&EPA
United States
Environmental Protection
Agency
Environmental Monitoring
Systems Laboratory
P.O. Box 15027
Las Vegas NV 89114-5027
EPA/600/4-86/022
DOE/DP/00539/056
April 1986
Research and Development
Off-Site
Environmental
Monitoring Report:
Radiation Monitoring
Around United States
Nuclear Test Areas,
Calendar Year
1985
prepared for the
United States 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 E07
Microfiche A01
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EPA-600/4-86-022
DOE/DP/00539-056
April 1986
OFF-SITE ENVIRONMENTAL MONITORING REPORT
Radiation Monitoring Around United States
Nuclear Test Areas, Calendar Year 1985
compiled by
R. F. Grossman, S. C. Black, R. E. Dye,
D. D. Smith, D. J. Thome, A. A. Mullen, and
Nuclear Radiation Assessment Division
prepared for the
U.S. Department of Energy
under Interagency Agreement
Number DE-AI08-76DP00539
0
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.
ii
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PREFACE
The U.S. Atomic Energy Commission (AEC) used the Nevada Test Site (NTS)
from January 1951 through January 19, 1975, for conducting nuclear weapons
tests, nuclear rocket-engine development, nuclear medicine studies, and other
nuclear and non-nuclear experiments. Beginning January 19, 1975, these activ-
ities became the responsibility of the newly formed U.S. Energy Research and
Development Administration (ERDA). On October 1, 1977 the ERDA was merged with
other energy-related agencies to form the U.S. Department of Energy (DOE).
Atmospheric nuclear tests were conducted periodically from January 27, 1951,
through October 30, 1958, after which a testing moratorium was in effect until
September 1, 1961. Since September 1, 1961, all nuclear detonations have been
conducted underground with the expectation of containment, except for four
slightly above-ground or shallow underground tests of Operation Dominic II in
1962 and five nuclear earth-cratering experiments conducted under the Plowshare
program between 1962 and 1968.
Prior to 1954, an off-site surveillance program was performed by the Los
Alamos Scientific Laboratory and the U.S. Army. From 1954 through 1970 the
U.S. Public Health Service (PHS), and from 1970 to the present the U.S. Envi-
ronmental Protection Agency (EPA) have provided an Off-Site Radiological Safety
Program under an Interagency Agreement. The PHS or EPA has also provided
off-site surveillance for U.S. nuclear explosive tests at places other than the
NTS.
Since 1954, an objective of this surveillance program has been to measure
levels and trends of radioactivity, if present, in the environment surrounding
testing areas to ascertain whether the testing is in compliance with existing
radiation protection standards. Off-site levels of radiation and radioactivity
are assessed by sampling milk, water, and air; by deploying dosimeters; and by
sampling food crops, soil, etc., as required. Personnel with mobile monitoring
equipment are placed in areas downwind from the test site prior to each test
in order to implement protective actions, provide immediate radiation monitoring,
and obtain environmental samples rapidly after any release of radioactivity.
Since 1962, aircraft have also been deployed to rapidly monitor and sample
releases of radioactivity during nuclear tests. Monitoring data obtained by
the aircraft crew immediately after a test are used to position mobile radiation
monitoring personnel on the ground. Data from airborne sampling are used to
quantify the amounts, diffusion, and transport of the radionuclides released.
Beginning with Operation Upshot-Knothole in 1953, a report was published
by the PHS summarizing the surveillance data for each test series. In 1959
for reactor tests, and in 1962 for weapons and Plowshare tests, such data were
published for those tests that released radioactivity detectable off the NTS.
iii
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The reporting interval was changed again in 1964 to semi-annual publication of
data for each 6-month period which also included the data from the individual
reports.
In 1971, the AEC implemented a requirement, now incorporated into DOE
Order 5484.1, that each contractor or agency involved in major nuclear act-
ivities provide a comprehensive annual radiological monitoring report. This is
the fourteenth annual report in this series; it summarizes the off-site
activities of the EPA during CY 1985.
IV
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CONTENTS
Page
Preface iii
Figures vii
Tables ix
Abbreviations, Symbols and Conversions xi
Prefixes, Conversions xii
1. Introduction 1
2. Summary 2
Purpose 2
Locations 2
Special Test Support 2
Pathways Monitoring 3
External Exposure 3
Internal Exposure 3
Community Monitoring Stations 4
Dose Assessment 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 1985 ... 8
4. Quality Assurance 10
Goals 10
Sample Collection 10
Sample Analysis 10
External QA 10
Internal QA 11
Validation 11
Audits 11
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. . 22
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CONTENTS (Continued)
Page
5. (Cont)
Milk Surveillance Network 25
Biomonitoring Program 30
External Exposure Monitoring 32
Thermo!uminescent Oosimetry Network 32
Pressurized Ion Chamber Network 39
Internal Exposure Monitoring 39
Network Design 40
Methods 41
Results 41
Community Monitoring Stations . 43
Claims Investigations 43
Public Information Program 44
Dose Assessment 45
6. References 48
Appendices
A. Site Data A-l
B. Sample Analysis Procedures B-l
C. Quality Assurance Procedures - C-l
D. Radiation Protection Standards for External and Internal
Exposure 0-1
E. Data Summary for the Monitoring Networks E-l
Addenda
1. REECO Nonradiological Supplement to the NTS Environmental
Monitoring Report Add-1
2. Environmental Permits, Orders, and Notices Add-4
3. Environmental Impact Statements and Environmental Assessments. . . Add-14
vi
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FIGURES
Number Page
1 Location of the Nevada Test Site 6
2 Air Surveillance Network stations (1985) 15
3 Standby Air Surveillance Network stations (1985) 16
4 Monthly average gross beta in air samples, 1981-1985 18
5 Noble Gas and Tritium Surveillance Network
sampling locations 19
6 Weekly average krypton-85 concentration in air, 1985 data 21
7 Trend in annual average krypton-85 concentration 21
8 LTHMP sampling locations on the NTS 23
9 LTHMP sampling locations near the NTS 24
10 Milk sampling locations within 300 km of the NTS 27
11 Standby milk surveillance network stations 28
12 Strontium-90 concentration in Pasteurized Milk Network
samples 30
13 Collection sites for bighorn sheep samples 31
14 Average strontium-90 concentration in animal bone 35
15 Locations monitored with TLD's 36
16 Average annual TLD exposure as a function of station
altitude 38
17 Location of families in the Off-Site Human Surveillance
Program 42
vii
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FIGURES (Continued)
Number Page
A-l Ground-water flow systems around the
Nevada Test Site A-4
A-2 General land use within 300 km of the
Nevada Test Site A-5
A-3 Population of Arizona, California, Nevada, and Utah
Counties near the Nevada Test Site (1980) A-7
A-4 Distribution of family milk cows and goats,
by county (1985) A-8
A-5 Distribution of dairy cows, by county (1985) A-9
A-6 Distribution of beef cattle, by county (1985) A-10
A-7 Distribution of sheep, by county (1985) A-ll
E-l Amchitka Island and background sampling locations
for the LTHMP E-13
E-2 LTHMP sampling locations for Project Cannikin E-15
E-3 LTHMP sampling locations for Projects Mil row and Long Shot .... E-16
E-4 LTHMP sampling locations for Project Rio Blanco E-18
E-5 LTHMP sampling locations for Project Rulison E-20
E-6 LTHMP sampling locations for Project Dribble -
towns and residences E-22
E-7 LTHMP sampling locations for Project Dribble - near GZ E-24
E-8 LTHMP sampling locations for Project Dribble -
near Salt Dome E-25
E-9 LTHMP sampling locations for Project Faultless E-27
E-10 LTHMP sampling locations for Project Shoal E-28
E-ll LTHMP sampling locations for Project Gasbuggy E-30
E-12 LTHMP sampling locations for Project Gnome E-32
vm
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TABLES
Number Page
1 Total Airborne Radionuclide Emissions at the NTS During 1985. ... 9
2 Annual Average Krypton-85 Concentrations in Air, 1976-1985 20
3 Water Sampling Locations Where Samples Contained
Man-made Radioactivity - 1985 26
4 Network Annual Average Concentrations of Tritium
and Strontium-90 in Milk, 1975-1985 29
5 Radionuclide Concentrations in Desert Bighorn Sheep
Samples - 1984 33
6 Dosimetry Network Summary for the Years 1971-1985 38
7 Pressurized Ion Chamber Readings - pR/hour 40
Appendices
A-l Characteristics of Climatic Types in Nevada A-2
B-l Summary of Analytical Procedures B-l
C-l Samples and Analyses for Duplicate Sampling Program - 1985 C-l
C-2 Sampling and Analytical Precision - 1985 C-3
C-3 EPA Quality Assurance Intercomparison Results - 1985 C-4
C-4 Quality Assurance Results from Other Organizations C-6
C-5 Quality Assurance Results for the Bioenvironmental Program - 1985 . C-8
D-l Routine Monitoring Frequency, Sample Size, MDC and
Concentration Guides D-2
E-l Summary of Analytical Results for Air Surveillance
Network Continuously Operating Stations - 1985 E-l
E-2 Summary of Analytical Results for Air Surveillance Network
Standby Stations Operated 1 or 2 Weeks per Quarter - 1985. ... E-3
IX
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TABLES (Continued)
Number Page
E-3 Summary of Gross Beta Analyses for
Air Surveillance Network - 1985 E-4
E-4 Plutonium-239 Concentration in Composited
Air Samples - 1985 E-5
E-5 Summary of Analytical Results for the Noble Gas
and Tritium Surveillance Network - 1985 E-6
E-6 Summary of Tritium Results for the NTS Network
Long-Term Hydrological Monitoring Program - 1985 E-9
E-7 Tritium Results for the Long-term Hydrological
Monitoring Program - 1985 E-10
E-8 Summary of Analytical Results for the Milk
Surveillance Network - 1985 E-36'
E-9 Analytical Results for the Standby Milk Surveillance
Network - 1985 E-37
E-10 Summary of Radiation Dose Equivalents from
TLD Data - 1985 E-42
E-ll Summary of Radiation Doses for Off-Site Residents - 1985 .... E-45
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ABBREVIATIONS, SYMBOLS AND CONVERSIONS
ASN Air Surveillance Network
Bq Becquerel, one disintegration per second
CG Concentration Guide
Ci Curie
CP-1 Control Point One
CY Calendar Year
d day
DOE U.S. Department of Energy
DOE/NV Department of Energy, Nevada Operations Office
EMSL-LV Environmental Monitoring Systems Laboratory, Las Vegas
EPA U.S. Environmental Protection Agency
eV electron volt
g gram
Gy Gray, equivalent to 100 rad (1 J/kg)
GZ Ground Zero
h hour
HTO tritiated water
L liter
LTHMP Long-Term Hydrological Monitoring Program
m meter
MDC Minimum Detectable Concentration
MSL Mean Sea Level
MSN Milk Surveillance Network
NGTSN Noble Gas and Tritium Surveillance Network
NTS Nevada Test Site
Pa Pascal - unit of pressure
R Roentgen
rad unit of absorbed dose, 100 ergs/g
rem the rad adjusted for biological effect
Sv Si evert, equivalent to 100 rem
TLD thermoluminescent dosimeter
xi
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Multiply
PREFIXES
a atto = 10-18
f femto = 10-15
p pico = 10-12
n nano = 10-9
y micro = 10"6
m milli = 10-3
k kilo = 103
M Mega = 106
CONVERSIONS
By
To Obtain
Concentration Guides
yCi/mL
yCi/mL
SI Units
rad
rem
pCi
109
1012
10-2
10-2
0.037
pCi/L
pCi/rn-3
Gray (Gy = 1
Si evert (Sv)
Becquerel
xii
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SECTION 1
INTRODUCTION
The EMSL-LV operates an Off-Site Radiological Safety Program around the
NTS and other sites as requested by the Department of Energy (DOE) under an
Interagency Agreement between DOE and EPA. This report, prepared in accordance
with DOE guidelines (DOE85a), covers the program activities for calendar year
1985. It contains descriptions of pertinent features of the NTS and its en-
virons, summaries of the EMSL-LV dosimetry and sampling methods, analytical
procedures, quality assurance, and the analytical results from environmental
measurements. Where applicable, dosimetry and sampling data are compared to
appropriate guides for external and internal exposures of humans to ionizing
radiation.
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SECTION 2
SUMMARY
PURPOSE
It is U.S. Environmental Protection Agency (EPA) policy to protect the
general public and the environment from pollution caused by human activities.
This includes radioactive contamination of the biosphere and concomitant
radiation exposure of the population. To this end and in concordance with U.S.
Department of Energy (DOE) policy of keeping radiation exposure of the general
public as low as reasonably achievable, the EPA's Environmental Monitoring
Systems Laboratory in Las Vegas (EMSL-LV) conducts an Off-Site Radiological
Safety Program centered on the DOE's Nevada Test Site. This program is con-
ducted under an Interagency Agreement between EPA and DOE.
