oEPA
United States
Environmental Protection
Agency
Environmental Monitoring
Systems Laboratory
PO. Box 15027
Las Vegas NV 89114-5027
EPA-600/4-84-040
DOE/DP/0539-051
July 1984
Research and Development
Offsite Environmental
Monitoring Report
Radiation Monitoring Around
United States Nuclear Test
Areas, Calendar Year 1983
prepared for the
U.S. Department of Energy
under Interagency Agreement
Number DE-AI08-76DP00539
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Printed in the United States of America
Available from:
National Technical Information Service
U.S. Department of Commerce
5285 Port Royal Road
Springfield, Virginia 22161
Price: Printed Copy, Code A07
Microfiche, Code A01
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EPA-600/4-84-040
DOE/DP/0539-051
July 1984
OFFSITE ENVIRONMENTAL MONITORING REPORT
Radiation Monitoring Around United States
Nuclear Test Areas, Calendar Year 1983
compiled by
R. G. Patzer, S. C. Black,
R. F. Grossman, 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 activ-
ities became the responsibility of the newly formed U.S. Energy Research and
Development Administration (ERDA). On October 1, 1977 the ERDA was merged with
other energy-related agencies to form the U.S. Department of Energy (DOE).
Atmospheric nuclear tests were conducted periodically from January 27, 1951,
through October 30, 1958, after which a testing moratorium was in effect until
September 1, 1961. Since September 1, 1961, all nuclear detonations have been
conducted underground with the expectation of containment, except for four
slightly above-ground or shallow underground tests of Operation Dominic II in
196? 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. Envi-
ronmental 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
196?, aircraft have also been deployed to rapidly monitor and sample releases
of radioactivity during nuclear tests. Monitoring data obtained by the aircraft
crew immediately after a test are used to position mobile radiation monitoring
personnel on the ground. Data from airborne sampling are used to quantify the
amounts, diffusion, and transport of the radionuclides released.
Beginning with Operation Upshot-Knothole in 1953, a report was published
by the PHS summarizing the surveillance data for each test series. In 1959
for reactor tests, and in 1962 for weapons and Plowshare tests, such data were
published for those tests that released radioactivity detectable off the NTS.
111
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The reporting was changed again in 1964 to semi-annual publication of data for
each 6-month period which also included the data from the individual reports.
In 1971, the AEC implemented a requirement, now referred to as the DOE
Order 54R4.1, that each contractor or agency involved in major nuclear act-
ivities provide a comprehensive annual radiological monitoring report. This is
the twelth annual report in this series; 1t summarizes the activities of the
EPA during CY 1983.
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CONTENTS
Preface iii
Figures vii
Tables ix
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 1983 ... 8
4. Quality Assurance 10
Goals 10
Sample Collection 10
Sample Analysis 10
Validation 11
Audits 12
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CONTENTS (Continued)
Page
5. Radiological Safety Activities 13
Special Test Support 13
Pathways Monitoring 14
Air Surveillance Network 14
Noble Gas and Tritium Surveillance Network 17
Long-Term Hydrological Monitoring Program 23
Milk Surveillance Network 27
Biomonitoring Program 30
External Exposure Monitoring 32
Thermoluminescent Dosimetry Network 32
Pressurized Ion Chamber Network 42
Internal Exposure Monitoring 43
Network Design 43
Methods 43
Results 45
Community Monitoring Stations 45
Claims Investigations 46
Public Information Program 47
Dose Assessment 47
6. Bibliography 50
Appendices
A. Site Data 53
R. Sample Analysis Procedures 64
C. Quality Assurance Procedures 66
D. Radiation Protection Standards for External and Internal
Exposure 73
E. Data Summary for Monitoring Networks 75
VI
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FIGURES
Number Page
1 Location of the Nevada Test Site 6
? Air Surveillance Network stations (1983) 15
3 Standby Air Surveillance Network stations (1983) 16
4 Monthly Average Gross Beta in air, 1981-1983 18
5 Noble Gas and Tritium Surveillance Network
sampling locations 20
6 Weekly average distribution of krypton-85 concentration in
air, 10R3 data 21
7 Trend in annual average krypton-85 concentration 21
8 LTHMP sampling locations on the NTS 24
9 LTHMP sampling locations near the NTS 25
10 Milk sampling locations within 300 km of the NTS 28
11 Strontium-90 concentration in Pasteurized Milk Network
samples 30
12 Collection sites for bighorn sheep samples 31
13 Average strontium-90 concentration in animal bone 36
14 Locations monitored with TLD's 39
15 Average annual TLD exposure as a function of station
altitude 41
16 Location of families participating in the Offsite Human
Surveillance Program 44
Appendix A
A-l Groundwater flow systems around the NTS 56
A-2 General land use within 300 km of the NTS 57
vii
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FIGURES (Continued)
Number Page
A-3 Population of Arizona, California, Nevada, and Utah
counties near the NTS (1980) 59
A-4 Distribution and number of family milk cows and goats,
by county 60
A-5 Distribution of dairy cows, by county 61
A-6 Distribution of beef cattle, by county 62
A-7 Distribution of sheep, by county 63
Appendix E
E-l Amchitka Island and Background sampling locations
for the LTHMP 90
E-2 LTHMP sampling locations for Project Cannikin 91
E-3 LTHMP sampling locations for Projects Mil row and Long Shot. . 93
E-4 LTHMP sampling locations for Project Rio Blanco 96
E-5 LTHMP sampling locations for Project Rulison 98
E-6 LTHMP sampling locations for Project Dribble -
towns and residences TOO
E-7 LTHMP sampling locations for Project Dribble - near GZ. . . . 102
E-8 LTHMP sampling locations for Project Dribble -
near salt dome 104
E-9 LTHMP sampling locations for Project Faultless 106
E-10 LTHMP sampling locations for Project Shoal 107
E-ll LTHMP sampling locations for Project Gasbuggy 109
E-12 LTHMP sampling locations for Project Gnome Ill
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TABLES
Number Page
1 Total Airborne Radionuclide Emissions at the NTS During 1983. . 9
2 Annual Average Krypton-85 Concentrations in Air, 1974-1983. . . 22
3 Water Sampling Locations Where Samples Contained
Man-made Radioactivity - 1983 26
4 Network Annual Average Concentrations of Tritium
and Strontium-90 in Milk, 1975-1983 29
5 Radionuclide Concentrations in Sheep Tissue Samples - 1983 . . 33
6 Radionuclide Concentrations in Cattle Tissue Samples - 1983 . . 35
7 Radionuclides in Selected Vegetable Crops - 1982 32
8 Dosimetry Network Summary for the Years 1971-1983 36
9 Pressurized Ion Chamber Readings - yR/hr 37
Appendix A
A-l Characteristics of Climatic Types in Nevada 54
Appendix B
B-l Summary of Analytical Procedures 64
Appendix C
C-l Samples and Analyses for Duplicate Sampling Program 66
C-2 Sampling and Analytical Precision 68
C-3 1983 Quality Assurance Intercomparison Results 69
C-4 Quality Assurance Results for the Bioenvironmental Program. . . 71
C-5 Summary Results of the Sixth International Intercomparison
of Environmental Dosimeters 72
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TABLES (Continued)
Number Page
Appendix D
D-l DOE Concentration Guides 74
Appendix E
E-l 1983 Summary of Analytical Results for ASN Continuously
Operating Stations 75
E-? 1983 Summary of Analytical Results for ASN Standby Stations
Operated 1 or ? Weeks per Quarter 77
E-3 1983 Summary of Analytical Results for the Noble Gas
and Tritium Surveillance Network 81
E-4 1983 Summary of Gross Beta Analyses for the ASN 83
E-5 1983 Summary of Plutonium Concentrations at Selected
ASN Stations 84
E-fi 1983 Summary of Tritium Results for the NTS Monthly
Long-term Hydrological Monitoring Program 86
E-7 Tritium Results for the NTS Long-term Hydrological
Monitoring Program, Semi-Annual Project for 1983 87
E-8 Tritium Results for the NTS Long-term Hydrological
Monitoring Program, Annual Project for 1983 89
E-9 Tritium Results for the Off-NTS Long-term Hydrological
Monitoring Program (1983 Annual Samples) 92
E-in 1983 Summary of Analytical Results for the Milk
Surveillance Network 113
E-ll Analytical Results for Standby Milk Surveillance Network - 1983
E-12 1983 Summary of Radiation Dose Equivalents from TLD Data ... 116
E-l3 1983 Summary of Radiation Doses for Offsite Residents 1?6
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ABBREVIATIONS, SYMBOLS AND CONVERSIONS
a annum (year)
ASN A1r Surveillance Network
CG Concentration Guide
C1 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 trltlated water
L liter
LTHMP Long-Term Hydrologlcal Monitoring Program
m meter
MDC Minimum Detectable Concentration
MSL Mean Sea Level
MSN M1lk 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 thermolumlnescent dosimeter
x1
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PREFIXES
a atto = 10-18
f femto = 10-15
p p1co = 10-12
n nano = 10-9
M micro = 10-6
m rnHH = 10-3
k kilo = 103
M Mega =
Multiply
CONVERSIONS
By
Concentration Guides
uC1/mL
uC1/mL
SI Units
rad
rem
pC1
109
1012
10-2
10-2
0.037
To Obtain
pCI/L
Gray (Gy = 1 Joule/kg)
Slevert (Sv)
Becquerel
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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
Doslmetry Network as described 1n Section 5 of this report. These services plus
a summary of the results and preliminary Interpretation are supplied, under
contract, to the Nuclear Radiation Assessment Division, EMSL-LV.
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SECTION 1
SUMMARY
PURPOSE
It 1s 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 1n concordance with U.S. Depart-
ment of Energy policy of keeping radiation exposure of the general public as
low as reasonably achievable, the EMSL-LV conducts an Offslte Radiological
Safety Program centered on the DOE's Nevada Test Site. This program 1s conduc-
ted under an Interagency Agreement between EPA and DOE.
A principal activity of the Offslte Radiological Safety Program Is routine
environmental monitoring for radioactive materials 1n various media and for
radiation 1n areas which may be affected by nuclear tests. It 1s conducted to
document compliance with standards, to Identify trends, and to provide informa-
tion to the public. This report summarizes these activities for CY 1983.
Locations
Most of the radiological safety effort 1s applied In the areas around the
Nevada Test Site 1n 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 1n the near offsite area is Beatty, located
about 65 km west of the NTS with a population of about 800.
Underground tests have been conducted In several other States for various
purposes. At these sites 1n Alaska, Colorado, New Mexico and Mississippi, a
long-term hydrologlcal monitoring program (LTHMP) 1s conducted to detect any
possible contamination of potable water and aquifers near these sites.
Pathways Monitoring
The pathways leading to human exposure to radlonuclides, 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.
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In 1983 the air surveillance network (ASN) consisted of 29 continuously
operating stations surrounding the NTS and 85 standby stations (operated 1 or 2
weeks each quarter) in all States west of the Mississippi. Other than naturally
occurring heryllium-7, the only activity detected hy this network was plutonium-
?39 from worldwide fallout.
The nohle qas and tritium sampling network (NGTSN) consisted of 16 sta-
tions offsite (off the NTS and exclusion areas) in 1983. No NTS-related radio-
activity was detected at any offsite station. Tritium concentration in air
remained below MPC levels and krypton-SB concentration continued the upward
trend which started in 1960, reflecting the worldwide increase in the use of
nuclear technology.
The long-term hydroloqical 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 28 sampling locations
within 3nn km of the NTS and about 86 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 qarrten vegetables. The radionuclide most frequently found in the edible
portion of the sampled animals is cesium-137. Its concentration has been low
since 1Q68. 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
Fxternal exposure is monitored by a network of Tin's at 86 locations
surrounding the NTS and hy TLO's worn by 46 offsite residents. In a few cases,
small exposures of a few mrem above the average for the person or location were
measured. Except for several occupational exposures, all such net exposures
were very low and were not related to NTS activities. The ranqe of exposures
measured, varying with altitude and soil constituents, 1s 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 1983, counts
were made on 154 offsite residents, and on 166 EPA and EG&G, ?. DRI, 1 REECo,
and 3 WSI 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 1n 1982. Each
station 1s operated by a resident of the community who 1s trained to collect
samples and Interpret some of the data. Each station 1s an Integral part of
the ASN, NGTSN and TLD networks and 1s also equipped with a pressurized ion
chamber system and recording barograph. Samples and data from the stations are
analyzed by EMSL-LV and are also Interpreted and reported by the Desert Research
Institute, University of Nevada. Data from these stations are reported herein
as part of the networks 1n 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 0.2 mrem
per year, a small fraction of the variation of 10 mrem per year due to the
natural radlonucllde content of the body. Since no radioactivity originating
on the NTS was detectable offslte, 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 5 x 10-5 man-rem for 1983.
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SECTION 2
INTRODUCTION
The EMSL-LV operates an Offslte Radiological Safety Program around the NTS
and other sites as requested by the Department of Energy (DOE) under an Inter-
agency Agreement between DOE and EPA. This report, prepared in accordance with
the guidelines in DOE/EP-0023 (DOE 1981a), covers the program activities for
calendar year 1983. 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 measure-
ments. 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 devel-
opment 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 1983, 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 1n 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 1s 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 varia-
tions in altitude and its rugged terrain. Generally, the climate is referred
to as continental arid. Throughout the year, there is insufficient precipita-
tion to support the growth of common food crops without irrigation.
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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 1n areas with less than 25 cm of rainfall per year or 1n 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 hydrologlcal 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 hydrologlcal characteristics for
much of the NTS are known In considerable detail (see Figure A-l). This is
particularly true for those areas 1n which underground experiments are conducted.
A comprehensive summary of the geology and hydrology of the NTS by Winograd and
Thordarson was published 1n 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 1s 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 1n 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
1n 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 1n the Las Vegas Valley. Some Lake Mead water is used
1n Arizona, southern California, and Mexico. Smaller reservoirs and lakes
located 1n 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 1983 showed 78,000 dairy cows, 757 family milk cows
and 847 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 650,000 cattle and 110,000 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 livestock statistics report, from 1983
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 ISO 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 3,900, is located about 72 km south-southwest of
the NTS CP-1. The Amargosa Farm Area, which has a population of about 1,500,
is located about 50 km southwest of CP-1. The largest town in the near-offsite
area is Reatty, which has a population of about 800 and is located approximately
65 km to the west of CP-1.
AIRBORNE RELEASES OF RADIOACTIVITY AT THE NTS DURING 1983
All nuclear detonations during 1983 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
(1984). 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 RAOIONUCLIDE EMISSIONS
AT THE NTS DURING 1983
= = s = s = = = = =! = = 3B = = = = = = =: = = = = = = 33: = = = = aB = = =:s = =! = = = = = =
Half-Life Quantity Released
Radionuclide (days) (C1)
Tritium 4,500 98.2
Iodine-131 8.04 1 x 10-5
Iodine-135 0.27 3 x 10-5
Xenon-133 5.29 26.6
Xenon-133m 2.33 1.5
Xenon-135 0.38 28.9
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SECTION 4
QUALITY ASSURANCE
GOALS
The goals of the EMSL-LV quality assurance program are to assure the col-
lection and analysts 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, 1t 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 Opera-
ting Procedures (SOP's). These SOP's prescribe the frequency and method of
collection, the type of collection media, sample containment and transport,
sample preservation, sample Identification and labeling, and operating param-
eters for the Instrumentation. Sample control 1s an Important segment of these
activities as 1t 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 Assur-
ance Project Plans that assure the results of analysis will be of known quality
and will be comparable to results obtained elsewhere with equivalent procedures.
These Plans are summarized 1n the following sections.
External QA
External QA provides the data from which the accuracy of analysis (a com-
bination of bias and precision) can be determined. Bias 1s assessed from the
results obtained on Intercomparlson study samples and on samples "spiked" with
10
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known amounts of radlonuclides. The Offslte Radiological Safety Program par-
ticipates in Intercomparison Study Programs that Include environmental sample
analysis, TLD doslmetry, 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. Repli-
cate counting of at least 10 percent of all samples yield data from which the
precision of counting can be determined.
If the bias and precision data are of sufficient quality (I.e., normalized
deviation in Table C-3 1s less than 3), then comparability, I.e., comparison of
the data with those of other analytical laboratories, can be assessed with con-
fidence. The results of external QA procedures are shown in Appendix C.
Internal QA
Internal QA consists of those procedures used by the analyst to assure
proper sample preparation and analysis. The principal procedures used are the
following:
o Instrument background counts
o Blank and reagent analyses
o Instrument calibration with known nuclldes
o Laboratory control standards analysis
o Performance check-source analysis
o Maintenance of control charts for background and check-source data
o Scheduled instrument maintenance
These procedures ensure that the Instrumentation 1s not contaminated, that cali-
bration 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.
11
-------
AUDITS
All analytical data are reviewed by personnel of the Dose Assessment
Branch for completeness and consistency. Investigations are conducted to
resolve any inconsistencies and corrective actions are taken if necessary.
SOP's and QA project plans are revised as needed following review of procedures
and methodology. The EMSL-LV QA Officer audits the operations periodically.
12
-------
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, thermolumlnescent 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 are 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 radio-
activity 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. Information
from these aircraft can be used 1n positioning the radiation monitors.
Previous to this year, emergency situations which arose as a result of
accidental leakage from any NTS nuclear tests, e.g., establishing road blocks,
advising residents to remain indoors, substituting feed for dairy herds, etc.,
13
-------
were handled informally with the cooperation of local authorities. These pro-
cedures are now being formalized. During 1983 an Emergency Response Plan was
formulated, among EPA, DOE, and Lincoln County Officials, which will become a
portion of the County Emergency Plan. Under this plan, the County will insti-
tute emergency response measures with the advice of EPA and DOE personnel.
Similar plans will be formulated with the counties of Nye, Clark, White Pine,
and Esmeralda in the near future.
During CY 1983 none of the tests conducted at the NTS released radioactiv-
ity that was detected offsite.
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.
The ASN is designed to cover the areas within 200 km of the NTS with some con-
centration of stations in the prevailing downwind direction (Figure 2). The
coverage is constrained to those locations having avvailable electrical power
and a resident willing to operate the equipment. This continuously operating
network is reinforced by a standby network which covers the contiguous States
west of the Mississippi River, Figure 3.
Methods--
During 1983 the ASN consisted of 29 continuously operating sampling sta-
tions and 85 standby stations. The air sampler at each station was equipped to
collect both particulate radionuclides and reactive gases.
Samples of airborne particulates were collected at each active station on
5-cm diameter glass-fiber filters at a flow rate of about 81 m3 per day. Fil-
ters were changed after sampler operation periods of 2 or 3 days (160 to 240
rr)3). Activated charcoal cartridges placed directly behind the filters to
collect gaseous radiolodlne were changed at the same time as the filters. The
standby network was activated for 1 to 2 weeks per quarter. The samplers are
identical to those used in the ASN and are operated by State and municipal
health department personnel or by local residents. All air filters and charcoal
cartridges were analyzed by the EMSL-LV.
