bighorn sheep) which might become a source
of exposure to humans. The NTS beef herd was transferred to the University
of Nevada, Reno, in 1981. Since then, cattle have been purchased from a
commercial herd maintained in the Tikaboo Valley northeast of the NTS.
Methods--
The beef herd of about 70 cattle had been maintained in Area 18, NTS,
since the early 1960's. Each spring and fall the herd was collected and 3 to
6 animals sacrificed, including both yearling and aged animals. The samples
collected from each animal included: liver, lung, tracheobronchial lymph
node, muscle, thyroid, kidney, (fetus, if present) and rumen contents for
gamma spectrometric analysis; blood (or tissue water) for tritium analysis;
and femur or hock bone for strontium and plutonium analyses. The same anal-
yses are performed on the commercial cattle samples. Other animals found
dead on the NTS, such as deer or sheep, were necropsied, examined for
suspicious lesions, and samples taken for histopathological examination in
addition to the samples taken for radionuclide analyses.
28
-------
to t-
A New Orleans
• Salt Lake City
• Las Vegas
GO
Figure 11. Strontium-90 concentration in Pasteurized Milk Network samples.
A sizeable mule deer herd resides in the mountainous regions of the
NTS during the summer. If they move to unrestricted lands, these deer may
be hunted by members of the public. A study designed to determine migration
patterns of the herd by tracking individual deer wearing collars containing
miniature radio transmitters was begun in 1975 and continued through 1982.
Limited tagging was done during 1982 and only five deer were captured.
Three of these animals were given visual markers and two were fitted with
radios recovered from deer that died. These two newly installed transmitters
brought to ten the total number of working transmitters in the field.
Laboratory personnel monitored the movements of the deer weekly with hand-
held receivers and directional antennae. The animals were tracked until
the end of December 1982 to complete the field portion of the Deer Migration
Study.
A program of sampling garden vegetables was started and vegetables from
Alamo, Rachel, Adaven, and Las Vegas were analyzed for gamma, tritium,
strontium, and plutonium. Kilogram samples of a leafy, root, and fruiting
vegetable were collected at each location.
Results--
Available tissue sample analytical
results are listed in Table 5.
29
-------
TABLE 5. RADIONUCLIDES IN ANIMAL TISSUE SAMPLES - 1982
Muscles
Lungs
Liver
Kidneys
Blood
Rumen Content
Bone
K (g/kg*)
Animal Cs-137 (pC1/kg*) K (g/kg*) K (g/kg*) K (g/kg*) Be-7 (pC1/kg*) Sr-90 (pC1/g ash)
Number Pu-239 (pC1/kg*) Pu-239 (pC1/kg*) Pu-239 (pC1/kg*) H-3 (pC1/H) H-3 (pC1/l) Pu-239 (pC1/kg*) Pu-239 (pCi/g ash)
Medlln Ranch. July 19B2
BOV-1
BOV-2
BOV-3
BOV-4
BOV-5
BOV-6
DEER-1
OEER-Z
3.6 l 0.3
<26
NA
5.2 i 0.3
14.0 i 9.2
NA
6.2 i 0.4
15.0 t 8.9
NA
5.1 t 0.4
<26
NA
3.5 ± 0.3
<30
0.064 i 0.066+
3.5 t 0.4
<26
0.035 * 0.038 +
5.6 * 0.3
<27
0.018 t 0.048+
3.4 t 0.3
<28
0.031 * 0.1+
2.9 i 0.4
NA
3.1 t 0.5
NA
2.6 t 0.5
NA
2.5 ± 0.6
NA
3.4 i 0.3
0.41 t 0.16
1,2 * 0.5
0.10 ± 0.017
2.2 i 0.6
0.093 i 0.11+
3.0 t 0.7
5.0 t 1.8
3.8 t 0.3
0.3 i 0.2
3.9 ± 0.3
0.04 t 0.07+
3.6 t 0.3
0.06 t 0.12+
3.7 i 0.3
0.09 t 0.16+
Nevada Test
4.4 t 0.4
0.5 ± 1.1+
3.8 i 0.3
0.40 ± 0.08 +
5.3 t 0.3
0.073 i 0.1+
4.2 t 0.3
0.93 t 2.9 +
2.0 ± 0.3 <460
NA
2.0 t 0.3 440 ± 290
NA
4.4 t 0.3 620 i 290
NA
3.0 t 0.3 480 i 290
NA
Site. October 1982
. 3.9 * 0.4 NS
<430
2.3 t 0.3 NS
<430
4.0 t 0.5 NS
<430
3.5 * 0.5 NS
<430
NS
NS
NS
NS
2.7 ± 0.3
1400 t 220
2.3 t 0.7
2.9 t 0.3
1300 ± 240
3.1 i 1.1
3.3 t 0.3
370 t 185
1.1 t 0.22
2.6 ± 0.1
720 ± 140
3.2 t 0.68
0.7 i 0.2
0.0011 i 0.26+
0.8 t 0.2
0.0007 ± 0.0027+
1.3 t 0.2
0.0000 ± 0.0033+
0.7 t 0.1
0.0007 ± 0.0025+
2.2 ± 0.3
NA
1.8 t 0.3
NA
1.4 ± 0.2
1.0 ± 2.0+
1.3 t 0.2
0.0 ± 1.1+
* Wet weight
t Aqueous portion of kidney tissue
+ Counting error exceeds reported activity
NS Not sampled
NA Not analyzed or analysis not complete
Other than the naturally occurring potassium-40 and beryllium-7, gamma-
emitting radionuclides were infrequently reported. Very low concentrations
of cesium-137 (14 and 15 pCi/kg) were found in two muscle samples from the
Tikaboo Valley cattle. Tritium levels were either below detectable limits
or in the range (400-600 pCi/L of blood) comparable with air concentrations
reported by the Noble Gas and Tritium Surveillance Network. The strontium-
90 results are consistent with previous data as shown in Figure 12.
Other than potassium-40, gamma-emitting radionuclides were not detected
in any of the vegetables collected from the four Nevada locations. Tritium
concentrations were also below detectable limits. Strontium and plutonium
analyses are shown in Table 6.
30
-------
^| Bighorn sheep
I I Deer
fcx;:j Cattle
Numbers at top of columns indicate
the number of bone samples in each
category. Numbers prior to 1964
are unknown.
57 59 61 63 65 67 69 71 73 75 77 79 81
CO
Year (1956-1981)
Figure 12. Strontium-90 concentration trends in animal bone.
The majority of marked deer (tagged or radio-equipped) from the Echo
Peak herd moved to the Timber Mountain and 40-Mile Canyon areas by February.
They remained in this general area the remainder of the winter and spring.
By mid-July, they returned to the Pahute Mesa area and were mainly
concentrated around the water sources.
The Rainier Mesa herd moved south to Shoshone Mountain and 40-Mile
Canyon areas with the exception of about three marked animals that stayed
around the northern and eastern sides of Rainier Mesa at or just below the
snow line. As warmer weather approached, they moved to the higher eleva-
tions where they remained until tracking operations ceased in December 1982.
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 exposure.
Until 1965, film badges were used to document external exposure, but TLD's
gradually replaced film as the measurement instrument because of their greater
31
-------
TABLE 6. RADIONUCLIDES IN SELECTED VEGETABLE CROPS - 1982
Vegeta-
tion
Date
Sr-89
(pCi/g ash)
(pCi/kg*)
Sr-90
(pCi/g ash)
(pCi/kg*)
Pu-238
(pCi/g ash)
(pCi/kg*)
Pu-239
(pCi/g ash)
(pCi/kg*)
Las Vegas
Lettuce
06-17-82
Zucchini
07-01-82
Turnips
08-04-82
Lamb's
Quarter
08-04-82
Zucchini
08-04-82
Beets
08-04-82
Turnip
Greens
10-24-82
Zucchini
08-04-82
Turnips
10-24-82
Zucchini
09-01-82
0.65
6.3
-3.1
-18
-1.2
-14
-4.3
-160
-3.7
-24
-70
-1200
0.41
7.0
1.5
11
-2.0
-15
-13
-64
+
±
±
±
±
±
±
+
+
+
±
±
±
+
±
±
±
±
±
±
8.9**
87**
15.0**
84**
7.7**
87**
6.9**
250**
28**
180**
110**
1800**
3.4**
57**
9.0**
65**
0.59**
45**
58**
280**
0.15
1.4
0.13
0.11
0.14
1.6
0.33
12
0.31
2.1
3
48
5.9
10
0.37
2.7
0.5
3.8
0.95
4.6
±
±
±
±
±
±
±
±
±
±
±
+
±
±
±
±
±
±
±
±
0.06
0.58
0.26**
1.5**
0.24**
2.6**
Hiko
0.087
3.2
0.77**
5.0**
3.3**
52**
Rachel
1.3
2.2
0.0009
0.008
-0.00044
-0.0019
-0.0004
-0.0045
0.0006 ±
0.022 ±
0.0048 ±
0.032 ±
0.0047 ±
0.075 ±
0.0065 ±
0.11 ±
0.11 -0.00032 ±
0.76 -0.0023 ±
0.51**
3.9**
Adaven
2.4**
11**
0.06 ±
0.0 ±
0.0037 ±
0.018 ±
± 0.0029**
± 0.028**
± 0.0016**
± 0.0089**
± 0.0019**
± 0.021**
0.0027**
0.1**
0.0064**
0.042**
0.0065**
0.1**
0.011**
0.21**
0.0015**
0.011**
0.002**
0.16**
0.0062** 0
0.03**
0.032
0.32
0.0044
0.025
0.022
0.25
0.055
2.0
0.0037
0.024
0.0064
0.11
0.011
0.19
0.0016
0.011
0.0014
0.011
.00093
0.0045
+
±
±
±
+
±
±
±
±
±
±
±
±
+
+
±
±
±
±
±
0.0087
0.084
0.0058**
0.033**
0.0066
0.07
0.015
0.53
0.0055**
0.037**
0.0078**
0.12**
0.016**
0.28**
0.0034**
0.024**
0.0037**
0.028**
0.0031**
0.015**
* Wet weight
** Counting error exceeds
reported activity
32
-------
sensitivity and precision. From 1970 to 1974 the EMSL-LV used the TLD-12
dosimeter but changed to the TLD-200 in 1975.
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 personal monitoring. Several individuals, some residing
within and some residing without estimated fallout zones from past nuclear
tests at the NTS, have been monitored so that any correlations that may exist
between personal and environmental monitoring could be obtained. The network
consists of 82 monitored locations encircling the NTS with some concentration
in the area of the estimated fallout zones (Figure 13). This arrangement
permits an estimate of average background exposure; yet any increase due to
NTS activities can be detected.
Methods—
In 1982 the TLD Network consisted of 82 stations at both inhabited and
uninhabited locations within a 300-km radius of the CP-1. Each station is
equipped with three Harshaw thermoluminescent dosimeters (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, 48 offsite residents wore dosimeters during 1982. All TLD's were
exchanged quarterly.
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 1 meter above ground level at each station to standardize the
exposure geometry. One dosimeter is issued to each of 48 offsite 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 the
response factor, the six TLD chip readings for each station were averaged.
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 within the range of previous background values for that station.
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. In the
absence of other independent exposure rate measurements, the present exposure
rate is compared with valid prior measurements of natural background.
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.
33
-------
Salt Lake City
| Garrison
Thermoluminescent Dosimeter Stations (82)
Figure 13. Locations monitored with TLD's.
34
-------
Depending on location, the background ranges from 15 to 35 mR per quarter.
The term "background," as used in this context, refers to naturally occurring
radioactivity plus a contribution from residual manmade fission products, such
as worldwide fallout.
Results--
Appendix Table E-12 lists the maximum, minimum, and average dose
equivalent 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 1982. No allowance was made for the small
additional exposure due to the neutron component of the cosmic ray spectrum.
Four stations exhibited exposure in excess of background. They were the
Austin, Mammoth Mountain, and Salt Lake City stations during the 3rd Quarter,
1982 and the Furnace Creek station during the 4th Quarter, 1982. Each
exposure was investigated and the possible cause of exposure noted in the
Quarterly Interim Report. None of the net exposures were attributed to
NTS activities.
Appendix Table E-13 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 offsite resident monitored
during 1982. Seven dosimeters worn by residents exhibited exposures in
excess of background. These exposures are attributed to higher background
levels in the residence than at the station location or to occupational
exposure (resident No. 49). Usually, the average dose equivalent rates of
the offsite 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.
Because of the great range in the results, 42 to 139 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 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
used and was split into two sections for plotting purposes. The results,
shown in Figure 14, indicate that the average exposure at altitudes between
4,000 and 6,000 feet is about 20 mrem/a higher than that at altitudes between
2,000 and 4,000 feet, although both curves follow the same trend as the over-
all 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 residence rather than on the average for the whole area monitored.
35
-------
TABLE 7. DOSIMETRY NETWORK SUMMARY
FOR THE YEARS 1971 - 1981
Environmental Radiation Dose Rate
(mrem/y)
Year
Maximum
Minimum Average
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
250
200
180
160
140
140
170
150
140
140
142
139
102
84
80
62
51
51
60
50
49
51
40
42
160
144
123
114
94
94
101
95
92
90
90
88
110
« 100-
03
D
(A
o
a
x
Ul
"co
3
C
90-
80-
70-
60
50
Station
Altitude
4-6,000 ft.
2-4,000 ft.
I I I I i I i
1975 76 77 78 79 80 81
Calendar Year
Figure 14. Average annual TLD exposure as a function of station altitude.
36
-------
Pressurized Ion Chamber Network (PIC)
This network is located at the 15 Community Monitoring Stations identi-
fied on Figure 2 plus two others at Twin Springs Ranch and Lathrop Wells.
The PIC used is manufactured by Reuter-Stokes and the output is recorded on
both paper tape, so the station manager can observe the response, and on
cassette tape. The cassette tapes are read into a computer at EMSL-LV each
week. The computer output is a table containing hourly, daily, and weekly
summaries of the maximum, minimum, average, and standard deviation of the
ion chamber response.
The data for the last 6 months of 1982 are displayed in Table 8 as the
average and standard deviation of the yR/hr from each station. When these
data are compared to the TLD results for the same 17 stations, it is found
that the PIC response is about 27% higher than the TLD response. This is
attributed, primarily, to the difference in energy response (plateau) of
the two instruments.
TABLE 8. PRESSURIZED ION CHAMBER READINGS - yR/HOUR
Location
Alamo, NV
Austin, NV
Beatty, NV
Cedar City, UT
Ely, NV
Fallini's
Goldfield, NV
Indian Springs, NV
Las Vegas (UNLV), NV
Lathrop Wells, NV
Overton, NV
Pahrump, NV
Rachel, NV
Salt Lake City, UT
Shoshone, CA
St. George, UT
Tonopah, NV
Range
07/21/82 -
07/20/82 -
07/19/82 -
07/21/82 -
07/20/82 -
07/09/82 -
07/19/82 -
07/19/82 -
07/20/82 -
10/04/82 -
07/20/82 -
07/19/82 -
07/21/82 -
07/27/82 -
07/19/82 -
02/08/82 -
07/19/82 -
of Dates
12/28/82
12/27/82
12/27/82
12/28/82
12/27/82
12/21/82
12/27/82
12/27/82
12/28/82
12/27/82
12/28/82
12/13/82
12/27/82
12/27/82
12/27/82
12/28/82
12/27/82
Annual
Mean
14.1
18.7
16.2
10.1
11.8
16.1
14.3
7.9
7.0
13.5
8.2
7.6
16.2
11.0
11.3
8.6
17.1
Standard
Deviation
0.5
0.9
0.4
0.5
0.4
2.6
0.8
0.3
0.3
0.7
0.4
0.4
0.5
0.6
0.3
0.6
0.5
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 body-burdens:
whole-body counting and urinalysis.
37
-------
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
radioactive materials which may have been inhaled or ingested into the body.
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 available 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 also emit low-energy X rays which can be
detected in the lungs by the phoswich detectors.
Network Design
This activity consists of two portions, an Offsite Human Surveillance
Program and a Radiological Safety Program. The design for the Offsite 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 compara-
tive study. The 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.
Methods
The Offsite 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 Nevada Test Site. Biannual counting
is performed in the spring and fall. This program started with 34 families
(142 individuals). In 1982, 16 of these families, 42 individuals, were still
active in the program. The geographical locations of the families which have
participated are shown in Figure 15.
These persons travel to the Environmental Monitoring Systems Laboratory
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 analysis and
a short medical history, complete blood count, thyroid profile and physical
examinations are obtained on each participant. Results of the whole-body
count are available before the families leave the facility and are discussed
with the subjects. The results of the blood and urine tests are sent to the
families, along with a letter of explanation from the examining physician.
In 1981, 15 new families were added to the surveillance program. These
people are in charge of the community monitoring stations described on page
35. As with the first group of families, each person receives a whole-body
count, medical history, complete blood count, thyroid profile, etc.