The principal activities of the Off-Site Radiological Safety Program are:
routine environmental monitoring for radioactive materials in various media and
for radiation in areas which may be affected by nuclear tests; and protective
actions in support of the nuclear testing program. These are conducted to
document compliance with standards, to identify trends, and to provide informa-
tion to the public. This report summarizes these activities for CY 1985.
Locations
Most of the radiological safety effort is applied in the areas around the
Nevada Test Site (NTS) in south-central Nevada. The principal activity at the
NTS is testing of nuclear devices, though other related projects are also con-
ducted. This portion of Nevada is sparsely settled, 0.5 person/km2, and has a
continental arid climate. The largest town in the near off-site area is Beatty,
located about 65 km west of the NTS with a population of about 900.
Underground tests have been conducted in several other States for various
purposes. At these sites in Alaska, Colorado, New Mexico, and Mississippi, a
long-term hydrological monitoring program is conducted to detect any possible
contamination of potable water and aquifers near these sites.
Special Test Support
During CY85, personnel were deployed in support of the 16 announced nu-
clear tests at the NTS. Only once was radioactivity detected off site. This
was during the planned ventilation of a tunnel following the Misty Rain test.
Xenon-133 was detected at an unpopulated location in a concentration which at
most would have led to a dose of 6 x 10'4 mrem (6 x 10~6) mSv); only 10% of
that dose would have been received by a resident at Rachel, NV.
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Pathways Monitoring
The pathways leading to human exposure to radionucTides, namely air, water,
and food, are monitored by networks of sampling stations. The networks are
designed not only to detect radiation from DOE/NV nuclear test areas but also
to detect increases in population exposure from other sources.
In 1985 the air surveillance network (ASN) consisted of 30 continuously
operating stations surrounding the NTS and 77 standby stations (operated 1 or 2
weeks each quarter) in all States west of the Mississippi River. Other than
naturally occurring beryllium-7, the only activity detected by this network was
plutonium-239 from worldwide fallout.
The noble gas and tritium sampling network (N6TSN) consisted of 17 sta-
tions off site (off the NTS and exclusion areas) in 1985. No NTS-related
radioactivity was detected at any off-site station by this network. Tritium
concentrations in air remained below MOC levels and krypton-85 concentration
continued the upward trend which started in 1960, reflecting the worldwide
increase in the use of nuclear technology.
The long-term hydrological monitoring of wells and surface waters near
sites of nuclear tests showed only background tritium and other radionuclide
concentrations except for those wells that had detectable activity in previous
years or those that had been spiked with radionuclides for hydrological tests.
The milk surveillance network consisted of 28 sampling locations within
300 km of the NTS and about 122 standby locations in the Western U.S. The
tritium concentration in milk was at background levels, and strontium-90 from
worldwide fallout continued the slow downward trend observed in recent years.
Other foods analyzed have been mainly meat from domestic or game animals
and garden vegetables. The radionuclide most frequently found in the edible
portion of the sampled animals is cesium-137. However, its concentration has
been near the MDC since 1968. Strontium-90 in samples of animal bone remain
at very low levels as does plutonium-239 in both bone and liver samples.
External Exposure
External exposure is monitored by a network of TLD's at 129 locations
surrounding the NTS and by TLD's worn by 53 off-site residents. In a few
cases, small exposures of a few mR above the average for the person were meas-
ured. Except for several occupational exposures, all such net exposures were
very low and were not related to NTS activities. The range of exposures meas-
ured, varying with altitude and soil constituents, is similar to the range of
such exposures found in other areas of the U.S.
Internal Exposure
Internal exposure is assessed by whole-body counting supplemented by
phoswich detectors to measure lung burdens of radioactivity. In 1985, counts
were made on 106 off-site residents, as well as on 260 other individuals for
occupational or other reasons. Natural potassium-40 was found as expected, but
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no nuclear test related radioactivity was detected. In addition, physical
examinations of the off-site residents revealed a normally healthy population
consonant with the age and sex distribution of that population.
Community Monitoring Stations
The 15 Community Monitoring Stations became operational in 1982. Each
station is operated by a resident of the community who is trained to collect
samples and interpret some of the data. Each station is an integral part of
the ASN, NGTSN and TLD networks and is also equipped with a pressurized ion
chamber system and recording barograph. Samples and data from the stations are
analyzed by EMSL-LV and are also interpreted and reported by the Desert Research
Institute, University of Nevada. Data from these stations are reported herein
as part of the networks in which they participate.
Dose Assessment
Doses were calculated for an average adult living in Nevada based on the
Kr-85, Sr-90, HTO and Pu-239 detected by the monitoring networks. Using con-
servative assumptions, the estimated dose would have been about 0.14 mrem/yr
(1.4 uSv/yr), a small fraction of the variation of 10 mrem/yr due to the natural
radionuclide content of the body. The only NTS-related radioactivity detected
during 1985 was xenon-133 picked up on a noble gas sampler placed at Rachel
during the tunnel ventilation following the Misty Rain test. The concentration
of 11 pCi/or for the 24-hour sample was not detectable on the normal noble gas
sampler. This concentration would have caused a dose of 0.06 yrem to a person
outdoors for the 24 hours. Otherwise, no radioactivity originating on the NTS
was detectable by the monitoring networks so no dose assessment could be made on
the reported emissions. However, atmospheric dispersion calculations, based on
those emissions, indicate that the highest individual dose would have been 40
nanorem (4 x IQ'AnSv) and the dose to the population with 80 km of CP-1 would
have been 2 x 10~4 person-rem (2 x 10~6 person-Sv).
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SECTION 3
DESCRIPTION OF THE NEVADA TEST SITE
Historically, the major programs conducted at the NTS have been nuclear
weapons development, proof-testing and weapons safety and effects, testing
peaceful uses of nuclear explosives (Plowshare Program), reactor engine devel-
opment for nuclear rocket and ramjet applications (Projects Rover and Pluto),
high-energy nuclear physics research, seismic studies (Vela Uniform), and
studies of high-level waste storage. During 1985, nuclear weapons development,
proof-testing and weapons safety, nuclear physics programs, and studies of high-
level waste storage were continued at the NTS. Project Pluto was discontinued
in 1964; Project Rover was terminated in January 1973; Plowshare tests were
terminated in 1970; Vela Uniform studies ceased in 1973. All nuclear weapons
tests since 1962 have been conducted underground. More detail and pertinent
maps for the portions of this section are included in Appendix A. Only selected
information is presented in this Section.
SITE LOCATION
The NTS is located in Nye County, Nevada, with its southeast corner about
90 km northwest of Las Vegas (Figure 1), It has an area of about 3,500 square
km and varies from 40 to 56 km in width (east-west) and from 64 to 88 km in
length (north-south). This area consists of large basins or flats about 900 to
1,200 m above mean sea level (MSL) surrounded by mountain ranges rising 1,800
to 2,300 m above MSL.
The NTS is surrounded on three sides by exclusion areas, collectively
named the Nell is Air Force Range, which provide a buffer zone between the test
areas and public lands. This buffer zone varies from 24 to 104 km between the
test area and land that is open to the public. Depending upon wind speed and
direction at the time of testing, from 2 to more than 6 hours will elapse
before any release of airborne radioactivity could pass over public lands.
CLIMATE
The climate of the NTS and surrounding area is variable, due to its 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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Scale in Miles
50 100
0 50 100 150 200
3/86 Scale in Kilometers
Figure 1. Location of the Nevada Test Site (NTS).
6
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As Houghton et al. (Ho75) point out, 90 percent of Nevada's population
lives in areas with less than 25 cm of rainfall per year or in areas that would
be classified as mid-latitude steppe to low-latitude desert regions.
The wind direction, as measured on a 30 m tower at an observation station
about 9 km NNW of Yucca Lake near CP-1, is predominantly northerly except
during May through August when winds from the south-southwest predominate
(Qu68). Because of the prevalent mountain/valley winds in the basins, south to
southwest winds predominate during daylight hours of most months. During the
winter months southerly winds have only a slight edge over northerly winds for
a few hours during the warmest part of the day. These wind patterns are often
quite different at other locations on the NTS because of local terrain effects
and differences in elevation.
GEOLOGY AND HYDROLOGY
Geological and hydrological studies of the NTS have been in progress by
the U.S. Geological Survey and various other organizations since 1956. Because
of this continuing effort, the surface and underground geological and hydro-
logical characteristics for much of the NTS are known in considerable detail
(see Figure A-l). This is particularly true for those areas in which under-
ground experiments are conducted. A comprehensive summary of the geology and
hydrology of the NTS was published in 1975 (Wi75).
The aquifers underlying the NTS vary in depths from about 200 m beneath
the surface of valleys in the southeastern part of the site to more than 500 m
beneath the surface of highlands to the north. Although much of the valley
fill is saturated, downward movement of water is retarded by various tuffs and
is extremely slow. The primary aquifer in these formations consists of
Paleozoic carbonates that underlie the more recent tuffs and alluviums.
LAND USE OF NTS ENVIRONS
Industry within the immediate off-NTS area includes approximately 40
active mines and mills, oil fields in the Railroad Valley area, and several
industrial plants in Henderson, Nevada. The number of employees for these
operations may vary from one person at several of the small mines to several
hundred workers for the oil fields north of the NTS and the industrial plants
in Henderson. Most of the individual mining operations involve less than 10
workers per mine; however, a few operations employ 100 to 250 workers.
The major body of water close to the NTS is Lake Mead (120 km southeast,
Figure A-2), a manmade lake supplied by water from the Colorado River. Lake
Mead supplies about 60 percent of the water used for domestic, recreational,
and industrial purposes in the Las Vegas Valley. Some Lake Mead water is used
in Arizona, southern California, and Mexico. Smaller reservoirs and lakes
located in the area are used primarily for irrigation, for watering livestock,
and for wildlife refuges.
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Dairy farming is not extensive within 300 km of the NTS. As shown in
Figures A-4 and A-5 the family cows and goats are distributed in all direc-
tions around the NTS, whereas most dairy cows are located to the southeast
(along the Muddy and Virgin River valleys and in Las Vegas, Nevada), northeast
(Lund), and southwest (near Barstow, California).
Grazing is the most common land use within 300 km of the site. Approxi-
mately 500,000 cattle and 150,000 sheep are distributed within the area as
shown in Figures A-6 and A-7, respectively. The estimates are based on infor-
mation supplied by the California Crop and Livestock reporting service (CA85),
from 1985 agricultural statistics supplied by the Nevada Department of Agri-
culture (NV86) and 1985 estimates based on 1982 census information supplied by
the Utah Department of Agriculture (UT82).
POPULATION DISTRIBUTION
Excluding Clark County, the major population center (approximately 536,000
in 1984), the population density within a 150 km radius of CP-1 on the NTS is
about 0.5 persons per square kilometer. For comparison, the 48 contiguous
states (1980 census) had a population density of approximately 29 persons per
square kilometer. The estimated average population density for all of Nevada
in 1980 was 2.8 persons per square kilometer.
The off-site area within 80 km of the NTS (the area in which the dose
commitment must be determined for the purpose of this report) is predominantly
rural, Figure A-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 5,500, is located about 72 km south of the NTS
CP-1. The Amargosa Farm Area, which has a population of about 1,200, is located
about 50 km southwest of CP-1. The largest town in the near off-site area is
Beatty, which has a population of about 900 and is located approximately 65 km
to the west of CP-1.
AIRBORNE RELEASES OF RADIOACTIVITY AT THE NTS DURING 1985
All nuclear detonations during 1985 were conducted underground and were
contained, although occasional releases of low-level radioactivity occurred
during re-entry drilling, seepage through fissures in the soil or ventilation
of tunnel areas. Table 1 shows the total quantities of radionuclides released
to the atmosphere, as reported by the DOE Nevada Operations Office (DOE86).
Because these releases occurred throughout the year, and because of the dis-
tance from the points of releases to the nearest sampling station, in only one
instance was radioactive material listed in this table detected off site.
8
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TABLE 1. TOTAL AIRBORNE RADIONUCLIDE EMISSIONS
AT THE NTS DURING 1985
Radionuclide
Tritium
Argon-37
Krypton-85
Xenon-133
Xenon-133m
Xenon-135
Iodine-131
Iodine-133
Iodine-135
Half -Life
(days)
4,500
35.1
3,920
5.24
2.2
0.38
8.07
0.87
0.28
Quantity Released
(Ci)
116
9.0
17
734.9
8.3
28.9
0.007
0.042
0.042
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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 analysis of environmental samples with the highest degree of
accuracy and precision obtainable with state-of-the-art instrumentation and to
achieve the best possible completeness and comparability given the extent and
type of networks from which samples are collected. To meet these goals, it is
necessary to devote strict attention to sample collection, sample analysis,
and quality assurance procedures.
SAMPLE COLLECTION
The collection of samples is governed by a detailed set of Standard Opera-
ting Procedures (SOP's). These SOP's prescribe the frequency and method of
collection, the type of collection media, sample containment and transport,
sample preservation, sample identification and labeling, and operating param-
eters for the instrumentation. Sample control is an important segment of these
activities as it enables tracking from collection to analysis for each sample
and governs the selection of duplicate samples for analysis and the samples
chosen for replicate analysis.