Results —
Throughout the network, beryllium-7 was the only nuclide detected by gamma
spectroscopy. The principal means of beryl!ium-7 production is from spallation
of oxygen-16 and nitrogen-14 1n the atmosphere by cosmic rays. Appendix Tables
14
-------
Scotty's Jet.
\«
Beany •
Lathrop Wei
Furnace Creek • p
Death Valley Jet. •
ada
stin Ely
0 • Sunnyside
bin Rn. Bk|e Eag)e Rn
• Nyala
• Twin Springs Rn.
•TTR
Rachel Hiko
• _ • Alamo
• (•Groom
|Test| Lake
X 'Jndian «Aov
\ Sprmgs A |
hrump • . J( Lak
1
%|
•
1
• I
Salt Lake City |
« 1
*- I
D
Delta • I
1
• Milford |
• Cedar City |
• St. George 1
Arizona
rton
e Mead
Shoshone
• Community Monitoring Stations (15)
• Other Locations (14)
3/84
Figure 2. Air Surveillance Network stations (1983)
15
-------
100 30O BOO TOO
Scale in Kilometers
A Stand-by ASM Station (85)
3/83
Figure 3. Standby Air Surveillance Network stations (1983)
16
-------
E-l and E-2 summarize the data from the ASN samples. All time-weighted aver-
ages (Avg in the tables) are less than 1 percent of the Concentration Guide
(Appendix D) for exposure to the general public, however, these guides do not
apply to naturally-occurring radionuclides.
During 1983, 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 of beryllium-7
for all stations during the year versus probits indicates that the air data are
approximately lognormally distributed. The distribution for the individual
nuclide that was detected indicated that there was a single source, assumed to
be worldwide, 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 contribu-
tion from thoron daughter activity. The data suggest little significant differ-
ence among stations and indicate a relatively stable concentration compared to
previous years (Figure 4). The maximum concentration measured was 0.08 pCi/m3,
the minimum was <0.006 pCi/m3, and the arithmetic average was 0.008 pCi/m3. A
summary of the data is shown in Appendix Table E-4. The gross beta analysis was
reinstated in July 1981. Fallout from the Chinese atmospheric test in 1980 was
still detectable at that time, but it appears to have decreased significantly.
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 compos-
ited quarterly, and those from the ASN stations are composited monthly. The
composites are analyzed radiochemically as indicated in Appendix B.
The available data for plutonium-238 and -239 concentration in air are
shown in the Appendix (Table E-5). All results were less than the MDC except
for the Missouri composite for May 1983. The actual net activity is displayed
in the Appendix table. The percent of the concentration guide that is shown is
calculated for the sum of the plutonium concentrations, assuming the concentra-
tion measured was the annual average for that sampling location.
Noble Gas and Tritium Surveillance Network
Network Design--
There are several sources for the radionuclides monitored by this network.
Noble gases are emitted from nuclear power plants, propulsion reactors, reproc-
essing facilities and nuclear explosions. Tritium is emitted from the same
17
-------
10-'-,
X
U
.£ 10-2-
*
CO
g
o
10-3-
1981
•• •
I I I I I M I I | I I I I I I I I I I I |
1982 1983
Figure 4. Monthly average gross beta in air samples, 1981-83.
18
-------
sources and is also produced naturally. The monitoring network will be affec-
ted 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 particularly in
drainage-wind channels leading from the test areas. In 1983 this network con-
sisted of 16 stations as shown in Figure 5.
Methodology-
Samples of air are collected by either of two methods; by directly compres-
sing 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 by condensing
the samples at liquid nitrogen temperature and using gas chromatography 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 adsorbed on the molecular
sieve 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 1983. The average concentrations of krypton-85 at
all network stations ranged from 23 to 27 pCi/m^ (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/m^ and a geometric standard deviation of 1.15.
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 nuclear technology.
The increase in ambient krypton-85 concentration was projected by Bernhardt, et
al., (1973). However, the measured network average in 1983 is only about 16%
percent of the 160 pCi/m^ predicted by Bernhardt. Since nuclear fuel reproces-
sing 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 in-
creased 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 pC1/m3 = 5.7 + 0.82t where t is number of years after
1960. The correlation coefficient, R, is 0.98.
19
-------
Ely
3/84
Rachel
• Alamo
BeattyB
Lathrop Well*
Salt Lake City
• Cedar City
• St. George
Arizona
• Mead
\ •«==• tfr°;
Figure 5. Noble Gas and Tritium Surveillance network sampling locations.
?0
-------
i 30-
V
o
a
c 20-
o
a
e •
to
CD
15-
10-
•• •
•e»e »e»
e e
i i I I I I I I i i | i I I I
13
I I I
26
I I I • I I I I T I I l I I II III T IT
' 39 62
Weeks- 1983
Figure 6. Weekley average distribtition of krypton-35 concentration
in air, 19R3 data.
30-i
1960
Least Squares Line: pCi mj 5.7 4 0.821
R 0.98
1980 1985
Time - Calendar Years
Figure 7. Trend in annual average krypton-RS concentration.
?\
-------
TABLE 2. ANNUAL AVERAGE KRYPTON-85 CONCENTRATIONS IN AIR, 1974-1983
Sampling
Locations
Alamo, Nev
Austin, Nev.
Beatty, Nev.
Diablo and
Rachel, Nev.
Ely, Nev.
Goldfield, Nev.
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 Jet.,
Calif.*
NTS, Area 15, Nev.*
NTS, Area 400, Nev.*
Lathrop Wells, Nev.
Pahrump, Nev.
Overton, Nev.
Cedar City, Ut.
St. George, Ut.
Salt Lake City, Ut.
Shoshone, CA
Network Average
:===========
1974
V W
—
17
17
__
— •
17
—
18
17
19
18
18
17
18
—
__
--
__
—
__
—
__
—
18
1975
M W
—
19
18
__
—
17
20
18
18
19
18
17
18
17
—
__
—
__
--
__
--
--
—
18
=3======================
Kr-85 Concentrations
1976
V W
—
20
19
__
—
17
20
19
20
20
20
19
18
20
—
__
--
__
--
__
--
__
--
19
1977
* M
—
20
19
__
—
19
20
20
19
21
19
19
20
20
--
__
--
__
--
__
--
-_
—
20
1978
tm ^
--
20
20
__
—
20
20
20
20
22
20
20
20
20
—
__
—
__
--
__
--
__
--
20
1979
^ ^^
—
19
19
__
—
19
19
19
19
21
19
18
--
19
19
18
19
__
--
__
—
__
--
19
======================
(pC1/m3)
1980
•• ^
—
21
21
__
—
21
21
21
21
23
21
21
--
_.
21
21
22
__
--
__
--
__
--
21
1981
27
—
24
24
__
—
24
24
23
24
26
24
25
24
__
25
23
24
23
26
--
--
--
—
24
1982
24
24
25
26
24
25
26
24
__
—
«• _
—
24
24
.._
—
__
24
24
24
25
24
25
25
24
1983
25
25
24
24
25
24
»
25
__
—
__
—
25
24
...
—
__
26
24
25
24
25
25
25
25
================================
*Stations discontinued
New stations
Station at Diablo was moved to
33333==========
Rachel in March 1979.
22
-------
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
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 0.08 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 1.5.
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.
The monitored locations for the NTS and nearby offsite areas are shown in
Figures 8 and 9. For Projects Cannikin, Longshot and Milrow 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 HNOs. 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 1n samples collected at most of these
locations has been reported 1n 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 concentration guide listed in Appendix D. No man-made gamma-
em.itting radionuclides were detected 1n any of the other water samples analyzed.
23
-------
Nuclear Rocket
Development Station
A Monthly (12)
• Semi-Annual (7)
3/84
Figure 8. LTHMP sampling locations on the NTS.
24
-------
Twin Springs Rn. A
^Tonopah
0TTR Well #6
Nellis
J? Air Force |_
.T Range
X O
^~*v, Nevada
"i Test Site
Springdale* X
X Goss Springs • Coffer's
X BeattV- 11S/48-1dd
,
^^ Neco
^ h^ NRDS Mercury
Lathrop Wells | \ *|
•v ^-^US
^
• Nyala
^Adaven Springs
^Tempiute
• Hiko
-i ^Crystal Springs
1 I
AF#2^Lj
• Indian Springs
K. BFairbanks Springs Sewer Co. Well #1
Well 17S/50E-14CACJI
X. iLCrystal Pool
Well 18S/51E-7db>»Ash Meadows
Death Valley Jct.« 'v
A Las Vegas
Xvfc •Calvada Well #3 " Well #28
ty&tr
\\
Lake Meadl
Intake
• Shoshone ""v
<
c
3/
•
Scale in Miles
) 10 20 30 40
^^^H^H[^Z^^H^lE.^^J^Hir^
1 1 1 i i i
) 10 20 30 40 50 60
'84 Scale in Kilometers
Annual Samples (11)
Semi-Annual Samples (12)
1 Nevada
k
Nevada Test Site &lkt
Nellis Air Force Range^D
Location Map\J
Figure 9. LTHMP sampling locations near the NTS.
-------
TABLE 3. WATER SAMPLING LOCATIONS WHERE SAMPLES
CONTAINED MAN-MADE RADIOACTIVITY - 19R3
Sampling Location
NTS (Nev.)
Well UE7NS
ADAVEN (Nev.)
PROJECT GNOME (N. Mex.)
USGS Well 4
USGS Well 8
Well LRL-7
PROJECT DRIRBLE (Miss.)
Well HMH-1 through 11
Well HM-S
Well HM-L
REECo Pit Drainage-B
Half Moon Creek
PROJECT LONG SHOT (Alaska)
EPA Well 1
Well WL-2
Well GZ, No. 1
Well GZ, No. 2
Mud Pit No. 1
Mud Pit No. 2
Mud Pit No. 3
Type of
Radioactivity
Hydrogen-3
Hydrogen-3
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
Hydrogen-3
Concentration
(PCi/L)
1500
650
330,000
9,000
10
260,000
5,700
61
23,000
13
220
38-85,000
19,000
2,200
12,400
550
820
290
3,800
270
600
590
740
26
-------
None of the racHonuclide concentrations found at the locations listed in
Table 3 are expected to result in measurable radiation exposures to residents
in the areas where the samples were collected. Well UE7NS 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 LRL-7 was
used for the disposal of contaminated soil and salt. As a result, this well is
expected to produce contaminated water.
The Project Dribble wells in Mississippi are about 1 mile from the nearest
residence and are not sources of drinking water. The spring at Adaven is fed
by melting snow containing tritium washed from the atmosphere. The concentra-
tion is only 3% of the EPA guide for continuous exposure and will decrease as
the runoff ceases.
The shallow wells at the Project Long Shot site on Amchitka Island in
Alaska are in an isolated location and are not sources of drinking water.
Milk Surveillance Network (MSN)
Network Design—
An important pathway for transport of radionuclides to humans is the air-
forage-cow-milk chain. This pathway is monitored by EMSL-LV through analysis
of milk. The design of the network is based on collections from areas likely
to be affected by accidental releases from the NTS as well as from areas un-
likely to be so affected. Additional considerations are: 1) a complete ring
of stations to cover any eventuality, 2) samples from major milksheds 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 1n all major milksheds west of the
Mississippi River from which samples are collected annually. One exception to
the latter portion of the network 1s Texas; the State Health Department per-
forms the surveillance of the milksheds 1n 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 1n cubitainers and preserved with formaldehyde
but they are collected by contacting State Food and Drug Administration Repre-
sentatives, after notification of the Regional EPA offices by telephone, and
mailed to EMSL-LV for analysis.
27
-------
• Elku
Larsen Rn I
•Reno
• Austin
| Young Rn.
• McGill
• Ely
Burdick Rn
Harbecke Rn
I
• Shoshone
0 50 100 150
Scale in Kilometers
3/84
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.
28
-------
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 1983 milk samples are summarized in Appen-
dix Table E-10 and Table E-ll where the maximum, minimum, and average concen-
trations 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 are considered to be low by about 25
percent in the fourth quarter of 1983.
TABLE 4. NETWORK ANNUAL AVERAGE CONCENTRATIONS OF
TRITIUM AND STRONTIUM-90 IN MILK, 1975 - 1983
=======3============:
Average Concentrations - pC1/L
Year H-3 Sr-90
1975
1976
1977
1978
1979
1980
1981
1982
1983
=3====
<400
<400
<400
<400
<400
<400
<400
<400
<400
=====================
<3
<2
<2
1.2
<3
<2
1.9
1.2
0.8
========================
Other than naturally occurring potassium-40, radionuclides were not de-
tected by gamma spectrometry in any of the samples from the MSN.
The tritium and strontium-90 concentrations for the whole milk network
were plotted versus probits. The tendency of the data to fit one straight line
indicates that the data represent a single source, which appears to be atmos-
pheric deposition. These results are consistent with the results obtained for
the Pasteurized Milk Network shown in Figure 11. This network is operated by
the Eastern Environmental Radiation Laboratory in Montgomery, Alabama.
29
-------
* New Orleans
• Salt Lake City
• Las Vegas
Figure 11. Strontium- 90 concentration in Pasteurized Milk Network samples.
Biomonitoring Program
Objective--
The pathways for transport of radionucl ides to man include air, water, and
food. Monitoring of air, water, and milk are discussed above, leaving garden
vegetables and meat as the other potential components of exposure to near
This program was established to document uptake from these
From 1957 through 1931, this was named the Animal Investigation
A summary report for those years was published recently (Smith and
offsite residents.
sources.
Program.
Black 1984).
Methods —
Samples of muscle, lung, liver, kidney, blood, and bone are collected
periodically from cattle purchased from a commercial herd that grazes areas
northeast of the NTS. These samples are analyzed for gamma emitters, tritium,
strontium, and plutonium. Also, each November and December, bone and kidney
samples from desort bighor-n sheep collected throughout southern Nevada (sae
Figure 12) are donated by licensed hunters and are analyzed. These kinds of
samples have been collected and analyzed for up to 26 years to determine long
term trends. In the late summer of alternate years, kilogram samples of a
leaf, a fruit, and a root vegetable will be collected from gardens in three
30
-------
COYOTE SMT
HANCOCK SMT.^f
I
NELLIS
AIR FORCE
I RANSE i(T;
j Desert
1 ^National
Wildlife
Range
^ ©
INDIAN SPRK
CACTUS SPRINGS
PAHRUMP "^(^ ('0
LAS VEGAS
O Indicates collection site of
individual animal
SEARCHLIGHT \
Figure 12. Collection sites for bighorn sheep samples.
31
-------
communities northeast of the NTS and a similar set of samples from a garden in
Las Vegas. These vegetable samples are analyzed for gamma emitters, tritium,
strontium, and plutonium.
Results--
Analytical data from bones and kidneys collected from desert bighorn sheep
during 1QR2 are presented in Table 5. Cesium-137 was detected in the kidneys
of two animals (24 ± 17 and 38 ± 21 pCi/kg). Tritium was not detected in any
of the kidneys sampled. Strontium-90 levels in the bones (average 1.59 pCi/g
ash) are consistent with the reports in recent years (Figure 13). Counting
errors generally exceeded the reported concentrations of plutonium-238 and -239
in the bone ash.
Analytical data for samples collected from four beef cattle are presented
in Table 6. These cattle grazed the Steve Medlin Ranch which is the first
ranch to the east of the Nevada Test Site. Other than the naturally ocurring
potassium-40, the only gamma-emitting radionuclide detected, was Cesium-137 in
one liver sample (23 ± 12 pCi/kg). Tritium and pluton1um-238 and -239 were not
detected in any of the samples analyzed. Strontium-90 detected in the bones
averaged 1.4 pCi/g of ash which continues the downward trend of recent years
(Figure 13).
Three reports summarizing the activities carried out by the Animal
Investigation Program (the predecessor of the Biomonitorlng Program) are at
various stages in the publishing process. One has been published as mentioned
above. The other two are:
o a report on the radionuclide uptake studies conducted at the NTS
Experimental Dairy Farm from 1963 to 1981, and
o a report describing the migration patterns of the NTS deer herd as
observed during the years 1977 to 1981.
Other than potassium-40, gamma-emitting radionuclides were not detected
in any of the vegetables collected from the four Nevada locations in 1982.
Tritium concentrations were also below detectable limits. Strontium and
plutonium analyses are shown in Table 7.
EXTERNAL EXPOSURE MONITORING
Thermo!uminescent 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
sensitivity and precision. From 1970 to 1974 the EMSL-LV used the TLD-12
dosimeter but changed to the TLD-200 in 1975.
32
-------
TABLE 5. RADIONUCLIDE CONCENTRATIONS IN SHEEP TISSUE SAMPLES
Bighorn Bone
Sheep 90Sr
(Collected (pC1/g Ash)
Dec. 1982) (pCi/kg)*
1 2.5 ± 0.092
640 ± 230
2 1.7 ± 0.07
570 ± 240
3 0.8 ± 0.05
280 ± 190
4 2.4 ± 0.089
920 ± 340
5 1.6 ± 0.074
580 ± 260
6 2.0 ± 0.092
690 ± 320
7 1.9 ± 0.083
500 ± 220
8 1.6 ± 0.069
380 ± 160
9 0.47 ± 0.041
150 ± 140
10 0.75 ± 0.5
190 ± 120
Bone
238Pu
(pCi/g Ash)
(pCi/kg)*
0.0013 ± 0.003**
0.33 ± 0.77
-0.0013 ± 0.0062**
-0.46 ± 2.2
0.0017 ± 0.0035**
0.6 ± 1.3
0.00027 ± 0.0013**
0.1 ± 0.48
0.0019 ± 0.0037**
0.67 ± 1.3
0.00034 ± 0.0016**
0.12 ± 0.55
0.00034 ± 0.0016**
0.088 ± 0.41
-0.0015 ± 0.0067**
-0.34 ± 1.6
-0.00039 ± 0.0018**
-0.13 ± 0.59
0.00064 ± 0.0021**
0.16 ± 0.52
Bone
239Pu
(pCi/g Ash) 1
(pCi/kg)*
0.019 ± 0.0053
4.9 ± 1.4
0.0027 ± 0.004**
0.92 ± 1.4
0.0027 ± 0.0045**
0.96 ± 1.6
0.00055 ± 0.0018**
0.21 ± 0.68
0.013 ± 0.0043
4.7 ± 1.5
0.0024 ± 0.0043**
0.83 ± 1.5
0.003 ± 0.0047**
0.79 ± 1.2
0.0011 ± 0.0029**
0.26 ± 0.69
0.0031 ± 0.0052**
1.0 ± 1.7
0.0016 ± 0.0033**
0.39 ± 0.82
Kidney
K(g/kg)*
37Cs(pCi/kg)
3H(pCi/l)*
2.8 ± 0.4
<35
<380
3.4 ± 0.4
<45
<390
4.4 ± 0.9
<97
<520
2.6 ± 0.5
<36
<200
2.0 ± 0.4
<34
<470
2.6 ± 0.7
<61
Sample Lost
3.1 ± 0.4
<38
<250
2.0 ± 0.8
<64
<250
3.2 ± 0.4
25 ± 17
<420
4.2 ± 1.1
<120
<400
*Wet weight.