38
-------
Blue Jay O
Tonopah
-------
In addition to these offsite families, counts are performed routinely on
EPA and EG&G employees as part of the health monitoring programs. Selected
individuals from the general population of Las Vegas and other cities are also
counted to obtain comparative data.
Results
During 1982, a total of 441 whole-body and 596 phoswich spectra were
obtained from individuals, of which 140 were from persons participating in the
Offsite Human Surveillance Program. Also, about 1,400 spectra for calibra-
tions and background were generated. Cesium-137 is generally the only fission
product detected though none was found in the persons counted this year. Body
burdens of Cs-137 in the offsite population detected in previous years were
similar to those in other U.S. residents from California to New York. All
spectra collected in 1982 were representative of normal background for people
and showed only natural potassium-40. No plutonium was detected in any of
the phoswich spectra.
The concentration of tritium in urine samples from the offsite residents
varied from 0 to 2,250 pCi/L with an average value of 418 pCi/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 values
(Salt Lake City residents) is unknown but is not attributed to NTS activities.
As reported in previous years, medical examination of the offsite
families revealed a generally healthy population. In regard to the hemato-
logical examinations and thyroid profiles, no abnormal results were observed
which could be attributed to past or present NTS testing operations. A report
on data for these families, "Results of a Surveillance Program for Persons
Living Around the Nevada Test Site - 1971 to 1980," was published in Health
Physics (Patzer and Kaye 1982).
A summary report of significant findings from the beginning of whole-body
counting at the Laboratory in 1963 has been prepared and is being reviewed.
COMMUNITY MONITORING STATIONS
To increase public knowledge about and participation in radiological
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
established a network of 15 Community Monitoring Stations in the off-NTS
areas. Each station is operated by a local resident, preferably 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)
40
-------
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 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 physician and a veterinarian, qualified by education or experience in the
field of radiobiology, investigate claims of radiation injury to determine
whether or not radiation exposure may be involved.
Investigation of claims from people involves determining the type of
illness, from examining physicians records and diagnoses, and determining the
possibility of radiation exposure through residence history and examination of
historical radiation surveillance data. These investigations can be conducted
by the Medical Liaison Officers Network (MLON) or by the EMSL-LV physician,
depending on where the claim is made. The MLON is composed of physicians, one
from each state, who are trained in radiobiology.
An MLON Conference will be held at the Environmental Monitoring Systems
Laboratory, Las Vegas, Nevada, during the fall of 1983. The purpose of the
meeting will be to update current information on the biological effects of
radiation, its diagnosis and treatment. During 1982 the MLON made 7 investi-
gations of persons with alleged radiation claims, responded to seven inquires
and completed seven evaluations.
The EMSL-LV veterinarian conducts similar investigations for claims of
injury to domestic animals. In most cases the injuries investigated have been
due to common causes such as bacterial infections or unusual events such as
feeding on halogeton, a poisonous plant. In 1981 one potential claim was
investigated; sudden death of two goat kids near Rachel, Nevada. By physical
examination, histopathology and radionuclide analysis of samples, and from
symptoms described by the owner, a diagnosis of enterotoxemia was made.
Radiation exposure apparently played no role in this incident. No such claims
were made in 1982.
PUBLIC INFORMATION PROGRAM
An important function of the Offsite Program has been to create and
maintain, 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 responsibili
is carried out through personal contact with offsite residents by the
ity
with offsite residents by the
41
-------
radiation monitors who advise the residents of program developments and
answer questions about test activities.
For any test where ground motion may be perceptible offsite, monitors
visit remote locations and active mines beforehand to advise operators of
possible 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 offsite.
To improve communications, the monitor's are being linked to a radio
net used by sheepmen north of the NTS so herders and ranchers can be more
readily contacted.
Town Hall type meetings were held in 13 communities of the Community
Monitoring Station Program. In these evening meetings, the objectives and
operation of the stations, their role in the Offsite Radiological Safety
and nuclear testing programs, and data availability were explained. An
open period for questions and free discussion was included.
Other activities included arranging NTS tours for residents of towns
such as Alamo, Nev. and St. George, Utah and for miners, ranchers, etc.
from the offsite areas. Talks were given to civic organizations in February
and May and to high school students in October. In August, a complete
Community Monitoring Station was displayed at the JC State Fair. Hundreds
of fact sheets were distributed during these activities.
DOSE ASSESSMENT
Dose assessment calculations for NTS-related radioactivity are not
possible because detectable levels of radioactivity from the 1982 nuclear
testing program at the NTS were not observed offsite by any of the monitoring
networks. However, an exposure can be calculated by using atmospheric
dispersion and reported releases of radioactivity from the NTS (Table 1).
This is shown below. Residual radioactivity was observed in waters from
wells in other nuclear testing areas known to be contaminated during past
nuclear tests at the Project Dribble Site near Hattiesburg, Mississippi;
Project Gnome near Malaga, New Mexico; and at the Project Long Shot Site on
Amchitka Island, Alaska. However, the waters from these contaminated wells
are not used for drinking purposes.
An estimate of exposure of an average adult in Nevada due to worldwide
radioactivity can be made based on the data from the monitoring networks. The
principal data are strontium-90 in milk (1.2 pCi/L) from previous atmospheric
tests; krypton-85 in air (24 pCi/m3) from power reactors and reprocessing
plants; and plutonium-239 in air (58 aCi/m3) from previous atmospheric tests.
Assumptions: 1) Breathing rate = 7,300 m^/a
2) Water intake = 438 L/a, milk = 1/2 of water or 219 I/a
3) 8,766 hr/a
42
-------
From DOE/EP-0023 Appendix B (DOE 1981a); first-year Dose Factors are:
1) Kr-85 (immersion) 2,200 mrem/hr per pCi/mL, whole body
(pCi/mL = 1012 pCi/m3),
2) Sr-90 (ingestion) 45 mrem/yCi intake, whole body, and
3) Pu-239 (inhalation) 48,000 mrem/yCi to lung.
Calculated annual dose:
24 pCi/m3
Kr-85: 2,200 mrem/hr x 8,766 hr/a x = 4.63 x 10~4 mrem/a
10*2 PCi/m3
Sr-90: 45 mrem/yCi x 1Q-6 yCi/pCi x 1.2 pCi/L x 219 L/a = 0.0118 mrem/a
Pu-239: 4.8 x 10^ mrem/pCi x 30 aCi/m3 x 10-12 Mci/aCi x 7,300 m3/a =
0.01 mrem/a
The total annual dose to the average adult in Nevada from worldwide
radioactivity detected by EMSL-LV monitoring networks is then 0.022 mrem.
Natural radioactivity in the body (K-40, C-14, Ra-226, etc.) causes annual
internal doses ranging from 26 to 36 mrem per year (FRC 1960), and the
calculated internal dose is only 0.2 percent of this 10 mrem variation.
The external exposures to Nevadans range from 40 to 142 mrem/a as
measured by the TLD network. In the U.S., reported external exposures
range from 63 to 200 mrem/a, depending on elevation (sea coast or Rocky
Mountains) and on the natural radioactivity in the soil (NCRP 1971). The
exposures measured by the TLD's compare favorably with that range as the
TLD station's altitude varies from 500 to over 7,000 feet above MSL and the
uranium content in soil probably also varies markedly among stations.
The highest postulated annual dose estimate to man, from the results
of the 1980 Biomonitoring Program, was calculated to be 0.17 mrem. This
would result from the Cs-137 content of muscle from the NTS beef herd if an
individual ate 0.5 kg per day for the whole year and if the muscle tissue
had the maximum measured cesium concentration all year. The highest postu-
lated annual dose from Pu-239 was calculated to be 0.0016 mrem to the
skeleton if 1/2 Ib of the leafy vegetable, Lamb's Quarter, were eaten each
day.
No radioactivity released at the NTS was measured offsite, therefore,
the dose to the offsite population from these releases was calculated by
using average weather data and atmospheric diffusion equations. Wind
direction and speed data were available for a 12-year period as were 25,000
hourly observations of Pasquill stability class. Based on noble gas releases
shown in Table 1, the estimated population dose to the 4600 people within
80 km of CP-1 was 9.9 x 10~6 man-rem. The highest estimated dose was 3 x
ID-6 mrem/yr to an individual living in Rachel, with lesser amounts to
individuals in Armogosa, Beatty, Lathrop Wells and Indian Springs, Nevada.
43
-------
SECTION 6
REFERENCES
ANSI, 1975. "American National Standard Performance Testing and Procedural
Specifications for Thermo!uminescent Dosimetry (Environmental
Applications)." ANSI N545-1975. American National Standards Institute,
Inc., New York, New York.
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, 1973.
California, 1982. Personal communication from California county agents.
DOE, 1981a. A Guide for Environmental Radiological Surveillance at U.S.
Department of Energy Installations. Report No. DOE/EP-0023, July 1981.
DOE, 1981b. Environmental Protection, Safety, and Health Protection Program
for DOE Operations; Chapter XI. Requirements for Radiation Protection.
Order DOE 5480.1, U.S. Department of Energy, April 1981.
DOE, 1981c, Environmental Protection, Safety, and Health Protection
Information Reporting Requirements. Order DOE 5484.1, U.S. Department of
Energy, Feburary 1981.
DOE, 1983. Personal communication from Health Physics Division, DOE/NV, April
1, 1983.
EPA, 1981. "Environmental Radioactivity Laboratory Intercomparison Studies
Program 1978-1979." EPA-600/4-81-004. Environmental Monitoring and
Support Laboratory, U.S. Environmental Protection Agency, Las Vegas,
Nevada. (Available from U.S. Department of Commerce, NTIS, Springfield,
VA 22161.)
ERDA, 1977. "Final Environmental Impact Statement, Nye County, Nevada."
ERDA-1551. U.S. Energy Research and Development Administration, Nevada
Operations Office, Las Vegas, Nevada. (Available from U.S. Department of
Commerce, NTIS, Springfield, VA 22161.)
Fenske, P. R. and T. M. Humphrey, Jr., 1980. "The Tatum Dome Project Lamar
County, Mississippi" NVO-225. U.S. Department of Energy. Nevada
Operations Office, Las Vegas, Nevada.
44
-------
FRC, 1960. Background Material for the Development of Radiation Protection
Standards. Staff Report No. 1, Federal Radiation Council, May 1960.
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.
Holder, L. E. "National Network of Physicians Investigates Claims of
Radiation Injury in the Non-Occupationally Exposed Population." American
Journal of Public Health. October 1972.
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.
Jarvis, A. N. and L. Siu, 1981. Environmental Radioactivity Laboratory
Intercomparison Studies Program - FY 1981-82, EPA-600/4-81-004, Las
Vegas, NV, February 1981.
National Park Service, 1980. Personal communication with Chief Ranger R.
Rainer, Death Valley National Monument, Death Valley, California.
NCRP, 1975. Natural Background Radiation in the United States. NCRP Report
No. 45, National Council on Radiation Protection and Measurements,
November 1975.
NCRP, 1971. Basic Radiation Protection Criteria. NCRP Report No. 39,
National Council on Radiation Protection and Measurements, January 1971.
Nevada Department of Agriculture, 1979. "Nevada Agricultural Statistics
1979." Nevada Crop and Livestock Reporting Service, Reno, Nevada.
Patzer, R. G. and M. E. Kaye, 1982. "Results of a Human Surveillance Program
in the Offsite Area Surrounding the Nevada Test Site." Health Phys.
43:791-801.
Potter, G. D., R. F. Grossman, W. A. Bliss, D. J. Thome, 1980. "Offsite
Environmental Monitoring Report for the Nevada Test Site and Other Test
Areas used for Underground Nuclear Detonation, January through December
1979." EMSL-LV-0539-36. U.S. Environmental Protection Agency,
Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Quiring, R. E., 1968. "Climatological Data, Nevada Test Site, Nuclear
Rocket Development Station (NRDS)." ERLTM-ARL-7. ESSA Research
Laboratories, Las Vegas, Nevada.
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), April 1981.
45
-------
Smith, D. D., K. R. Giles and D. E. Bernhardt, 1982. Animal Investigation
Program 1980 Annual Report: Nevada Test Site and Vicinity. U.S.
Environmental Protection Agency Report EPA 600/3-82-077, Aug. 1982.
Toonkel, L. E., 1980. "Appendix to Environmental Measurements Laboratory,
Environmental Quarterly." EML-371 Appendix, UC--11. Environmental
Measurements Laboratory. U.S. Department of Energy, New York, N.Y.
10014.
UNSCEAR, 1977. Sources and Effects of Ionizing Radiations, United Nations
Scientific Committee on the Effects of Atomic Radiation 1977 Report to
the General Assembly.
Utah Department of Agriculture, 1979. "Utah Agricultural Statistics, 1978."
State of Utah Department of Agriculture, Salt Lake City, Utah.
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, CO.
46
-------
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 I 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 Nell is 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
airborne radioactivity could pass over public lands.
Climate
The climate of the NTS and surrounding area is variable, due to its
variations 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. (1975), 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 (Houghton et al. 1975)
summarizes the characteristics of climatic types for Nevada.
According to Quiring (1968), the NTS average annual precipitation ranges
from about 10 cm at the lower elevations to around 25 cm on the higher
elevations. During the winter months, the plateaus may be snow-covered for a
period of several days or weeks. Snow is uncommon on the flats. Temperatures
vary considerably with elevation, slope, and local air currents. The average
daily high (low) temperatures at the lower altitudes are around 50F (25F) in
January and 95F (55F) in July, with extremes of 110F and -15F. Corres-
ponding temperatures on the plateaus are 35F (25F) in January and 80F
(65F) in July with extremes of 100F and -20F. Temperature extremes as low
as -30F and higher than 115F have been observed.
47
-------
TABLE A-l. CHARACTERISTICS OF CLIMATIC TYPES IN NEVADA (from Houghton et al. 1975)
00
Climate Type
Alpine
tundra
Humid
continental
Subhumid
continental
Mid-latitude
steppe
Mid-latitude
desert
Low- latitude
desert
Mean Temperature
°C
(°F)
Winter Summer
-18°
( 0°
-12°
(10°
-12°
(10°
-7°
(20°
-7°
(20°
-4°
(40°
to -9°
to 15°)
to -1°
to 30°)
to -1°
to 30°)
to 4°
to 40°)
to 4°
to 40°)
to 10°
to 50°)
4°
(40°
10°
(50°
10°
(50°
18°
(65°
18°
(65°
27°
(80°
to
to
to
to
to
to
to
to
to
to
to
to
10°
50°)
21°
70°)
21°
70°)
27°
80°)
27°
80°)
32°
90°)
Annual Precipitation
cm
(inches)
Total* Snowfall
38
(15
64
(25
30
(12
15
( 6
8
( 3
5
( 2
to
to
to
to
to
to
to
to
to
to
to
to
114
45)
114
45)
64
25)
38
15)
20
8)
25
10)
Medium to
heavy
Heavy
Moderate
Light to
moderate
Light
Negligible
Dominant
Vegetation
Alpine
meadows
Pine-fir
forest
Pine or scrub
woodland
Sagebrush,
grass, scrub
Greasewood,
shadscale
Creosote
bush
Percent
of Area
--
1
15
57
20
7
*Limits of annual precipitation overlap because
water balance.
of variations in temperature which affect the
-------
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
(Quiring 1968). Because of the prevalent mountain/valley winds in the basins,
south to southwest winds predominate during daylight hours of most months.
During the winter months southerly winds have only a slight edge over
northerly winds for a few hours during the warmest part of the day. These
wind patterns may be quite different at other locations on the NTS because of
local terrain effects and differences in elevation.
Geology and Hydrology
Two major hydrologic systems shown in Figure A-l exist on the NTS (ERDA
1977). Ground water in the northwestern part of the NTS or in the Pahute Mesa
area has been reported to flow 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.
It is estimated that the 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 southwestward 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 agricultural activity is grazing of cattle and sheep.
Minor agriculture, primarily the growing of alfalfa hay, is found in this
portion of the State within 300 km of the NTS Control Point-1 (CP-1). Many of
the residents grow or have access to locally grown fruits and vegetables.
Many recreational areas, in all directions around the NTS (Figure 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.
49
-------
Ash Meadows
Ground Water System
\
X
v
/
Pahute Mesa
Ground Water
System
V x
0 10 20 30 40
3 81 Scale in Kilometers
Flow Direction
Ground Water System Boundaries
Silent Canyon Caldera
Timber Mountain Caldera
Figure A-l. Groundwater flow systems around the Nevada Test Site.
50
-------
O>
OJ
O)
O)
JC
O
O
CO
2
O)
3
to
03
O)
c
O)
CM
£
3
CD
-------
Population Distribution
Figure A-3 shows the current population of counties surrounding the NTS
based on preliminary 1980 census figures. Excluding Clark County, the major
population center (approximately 462,000 in 1980), 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 offsite 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 3,600, is located about 72 km south-southwest of the NTS
CP-1. The Amargosa Farm Area, which has a population of about 1,600, is
located about 50 km southwest 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.