These procedures provide assurance that sample collection, labeling and
handling are standardized to minimize sample variability due to inconsistency
among these variables.
individual Quality Assur
plans assure that the
be comparable to results
Plans are summarized in
SAMPLE ANALYSIS
All of the networks operated by the EMSL-LV have
ance Project Plans. The procedures required by these
results of analysis will be of known quality and will
obtained elsewhere with equivalent procedures. These
the following sections.
External QA
External QA provides the data from which the accuracy of analysis (a com-
bination of bias and precision) can be determined. Bias is assessed from the
results obtained on intercomparison study samples and on samples "spiked" with
known amounts of radionuclides. The Off-Site Radiological Safety Program
10
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participates in Intercomparison Study Programs that include environmental
sample analysis, TLD dosimetry, and whole-body counting. Also, samples which
are undisclosed to the analyst are spiked by adding known amounts of radio-
nuclides and then entered into the normal chain of analysis.
Data for precision are collected from duplicate and replicate analyses.
At least 10 percent of all samples are collected in duplicate. When analyzed,
the data indicate the precision of both sample collection and analysis. Repli-
cate counting of at least 10 percent of all samples yield data from which the
precision of counting can be determined.
If the bias and precision data are of sufficient quality (i.e., normalized
deviation in Table C-3 is less than 3), then comparability, i.e., comparison of
the data with those of other analytical laboratories, can be assessed 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 nuclides
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 is not contaminated, that
calibration is correct, and that standards carried through the total analytical
procedure are accurately analyzed.
VALIDATION
After the results are produced, supervisory personnel examine the data to
determine whether or not the analysis is valid. This includes checking all
procedures from sample receipt to analytical result with particular attention
to the internal QA data and comparison of the results with previous data from
similar samples at the same location.
Any variant result or failure to follow internal QA procedures during
sample analysis will trigger an internal audit of the analytical procedures
and/or a re-analysis of the sample or its duplicate.
AUDITS
All analytical data are reviewed by personnel of the Dose Assessment
Branch for completeness and consistency. Investigations are conducted to
11
-------
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 which
includes pathways monitoring and internal and external exposure monitoring.
Both of these activities are designed to detect any increase in environmental
radiation which might cause exposure to individuals or population groups so
that protective actions may be taken, to the extent feasible. These activities
are described in the following portions of this report.
SPECIAL TEST SUPPORT
Before each nuclear test, mobile monitoring personnel are positioned in
the off-site areas most likely to be affected should a release of radioactive
material occur. They ascertain the locations of residents, work crews and
animal herds and obtain information relative to controllability of residents
in communities and remote areas. These monitors, equipped with radiation
survey instruments, gamma exposure-rate recorders, thermoluminescent dosimeters
(TLD's), portable air samplers, and supplies for collecting environmental
samples, are prepared to conduct a monitoring program as directed from the NTS
Control Point (CP-1) via two-way radio communications.
For those tests which might cause ground motion detectable off site, EPA
monitors are stationed at locations where hazardous situations might ensue. At
these locations, 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 always flown over the NTS
to obtain samples, assess total cloud volume, and provide long-range tracking
in the event of a release of airborne radioactivity. A second aircraft is also
flown to gather meteorological data and to perform cloud tracking. Information
from these aircraft can be used in positioning the radiation monitors.
During CY 1985, EMSL personnel were deployed in support of the 16 announced
underground tests, none of which accidently released radioactivity which could
be detected off site. However, following the Misty Rain event, conducted on
April 6, radioactivity was detected in the tunnel leading to the test point
13
-------
although containment measures prevented escape of the radioactivity to the
atmosphere. To gain entry to the tunnel and the instrumentation contained
therein, the tunnel was ventilated and the escaping gas passed through high
efficiency and charcoal filters. To monitor this activity, special compressed
gas samplers were placed at six locations off the NTS. The locations were
Rachel, Hiko, Tempiute, Medlin's Ranch, Reed Ranch and Lathrop Wells. The
sampler at Reed Ranch detected xenon-133 at a concentration of 47 ± 10 pCi/m3
and at Rachel 11 ± 5 pCi/m3. If the concentration of 47 pCi/m3 (1.7 Bq/m3)
had been maintained for the full week of the ventilating period, and someone
had been livigg at that location, the dose would have amounted to 6 x 10~4
mrem (6 x 10"° mSv) to the skin or about equivalent to 5 minutes exposure to
background at that location. The dose at Rachel is calculated in Section 5.
None of the other samplers detected noble gases above the background values.
Also, none of the noble gas samplers in the routine sampling network detected
any of the radioactive xenon released during this tunnel ventilation.
PATHWAYS MONITORING
The off-site radiation monitoring program includes a pathways monitoring
system consisting of air, water and milk surveillance networks surrounding the
NTS and a limited animal sampling project. These are explained in detail
below.
Air Surveillance Network (ASN)
Network Design—
The ASN monitors an important route of human exposure to radionuclides:
inhalation of airborne materials. The concentration and the source must both
be determined if appropriate corrective actions are to be taken. The ASN is
designed to cover the areas within 350 km of the NTS with some concentration of
stations in the prevailing downwind direction (Figure 2). The coverage is con-
strained to those locations having available 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 1985 the ASN consisted of 30 continuously operating sampling sta-
tions and 77 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
m3). Activated charcoal cartridges placed directly behind the filters to
collect gaseous radioiodine were changed at the same time as the filters. The
standby network was activated for 1 to 2 weeks per quarter at most locations.
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.
14
-------
Ely
Stone Cabin Rn.
Tonopah •
Goldfield
•
•TTR
9 • Sunnyside
Blue Eagle Rn.
• Nyala
Twin Springs Rn.
Salt Lake City
CD
Delta i
i Milford
Pioche
Scotty's Jet.
\«
Beat?« r«
\ Site
Lathrop Wells*
Furnace Creek* Pahrump
Death Valley Jet. •
Shoshone
Rachel
• Hiko
• Alamo
Groom
Lake
• Indian
Springs
I
• Cedar City |
I
i St. George
Arizona
• Community Monitoring Stations (15)
• Other Locations (15)
12/85
Pverton
I
Lake Mead
Figure 2. Air Surveillance Network stations (1985).
15
-------
\
North Dakota \ Minnesota
M /
South Dakota
A / ^^^^^^*
California/ Nevada
f A A
Ari«ona I NewMexico
\ J
Scale in Miles
100 300 500 700
Scale in Kilometers
Stand-by ASN Station
12/85
Figure 3. Standby Air Surveillance Network stations (1985).
16
-------
Results—
During 1985, no airborne radioactivity related to nuclear testing at the
NTS was detected on any sample from the ASN. Throughout the network,
beryllium-7 was the only nuclide detected by gamma spectroscopy. The principal
means of beryllium-7 production is from spallation of oxygen-16 and nitrogen-14
in the atmosphere by cosmic rays. Appendix Tables E-l and E-2, summarize the
data from the ASN samples. All time-weighted averages (Avg in the tables) are
less than 1 percent of the Concentration Guide (Appendix D) for exposure to the
general public, however, these guides do not apply to naturally occurring
radionuclides.
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 15 states. The results from the
plutonium-239 analyses are shown in Appendix Table E-4; plutonium-238 results
were
-------
KA
CO
E
o
a
<
•S 10'2H
0
0)
m
8
2
o
10
'3
..
• •
,-
1981
1982
1983
1984
1985
Figure 4. Monthly average gross beta in air samples, 1981-85.
For tritium sampling, a molecular sieve column is used to collect water
from air after it passes through a particulate filter. Up to 10 m3 of air are
passed through the column over a 7-day sampling period. Water adsorbed on
the molecular sieve is recovered, and the concentration of tritium in the water
(HTO) is determined by liquid scintillation counting techniques (see Appendix
B).
Results—
The results from the samples collected by the NGTSN are shown in the
Appendix (Table E-5) as the maximum, minimum and average concentration for each
station. The average krypton-85 concentration per station ranged from 29 to
31 pCi/m3. The concentration over the whole network appeared to have a normal
distribution with a mean of 29.4 pCi/m3 (1.1 Bq/m3) and a standard deviation
of 3.2. The weekly averages for the network are shown in Figure 6. This network
average concentration, as shown in Table 2 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., (Be73). However, the measured network average in 1985 is only
about 13% percent of the 250 pCi/m3 (9 Bq/m3) predicted by Bernhardt. Since nu-
clear fuel reprocessing is the primary source of krypton-85, the decision of the
18
-------
Ely I
12/85
Salt Lake City
| Cedar City
St. George
Arizona
Indian • Overton
Springs A |
Lake Mead
Figure 5. Noble Gas and Tritium Surveillance Network sampling locations,
19
-------
TABLE 2. ANNUAL AVERAGE KRYPTON-85 CONCENTRATIONS IN AIR, 1976-1985
Kr-85 Concentrations
oamy i i ny
Locations
Alamo, NV
Austin, NV
Beatty, NV
Diablo and
Rachel, NV**
Ely, NV
Goldfield, NV*
Hiko, NV*
Indian Springs,
NV
NTS, Mercury, NV*
NTS, Area 51, NV*
NTS, BJY, NV*
NTS, Area 12, NV*
Tonopah, NV
Las Vegas, NV
Death Valley Oct.,
CA*
NTS, Area 15, NV*
NTS, Area 400, NV*
Lathrop Wells, NV
Pahrump, NV
Overton, Nev.
Cedar City, Ut.
St. George, Ut.
Salt Lake City, Ut.
Shoshone, CA
1976
._
—
20
19
__
—
17
20
19
20
20
20
19
18
20
—
__
—
_.
—
._
—
__
—
1977
„
—
20
19
__
—
19
20
20
19
21
19
19
20
20
--
__
--
__
—
__
--
__
--
1978
..
—
20
20
M _
—
20
20
20
20
22
20
20
20
20
—
__
—
__
--
__
--
__
—
1979
„
—
19
19
.»_
--
19
19
19
19
21
19
18
--
19
19
18
19
__
~
__
--
__
—
1980
—
21
21
MM
—
21
21
21
21
23
21
21
--
__
21
21
22
-..
--
__
--
__
—
1981
27
—
24
24
• •
—
24
24
23
24
26
24
25
24
__
25
23
24
23
26
__
--
_.
--
1982
24
24
25
26
24
25
26
24
_—
--
__
--
24
24
-_
—
__
24
24
24
25
24
25
25
1983
25
25
24
24
25
24
_„
25
__
—
__
--
25
24
__
—
__
26
24
25
24
25
25
25
1984
28
27
26
26
26
28
— _
25
— —
—
__
-- .
26
27
__
—
..
26
27
26
26
26
29
26
1985
29
30
30
30
29
30
__
29
— ^
—
_w
,
30
30
__
--
__
29
30
29
29
29
30
29
NETWORK AVERAGE 19 20 20 19 21 24 24 25 27 29
==========================================================
*Stations discontinued
**Station at Diablo was moved to Rachel in March 1979.
20
-------
—
^•^"* "^
5 1B2'BI8182BIB 162s's 1B2B's 162s's ISZE's 1B2BIB ISZB's IS 26* 5 ISz'fi's 1B25'8 1B2S1
Jan Fob Mar Apr May Jun Jul Aug Sept Oct Nov Dec
1985
Figure 6. Weekly average krypton-85 concentration in air, 1985 data,
Least Squares: pCi/m3= 5.0 + 0.87t
R= 0.983
1960 1965 1970 1975 1980 1985 1990
Time - Calendar Years
Figure 7. Trend in annual average krypton-85 concentration,
21
-------
United States to defer fuel reprocessing may be one reason why krypton-85 levels
have not increased as fast as predicted.
Using published data for krypton-85 concentration in air (NCRP75) and the
data from our network (Table 2), the change over time was plotted as shown in
Figure 7. Linear correlation analysis indicates that the krypton concentration/
time relation is pCi/m3 = 5.0 + 0.87t where t is number of years after 1960. The
correlation coefficient, R, is 0.983.
As in the past, tritium concentrations in atmospheric moisture samples from
the off-NTS stations were generally below the minimum detectable concentration
(MDC) of about 400 pCi/L water (Appendix Table E-5). The tritium concentrations
observed at off-NTS stations were considered to be representative of environ-
mental background. The mean of the tritium concentrations for all off-site
stations was 0.43 pCi/m^ (16 m Bq/m^) of air. Only six of the 857 collected
samples were above the MDC.
Long-Term Hydro!ogical Monitoring Program
Network Design—
A major pathway for the transport of radionuclides to individuals is via
potable water. This program monitors possible radioactive contamination of
potable water sources. The design is for a system to monitor the aquifers
underlying, and surface waters on or near, sites where nuclear explosions have
occurred. For aquifers, monitoring is limited by the availability of wells
that tap those sources. For the sites considered herein, a suitable number of
wells is present so that sufficient monitoring data are obtained.