**Counting error exceeds reported activity.
^Aqueous Portion of Kidney Tissue.
Continued
33
-------
TABLE 5. CONTINUED
Bighorn Bone
Sheep 90Sr
(Collected (pCi/9 Ash)
Dec. 1982) (pCi/kg)*
11 1.5
560
12 0.48
120
13 0.62
240
14 0.78
270
15 1.3
490
16 1.2
360
17 4.3
1030
18 2.7
630
Median
+
±
±
+
±
±
±
±
±
±
±
±
±
±
±
±
1.
0.078
300
0.43
110
0.44
170
0.48
170
0.061
230
0.082
250
0.12
290
0.096
230
55
495
======================================================
Bone Bone Kidney
238Pu 239Pu K(g/kg)*
(pCi/g Ash) (pCi/g Ash) 137Cs(pCi/kg)
(pCi/kg)* (pCi/kg)* 3H(pCi/l)*
-0.00097
-0.37
0.00095
0.24
-0.00067
-0.26
0.002
0.7
-0.00065
-0.25
0.00
0.00
0.0024
0.59
0.0013
0.31
0.
0
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
0
1
0
0
0
1
0
1
1
1
0
0
0
1
0
1
.0045**
.7
.0026**
.63
.0031**
.2
.0036**
.2
.003**
.2
.0016**
.48
.0051**
.2
.0042**
.0
00034**
0.00033
0.12
-0.00095
0.24
-0.00067
-0.26
-0.00029
-0.1
0.0013
0.49
0.00069
0.21
0.0019
0.47
0.0026
0.61
0.
.11**
+
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
0.0015**
0.57
0.0025**
0.63
0.0031**
1.2
0.0013**
0.46
0.003**
1.2
0.0023**
0.69
0.0046**
1.1
0.006**
1.4
00175**
0.
48**
2.8
5.0
3.1
2.1
3.6
2.5
Sampl
3.5
Sampl
2.7
38
Sampl
± 0.5
<57
<510
± 0.5
<52
<120
± 0.4
<39
<290
± 0.3
<36
<270
± 0.4
<39
<120
± 0.49
<63
e Lost
± 0.4
<39
e Lost
± 0.41
± 21
e Lost
3.95
<39
<385
Range 0.47
120
-
4.3
1030
-0.0015**
-0.46**
-
0.
0.
0024**
7**
-0.00095**
-0.26**
-
™™ ~
0.019
4.9
• ••••••••• — •»••
2.0
25
<120
- 5.0
- <120
- <520
*Wet weight.
**Counting error exceeds reported activity.
^Aqueous Portion of Kidney Tissue.
34
-------
l^| Bighorn sheep
I I Deer
EU Cettle
Numbers at top of columns indicate
the number of bone samples in each
category. Numbers prior to 1964
are unknown.
56 58 60 62 64 66
70 72 74 76 78 80 82
Year (1956-1982)
Figure 13. Average strontium-90 concentration in animal bone.
Network Design--
The TLD network is designed to measure environmental radiation exposur? a!".
a location rather than to an individual because of the nany uncertainties asso-
ciated with personnel 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 person-
nel and environmental monitoring could be obtained. The network consists of %
monitored locations encircling the NTS with some concentration in the araa of
the estimated fallout zones (Figure 14). This arrangement permits an estimate
of average background exposure; yet any increase due to NTS activities can be
detected.
35
-------
TABLE 6. RADIONUCLIDE CONCENTRATIONS IN CATTLE TISSUE SAMPLES - 1983
MUSCLES
K(g/kg*)
MEDLIN RANCH, Oct 19*
BOV-1 5.9 ± 0.3
BOV-? 3 ± 0.3
LIVER
K(g/kg*)
LUNGS 137Cs(pCi/kg)
K(g/kg*) 239Pu(pCi/kg*)
J3:
1.2 ± 0.4 2.8 ± 0.3
<26
0.092 ± 0.16**
1.2 ± 0.5 2.1 ± 0.2
BONE
BLOOD 90Sr(pC1/g ash)
3H(pCi/l) 239Pu(pCi/g ash)
<400 1.8 ± 0.08
0.0017 ± 0.004**
<400 1.1 ± 0.064
BOV-3 4.9 ± 0.4
BOV-4 4.1 ± 0.3
2.6 ± 0.7
5.5 ± 0.7
<24
0.71 ± 0.75**
2.8 ± 0.4
<24
0.009 ± 0.04**
5.2 ± 0.4
23 ± 14
0.15 ± 0.23**
0.002 ± 0.0046**
<400 0.97 ± 0.06
0.0051 ± 0.0076**
<400 1.7 ± 0.084
0.004 ± 0.007**
*Wet weight.
**Counting error exceeds reported activity.
36
-------
TABLE 7. RADIONUCLIDES IN SELECTED VEGETABLE CROPS - 1982
Vegeta-
tion
Date
Lettuce
06-17-82
Zucchini
07-01-82
Turnips
08-04-82
Lamb's
Quarter
OR-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
Sr-89
(pCi/g ash)
(pCi/kg*)
0.65 ± 8.9**
6.3 ± 87**
-3.1 ± 15.0**
-18 ± 84**
-1.2 ± 7.7**
-14 ± 87**
-4.3 ± 6.9**
-160 ± 250**
-3.7 ± 28**
-24 ± 180**
-70 ± 110**
-1200 ± 1800**
0.41 ± 3.4**
7.0 ± 57**
1.5 ± 9.0**
11 ± 65**
-2.0 ± 0.59**
-15 ± 45**
-13 ± 58**
-64 ± 280**
Sr-90
(pCi/g ash)
(pCi/kg*)
Las Vega:
0.15 ± 0.06
1.4 ± 0.58
0.13 ± 0.26** •
0.11 ± 1.5**
0.14 ± 0.24**
1.6 ± 2.6**
Hiko
0.33 ± 0.087
12 ± 3.2
0.31 ± 0.77**
2.1 ± 5.0**
3 ± 3.3**
48 ± 52**
Rachel
5.9 ± 1.3
10 ± 2.2
0.37 ± 0.11 -
2.7 ± 0.76
0.5 ± 0.51**
3.8 ± 3.9**
Adaven
0.95 ± 2.4**
4.6 ± 11**
Pu-238
(pCi/g ash)
(pCi/kg*)
5
0.0009 ± 0.0029**
0.008 ± 0.028**
-0.00044 ± 0.0016**
-0.0019 ± 0.0089**
-0.0004 ± 0.0019**
-0.0045 ± 0.021**
0.0006 ± 0.0027**
0.022 ± 0.1**
0.0048 ± 0.0064**
0.032 ± 0.042**
0.0047 ± 0.0065**
0.075 ± 0.1**
0.0065 ± 0.011**
0.11 ± 0.21**
0.00032 ± 0.0015**
-0.0023 ± 0.011**
0.06 ± 0.002**
0.0 ± 0.16**
0.0037 ± 0.0062**
0.018 ± 0.03**
Pu-239
(pCi/g ash)
(pCi/kg*)
0.032 ± 0.0087
0.32 ± 0.084
0.0044 ± 0.0058**
0.025 ± 0.033**
0.022 ± 0.0066
0.25 ± 0.07
0.055 ± 0.015
2.0 ± 0.53
0.0037 ± 0.0055**
0.024 ± 0.037**
0.0064 ± 0.0078**
0.11 ± 0.12**
0.011 ± 0.016**
0.19 ± 0.28**
0.0016 ± 0.0034**
0.011 ± 0.024**
0.0014 ± 0.0037**
0.011 ± 0.028**
0.00093 ± 0.0031**
0.0045 ± 0.015**
* Wet weight
** Counting error exceeds
reported activity
37
-------
Methods--
In 1983 the TLD Network consisted of 86 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, 46 offsite residents wore dosimeters during 1983. 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 dosim-
eter is issued to each of 46 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 re-
sponse 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 back-
ground 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.
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.
38
-------
f
• Austin
Young Rn
Eureka
Gabbs • Round Mtn «
Manhattan •
Mma0 Stone Cabin
Duckwater (
Hot Creek
Rn. ,
. _ w S
Tonopah^ Twin Spgs Rn
Goldfield
• Ely
Kirkeby Rn
Cuffant •Lund
. ^Blue Eagle W^vser
^n •Sunnyside
• Complex I
(Pine Creek Rn •Pioche
Jf
Salt Lake City
| Garrison
Mammoth Mtn
Bishop
•Hiko |
-Tempiute •Cahente _
1^ 9 '
"
Smt
Independence •
Lone Pine*
Olancha^
0 50 100
n ,«- Scale in Kilometers
3/84
150
BeattvC
US Ecology)
Lathrop Wells
Mesquite
^Ridgecrest
• Barslow
iThermoluminescent Dosimeter Stations
(86)
Figure 14. Locations monitored with TLD's.
39
-------
Results--
Appendix Table E-12 lists the maximum, minimum, and average dose equiva-
lent rate (mrem/day) and the annual adjusted dose equivalent rate (average in
mrem/day times the number of days in the year) measured at each station in the
Network during 1983. No allowance was made for the small additional exposure
due to the neutron component of the cosmic ray spectrum. Six stations exhib-
ited exposure in excess of background. They were the Currant and Groom Lake
stations during the first Quarter, Baker, Mammoth Mt., and Warm Springs during
the second quarter, and the Sherri's Ranch station during the 4th Quarter of
1983. 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 1983. Eighteen dosimeters worn by residents exhibited exposures in
excess of background. These exposures are attributed to 'higher background
levels in the residence than at the background station location or to occupa-
tional exposure (Nos. 49, 52, 57). 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 8 shows that the average annual dose rate for the Dosimetry Network
is consistent with the Network average established in 1975. Annual doses
decreased from 1971 to 1975 with a leveling trend since 1975, except for a high
bias in the 1977 results attributed to mechanical readout problems. The trend
shown by the Network average is indicative of the trend exhibited by individual
stations, although this average is also affected by the mix of stations at
different altitudes (note Figure 15).
Because of the great range in the results, 42 to 140 mrem, an average for
the whole area monitored may be inappropriate for estimating individual exposure,
This would be particularly true if the exposure of a particular resident were
desired. Since environmental radiation exposure can vary markedly with both
altitude and the natural radioactivity in the soil, and since the altitude of
the TLD station location is relatively easy to obtain, the measured dose rates
for 1975 to 1983 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 15, 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 overall averages
listed in Table 8. Thus, if an individual does not live near a monitored loca-
tion, an estimate of exposure could be based on the altitude of his residence
rather than on the average for the whole area monitored.
40
-------
TABLE 8. nOSIMETRY NETWORK SUMMARY FOR THE YEARS 1971 - 1983
Environmental Radiation Dose Rate (mrem/y)
Year Maximum Minimum Average
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
250
200
180
160
140
140
170
150
140
140
142
139
140
102
84
80
62
51
51
60
50
49
51
40
42
42
160
144
123
114
94
94
101
95
9?
90
90
88
87
110-1
Station
Attitude
4 - 6,000 ft.
75 76 77 78 79 80 81 82 83 84
2 - 4,000 ft.
Calendar Year 19--
Figure 15. Average annual TLD exposure as a function of station altitude.
41
-------
Pressurized Ion Chamber Network (PIC)
This network is located at the 15 Community Monitoring Stations identified
on Figure ?. plus stations at Complex I, Furnace Creek, Nyala, Stone Cabin Ranch,
Tikaboo Valley, Twin Springs, 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 gamma exposure rate.
The data for 1983 are displayed in Table 9 as the average yR/hr and annual
mR from each station. When these data are compared to the TLD results for the
same 22 stations, it is found that the PIC response is about 34% higher than
the TLD response. This is attributed, primarily, to the difference in energy
response (plateau) of the two instruments.
TABLE 9. PRESSURIZED ION CHAMBER READINGS - yR/HOUR
STATION LOCATION
EXPOSURE RATE
(MICRO-R/H)*
MEASUREMENT PERIOD MAX. MIN.
ANNUAL
ADJUSTED
EXPOSURE
AVG. (MR/A)
ALAMO, NV
AUSTIN, NV
BEATTY, NV
CEDAR CITY, UT
COMPLEX 1, NV
ELY, NV
FURNACE CREEK, CA
GOLDFIELD, NV
INDIAN SPRINGS, NV
LAS VEGAS (UNLV) NV
LATHROP WELLS, NV
NYALA, NV
OVERTON, NV
PAHRUMP, NV
RACHEL, NV
SALT LAKE CITY, UT
SHOSHONE, CA
ST. GEORGE, UT
STONE CABIN RNCH, NV
TIKABOO VALLEY, NV
TONOPAH, NV
TWIN SPRGS RNCH, NV
83/01/01
83/01/01
83/01/01
83/01/03
83/06/06
83/01/01
83/11/10
83/01/01
83/01/01
83/01/01
83/01/01
83/01/01
83/01/01
83/01/03
83/01/01
83/01/01
83/01/01
83/01/01
83/05/17
83/05/16
83/01/01
83/01/01
83/12/30
83/12/29
83/12/30
83/12/30
83/12/29
83/12/30
83/12/30
83/12/29
83/12/30
83/12/30
83/12/29
83/12/30
83/12/29
83/12/30
83/12/30
83/12/30
83/12/30
83/12/30
83/12/30
83/12/30
83/12/30
83/12/30
20.1
23.5
19.9
18.5
34.5
16.5
12.6
19.6
12.1
14.5
35.4
18.6
34.7
14.8
21.1
19.4
15.0
13.1
23.3
19.7
25.6
21.8
7.7
14.3
6.4
8.0
15.8
10.2
9.5
12.1
6.3
5.7
5.3
10.3
2.4
4.4
14.4
9.4
9.1
6.1
10.2
10.2
15.3
14.0
12.80
18.36
15.85
10.35
18.29
12.09
10.21
14.33
7.97
6.99
12.58
12.43
8.32
7.78
16.67
11.22
11.24
8.63
17.58
15.33
17.23
17.24
112
161
139
91
160
106
89
126
70
61
110
109
73
68
146
98
98
76
154
134
151
151
*The MAX and MIN values are obtained from the instantaneous readings.
42
-------
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.
The whole-body counting facility has been maintained at EMSL-LV since 1966
and is equipped to determine the identity and quantity of gamma-emitting radio-
active materials which may have been inhaled or ingested 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 comparative 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. Some DOE contractor employees are included in this.
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 1983, 17 of these families, 41 individuals, were still active
in the program. The geographical locations of the families which participated
in 1983 are shown in Figure 16.
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 exam-
inations are obtained on each participant at one of the visits. 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.
43
-------
Round Mt.O
Blue Jay O
Tonopah*^
°Nyala Eagle Valley
O Adaven
Salt Lake City j
I
• Cedar City f
I
Beatty^ *»•*.
(Site
Lathrop We~HsCr""V.
\Olndian
Springs
Pahrump^ gQ
• St. George
Arizona
•.Overton
Lake Mead
Shoshone
O Offsite Family
• Community Monitoring Sta. Family
Las
Vegas'
w»wvo
«#
3/84
Figure 16. Location of families in the Human Surveillance Program.
44
-------
In 1982, 15 new families were added to the surveillance program. These
people are in charge of the community monitoring stations described in the fol-
lowing section. In 1983, three long-time residents in the offsite area, with
their families, were added. As with the first group of families, each person
receives a whole-body count, medical history, complete blood count, thyroid
profile, etc.
In addition to these offsite families, counts are performed routinely on
EPA and EG&G employees as part of health monitoring programs. Selected indi-
viduals from the general population of Las Vegas and other cities are also
counted to obtain comparative data.
Results
During 1983, a total of 326 Nal(Tl) and 652 phoswich spectra were obtained
from individuals, of which 154 were from persons participating in the Offsite
Human Surveillance Program. Also, about 1,400 spectra for calibrations 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 collec-
ted in 1983 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 1,340 pCi/L with an average value of 167 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. The
tritium concentration in urines from EPA employees had a mean of 209 pCi/L and
a range of 0 to 2170 pCi/L.
As reported in previous years, medical examination of the offsite families
revealed a generally healthy population. In regard to the hematological examin-
ations 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).
There were three deaths among the offsite families during 1983. One
female member of an offsite family died of multiple pathology (diabetes, kidney,
liver). She also was the oldest person among the families counted and was 83
years old at the time of her death. Another female, 70 years of age, died of
multiple myeloma. One male, age 62, died of coronary problems.
COMMUNITY MONITORING STATIONS
To increase public knowledge about and participation in radiological sur-
veillance activities as conducted by DOE and EPA; the DOE, through an Inter-
agency Agreement with EPA and contracts with the Desert Research Institute
45
-------
(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) 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 9 contains a summary of
the PIC data.
CLAIMS INVESTIGATIONS
One of the public service functions of the EMSL-LV is to investigate
claims of injury allegedly due to radiation originating from NTS activities. A
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 was held at the Environmental Monitoring Systems Labor-
atory, Las Vegas, Nevada, during the fall of 1983. The purpose of the meeting
was to update current information on the biological effects of radiation, its
diagnosis and treatment. During 1983 the MLON made 4 investigations of persons
with alleged radiation claims, responded to 3 inquires and completed 4 evalua-
tions.
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
46
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symptoms described by the owner, a diagnosis of enterotoxemia was made. Radia-
tion exposure apparently played no role in this incident. No such claims were
made in 1983.
PUBLIC INFORMATION PROGRAM
An important function of the Offsite Program has been to create and main-
tain, to the extent possible, public confidence that all reasonable safeguards
are being employed to preserve public health and property from possible hazards
resulting from nuclear testing. Much of this responsibility is carried out
through personal contact with offsite residents by the radiation monitors who
advise the residents of program developments and answer questions about test
activities.
For any test where ground motion may be perceptible offsite, monitors
visit remote locations and active mines beforehand to advise operators of pos-
sible problems. They also stand by on test day to advise of schedule changes.
Mine operators are reimbursed for time lost due to these activities. After the
test, monitors inform all their contacts that the test is over and whether or
not any radiation was detected offsite.
To improve communications, the monitor's have been 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 Panaca and Boulder City, Nevada
and Hurricane, Utah for residents of those areas. In these evening meetings,
the objectives and operation of the Community Monitoring Stations, their role
in the Offiste Radiological Safety and nuclear testing programs, and data
availability were explained. An open period for questions and free discus-
sion was included for each meeting.
Other activities included arranging NTS tours for business and community
leaders from Beatty, Death Valley, Lathrop Wells and Pahrump; for attendees
at the American Water Works Assn. meeting in Las vegas, and for members of
the Medical Liaison Officers Network. A tour of the offsite mining area was
conducted for Blume and Associates. Talks on the Offsite Program were given
to civic and professional organizations in March, May, June, August, October,
and November. A complete Community Monitoring Station was exhibited at the
Lincoln County Fair in Panaca and at the JC State Fair in Las Vegas, both
of which occurred in August.