The Mojave Desert of California, which includes Death Valley National
Monument, lies along the southwestern border of Nevada. The National Park
Service (1980) estimates that the population within the Monument boundaries
ranges from a minimum of 900 permanent residents during the summer months to
as many as 35,000 tourists and campers on any particular day during the major
holiday periods in the winter months, and as many as 80,000 during "Death
Valley Days" in the month of November. The largest town and contiguous
populated area in the Mojave Desert is Barstow, located 265 km south-southwest
of the NTS, with a population of about 17,600. The next largest populated
area is the Ridgecrest-China Lake area, which has a population of about 20,000
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-northwest 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
communities 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
9,200. Figures A-4 through A-7 show the domestic animal populations in the
counties near the NTS.
52
-------
Storey
1,500
Carson
City
33,600
0 50 100 150
3/81 Scale in Kilometers
Figure A-3. Population of Arizona, California, Nevada, and Utah
counties near the Nevada Test site (1980).
53
-------
Figure A-4. Distribution of family milk cows and goats, by county (1981),
54
-------
Scale m Miles
9 25 50 75 100
0 50 100 150
3 83 Scale in Kilometers
Figure A-5. Distribution of dairy cows, by county (1981).
55
-------
Storey-
100
Carson
City
1,300
Figure A-6. Distribution of beef cattle, by county.
56
-------
Figure A-7. Distribution of sheep, by county.
57
-------
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
Nal(Tl) Gamma
Spectrometry**
IG & Ge(L1)
Gamma
Spectrometry**
Gross beta
on air filters
Analytical
Equipment
Nal detector
calibrated at
10 keV per
channel (0.05-
2.0 MeV range).
IG or Ge(L1)
detector cali-
brated at 0.5 keV/
channel (0.04
to 2 MeV range)
Individual detec-
tor efficiencies
ranging from
M5X to 35%.
Low-level end
window, gas
flow proportional
counter with a
12.7 cm diameter
window (80 pg/cm2)
Counting
Period
(m1n)
10 m1n. for
air charcoal
cartridges
Individual
air filters,
30 m1n;
air filter
composites,
M200 m1n.
100 m1n for
milk, water,
suspended
solids.
30
Analytical Sample
Procedures Size
Radlonucllde 120-1200 m3
concent ra- for air
tlons quan- charcoal
tlfled from cartridge
gamma spec- samples.
tral data by
computer
using a least
squares
technique.
Radlonucllde 120-1200 m3
concentration for air
quantified filters;
from gamma 3-1/2 liters
spectral data for milk
by on-line and water.
computer pro-
gram. Radio-
nuclldes In air
filter composite
samples are
Identified only.
Samples are 120-1200 m3
counted after
decay of
natural Iy-occurr1ng
radlonuclldes
and, If necessary
extrapolated to
mid-point of
collection 1n
accordance with
t_-1.2 decay or an
experimentally-
derived decay.
Approximate
Detection
Limit*
0.04 pC1/m3.
For routine milk
and water generally,
•^5 pCI/L for
most common fallout
radlonuclldes In a
simple spectrum.
Filters for LTHMP
suspended solids,
6 pC1/L. Air
filters, 0.04 pCi/m3.
0.5 pd/sample.
58
(continued)
-------
TABLE B-l. (Continued)
Type of
Analysis
Sr-89-90
H-3
H-3 Enrichment
(Long-Term
Hydrological
Samples)
Pu-238,239
Kr-85, Xe-133,
Xe-135
Counting
Analytical Period
Equipment (m1n)
Low-background 50
th1n-w1ndow,
gas-flow pro-
portional
counter with a
5.7-cm diameter
window (80 wg/cm?)
Automatic 200
liquid
scintillation
counter with
output printer.
Automatic 200
scintillation
counter with
output printer.
Alpha spectro- 1000-1400
meter with 450
mm, 300- vm
depletion depth,
silicon surface
barrier detectors
operated In
vacuum chambers.
Automatic 200
liquid scintil-
lation counter
with output
printer.
Analytical :
Procedures
Separation of
strontium by wet
chemical method.
After an Ingrowth
period, yttrium
1s separated and
Sr-90 activity 1s
calculated from
the activity of the
Y-90 daughter. Sr-8!
activity 1s obtained
by decay curve
analysis.
Sample pre-
pared by
distillation.
Sample concen-
trated by
electrolysis
followed by
distillation.
Water sample or
acid-digested
tissue samples
separated by 1on
exchange, electro-
plated on stainless
steel planchet.
Physical
separation by
gas chroma-
tography; dis-
solved 1n
toluene
"cocktail" for
counting
Sampl e
Size
1.0 liter
for milk
or water.
0.1-1 kg
for tissue.
9
4 ml
for water
250 ml
for water
1.0 liter
for water;
0.1-1 kg
for tissue;
5,000-
10,000 m3
for air.
0.4-1.0 m3
for air
Approximate
Detection
Limit*
Sr-89 = 5 pCi/L
Sr-90 * 2 pCi/L.
400 pC1/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/m^
for plutonlum on air
filters.
Kr-85, Xe-133, Xe-135
- 4 pC1/m3.
*The detection limit for all samples received after January 1, 1978 1s defined as 3.29 slgma where
slgma equals the counting error of the sample and Type I error - Type II error * 5 percent.
(J. P. Corley, D. H. Denham, R. E. Jaquish, D. E. Michels, A. R. Olsen, D. A. Waite, A Guide for
Environmental Radiological Surveillance at U.S. Dept. of Energy Installations, July 1981, Office
of Operational Safety Report DOE/EP-0023, U.S. DOE. Washington, D. C.)
**Ganma Spectrometry performed by thallium activated sodium Iodide (Nal(Tl)), Intrinsic germanium (IG),
or lithium-drifted germanium diode (6e(L1)) detectors.
59
-------
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 involves the collection and analysis of duplicate samples from
the ASN, the NGTSN, the LTHMP, and the MSN. Due to difficulties anticipated
in obtaining sufficient quantities of milk for duplicate samples from the Milk
Surveillance Network, duplicate samples are normally collected during the
annual activation of the SMSN. In general, the NGTSN samples are 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 A-2 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, s^, of each
TABLE C-l. SAMPLES AND ANALYSES FOR DUPLICATE SAMPLING PROGRAM
Surveillance
Network
ASN
NGTSN
Dosimetry
SMSN
Number of
Sampling
Locations
121
16
82
167
Sets of
Samples Duplicate
Collected Samples
Per Year Collected
9,200 456
779 (NG) 44
862 (H3) 6
320 320
240 26
Number
Per Set
2
2
4-6
2
Sample
Analysis
Gross beta,
Y Spectrometry
Kr-85, H-3,
H20, HTO
Effective dose
from gamma
K-40, Sr-89,
Sr-90
LTHMP
134
254
27
H-3
60
-------
set of replicate TLD results (n=6) was estimated from the results by
the standard expression,
k _ 2
s2 = Z (x, - x) / (k - 1)
• 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 deviation is obtained by taking the square root.
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:**
fk „ k I
l (ni - l)Si2/ I (ni - 1)
|_i=l i=l J
1/2
where n-j-1 = the degrees of freedom for n samples collected for the
th replicate sample
2
s-j = the expected variance of the th 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 cr2).
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
precision data in Table C-2 represents errors principally in analysis.
*Snedecor, G. W., and W. G. Cochran. Statistical Methods. The Iowa State
University Press, Ames, Iowa. 6th Ed. 1967. pp. 39-47.
**Freund, J. E. Mathematical Statistics. Prentice Hall, Englewood, New
Jersey. 1962. pp 189-235.
61
-------
TABLE C-2. SAMPLING AND ANALYTICAL PRECISION
Surveillance
Network
Analysis
Sets of
Replicate
Samples
Evaluated
Coefficient
of Variation
ASN
Gross
Be-7
26
9
51
37
NGTSN
Kr-85
H-3 (1981 data)
H20
44
17
8
9.7
23
12
Dosimetry
SMSN
Y(TLD)
K-40
Sr-89
Sr-90
328
33
26
26
3.2
11
45
35
LTHMP
H-3 (conv. 1981)
H-3 (enrich. 1981)
6
32
10
18
ACCURACY OF ANALYSIS
Data from the analysis of intercomparison samples are statistically
analyzed and compared to known values and values obtained from other
participating laboratories. A summary of the statistical analysis is given in
Table 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 (Jarvis and Siu). 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 variation. However, if the parameters exceed these
limits, one must suspect that there is some cause other than normal statis-
tical variations that contributed to the difference between the measured
values and the known value. As shown by this table, the strontium-90
analysis for milk samples exceeded the control limit in two out of four
cross-checks and nearly exceeded it on one other. The problem was attributed
to contamination in the yttrium carrier for which an overcorrection was
made. A new supply of uncontaminated yttrium carrier is now in use.
62
-------
TABLE C-3. 1982 QUALITY ASSURANCE INTERCOMPARISON RESULTS
Analysis Month
Mean of
Replicate Known
Analyses Value
(x 10-9 yCi/ml) (x 10-9yCi/ml)
Normalized
Deviation from:
Known Cone.
H-3 in
water
H-3 in
urine
Co-60 in
water
Ru-106
Cs-134 in
water
Cs-137 in
water
1-131 in
milk
Sr-89 in
mi 1 k**
Sr-90 in
mi 1 k**
137-Cs in
milk
Feb
Apr
Jun
Aug
Oct
May
Dec
Feb
Jun
Oct
Feb
Jun
Oct
Feb
Jun
Oct
Feb
Jun
Oct
Apr
Oct
Jan
Apr
Jul
Oct
Jan
Apr
Jul
Oct
Apr
Oct
1735
2557
1681
2866
2349
1279
3609
20
28
19
<75
<75
<75
21
30
17
23
24
19
<5
41
<24
<36
<50
<37
11
14
25
12
27
33
1820
2860
1830
2890
2560
1330
3830
20
29
20
0
0
30
22
35
19
23
25
20
0
42
12
25
42
0
15
16
25
19
28
34
-0.4
-1.5
-0.8
-0.1
-1.0
-0.3
-1.0
-0.1
-0.2
-0.3
_
-
-
-0.3
-1.7
-0.7
-0.1
-0.3
-0.2
_
-0.4
—
-
-
-
-4.9
-2.9
-0.2
-8.1
-0.3
-0.4
(continued)
63
-------
TABLE C-3. (Continued)
Mean of
Replicate Known Normalized
Analyses Value Deviation from:
Analysis Month (x ICT9 jiCi/ml) (x 10~9 yCi/ml) Known Cone.
Ba-140 in
milk
Cs-137 in
air filters
(pCi/filter)
Apr
Oct
Mar*
Sep
Nov
<6
<6
32
24
36
0
0
23
27
Not available
-
3.1
-0.9
-
*Grand average of all laboratories participating was 27 ± 6 (Is).
**These analyses were performed by Government contractor.
To measure the performance of the contractor laboratory for analysis
of animal and vegetable samples, a known amount of activity was added to
several samples. The reported activity is compared to the known amount in
Table C-4. The Sr-90 results indicated a bias of - 35 percent.
QUALITY ASSURANCE-DOSIMETRY
Radioanalytical counting systems and TLD systems are calibrated using
radionuclide standards that are traceable to the National Bureau of Standards
(NBS). These standards are obtained from the Quality Assurance Division at
EMSL-LV or from NBS. Each standard source used for TLD calibrations is
periodically checked for accuracy in accordance with procedures traceable to
NBS.
To determine accuracy of the data obtained from the TLD systems,
dosimeters are periodically submitted to the University of Texas School of
Public Health for intercomparisons of environmental dosimeters. Dosimeters
were submitted to the Sixth International Intercomparison in July 1981.
The results for which are not yet available. The results from the Fifth
Intercomparison are shown in Table C-5. All TLD measurements are performed
in conformance with standards proposed by the American National Standards
Institute (ANSI 1975).
64
-------
TABLE C-4. QUALITY ASSURANCE RESULTS FOR THE BIOENVIRONMENTAL PROGRAM
Sample Type
and
Shipment
Number
Vegetation
Zucchini A
No. 39
Zucchini B
No. 39
Zucchini C
No. 39
Zucchini D
No. 39
Bone Ash
Ash No. 6
No. 31
Ash No. 7
No. 31
Ash No. 9
No. 31
Hamburger
Meat
Bov E Muscle
No. 39
Bov F Muscle
No. 39
Bov G Muscle
No. 39
Duplicate
Samples
MD-2 Bone
No. 39
MD-Yellow
Bone
Wo. 39
Activity Added Activity Reported
(pCi/kg*) Vegetable (pCi/kg*) Vegetable
Nuclide (pCi/g ash) Bone (pCi/g ash) Bone
Pu-239
Sr-90
Pu-239
Sr-90
Pu-239
Sr-90
Pu-239
Sr-90
Sr-90
Sr-90
Sr-90
Pu-239
Pu-239
Pu-239
Pu-239
Sr-90
Pu-239
Sr-90
42.4
56.1
34
45
35
45
0
0
0
3.12
10.8
1.26
1.26
0
0
0
0
0
33 ± 4.3
30 ± 4.4
37 ± 5.2
33 ± 5.1
34 ± 4.5
33 ± 5.1
0.61 ± 0.17
1.3 ± 1.7
1.5 ± 0.26
3.4 ± 0.56
9.4 ± 1.5
1.5 ± 0.3
1.1 ± 0.26
0.00 ± 0.036
0.00 ± 10.33
1.4 ± 0.21
0.00 ± 1.1
1.3 ± 0.21
Preci-
% Bias* ion No.*
-23
-48
+7
-30
-5
-34
-39
-27
-19
-13
--
.066
* Wet weight / >
t Bias (B) = Recovery -1; recovery is average recovery [xl
where xi = net activity reported
u = activity added
Precision (Cv) = 2
. x2)
x T---- where
1.128
= first value
= seconc| va]ue
65
-------
TABLE C-5. SUMMARY RESULTS OF THE FIFTH INTERNATIONAL
INTERCOMPARISON OF ENVIRONMENTAL DOSIMETERS
Quantity
Mean
Standard
Deviation
Comments
Summary of "Beginning" Exposure Laboratory Results (mR):
EMSL-LV Dosimeters 66.4
All Dosimeters 75.8
Calculated Exposure 75.2
5.0 EMSL-LV results 12% lower
20.2 than all dosimeters and
3.8 11.7% lower than the
calculated exposure.
Summary of "End" Exposure Laboratory Results (mR):
EMSL-LV Dosimeters 80.2
All Dosimeters 90.7
Calculated Exposure 88.4
Summary of Field Results (mR):
EMSL-LV Dosimeters 24.0
All Dosimeters 30.2
Calculated Exposure 30.0
6.0 EMSL-LV results 11.6% lower
15.6 than all dosimeters and 9.3%
4.4 lower than the calculated
exposure.
1.8 EMSL-LV results 20% lower
7.3 than all dosimeters and
3.0 20% lower than the
calculated exposure.
66
-------
APPENDIX D. RADIATION PROTECTION STANDARDS FOR
EXTERNAL AND INTERNAL EXPOSURE
DOE ANNUAL DOSE COMMITMENT
The annual dose commitment tabulated below is from "Basic Radiation
Protection Criteria" in NCRP Report No. 39.
Dose Limit to Individuals Dose Limit to Suitable
in Uncontrolled Area at Sample of the Exposed
Points of Maximum Probable Population in an
Type of Exposure Exposure (rem) Uncontrolled Area (rem)
Whole body, gonads, 0.5 0.17
or bone marrow
Other organs 1.5 0.5
DOE CONCENTRATION GUIDES
The concentration guides (CG's) in Table D-l are from the DOE Order
5480.1, Chapter XI, "Requirements for Radiation Protection." All values are
annual average concentrations. The Concentration Guides are based on a
suitable sample of the exposed population in an uncontrolled area. The
final column lists the Minimum Detectable Concentration from Appendix B as
a percent of the CG.
EPA CONCENTRATION GUIDE
In 1976 the Environmental Protection Agency published concentration
guides for drinking water (Part 141, CFR 40, Amended) which included 20,000
pCi/L for tritium. This concentration would result in 4 mrem/a to an
individual from continuous exposure. The percent CG values for tritium in the
tables of Appendix E may be multiplied by 50 if the relation to this guide
is desired, e.g., a <0.01 would become <0.5.