The monitored locations for the NTS and nearby off-site areas are shown in
Figures 8 and 9. For Projects Cannikin, Longshot and Milrow in Alaska; for
Projects Rio Blanco and Rulison in Colorado; for Project Dribble in Mississippi;
for Projects Faultless and Shoal in Nevada; and for Projects Gasbuggy and Gnome
in New Mexico, the sampling locations are shown in Figures E-l through E-12 in
Appendix E.
Methods—
At each sampling location, four samples are collected. Two samples are
collected in 500-mL glass bottles; one is used for tritium analysis and the
other stored for use as a duplicate sample or to replace the original sample if
it is lost in analysis. Two 3.5-L samples are filtered through 10 cm diameter
membrane filters into cubitainers and acidified with HN03. One sample and the
filter are gamma-scanned, the other sample is stored for duplicate analysis or
for reanalysis as required.
Beginning in July 1984, this procedure was modified for the locations around
the NTS which had been sampled semi-annually and annually. At these locations,
the sampling frequency was changed to monthly and the above sampling procedure
was used only twice a year. During the other months, only a 3.5-L sample was
collected for analysis by gamma spectrometry.
22
-------
r ^K^^"I *»«juoii
\weii\ \7
\~1VI z
4\ / Test Well D
Figure 8. LTHMP sampling locations on the NTS.
23
-------
Twin Springs Rn •
• Tonopah
• TTR wen #6
Nellis
^? Air Force
.1 Range
X v
\. •Tolicha \
X Peak \
Road D Well •S >
— s_
Tn
Springdale. "X,
\. Goss Springs • ^[jCof
^ v Beatty £ 1 1 J
|
1
c
(
12
V^ US Ecology
N IT^
Lathrop Wells
N
V
• Nvala
• Adaven Springs
L-i
• Penoyer
—
^^
Nevada
Test Site
er's
5/48-1dd
NRDS Mercury
• v_n ^ i
• Hiko
• Crystal Springs
• Alamo
_ ^Indian Springs
•Fairbanks Springs Sewer Co Well #1
Well 17S/50E-14CAC«_
V. •Crystal Pool
Well 18S/51E-
Death Valley Jet
Scale in Miles
) 10 20 30 4(
pL, rH 'rn '
i i i i i i
) 10 20 30 40 50 60
/85 Scale m Kilometers
7db^ *Ash Meadows
^^^
• V^
Ny^ •Calvada Well #3
^X
^V Nevad
^Shoshone ^
3 w Spring ^ \^
Nevada Test Site &B|
Nellis Air Force Range^
Location Map
• Las Vegas
Well #28
Intake
3
k
\T
Figure 9. LTHMP sampling locations near the NTS.
24
-------
The tritium and gamma spectrometric analyses are described in Appendix B.
If the tritium concentration detected by the conventional analysis is less than
700 pCi/L (26 Bq/L) then the sample is reanalyzed using the enrichment method.
Results-
Table 3 lists the locations at which water samples were found to contain
man-made radioactivity. Radioactivity in samples collected at most of these
locations has been reported in previous years, the data for all samples ana-
lyzed are compiled in Appendix Tables E-6 and E-7 together with the percent of
the relevant concentration guide listed in Appendix D. Radiochemical analyses
of water samples from 10 new stations indicate only normal concentrations of
uranium and radium.
None of the radionuclide concentrations found at the locations listed in
Table 3 are expected to result in measurable radiation exposures to residents
in the areas where the samples were collected. Well UE7NS and Test Well B are
located on the NTS, and are not used as sources of domestic water.
USGS Wells 4 and 8, which were contaminated with the reported nuclides
during tracer studies years ago, are on private land at the Project Gnome site
in New Mexico and are closed and locked to prevent their use. Well LRL-7 was
used for the disposal of contaminated soil and salt so this well is expected to
produce contaminated water.
The Project Dribble wells in Mississippi are about 1 mile from the nearest
residence and are not sources of drinking water.
The shallow wells at the Project Long Shot site on Amchitka Island in
Alaska are in an isolated location and are not sources of drinking water.
Milk Surveillance Network (MSN)
Network Design—
An important pathway for transport of radionuclides to humans is the air-
forage-cow-milk chain. This pathway is monitored by EMSL-LV through analysis
of milk. The design of the network is based on collections from areas likely
to be affected by accidental releases from the NTS as well as from areas un-
likely to be so affected. Additional considerations are: 1) a complete ring
of stations to cover any eventuality, and 2) samples from major milksheds as
well as from family cows. The availability of milk cows or goats sometimes
restricts sample collection in certain areas.
Methods—
The network consists of two major portions, the MSN at locations within
300 km of the NTS from which samples are collected monthly (Figure 10) and the
standby network (SMSN) at locations in all major milksheds west of the Miss-
issippi River (Figure 11) from which samples are collected annually. One
exception to the latter portion of the network is Texas; the State Health
Department performs the surveillance of the milksheds in that State.
The monthly raw milk samples are collected by EPA monitors in 4-liter
plastic containers (cubitainers) and preserved with formaldehyde. The annual
25
-------
TABLE 3. WATER SAMPLING LOCATIONS WHERE SAMPLES CONTAINED MAN-MADE
RADIOACTIVITY - 1985
Sampling Location
Type of
Radioactivity
Concentration
(pCi/L)
NTS, NV
Test Well B
Well UE7NS
PROJECT GNOME, NM
USGS Well 4
USGS Well 8
Well LRL-7
PROJECT DRIBBLE, MS
Well HMH-1 through 11
Well HM-S
Well HM-L
REECo Pit Drainage-B
REECo Pit Drainage-C
Half Moon Creek Overflow
PROJECT LONG SHOT, AK
Well EPA-1
Well WL-2
Well GZ, No. 1
Well GZ, No. 2
Mud Pit No. 1
Mud Pit No. 2
Mud Pit No. 3
Stream East of Long Shot
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Cesium-137
Hydrogen-3
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
Hydrogen-3
Hydrogen-3
140-170
2000-3100
260,000
190,000
58
17,000
210
0-35,000
16,000
1,600
2,500
1,600
350
320
240
2,800
170
380
540
500
130
26
-------
• Winnemucca
• Walls
• Elko
Larsen Rn I
• McGill
• Reno
I Austin
I Young Rn.
• Ely
Burdick Rn.
Lemon Rn.
Dyer
Round Mtn. _
Berg Rn. •
Warm Springs •
Twin Spgs. Rn.l
Frayn. Re..*T°nOpah
Manzonia Rn
Currant •
• • Harbecke Rn.
• Shoshone
Lund |
McKenzie Dairy
| Blue Eagle Rn.
.Nyala
1 Sharp's Rn.
Rache,
I June Cox
Caliente
10
Whipple Rn.
Lathrop Wells*
John Deer41 Indian Spgs. Decade Corp
Rn.
Cedar City
Western
General Dairy
•St. George
Gentry Dairy
LDS Dairy Farm
Scale in Miles
50
100
50 100 150
Scale in Kilometers
i Ridgecrest
Cedarsage Farm
• Milk Sampling Locations
NOTE: When sampling location occured '
in chy or town, the sampling location
symbol was used for showing both town
and sampling location
Mesquite
SF and K Dairy
Knudsen Corp
Logandale
|« Barstow
Bill Nelson Dairy
Hinkley
12/85
Figure 10. Milk sampling locations within 300 km of the NTS.
27
-------
Figure 11. Standby milk surveillance network stations.
28
-------
milk samples are also collected in cubitainers and preserved with formaldehyde
but they are collected by contacting State Food and Drug Administration Repre-
sentatives, after notification of the Regional EPA offices, who arrange for the
samples to be mailed to EMSL-LV.
All the milk samples are analyzed first for gamma-emitting nuclides by
high-resolution gamma spectrometry and periodically for strontium-89 and
strontium-90 by the methods outlined in Appendix B, after a portion of milk
is set aside for tritium analysis. Occasionally a milk sample will sour, thus
preventing its passage through the ion exchange column and its subsequent
strontium analysis; however, the other analyses can generally be performed
satisfactorily. For the SMSN, two locations in each State are selected for
tritium and strontium analyses.
Results—
The analytical results from the 1985 MSN samples are summarized in Appen-
dix Table E-8 where the maximum, minimum, and average concentrations of tritium,
strontium-89 and strontium-90 are shown for each sampling location. As shown in
Table 4, the average concentrations of tritium and strontium-90 for the whole
network are similar to the network averages for previous years. The results
obtained from the standby network are listed in Table E-9.
TABLE 4. NETWORK ANNUAL AVERAGE CONCENTRATIONS OF
TRITIUM AND STRONTIUM-90 IN MILK, 1975-1985
Average Concentrations - pCi/L
Year H-3 Sr-90
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<3
<2
<2
1.2
<3
<2
1.9
1.2
0.8
0.5
0.7
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
29
-------
the Pasteurized Milk Network shown in Figure 12. The consistently higher
results from New Orleans reflect the higher rainfall in that area. That net-
work is operated by the Eastern Environmental Radiation Facility in Montogmery,
Alabama.
Biomonitoring Program
Objective—
The pathways for transport of radionuclides to man include air, water, and
food. Monitoring of air, water, and milk are discussed above. Meat is a food
component that may be a potential route of exposure to off-site residents.
Methods-
Samples of muscle, lung, liver, kidney, blood, and bone are collected
periodically from cattle purchased from 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 desert bighorn sheep collected throughout southern Nevada (see
Figure 13) are donated by licensed hunters and are analyzed. These kinds of
samples have been collected and analyzed for up to 28 years to determine long
term trends.
A New Orleans
• Salt Lake City
• Las Vegas
1960
1965
1970
197S
1980
1985
Figure 12. Strontium-90 concentration in Pasteurized Milk Network samples,
30
-------
8
Goldfield
Q.C. Smt.
Tempiute
Coyote Smt.^
Hancock Smt
Nellis
Air Force
Range
V Beatty
IB)Range (20
Lathrop
Wells
DeatlM X
Cactus
Springs
Furnace
Creek
Valley Jet.
Shoshone v
>
Ridgecrest
Indicates collection site of
Searchlight
individual animal
Figure 13. Collection sites for bighorn sheep samples.
31
-------
Results--
Analytical data from bones and kidneys collected from desert bighorn sheep
during the late Fall of 1984 are presented in Table 5. Tritium and gamma-
emitting radionuclides, other than the naturally occurring potassium-40, were
not detected in any of the kidneys. Strontium-90 levels in the bones (average
1.6 pCi/g ash, 59 Bq/kg) are consistent with the reports in recent years
(Figure 14). Counting errors exceeded the reported concentrations of plutonium-
238 in all samples of bone ash. Plutonium-239 concentrations in the ash ranged
from -1.1 to 31 fCi/g, however, only the latter value significantly exceeded
the counting error.
Eight beef cattle were sampled during 1985; four from the Orin Nash ranch
collected in May, and four from the Jay Wright ranch collected in October. The
only gamma-emitting radionuclide detected in soft tissue was naturally occurr-
ing potassium-40. Tritium was not detected in any of the blood, samples. The
bone samples from the cattle sampled in October 1984 have been analyzed as well
as those from the cattle sampled in May 1985. The results are: Pu-239 concen-
tration ranged from 4 to 41, average 23 fCi/g ash (0.8 Bq/kg) for the October
samples and only one positive result, 1.9 fCi/g ash, for the May samples. The
Sr-90 ranged from 1.4 to 1.9, average 1.7 pCi/g ash (63 Bq/kg) for the October
samples and ranged from 1.6 to 2.2, pCi/g ash, average 2.0, pCi/g ash, for the
May samples. Plutonium-238 and strontium-89 were not detectable in any sample.
Of the soft tissue samples, only liver samples from the October 1984 col-
lection contained detectable activity. The concentration of plutonium-239 in
those four samples ranged from 3.2 to 7.8, median of 3.6 fCi/kg (0.13 mBq/kg).
No samples were collected from mule deer, however, Giles' study of mule deer
migration on the NTS was published this year (Gi85).
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 thermo-
1uminescent dosimeters (TLD) gradually replaced film as the measurement instru-
ment 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.
Network Design—
The TLD network is designed to measure environmental radiation exposure
at a location rather than to an individual because of the many uncertainties
associated with personnel monitoring. However, several individuals, some
residing within and some residing outside of estimated fallout zones from past
nuclear tests at the NTS, have been monitored so that any correlations that may
exist between personnel and environmental monitoring could be obtained. The
network consists of 129 monitored locations encircling the NTS with some con-
centration in the area of the estimated fallout zones (Figure 15). This
32
-------
TABLE 5. RADIONUCLIDE CONCENTRATIONS IN DESERT BIGHORN SHEEP SAMPLES - 1984
Bighorn
Sheep Bone
(Collected 90 Sr
Winter 1984) (pCi/g Ash)
1 0.6
2 2.0
3 1.1
4 1.3
5 1.5
6 1.5
7 1.2
8 1.8
9 3.2
10 2.3
11 1.1
12 0.8
13 2.7
14 0.9
± 0.