DOSE ASSESSMENT
Dose assessment calculations for NTS-related radioactivity are not pos-
sible because detectable levels of radioactivity from the 1983 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.
47
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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 (0.8 pCi/L) from previous atmospheric
tests; krypton-85 in air (25 pCi/m3) from power reactors and reprocessing
plants; and plutonium-239 in air (6.0 aCi/m3) from previous atmospheric tests.
Assumptions: 1) Breathing rate = 7,300 m3/a
2) Water intake = 438 L/a, milk
3) 8,766 hr/a
1/2 of water or 219 L/a
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
(jiC1/mL = 10*2 pCi/m3),
2) Sr-90 (ingestion) 45 mrem/uCi intake, whole body, and
3) Pu-239 (inhalation) 48,000 mrem/yCi to lung.
Calculated annual dose:
25 pCi/m3
Kr-R5: 2,200 mrem/hr x 8,766 hr/a x ........... = 4.82 x 10-4 mrem/a
pci/m3
Sr-90: 45 mrem/yCi x 10"6 pCi/pCi x 0.8 pCi/L x 219 L/a = 0.0079 mrem/a
Pu-239: 4.8 x 10* mrem/yCi x 6.0 aCi/m3 x 10"1? yCi/aCi x 7,300 m3/a =
0.002 mrem/a
The highest postulated annual dose estimate to man, from the results of
the 1983 Biomonitoring Program, was calculated to be 0.18 mrem. This would
result from the Cs-137 content of liver from the cattle sample if an individual
ate 0.5 kg per day for the whole year and if the liver tissue had the maximum
measured cesium concentration all year. The highest postulated 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.
The total annual dose to the average adult in Nevada from worldwide radio-
activity detected by EMSL-LV monitoring networks is then 0.19 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 I960), and the calculated internal
dose is only 1.9 percent of this 10 mrem variation.
The external exposures to Nevadans range from 42 to 140 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.
48
-------
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 observa-
tions of Pasquill stability class. Based on the releases shown in Table 1, the
estimated population dose to the 4600 people within 80 km of CP-1 was 5 x 10~5
man-rem. The highest estimated dose was 1.8 x 10~fi mrem/yr to an individual
living in Rachel, with lesser amounts to individuals in Armogosa, Beatty,
Lathrop Wells and Indian Springs, Nevada.
49
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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.
Rernhardt, D. E., A. A. Moghissi and J. A. Cochran, 1973. Atmospheric Concen-
trations 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
ERDA, 1977. "Final Environmental Impact Statement, Nye County, Nevada." ERDA-
1551. U.S. Energy Research and Development Administration, Nevada Opera-
tions 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 Opera-
tions Office, Las Vegas, Nevada.
50
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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 Inter-
comparison 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 Envi-
ronmental 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:
9°Sr and 137Cs Measurements from 1956 to 1977. U.S. Environmental Pro-
tection Agency Report EPA-600/3-81-027 (DOE/DP/00539-040), April 1981.
51
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Smith, D. D. and S. C. Black, 1984. Animal Investigation Program for the Nevada
Test Site 1957-1981, U.S. Environmental Protection Agency, Environmental
Monitoring Systems Laboratory Report EPA 600/6-84-020, Las Vegas, Nev.
Smith, D. D., K. R. Giles and D. E. Bernhardt, 1982. Animal Investigation
Program 1980 Annual Report: Nevada Test Site and Vicinity. U.S. Envir-
onmental 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 Meas-
urements 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. Hydrogeologlc and hydrochemical
framework, south-central Great Basin, Nevada-California, with special
reference to the Nevada Test Site, USGS Professional Paper 712-C, Denver,
CO.
52
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APPENDIX A. SITE DATA
SITE DESCRIPTION
A summary of the uses of the NTS and its immediate environs is included in
Section 3 of this report. More detailed data and descriptive maps are contained
in this Appendix.
Location
The NTS is located in Nye County, Nevada, with its southeast corner about
90 km northwest of Las Vegas (Figure 1 in main report). It has an area of
about 3,500 square km and varies from 40 to 56 km in width (east-west) and from
64 to 88 km in length (north-south). This area consists of large basins or
flats about 900 to 1,200 m above mean sea level (MSL) surrounded by mountain
ranges rising 1,800 to 2,300 m above MSL.
The NTS is surrounded on three sides by exclusion areas, collectively
named the 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 air-
borne radioactivity could pass over public lands.
C1imate
The climate of the NTS and surrounding area is variable, due to its varia-
tions in altitude and its rugged terrain. Generally, the climate is referred
to as continental arid. Throughout the year, there is insufficient water to
support the growth of common food crops without irrigation.
Climate may be classified by the types of vegetation indigenous to an
area. According to Houghton et al. (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) summar-
izes 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 eleva-
tions. During the winter months, the plateaus may be snow-covered for a period
of several days or weeks. Snow is uncommon on the flats. Temperatures vary
considerably with elevation, slope, and local air currents. The average daily
high (low) temperatures at the lower altitudes are around 50F (25F) in January
and 95F (55F) in July, with extremes of 110F and -15F. Corresponding tempera-
tures on the plateaus are 35F (25F) in January and 80F (65F) in July with ex-
tremes of 100F and -20F. Temperature extremes as low as -30F and higher than
115F have been observed.
53
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TABLE A-l. CHARACTERISTICS OF CLIMATIC TYPES IN NEVADA (from Houghton et al. 1975)
01
-p.
Climate Type
Al pi ne
tundra
Humid
continental
Sub humid
continental
Mid-latitude
steppe
Mid-latitude
desert
Low-latitude
desert
Mean Temperature
°C
(8F)
Hi nter Summer
-18° to -9°
( 0° to 15°)
-12° to -1°
(10° to 30°)
-12° to -1°
(10° to 30°)
-7° to 4°
(20° to 40°)
-7° to 4°
(20° to 40°)
-4° to 10°
(40° to 50°)
4° to 10°
(40° to 50°)
10° to 21°
(50° to 70°)
10° to 21°
(50° to 70°)
18' to 27°
(65° to 80°)
18° to 27°
(65° to 80°)
27° to 32°
(80° to 90°)
Annual Precipitation
cm
(inches)
Total* Snowfall
38 to 114
(15 to 45)
64 to 114
(25 to 45)
30 to 64
(12 to 25)
15 to 38
( 6 to 15)
8 to 20
( 3 to 8)
5 to 25
( 2 to 10)
Medium to
heavy
Heavy
Moderate
Light to
moderate
Light
Negligible
Dominant Percent
Vegetation of Area
Alpine
meadows
Pine-fir 1
forest
Pine or scrub 15
woodland
Sagebrush, 57
grass, scrub
Greasewood, 20
shadscale
Creosote 7
bush
*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 agricul-
tural activity is grazing of cattle and sheep. Minor agriculture, primarily
the growing of alfalfa hay, is found in this portion of the State within 300 km
of the NTS Control Point-1 (CP-1). Many of the residents grow or have access
to locally grown fruits and vegetables.
Many recreational areas, in all directions around the NTS (Figure A-2) are
used for such activities as hunting, fishing, and camping. In general, the
camping and fishing sites to the northwest, north, and northeast of the NTS are
utilized throughout the year except for the winter months. Camping and fishing
locations to the southeast, south, and southwest are utilized throughout the
year. The hunting season is from September through January.
55
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Pahute Mesa
Ground Water
System
Ash Meadows
Ground Water System
Nevada
Test
Site
Indian Springs
Scale in Miles
10 20
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.
56
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Q0n°Pa O GRAZING )
I L Q ^•"" GRAZING/
I •— — ^N /[]
«BMSo , _
DAIRIES
A
FARMS v«-.^
Haiwee Res / O\O
FARMS
/O
Moiave Deserl
6 50 100 150
3/81 Scale in Kilometers
A Camping & Recreational
Areas
d Hunting
• Fishing
OMines
A Oil Fields
JA
Lake Havasu
Figure A-2. General land use within 300 km of the Nevada Tost Sits.
57
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Population Distribution
Figure A-3 shows the current population of counties surrounding the NTS
based on 1980 census figures. Excluding Clark County, the major population
center (approximately 462,000 In 1980), the population density within a 150 km
radius of the NTS 1s 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 3,900, 1s 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 800 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 5,000 tourists and campers on any particular day during the major hol-
iday periods in the winter months, and as many as 30,000 during "Death Valley
Days" in the month of November. The largest town and contiguous populated area
(about 40 square miles) in the Mojave Desert is Barstow, located 265 km south-
southwest of the NTS, with a 1983 population of about 36,000. The next largest
populated area is the Ridgecrest-China Lake area, which has a current population
of about 25,000 and 1s 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 1s Bishop, located 225 km west-north-
west of the NTS, with a population of about 5,300 Including contiguous populated
areas.
The extreme southwestern region of Utah is more developed than the adjacent
part of Nevada. The largest community is St. George, located 220 km east of
the NTS, with a population of 11,300. The next largest town, Cedar City, with
a population of 10,900, is located 280 km east northeast of the NTS.
The extreme northwestern region of Arizona is mostly range land except for
that portion 1n the Lake Mead Recreation Area. In addition, several small com-
munities lie along the Colorado River. The largest town in the area is Kingman,
located 280 km southeast of the NTS, with a population of about 9,200. Figures
A-4 through A-7 show the domestic animal populations in the counties near the
NTS.
58
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Storey
1,500
Carson
City
33,600
Douglas
19,500
0 50 100 ISO
3/81 Scale in Kilometers
Figure A-3. Population of Arizona, California, Nevada, and Utah
counties near the Nevada Test site (1980).
59
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0 50 100 150
3/84 Scale in Kilometers
XX - Cows
(XX) - Goats
Figure A-4. Distribution of family milk cows and goats, by county (1983)
60
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0 50 100 150
3/84 Scale in Kilometers
Figure A-5. Distribution of dai^y cows, by county (1983),
61
-------
Storey.
100
Carson
City
1,200
Figure A-6. Distribution of beef cattle, by county, 1983.
62
-------
0 50 100 150
3/84 Scale in Kilometers
Figure A-7. Distribution of sheep, by county, 1983.
63
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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
NiKTl) Gamma
Spectrometry"
IG Ge(U)
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(U)
detector cali-
brated at 0.5 keV/
channel (0.04
to 2 MeV range)
Individual detec-
tor efficiencies
ranging from
15* to 35*.
LoM-level end
window, gas
flow proportional
counter with a
12.7 cm diameter
window (80 ug/or)
Counting
Period
(mln)
10 nln. for
air charcoal
cartridges
Individual
air filters.
30 nln;
air filter
composites.
1200 min.
100 min for
milk, water.
suspended
solids.
30
Analytical
Procedures
Radionucllde
concentra-
tions quan-
tified from
gamma spec-
tral data by
computer
using a least
squares
technique.
Radionucllde
concentration
quantified
from gamma
spectral data
by on-line
computer pro-
gram. Radlo-
nuclldes In atr
filter composite
samples are-
Identified only.
Samples are
counted after
decay of
naturally-
occurlng
ratMonuelides
and, if neces-
sary, extrapo-
lated to mid-
point of col-
lection in
accordance with
t--I.Z decay or
an experiment-
ally-derived
decay.
Sample
Size
120-300 m3
for air
charcoal
cartridge
samples.
120-300 i»3
for air
filters;
3-1/2 liters
for milk
and water.
120-300 m3
Approximate
Detection
Limit*
0.04 pC1/m3.
For routine milk
and water generally,
5 pCI/L for
most common fallout
radionuclides in a
simple spectrum.
Filters for LTHMP
suspended solids.
6 pCI/L. A1r
filters. 0.04 pd/m3.
O.S pCI/sample.
(continued)
64
-------
TABLE B-l. (Continued)
Type of
Analysis
Sr-89-90
H-3
H-3 Enrichment
(Long-Tenn
Hydrologlcal
Samples)
Pu-238.239
Counting
Analytical Period
Equipment (mini
Low-background SO
thin-window.
gas-flow pro-
portional
counter.
Automatic 200
liquid
scintillation
counter with
output printer.
Automatic 200
scintillation
counter with
output printer.
Alpha spectro- 1000-1400
meter with 450
mm, 300 -ym
depletion depth.
silicon surface
barrier detectors
operated In
vacuum chambers.
Analytical
Procedures
Chemical separa-
tion by Ion ex-
change. Separated
sample counted
successively; ac-
tivity calculated
by simultaneous
solution of equa-
tions.
Sample pre-
pared by
distillation.
Sample concen-
trated by
electrolysis
followed by
distillation.
Water sample or
acid-digested
filter or tissue
samples separated
by Ion exchange,
electro-plated on
stainless steel
planchet.
Sample
Size
1.0 liter
for milk
xi r water.
0.1-1 kg
for tissue.
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.
Approximate
Detection
Limit*
Sr-89 • 5 pCl/L
Sr-90 « 2 pCI/L.
400 pCI/L.
10 pCI/L.
Pu-238 • 0.08 pC1/L
Pu-239 • 0.04 pCI/L
for water. For
tissue samples,
0.04 pCI per total
sample for all
Isotopes; 5-10 aCI/m3
for plutonlum on air
filters.
Kr-flS. Xe-133.
Xe-135
Automatic
liquid scintil-
lation counter
with output
printer.
200
Separation by
gas chromatogra-
phy; dlsolved In
toluene "cocktail"
for counting
0.4-1.0 i»3 Kr-85, Xe-133, Xe-135
for air • 4 pCl/m3.
•The detection limit for all samples received after January 1, 1978 Is 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, 0. H. Denham. R. E. Jaqulsh, D. E. Mchels, A. R. 01 sen. D. A. Walte, 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.)
"Gamma Spectrometry performed by thallium activated sodium Iodide (NaKTD), Intrinsic germanium (IG).
or lithium-drifted germanium diode (Ge(LD) detectors.
65
-------
APPENDIX C. QUALITY ASSURANCE PROCEDURES
PRECISION OF ANALYSIS
The duplicate sampling program was initiated for the purpose of routinely
assessing the errors due to sampling, analysis, and counting of samples obtained
from the surveillance networks maintained by the EMSL-LV.
The program consists of the analysis of duplicate or replicate samples
from the ASN, the NGTSN, the LTHMP, and the Dosimetry Network. As the radio-
activity concentration in samples collected from the LTHMP and the MSN are
below detection levels, most duplicate samples for these networks are prepared
from spiked solutions. The NGTSN samples are generally split for analysis.
At least 30 duplicate samples from each network are normally collected and
analyzed over the report period. Since three TLD cards consisting of two TLD
chips each are used at each station of the Dosimetry Network, no additional
samples were necessary. Table C-l summarizes the sampling information for each
surveillance network.
To estimate the precision of a methodology, the standard deviation of
replicate results is needed. Thus, for example, the variance, s^, of each set
TABLE C-l. SAMPLES AND ANALYSES FOR DUPLICATE SAMPLING PROGRAM, 1983
Surveillance
Network
ASN
NGTSN
Dosimetry
MSN
Number of
Sampling
Locations
121
16
86
27
Sets of
Samples Duplicate
Collected Samples
Per Year Collected
4,965 616
824 (NG) 47
829 (H3) 57
344 344
98 25
Number
Per Set
2
2
4-6
2
Sample
Analysis
Gross beta,
Spectrometry
Kr-85, H-3,
H20, HTO
Effective dose
from gamma
K-40, Sr-89,
Sr-90
LTHMP
134
254
34
H-3
66
-------
of replicate TLD results (n=6) was estimated from the results by the standard
expression,
k -2
I (x1 - x) / (k - 1)
1
1=1
where k = number of sets of replicates.
Since duplicate samples were collected for all other sample tvpes, the
variances, s2, for these types were calculated from s2 = (0.886R)2, where R is
the absolute difference between the duplicate sample results. For small sample
sizes, this estimate of the variance 1s statistically efficient* and certainly
more convenient to calculate than the standard expression. The standard devia-
tion is obtained by taking the square root.
The principle that the variances of random samples collected from a normal
population follow a ch1 -square distribution (X2) was then used to estimate the
expected population standard deviation for each type of sample analysis. The
expression used 1s as follows:**
s =
k o k
E (m - l)s<2/ I
1=1
(n - 1)
1=1
1/2
where n^-1 = the degrees of freedom for n samples collected for the ith
replicate sample
2
s^ = the expected variance of the 1th replicate sample
s = the best estimate of sample standard deviation derived from the
variance estimates of all replicate samples (the expected value
of s2 1s a2).
For expressing the precision of measurement 1n common units, the coefficient
of variation (s/x) was calculated for each sample type. These are displayed in
Table C-2 for those analyses for which there were adequate data.
To estimate the precision of counting, approximately 10 percent of all
samples are counted a second time. These are unknown to the analyst. Since
all such replicate counting gave results within the counting error, the preci-
sion data in Table C-2 represents errors principally 1n 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.
67
-------
TABLE C-2. SAMPLING AND ANALYTICAL PRECISION, 1983
Surveillance
Network
ASN
NGTSN
Analysis
Gross p
Be-7 (1982)
Kr-85
HTO
H?0
Sets of
Replicate
Samples
Evaluated
18
9
18
*
48
Coefficient
of Variation
(*)
20
37
14
24
23
Dosimetry
SMSN
LTHMP
(TLD)
K-40
Sr-89
Sr-90
H-3 (conv. 1983)
H-3 (enrich. 1983)
337
33
20
25
52
23
3.9
10
12
6
8
18
*Estimate of precision was calculated from the errors in the H-3 conventional
analysis and the measurement of atmospheric moisture
ACCURACY OF ANALYSIS
Data from the analysis of intercomparison samples are statistically anal-
yzed and compared to known values and values obtained from other participating
laboratories. A summary of the statistical analysis is given in Table C-3,
which compares the mean of three replicate analyses with the known value. The
normalized deviation is a measure of the accuracy of the analysis when compared
to the known concentration. The determination of this parameter is explained
in detail separately (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 statis-
tical variation. However, if the parameters exceed these limits, one must
suspect that there is some cause other than normal statistical variations that
contributed to the difference between the measured values and the known value.
As shown by this table, all analyses were within the control limit.
68
-------
TABLE C-3. 1983 QUALITY ASSURANCE INTERCOMPARISON RESULTS
Mean of
Replicate Known Normalized
Analyses Value Deviation from:
Analysis Month (pCi/L) (pCi/L) Known Cone.