67
-------
TABLE D-l. DOE CONCENTRATION GUIDES
Sampl ing
Network or Program Medium
Air Surveillance air
Network
Noble Gas and Tritium air
Surveillance Network
Long-Term water
Hydrological Program
Milk Surveillance milk
Networks
Radio-
nucl ide
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
Kr-85
H-3
Xe-133
Xe-135
H-3
Sr-89
Sr-90
Cs-137
Ra-226
U-234
U-235
U-238*
Pu-238
Pu-239
H-3
Cs-137
Sr-89
Sr-90
CG
(pC1/m3)
1.3 x 104
3.3 x 102
1.0 x 103
2.3 x 103
1.0 x 103
3.3 x IQl
1.3 x 103
1.7 x 102
3.3 x 102
1.3 x 103
1.7 x 103
6.7 x 101
2.0 x 10-2
1.0 x 105
6.7 x 104
1.0 x 105
3.3 x 104
(pCI/L)
1.0 x 106
1.0 x 103
1.0 x 102
6.7 x 103
1.0 x 101
1.3 x 103
1.3 x 103
2.0 x 102
1.7 x 103
1.7 x 103
1.0 x 106
6.7 x 103
1.0 x 103
1.0 x 102
MDC as % of CG
3.1 x 10-4
1.2 x lO'2
4.0 x 10-3
1.7 x 10-3
4.0 x 10~3
1.2 x 10-1
3.1 x 10-3
2.4 x lO'2
1.2 x 10~2
3.1 x lO'3
2.4 x lO'3
6.0 x lO'2
5.0 x 10"2
4.0 x 10-3
6.0 x 10-1
4.0 x 10-3
1.2 x 10-2
1.0 x ID"3
5.0 x 10-1
2.0 x 10-°
1.5 x 10-1
4.7 x ID"3
2.4 x 10~3
1.0 x 10-3
1.5 x 10-1
5.0 x 10-1
2.0 x 10-°
*Concentration based on chemical toxicity.
68
-------
APPENDIX E. DATA SUMMARY FOR MONITORING NETWORKS
TABLE E-l. 1982 SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
CONTINUOUSLY OPERATING STATIONS
SAMPLING LOCATION
DEATH VALLEY JCT CA
FURNACE CREEK CA
SHOSHONE CA
ALAMO NV
AUSTIN NV
BEATTY NV
STONE CABIN RANCH NV
CURRANT NV - BLUE EAGLE RANCH
ELY NV
GOLDFIELD NV
NTS NV - AREA 51
HIKO NV
INDIAN SPRINGS NV
LAS VEGAS NV
NYALA NV
OVERTON NV
NO. DAYS
DETECTED
/SAMPLED
2.0/362.1
10.0/341.8
20.7/327.4
14.0/354.8
12.1/236.2
17.9/343.1
6.9/336.4
17.8/360.1
18.5/347.8
14.5/362.3
10.0/318.0
13.0/357.1
16.2/363.7
13.0/362.5
11.0/365.8
11.6/355.9
RAD 10-
NUCLIDE
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
RADIOACTIVITY
(pCi/m3)
MAX
0.58
0.44
0.56
0.63
0.58
0.71
0.60
0.65
0.47
0.77
0.51
0.63
0.41
0.50
0.64
0.52
MIN
0.58
0.24
0.21
0.28
0.40
0.14
0.28
0.22
0.30
0.35
0.36
0.37
0.25
0.29
0.33
0.34
CONC.
AVG
0.0032
0.0086
0.023
0.016
0.024
0.022
0.0086
0.022
0.019
0.021
0.014
0.020
0.015
0.013
0.014
0.013
(CONTINUED)
69
-------
TABLE E-l. (CONTINUED)
SAMPLING LOCATION
PAHRUMP NV
SCOTTY'S JCT NV
SUNNYSIDE NV
RACHEL NV - ROBINSON TRAILER
TONOPAH NV
TTR NV
FALL INI1 S (TWIN SPGS) RANCH NV
CEDAR CITY UT
DELTA UT
MILFORD UT
ST GEORGE UT
SALT LAKE CITY UT
NO. DAYS
DETECTED
/SAMPLED
17.0/353.5
10.0/350.3
13.2/336.3
6.9/354.8
17.6/365.3
22.9/227.8
8.9/362.7
17.0/357.2
122.1/354.6
106.3/329.7
8.0/363.0
35.0/306.5
RADIO-
NUCLIDE
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
RADIOACTIVITY
(pC1/m3)
MAX
0.63
0.56
0.53
0.60
0.84
0.62
0.38
0.69
0.58
0.51
0.54
0.51
MIN
0.21
0.46
0.39
0.46
0.18
0.19
0.36
0.19
0.15
0.15
0.31
0.27
CONC.
AVG
0.020
0.014
0.018
0.010
0.024
0.036
0.0091
0.021
0.096
0.089
0.0085
0.046
THE FOLLOWING STATION HAD NEGLIGIBLE GAMMA-SPECTRA:
LATHROP WELLS NV
70
-------
TABLE E-2. 1982 SUMMARY OF ANALYTICAL RESULTS FOR ASN STANDBY STATIONS -
OPERATED 1 OR 2 WEEKS PER QUARTER
SAMPLING LOCATION
KINGMAN AZ
PHOENIX AZ
SELIGMAN AZ
WINSLOW AZ
BAKER CA
BARSTOW CA
BISHOP CA
INDIO CA
LONE PINE CA
NEEDLES CA
RIDGECREST CA
DENVER CO
DURANGO CO
GRAND JUNCTION CO
PUEBLO CO
BOISE ID
IDAHO FALLS ID
POCATELLO ID
PRESTON ID
TWIN FALLS ID
NO. DAYS
DETECTED
/SAMPLED
2.0/28.0
18.2/31.3
2.0/28.0
14.0/28.0
6.0/19.3
12.0/50.8
4.6/27.7
4.0/23.1
20.0/32.0
11.0/28.0
10.1/25.4
10.0/28.1
3.0/21.4
13.1/23.9
4.1/28.3
3.0/34.9
3.1/27.9
3.0/25.9
5.0/27.0
11.0/28.0
RAD 10-
NUCLIDE
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
RADIOACTIVITY
(pC1/m3)
MAX
0.29
0.97
0.36
0.35
0.17
0.36
0.36
0.22
0.32
0.22
0.35
0.55
0.32
0.55
0.34
0.14
0.24
0.21
0.33
0.37
MIN
0.29
0.17
0.36
0.13
0.16
0.22
- 0.25
0.19
0.24
0.12
0.22
0.18
0.32
0.24
0.31
0.14
0.24
0.21
0.29
0.27
CONC.
AVG
0.021
0.21
0.026
0.13
0.052
0.067
0.051
0.036
0.17
0.064
0.11
0.13
0.044
0.19
0.046
0.013
0.027
0.024
0.056
0.12
(CONTINUED)
71
-------
TABLE E-2. (CONTINUED)
SAMPLING LOCATION
DODGE CITY KS
LAKE CHARLES LA
MONROE LA
MINNEAPOLIS MN
CLAYTON MO
ST JOSEPH MO
BILLINGS MT
BOZEMAN MT
MISSOULA MT
NORTH PLATTE NB
BATTLE MOUNTAIN NV
BLUE JAY NV
CALIENTE NV
CURRANT NV - ANGLE WORM RANCH
CURRIE NV
DUCKWATER NV
ELKO NV
EUREKA NV
FALLON NV
FRENCHMAN STATION NV
LOVELOCK NV
NO. DAYS
DETECTED
/SAMPLED
8.0/28.0
2.0/27.9
5.5/28.1
4.0/36.5
4.0/22.0
18.0/39.5
4.9/26.3
7.2/27.4
11.2/28.3
8.1/25.2
3.0/21.0
2.9/13.9
16.1/27.1
11.9/28.2
11.3/20.1
2.0/6.0
9.1/14.9
15.2/27.0
2.0/20.9
2.0/20.0
8.8/21.5
RADIO-
NUCLIDE
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
RADIOACTIVITY
(pC1/m3)
MAX
0.32
0.18
0.24
0.37
0.23
0.29
0.34
0.28
0.27
0.22
0.30
0.25
0.51
0.45
0.42
0.42
0.53
0.59
0.32
0.47
0.39
MIN
0.27
0.18
0.17
0.21
0.12
0.10
0.16
0.14
0.16
0.15
0.30
0.25
0.26
0.21
0.24
0.42
0.19
0.18
0.32
0.47
0.13
CONC.
AVG
0.083
0.013
0.041
0.032
0.031
0.093
0.043
0.053
0.089
0.063
0.042
0.052
0.21
0.14
0.18
0.14
0.20
0.17
0.030
0.046
0.11
(CONTINUED)
72
-------
TABLE E-2. (CONTINUED)
SAMPLING LOCATION
LUND NV
MESQUITE NV
PIOCHE NV
RENO NV
ROUND MOUNTAIN NV
WELLS NV
WINNEMUCCA NV
ALBUQUERQUE NM
CARLSBAD NM
MUSK OGEE OK
NORMAN OK
MEDFORD OR
BURNS OR
ABILENE TX
AMARILLO TX
AUSTIN TX
BRYCE CANYON UT
CAPITOL REEF NAT'L MONUMENT UT
DUGWAY UT
ENTERPRISE UT
GARRISON UT
NO. DAYS
DETECTED
/SAMPLED
15.6/27.6
22.0/35.0
14.2/26.9
8.1/27.9
9.9/27.2
11.3/28.0
2.9/26.3
14.1/51.6
5.6/24.9
5.0/18.0
2.0/20.0
7.9/33.6
5.0/28.0
9.3/21.3
3.0/28.0
11.0/33.8
6.0/25.9
14.3/27.2
11.6/24.6
12.0/28.0
7.5/28.2
RAD 10-
NUCLIDE
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
RADIOACTIVITY
(pCi/m3)
MAX
0.53
0.32
0.66
0.33
0.42
0.62
0.18
0.36
0.22
0.26
0.30
0.26
0.33
0.32
0.24
0.27
0.54
0.52
0.52
0.51
0.37
MIN
0.31
0.10
0.38
0.27
0.25
0.23
0.18
0.23
0.17
0.20
0.30
0.17
0.19
0.18
0.24
0.12
0.52
0.28
0.18
0.20
0.32
CONC.
AVG
0.22
0.14
0.25
0.086
0.12
0.14
0.020
0.083
0.044
0.062
0.030
0.048
0.043
0.10
0.026
0.058
0.12
0.17
0.14
0.15
0.089
(CONTINUED)
73
-------
TABLE E-2. (CONTINUED)
SAMPLING LOCATION
LOGAN UT
MONTICELLO UT
PROVO UT
VERNAL UT
WENDOVER UT
SEATTLE WA
SPOKANE WA
CASPER WY
ROCK SPRINGS WY
WORLAND WY
NO. DAYS
DETECTED
/SAMPLED
9.0/28.1
9.8/26.7
14.1/55.9
10.0/24.9
5.0/28.0
2.0/22.0
5.0/56.0
8.0/21.0
8.0/26.0
3.0/28.0
RADIO-
NUCLIDE
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
Be-7
RADIOACTIVITY CONC.
(pCi/m3)
MAX
0.24
0.56
0.61
0.45
0.36
0.19
0.21
0.40
0.41
0.34
MIN
0.20
0.24
0.22
0.12
0.22
0.19
0.19
0.23
0.19
0.34
AVG
0.071
0.15
0.079
0.11
0.049
0.017
0.018
0.12
0.079
0.036
THE FOLLOWING STATIONS HAD NEGLIGIBLE GAMMA-SPECTRA:
LITTLE ROCK AK
MOUNTAIN HOME ID
IOWA CITY IA
SIOUX CITY IA
NEW ORLEANS LA
JOPLIN MO
GEYSER RANCH NV
WARM SPRINGS NV
ABERDEEN SD
RAPID CITY SD
FORT WORTH TX
PAROWAN UT
74
-------
TABLE E-3. 1982 SUMMARY OF ANALYTICAL RESULTS FOR THE
NOBLE GAS AND TRITIUM SURVEILLANCE NETWORK
NO.
SAMPLING DAYS
LOCATION DETECTED
SHOSHONE
CA
ADAVEN (CANFIELD)
NV**
ALAMO
NV
AUSTIN
NV
BEATTY
NV
DIABLO (REVEILLE)
NV**
ELY
NV
GOLDFIELD
NV
HIKO
NV**
268.4
254.5
335.7
335.7
2.0
2.0
344.8
317.8
349.0
349.0
219.9
212.9
236.0
236.0
348.5
320.5
362.6
362.6
2.6
2.6
279.7
253.6
306.1
306.1
333.3
319.3
293.8
293.8
2.6
2.6
RADIOACTIVITY CONC.
(pCi/m3)*
RADIONUCLIDE
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
MAX
33
<30
<0.5
<8
23
<50
31
<30
0.51
<9
32
<40
<0.5
<6
31
<100
0.57
<6
22
<30
32
<30
0.57
6.2
34
<30
0.54
<6
26
<6
MIN
20
<6
<0.4
<2
23
<50
20
<7
<0.4
<2
16
<7
<0.5
<2
17
<7
<0.3
<1
22
<30
17
<5
<0.4
<2
17
<8
<0.4
<2
26
<6
AVG
25
3.6
0.082
0.49
23
20
24
4.9
0.055
0.40
24
4.8
0.10
0.68
25
8.0
0.11
0.63
22
16
24
3.5
0.11
0.74
25
6.0
0.084
0.55
26
1.9
PERCENT
CONC.
GUIDE+
0.02
<0.01
_
<0.01
0.02
0.02
0.02
<0.01
_
<0.01
0.02
<0.01
_
<0.01
0.02
<0.01
-
<0.01
0.02
0.02
0.02
<0.01
_
<0.01
0.02
<0.01
-
<0.01
0.03
<0.01
(CONTINUED)
75
-------
TABLE E-3. (CONTINUED)
SAMPLING
LOCATION
INDIAN SPRINGS
NV
LAS VEGAS
NV
LATHROP WELLS
NV
OVERTON
NV
PAHRUMP
NV
RACHEL
NV
TONOPAH
NV
TWIN SPRINGS RN
NV**
CEDAR CITY
UT
NO.
DAYS
DETECTED
307.8
307.8
355.7
355.7
317.5
310.5
364.8
357.8
361.5
340.6
338.5
338.5
307.3
281.2
361.5
354.4
337.5
344.7
363.7
363.7
347.7
326.6
361.9
361.9
355.3
348.3
355.6
355.6
2.6
2.6
279.5
251.5
336.0
336.0
RADIOACTIVITY CONC.
(pCi/m3)* 1
RADIONUCLIDE
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
MAX
32
<40
0.75
<6
32
<20
<0.5
<8
29
<200
<0.5
<7
30
<60
<0.5
<8
30
<40
<0.5
<8
31
<40
<0.5
<7
31
<60
0.54
<5
27
<200
32
<50
0.52
<7
MIN
17
<5
<0.4
<0.6
18
<4
<0.4
<0.8
19
<7
<0.4
<0.9
18
<6
<0.4
<2
20
<6
<0.4
<0.9
19
<5
<0.3
<0.6
16
<7
<0.4
<2
27
<200
20
<5
<0.4
<2
AVG
24
3.9
0.084
0.31
24
3.0
0.061
0.35
24
8.0
0.13
0.69
24
5.5
0.039
0.15
24
3.9
0.057
0.39
26
4.2
0.083
0.48
24
6.0
0.087
0.45
27
55
25
6.8
0.073
0.35
PERCENT
CONC.
GUIDE+
0.02
<0.01
_
<0.01
0.02
<0.01
-
<0.01
0.02
<0.01
-
<0.01
0.02
<0.01
-
<0.01
0.02
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.02
<0.01
-
<0.01
0.03
0.06
0.02
<0.01
-
<0.01
(CONTINUED)
76
-------
TABLE E-3. (CONTINUED)
SAMPLING
LOCATION
ST GEORGE
UT
SALT LAKE CITY
UT
NO.
DAYS
DETECTED RADIONUCLIDE
294.6
287.7
336.6
336.6
224.1
208.1
224.1
224.1
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
Kr-85
Xe-133
H-3 IN ATM. M.*
H-3 AS HTO IN AIR
RADIOACTIVITY CONC.
(pCi/m3)* P
MAX
30
<30
0.49
<7
32
<40
0.53
<8
MIN
19
<7
<0.4
<0.9
19
<4
<0.5
<3
AVG
24
4.6
0.049
0.33
25
5.1
0.089
0.67
ERCENT
CONC.
GUIDE+
0.02
<0.01
_
<0.01
0.02
<0.01
_
<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.
**SPECIAL SAMPLING PROGRAM, SEE TEXT.
77
-------
TABLE E-4. 1982 SUMMARY OF GROSS BETA ANALYSES FOR FIVE ASN STATIONS
SAMPLING LOCATION
SHOSHONE CA
LAS VEGAS NV
DELTA UT
MILFORD UT
ST GEORGE UT
NO.
DAYS
SAMPLED
327.4
362.5
354.6
329.7
363.0
RADIOACTIVITY CONC.
(pCi/m3)
MAX
0.052
0.090
0.070
0.055
0.048
MIN
0.0033
<0.004
0.0022
<0.002
0.0028
AVG
0.0095
0.012
0.011
0.012
0.012
78
-------
TABLE E-5. 1982 SUMMARY OF PLUTONIUM CONCENTRATIONS AT SELECTED
AIR SURVEILLANCE NETWORK STATIONS
NO.