± 0.
± 0.
± 0.
± 0.
± 0.
± 0.
± 0.
± 0.
± 0.
± 0.
± 0.
1
1
1
1
1
1
1
1
4
1
1
1
± 0.1
± 0.1
Bone
238 Pu
(fCi/g Ash)
1.
1.
0.
-0.
-0.
0.
2.
2.
0.
0.
-5.
0 ±
3 ±
6 ±
3 ±
8 ±
9 ±
4 ±
4 ±
0 ±
5 ±
4 ±
2.1 ±
0.0 ±
0.3 ±
4.0**
3.4**
3.5**
0.3**
3.4**
4.0**
3.7**
5.7**
4.8**
5.3**
60**
7.8**
4.6**
3.4**
Bone
239 Pu
(fCi/g Ash)
1.
1.
-0.
0.
-1.
-0.
0.
6.
0.
4.
1.
0.
31.
1.
3
0
6
9
1
3
4
1
5
4
6
0
0
2
± 7.2**
± 2.2**
± 1.4**
± 2.1**
± 2**
± 1.9**
± 2.8**
± 5.0
± 3.8**
± 4.2
± 3.9**
± 4.2**
± 16.0
± 2.2**
Kidney
K(g/kg)*
4.5
60
9.2
110
7.6
40
2.7
20
3.3
20
8.5
140
4.4
450
4.4
250
5.2
-160
4.5
-180
7.0
-270
3.7
-120
6.7
40
3.7
60
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
±
0.9
450
1.5
450
0.9
450
0.8
450
0.6
450
1.0
450
0.5
450
0.5
450
0.6
450
0.6
450
0.8
450
1.2
450-
0.8
450
0.5
450
(continued)
33
-------
TABLE 5. Continued
Bighorn
Sheep Bone
(Collected 90 Sr
Winter 1984) (pCi/g Ash)
15
16
17
18
19
20
21
22
23
24
Median
3
.2 ±
2.3 ±
1
1
1
1
1
1
1
0
1
.9 ±
.2 ±
.4 ±
.1 ±
.2 ±
.1 ±
.4 ±
.9 ±
.26
0.1
0.1
0.1
0.1
0.1
0.1
0.1
0.1
0.1
0.1
Bone
238 Pu
(fCi/g Ash)
2.
0.
-1.
1.
0.
2.
1.
2.
0.
-0.
0.
3 ±
9 ±
2 ±
5 ±
5 ±
2 ±
2 ±
8 ±
8 ±
5 ±
9
6.
4.
3.
4.
3.
4.
3.
4.
3.
3.
0**
6**
5**
g**
2**
6**
6**
3**
4**
3**
Bone
239 Pu
(fCi/g Ash)
1.1
4.1
2.7
4.6
1.0
2.2
2.7
2.1
0.6
-2.0
1.2
± 4.6**
± 3.8
± 2.9**
± 4.1
± 1.9**
± 2.8**
± 2.5
± 2.9**
± 1.8**
± 4.5**
Kidney
K(g/kg)*
3H(pCi/l)*
7.8 ±
20 ±
3.6 ±
-40 ±
5.8 ±
60 ±
4.9 ±
140 ±
5.4 ±
-120 ±
5.0 ±
-110 ±
NS
NS
NS
NS
4.
0.9
450
0.6
450
0.8
450
0.7
450
0.7
450
0.6
450
9
30
Range
0.
32 -
3.2
-5.
,4 -
2.
,8
-1.1
- 3.1
2.7 -
-270 -
9.2
450
* Wet weight. -
** Counting error exceeds reported activity,
t Aqueous portion of kidney tissue.
NS not sampled.
34
-------
30-i
v>
m 25
o»
§"E
-° 2 ««
.£ o 20
J2 5
o> a.
S g IS-
C' 'i
7 1
i S 10
o
*»
CO
5-
11
6
5
12
20
14
14
1417
lit 123
4 6
Bighorn sheep
Deer
Cattle
Numbers at top of columns indicate
the number of bone samples in each
category. Numbers prior to 1964
are unknown
13
18
13
121213
14]ih24
56 58 60 62 64 66 68 70 72 74 76 78 80 82 84
3 16«0
3 1718
144 2
2310
4 24
Year (1956-1985)
Figure 14. Average strontium-90 concentration in animal bone.
arrangement permits an estimate of average background exposure; yet any in-
crease due to NTS activities can be detected.
Methods—
In 1985 the TLD Network consisted of 129 stations at both inhabited and
uninhabited locations within a 500-km radius of the CP-1. Each station is
equipped with three Harshaw TLD's to measure gamma exposures resulting from
environmental background as well as accidental releases of gamma-emitting
radioactivity. Within the area covered by the Network, 52 off-site residents
wore dosimeters during 1985. All environmental TLD's were exchanged quarterly,
and all personnel TLD's were exchanged monthly.
The Harshaw Model 2271-G2 (TLD-200) dosimeter consists of two small "chips"
of dysprosium-activated calcium fluoride mounted in a window of Teflon plastic
attached to a small aluminum card. An energy compensation shield of 1.2-mm
thick cadmium metal is placed over the card containing the chips, and the
shielded card is then sealed in an opaque plastic card holder. Three of these
dosimeters are placed in a secured, rugged, plastic housing one meter above
ground level at each station to standardize the exposure geometry. One dosim-
eter is issued to each of 53 off-site residents who are instructed in its
proper wearing.
35
-------
Figure 15. Locations monitored with TLD's,
36
-------
After appropriate corrections were made for exposure accumulated during
shipment between the laboratory and the monitoring location, and for fading
and the response factor, the six TLD chip readings for each station were aver-
aged. The average value for each station was then compared to the values
obtained during the previous four quarters at that station to determine whether
the new value was statistically different from the previous values. The result
from each of the personnel dosimeters was compared to the average background
value measured at the nearest fixed station over the previous four quarters.
The smallest exposure above background radiation that can be determined
from these TLD readings depends primarily on the magnitude of variations in the
natural background exposure rate at the particular station. 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.
Results—
Appendix Table E-10 lists the maximum, minimum, and average dose equiva-
lent rate (mrem/day) and the annual adjusted dose equivalent rate (average in
mrem/day times the number of days in the year) measured at each station in the
Network during 1985. No allowance was made for the small additional exposure
due to the neutron component of the cosmic ray spectrum. No station exhibited
an exposure in excess of background during 1985.
Appendix Table E-ll lists the personnel number; associated background
station; the maximum, minimum, and average dose equivalent rate (mrem/d); and
the annual dose equivalent (mrem) measured for each off-site resident monitored
during 1985. Nine dosimeters worn by residents exhibited exposures in excess
of background. These exposures are attributed to higher background levels in
the residence than at the background station location or to occupational ex-
posure (Nos. 45, 49, 52, 57). Usually, the average dose equivalent rates of
the off-site residents is lower than their background stations due to the shield-
ing provided by their homes or places of work.
Table 6 shows that the average annual dose rate for the Dosimetry Network
is consistent with the Network average established in 1975. Annual doses
decreased from 1971 to 1975 with a leveling trend since 1975, except for a high
bias in the 1977 results attributed to mechanical readout problems. The trend
shown by the Network average is indicative of the trend exhibited by individual
stations, although this average is also affected by the mix of stations at
different altitudes (note Figure 16).
Because of the great range in the results, 40 to 142 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
37
-------
TABLE 6. DOSIMETRY NETWORK SUMMARY FOR THE YEARS 1971 - 1985
Environmental Radiation Dose Rate (mrem/y)
Yaar Maximum Minimum Average
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
250
200
180
160
140
140
170
150
140
140
142
139
140
133
142
102
84
80
62
51
51
60
50
49
51
40
42
42
35
40
160
144
123
114
94
94
101
95
92
90
90
88
87
85
85
110
Station Attitude
4 - 6,000 ft.
76 77 78 79 80 81 82 83 84 85
75
Calendar Year 19—
Figure 16. Average annual TLD exposure as a function of station altitude,
38
-------
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 1985 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 16, indicate that the average exposure at altitudes between 4,000 and
6,000 feet is about 20 mrem/yr (0.2 mSv/yr) higher than that at altitudes
between 2,000 and 4,000 feet, although both curves follow the same trend as the
overall averages listed in Table 6. Thus, if an individual does not live near
a monitored location, an estimate of exposure could be based on the altitude of
his residence rather than on the average for the whole area monitored.
Pressurized Ion Chamber Network (PIC)
This network is located at the 15 Community Monitoring Stations identified
on Figure 2 plus stations at Complex I, Furnace Creek, Nyala, Pioche, Stone
Cabin Ranch, Tikaboo Valley, Twin Springs, and Lathrop Wells. The PIC used is
manufactured by Reuter-Stokes. The output is displayed on both a paper tape
and a digital readout, so the station manager can observe the response. All
data is stored on cassette tapes which are read into a computer at EMSL-LV each
week. The computer output consists of a table containing hourly, daily, and
weekly summaries of the maximum, minimum, average, and standard deviation of
the gamma exposure rate.
The data for 1985 are displayed in Table 7 as the average vR/hr and annual
mR from each station. When these data are compared to the TLD results for the
same 23 stations, it is found that the PIC response is about 28% higher than
the TLD response. This is attributed, primarily, to the difference in energy
response of the two instruments.
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 radionuclides also emit low-energy X-rays which can
be detected in the lungs by the phoswich detectors. An additional phoswich
detector is used to determine low-energy radionuclide concentrations in bone,
by moving the detector around the skull.
39
-------
TABLE 7. PRESSURIZED ION CHAMBER READINGS - yR/HOUR
EXPOSURE RATE
(MICRO-R/H)*
STATION LOCATION
ALAMO, NV
AUSTIN, NV
BEATTY, NV
CEDAR CITY, UT
COMPLEX 1, NV
ELY, NV
FURNACE CREEK, CA
60LDFIELD, NV
INDIAN SPRINGS, NV
LAS VEGAS, NV (UNLV)
LATHROP WELLS, NV
NYALA, NV
OVERTON, NV
PAHRUMP, NV
PIOCHE, NV
RACHEL, NV
SALT LAKE CITY, UT
SHOSHONE, CA
ST. GEORGE, UT
STONE CABIN RNCH, NV
TIKABOO VALLEY, NV
TONOPAH, NV
TWIN SPRGS RANCH, NV
MEASUREMENT PERIOD
85/01/01-85/12/31
85/01/03-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
85/01/01-85/12/31
MAX.
18.5
25.2
19.6
15.8
24.5
18.7
15.7
24.8
12.5
9.5
21.8
18.1
12.8
12.0
16.7
22.2
40.0
14.6
13.5
22.8
21.9
29.2
21.2
MIN.
8.0
2.0
14.8
6.0
15.0
8.6
1.2
9.8
7.2
5.7
10.3
10.5
7.1
2.0
11.4
9.7
1.7
10.3
5.0
13.0
10.0
14.1
12.8
AVG.
13.55
17.98
16.29
10.49
17.99
12.12
9.97
13.56
8.23
6.82
13.56
12.54
8.35
7.67
12.80
16.49
11.20
11.34
8.74
16.57
16.26
17.11
17.06
ANNUAL
ADJUSTED
EXPOSURE
(MR/Y)
119
158
143
92
158
106
87
119
72
60
119
110
73
67
112
144
98
99
77.
145
142
150
149
*The MAX and MIN values are obtained from the instantaneous readings.
Network Design
This activity consists of two portions, an Off-Site Human Surveillance
Program and a Radiological Safety Program. The design for the Off-Site Human
Surveillance Program is to measure radionuclide body-burdens in a representative
number of families who reside in areas that were subjected to fallout during
the early years of nuclear weapons tests. A few families who reside in areas
not affected by such fallout were also selected for comparative study. The
principal constraint to the program is the cooperation received from the people
in the area of study.
The Radiological Safety Program portion requires all employees who may be
exposed to radioactive materials in the course of their work to undergo a
periodic whole-body count. Some DOE contractor employees are also included in
this program.
40
-------
Methods
The Off-Site Human Surveillance Program was initiated in December 1970 to
determine levels of radioactive nuclides in some of the families residing in
communities and ranches surrounding the Nevada Test Site. Biannual counting is
performed in the spring and fall. This program started with 34 families (142
individuals). In 1985, 16 of these families (37 individuals) were still active
in the program together with 18 families added in recent years. The geograph-
ical locations of the families which participated in 1985 are shown in Figure
17.
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 radio-analysis.
Results of the whole-body count are available before the families leave the
facility and are discussed with the subjects. In November 1985 an agreement
was made with REECo Medical Service to do an annual physical examination on
participants of the Off-Site Human Surveillance Program. A health history and
the following are performed: a urinalysis, complete blood count, serology,
chest x ray (3-year intervals), sight screening, audiogram, vital capacity,
EKG (over 40 years old), and thyroid panel. The individual is then examined
by a physician. The results of the examination can then be requested for
use by their family physician.