H-3 in
water
H-3 in
urine
Cr-51 in
water
Co- 60 in
water
Zn-65 in
water
Ru-106 in
water
1-131 in
water
Cs-134 in
water
Cs-137 in
water
Sr-R9 in
milk
Feb
Apr
Jun
Aug
Oct
Dec
Mar
Jun
Nov
Feb
Jun
. Oct
Feb
Jun
Oct
Feb
Jun
Oct
Feb
Jun
Oct
Apr
Aug
Feb
Jun
Oct
Feb
Jun
Oct
Feb
Jun
Oct
2479
3274
1391
1713
1135
2187
1977
1508
820
50
<60
46
22
13
18
20
34
43
41
<75
45
23.7
14
18
40
15
18
25
22
40.0
27
21
2560
3330
1529
1836
1210
2389
2470
1589
1008
45
60
51
22
13
19
21
36
40
48
40
52
26.8
14
20
47
15
19
26
22
37.4
25
15
-0.4
-0.3
-0.7
-0.6
-0.4
-1.0
-2.4
-0.4
-1.0
1.6
-
-1.8
0.1
0.0
-0.5
-0.2
-0.7
1.2
-2.4
-
-2.5
-0.9
0.3
-0.8
-2.4
-0.1
-0.3
-0.2
0.1
0.9
0.8
2.2
(continued)
69
-------
TABLE C-3. (Continued)
Analysis
Sr-90 in
milk
1-131 in
milk
Cs-137 in
milk
Cs-137 in
air filters
(pCi/filter)
Month
Feb
Jim
Oct
Feb
Jun
Oct
Feb
Jun
Oct
Mar
Aug
Mean of
Replicate
Analyses
(pCI/L)
19.0
16
18
53.3
26
36
24.3
45
33
34
18
Known
Value
(pCi/L)
17.8
16
14
54.5
30
40
25.6
47
33
27
15
Normalized
Deviation from:
Known Cone.
1.4
-0.3
4.2
-0.3
-1.1
-1.2
-0.4
-0.6
-0.1
2.4
0.9
===================
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 average bias for Sr-90 was -28% and for Pu-239 was 0.7%.
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 submitted to the international intercomparison of environmental
dosimeters. Dosimeters were submitted to the Sixth International Intercompar-
ison in July 1981 (Table C-5). All TLD measurements are performed in conform-
ance with standards proposed by the American National Standards Institute (ANSI
1975).
70
-------
TABLE C-4. QUALITY ASSURANCE RESULTS FOR THE BIOENVIRONMENTAL PROGRAM
Sample Type
and
Shipment
Number
Nuclide
Activity Added
(pCi/kg*) Liver
(pCi/g ash) Bone
Activity Reported
(pCi/kg*) Liver
(pCi/g ash) Bone
% Bias+
Bone Ash
Ash 1
45
Ash 2
45
Ash 3
45
Ash 4
45
Ash 1
51
Ash 2
51
ASL 3
51
ASL 4
51
Liver 1
51
Liver 2
51
Liver 3
51
Liver 4
239PU
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
239Pu
239Pu
239Pu
0
0
0
0
0.16
14.8
0.13
27.4
0
0
5.15
9.96
6.24
12.1
5.43
10.51
0
4.64
4.71
5.04
0.00
1.5
-0.001
1.7
0.16
9.22
0.17
14.1
0.00052**
1.71
5.16
9.85
5.96
11.8
5.40
11.0
0.11**
4.18
4.34
4.92
_
_
_
0
-42
31
-49
_
_
0.2
-4.5
-4.5
-16
-0.6
-12
-
_
-12
-10
-4.6
Duplicate Samples
Bov-2-Li
51
Rov-2-Li
51
ver 239Pu
ver ?39Pu
0
0
0.71*-0.75**
0.44*-0.12
* Wet weight
+ Bias (B) = Recovery -1; where recovery is
u
and xi = net activity reported
u = activity added
Precision (Cv) = 2 — ...... x — rr- where
xl + X2 1-128
**Counting error exceeds reported activity
xj = first value
x _ secon(j value
71
-------
TABLE C-5. SUMMARY RESULTS OF THE SIXTH INTERNATIONAL
INTERCOMPARISON OF ENVIRONMENTAL DOSIMETERS
Quantity
Mean
Standard
Deviation
Comments
Summary of Laboratory Results (mR):
EMSL-LV Dosimeters 146 11
All Dosimeters 149 21
Calculated Exposure 158 8
Summary of Field (Pre-irradiated) Results (mR)
EMSL-LV Dosimeters 191 14
All Dosimeters 191 30
Calculated Exposure 202 10
Summary of Field Results (mR):
EMSL-LV Dosimeters 43.1
All Dosimeters 45.0
Calculated Exposure 43.5
3.2
16.4
2.2
EMSL-LV results 2% lower
than all dosimeters and
8% lower than the
calculated exposure.
EMSL-LV results 0% lower
than all dosimeters and 5%
lower than the calculated
exposure.
EMSL-LV results 4.2% lower
than all dosimeters and
0.9% lower than the
calculated exposure.
72
-------
APPENDIX D. RADIATION PROTECTION STANDARDS FOR
EXTERNAL AND INTERNAL EXPOSURE
DOE ANNUAL DOSE COMMITMENT
The annual dose commitment tabulated below 1s from "Basic Radiation
Protection Criteria" 1n 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
pC1/L for tritium. This concentration would result in 4 mrem/a to an
individual from continuous exposure.
73
-------
TABLE D-l. DOE CONCENTRATION GUIDES
Network or Program
Sampling
Medium
Network
a1r
Noble Gas and Tritium
Surveillance Network
air
Long-Term
Hydrologlcal Program
water
M1lk Surveillance
Networks
milk
Radio-
nuclide
Be_7
Zr-95
Nb-95
Mo-99
Ru-103
M31
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
Concentration based on chemical toxldty.
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 IQl
2.0 x 10-2
1.0 x 105
6.7 x 10*
1.0 x 105
3.3 x 10*
(pC1/L)
1.0 x 106
1.0 x 103
1.0 x 102
6.7 x 103
1.0 x 10l
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 10-2
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 10-2
1.2 x 10-2
3.1 x 10-3
2.4 x 10-3
6.0 x 10-2
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 10-3
5.0 x 10-1
2.0 x 10-0
1.5 x 10-1
4.7 x 10-3
2.4 x 10-3
1.0 x lO-3
1.5 x 10-1
5.0 x 10-1
2.0 x 10-0
==============
74
-------
APPENDIX E. DATA SUMMARY FOR THE MONITORING NETWORKS
TABLE E-l. 1983 SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
CONTINUOUSLY OPERATING STATIONS
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
DEATH VALLEY JCT CALIF
FURNACE CREEK CALIF
SHOSHONE CALIF
ALAMO NEV
AUSTIN NEV
BEATTY NEV
STONE CABIN RANCH NEV
CURRANT NEV - BLUE EAGLE RANCH
ELY NEV
GOLDFIELD NEV
NTS NEV - AREA 51
HIKO NEV
INDIAN SPRINGS NEV
LAS VEGAS NEV
LATHROP WELLS NEV
UU 1 C.^ 1 C.U
/SAMPLED
23.0/364.0
21.8/360.4
9.5/350.4
15.6/352.1
6.0/314.8
16.9/355.3
5.9/357.0
15.5/331.1
3.0/350.0
11.2/355.8
8.2/354.2
14.0/354.0
15.9/359.8
22.9/363.3
14.0/366.6
rvnu lu—
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
MAX
0.51
0.62
0.66
0.69
0.52
0.58
0.50
0.76
0.22
0.67
0.52
0.60
0.55
0.64
0.48
MIN
0.29
0.25
0.28
0.36
0.23
0.30
0.38
0.43
0.22
0.50
0.15
0.28
0.27
0.23
0.36
AVG*
0.025
0.022
0.012
0.021
0.0072
0.018
0.0072
0.026
0.0019
0.019
0.0054
0.017
0.019
0.026
0.016
CONTINUED
75
-------
TABLE E-l. CONTINUED
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
OVERTON NEV
PAHRUMP NEV
SCOTTY'S JCT NEV
SUNNYSIDE NEV
RACHEL NEV - ROBINSON TRAILER
TONOPAH NEV
TTR NEV
FALLINI'S (TWIN SPGS) RANCH NE
CEDAR CITY UTAH
DELTA UTAH
MILFORD UTAH
ST GEORGE UTAH
SALT LAKE CITY UTAH
L/L. 1 L.U 1 L.U
/SAMPLED
18. 6/354. 3
11.9/361.1
5.0/355.7
4.9/347.9
23.7/361.4
5.9/357.7
68.2/360.3
17.3/359.3
18.8/361.6
13.7/258.6
68.6/355.7
7.0/372.4
39.6/366.0
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
MAX
0.79
0.66
0.71
0.59
0.83
0.51
0.41
0.59
0.53
0.62
0.41
0.78
0.47
MIN
0.32
0.37
0.36
0.46
0.30
0.45
0.10
0.32
0.31
0.32
0.088
0.33
0.16
AVG*
0.023
0.016
0.0070
0.0075
0.028
0.0079
0.044
0.023
0.021
0.022
0.039
0.0094
0.033
*TIME-WEIGHTED AVERAGE INCLUDES ALL DAYS OF
THE FOLLOWING STATIONS HAD NEGLIGIBLE GAMMA-SPECTRA:
ALAMO NEV - SHERRI'S RANCH
NYALA NEV
NON-DETECTABLE ACTIVITY.
76
-------
TABLE E-2. 1983 SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
STANDBY STATIONS - OPERATED 1 OR 2 WEEKS PER QUARTER
===============================================================================
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
KINGMAN ARIZ
PHOENIX ARIZ
SELIGMAN ARIZ
TUCSON ARIZ
WINSLOW ARIZ
BAKER CALIF
BARSTOW CALIF
BISHOP CALIF
CHICO CALIF
INDIO CALIF
LONE PINE CALIF
NEEDLES CALIF
RIDGECREST CALIF
CORTEZ COLO
DENVER COLO
DURANGO COLO
GRAND JUNCTION COLO
PUEBLO COLO
BOISE IDA
IDAHO FALLS IDA
/SAMPLED
6.1/23.2
3.0/11.0
3.0/14.0
4.0/20.0
8.0/27.0
10.1/24.6
5.9/27.9
3.2/15.5
6.0/14.1
3.0/26.8
2.0/20.0
6.0/28.0
3.0/21.7
2.8/12.6
5.1/26.2
6.4/14.0
3.1/25.8
8.0/13.9
6.0/14.0
6.0/13.8
i\«uiu-
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
MAX
0.43
0.27
0.21
0.33
0.23
0.27
0.26
0.56
0.28
0.21
0.25
0.19
0.41
0.63
0.55
0.34
0.26
0.39
0.21
0.23
MIN
0.33
0.27
0.21
0.33
0.19
0.24
0.20
0.56
0.17
0.21
0.25
0.18
0.41
0.63
0.24
0.27
0.26
0.22
0.15
0.22
AVG
0.10
0.073
0.046
0.067
0.061
0.11
0.049
0.12
0.095
0.023
0.025
0.039
0.056
0.14
0.072
0.14
0.031
0.16
0.075
0.098
CONTINUED
77
-------
TABLE E-2. CONTINUED
SAMPLING LOCATION
MOUNTAIN HOME IDA
NAMPA IDA
POCATELLO IDA
TWIN FALLS IDA
IOWA CITY IOWA
SIOUX CITY IOWA
DODGE CITY KAN
MONROE LA
NEW ORLEANS LA
MINNEAPOLIS MINN
CLAYTON MO
ST JOSEPH MO
BILLINGS MONT
BOZEMAN MONT
MISSOULA MONT
BATTLE MOUNTAIN NEV
BLUE JAY NEV
CALIENTE NEV
CURRANT NEV - ANGLE WORM RANCH
CURRIE NEV
NO. DAYS
DETECTED
/SAMPLED
10.0/28.0
3.0/14.2
6.0/27.8
5.0/14.0
3.0/27.0
3.0/7.0
3.0/28.0
2.1/27.2
1.9/13.7
2.0/26.1
8.0/28.0
5.0/35.7
3.0/13.9
2.9/9.1
3.0/12.5
1.9/21.9
7.0/23.7
4.0/26.8
2.9/29.3
4.8/12.6
RADIO-
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
RADIOACTIVITY
(PCI/M3)
MAX
0.31
0.32
0.34
0.38
0.21
0.17
0.20
0.22
0.19
0.19
0.22
0.23
0.30
0.22
0.17
0.61
0.39
0.54
0.47
0.62
MIN
0.14
0.32
0.26
0.29
0.21
0.17
0.20
0.22
0.19
0.19
0.16
0.13
0.30
0.22
0.17
0.61
0.32
0.33
0.47
0.62
CONC.
AVG
0.078
0.067
0.066
0.12
0.023
0.074
0.021
0.016
0.026
0.014
0.056
0.024
0.064
0.069
0.041
0.053
0.10
0.064
0.047
0.24
CONTINUED
78
-------
TABLE E-2. CONTINUED
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
DUCKWATER NEV
ELKO NEV
EUREKA NEV
FALLON NEV
FRENCHMAN STATION NEV
LOVELOCK NEV
LUND NEV
MESQUITE NEV
PIOCHE NEV
RENO NEV
WARM SPRINGS NEV
WELLS NEV
CARLSBAD N M
NORMAN OKLA
DUGWAY UTAH
GARRISON UTAH
CASPER WYO
L/U. 1 UVs 1 UU
/SAMPLED
11.0/64.1
14.7/31.4
4.8/20.7
8.0/22.8
2.9/25.6
5.9/29.4
6.9/26.1
13.0/22.0
6.6/20.3
5.0/25.5
5.0/20.6
5.0/27.1
5.0/22.1
3.0/14.0
3.0/7.0
4.1/16.1
5.0/14.0
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
MAX
0.69
0.30
0.41
0.40
0.24
0.21
0.47
0.37
0.45
0.78
0.83
0.40
0.36
0.15
0.13
0.32
0.42
MIN
0.19
0.18
0.28
0.22
0.24
0.17
0.41
0.17
0.32
0.32
0.22
0.32
0.15
0.15
0.13
0.32
0.28
AVG
0.062
0.094
0.078
0.11
0.028
0.039
0.12
0.17
0.12
0.12
0.14
0.064
0.053
0.032
0.055
0.080
0.12
THE FOLLOWING STATIONS HAD NEGLIGIBLE GAMMA-SPECTRA:
GLOBE ARIZ
YUMA ARIZ
79
CONTINUED
-------
TABLE E-2. CONTINUED
THE FOLLOWING STATIONS
LITTLE ROCK ARK
SANTA ROSA CALIF
PRESTON IDA
FORT DODGE IOWA
LAKE CHARLES LA
JOPLIN MO
GREAT FALLS MONT
KALISPELL MONT
MILES CITY MONT
NORTH PLATTE NEB
GEYSER RANCH NEV
ROUND MOUNTAIN NEV
WINNEMUCCA NEV
ALBUQUERQUE N M
SHIPROCK NM
BISMARK ND
FARGO ND
WILLISTON ND
MUSKOGEE OKLA
MEDFORD ORE
BURNS ORE
HAD NEGLIGIBLE GAMMA-SPECTRA:
ABERDEEN S D
RAPID CITY S D
ABILENE TEX
AMARILLO TEX
AUSTIN TEX
FORT WORTH TEX
MIDLAND TEX
TYLER TEX
BRYCE CANYON UTAH
CAPITOL REEF NAT'L MONUMENT UTAH
ENTERPRISE UTAH
LOGAN UTAH
MONTICELLO UTAH
PAROWAN UTAH
PROVO UTAH
VERNAL UTAH
WENDOVER UTAH
SEATTLE WASH
SPOKANE WASH
ROCK SPRINGS WYO
WORLAND WYO
80
-------
TABLE E-3. 1983 SUMMARY OF ANALYTICAL RESULTS FOR THE
NOBLE GAS AND TRITIUM SURVEILLANCE NETWORK
SAMPLING
LOCATION
SHOSHONE,
CALIF.
ALAMO ,
NEV.
AUSTIN,
NEV.
BEATTY,
NEV.
ELY,
NEV.
GOLDFIF.LD,
NEV.
INDIAN SPRINGS,
NEV.
LAS VEGAS,
NEV.
NUMBER
SAMPLES
POSITIVE/
NEGATIVE
42/10
41/11
50/1
50/1
41/11
39/13
52/0
52/0
49/3
45/7
52/0
52/0
46/6
45/7
52/0
52/0
48/4
45/7
52/0
52/0
50/2
50/2
52/0
52/0
44/8
44/8
52/0
52/0
46/6
44/8
51/1
51/1
RADIOACTIVITY CONC.
(PCI/M3)* PERCENT
rnwr
RADIONUCLIDE
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
MAX
31
47
0.55
4.8
33
18
0.44
3.8
30
24
0.49
2.9
30
23
0.33
2.2
31
24
0.44
3.1
30
11
0.35
2.3
31
8.8
0.50
3.7
31
30
0.50
5.0
MIN
19
-6.9
-0.46
-2.5
19
-9.1
-0.26
-2.2
19
-12
-0.22
-1.1
20
-12
-0.20
-1.3
19
-2.9
-0.37
-2.7
20
-8.2
-0.27
-1.1
19
-25
-0.27
-4.4
20
-28
-0.34
-2.3
AVG GUIDE±
25 0.03
2.8 <0.01
0.065 -
0.43 <0.01
25 0.02
1.7 <0.01
0.056 -
0.47 <0.01
25 0.03
2.1 <0.01
0.097 -
0.55 <0.01
24 0.02
2.9 <0.01
0.086 -
0.48 <0.01
25 0.02
3.8 <0.01
0.081
0.46 <0.01
24 0.02
1.0 <0.01
0.053 -
0.33 <0.01
25 0.02
1.2 <0.01
0.057 -
0.34 <0.01
24 0.02
1.3 <0.01
0.079 -
0.58 <0.01
(CONTINUED)
81
-------
TABLE E-3. CONTINUED
SAMPLING
LOCATION
LATHROP WELLS,
NEV.
OVERTON,
NEV.
PAHRUMP ,
NEV.
RACHEL,
NEV.
TONOPAH,
NEV.
CEDAR CITY,
UTAH
ST GEORGE,
UTAH
SALT LAKE CITY,
UTAH
NUMBER
SAMPLES
POSITIVE/
NEGATIVE
50/2
49/3
52/0
52/0
48/4
47/5
51/1
51/1
42/10
39/13
52/0
52/0
45/6
44/7
52/0
52/0
44/7
42/9
52/0
52/0
46/6
42/10
52/0
52/0
47/5
44/8
49/2
49/2
31/15
29/17
47/4
47/4
RADIONUCLIDE
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
RADIOACTIVITY CONC.
(PCI/M3)* 1
MAX
32
26
0.42
2.8
30
35
0.48
4.7
30
7.6
0.51
3.5
31
16
0.48
4.4
32
54
0.39
2.5
28
16
0.53
2.8
32
11
0.40
3.6
34
32
0.52
4.4
MIN
19
-9.9
-0.22
-2.1
19
-11
-0.18
-1.7
18
-9.2
-0.30
-3.5
20
-56
-0.20
-1.1
21
-13
-0.34
-2.2
18
-6.7
-0.25
-1.2
19
-11
-0.31
-2.5
18
-6.3
-0.25
-1.8
AVG
26
4.8
0.10
0.54
25
5.3
0.060
0.44
24
1.9
0.048
0.25
24
0.74
0.13
0.71
25
3.4
0.083
0.47
24
2.3
0.074
0.46
25
0.61
0.087
0.62
25
2.6
0.12
0.75
PERCENT
CONC.