SAMPLING DAYS
LOCATION SAMPLED
(WINSLOW and PHOENIX)
AZ
(BARSTOW and BISHOP)
CA
(DURANGO and PUEBLO)
CO
(BOISE and MOUNTAIN HOME)
ID
(IOWA CITY and SIOUX CITY)
IA
(MONROE and NEW ORLEANS)
LA
(JOPLIN and ST. JOSEPH)
MO
(BOZEMAN and MISSOULA)
MT
LAS VEGAS,
NV
LATHROP WELLS,
NV
RACHEL,
NV
(ALBUQUERQUE and CARLSBAD)
NM
(MUSKOGEE and NORMAN)
OK
(BURNS and MEDFORD)
OR
59.3
59.3
78.5
78.5
42.7
42.7
56.0
56.0
40.6
40.6
49.0
49.0
66.5
66.5
55.8
55.8
361.2
361.2
326.7
326.7
346.7
346.7
76.4
76.4
39.0
39.0
61.6
61.6
RAD 10-
NUCLIDE
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
Pu-238
Pu-239
RADIOACTIVITY CONC.
(aCi/m3) P
MAX
<10
190
<8
13
<200
730
<20
<20
<20
27
<20
<30
<4
22
<20
<20
<40
250
<30
160
<30
190
<10
25
<5
<20
<30
<30
MIN
<4
<7
<2
<8
<5
<20
<5
<5
<4
<7
<3
<6
<2
<5
<6
<7
<7
<20
<8
<20
<7
<20
<2
<5
<3
<5
<2
<6
AVG
3.0
69
0.61
9.7
35
260
3.1
12
0.20
14
1.5
4.1
-0.17
12
-0.075
6.8
5.5
60
5.8
65
3.6
46
1.0
11
-0.30
5.9
0.13
4.9
ERCENT
CONC.
GUIDE
0.01
0.3
<0.01
0.05
0.2
1
0.01
0.06
<0.01
0.07
<0.01
0.02
<0.01
0.06
<0.01
0.03
0.02
0.3
0.03
0.3
0.02
0.2
<0.01
0.05
<0.01
0.03
<0.01
0.02
(CONTINUED)
79
-------
TABLE E-5. (CONTINUED)
SAMPLING
LOCATION
NO.
DAYS RADIO-
SAMPLED NUCLIDE
RADIOACTIVITY CONC.
(aCi/m3)
MAX
MIN
AVG
PERCENT
CONC.
GUIDE
(ABERDEEN and RAPID CITY) 40.6 Pu-238 <30
SD 40.6 Pu-239 <20
(AUSTIN and FT.WORTH) 37.8 Pu-238 <40
TX 37.8 Pu-239 <20
(PROVO and VERNAL) 80.8 Pu-238 <7
UT 80.8 Pu-239 16
(SEATTLE and SPOKANE) 78.0 Pu-238 <7
WA 78.0 Pu-239 <8
(CASPER and WORLAND) 49.0 Pu-238 <20
WY 49.0 Pu-239 <20
<2
<3
<4
<5
<3
<2
<3
<3
<3
<9
-1.8
0.42
11
3.7
-0.71
7.2
-0.019
1.3
2.2
6.1
<0.01
<0.01
0.05
0.02
<0.01
0.04
<0.01
<0.01
<0.01
0.03
80
-------
TABLE E-6. 1982 SUMMARY OF TRITIUM RESULTS FOR THE NTS MONTHLY
LONG-TERM HYDROLOGICAL MONITORING PROGRAM
SAMPLING
LOCATION
WELL 8
WELL A
WELL C
WELL 5C
WELL ARMY 1
WELL 2
TEST WELL B
WELL 3
WELL 4
WELL J-13
WELL U19C
WELL UE7NS
NO.
SAMPLES
8
9
9
9
9
9
7
9
9
9
9
2
TRITIUM
MAX
<9
<9
280
<9
14
13
160
<9
<9
<9
<9
1500
CONCENTRATION
(pCi/L)
MIN
<7
<7
22
<7
<8
<7
110
<7
<7
<7
<7
1400
AVG
-1.7
-2.9
79
-1.5
-0.84
0.40
130
3.5
-1.5
-3.0
-1.4
1400
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
0.1
81
-------
TABLE E-7. TRITIUM RESULTS FOR THE NTS SEMI-ANNUAL LONG-TERM HYDROLOGICAL
MONITORING PROGRAM
SAMPLING LOCATION
ASH MEADOWS NV
CRYSTAL POOL
WELL 18S-51E-7DV
WELL 17S-50E-14CAC
FAIRBANKS SPRINGS
BEATTY NV
NECO WELL
COFFERS WELL
11S/48/1DD
CITY SUPPLY
12S-47E-7DB
BOULDER CITY NV
LAKE MEAD INTAKE
INDIAN SPRINGS NV
COLLECTION
DATE
1982
01/14
07/07
01/14
07/07
01/14
07/07
01/14
07/07
01/14
07/08
01/13
07/06
01/13
07/08
07/30
01/12
TRITIUM
CONC. ± 2 SIGMA
(pCi/L)
-3.2 ± 5.0*
-2.4 ± 5.6*
-2.8 ± 5.5*
0.34 ± 5.5*
-3.2 ± 4.9*
-0.56 ± 5.5*
-3.5 ± 4.8*
-5.0 ± 6.2*
10 ± 4
1.9 ± 5.7*
-3.3 ± 4.6*
170 ± 6
4.9 ± 4.6*
2.7 ± 5.4*
160 ± 7
(SEE NOTE 1)
1.1 ± 4.9*
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
0.02
<0.01
<0.01
0.02
<0.01
USAF WELL 2
(CONTINUED)
82
-------
TABLE E-7. (CONTINUED)
SAMPLING LOCATION
INDIAN SPRINGS NV (ContJ
USAF WELL 2
SEWER CO INC WELL 1
LATHROP WELLS NV
CITY 15S-50E-18CDC
NTS NV
WELL UE18R
WELL UE15D
TEST WELL D
WELL UE1C
WELL C-l
WELL UE5C
COLLECTION
DATE
1982
07/06
01/12
07/06
01/14
07/08
01/20
07/14
01/20
07/15
01/21
07/15
01/21
07/15
01/20
07/14
01/19
07/14
TRITIUM
CONC. ± 2 SIGMA
(pCi/L)
-1.1 ± 5.2*
-2.4 ± 4.6*
-1.3 ± 5.3*
-3.0 ± 4.6*
5.6 ± 5.2*
NO SAMPLE COLLECTED
NO SAMPLE COLLECTED
NO SAMPLE COLLECTED
NO SAMPLE COLLECTED
6.5 ± 5.1*
3.3 ± 5.3*
0.32 ± 5.0*
1.3 ± 5.4*
14 ± 4
6.6 ± 5.3*
10 ± 5
180 ± 7
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
0.02
(CONTINUED)
83
-------
TABLE E-7. (CONTINUED)
SAMPLING LOCATION
NTS NV (Cont)
WELL 5B
TEST WELL F
COLLECTION
DATE
1982
01/19
07/14
01/13
07/15
TRITIUM
CONC. ± 2 SIGMA
(pCi/L)
-2.3 ± 6.3*
180 ± 7
NO SAMPLE COLLECTED
NO SAMPLE COLLECTED
PCT OF
CONC.
GUIDE
0.02
WELL U16D
OASIS VALLEY NV
GOSS SPRINGS
SARCOBATUS FLAT NV
07/14 -8.9 ± 5.3*
(SEE NOTE 2)
01/13 -1.6 ± 5.3*
07/08 190 ± 7
01/13 NO SAMPLE COLLECTED
0.02
RD D WNDMLL 594637AL
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
ANALYSIS RESULT 2 SIGMA UNITS
NOTE 1
NOTE 2
Ra-226
Sr-89
Pu-238
Sr-90
Pu-239
Ra-226
Pu-238
Sr-90
Pu-239
0.52
0.99
0.024
0.25
0.12
1.3
0.021
LOST
0.013
0.13
2.1*
0.028*
0.60*
0.04
0.2
0.032*
IN CHEMISTRY
0.025*
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
84
-------
TABLE E-8. TRITIUM RESULTS FOR THE NTS ANNUAL LONG-TERM HYDROLOGICAL
MONITORING PROGRAM
SAMPLING LOCATION
SHOSHONE CA
SHOSHONE SPRING
ADAVEN NV
ADAVEN SPRING
ALAMO NV
CITY WELL 4
CLARK STATION NV
TTR WELL 6
HIKO NV
CRYSTAL SPRINGS
LAS VEGAS NV
WATER DISTRICT WELL
NYALA NV
SHARP'S RANCH
PAHRUMP NV
CALVADA WELL 3
TEMPIUTE NV
UNION CARBIDE WELL
TONOPAH NV
CITY WELL
WARM SPRINGS NV
TWIN SPRINGS RCH
COLLECTION TRITIUM PCT OF
DATE CONC. ± 2 SIGMA CONC.
1982 (pCi/L) GUIDE
08/24
08/25
08/31
08/25
08/31
08/23
28
08/25
08/24
08/31
08/26
08/25
130 ±
350 ±
79 ±
50 ±
50 ±
130 ±
-84 ±
-20 ±
-20 ±
15 ±
-180 ±
220*
190
220*
220*
220*
220*
220*
220*
220*
220*
220*
0.01
0.03
<0.01
<0.01
<0.01
0.01
<0.01
<0.01
<0.01
<0.01
<0.01
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
85
-------
Pacific Ocean
Constantine Harbor
0 5 10
3/83 Scale in Kilometers
Base Camp Area
^Surface Ground Zero
VAX
Sampling Locations
infantry Road
Mason Lakeo
/-"
Constantine Spring
South Hangar
Maintenance Building
~-^- • • **^ ^^^
Sampling Locations
SPacmcOcean
Figure E-l. Amchitka Island and background sampling locations for the LTHMP.
86
-------
Surface Ground Zero
Sampling Locations
Figure E-2. LTHMP sampling locations for Project Cannikin.
87
-------
TABLE E-9. TRITIUM RESULTS FOR THE OFF-NTS LONG-TERM HYDROLOGICAL MONITORING
PROGRAM (Annual Samples)
COLLECTION
DATE
SAMPLING LOCATION 1982
PROJECT CANNIKIN— AMCHITKA
SOUTH END
CANNIKIN LAKE
NORTH END
CANNIKIN LAKE
WELL HTH-3
ICE BOX LAKE
WHITE ALICE CREEK
WELL AEC-1
PIT S OF CANNIKIN GZ
PROJECT MILROW - AMCHITKA,
HEART LAKE
WELL W-2
WELL W-3
WELL W-4
WELL W-5
WELL W-6
WELL W-7
WELL W-8
WELL W-10
WELL W-ll
, ALAS
09/14
09/14
09/14
09/14
09/14
09/14
ALAS
09/15
09/15
09/15
09/15
09/15
09/15
09/15
09/15
09/15
09/15
TRITIUM
CONC. ± 2 SIGMA
(pCi/L)
51 ± 5
54 ± 6
62 ± 6
47 ± 5
62 ± 6
NO SAMPLE COLLECTED
48 ± 6
61 ± 6
50 ± 6
40 ± 6
NO SAMPLE COLLECTED
59 ± 6
58 ± 6
46 ± 6
73 ± 6
67 ± 5
82 ± 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
<0.01
(CONTINUED)
-------
Scale in Feet
0 600 1200
iSurface Ground Zero
Sampling Locations
Long Shot
Pond #3
Surface Ground Zero
Sampling Locations
Figure E-3. LTHMP sampling locations for Projects Mil row and Long Shot.
89
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
COLLECTION
DATE
1982
TRITIUM
CONC. ± 2 SIGMA
(pCI/L)
PCT OF
CONC.
GUIDE
PROJECT MILROW - AMCHITKA AK (Cont)
WELL W-12
WELL W-13
WELL W-15
WELL W-18
WELL W-19
CLEVENGER CREEK
PROJECT LONG SHOT -
WELL WL-2
EPA WELL-1
REED POND
WELL GZ 1
WELL GZ 2
WELL WL-1
MUD PIT 1
MUD PIT 2
MUD PIT 3
LONG SHOT POND NO
LONG SHOT POND NO
09/15
09/15
09/15
09/15
09/16
09/16
AMCHITKA AK
09/16
09/16
09/16
09/16
09/16
09/16
09/17
09/16
09/16
1 09/17
2 09/17
NO SAMPLE COLLECTED
71 ± 6
49 ± 5
58 ± 5
NO SAMPLE COLLECTED
73 t 6
420 ± 9
97 ± 6
70 ± 6
3800 ± 240
320 ± 9
64 ± 6
690 ± 200
850 ± 210
1000 ± 210
48 ± 6
(SEE NOTE 2)
58 ± 6
(SEE NOTE 3)
<0.01
<0.01
<0.01
<0.01
0.04
0.01
<0.01
0.4
0.03
<0.01
0.07
0.08
0.1
<0.01
<0.01
(CONTINUED)
90
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
PROJECT LONG SHOT -
LONG SHOT POND NO
BACKGROUND SAMPLES -
CONSTANTINE SPRING
JONES LAKE
DUCK COVE CREEK
RAIN SAMPLE
ARMY WELL 1
ARMY WELL 2
ARMY WELL 3
ARMY WELL NO 4
SITE E HYDRO
EXPLOR HOL
SITE D HYDRO
EXPLOR HOL
COLLECTION TRITIUM
DATE CONC. ± 2 SIGMA
1982 (pCi/L)
AMCHITKA AK
3 09/17
AMCHITKA AK
09/14
09/14
09/15
09/16
09/18
09/19
09/14
09/15
09/15
09/15
09/15
09/15
09/15
(Cont)
69 ± 6
(SEE NOTE 4)
94 ± 7
67 ± 7
63 ± 6
65 ± 6
88 ± 6
(SEE NOTE 1)
78 ± 6
72 ± 6
32 ± 6
79 ± 6
NA
82 ± 6
(SEE NOTE 5)
200 ± 7
OIL & DIESEL FUEL IN
100 ± 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
0.02
WELL
<0.01
CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
91
-------
NOTE 1
NOTE 2
NOTE 3
NOTE 4
TABLE E-9. CONTINUED
±~HZ£ZZ™Z!w~SZ:™Z?!ZZ!!«^^ZI — « « « ^£ « « -C£ * - * — ^ ^ Z^rr — ZZ -
ANALYSIS RESULT 2SIGMA UNITS
U-238
U-234
U-235
Ra-226
Sr-89
Sr-90
Pu-238
Pu-239
0.077
0.10
0.0037
0.16
2.2
-0.49
-0.0098
-0.0025
0.038
0.05
0.019*
0.11
2.8*
0.62*
0.032*
0.0081*
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
U-238
U-234
U-235
Ra-226
Pu-238
Pu-239
Sr-90
Sr-89
0.13
0.18
0.0050
0.096
-0.013
0.013
0.16
0.36
0.05
0.07
0.026*
0.079*
0.44*
0.020*
0.56*
2.5*
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
U-235
U-238
U-234
Pu-238
Ra-226
Pu-239
Sr-90
Sr-89
0.0040
0.064
0.044
-0.0053
0.23
-0.0026
-0.25
2.1
0.023*
0.036
0.049*
0.017*
0.13
0.0087*
0.51*
2.4*
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
U-234
U-238
U-235
Pu-238
Ra-226
Pu-239
Sr-90
Sr-89
0.0060
0.048
-0.0030
-0.016
0.15
-0.0027
0.15
0.64
0.060*
0.038*
0.035*
0.054*
0.10
0.0090*
0.54*
2.4*
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
(CONTINUED)
92
-------
TABLE E-9. CONTINUED
ANALYSIS RESULT 2SIGMA UNITS
NOTE 5 U-235 0.049 0.064* pCi/L
U-238 0.21 0.09 pCi/L
U-234 0.25 0.10 pCi/L
Ra-226 0.32 0.25 pCi/L
Pu-239 -0.0056 0.019* pCi/L
Sr-90 0.36 0.61* pCi/L
Sr-89 -1.1 2.8* pCi/L
Pu-238 -0.014 0.046* pCi/L
93
-------
Johnson
Artesian
Fawn Cr 500' Downstream
RB-D-01
SGZ
Fawn Cr 500' Upstream
Rio Blanco County
Garfield County
Rio Blanco County
Location Maps
Figure E-4. LTHMP sampling locations for Project Rio Blanco.