In addition to the above off-site families, counts are performed routinely
on EPA and on contractor's employees as a part of the health monitoring pro-
grams. Counts on other individuals in the general population from Las Vegas
and other cities are used for comparison.
Results
During 1985, a total of 367 Nal(Tl) and 734 phoswich spectra were obtained
from individuals, of whom 106 were participants in the Off-Site Human Surveil-
lance Program. Also, about 2,732 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
off-site population detected in previous years were similar to those in other
U.S. residents from California to New York. All spectra collected in 1985
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 off-site residents
varied from 0 to 950 pCi/L with an average value of 210 pCi/L (7.8 Bq/L).
Nearly all the concentrations measured were in the range of background levels
measured in water and reflect only natural exposure. The source for the high
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 270 pCi/L and a range of 60 to 600, average 270 pCi/L (10 Bq/L).
41
-------
Round Mt.O
Blue Jay O
Tonopah^
Goldfield
°Nyala Eagle a.ley
O Adaven
Lathrop Wells
Shoshone
O Offsite Family
• Community Monitoring Sta. Family
3/84
Figure 17. Location of families in the Off-Site Human Surveillance Program.
42
-------
As reported in previous years, medical examination of the off-site 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.
COMMUNITY MONITORING STATIONS
In order to increase public knowledge about and participation in radio-
logical surveillance activities as conducted by DOE and EPA; the DOE, through
an Interagency Agreement with EPA and contracts with the Desert Research Insti-
tute (DRI) of the University of Nevada and the University of Utah, has estab-
lished a network of 15 Community Monitoring Stations in the off-NTS areas. Each
station is operated by a local resident, in most cases a science teacher, who
is trained in radiological surveillance methods by the University of Utah. The
stations are equipped and maintained, and samples are collected and analyzed by
EMSL-LV. DRI provides data interpretation to the communities involved and pays
the station operators for their services.
Each station contains one of the samplers for the ASN, NGTSN and Dosimetry
networks discussed earlier, plus a pressurized ion chamber (PIC) and recorder
for immediate readout of external gamma exposure, and a recording barograph.
All of the equipment is mounted on a stand at a convenient location in each
community so the residents are aware of the surveillance and, if interested,
can have ready access to the data. The station locations are those indicated
in Figure 2.
The data from these stations are included in the tables in Appendix E with
the other data from the appropriate networks. Table 7 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 were conducted by
the Medical Liaison Officers Network (MLON) or by the EMSL-LV physician (until
his retirement in May), depending on where the claim was made. The MLON is
composed of physicians, one from each state, who are trained in radiobiology.
No claims of radiation injury were made in 1985.
The EMSL-LV veterinarian conducts similar investigations for claims of
injury to domestic animals. In most cases the injuries investigated have been
43
-------
due to common causes such as bacterial infections or unusual events such as
feeding on halogeton, a poisonous plant. No such claims were made in 1985.
PUBLIC INFORMATION PROGRAM
An important function of the Off-Site Program has been to create and main-
tain, to the extent possible, public confidence that all reasonable safeguards
are being employed to preserve public health and property from possible hazards
resulting from nuclear testing. Much of this responsibility is carried out
through personal contact with off-site residents by the radiation monitors who
advise the residents of program developments and answer questions about test
activities.
For any test where ground motion may be perceptible off site, monitors
visit remote locations and active mines beforehand to advise operators of pos-
sible problems. They also stand by on test day to advise of schedule changes.
Mine operators are reimbursed for time lost due to these activities. After the
test, monitors inform all their contacts that the test is over and whether or
not any radiation was detected off site.
The series of "town hall" meetings, initiated during Fiscal Year 1982 near
community monitoring stations was continued for CY 1985. The meetings were
organized to familiarize the local citizenry with the NTS nuclear testing and
related activities, to show how the surveillance networks function, and to
answer questions or expressed concerns of the attending public. During CY85,
meetings were held according to the following schedule:
Cedar City, UT
St. George, UT
Henderson, NV
Beaver, UT
Parowan, UT
Bullhead City, AZ
Caliente, NV
January 23
January 24
March 13
April 17
April 18
April 19
May 22
Pioche, NV
La Verkin, UT
Washington, UT
Bunkerville, NV
Tecopa Hot Springs, CA
North Las Vegas, NV
May 23
July 9
July 10
September 19
October 25
December 12
Other activities included arranging NTS tours for businesses and community
leaders in Amargosa Valley, for park rangers of Death Valley, and for EPA
employees and spouses. Talks on the deer migration studies were presented for
the vocational agriculture classes at White Pine High School, the Wildlife
Society and Society for Range Management meetings in Ely, the Pioche Rod and
Gun Club, and the Boulder City Horseman's Association. Presentations on the
Off-Site Safety Program were given to the Nye County commissioners, the
St. George Chamber of Commerce, Twin Springs School, and Pioche Elementary
School. The mobile whole body, thyroid, and sample-counting trailer and a
replica of a community monitoring station were displayed and demonstrated at
the Jaycees State Fair in Las Vegas in October.
With the continued population growth in the off-site area in recent years
and the continuing concern for keeping radiation exposures as low as reasonably
achievable, the EMSL-LV realized that it would need local government assistance
to implement all protective actions that could be needed to protect close-in
44
-------
population centers should an underground nuclear test accidently vent. EMSL-LV
staff discussed the kinds of assistance needed with the Nevada State Division
of Emergency Management, and obtained the State's concurrence with its plan to
work with County emergency management officials to develop modifications or
additions to their adopted emergency response plans. These changes would
specify protective actions and procedures for implementing them and would serve
as formal agreements on Federal and local government responsibilities and
authorities.
During 1985, an Appendix to the Radiological Defense Annex of the
Esmeralda and White Pine Counties (Nevada) emergency plans was prepared. This
Appendix is expected to serve as a model for developing a similar agreement
with officials of Clark County and Inyo County, CA. The County plans, with
their new appendices, will be annexed to the master plan DOE is developing for
off-site emergency response for an accidental venting or seepage at the Nevada
Test Site. As part of these plans, 12,000 Film badges were distributed to 13
locations in Lincoln and Nye Counties with the objective of providing personal
dosimetry for at least one person per family or about two-thirds of the total
population in major population centers. Issue of badges will be performed by
county or state personnel in the unlikely event of a significant release of
radioactive material from the NTS.
DOSE ASSESSMENT
Dose assessment calculations for NTS-related radioactivity are not pos-
sible because detectable levels of radioactivity from the 1985 nuclear testing
program at the NTS were not observed off site by any of the monitoring networks.
However, an exposure can be calculated by using atmospheric dispersion calcula-
tions and reported releases of radioactivity from the NTS (Table 1). This
calculation is shown below. Residual radioactivity was observed in waters from
wells in other nuclear testing areas known to be contaminated during past
nuclear tests at the Project Dribble Site near Hattiesburg, Mississippi;
Project Gnome near Malaga, New Mexico; and at the Project Long Shot site on
Amchitka Island, Alaska. However, the waters from these contaminated wells are
not used for drinking purposes.
An estimate of exposure of an average adult in Nevada due to worldwide
radioactivity can be made based on the data from the monitoring networks. The
principal data are strontium-90 in milk (28 mBq/L) and plutonium-239 in beef
liver (0.29 mBq/kg) from past atmospheric tests; krypton-85 in air from use
of nuclear technology (1.1 Bq/m3); and the average tritium concentration in
air (HTO = 16 mBq/m3).
Assumptions: (1) breathing rate = 8400 m3/yr,
(ICRP-23)
(2) milk intake (10-year old) = 160 L/yr,
(3) hours per average year = 8766.
45
-------
From ICRP-30, the committed dose equivalent conversion factors are:
(1) Kr-85 (immersion) - 4.7 x 10~H Sv/hr per Bq/m3 to the skin,
= 4.12 x 10'7 Sv/yr per Bq/m3
= 1.53 x 10~3 mrem/yr per pCi/m3
(2) Sr-90 (ingestion) - 1.9 x 10'7 Sv/Bq
= 1.9 x 10~2 mrem/Bq
= 7 x ID"4 mrem/pCi,
(3) HTO (inhalation) - 9.9 x 10'15 Sv/hr per Bq/m3
= 3.2 x 10~7 mrem/yr per pCi/m3
\
(4) Pu-239 (ingestion) - 2.1 x ID'6 Sv/Bq
= 7.8 x 10-3 mrem/pCi
Calculated annual dose equivalent:
Kr-85: 1.53 x lO'3 mrem/yr x 29.5 pCi/m3 = .045 mrem
Sr-90: 7 x 10~4 mrem/pCi x 0.77 pCi/L x 160 L/yr = 0.086 mrem
HTO: 3,2 x 10~7 mrem/yr x 0.43 pCi/m3 = 1.4 x 10'7 mrem
The highest postulated annual dose equivalent to man as calculated from
the Biomonitaring Program would be .0062 mrem. This is based on the assumption
that all the liver samples would have the maximum Pu-239 concentration (0.0078
pCi/kg) and that consumption was 0.28 kg/d for 365 days/yr (ICRP-29).
Therefore, the total annual dose equivalent to an adult in Nevada based
on the results from the monitoring program would be the sum of the above, or
0.14 mrem (1.4 ySv) at maximum. This is a small fraction of the dose equiva-
lent delivered by the natural radioactive content of the average man.
The external exposures to Nevadans range from 40 to 142 mrem/yr as meas-
ured 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 (NCRP71). 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.
46
-------
Other than the Xe-133 detected during the planned ventilation of the
tunnel following the Misty Rain event, none of the radionuclides released at
the NTS as listed in Table 1 were detected off site. The normal 1 week noble
gas sample at Rachel had no detectable xenon so that the 11 pCi/m3 detected on
the 1 day sample at Rachel (as stated in the section on Special Test Support)
probably was valid only for that day. The skin dose from that concentration
would have been about 0.06 yrem or about 0.002% of the background exposure
measured by the PIC at Rachel.
Because no significant radioactivity of recent NTS origin was detectable
off site by the air, water, milk, TLD or biological monitoring networks, other
than as described above, no impact on the population living around the NTS
would be expected. However, to substantiate those findings, it is instructive
to calculate public exposure from those radionuclides released from the NTS
as stated in Table 1. There were no waterborne radioactive effluents and only
tritium (116 Ci) and Xe-133 (735 Ci) were released in airborne emissions in
significant quantities. Since human exposure to these nuclides is straight-
forward, a simple atmospheric dispersion calculation will suffice. AIRDOSE-
RADRISK, which calculates exposure resulting from multiple transport pathways,
is inappropriate for those cases, such as the present one, where a single
pathway predominates. The atmospheric dispersion calculation yields a maximum
individual dose of 4 x 10~5 mrem (4 x 10~7 mSv) and a population dose, to the
6500 people living within 80 km of CP-1, of 2 x 10'4 person-rem (2 x 10~6
person-Sv).
As confirmation of the above results, an AIRDOSE run using the effluents
listed in Table 1 yielded a maximum individual dose of 4.2 x 10~5 mrem and a
population dose of 1.3 x 10~4 person-rem, an insignificant difference from the
atmospheric dispersion calculation.
47
-------
SECTION 6
REFERENCES
ANSI75 American National Standards Institute, Inc., 1975, "American National
Standard Performance Testing and Procedural Specifications for Thermolumi-
nescent Dosimetry (Environmental Applications)." ANSI N545-1975.
Be73 Bernhardt, D. E., A. A. Moghissi and J. A. Cochran, 1973, Atmospheric
Concentrations of Fission Product Noble Gases, pp. 4-19, in Noble Gases,
CONF-730915.
B184 Black, S. C. and D. D. Smith, 1984, "Nevada Test Site Experimental
Farm Summary Report 1963-1981". EPA 600/4-84-066, DOE/DP/0539-052. U.S.
Environmental Protection Agency, Environmental Monitoring Systems Labor-
atory, Las Vegas, Nevada.
CA85 California, 1985, Personal communication from California county agents.
DOE85a U.S. Department of Energy, 1985, Amendment to DOE Order 5480.1A, Radia-
tion Standards for Protection of the Public in the Vicinity of DOE
Facilities.
DOE85 U.S. Department of Energy, 1985, Environmental Protection, Safety, and
Health Protection Information Reporting Requirements. Order DOE 5484.1.
DOE86 U.S. Department of Energy, 1986, Personal communication from Health Physics
Division, DOE/NV, Las Vegas, NV.
EPA81 U.S. Environmental Protection Agency, 1981, "Environmental Radioactivity
Laboratory Intercomparison Studies Program 1978-1979." EPA-600/4-81-004.
Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
(Available from U.S. Department of Commerce, NTIS, Springfield, VA 22161.)
ERDA77 U.S. Energy Research and Development Administration, 1977, "Final Environ-
mental Impact Statement, Nye County, Nevada." Nevada Operations Office, Las
Vegas, NV, Report ERDA-1551. (Available from U.S. Department of Commerce,
NTIS, Springfield, VA 22161.)