GUIDE*
0.03
<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
0.02
<0.01
-
<0.01
0.03
<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 POPUL-
ATION IN AN UNCONTROLLED AREA.
82
-------
TABLE E-4. 1983 SUMMARY OF GROSS BETA ANALYSES FOR AIR SURVEILLANCE NETWORK
SAMPLING LOCATION
SHOSHONE CALIF
LAS VEGAS NEV
DELTA UTAH
MILFORD UTAH
ST GEORGE UTAH
NO.
SAMPLED
350.4
360.2
255.8
355.7
372.4
RADIOACTIVITY CONC.
(PCI/M3)
MAX
0.083
0.082
0.027
0.029
0.039
MIN
-0.027
-0.016
-0.0080
-0.011
-0.0058
AVG
0.0064
0.010
0.0076
0.0082
0.0082
83
-------
TABLE E-5. PLUTONIUM CONCENTRATION IN COMPOSITED AIR SAMPLES - 1983
Station Location
(WINSLOW and PHOENIX)
AZ
(BARSTOW and BISHOP)
CA
(DURANGO and PUEBLO)
CO
(BOISE and MOUNTAIN HOME)
ID
(IOWA CITY and SIOUX CITY)
IA
(MNROE and NEW ORLEANS)
LA
(JOPLIN and ST. JOSEPH)
MO
(BOZEMAN and MISSOLULA)
MT
LAS VEGAS, NV
LATHROP WELLS, NV
RACHEL, NV
(ALBUQUERQUE and CARLSBAD)
NM
(MUSKOGEE and NORMAN)
OK
(BURNS and MEDFORD)
OR
Month
Collected
Feb
May
Feb
May
Feb
May
Feb
May
Feb
May
Feb
May
Feb
May
Feb
May
Jan thru Jim
Jan thru Jun
Jan thru Jun
Feb
May
Jan
Feb
May
Jan
Mar
Jun
Pu-238*
aCi/m3
5.3
0
0.9
NA
0
0
2.6
0
34
0
4.6
2.1
0.9
0
0
0
3.3 ± 3.2**
4.2 ± 4.1**
1.4 ± 3.4**
3.0
3.8
0
4.5
0
2.6
0
4.9
Pu-239*
aCi/m3
9.9
0
5.5
NA
1.2
5.1
1.6
4.7
7.3
1.1
2.2
1.6
2.7
13.6*
2.7
4.0
4.8 ± 2.8**
7.8 ± 4.6**
5.4 ± 4.3**
4.5
6.4
2.3
2.0
2.9
2.2
0.9
7.3
Pet. CG
<0.08
-
0.04
-
<0.01
<0.04
<0.02
<0.03
<0.2
<0.01
<0.04
<0.03
<0.03
0.07
<0.02
0.02
0.04
0.06
<0.04
<0.04
0.05
<0.02
<0.04
<0.02
<0.03
<0.01
0.06
*A11 results less than MDC except the May composite from Missouri. A negative
result is indicated by 0.
**Average and std. deviation of the six monthly composites. All less than MDC.
CONTINUED
84
-------
TABLE E-5. CONTINUED
—========================
Station Location
(ABERDEEN and RAPID CITY)
SD
(AUSTIN and FT. WORTH)
TX
(PROVO and VERNAL)
UT
(SEATTLE and SPOKANE)
WA
(CASPER and WORLAND)
WY
Month
Collected
Mar
Jun
Mar
Jun
Mar
Jun
Mar
Jun
Feb
May
Pu-238*
aCi/m3
0.6
NA
0
NA
3.6
NA
0
0
3.0
0
Pu-239*
aCi/m3
2.6
NA
2.4
NA
1.4
NA
0
2.3
0.8
NA
Pet. CG
<0.02
<0.02
<0.03
<0.02
<0.03
*A11 results less than MDC except the May composite from Missouri. A negative
result is indicated by 0.
85
-------
TABLE E-6. 1983 SUMMARY OF TRITIUM RESULTS FOR THE NTS
MONTHLY LONG-TERM HYDROLOGICAL MONITORING PROGRAM
SAMPLING
LOCATION
WELL 8
WELL J-12
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
11
1
11
11
11
11
11
11
11
11
10
11
1
TRITIUM CONCENTRATION
(PCI/L)
MAX
9.4
-3.0
23
120
6.4
88
9.7
180
49
4.7
8.8
10
_
MIN
-4.7
-3.0
-2.4
-2.0
-6.0
-4.2
-1.5
110
-19
-9.4
-10
-3.2
_
AVG
1.5
-3.0
5.4
36
-0.42
9.8
2.6
150
6.0
-0.66
0.40
1.8
1500
PERCENT
CONC.
GUIDE
<0.01
<0.01
0.03
0.20
<0.01
0.05
0.02
0.75
0.03
<0.01
<0.01
<0.01
7.5
86
-------
TABLE E-7. TRITIUM RESULTS FOR THE LONG-TERM HYDROLOGICAL MONITORING PROGRAM
NTS SEMI-ANNUAL PROJECT FOR 1983
SAMPLING LOCATION
BOULDER CITY NEV
LAKE MEAD INTAKE
ASH MEADOWS NEV
CRYSTAL POOL
WELL 18S-51E-7DB
WELL 17S-50E-14CAC
FAIRBANKS SPRINGS
BEATTY NEV
NECO WELL
COFFERS WELL 11S/48/1DD
CITY SUPPLY 12S-47E-7DB
INDIAN SPRINGS NEV
USAF WELL 2
SEWER CO INC WELL 1
COLLECTION
DATE
1983
01/17
07/15
01/11
07/07
01/11
07/07
01/11
07/07
01/11
07/07
01/12
07/06
01/12
07/12
01/12
07/12
01/11
07/06
01/11
07/06
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
220 ± 7
190 ± 7
3.2 i 5.6*
1.6 ± 5.2*
0.73 ± 5.3*
3.5 ± 5.3*
-2.1 ± 5.6*
3.5 ± 5.0*
2.5 ± 5.3*
3.9 ± 5.0*
2.0 ± 5.3*
6.3 ± 5.0*
7.1 ± 6.0*
3.4 ± 4.9*
12 ± 5
10 ± 5
9.8 ± 5.0
7.5 ± 4.3
19 ± 5
3.3 ± 5.2*
PCT OF
CONC.
GUIDE
1
0.9
0.02
<0.01
<0.01
0.02
<0.01
0.02
0.01
0.02
0.01
0.03
0.04
0.02
0.06
0.05
0.05
0.04
0.09
0.02
CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
87
-------
TABLE E-7. CONTINUED
SAMPLING LOCATION
LATHROP WELLS NEV
CITY 15S-50E-18CDC
NTS NEV
WELL UE18R
WELL UE15D
TEST WELL D
WELL UE1C
WELL C-l
WELL UE5C
WELL 5B
TEST WELL F
WELL U16D
OASIS VALLEY NEV
GOSS SPRINGS
COLLECTION
DATE
1983
01/12
07/06
01/14
01/13
07/08
01/13
07/13
01/13
07/13
01/19
07/08
01/18
07/13
01/18
07/13
01/14
01/19
07/08
01/12
07/12
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
1.0 ± 5.9*
2.8 ± 5.1*
NO SAMPLE COLLECTED
NO SAMPLE COLLECTED
42 ± 5
73 ± 5
5.2 ± 5.3*
8.2 ± 5.0
3.1 ± 5.0*
140 ± 6
14 ± 5
9.8 ± 5.7
4.2 ± 5.0*
11 ± 5
5.1 ± 5.7*
NO SAMPLE COLLECTED
1.8 ± 5.4*
0.24 ± 5.1*
8.1 ± 4.8
4.0 ± 5.2*
PCT OF
CONC.
GUIDE
<0.01
0.01
0.2
0.4
0.03
0.04
0.02
0.7
0.07
0.05
0.02
0.05
0.03
<0.01
<0.01
0.04
0.02
CONCENTRATION IS LESS THAN
THE MINIMUM DETECTABLE CONCENTRATION
(MDC).
88
-------
TABLE E-8. TRITIUM RESULTS FOR THE LONG-TERM HYDROLOGICAL MONITORING PROGRAM
NTS ANNUAL PROJECT FOR 1983
SAMPLING LOCATION
SHOSHONE CA
SHOSHONE SPRING
ADAVEN NEV
ADAVEN SPRING
ALAMO NEV
CITY WELL 4
CLARK STATION NEV
TTR WELL 6
HIKO NEV
CRYSTAL SPRINGS
LAS VEGAS NEV
WATER DISTRICT WELL 28
NYALA NEV
SHARP'S RANCH
PAHRUMP NEV
CALVADA WELL 3
TEMPIUTE NEV
UNION CARBIDE WELL
TONOPAH NEV
CITY WELL
WARM SPRINGS NEV
COLLECTION
DATE
1983
08/16
08/01
08/09
08/02
08/09
08/17
08/01
08/16
08/10
08/02
08/03
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
1.1 ± 5.5*
650 ± 150
-0.82 ± 5.3*
1.2 ± 5.0*
71 ± 5
-3.4 ± 5.7*
2.2 ± 5.6*
0.80 ± 5.4*
0.21 ± 5.0*
-3.4 ± 5.4*
1.8 ± 5.5*
PCT OF
CONC.
GUIDE
<0.01
3
<0.01
<0.01
0.4
<0.01
0.01
<0.01
<0.01
<0.01
<0.01
TWIN SPRINGS RCH
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
89
-------
Surface Ground Zero
Sampling Locations
gs^^=Pacmcocean
Figure E-l Amchitka Island and hackground sampling locations for the LTHMP.
90
-------
:5=sg^5^jDermg oeagg^^g^gjr^^^g^^^^^gf
Surf ace Ground Zero
Sampling Locations
Figure E-2. LTHMP sampling locations for Project Cannikin.
91
-------
TABLE E-9. TRITIUM RESULTS FOR THE LONG-TERM HYDROLOGICAL MONITORING PROGRAM
(1983 Annual Samples)
COLLECTION
DATE
SAMPLING LOCATION 1983
BACKGROUND SAMPLES - AMCHITKA
DUCK COVE CREEK
CONSTANTINE SPRING
JONES LAKE
RAIN SAMPLE
ARMY WELL 1
ARMY WELL 2
ARMY WELL 3
ARMY WELL 4
SITE E HYDRO EXPLOR HOL
SITE D HYDRO EXPLOR HOL
PROJECT CANNIKIN - AMCHITKA,
SOUTH END CANNIKIN LAKE
NORTH END CANNIKIN LAKE
WELL HTH-3
ICE BOX LAKE
WHITE ALICE CREEK
PIT S OF CANNIKIN GZ
DK-45 LAKE
, AK
08/08
08/09
08/08
08/16
08/09
08/09
08/09
08/09
08/09
08/09
AK
08/08
08/08
08/08
08/08
08/08
08/08
08/10
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
46 ± 5
91 ± 6
39 ± 5
55 ± 6
71 ± 6
26 ± 6
74 ± 5
77 ± 6
170 ± 6
88 ± 5
51 ± 6
30 ± 5
51 ± 6
44 ± 5
48 ± 5
34 ± 5
61 ± 6
PCT OF
CONC.
GUIDE
0.2
0.5
0.2
0.3
0.4
0.1
0.4
0.4
0.8
0.4
0.3
0.2
0.3
0.2
0.2
0.2
0.3
CONTINUED
92
-------
Collapse
Boundary,
^Surface 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.
93
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
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
LONG SHOT POND
LONG SHOT POND
PROJECT MILROW -
HEART LAKE
WELL W-2
WELL W-3
WELL W-4
WELL W-5
WELL W-6
WELL W-7
WELL W-8
======================5
COLLECTION
DATE
1983
- AMCHITKA, AK
08/08
08/08
08/08
08/08
08/08
08/08
08/08
08/08
08/08
1 08/08
2 08/08
3 08/08
AMCHITKA, AK
08/08
08/08
08/08
08/08
08/08
08/08
08/08
08/08
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
290 ± 8
820 ± 150
76 ± 6
3800 ± 180
270 ± 8
59 ± 6
600 ± 140
590 ± 140
740 ± 150
51 ± 6
57 ± 6
51 ± 5
31 ± 5
41 ± 5
33 ±5
NO SAMPLE COLLECTED
38 ± 5
42 ± 5
44 ± 5
40 ± 5
PCT OF
CONC.
GUIDE
1
4
0.4
20
1
0.3
3
3
4
0.3
0.3
0.3
0.2
0.2
0.2
0.2
0.2
0.2
0.2
CONTINUED
94
-------
SAMPLING LOCATION
TABLE E-9. CONTINUED
COLLECTION CONC. ± 2 SIGMA PCT OF
DATE TRITIUM CONC.
1983 (PCI/L) GUIDE
PROJECT MILROW - AMCHITKA. AK (Cont.)
WELL W-10
WELL W-ll
WELL W-13
WELL W-15
WELL W-16
WELL W-18
WELL W-19
CLEVENGER CREEK
08/08
08/08
08/08
08/08
08/08
08/08
08/08
08/10
47 ± 5 0.2
98 ± 6 0.5
58 ± 5 0.3
37 ± 5 0.2
49 ± 5 0.2
60 ± 6 0.3
NO SAMPLE COLLECTED
51 ± 5 0.3
* CONCENTRATION IS LESS THAN MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
95
-------
Johnson
Artesian
Fawn Cr. 500' Downstream
RB-D-01
SGZ
Fawn Cr. 500' Upstream
Rio Blanco County
Garfield County
Surface Ground Zero Q Water Well
Artesian Well A Spring
Windmill | Stream
Location Maps
Figure E-4. LTHMP sampling locations for Project Rio Blanco.
96
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
PROJECT RIO BLANCO - RIO
FAWN CREEK
6800 FT UPSTREAM
FAWN CREEK
500 FT UPSTREAM
FAWN CREEK
500FT DOWNSTREAM
FAWN CREEK
8400 FT DOWNSTREAM
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
1983
BLANCO, CO
05/31
05/31
05/31
05/31
05/31
05/31
06/01
06/01
06/01
06/01
06/01
05/31
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
130 ± 6
140 ± 6
130 ± 6
130 ± 6
68 ± 5
82 ± 5
140 ± 6
120 ± 6
160 ± 6
96 ± 5
4.7 ± 4.8*
0.21 ± 6.1*
PCT OF
CONC.
GUIDE
0.6
0.7
0.7
0.6
0.3
0.4
0.7
0.6
0.8
0.5
0.02
<0.01
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
97
-------
ifle
Grand Valley
City Water
Grand Vallev/t-l
'»' 1
Scale in Miles
0 5
0 8
Scale m Kilometers
Surface Ground Zero
Water Sampling Locations
3/81
• Sefcovic Rn
. Hay ward Rn
Battlement Creek
|£ER Test Well
Ipring
Location Maps
Figure E-5. LTHMP sampling locations for Project Rulison.
98
-------
SAMPLING LOCATION
TABLE E-9.
COLLECTION
DATE
1983
CONTINUED
CONC. ± 2 SIGMA PCT OF
TRITIUM CONC.
(PCI/L) GUIDE
PROJECT RULISON - GRAND VALLEY. CO
ALBERT GARDNER RANCH 05/29
GRAND VALLEY CITY SPRIN 05/29
SPRING 300 YRDS NW OF G 05/30
BATTLEMENT CREEK 05/30
CER TEST WELL 05/30
LEE HAYWARD RANCH 05/29
G. SCHWAB RANCH 05/29
(R. SEARCY)
FELIX SEFCOVIC RANCH 05/29
POTTER RANCH 05/30
260 ± 7 1
110 ± 6 0.6
NO SAMPLE COLLECTED
200 ± 7 1
NO SAMPLE COLLECTED
260 ± 7 1
170 ± 6 0.9
360 ± 8 2
250 ± 7 1
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
99
-------
N
A.C. Mills R Mills Lower Little Creek^
r k-^n • — I S^rH. Anderson
G KellyBB | /XB.R. Anderson(n]
B. ChamblissH ~3jU-SGZ
vT.^peightsBji/_ HR.L. Anderson/
^Lowe
BaxterVilleFjR Readv
Well Ascot 21
Lumberton
Scale in Miles
5 10
3/83
5 10 15 20
Scale in Kilometers
25
Mississippi
Surface Ground Zero
Water Sampling Stations
La mar
County
Tatum Dome®SGZ
"
Location Maps
Figure F-6. LTHMP sampling locations for Project Dribble
towns and residences.
100
-------
TABLE E-9. CONTINUED
COLLECTION
DATE
SAMPLING LOCATION 1983
PROJECT DRIBBLE - BAXTERVILLE,
BAXTERVILLE CITY WELL
COLUMBIA MS
CITY WELL 64B
LUMBERTON MS
CITY WELL 2
PURVIS MS
CITY SUPPLY
HALF MOON CREEK
LOWER LITTLE CREEK
B R ANDERSON
H ANDERSON
R L ANDERSON
B CHAMBLISS
W DANIELS JR
G KELLY
M LOWE
A C MILLS
R MILLS
R READY
T SPEIGHTS
WELL ASCOT 2
MS
11/03
11/03
11/03
11/03
11/04
11/05
11/04
11/04
11/04
11/04
11/04
11/04
11/05
11/04
11/04
11/04
11/04
11/04
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
62 ± 6
-3.7 ± 7.3*
-11 ± 7*
-8.0 ± 6.2*
52 ± 5
53 ± 5
30 ± 6
34 ± 5
39 ± 6
1.9 ± 5.0*
43 ± 5
-0.91 ± 4.9*
32 ± 5
4.7 ± 5.2*
52 ± 6
81 ± 5
83 ± 6
NO SAMPLE COLLECTED
PCT OF
CONC.
GUIDE
0.3
<0.01
<0.01
<0.01
0.3
0.3
0.1
0.2
0.2
<0.01
0.2
<0.01
0.2
0.02
0.3
0.4
0.4
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
101
-------
•. o
N*
'•o
Half Moon Creek /
.Overflow
HMH-9
Scale in Feel
100 200 300
50
Scale in Meters
100
^Surface Ground Zero
Water Sampling Locations
\
(Mississippi / Lamar
/ County
Location Maps
Figure E-7. LTHMP sampling locatiions for Project Dribble - near GZ.
10?
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
PROJECT DRIBBLE -
HALF MOON CREEK
WELL E-7
WELL HM-1
WELL HM-2A
WELL HM-2B
WELL HM-3
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-L
COLLECTION
DATE
1983
BAXTERVILLE, MS (Cont.)
OVRFLW 11/03
11/05
11/03
11/03
11/03
11/03
11/04
11/04
11/03
11/03
11/04
11/04
11/03
11/03
11/03
11/04
11/03
11/03
11/03
11/03
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
550 ± 150
1.2 ± 6.1*
1.6 ± 4.9*
-2.9 ± 5.4*
0.33 ± 4.9*
1.9 ± 5.2*
85000 ± 590
16000 ± 280
140 ± 6
38 ± 5
11000 ± 250
1300 ± 160
460 ± 9
51 ± 5
63 ± 5
200 ± 7
470 ± 140
2200 ± 170
1300 ± 160
1300 ± 180
PCT OF
CONC.