94
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
PROJECT RIO BLANCO - RIO
FAWN CREEK
6800FT UPSTR
FAWN CREEK
500FT UPSTRE
FAWN CREEK
500FT DWNSTR
FAWN CREEK
8400FT DWNST
FAWN CREEK 1
FAWN CREEK 3
CER 1 BLACK SULPHUR
CER 4 BLACK SULPHUR
B-l EQUITY CAMP
BRENNAN WINDMILL
JOHNSON
ARTESIAN WELL
WELL RB-D-01
COLLECTION
DATE
1982
BLANCO CO
05/18
05/18
05/18
05/18
05/18
05/18
05/19
05/19
05/19
05/18
05/19
05/19
TRITIUM
CONC. ± 2 SIGMA
(pCi/L)
69 ± 6
72 ± 6
74 ± 6
84 ± 6
57 ± 6
50 ± 6
73 ± 6
120 ± 6
130 ± 6
NO SAMPLE COLLECTED
-1.5 ± 6.4*
0.42 ± 5.5*
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
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC),
95
-------
Grand Valley
City Water
Grand
G Schwab_p , -^n /
Rn >XW.-- /
Scale in Miles
0 5
Scale in Kilometers
) Surface Ground Zero
Water Sampling Locations
. _
>Rulison /
" -- "I ^^'
JBSefcovic Rn
,L Hayward Rn
*""»
Battlement Creek
Test Well
Spring
Location Maps
3'81
Figure E-5. LTHMP sampling locations for Project Rulison.
96
-------
TABLE E-9. CONTINUED
COLLECTION
DATE
SAMPLING LOCATION 1982
TRITIUM PCT OF
CONC. ± 2 SIGMA CONC.
(pCi/L) GUIDE
PROJECT RULISON - GRAND VALLEY CO
ALBERT GARDNER RANCH
GRAND VALLEY
CITY SPRIN
SPRING 300 YRDS
NW OF G
BATTLEMENT CREEK
CER TEST WELL
LEE HAYWARD RANCH
ROBERT SEARCY
RANCH(G S)
FELIX SEFCOVIC RANCH
POTTER RANCH
05/21
05/23
05/22
05/22
05/22
05/21
05/21
05/23
05/23
250
74
190
190
280
370
320
320
270
± 8
± 6
± 7
± 7
± 8
± 8
± 8
± 8
± 8
0.03
<0.01
0.02
0.02
0.03
0.04
0.03
0.03
0.03
CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
97
-------
SGZ
HTH 2
(•HTH 1
\
I
I
I
x^ S
Six Mile WellH*
I Jim Bias Well
(Blue Jay Springs)
)Surface Ground Zero
Water Sampling Locations
I Blue Jay
Maint Sta
Nevada
Location Maps
Figure E-6. LTHMP sampling locations for Project Faultless.
98
-------
Churchill County
Mineral County
0 5 10 15
3 81 Scale in Kilometers
^Surface Ground Zero
Water Sampling Locations
Location Maps
Figure E-7. LTHMP sampling locations for Project
99
Shoal.
-------
TABLE E-9. CONTINUED
COLLECTION TRITIUM PCT OF
DATE CONC. t 2 SIGMA CONC.
SAMPLING LOCATION 1982 (pCi/L) GUIDE
PROJECT FAULTLESS - BLUE JAY NV
MAINTENANCE STATION
SIX MILE WELL
WELL HTH-1
WELL HTH-2
BIAS WELL
PROJECT SHOAL - FRENCHMAN
FRENCHMAN STATION
WELL HS-1
WELL H-3
FLOWING WELL
HUNTS STATION
07/22
07/21
07/21
10/14
07/21
10/14
07/22
STATION
02/24
02/24
02/25
02/24
02/24
5.8 ± 5.2* <0.01
3.7 ± 5.2* <0.01
240 ± 7 0.02
-5.2 ± 5.6*
SAMPLE LOST
2.2 ± 5.3* <0.01
4.7 t 5.4* <0.01
NV
2.0 ± 6.3* <0.01
0 ± 5.6* <0.01
NO SAMPLE COLLECTED
5.9 ± 5.5* <0.01
2.9 ± 5.4* <0.01
CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC),
100
-------
SGZ
HCave Spring
I Arnold Rn
Scale in Kilometers
0 5
3/81 Scale in Miles
I Surface Ground Zero
Water Sampling Locations
Lower Burro Canyon
New Mexico
®SGZ
Rio Arriba County
Location Maps
Figure E-8. LTHMP sampling locations for Project Gasbuggy.
101
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
COLLECTION TRITIUM PCT OF
DATE CONC. ± 2 SIGMA CONC.
1982 (pCi/L) GUIDE
PROJECT GASBUGGY - GOBERNADOR NM
ARNOLD RANCH 05/03
WELL 30.3.32.343 05/02
NORTH
WELL 28.3.33.233 05/03
SOUTH
LOWER BURRO CANYON 05/06
BIXLER RANCH 05/02
CAVE SPRINGS 05/06
WINDMILL 2 05/02
BUBBLING SPRINGS 05/02
EPNG WELL 10-36 05/06
LA JARA CREEK 05/02
-3.2 ± 6.1*
NO SAMPLE COLLECTED
NO SAMPLE COLLECTED
-10 ± 6*
13 ± 5 <0.01
57 ± 6 <0.01
NO SAMPLE COLLECTED <0.01
87 ± 6 <0.01
20 ± 5 <0.01
81 ± 6 <0.01
CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC),
102
-------
Carlsbad
Carlsbad City Well #7
Loving City Well #2
PHS Well #9B
PHS Well #10
Pecos River
Pumping Station Well #1
Scale in Miles
0 5 10
3/81
10 15
Scale in Kilometers
Ground Zero
A On-Site Water Sampling Locations
I Off-Site Water Sampling Locations
New Mexico
SGZ(
1
•""Eddy County
Location Maps
Figure E-9. LTHMP sampling stations for Project Gnome.
103
-------
TABLE E-9. CONTINUED
COLLECTION
DATE
SAMPLING LOCATION 1982
PROJECT GNOME -
CARLSBAD CITY
WELL 7
PROJECT GNOME -
LOVING CITY
WATER WELL
PROJECT GNOME -
USGS WELL 1
USGS WELL 4
USGS WELL 8
PHS WELL 6
PHS WELL 8
PHS WELL 9
PHS WELL 10
PECOS PUMPING
STATION W
WELL LRL-7
WELL DD-1
CARSBAD NM
04/26
LOVING NM
04/23
MALAGA NM
04/29
04/25
04/25
04/24
04/24
04/28
04/28
04/23
04/27
04/27
TRITIUM PCT OF
CONC. ± 2 SIGMA CONC.
(pCi/L) GUIDE
-3.1 ± 5.9* <0.01
6.2 ± 5.7* <0.01
-4.5 ± 6.2* <0.01
(SEE NOTE 1)
360000 ± 1600 40
(SEE NOTE 2)
290000 ± 1500 30
(SEE NOTE 3)
69 ± 6 <0.01
5.5 ± 5.3* <0.01
-4.6 ± 5.3* <0.01
(SEE NOTE 4)
-1.8 ± 5.4* <0.01
-1.8 ± 5.4* <0.01
22000 ± 440 2
(SEE NOTE 5)
1.5E±08 ± 45000 10,000
(SEE NOTE 6)
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC),
104
-------
TABLE E-9. CONTINUED
NOTE 1
NOTE 2
NOTE 3
NOTE 4
NOTE 5
ANALYSIS
Ra-226
Ra-226
Sr-89
Sr-90
Pu-238
Pu-239
Cs-137
Ra-226
Sr-89
Sr-90
Pu-238
Pu-239
Ra-226
Cs-137
Sr-89
Sr-90
Pu-238
Pu-239
RESULT
5.5
3.5
-35000
8500
-0.16
-0.079
21
1.2
-6100
6900
0
0
0.18
250
-50
10
0
0.045
2SIGMA
0.4
0.3
110000*
2600
0.52*
0.26*
10
0.2
20000*
2100
0.2*
0.2*
0.09
21
730*
16*
0.1*
0.15*
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
NOTE 6 Cs-137 970000 11000 pCi/L
Sr and Pu Sample lost
105
-------
N
R. Mills ^ Lower Little Creek>
•I. Anderson
Anderson I
B Chambhssl
Speights I
1. Lowe1
ii ^JR Ready
BaxtervilleP™ r
Well Ascot 21
SGZ
|R L Anderson'
W Daniels Jr
Lumberton
Scale in Miles
5 10
0
3/83
5 10 15 20 25
Scale in Kilometers
.Mississippi
Surface Ground Zero
Water Sampling Stations
V
Tatum Dome®SGZ
La mar
County
Location Maps
Figure E-10. LTHMP sampling locations for Project Dribble
towns and residences.
106
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
COLLECTION
DATE
1982
TRITIUM
CONC. ± 2 SIGMA
(PCI/L)
PCT OF
CONC.
GUIDE
PROJECT DRIBBLE - BAXTERVILLE MS
PIT EAST OF GZ
PIT SOUTH OF GZ
BAXTERVILLE
CITY WELL
LOWER LITTLE CREEK
WELL HT-2C
WELL HT-4
WELL HT-5
WELL E-7
HALF MOON CREEK
T SPEIGHTS
R L ANDERSON
M LOWE
R READY
W DANIELS OR
HALF MOON
CREEK OVRFLW
WELL ASCOT 2
WELL HMH-1
WELL HMH-2
WELL HMH-3
03/18
03/18
03/17
03/16
03/22
03/21
03/21
03/21
03/19
03/17
03/18
03/16
03/18
03/16
03/16
03/23
03/18
03/16
03/16
39 ± 5
27 ± 6
53 ± 5
52 ± 5
8.8 ± 4.7
95 ± 6
2.2 ± 5.4*
6.6 ± 4.9*
52 ± 6
64 ± 6
44 ± 6
40 ± 5
73 ± 6
44 ± 5
110 ± 6
32 ± 6
10000 ± 320
2100 ± 220
110 ± 7
<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
1
0.2
0.01
(CONTINUED)
107
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
COLLECTION
DATE
1982
TRITIUM
CONC. ± 2 SIGMA
(pCi/L)
PCT OF
CONC.
GUIDE
PROJECT DRIBBLE - BAXTERVILLE MS
COLUMBIA MS
CITY WELL 64B
LUMBERTON MS
CITY WELL 2
PURVIS MS
CITY WELL 2
BAXTERVILLE
CITY WELL
LOWER LITTLE CREEK
WELL ASCOT 2
T SPEIGHTS
R L ANDERSON
M LOWE
R READY
W DANIELS JR
B CHAMBLISS
B R ANDERSON
R MILLS
A C MILLS
G KELLY
H ANDERSON
HALF MOON
03/16
03/16
03/16
03/17
03/16
03/23
03/17
03/18
03/16
03/18
03/16
03/16
03/18
03/18
03/18
03/18
03/18
03/16
6.8 ± 5.0*
5.4 ± 4.9*
1.7 ± 5.2*
53 ± 5
52 ± 5
32 ± 6
64 ± 6
44 ± 6
40 ± 5
73 ± 6
44 ± 5
4.7 ± 4.9*
49 ± 5
52 ± 6
2.0 ± 6.2*
2.9 ± 5.0*
39 ± 5
110 ± 6
<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
CREEK OVRFLW
(CONTINUED)
108
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
PROJECT DRIBBLE -
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
WELL HMH-10
WELL HMH-11
WELL HM-S
WELL HM-1
WELL HM-L
WELL HM-2A
WELL HM-2B
WELL HM-3
WELL HT-2C
WELL HT-4
WELL HT-5
WELL E-7
COLLECTION
DATE
1982
BAXTERVILLE MS
03/18
03/16
03/16
03/17
03/17
03/17
03/16
03/16
03/16
03/16
03/16
03/18
03/16
03/17
03/16
03/16
03/16
03/22
03/21
03/21
03/21
TRITIUM
CONC. ± 2 SIGMA
(pCi/L)
10000 ± 320
2100 ± 220
110 ± 1
33 ± 5
1600 ± 210
1700 ± 220
210 ± 8
29 ± 6
63 ± 6
29 ± 5
100 ± 6
24000 ± 450
2.3 ± 4.9*
2000 ± 220
0.12 ± 5.0*
4.0 ± 5.7*
2.0 ± 5.0*
8.8 ± 4.7
95 ± 6
2.2 ± 5.4*
6.6 ± 4.9*
PCT OF
CONC.
GUIDE
1
0.2
0.01
<0.01
0.2
0.2
0.02
<0.01
<0.01
<0.01
0.01
2.4
<0.01
0.2
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
(CONTINUED)
109
-------
HMH-6
HMH-5
HMH-10 -.-f
)
Half Moon Creek !
, ^Overflow
HMH-1\£5s. (
HMH-11
IHMH-9
Scale in Feet
0 100 200
0
3/83
50 100
Scale in Meters
)Surface Ground Zero
Water Sampling Locations
\
Mississippi /
County
Tatum DomeffiSGZ
Lamar
Location Maps
Figure E-ll. LTHMP sampling locations for Project Dribble - near GZ,
110
-------
REECO Pit - C
REECO Pit - B
REECO Pit - A
Half Moon Creek
Overflow \%
'
\t s-x /
•-^: \ -V
tiL3 x •>•..£.
0 100 200 300 400 500 600
3/83 Scale in Meters
Tatum Dome^SGZ
"
Surface Ground Zero
Water Sampling Locations
Figure E-12. LTHMP sampling locations for Project Dribble - near salt dome.
Ill
-------
TABLE E-9. CONTINUED
COLLECTION TRITIUM PCT OF
DATE CONC. ± 2 SIGMA CONC.
SAMPLING LOCATION 1982 (pCi/L) GUIDE
PROJECT DRIBBLE - BAXTERVILLE MS
WELL HM-L2 03/17 4.4 ± 5.0* <0.01
(SEE NOTE 1)
HALF MOON CREEK
REECO PIT
DRAINAGE-A
REECO PIT
DRAINAGE-B
REECO PIT
DRAINAGE-C
PIT EAST OF GZ
PIT SOUTH OF GZ
POND WEST OF GZ
03/19
03/18
03/18
03/18
03/18
03/18
03/19
52 ± 6
96 ± 6
1200 ± 210
1400 ± 210
39 ± 5
27 ± 6
33 ± 5
<0.01
<0.01
0.1
0.1
<0.01
<0.01
<0.01
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
ANALYSIS RESULT 2SIGMA UNITS
NOTE 1 90SR 1.5 2.4* pCi/L
112
-------
TABLE E-10. 1982 SUMMARY OF ANALYTICAL RESULTS FOR THE
MILK SURVEILLANCE NETWORK
SAMPLING
LOCATION
HINKLEY CA
BILL NELSON DAIRY
RIDGECREST CA
CEDARSAGE FARM
RIDGECREST CA
JANE SZYMANSKI RANCH
ALAMO NV
BUCK HORN RANCH
AUSTIN NV
YOUNG'S RANCH
CURRANT NV
BLUE EAGLE RANCH
CURRANT NV
MANZONIE RANCH
HIKO NV
DARREL HANSEN RANCH
SAMPLE NO. OF
TYPE SAMPLES
12 4
4
4
10 1
1
1
13 2
2
2
13 1
1
1
13 4
4
4
13 4
3
3
13 4
3
3
13 2
2
2
RAD 10-
NUCLIDE
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
RADIOACTIVITY CONC.
(pCi/L)
MAX
560
<30
<3
<300
<20
<3
470
<30
<3
<400
<5
<0.6
<500
<40
<4
<500
<20
3.1
<500
<50
<6
<500
<30
<3
MIN
<300
<8
<0.9
<300
<20
<3
<500
<20
<2
<400
<5
<0.6
<300
<20
<2
<300
<6
<0.8
<300
<8
<2
<300
<20
<2
AVG
210
-0.97
0.61
100
-7.4
1.4
280
7.4
0.47
52
4.0
-0.13
180
2.7
1.7
16
-0.77
1.4
110
-0.46
1.3
110
-5.9
1.2
(CONTINUED)
113
-------
TABLE £-10. (CONTINUED)
SAMPLING
LOCATION
LAS VEGAS NV
LDS DAIRY FARMS
LATHROP WELLS NV
R J EASTMAN RANCH
LIDA NV
LIDA LIVESTOCK COMPANY
LOGANDALE NV
KNUDSEN CORP
LUND NV
MCKENZIE DAIRY
MCGILL NV
LARSEN RANCH
MESQUITE NV
SF AND K DAIRY
MOAPA NV
DECADE CORP
NYALA NV
SHARP'S RANCH
SAMPLE NO. OF
TYPE SAMPLES
12 4
4
4
13 3
3
3
13 4
4
4
12 5
4
4
12 4
4
4
13 2
2
2
12 4
4
4
12 4
4
4
13 4
4
4
RAD 10-
NUCLIDE
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
RADIOACTIVITY CONC.