Gi79 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.
48
-------
Gi85 Giles, K. R. and 0. Cooper, 1985, "Characteristics and Migration Patterns of
Mule Deer on the Nevada Test Site," U.S. Environmental Protection Agency,
Environmental Monitoring Systems Laboratory Report EPA-60/4-85-030 (DOE/OP/
00539-054).
Ho75 Houghton, J. G., C. M. Sakamoto, and R. 0. Gifford, 1975, "Nevada's Weather
and Climate." Special Publication 2. Nevada Bureau of Mines and Geology,
Mackay School of Mines, University of Nevada, Reno, Nevada, pp. 69-74.
ICRP75 International Commission in Radiological Protection, 1975, Report of the
Task Group on Reference Man, Report ICRP-23.
ICRP77 International Commission in Radiological Protection, 1977, Recommendations
of the ICRP, Report ICRP-26.
ICRP79 International Commission in Radiological Protection, 1979, Radionuclide
Releases to the Environment: Assessment of Dose to Man, Report ICRP-24.
ICRP79 International Commission in Radiological Protection, 1979, Limits for
Intake of Radionuclides by Workers, Report ICRP-30, 3 parts.
Ja81 Jarvis, A. N. and L. Siu, 1981, Environmental Radioactivity Laboratory
Intercomparison Studies Program - FY 1981-82, EPA-600/4-81-004, U.S. EPA,
Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
NPS80 National Park Service, 1980, Personal Communication with Chief Ranger R.
Rainer, Death Valley National Monument, Death Valley, California.
NCRP71 National Council on Radiation Protection and Measurements, 1971, Basic
Radiation Protection Criteria. NCRP Report No. 39.
NCRP75 National Council on Radiation Protection and Measurements, 1975, Natural
Background Radiation in the United States. NCRP Report No. 45.
NV86 Nevada Department of Agriculture, 1986, "Nevada Agricultural Statistics 1985."
Nevada Crop and Livestock Reporting Service, Reno, Nevada.
Pi82 Patzer, R. G. and M. E. Kaye, 1982, "Results of a Human Surveillance
Program in the Off-site Area Surrounding the Nevada Test Site." Health
Phys. 43:791-801.
Qu68 Quiring, R. E., 1968, "Climatological Data, Nevada Test Site, Nuclear Rocket
Development Station (NRDS)." ERLTM-ARL-7. ESSA Research Laboratories,
Las Vegas, Nevada.
Sm81 Smith, D. D. and V. E. Andrews, 1981, Selected Radioisotopes in Animal Tissues;
90Sr and 137Cs Measurements from 1956 to 1977. U.S. Environmental Pro-
tection Agency Report EPA-600/3-81-027 (DOE/DP/00539-040). Las Vegas,
Nevada.
49
-------
Sm84 Smith, 0. 0. and S. C. Black, 1984, Animal Investigation Program for the Nevada
Test Site 1957-1981, U.S. Environmental Protection Agency, Environmental
Monitoring Systems Laboratory Report EPA 600/6-84-020, Las Vegas, Nevada.
UT82 Utah Department of Agriculture, 1982, "Utah Agricultural Statistics, 1982."
State of Utah Department of Agriculture, Salt Lake City, Utah.
Wi75 Winograd, I. J. and W. Thordarson, 1975, Hydrogeologic and hydrochemical
framework, south-central Great Basin, Nevada-California, with special
reference to the Nevada Test Site, USGS Professional Paper 712-C, Denver,
Colorado.
50
-------
APPENDIX A
SITE DATA
-------
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. (Ho75), this method of classification of
dry condition, developed by Doppen, is further subdivided on the basis of
temperature and severity of drought. Table A-l (Ho 1975) summarizes the charac-
teristics of climatic types for Nevada.
According to Quiring (Qu68), the NTS average annual precipitation ranges
from about 10 cm at the lower elevations to around 25 cm on the higher eleva-
tions. During the winter months, the plateaus may be snow-covered for a
period of several days or weeks. Snow is uncommon on the flats. Temperatures
vary considerably with elevation, slope, and local air currents. The average
daily high (low) temperatures at the lower altitudes are around 50F (25F) in
A-l
-------
TABLE A-l. CHARACTERISTICS OF CLIMATIC TYPES IN NEVADA (from Houghton et al. 1975)
I
ro
Mean Temperature
°C
(°F)
Climate Type Winter Summer
Al pi ne
tundra
Humid
continental
Subhumid
continental
Mid-latitude
steppe
Mid-latitude
desert
Low-latitude
desert
-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
-------
January and 95F (55F) in July, with extremes of 110F and -15F. Corresponding
temperatures on the plateaus are 35F (25F) in January and 80F (65F) in July
with ex-15F have been observed.
The wind direction, as measured on a 30 m tower at an observation station
about 9 km NNW of Yucca Lake, is predominantly northerly except during the
months of May through August when winds from the south-southwest predominate
(Qu68). Because of the prevalent mountain/valley winds in the basins, south to
southwest winds predominate during daylight hours of most months. During the
winter months southerly winds have only a slight edge over northerly winds for
a few hours during the warmest part of the day. These wind patterns may be
quite different at other locations on the NTS because of local terrain effects
and differences in elevation.
Geology and Hydrology
Two major hydrologic systems shown in Figure A-l exist on the NTS (ERDA77).
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.
A-3
-------
7
/ /* \
_ • ri
\
Pahute Mesa
Ground Water
Ash Meadows
Ground Water System
i i i i
10 20 30 40
3/81 Scale in Kilometers
•^ Flow Direction
— Ground Water System Boundaries
• — Silent Canyon Caldera
•••• Timber Mountain Caldera
Figure A-l. Ground-water flow systems around the Nevada Test Site.
A-4
-------
A
O / GRAZING/ _ / (
GRAZING,/—""V X\U/GRAZING
Tonopah <-"-• \/ V \
GRAZING J
GRAZING /
• DAIRIES* ••
(• Cedar City
\PA/
DAIRIES
0 50 100 150
3/86 Scale in Kilometers
A Camping & Recreational
Areas
D Hunting
• Fishing
O Mines
A Oil Fields
Figure A-2. General land use within 300 km of the Nevada Test Site.
A-5
-------
Population Distribution
Figure A-3 shows the current population of counties surrounding the NTS
based on 1980 census figures. Excluding Clark County, the major population
center (approximately 536,000 in 1984), the population density within a 150 km
radius of the NTS is about 0.5 persons per square kilometer. For comparison,
the 48 contiguous states (1980 census) had a population density of approximately
29 persons per square kilometer. The estimated average population density for
Nevada in 1980 was 2.8 persons per square kilometer.
The off-site area within 80 km of the NTS (the area in which the dose
commitment must be determined for the purpose of this report) is predominantly
rural. Several small communities are located in the area, the largest being in
the Pahrump Valley. This growing rural community, with an estimated population
of about 5,500, is located about 72 km south of the NTS CP-1. The Amargosa
Farm Area, which has a population of about 1,200, is located about 50 km south-
west of CP-1. The largest town in the near-offsite area is Beatty, which has a
population of about 900 and is located approximately 65 km to the west of CP-1.
A report by Smith and Coogan was published in 1984 which summarizes the popula-
tion distribution within selected rural areas out to 200 kilometers from the
Control Point on the NTS.
The Mojave Desert of California, which includes Death Valley National
Monument, lies along the southwestern border of Nevada. The National Park
Service (NPS80) estimated that the population within the Monument boundaries
ranges from a minimum of 200 permanent residents during the summer months to as
many as 5,000 tourists and campers on any particular day during the major hol-
iday periods in the winter months, and as many as 30,000 during "Death Valley
Days" in the month of November. The largest town and contiguous populated area
(about 40 square miles) in the Mojave Desert is Barstow, located 265 km south-
southwest of the NTS, with a 1983 population of about 36,000. The next largest
populated area is the Ridgecrest-China Lake area, which has a current population
of about 25,000 and is located about 190 km southwest of the NTS. The Owens
Valley, where numerous small towns are located, lies about 50 km west of Death
Valley. The largest town in Owens Valley is Bishop, located 225 km west-north-
west of the NTS, with a population of about 5,300 including contiguous populated
areas.
The extreme southwestern region of Utah is more developed than the adjacent
part of Nevada. The largest community is St. George, located 220 km east of
the NTS, with a population of 11,300. The next largest town, Cedar City, with
a population of 10,900, is located 280 km east northeast of the NTS.
The extreme northwestern region of Arizona is mostly range land except for
that portion in the Lake Mead Recreation Area. In addition, several small com-
munities lie along the Colorado River. The largest town in the area is Kingman,
located 280 km southeast of the NTS, with a population of about 9,300. Figures
A-4 through A-7 show the domestic animal populations in the counties near the
NTS.
A-6
-------
Storey4
1.800
Carson
City
35,400
Douglas
21,000
N
San Bernardino
1,033,700
Scale in Miles
26 50 75 100
0 50 100 150
3/86 Sole in Kilometeri
Figure A-3. Population of Arizona, California, Nevada, and Utah
Counties near the Nevada Test Site (1980).
A-7
-------
XX - Cows
(XX) - Goats
0 50 100 150
3/86 Scale m Kilometers
Figure A-4. Distribution of family milk cows and goats, by county (1985).
A-8
-------
0 50 100 150
3/86 Scale in Kilometers
Figure A-5. Distribution of dairy cows, by county (1985).
A-9
-------
0 50 100 150
3/86 Scale in Kilometers
Figure A-6. Distribution of beef cattle, by county (1985)
A-10
-------
0 SO 100 150
3/86 Scale in Kilometers
Figure A-7. Distribution of sheep, by county (1985).
A-ll
-------
APPENDIX B
SAMPLE ANALYSIS PROCEDURES
-------
APPENDIX B
SAMPLE ANALYSIS PROCEDURES
ANALYTICAL PROCEDURES
The procedures for analyzing samples collected for offsite surveillance are
described by Johns et al. in "Radiochemical Analytical Procedures for Analyses
of Environmental Samples" (EMSL-LV-0539-17, 1979) and are summarized in Table
B-l.
TABLE B-l. SUMMARY OF ANALYTICAL PROCEDURES
Type of
Analysis
IG Ge(L1)
Gamma
Spec
trometry**
Analytical
Equipment
IG or Ge(L1)
detector cali-
brated at 0.5 keV/
channel (0.04
to 2 MeV range)
Individual detec-
tor efficiencies
ranging from
15X to 35X.
Counting
Period
(m1n)
A1r charcoal
cartridges
and Individual
air filters,
30 m1n; air
filter com-
posites, 1200
m1n. 100 m1n
for milk,
water, sus-
pended solids.
Analytical
Procedures
Rad1onuc11de
concentration
quantified
from gamma
spectral data
by on-Hne
computer pro-
gram. Radlo-
nuclldes 1n air
filter composite
samples are
Identified only.
Sampl e
Size
120-300 m3
for air
filters;
and char-
coal car-
tridges;
3-1/2
liters for
milk and
i water.
Approximate
Detection
Limit*
For routine milk
and water generally,
5 pC1/L for most
common fallout
radlonuclldes In a
simple spectrum.
Filters for LTHMP
suspended sol Ids,
6 pC1/L. Air
filters and char-
coal cartridges,
0.04 pC1/m3.
Gross beta
on air
filters
Low-level end
window, gas
flow proportional
counter with a
12.7 cm diameter
window (80 yg/cm2)
30
Samples are
counted after
decay of
naturally-
occurlng
radlonuclldes
and, 1f neces-
sary, extrapo-
lated to mid-
point of col-
lection In
accordance with
t.-1.2 decay or
an experiment-
ally-derived
decay.
120-300 m3 0.5 pC1/sample.
(continued)
B-l
-------
TABLE B-l. (Continued)
Type of
Analysis
Sr-89-90
Analytical
Equipment
Low-background
thin-window,
gas-flow pro-
portional
counter.
Counting
Period
(mln)
50
Analytical
Procedures
Chemical separa-
tion by Ion ex-
change. Separated
sample counted
successively; ac-
tivity calculated
by simultaneous
solution of equa-
tions.
Sample
Size
1.0 liter
for milk
or water.
0.1-1 kg
for tissue.
Approximate
Detection
Limit*
Sr-89 - 5 pCI/L
Sr-90 - 2 pCI/L.
H-3
H-3
Enrichment
(Long-Term
Hydro-
logical
Samples)
Pu-238,239
Kr-85,
Xe-133,
Xe-135
Automatic 200
liquid
scintillation
counter with
output printer.
Automatic 200
scintillation
counter with
output printer.
Alpha spectre- 1000-1400
meter with 450
mm, 300-urn
depletion depth,
silicon surface
barrier detectors
operated 1n
vacuum chambers.
Automatic 200
liquid scintil-
lation counter
with output
printer.
Sample pre-
pared by
distillation.
Sample concen-
trated by
electrolysis
followed by
distillation.