GUIDE
3
<0.01
<0.01
<0.01
<0.01
<0.01
400
80
0.7
0.2
50
7
2
0.3
0.3
1
2
10
7
7
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
103
-------
REECO Pit - C
REECO Pit - B
REECO Pit - A
Half Moon Creek
Overflow X-
HM-2B,
Well HT-2C
0 100 200 300 400 500 600
3783 Seal* in Meters
Mississippi
JSurface Ground Zero
Water Sampling Locations
Location Maps
Figure E-8. LTHMP sampling locations for Project Dribble - near salt dome.
104
-------
TABLE E-9. CONTINUED
COLLECTION
DATE
SAMPLING LOCATION 1983
PROJECT DRIBBLE - BAXTERVILLE
WELL HM-L
WELL HM-L2
WELL HM-S
WELL HT-2C
WELL HT-4
WELL HT-5
REECO PIT DRAINAGE-A
REECO PIT DRAINAGE-B
REECO PIT DRAINAGE-C
POND WEST OF GZ
, MS (Cont.)
11/03
11/03
11/03
11/03
11/04
11/04
11/05
11/06
11/07
11/07
11/05
11/05
11/04
11/04
11/04
11/04
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
1400 ± 180
1400 ± 180
1500 ± 180
1400 ± 160
-0.91 ± 5.3*
19000 ± 300
19000 ± 330
19000 ± 330
19000 ± 330
23 ± 4
9.9 ± 4.5
-0.88 ± 5.7*
NO SAMPLE COLLECTED
12000 ± 250
NO SAMPLE COLLECTED
79 ± 5
PCT OF
CONC.
GUIDE
7
7
7
7
<0.01
90
100
100
100
0.1
0.05
<0.01
60
0.4
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
105
-------
N
SGZ
HTH 2
(•HTH 1
\
I
I
I
Six Mile
I Jim Bias Well
(Blue Jay Spnngsl
o 5 10
3 81 Scale in Kilometers
) Surface Ground Zero
Water Sampling Locations
I Blue Jay
Maint Sta
Location Maps
Figure E-9. LTHMP sampling locations for Project Faultless.
106
-------
Churchill County
Mineral Countv
Surface Ground Zero
Water Sampling Locations
Figure E-10. LTHMP sampling locations for Project Shoal
107
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
COLLECTION CONC. ± 2 SIGMA PCT OF
DATE TRITIUM CONC.
1983 (PCI/L) GUIDE
PROJECT FAULTLESS - BLUE JAY. NV
MAINTENANCE STATION
SIXMILE WELL
WELL HTH-1
WELL HTH-2
BIAS WELL
PROJECT SHOAL - FRENCHMAN
HUNTS STATION
FRENCHMAN STATION
WELL HS-1
WELL H-3
FLOWING WELL
07/20
07/20
07/19
07/19
07/20
STATION, NV
02/23
02/24
02/24
02/23
02/23
5.5 ± 5.2*
19 ± 5
7.3 ± 5.4*
6.0 ± 5.3*
180 ± 7
2.2 ± 5.1*
1.8 ± 4.9*
1.7 ± 5.1*
-0.72 ± 4.9*
2.1 ± 5.0*
0.03
0.09
0.04
0.03
0.9
0.01
<0.01
<0.01
<0.01
0.01
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
108
-------
EPNG Well 10-36
SGZ
• Cave Spring
| Arnold Rn Lower Burro Canyon
N
Scale in Kilometers
I Surface Ground Zero
Water Sampling Locations
New Mexico
(&SGZ
Rio Arnba County
Location Maps
Figure E-ll. LTHMP sampling locations for Project Gashugg.y.
109
-------
TABLE E-9. CONTINUED
SAMPLING LOCATION
COLLECTION CONC. ± 2 SIGMA PCT OF
DATE TRITIUM CONC.
1983 (PCI/L) GUIDE
PROJECT GASBUGGY - GOBERNADOR. NM
ARNOLD RANCH 06/03
BIXLER RANCH 06/03
BUBBLING SPRINGS 06/05
CAVE SPRINGS 06/05
LA JARA CREEK 06/05
LOWER BURRO CANYON 06/03
WELL 28.3.33.233 SOUTH 06/05
WELL 30.3.32.343 NORTH 06/05
WINDMILL 2 06/05
EPNG WELL 10-36 06/04
1.1 ± 5.1* <0.01
18 ± 5 0.09
110 ± 6 0.5
100 ± 6 0.5
100 ± 6 0.5
4.6 ± 7.4* 0.02
NO SAMPLE COLLECTED
NO SAMPLE COLLECTED
NO SAMPLE COLLECTED
18 ± 5 0.09
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
110
-------
Carlsbad
Carlsbad City Well #7
Loving City Well #2
Pecos River
Pumping Station Well #1
Scale in Miles
0 5 10
0 5 10 15
oi Scale in Kilometers
Ground Zero
A On-Site Water Sampling Locations
| Off-Site Water Sampling Locations
New Mexico
SGZ(
1
.- •"'Eddy County
Location Maps
Figure E-12. LTHMP sampling stations *or Project Gnome.
Ill
-------
TABLE E-9. CONTINUED.
COLLECTION
DATE
SAMPLING LOCATION 1983
PROJECT GNOME -
CARLSBAD CITY
PROJECT GNOME -
CARLSBAD, NM
WELL 7
LOVING, NM
LOVING CITY WATER WELL
PECOS PUMPING
PROJECT GNOME -
USGS WELL 1
USGS WELL 4
STATION
MALAGA, NM
03/28
03/28
03/26
03/29
03/29
ssasssassssssssissssssssssssssssssisssssz
CONC. ± 2 SIGMA PCT OF
TRITIUM CONC.
(PCI/L) GUIDE
-0.85 ± 5.1* <0.01
4.9 ± 4.9* 0.02
-0.79 ± 5.0* <0.01
-2.3 ± 5.1* <0.01
330000 ± 4100 2000
USGS WELL 8
PHS WELL 6
PHS WELL 8
PHS WELL 9
PHS WELL 10
WELL LRL-7
03/29
(SEE NOTE 1)
260000 ± 3800
(SEE NOTE 2)
(SEE NOTE 3)
1000
03/27
03/28
03/28
03/28
03/30
130 ± 6
15 ± 5
-1.7 ± 5.1*
-2.2 ± 5.2*
23000 ± 2100
0.6
0.08
<0.01
<0.01
100
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC)
ANALYSIS RESULT 2 SIGMA UNITS
NOTE 1
NOTE 2
NOTE 3
90Sr
137CS
90Sr
137Cs
90Sr
137CS
9000
10
5700
61
13
220
64
2
49
11
2
20
pCi/L
pCi/L
pCi/L
pd/L
pCi/L
pd/L
112
-------
TABLE E-10. 1983 SUMMARY OF ANALYTICAL RESULTS FOR THE
MILK SURVEILLANCE NETWORK
SAMPLING
LOCATION
BISHOP, CA,
WHITE MOUNTAIN RANCH
HINKLEY, CA,
BILL NELSON DAIRY
RIDGECREST, CA,
CEDARSAGE FARM
KEOUGH HOT SPGS, CA,
YRIBARREN RCH
ALAMO, NV,
WHIPPLE RANCH
RACHEL, NV,
FALL IS RANCH
RACHEL, NV,
JAMES MOODY
AUSTIN, NV,
YOUNG'S RANCH
CURRANT, NV,
BLUE EAGLE RANCH
CURRANT, NV,
MANZONIE RANCH
SAMPLE
TYPE
13
12
10
13
13
10
13
13
13
13
NO. OF
SAMPLES
1
1
1
4
3
4
3
3
3
3
2
2
3
3
3
4
4
4
2
2
2
4
4
4
4
4
4
3
3
3
RAD 10-
NUCLIDE
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
RADIOACTIVITY CONC.
(PCI/L)
MAX
200
-0.60
-0.60
330
2.8
1.7
63
5.6
-0.25
150
4.3
3.4
170
1.0
1.4
190
0.68
3.3
140
0.41
1.0
220
1.5
1.8
190
1.5
5.1
190
3.1
2.9
MIN
200
-0.60
-0.60
-360
-1.5
0.053
-160
1.7
-1.0
-160
3.4
2.6
-20
-4.7
-0.37
-140
-8.4
-1.5
-18
-0.86
0.66
45
-2.0
-0.55
-100
-8.5
0.38
-140
-7.5
-1.0
AVG
200
-0.60
-0.60
-32
1.1
0.70
-79
3.1
-0.54
-53
3.9
3.0
58
-0.94
0.23
24
-3.1
1.2
63
-0.23
0.84
110
0.31
0.46
-9.9
-2.4
2.7
-0.67
-1.3
1.1
CONTINUED
113
-------
TABLE E-10. (Cont.)
SAMPLING
LOCATION
HIKO, NV,
DARREL HANSEN RANCH
LAS VEGAS, NV,
LDS DAIRY FARMS
LIDA, NV,
LIDA LIVESTOCK COMPANY
LOGANDALE, NV,
KNUDSEN DAIRY
LUND, NV,
MCKENZIE DAIRY
MCGILL, NV,
LARSEN RANCH
MESQUITE, NV,
SF AND K DAIRY
MOAPA, NV,
DECADE CORP
NYALA, NV,
SHARP'S RANCH
CALIENTE, NV,
JUNE COX RANCH
ROUND MT, NV,
BERG'S RANCH
:=================:
SAMPLE NO. OF
TYPE SAMPLES
13
12
13
12
12
13
12
12
13
13
13
1
1
1
4
4
4
3
2
3
4
4
4
4
4
4
3
3
3
4
3
3
4
4
4
4
4
4
4
4
4
2
2
2
RAD 10-
NUCLIDE
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
RADIOACTIVITY
(PCI/L)
MAX
360
-3.5
1.0
310
2.5
1.5
34
5.0
1.4
230
6.6
4.0
86
2.1
0.25
99
3.0
2.1
300
-1.3
0.61
210
4.8
1.8
210
7.8
0.76
190
0.66
1.6
-73
0.35
2.0
MIN
360
-3.5
1.0
-86
-8.2
-0.57
-140
-0.78
-2.0
-170
-13
-1.7
-320
0.020
-0.41
-130
0.83
-0.22
-320
-7.7
-0.72
-170
-1.9
-2.1
-5.2
-0.92
-2.7
-37
-0.16
-0.63
-110
-3.1
0.77
CONC.
AVG
360
-3.5
1.0
39
-1.1
0.14
-26
2.1
-0.31
-1.8
-1.7
0.98
-100
0.81
0.048
-8.4
1.9
0.65
-42
-3.5
-0.18
-32
1.6
-0.074
87
4.0
-0.37
92
0.12
0.58
-91
-1.4
1.4
CONTINUED
114
-------
TABLE E-10. (Cont.)
RADIOACTIVITY CONC.
(PCI/L)
onrir u A. mw
LOCATION
SHOSHONE, NV,
HARBECKE RANCH
WARM SPRINGS, NV,
TWIN SPRINGS RCH
CEDAR CITY, UT,
WESTERN GEN DAIRIES
ST GEORGE, UT,
DROUBAY DAIRY
onpirut
TYPE
13
13
12
12
IKU . ur
SAMPLES
4
4
4
3
3
3
4
4
4
4
4
4
rvrtuiu-
NUCLIDE
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
MAX
260
4.3
3.6
88
7.3
2.0
230
4.1
1.6
170
5.5
4.3
MIN
-94
-3.6
0.055
-89
1.0
-0.63
-180
0.45
-0.49
-24
-9.3
-2.8
AVG
110
0.47
1.5
-1.8
4.1
0.68
48
2.0
0.56
81
0.22
1.5
115
-------
TABLE E-ll. ANALYTICAL RESULTS FOR THE STANDBY MILK SURVEILLANCE NETWORK 1983
= = = = = = = = = ___
COLLECTION CONC. ± 2 SIGMA
DATE 3H 89SR 90SR
SAMPLING LOCATION 1983 (PCI/L) (PCI/L) (PCI/L)
A. GAMMA
TAYLOR ARIZ
SUNRISE DAIRY
TUCSON ARIZ
SHAMROCK DAIRY (PIMA CO)
LITTLE ROCK ARK
BORDENS
RUSSELLVILLE ARK
ARKANSAS TECH UNIV
BAKERSFIELD CALIF
CARNATION DAIRY
LEMON GROVE CALIF
MILLER DAIRY
WEED CALIF
MEDO-BEL CREAMERY
WILLOWS CALIF
FOREMOST FOODS COMPANY
GRAND JCT COLO
COLORADO WEST DAIRIES
PUEBLO COLO
HYDE PARK DAIRY CO
IDAHO FALLS IDA
WESTERN GENERAL DAIRY
BURLINGTON IOWA
MISS VALLEY MILK PRO
DAVENPORT IOWA
SWISS VALLEY FARMS CO
SPECTRAL AND
06/06
06/06
0815
08/19
07/11
07/11
07/12
07/12
07/25
07/27
08/15
06/06
06/04
89SR
RADIOCHEMICAL ANALYSES
35 ± 340* -8.8 ± 4.9*
-27 ± 340* -0.21 ± 4.1*
150 ± 320* NA
92 ± 320* NA
40 ± 340* -1.7 ± 3.2*
NA 2.7 ± 4.2*
NA 1.7 ± 2.0*
-210 ± 340* 2.5 ± 4.1*
-200 ± 340* NA
(LOST)
190 ± 340* 2.7 ± 2.3*
98 ± 340* NA
-71 ± 340* -4.2 ± 3.6*
-130 ± 34* NA
LOST
1.9 ± 2.8*
0.26 ± 2.3*
NA
NA
1.3 ± 2.7*
-0.21 ± 2.5*
-0.35 ± 2.0*
0.29 ± 2.7*
-0.57 ± 2.0*
0.14 ± 1.9*
NA
4.6 ± 3.2
1.9 ± 1.9*
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
CONTINUED
116
-------
TABLE E-ll. (Cont.)
SAMPLING LOCATION
LEMARS IOWA
WELLS DAIRY
CONCORDIA KAN
FAIRMONT FOOD CO
GARDEN CITY KAN
MYERS MILK PROD
MONROE LA
BORDEN'S
NEW ORLEANS LA
BORDEN'S
ROCHESTER MINN
ASSC MILK PRODUCERS
AURORA MO
MID-AMERICA DAIRY INC
CHILL ICOTHE MO
MID-AMERICA DAIRYMEN
NORFOLK NEB
GILLETTE DAIRY
NORTH PLATTE NEB
MID AMERICA DAIRYMEN
FALLON NEV
CREAMLAND DAIRY
LAS VEGAS NEV
ANDERSON DAIRY
BISMARCK N DAK
BRIDGEMENS CREAMERY
GRAND FORKS N DAK
MINNESOTA DAIRY
* CONCENTRATION IS LESS
COLLECTION CONC. ± 2 SIGMA
DATE 3H 89SR 90SR
1983 (PCI/L) (PCI/L) (PCI/L)
06/06
06/23
06/04
06/28
08/09
08/23
06/05
06/06
07/05
06/06
07/11
07/12
07/26
07/25
THAN THE
NA 1.4 ± 3.0*
22 ± 340* -4.0 ± 3.6*
170 ± 340 -7.3 ± 3.8*
NA 16 ± 11*
67 ± 340* 4.3 ± 4.4*
160 ± 320* 0.12 ± 3.4*
120 ± 340* -1.3 ± 3.2*
-140 ± 340* -0.92 ± 3.3*
140 ± 300* 0.88 ± 3.8*
170 ± 340* -13 ± 5*
-170 ± 340* 2.8 ± 3.9*
NA 0.76 ± 2.4*
67 ± 340* 0.15 ± 1.5*
190 ± 310* NA
(LOST)
MINIMUM DETECTABLE CONCENTRATION
2.0 ±
3.2 ±
2.0 ±
0.67 ±
2.7 ±
0.64 ± 3
5.3 ±
4.2 ±
0.17 ±
6.1 ±
0.037 ±
0.57 ±
2.6 ±
0.45 ±
(MDC).
2.4*
2.7
2.3*
5.4*
3.5*
.4*
2.8
2.9
3.3*
3.8
2.3*
2.2*
2.5
2.5*
CONTINUED
117
-------
TABLE E-ll. (Cont.)
SAMPLING LOCATION
ENID OKLA
AMPI GOLDSPOT DIVISION
MCALESTER OKLA
OKLA ST PENITENTIARY
CORVALLIS ORE
SUNNY BROOK DAIRY
MEDFORD ORE
DAIRYGOLD FARMS
SIOUX FALLS S DAK
TERRACE PARK DAIRY
PROVO UTAH
BYU DAIRY PRODUCTS LAB
SEATTLE WASH
CONSOLIDATED DAIRY PRO
SPOKANE WASH
CONSOLIDATED DAIRY
SAMPLING LOCATION
PIMA ARIZ
SMITH HUNT DAIRY
TEMPE ARIZ
UNITED DAIRYMEN OF AZ
FAYETTEVILLE ARK
UNIVERSITY OF ARK
COLLECTION
DATE
1983
07/22
06/23
08/16
08/15
07/25
07/25
08/16
D
08/14
B. GAMMA
COLLECTION
DATE
1983
06/06
06/06
08/15
CONC. ± 2 SIGMA
3H 89SR
(PCI/L) (PCI/L)
-80 ± 340* -4.0 ± 1.7*
100 ± 300* 1.0 ± 3.0*
-24 ± 320* NA
130 ± 320* 0.77 ± 1.6*
-130 ± 340* NA
(LOST)
170 ± 310* -2.1 ± 2.1*
160 ± 320* 0.90 ± 2.1*
160 ± 320* -2.8 ± 5.3*
SPECTRAL ANALYSES ONLY**
SAMPLING LOCATION
KINGMAN ARIZ
CANYON FARMS
YUMA ARIZ
GOLDEN WEST DAIRY
PARAGOULD ARK
FOREMOST FOODS INC
90SR
(PCI/L)
4.6 ± 2.6
2.1 ± 2.2*
NA
1.6 ± 1.8*
1.8 ± 2.3*
2.5 ± 2.4*
0.95 ± 2.3*
1.3 ± 4.5*
COLLECTION
DATE
1983
06/06
06/06
08/17
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
**POTASSIUM-40 WAS THE ONLY GAMMA-EMITTER DETECTED IN THESE SAMPLES.
CONTINUED
118
-------
TABLE E-ll. (Cont.)