(pCi/L)
MAX
<500
<50
12
<500
<20
<2
<500
<30
4.4
<500
<20
<2
<500
<50
12
<500
<20
<2
<500
<20
<2
600
<20
<3
<500
<30
<3
MIN
<300
<5
<0.7
<300
<9
<2
<300
<6
1.2
<300
<6
<0.8
<300
<7
<0.9
<500
<20
<2
<300
<8
<1
<300
<6
<0.8
<300
<8
<0.9
AVG
160
6.9
3.6
92
-0.003
0.53
74
1.2
2.3
79
6.3
-0.041
54
-1.1
3.4
190
-1.2
0.66
16
2.2
0.27
230
5.7
0.10
120
5.0
-0.078
(CONTINUED)
114
-------
TABLE E-10. (CONTINUED)
SAMPLING
LOCATION
CALIENTE NV
JUNE COX RANCH
ROUND MT NV
BERG'S RANCH
SHOSHONE NV
HARBECKE RANCH
WARM SPRINGS NV
TWIN SPRINGS RCH
CEDAR CITY UT
WESTERN GEN DAIRIES
ST GEORGE UT
DROUBAY DAIRY
SAMPLE NO. OF
TYPE SAMPLES
13 4
4
4
13 3
3
3
13 3
3
3
13 2
2
2
12 4
4
4
12 4
4
4
RADIO-
NUCLIDE
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
H-3
Sr-89
Sr-90
RADIOACTIVITY CONC.
(pCi/L)
MAX
<500
<50
<8
<500
<20
3.1
<500
<300
5.5
<500
<20
<3
560
<90
<9
<500
<30
<4
MIN
<300
<5
<0.8
<300
<9
<2
<300
<20
<2
<300
<20
<2
<300
<7
<2
<300
<7
<1
AVG
30
-0.71
1.1
55
1.5
2.5
200
-22
2.4
-52
8.0
0.91
200
15
-0.45
180
0.30
1.2
115
-------
TABLE E-ll. 1982 ANALYTICAL RESULTS FOR STANDBY MILK SURVEILLANCE NETWORK
COLLECTION
DATE
SAMPLING LOCATION 1982
KINGMAN AZ
CANYON FARMS
PIMA AZ
SMITH HUNT DAIRY
TAYLOR AZ
SUNRISE DAIRY
TEMPE AZ
UNITED DAIRYMEN OF AZ
TUCSON AZ
SHAMROCK DAIRY (PIMA CO
YUMA AZ
GOLDEN WEST DAIRY
FAYETTEVILLE AR
UNIVERSITY OF AR
LITTLE ROCK AR
BORDENS
RUSSELLVILLE AR
ARKANSAS TECH UNIV
BAKERSFIELD CA
CARNATION DAIRY
FERNBRIDGE CA
HUMBOLDT CREAMERY
FRESNO CA
STATE UNIV CREAMERY
HOLTVILLE CA
SCHAFFNER AND SON DAIRY
LEMON GROVE CA
08/31
08/31
08/31
08/31
08/31
08/31
07/26
07/26
07/27
08/30
08/30
08/31
09/01
08/30
CONCENTRATION ± 2 SIGMA (pCi/L)
H-3
NA
NA
410 ± 300*
NA
250 ± 300*
NA
NA
210 ± 320*
180 ± 320*
370 ± 300*
NA
NA
NA
410 ± 300*
SR-89
-13 ±
- 5.7 ±
0.91 ±
-3.2 ±
-6.7 ±
-5.0 ±
4.0 ±
11 ±
3.3 ±
-0.36 ±
-1.8 ±
-23 ±
-0.79 ±
-8.4 ±
15*
10*
11*
18*
11*
11*
8.8*
13*
10*
8.4*
14*
17*
2.5*
10*
SR-90
2.3 ±
0.91 ±
0.83 ±
0.89 ±
1.1 ±
1.1 ±
2.2 ±
3.9 ±
2.4 ±
0.67 ±
2.1 ±
2.8 ±
0.65 ±
1.3 ±
0.8
0.82*
0.84*
1.7*
0.9*
0.9*
0.6
0.8
0.7
0.68*
0.7
1.0
2.4*
0.5
MILLER DAIRY
(CONTINUED)
116
-------
TABLE E-ll. (CONTINUED)
COLLECTION
DATE
SAMPLING LOCATION 1982
MANTECA CA
LEGEND DAIRY FARMS
MODESTO CA
FOSTER FARMS DAIRY
OXNARD CA
CHASE BROS DAIRY
REDDING CA
MCCOLL'S DAIRY PROD
SAN LUIS OBISPO CA
CAL STATE POLY
SMITH RIVER CA
COUNTRY MAID DAIRY
SOL ED AD CA
CTF DAIRY
WILLITS CA
RIDGEWOOD RANCH DAIRY
WILLOWS CA
FOREMOST FOODS COMPANY
COLORADO SPGS CO
SINTON DAIRY CO
DELTA CO
ARDEN MEADOW GOLD DAIRY
GRAND JCT CO
COLORADO WEST DAIRIES
PUEBLO CO
HYDE PARK DAIRY CO
BOISE ID
08/31
11/14
09/07
08/31
09/01
08/31
09/01
09/01
08/30
08/16
08/19
08/16
08/17
07/26
CONCENTRATION ± 2 SIGMA (pCi/L)
H-3
NA
NA
NA
NA
NA
NA
NA
NA
340 ± 300*
NA
NA
200 ± 320*
320 ± 310*
590 ± 280
SR-89
-2.5 ±
1.3 ±
-16 ±
13 ±
-7.8 ±
-3.3 ±
-8.1 ±
-5.5 ±
9.7 ±
-41 ±
-9.6 ±
-9.3 ±
-7.4 ±
3.5 ±
33*
2.3*
12*
26*
14*
15*
16*
15*
18*
33*
15*
19*
15*
9.8*
SR-90
0.79 ±
0.14 ±
2.1 ±
0.069 ±
1.5 ±
2.6 ±
0.84 ±
1.6 ±
0.045 ±
3.3 ±
1.7 ±
1.7 ±
1.4 ±
0.68 ±
3.2*
0.23*
0.7
2.5*
1.3*
0.7
1.2*
1.5*
1.6*
1.0
0.6
1.4*
1.1*
0.92*
MEADOW GOLD DAIRIES
(CONTINUED)
117
-------
TABLE E-ll. (CONTINUED)
COLLECTION
DATE
SAMPLING LOCATION 1982
TWIN FALLS ID
YOUNGS DAIRY
CALDWELL ID
OCA RECEIVING STA
IDAHO FALLS ID
WESTERN GENERAL DAIRY
LEWISTON ID
GOLDEN GRAIN DAIRY PROD
POCATELLO ID
ROWLAND'S DAIRY
DAVENPORT I A
SWISS VALLEY FARMS CO
KIMBALLTON IA
AMP I RECEIVING STA
LAKE MILLS IA
LAKE MILLS COOP CRMY
LEMARS I A
WELLS DAIRY
CONCORDIA KS
FAIRMONT FOOD CO
GARDEN CITY KS
MYERS MILK PROD
ELLIS KS
MID-AMERICA DAIRY
TOPEKA KS
THE DAIRY CO.
BATON ROUGE LA
09/03
09/15
07/26
07/26
07/26
09/14
09/14
09/13
09/13
09/13
09/13
09/13
09/14
07/26
CONCENTRATION ± 2 SIGMA (pCi/L)
H-3
NA
NA
660 ± 280
NA
NA
-53 ± 310*
NA
SR-89
7.2 ± 25*
-8.6 ± 20*
6.0 ± 8.1*
8.0 ± 6.0*
4.4 ± 6.0*
-0.091 ± 13*
0.038 ± 12*
NA NA
NO SR ANALYSES-SOUR MILK
NA
41 ± 310*
41 ± 310*
NA
NA
98 ± 320*
-2.4 ± 10*
-2.2 ± 12*
-5.0 ± 12*
-4.2 ± 18*
-3.3 ± 11*
-1.2 ± 7.2*
SR-90
1.1 ± 2.5*
2.3 ± 2.1*
1.1 ± 0.5
0.89 ± 0.34
1.0 ± 0.4
2.8 ± 0.8
2.5 ± 0.6
NA
1.7 ± 0.5
NA
2.5 ± 0.6
2.5 ± 1.8*
2.3 ± 0.6
1.2 ± 0.4
LA STATE UNIV
(CONTINUED)
118
-------
TABLE E-ll. (CONTINUED)
COLLECTION
DATE
SAMPLING LOCATION 1982
HAMMOND LA
SOUTHEASTERN LA COLLEGE
LAFAYETTE LA
UNIV SOUTHWESTERN LA
LAKE CHARLES LA
BORDEN'S
MONROE LA
BORDEN'S
NEW ORLEANS LA
BORDEN'S
RUSTON LA
TECH UNIV DAIRY
SHREVEPORT LA
MIDWEST FARMS
DALTON MN
DALTON CO-OP CREAMERY
FLENSBURG MN
FLENSBURG CO-OP CMRY
FOSSTON MN
LAND 0' LAKES INC
NICOLLET MN
WALTER SCHULTZ FARM
ROCHESTER MN
ASSC MILK PRODUCERS
AURORA MO
MID-AMERICA DAIRY INC
CHILLICOTHE MO
MID-AMERICA DAIRYMEN
07/26
07/26
08/05
07/30
07/25
07/26
08/17
08/17
08/16
08/24
08/17
08/16
09/13
09/13
CONCENTRATION ± 2 SIGMA (pCi/L)
H-3
NA
NA
NA
150 ± 320*
380 ± 320*
NA
NA
NA
270 ± 200*
(SEE NOTE 1)
500 ± 270
NA
140 ± 310*
140 ± 310*
16 ± 310*
SR-89
11 ± 8*
5.3 ± 6.3*
3.0 ± 6.7*
7.3 ± 7.8*
-0.41 ± 12*
7.0 ± 7.4*
-7.4 ± 19*
-8.5 ± 19*
-20 ± 26*
-7.5 ± 38*
-8.4 ± 20*
-14 ± 22*
-7.8 ± 17*
-3.3 ± 14*
SR-90
0.95 ± 0.39
0.88 ± 0.41
1.7 ± 0.5
1.4 ± 0.4
3.0 ± 0.7
0.87 ± 0.38
2.8 ± 0.9
2.3 ± 0.8
2.7 ± 0.8
4.3 ± 3.2*
1.5 ± 1.5*
3.0 ± 1.0
4.6 ± 0.9
2.0 ± 0.7
(CONTINUED)
119
-------
TABLE E-ll. (CONTINUED)
COLLECTION
DATE
SAMPLING LOCATION 1982
JACKSON MO
MID-AMERICA DAIRYMEN IN
ST CHARLES MO
ST CHARLES DAIRY
BOZEMAN MT
DARIGOLD FARMS
GREAT FALLS MT
MEADOW GOLD DAIRY
KALISPELL MT
EQUITY SUPPLY CO
HASTINGS NB
ABBOTTS DAIRY
NORTH PLATTE NB
MID AMERICA DAIRYMEN
FALLON NV
CREAMLAND DAIRY
LAS VEGAS NV
ANDERSON DAIRY
RENO NV
MODEL DAIRY
YERINGTON NV
VALLEY DAIRY
LAS CRUCES NM
LONG'S DAIRY
BISMARCK ND
BRIDGEMENS CREAMERY
DEVILS LAKE ND
09/13
09/16
11/10
07/01
11/14
09/14
09/14
09/03
09/02
09/02
09/02
10/06
08/16
08/16
CONCENTRATION ± 2 SIGMA (pCI/L)
H-3
NA
NA
NA
NA
NA
NA
-41 ± 310*
38 ± 290*
NA
NA
NA
NA
150 ± 310*
NA
SR-89
-9.2 ± 13*
-12 ± 13*
-12 ± 23*
-39 ± 42*
-2.0 ± 7.4*
-8.1 ± 12*
-29 ± 22*
-5.1 ± 16*
4.1 ± 8.0*
8.7 ± 11*
-5.3 ± 14*
-18 ± 23*
-6.7 ± 19*
-17 ± 37*
SR-90
2.7 ± 0.7
2.9 ± 0.7
4.6 ± 3.8*
3.2 ± 0.9
2.1 ± 0.7
2.8 ± 0.7
6.5 ± 1.3
1.8 ± 1.6*
0.40 ± 0.62*
0.26 ± 0.87*
1.1 ± 1.4*
2.8 ± 2.3*
3.6 ± 0.8
3.4 ± 1.2
LAKE VIEW DAIRY
(CONTINUED)
120
-------
TABLE E-ll. (CONTINUED)
COLLECTION
DATE
SAMPLING LOCATION 1982
FARGO ND
CASSCLAY CREAMERY
GRAND FORKS ND
MINNESOTA DAIRY
JAMESTOWN ND
COUNTRY BOY DAIRY
WILLISTON ND
PETERSONS CREAMERY
ATOKA OK
MUNGLE DAIRY
CLAREMORE OK
SWAN BROS DAIRY
ENID OK
AMPI GOLDSPOT DIVISION
MCALESTER OK
OKLA ST PENITENTIARY
STILLWATER OK
OSU DAIRY
CORVALLIS OR
SUNNY BROOK DAIRY
EUGENE OR
ECHO SPRINGS DAIRY
GRANTS PASS OR
VALLEY OF ROGUE DAIR
KLAMATH FALLS OR
NEDO BEL CREAMERY
MEDFORD OR
08/18
08/17
08/24
09/27
11/15
08/16
07/26
07/26
08/18
07/26
07/26
07/26
07/26
07/27
CONCENTRATION ± 2 SIGMA (pCi/L)
H-3
NA
340 ± 310*
NA
NA
NA
NA
49 ± 320*
670 ± 290
NA
410 ± 310*
NA
NA
NA
580 ± 280
SR-89
-13 ± 25*
-2.3 ± 18*
-12 ± 22*
-15 ± 32*
5.6 ± 10*
-6.8 ± 17*
5.1 ± 9.6*
-3.1 ± 7.7*
23 ± 36*
2.4 ± 6.1*
3.1 ± 5.7*
4.8 ± 4.5*
6.6 ± 6.2*
5.1 ± 6.0*
SR-90
4.0 ± 1.1
2.8 ± 0.7
4.2 ± 1.0
4.3 ± 3.1*
4.8 ± 1.0
2.5 ± 0.7
2.0 ± 0.6
1.8 ± 0.5
3.0 ± 1.0
0.62 ± 0.58*
0.81 ± 0.34
0.37 ± 0.44*
0.97 ± 0.36
0.46 ± 0.60*
DAIRYGOLD FARMS
(CONTINUED)
121
-------
TABLE E-ll. (CONTINUED)
COLLECTION
DATE
SAMPLING LOCATION 1982
MILTON-FREEWATER OR
PARENTS DAIRY
MYRTLE POINT OR
SAFEWAY STORES INC
PORTLAND OR
DARIGOLD FARMS
REDMOND OR
EBERHARD'S CREAMERY INC
TILLAMOOK OR
TILLAMOOK CO CRMY
MITCHELL SD
CULHANES DAIRY
RAPID CITY SD
BROWN SWISS DAIRY
SIOUX FALLS SD
TERRACE PARK DAIRY
VOLGA SD
LAND 0' LAKES INC
BEAVER UT
CACHE VALLEY DAIRY
PROVO UT
BYU DAIRY PRODUCTS LAB
CEDAR CITY UT
WESTERN GEN DAIRIES
RICHFIELD UT
IDEAL DAIRY
SMITHFIELD UT
CACHE VALLEY DAIRY
07/26
07/26
07/27
07/26
07/26
08/16
11/11
08/16
11/14
08/19
08/16
08/16
08/17
08/19
CONCENTRATION ± 2 SIGMA (pCi/L)
H-3
NA
NA
NA
NA
NA
NA
NA
350 ± 310*
NA
NA
150 ± 310*
NA
NA
NA
SR-89
4.0 ±
10 ±
4.3 ±
7.0 ±
11 ±
-18 ±
-11 ±
-22 ±
-2.9 ±
-0.25 ±
-9.6 ±
-8.7 ±
-15 ±
-7.6 ±
5.5*
8*
7.7*
6.6*
11*
25*
14*
26*
11*
13*
18*
15*
46*
18*
SR-90
0.94 ± 0.32
0.65 ± 0.69*
1.7 ± 0.5
0.39 ± 0.64*
2.6 ± 0.6
3.9 ± 1.1
4.3 ± 1.4
3.6 ± 1.1
2.5 ± 1.0
1.2 ± 1.0*
2.6 ± 0.7
1.5 ± 0.6
2.6 ± 2.5*
2.5 ± 0.7
(CONTINUED)
122
-------
TABLE E-ll. (CONTINUED)
COLLECTION CONCENTRATION ± 2 SIGMA (pCi/L)
DATE
SAMPLING LOCATION 1982 H-3 SR-89 SR-90
MOSES LAKE WA 09/10 NA -25 ± 22* 3.9 ± 1.3
SAFEWAY STORES INC
SPOKANE WA 07/27 510 ± 280 12 ± 16* 1.6 ± 1.6*
CONSOLIDATED DAIRY
CHEYENNE WY 08/17 NA -10 ± 21* 2.9 ± 0.9
DAIRY GOLD FOODS
LARAMIE WY 11/12 NA -0.34 ± 7.4* 1.9 ± 0.7
UNIV OF WYO (DAIRY)
POWELL WY 08/15 -64 ± 320* -12 ± 19* 3.3 ± 0.8
CREAM OF THE VALLEY DAI
RIVERTON WY 08/19 NA -19 ± 18* 3.2 ±0.7
ALBERTSON'S PLANT
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
ANALYSIS RESULT 2SIGMA UNITS
NOTE 1 137CS 16 8 pCi/L
123
-------
TABLE E-12. 1982 SUMMARY OF RADIATION DOSES FOR THE DOSIMETRY NETWORK
STATION
LOCATION
ADAVEN, NV
ALAMO, NV
AMERICAN BORATE, NV
AUSTIN, NV
BAKER, CA
BARSTOW, CA
BEATTY, NV
BISHOP, CA
BLUE EAGLE RANCH, NV
BLUE JAY, NV
CACTUS SPRINGS, NV
CALIENTE, NV
CARP, NV
CASEY'S RANCH, NV
CEDAR CITY, UT
CLARK STATION, NV
COMPLEX I, NV
CORN CREEK STATION, NV
COYOTE SUMMIT, NV
CURRANT, NV
DEATH VALLEY OCT., CA
MEASUREMENT PERIOD
ISSUE COLLECT
01/20/82
01/08/82
01/05/82
01/12/82
01/11/82
01/11/82
01/05/82
01/12/82
01/06/82
01/12/82
01/04/82
01/06/82
01/07/82
01/12/82
01/05/82
01/11/82
01/20/82
01/04/82
01/11/82
01/06/82
01/14/82
01/12/83
01/13/83
01/10/83
01/11/83
01/10/83
01/10/83
01/12/83
01/12/83
01/11/83
01/12/83
01/10/83
01/12/83
01/13/83
01/12/83
01/11/83
01/11/83
01/12/83
01/10/83
01/11/83
01/11/83
01/13/83
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.36
0.24
0.26
0.35
0.23
0.30
0.31
0.27
0.18
0.33
0.16
0.31
0.30
0.20
0.20
0.32
0.28
0.14
0.34
0.28
0.21
MIN.
0.28
0.23
0.26
0.31
0.22
0.29
0.29
0.26
0.17
0.31
0.15
0.29
0.27
0.20
0.19
0.31
0.24
0.14
0.32
0.27
0.19
AVG.
0.33
0.24
0.26
0.33
0.22
0.30
0.30
0.27
0.18
0.32
0.15
0.30
0.28
0.20
0.19
0.31
0.27
0.14
0.33
0.27
0.20
ANNUAL
ADJUSTED
DOSE
EQUIVALENT
(MREM/A)
121
87
94
121
82
108
109
97
64
115
56
109
103
73
69
115
98
51
118
99
74
(CONTINUED)
124
-------
TABLE E-12. CONTINUED
STATION
LOCATION
DIABLO MAINT. STA. , NV
DUCKWATER, NV
ELGIN, NV
ELY, NV
ENTERPRISE, UT
EUREKA, NV
FURNACE CREEK, CA
GARRISON, UT
GEYSER MAINT. STA. , NV
GOLDFIELD, NV
GROOM LAKE, NV
HANCOCK SUMMIT, NVl
HIKO, NV
HOT CREEK RANCH, NV
INDEPENDENCE, CA
INDIAN SPRINGS, NV
KIRKEBY RANCH, NV
KOYNES, NV
LAS VEGAS (AIRPORT), NV
LAS VEGAS (PLACAK), NV
LAS VEGAS (UNLV), NV
MEASUREMENT PERIOD
ISSUE COLLECT
01/11/82
01/06/82
01/07/82
01/07/82
01/05/82
01/11/82
01/14/82
01/07/82
01/07/82
01/13/81
01/11/82
01/11/82
01/08/82
01/11/82
01/12/82
01/04/83
01/07/82
01/13/82
01/04/82
01/04/82
01/04/82
01/11/83
01/11/83
01/13/83
01/13/83
01/12/83
01/11/83
01/13/83
01/11/83
01/10/83
01/10/83
01/10/83
01/10/83
01/13/83
01/12/83
01/12/83
01/10/83
01/10/83
01/11/83
12/29/82
12/19/82
12/29/82
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.34
0.28
0.34
0.22
0.27
0.30
0.19
0.18
0.28
0.24
0.19
0.39
0.21
0.25
0.26
0.14
0.21
0.26
0.14
0.14
0.12
MIN.
0.34
0.26
0.32
0.20
0.26
0.28
0.17
0.17
0.27
0.23
0.19
0.37
0.19
0.25
0.25
0.14
0.20
0.24
0.13
0.13
0.11
AVG.
0.34
0.27
0.33
0.21
0.26
0.29
0.18
0.18
0.27
0.24
0.19
0.38
0.20
0.25
0.25
0.14
0.20
0.25
0.14
0.14
0.12
ANNUAL
ADJUSTED
DOSE
EQUIVALENT
(MREM/A)
124
98
120
78
96
107
66
66
100
88
69
139
71
90
92
50
72
90
49
50
47
(CONTINUED)
125
-------
TABLE E-12. CONTINUED
STATION
LOCATION
LAS VEGAS (USDI), NV
LATHROP WELLS, NV
LAVADAS MARKET, NV
LIDA, NV
LONE PINE, CA
LUND, NV
MAMMOTH MTN. , CA?
MANHATTAN, NV
MESQUITE, NV
NEVADA FARMS, NV
NYALA, NV
OLANCHA, CA
OVERTON, NV
PAHRUMP, NV
PINE CREEK RANCH, NV
PIOCHE, NV
QUEEN CITY SUMMIT, NV
RACHEL, NV
REED RANCH, NV
RIDGECREST, CA
ROUND MOUNTAIN, NV
MEASUREMENT PERIOD
ISSUE COLLECT
01/04/82
01/05/82
01/05/82
01/13/82
01/12/82
01/08/82
01/13/82
01/12/82
01/04/82
01/11/82
01/12/82
01/12/82
01/12/82
01/04/82
01/20/82
01/06/82
01/11/83
01/11/82
01/11/82
01/12/82
01/12/82
12/29/82
01/10/83
01/12/83
01/10/83
01/12/83
01/13/83
10/05/82
01/11/83
01/10/83
01/11/83
01/12/83
01/12/83
01/10/83
01/13/83
01/12/83
01/12/83
01/10/83
01/11/83
01/11/83
01/11/83
01/11/83
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.17
0.27
0.24
0.26
0.26
0.23
0.34
0.34
0.17
0.31
0.23
0.26
0.16
0.14
0.32
0.23
0.35
0.30
0.31
0.25
0.30
MIN.
0.16
0.24
0.22
0.25
0.24
0.22
0.23
0.31
0.17
0.30
0.20
0.25
0.15
0.14
0.28
0.22
0.34
0.29
0.30
0.24
0.29
AVG.
0.16
0.26
0.23
0.26
0.25
0.22
0.26
0.33
0.17
0.31
0.21
0.26
0.16
0.14
0.31
0.22
0.35
0.29
0.30
0.24
0.30
ANNUAL
ADJUSTED
DOSE
EQUIVALENT
(MREM/A)
59
94
85
94
90
81
96
118
62
112
77
93
57
51
112
80
127
107
110
88
108
(CONTINUED)
126
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TABLE E-12. CONTINUED
STATION
LOCATION
ROX, NV
SALT LAKE CITY, UT
SCOTTY'S JUNCTION, NV
SHERRI'S BAR, NV
SHOSHONE, CA
SPRINGDALE, NV
SPRING MEADOWS, NV
ST. GEORGE, UT
STONE CABIN RANCH, NV
SUNNYSIDE, NV
TEMPIUTE, NV
TICKABOO VALLEY, NV
TONOPAH, NV
TONOPAH TEST RANGE, NV
TWIN SPRINGS RANCH, NV
U.S. ECOLOGY, NV
VALLEY CREST, CA
WARM SPRINGS, NV
YOUNG'S RANCH, NV
MEASUREMENT PERIOD
ISSUE COLLECT
01/04/82
01/05/82
01/13/82
01/08/82
01/14/82
01/06/82
01/05/82
01/04/82
01/12/82
01/08/82
01/13/82
10/12/82
01/12/82
01/12/82
01/12/82
01/05/82
01/14/82
01/11/82
01/12/82
01/10/83
01/17/83
01/10/83
01/14/83
01/13/83
01/11/83
01/10/83
01/11/83
01/12/83
01/13/83
01/11/83
01/10/83
01/11/83
01/11/83
01/11/83
01/11/83
01/13/83
01/12/83
01/11/83
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.20
0.24
0.28
0.20
0.21
0.30
0.17
0.16
0.30
0.18
0.30
0.27
0.31
0.27
0.30
0.31
0.16
0.31
0.25
MIN.
0.18
0.20
0.27
0.19
0.19
0.29
0.16
0.15
0.28
0.16
0.30
0.27
0.30
0.26
0.27
0.29
0.15
0.29
0.24
AVG.
0.19
0.22
0.28
0.20
0.20
0.29
0.16
0.15
0.30
0.17
0.30
0.27
0.31
0.27
0.28
0.30
0.15
0.30
0.24
ANNUAL
ADJUSTED
DOSE
EQUIVALENT
(MREM/A)
67
79
101
71
73
106
59
55
108
63
110
97
112
97
103
108
55
110
89
ISTATION VANDALIZED SECOND QUARTER 1982.
STATION VALDALIZED FOURTH QUARTER 1982.
127
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TABLE E-13. 1982 SUMMARY OF RADIATION DOSES FOR OFFSITE RESIDENTS
RESI-
DENT BACKGROUND STATION
NO. LOCATION
2
3
6
7
8
9
10
11
12
13
14
15
17
18
19
21
22
24
25
27
28
CALIENTE, NV
BLUE JAY, NV
INDIAN SPRINGS, NV
GOLDFIELD, NV
TWIN SPRINGS RANCH, NV
BLUE EAGLE RANCH, NV
COMPLEX I, NV
COMPLEX I, NV
CORN CREEK, NV
KOYNES RANCH, NV
HANCOCK SUMMIT, NV
HANCOCK SUMMIT, NV
NYALA, NV
NYALA, NV
GOLDFIELD, NV
BEATTY, NV
ALAMO, NV
CORN CREEK, NV
CORN CREEK, NV
PAHRUMP, NV
HOT CREEK RANCH, NV
MEASURE-
MENT
ISSUE
01/12/82
01/12/82
01/08/82
01/13/82
01/12/82
01/06/82
01/20/82
01/20/82
01/04/82
01/13/82
01/11/82
01/11/82
01/12/82
01/12/82
01/13/82
01/05/82
01/08/82
01/04/82
01/04/82
01/07/82
01/12/82
PERIOD
COLLECT
01/12/83
01/12/83
01/10/83
01/10/83
01/11/83
01/11/83
01/12/83
01/12/83
12/29/82
01/11/83
01/11/83
01/10/83
01/12/83
01/12/83
01/10/83
01/11/83
01/13/83
12/29/82
12/29/82
01/13/83
01/12/83
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.26
0.25
0.15
0.21
0.28
0.18
0.28
0.28
0.13
0.23
0.26
0.24
0.20
0.21
0.21
0.27
0.18
0.12
0.22
0.17
0.27
MIN.
0.24
0.23
0.14
0.20
0.27
0.16
0.23
0.24
0.12
0.18
0.21
0.22
0.18
0.18
0.19
0.22
0.17
0.10
0.14
0.16
0.23
AVG.
0.25
0.24
0.14
0.20
0.28
0.16
0.26
0.26
0.13
0.19
0.24
0.23
0.19
0.20
0.21
0.24
0.18
0.11
0.18
0.16
0.24
NET
EXPOSURE
(MREM)
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
0.0
0.0
0.0
12
2.0
0.0
(CONTINUED)
128
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TABLE E-13. CONTINUED
RESI-
DENT BACKGROUND STATION
NO. LOCATION
29
30
33
34
35
36
37
38
40
41
42
43
44
45
47
48
49
50
51
52
53
STONE CABIN RANCH, NV
RACHEL, NV
LATHROP WELLS, NV
FURNACE CREEK, CA
DEATH VALLEY OCT. , CA
PAHRUMP, NV
INDIAN SPRINGS, NV
BEATTY, NV
GOLDFIELD, NV
AUSTIN, NV
TONOPAH, NV
ALAMO, NV
CEDAR CITY, UT
ST. GEORGE, UT
ELY, NV
RACHEL, NV
LAS VEGAS, UNLV
HOT CREEK RANCH, NV
TONOPAH, NV
SALT LAKE CITY, UT
SHOSHONE, CA
MEASURE-
MENT
ISSUE
01/12/82
01/13/82
07/14/82
04/07/82
01/14/82
01/04/82
01/04/82
01/04/82
01/13/82
01/12/82
01/13/82
01/08/82
01/05/82
01/04/82
01/07/82
01/13/82
01/13/82
01/12/82
01/12/82
01/05/82
04/26/82
PERIOD
COLLECT
01/12/83
01/11/83
10/05/82
01/13/82
01/14/83
01/13/83
01/10/83
01/13/83
10/06/82
01/11/83
01/11/83
01/13/83
01/11/83
01/11/83
01/13/83
01/11/83
12/29/82
01/12/83
01/10/83
01/11/83
01/17/83
DOSE
EQUIVALENT RATE
IMREM/DJ
MAX.
0.29
0.25
0.24
0.17
0.19
0.13
0.14
0.31
0.22
0.29
0.26
0.25
0.23
0.18
0.18
0.24
0.41
0.27
0.23
0.28
0.23
MIN.
0.26
0.24
0.22
0.16
0.19
0.12
0.14
0.25
0.21
0.26
0.22
0.18
0.19
0.16
0.18
0.21
0.26
0.21
0.22
0.24
0.19
AVG.
0.27
0.25
0.23
0.16
0.19
0.13
0.14
0.28
0.22
0.28
0.24
0.20
0.21
0.17
0.18
0.22
0.32
0.24
0.22
0.25
0.21
NET
EXPOSURE
(MREM)
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
*7.2
0.0
0.0
0.0
74
0.0
0.0
7.4
0.0
(CONTINUED)
129
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TECHNICAL REPORT DATA
(Please read Instructions on the reverse before completing)
1. REPORT NO.
EPA 600/4-83-032
3. RECIPIENT'S ACCESSION NO.
4. TITLE ANDSUBTITLE
OFFSITE ENVIRONMENTAL MONITORING REPORT
Radiation Monitoring Around U.S. Nuclear Test Areas,
Calendar Year 1982
5. REPORT DATE
6. PERFORMING ORGANIZATION CODE
'. AUTHOR(S)
S.C. Black, R.F. Grossman, A.A. Mullen
D.D. Smith and J. L. Hopper
8. PERFORMING ORGANIZATION REPORT NO
G.D. Potter,
9,_PERFORMING ORGANIZATION ,NAME,AND ADDR.ESS
EnvironmentaTTTomtonng Systems Laboratory
Office of Research and Development
U.S. Environmental Protection Agency
Las Vegas, Nevada 89114
10. PROGRAM ELEMENT NO.
X6EH10
11. CONTRACT/GRANT NO.
IAG DE-AI08-76DP00539
12. SPONSORING AGENCY NAME AND ADDRESS
U.S. Department of Energy
Nevada Operations Office
P. 0. Box 14100
Las Vegas, NV 89114
13. TYPE OF REPORT AND PERIOD COVERED
Response - 1982
14. SPONSORING AGENCY CODE
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 environmental
radiation, and to provide such information to the public. It summarizes these activi-
ties for calendar year 1982.
No radioactivity attributable to NTS activities was detectable offsite by the monitor-
ing networks. Using recorded wind data and Pasquill stability categories, atmospheric
dispersion calculations based on reported radionuclide releases yield an estimated
dose of 10~ man-rem to the population within 80 km of the Nevada Test Site during 1982.
World-wide fallout of Kr-85, Sr-90, Cs-137, and Pu-239 detected by the monitoring net-
works would cause maximum exposure to an individual of less than 0.3 mrem per year.
Plutonium and krypton in air were similar to 1981 levels while cesium and strontium in
other samples were near the detection limits. An occasional net exposure to offsite
residents has been detected by the TLD network. On investigation , the cause of such
net exposures has been due to personal habits or occupational activities, not to NTS
activities.
7.
KEY WORDS AND DOCUMENT ANALYSIS
DESCRIPTORS
b.IDENTIFIERS/OPEN ENDED TERMS C. COSATI Field/Group
8. DISTRIBUTION STATEMENT
RELEASE TO THE PUBLIC
19. SECURITY Ct ASS (This Report)
UNCLASSIFIED
21. NO. OF PAGES
20 SECURITY
22. PRICE
EPA Form 2220-1 (R«v. 4-77) PREVIOUS EDITION is OBSOLETE
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