COLLECTION
DATE
SAMPLING LOCATION 1983
HELENDALE CALIF
OSTERKAMP DAIRY NO 2
FERNBRIDGE CALIF
HUMBOLDT CREAMERY
MANTECA CALIF
DEJAGER DAIRY A2 NORTH
OXNARD CALIF
CHASE BROS DAIRY
PALO ALTO CALIF
PENINSULA CREAMERY
REDDING CALIF
MCCOLL'S DAIRY PROD
SAN LUIS OBISPO CALIF
CAL STATE POLY
SANTA ROSA CALIF
GLEN OAKS FARM
SAUGUS CALIF
WAYSIDE HONOR RANCH
SMITH RIVER CALIF
COUNTRY MAID DAIRY
TRACY CALIF
DEUEL VOC INST
FT COLLINS COLO
POUDRE VALLEY DAIRY
KIMBALLTON IOWA
AMPI RECEIVING STA
LAKE MILLS IOWA
LAKE MILLS COOP CRMY
07/13
07/11
07/11
07/13
07/12
07/11
07/11
07/11
07/13
07/11
07/12
07/25
06/06
06/06
:=========================================
COLLECTION
DATE
SAMPLING LOCATION 1983
CHINO CALIF
CALIF INST FOR MEN
FRESNO CALIF
STATE UN IV CREAMERY
MODESTO CALIF
FOSTER FARMS DAIRY
DALTON MINN
DALTON CO-OP CREAMERY
FLENSBURG MINN
FLENSBURG CO-OP CMRY
NICOLLET MINN
WALTER SCHULTZ FARM
JACKSON MO
MID-AMERICA DAIRYMEN IN
JEFFERSON CITY MO
CENTRAL DAIRY CO
ALBUQUERQUE NM
BORDEN'S VALLEY GOLD
MEADOW GOLD DAIRY
BOZEMAN MONT
DARIGOLD FARMS
LA PLATA NM
ROTHLISBERGER DAIRY
GREAT FALLS MONT
MEADOW GOLD DAIRY
LAS CRUCES NM
LONG'S DAIRY
EQUITY SUPPLY CO
08/16
07/11
07/11
08/22
08/22
08/22
06/06
06/03
07/05
07/25
07/27
07/05
07/27
07/06
07/25
CONTINUED
119
-------
TABLE E-ll. (Cont.)
COLLECTION
DATE
SAMPLING LOCATION 1983
ELLIS KAN
MID-AMERICA DAIRY
HAMMOND LA
SOUTHEASTERN LA COLLEGE
LAFAYETTE LA
UNIV SOUTHWESTERN LA
RUSTON LA
TECH UNIV DAIRY
DEVILS LAKE N DAK
LAKE VIEW DAIRY
FARGO N DAK
CASSCLAY CREAMERY
WILLISTON N DAK
PETERSONS CREAMERY
CLAREMORE OKLA
06/04
06/25
06/27
06/27
07/25
07/26
07/25
06/22
COLLECTION
DATE
SAMPLING LOCATION 1983
MISSOULA MONT
MEADOW GOLD DAIRY
RENO NEV
MODEL DAIRY
STILLWATER OKLA
OSU DAIRY
MITCHELL S DAK
CULHANES DAIRY
VOLGA S DAK
LAND 0' LAKES INC
BEAVER UTAH
CACHE VALLEY DAIRY
CEDAR CITY UTAH
WESTERN GEN DAIRIES
SMITHFIELD UTAH
07/25
07/11
07/25
07/25
07/26
07/25
07/26
07/26
SWAN BROS DAIRY
CACHE VALLEY DAIRY
120
-------
TABLE E-12. 1983 SUMMARY OF RADIATION DOSE EQUIVALENTS FROM TLD DATA
STATION
LOCATION
ADAVEN, NV
ALAMO, NV
AMERICAN BORATE, NV
AUSTIN, NY
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
COALDALE, NV
COMPLEX 1, NV
CORN CREEK, NV
COYOTE SUMMIT, NV
CRYSTAL, NV
iiS = = = = = = = = = S = = = = = = = = == =
MEASUREMENT PERIOD
ISSUE COLLECT
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
07/19/83
01/12/83
01/10/83
01/11/83
07/05/83
01/06/84
01/06/84
01/04/84
01/05/84
01/03/84
01/03/84
01/04/84
01/04/84
01/05/84
01/05/84
01/03/84
01/09/84
01/09/84
01/04/84
01/05/84
01/05/84
01/04/84
01/06/84
01/03/84
01/03/84
01/04/84
; = =s=ss = = ==s= = = = = = 55 = = s = :
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.35
0.25
0.26
0.34
0.24
0.29
0.29
0.27
0.19
0.33
0.15
0.29
0.29
0.20
0.21
0.31
0.28
0.32
0.13
0.33
0.19
MIN.
0.30
0.23
0.26
0.31
0.22
0.28
0.29
0.25
0.17
0.30
0.15
0.28
0.27
0.19
0.18
0.30
0.22
0.28
0.12
0.32
0.19
AVG.
0.32
0.24
0.26
0.33
0.23
0.29
0.29
0.26
0.18
0.32
0.15
0.29
0.28
0.19
0.19
0.30
0.25
0.30
0.12
0.32
0.19
ANNUAL
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
117
86
94
121
83
105
106
96
65
116
55
104
102
70
68
110
91
110
45
117
68
(CONTINUED)
121
-------
TABLE E-12. CONTINUED
STATION
LOCATION
CURRANT, NV
DEATH VALLEY JCT, CA
DIABLO MAINT. STA.
DUCKWATER, NV
ELGIN, NV
ELY, NV
ENTERPRISE, UT
EUREKA, NV
FURNACE CREEK, CA
GABBS, NV
GARRISON, UT
GEYSER RANCH, NV
GOLDFIELD, NV
GROOM LAKE-NTS, NV
HANCOCK SUMMIT, NV
HIKO, NV
HOT CK RNCH, NV
INDEPENDENCE, CA
INDIAN SPRINGS, NV
KIRKEBY RANCH, NV
KOYNES, NV
MEASUREMENT PERIOD
ISSUE COLLECT
01/11/83
01/13/83
01/11/83
01/11/83
01/13/83
01/13/83
01/12/83
01/11/83
01/13/83
07/19/83
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
01/03/84
01/06/84
01/04/84
01/03/84
01/09/84
01/04/84
01/05/84
01/05/84
01/06/84
01/04/84
01/04/84
01/04/84
01/03/84
01/03/84
01/03/84
01/10/84
01/05/84
01/04/84
01/03/84
01/04/84
01/04/84
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.29
0.20
0.34
0.27
0.32
0.22
0.28
0.30
0.19
0.21
0.20
0.29
0.25
0.21
0.41
0.21
0.25
0.25
0.14
0.21
0.25
MIN.
0.27
0.19
0.32
0.26
0.32
0.21
0.26
0.27
0.17
0.15
0.18
0.27
0.22
0.18
0.37
0.19
0.24
0.23
0.13
0.19
0.24
AVG.
0.28
0.20
0.33
0.26
0.32
0.22
0.27
0.29
0.18
0.18
0.19
0.28
0.24
0.19
0.38
0.20
0.24
0.24
0.13
0.20
0.24
ANNUAL
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
101
72
121
95
117
78
99
105
65
66
69
101
87
70
140
71
88
88
49
73
88
(CONTINUED)
122
-------
TABLE E-12. CONTINUED
STATION
LOCATION
LAS VEGAS (AIRPORT)
LAS VEGAS (PLACAK)
LAS VEGAS (UNLV) NV
LAS VEGAS (USDI)
LATHROP WELLS, NV
LAVADA'S MARKET NV
LIDA, NV
LONE PINE, CA
LUND, NV
MAMMOTH MOUNTAIN, CA
MANHATTAN, NV
MESQUITE, NV
MINA, NV
MOAPA, NV
NYALA, NV
OLANCHA.CA.
OVERTON, NV
PAHRUMP, NV
PENOYER FARMS, NV
PINE CK RNCH, NV
PIOCHE, NV
MEASUREMENT PERIOD
ISSUE COLLECT
12/29/82
12/29/82
12/29/82
12/29/82
01/10/83
01/12/83
01/10/83
01/12/83
01/13/83
01/12/83
01/11/83
01/10/83
07/19/83
01/10/83
01/12/83
01/12/83
01/10/83
01/13/83
01/11/83
01/12/83
01/12/83
01/03/84
01/03/84
01/03/84
01/03/84
01/03/84
01/04/84
01/03/84
01/04/84
01/03/84
01/05/84
01/05/84
01/04/84
01/04/84
01/03/84
01/04/84
01/04/84
01/04/84
01/04/84
01/04/84
01/06/84
01/09/84
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.14
0.14
0.12
0.17
0.24
0.24
0.27
0.25
0.23
0.34
0.33
0.17
0.26
0.18
0.22
0.25
0.16
0.14
0.31
0.33
0.22
MIN.
0.14
0.14
0.11
0.16
0.23
0.21
0.25
0.24
0.22
0.22
0.24
0.16
0.21
0.17
0.22
0.25
0.15
0.13
0.30
0.31
0.20
AV5.
0.14
0.14
0.12
0.17
0.24
0.22
0.26
0.24
0.22
0.27
0.30
0.16
0.24
0.18
0.22
0.25
0.15
0.13
0.30
0.32
0.21
ANNUAL
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
51
51
42
60
87
81
93
88
81
97
110
60
86
64
79
91
55
49
109
117
77
(CONTINUED)
123
-------
TABLE E-12. CONTINUED
STATION MEASUREMENT PERIOD
LOCATION ISSUE COLLECT
QUEEN CITY SMT. NV
RACHEL, NV
REED RANCH, NV
RID6ECREST, CA
ROUND MT, NV
S. DESERT COR. CENTR
SALT LAKE CITY, UT
SCOTTY'S JCT, NV
SHERI'S RANCH, NV
SHOSHONE, CA
SPRING MEADOWS, NV
SPRINGDALE, NV
ST. GEORGE, UT
STONE CABIN RNCH, NV
SUNNYSIDE, NV
TEMPIUTE, NV
TIKABOO VALLEY, NV
TONOPAH TEST RNG, NV
TONOPAH, NV
TWIN SPRGS RNCH, NV
USECOLOGY
01/10/83
01/11/83
01/11/83
01/11/83
01/11/83
07/05/83
01/17/83
01/10/83
01/14/83
01/13/83
01/10/83
01/11/83
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
01/04/84
01/04/84
01/04/84
01/04/84
01/05/84
01/03/84
01/23/84
01/03/84
01/10/84
01/06/84
04/05/83
01/03/84
01/04/84
01/05/84
01/03/84
01/03/84
01/03/84
01/04/84
01/04/84
01/04/84
01/03/84
2=as=ass3a=3=s==3=====
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.36
0.29
0.30
0.24
0.30
0.13
0.22
0.29
0.22
0.21
0.15
0.30
0.15
0.32
0.17
0.30
0.29
0.28
0.32
0.30
0.30
MIN.
0.33
0.28
0.27
0.22
0.20
0.13
0.21
0.26
0.19
0.20
0.15
0.28
0.14
0.30
0.15
0.29
0.28
0.25
0.30
0.29
0.28
AVG.
0.34
0.29
0.29
0.23
0.28
0.13
0.22
0.27
0.20
0.20
0.15
0.29
0.15
0.31
0.16
0.30
0.29
0.27
0.31
0.29
0.29
ANNUAL
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
125
105
104
84
100
46
78
99
72
73
56
105
53
112
57
107
104
98
112
107
104
(CONTINUED)
124
-------
TABLE E-12. CONTINUED
STATION
LOCATION
VALLEY CREST, CA
WARM SPRINGS, NV
YOUNG'S RANCH, NV
===================
MEASUREMENT PERIOD
ISSUE COLLECT
01/13/83
01/12/83
01/11/83
01/06/84
01/05/84
01/05/84
========================
ANNUAL
DOSE ADJUSTED
EQUIVALENT RATE DOSE
(MREM/D) EQUIVALENT
MAX.
0.16
0.33
0.25
_________
MIN.
0.15
0.30
0.25
=======
AVG. (MREM/Y)
0.15 55
0.32 115
0.25 91
====================
125
-------
TABLE £-13. 1983 SUMMARY OF RADIATION DOSES FOR OFFSITE RESIDENTS
RES-
I- BACKGROUND
DENT STATION MEASUREMENT PERIOD
NO. LOCATION ISSUE COLLECT
2
3
6
7
8
9
10
11
12
13
14
15
17
18
19
21
22
24
25
27
Callente, NV
Blue Jay, NV
Indian Springs, NV
Goldfleld, 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
Goldfleld, NV
Beatty, NV
Alamo, NV
Corn Creek, NV
Corn Creek, NV
Pahrump, NV
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
01/10/83
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
01/09/84
01/05/84
01/03/84
01/03/84
01/04/84
01/09/84
01/06/84
01/06/84
10/03/83
01/04/84
01/19/84
01/19/84
07/06/83
01/04/84
01/08/84
01/04/84
01/06/84
01/03/84
01/03/84
01/04/84
=====S==s==========s===:
DOSE
EQUIVALENT RATE
(MREM/D) 1
MAX.
0.29
0.40
0.15
0.21
0.27
0.17
0.29
0.28
0.12
0.18
0.27
0.26
0.19
0.20
0.24
0.24
0.19
0.13
0.14
0.17
MIN.
0.22
0.24
0.13
0.19
0.26
0.16
0.26
0.25
0.11
0.17
0.24
0.22
0.18
0.18
0.20
0.21
0.16
0.11
0.14
0.16
AVG.
0.25
0.35
0.14
0.20
0.27
0.17
0.28
0.27
0.11
0.18
0.25
0.24
0.19
0.19
0.21
0.23
0.17
0.12
0.14
0.17
NET
EXPOSURE
(MREM)
0.0
20
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
9.1
(CONTINUED)
126
-------
TABLE E-13. CONTINUED
RES-
I-
DENT
NO.
28
29
30
33
34
35
36
37
38
40
41
42
43
44
45
47
48
49
50
51
BACKGROUND
STATION
LOCATION
Hot Creek Ranch, NV
Stone Cabin Ranch, NV
Rachel, NV
Lathrop Wells, NV
Furnace Creek, CA
Death Valley Jet., 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
MEASUREMENT PERIOD
ISSUE COLLECT
01/12/83
01/12/83
01/11/83
04/05/83
01/13/83
01/13/83
01/13/83
01/10/83
01/13/83
01/10/83
01/11/83
01/11/83
01/13/83
01/11/83
01/11/83
01/11/83
01/11/83
12/29/82
01/12/83
04/06/83
01/05/84
01/05/84
01/03/84
01/04/84
01/06/84
01/06/84
01/04/84
01/03/84
01/04/84
10/03/83
01/05/84
01/04/84
04/08/83
01/05/84
01/19/84
01/05/84
01/04/84
01/03/84
01/05/84
01/04/84
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.28
0.27
0.24
0.25
0.16
0.19
0.13
0.23
0.38
0.22
0.35
0.27
0.20
0.25
0.20
0.19
0.22
0.25
0.27
0.23
MIN.
0.23
0.24
0.23
0.19
0.08
0.18
0.12
0.13
0.24
0.20
0.27
0.25
0.20
0.19
0.15
0.16
0.21
0.20
0.25
0.23
AVG.
0.25
0.26
0.24
0.22
0.13
0.18
0.13
0.16
0.29
0.21
0.31
0.26
0.20
0.21
0.17
0.18
0.22
0.23
0.26
0.23
NET
EXPOSURE
(MREM)
4.0
0.0
0.0
0.0
0.0
0.0
0.0
8.9
7.7
0.0
0.0
0.0
0.0
6.5
6.8
0.0
0.0
45
2.2
0.0
(CONTINUED)
127
-------
TABLE E-13. CONTINUED
RES-
I- BACKGROUND
DENT STATION
NO. LOCATION
52
53
54
55
56
57
58
59
60
Salt Lake City, UT
Shoshone, CA
Rachel, NV
Rachel, NV
Corn Creek Station
Overton, NV
Alamo, NV
Cedar City, UT
Shoshone, CA
======================
MEASUREMENT PERIOD
ISSUE COLLECT
01/17/83
01/13/83
01/11/83
01/11/83
NV 12/29/82
01/10/83
07/01/83
08/05/83
10/14/83
=============
02/06/84
10/14/83
01/04/84
01/04/84
01/03/84
01/19/84
01/06/84
01/05/84
01/18/84
DOSE
EQUIVALENT RATE
(MREM/D)
MAX.
0.33
0.20
0.28
0.28
0.17
0.22
0.19
0.20
0.19
MIN.
0.24
0.16
0.26
0.25
0.16
0.20
0.18
0.18
0.19
AVG.
0.29
0.18
0.27
0.27
0.16
0.21
0.19
0.19
0.19
NET
EXPOSURE
(MREM)
20
0.0
0.0
0.0
9.9
21
0.0
0.0
0.0
128
-------
TECHNICAL REPORT DATA
(Pleaie read Instructions on the revertt before completing)
DREF
39-051 May 1984
2.
3. RECIPIENT'S ACCESSION NO.
. TITLE AND SUBTITLE
OFFSITE ENVIRONMENTAL MONITORING REPORT
Radiation Monitoring Around U.S. Nuclear Test Areas,
Calendar Year 1983
5. REPORT DATE
6. PERFORMING ORGANIZATION CODE
..AUTHOR1S) ~ ~
R. G. Patzer, S. C. Black, R. F. Grossman, and
D. D. Smith
8. PERFORMING ORGANIZATION REPORT NO.
EPA-600/4-84-040
PERFORMING ORGANIZATION NAME AND ADDRESS
Environmental Monitoring 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-A108-76DP00539
12. SPONSORING AGENCY NAME AND ADDRESS
U.S. Department of Energy
Nevada Operations Office
P.O. Box 14100
Las Vegas, NV 89114
13. TYPE OF REPORT AND PERIOD COVERED
Response - 1983
14. SPONSORING AGENCY CODE
15. SUPPLEMENTARY NOTES
Prepared for the U.S. Department of Energy under Interagency Agreement No.
DE-A108-76DP00539
KLABSTRACT
This report covers the routine radiation monitoring activities conducted by the
Environmental Monitoring Systems Laboratory-Las Vegas in areas which may be
affected by nuclear testing programs of the Department of Energy. This monitoring
is conducted to document compliance with standards, to identify trends in environ-
mental radiation, and to provide such information to the public. It summarizes these
activities for calendar year 1983.
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 yeild an estimated
dose of 5X10 man-rem to the population within 80 km of the Nevada Test Site during
1983. World-wide fallout of Kr-85, Sr-90, Cs-137, and Pu-239 detected by the monitor-
ing networks would cause maximum exposure to an individual of less than 0.2 mrem per
year. Plutonium and krypton in air were similar to 1982 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.
17.
KEY WORDS AND DOCUMENT ANALYSIS
DESCRIPTORS
b.IDENTIFIERS/OPEN ENDED TERMS
cos AT I Field/Group
18. DISTRIBUTION STATEMENT
RELEASE TO THE PUBLIC
19. SECURITY CLASS (This Report I
UNCLASSIFIED
21. NO. OF PAGES
141
20. SECURITY CLASS (This page)
UNCLASSIFIED
22. PRICE
EPA Form 2220-1 (R«v. 4-77) PREVIOUS EDITION i» OBSOLETE
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