Water sample or
acid-digested
filter or tissue
samples separated
by 1on exchange,
electro-plated on
stainless steel
planchet.
Separation by
gas chromatogra-
phy; dlsolved In
toluene "cocktail*
for counting
4 ml
for water
250 ml
for water
1.0 liter
for water;
0.1-1 kg
for tissue;
5,000-
10,000 m3
for air.
0.4-1.0
for air
400 pC1/L.
10 pC1/L.
Pu-238 • 0.08 pC1/L
Pu-239 « 0.04 PC1/L
for water. For
tissue samples,
0.04 pC1 per total
sample for all
Isotopes; 5-10 ad/m3
for plutonlum on air
filters.
Kr-85, Xe-133, Xe-135
» 4 pd/m3.
*The detection limit Is defined as 3.29 slgma where slgma equals the counting error of the sample
and Type I error • Type I! error * 5 percent. (J. P. Corley, 0. H. Denham, R. E. Jaqulsh, D. E.
Michels, A. R. Olsen, 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. 0. C.)
**Gamma Spectrometry using either an Intrinsic germanium (IG), or lithium-drifted germanium diode
(Ge(LD) detector.
B-2
-------
APPENDIX C
QUALITY ASSURANCE PROCEDURES
-------
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, s2, of each set
TABLE C-l. SAMPLES AND ANALYSES FOR DUPLICATE SAMPLING PROGRAM - 1985
Surveillance
Network
ASN
NGTSN
Dosimetry
MSN
Number of
Sampl i ng
Locations
114
16
129
31
Samples
Collected
This Year
5,146
818 (NG)
866 (H3)
1,548
286
Sets of
Duplicate
Samples
Collected
309
39
87
1,548
63
Number
Per Set
2
2
4-6
2
=================
Sample
Analysis
Gross beta,
Y Spectrometry
Kr-85, H-3,
H20, HTO
Effective dose
from gamma
K-40, Sr-89,
Sr-90, H-3
LTHMP 134
716 144
H-3
C-l
-------
of replicate TLD results (n=6) was estimated from the results by the standard
expression,
9 _2
sz = z (x, - x) / (k - 1)
1-1
where k = number of sets of replicates.
Since duplicate samples were collected for all other sample types, the
variances, s2, for these types were calculated from s2 = (0.886R)S where R is
the absolute difference between the duplicate sample results. For small sample
sizes, this estimate of the variance is statistically efficient* and certainly
more convenient to calculate than the standard expression. The standard devia-
tion is obtained by taking the square root.
The principle that the variances of random samples collected from a normal
population follow a chi -square distribution (x2) was then used to estimate the
expected population standard deviation for each type of sample analysis. The
expression used is as follows:**
k k
s - z (n,- - l)s..2/ z (n, - 1)
1-1 1-1
1/2
where n-j-1 = the degrees of freedom for n samples collected for the ith
replicate sample
2
s-j = the expected variance of the ith replicate sample
s = the best estimate of sample standard deviation derived from the
variance estimates of all replicate samples (the expected value
of s2 is a2).
For expressing the precision of measurement in common units, the coefficient
of variation (s/x) was calculated for each sample type. These are displayed in
Table C-2 for those analyses for which there were adequate data.
To estimate the precision of counting, approximately 10 percent of all
samples are counted a second time. These are unknown to the analyst. Since
all such replicate counting gave results within the counting error, the preci-
sion data in Table C-2 represents errors principally in analysis.
*Snedecor, G. W., and W. G. Cochran. Statistical Methods. The Iowa State
University Press, Ames, Iowa. 6th Ed. 1967. pp. 39-47.
**Freund, 0. E. Mathematical Statistics. Prentice Hall, Englewood, New Jersey.
1962. pp 189-235.
C-2
-------
TABLE C-2. SAMPLING AND ANALYTICAL PRECISION - 1985
Sets of
Replicate Coefficient
Surveillance Samples of Variation
Network Analysis Evaluated (%)
ASN
NGTSN
Dosimetry
MSN
LTHMP
Gross B
Be-7
Kr-85
HTO
H20
TLD (1984)
K-40
Sr-89
Sr-90
H-3
H-3+
40
4
38
*
73
344
61
33
38
36
58
97
13
12
39
39
4.1
11
17
17
5.2
11
:===================================
*Estimate of precision was calculated from the errors in the H-3 conventional
analysis and the measurement of atmospheric moisture (H20).
ACCURACY OF ANALYSIS
Data from the analysis of intercomparison samples are statistically anal-
yzed and compared to known values and values obtained from other participating
laboratories. A summary of the statistical analysis is given in Table C-3,
which compares the mean of three replicate analyses with the known value. The
normalized deviation is a measure of the accuracy of the analysis when compared
to the known concentration. The determination of this parameter is explained
in detail separately (Ja81). If the value of this parameter (in multiples of
standard normal deviate, unitless) lies between control limits of -3 and +3,
the precision or accuracy of the analysis is within normal statistical varia-
tion. However, if the parameters exceed these limits, one must suspect that
there is some cause other than normal statistical variations that contributed
to the difference between the measured values and the known value. As shown by
this table, all but one of the analyses were within the control limit.
The analytical methods were further checked on by Laboratory participation
in the semiannual Department of Energy Quality Assessment Program conducted by
the Environmental Measurements Laboratory, New York, N.Y. and in the inter-
comparison studies conducted by the World Health Organizations International
Reference Center for Radioactivity located in France. The results from both
of these tests (Table C-4) indicate that this Laboratory's results were of
acceptable quality.
C-3
-------
TABLE C-3. EPA QUALITY ASSURANCE INTERCOMPARISON RESULTS - 1985
Analysis
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-89 in
milk
Sr-90 in
milk
1-131 in
milk
Cs-137 in
milk
Month
Feb
Apr
Jim
Aug
Oct
Apr
Jul
Nov
Feb
Feb
Apr
Feb
Feb
Apr
Feb
Apr
Feb
Apr
June
Oct
June
Oct
Feb
Oct
June
Oct
Mean of
Replicate
Analyses
(pCi/L)
4083
3826
2341
4402
2072
3119
2515
3548
50
19
16
57
<30
7.5
33
15
24
13
12
50
11
23
9
41
10
57
Known
Value
(pCi/L)
3796
3559
2416
4480
1974
3056
2444
3586
48
20
15
55
25
7.5
35
15
25
15
11
50
11
28
9
42
11
56
Normalized
Deviation from:
Known Cone.
1.4
1.3
-0.4
-0.3
0.5
0.3
0.4
-0.2
0.7
-0.3
0.3
0.6
_
0
-0.8
-0.2
-0.2
-0.7
0.3
0
0
-5.4
-0.4
-0.2
-0.2
0.3
(continued)
C-4
-------
Analysi
K in
Milk
(nig/1 )
s Month
Jim
Oct
TABLE C-3.
Mean of
Replicate
Analyses
(pCi/L)
1512
1513
(Continued)
Known
Value
(pCi/L)
1525
1540
Normalized
Deviation from:
Known Cone.
-0.3
-0.6
Cs-137 in
air filter
(pCi/filter)
Mar
0.1
To measure the performance of the contractor laboratory for analysis
of animal tissues, a known amount of activity was added to several samples.
The reported activity is compared to the known amount in Table C-5. The aver-
age bias for Sr-90 was -37 percent and for Pu-239 was -13 percent. The pre-
cision was 9% for both analyses.
In addition to calibration of the TLD's with a Cs-137 source traceable to
NBS, the accuracy of the results obtained from the Dosimetry Network is af-
firmed by participation in the International Intercomparison of Environmental
Dosimeters Program operated by the Idaho Operations Office of the DOE. The
eighth such intercomparison study is presently nearing completion.
For personal dosimeters, this Laboratory was accredited in 1985 under the
National Voluntary Laboratory Accreditation Program operated by the National
Bureau of Standards. For both personal and environmental dosimeters, the
TLD measurements are performed according to standards proposed by the American
National Standards Institute (ANSI75).
C-5
-------
TABLE C-4. QUALITY ASSURANCE RESULTS FROM OTHER ORGANIZATIONS
:=============================================================================
Analysis
Environmental
H-3 in
water
Mn-54 in
water
Fe-59 in
water
Co-60 in
water
Sr-90 in
water
Cs-137 in
water
Ce-141 in
water
Ce-144 in
water
Pu-239 in
water
Pu-239 in
air filter
No. 1
Pu-239 in
air filter
No. 2
K-40 in
soil
Cs-137 in
soil
Pu-239 in
soil
Month
EMSL-LV
Results
Measurements Laboratory
May
Nov
May
Nov
Nov
May
Nov
May
Nov
May
Nov
Nov
May
May
Nov
May
Nov
May
May
Nov
May
Nov
May
Nov
19.1
19.3
3.50
4.50
0.453
5.09
4.80
1.05
0.415
5.49
4.62
4.30
42.9
0.0349
0.0248
4.67
5.34
5.32
22.2
21.2
0.849
0.290
0.0445
0.277
EML
Results
, DOE
18.5
19.5
3.42
4.43
0.453
4.91
4.82
1.02
0.440
5.36
4.62
4.45
40.6
0.0428
0.0400
4.81
4.91
4.81
20.3
19.4
0.760
0.270
0.0350
0.240
Ratio
EMSL-LV/EML
1.03
0.99
1.02
1.02
1.00
1.04
1.00
1.03
0.94
1.02
1.00
0.97
1.06
0.82
0.62
0.97
1.09
1.11
1.09
1.09
1.12
1.07
1.27
1.15
Units
pCi/ml
pCi/ml
pCi /ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi/ml
pCi /filter
pCi/filter
pCi/filter
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
(continued)
C-6
-------
TABLE C-4. (Continued)
===3=3=—= — — :
Analysis
K-40 in
tissue
Co-60 in
tissue
Cs-137 in
tissue
Pu-239 in
tissue
International
H-3 in
milk
K-40 in
milk
Month
May
Nov
May
May
Nov
May
Nov
Reference
Jan
Jan
EMSL-LV
Results
9.69
4.01
0.584
1.41
0.882
0.0117
0.423
Center for
111
1.57
EML
Results
3.86
1.76
0.360
0.810
0.440
0.0081
0.410
Radioactivity,
89
1.58
I —===3333=3=
Ratio
EMSL-LV/EML
2.51*
2.28*
1.62*
1.74*
2.00*
1.44
1.03
WHO
1.25
0.99
Units
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
Bq/L
g/L
Ce-137 in Jan 0.66 0.68 0.97 Bq/L
milk
*These were ashed samples. The EMSL-LV system is calibrated for homogenized
fresh tissue so the results are expected to be high.
C-7
-------
TABLE C-5. QUALITY ASSURANCE RESULTS FOR THE BIOENVIRONMENTAL PROGRAM - 1985
Sample Type
and
Shipment
Number
Nuclide
Activity Added
pCi/g Bone Ash
Activity Reported
pCi/g Bone Ash
% Bias+
or
Precision*
Bone Ash
Ash A
60
Ash B
60
Ash 11
60
Ash 12
60
Ash 25
62
Ash 26
62
Ash 27
62
Ash 28
62
Ash C
65
Ash D
65
Duplicate Samples
Bov-4
Bov-4 Dup
239Pu
90Sr
239Pu
90Sr
239PU
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
Spiked Samples
0
0
0
0
0.15
29.4
0.114
13.8
0
0
0
0
0.14
22.9
0.12
17.5
0.16
13.6
0.18
10.8
0.002**
1.2
0.001**
1.5
0.15
-21.4
0.11
10.2
-0.002**
1.5
0.002**
1.2
0.12
19.9
0.10
14.4
0.13
9.2
0.14
7.5
-0.001
1.9
0.0009
2.1
-1
-32
-5
-36
-15
-19
-18
-25
-20
-42
-23
-43
0.09
0.09
+ Bias (B) = Recovery -1; where recovery is _^1_
u
and xi = net activity reported
u = activity added
Precision (Cv) = 2
xl - X2
xl + X2
**Counting error exceeds reported activity
x - where
1.128
= first value
= second value
C-8
-------
APPENDIX D
RADIATION PROTECTION STANDARDS FOR EXTERNAL AND INTERNAL EXPOSURE
-------
APPENDIX D
RADIATION PROTECTION STANDARDS FOR EXTERNAL AND INTERNAL EXPOSURE
DOE EQUIVALENT COMMITMENT
For stochastic effects in members of the public, the following limits are
used:
Effective Dose Equivalent*
mrem/yr mSv/yr
Occasional annual exposures** 500 5
Prolonged period of exposure 100 1
*Includes both effective dose equivalent from external radiation and
committed effective dose equivalent from ingested and inhaled
radionuclides.
**0ccasional exposure implies exposure over a few years with the proviso
that over a lifetime the average exposure does not exceed 100 mrem
(1 mSv) per year (ICRP-39).
CONCENTRATION GUIDES
ICRP-30 lists Derived Air Concentrations (DAC) and Annual Limits of Intake
(ALI). The ALI is the secondary limit and can be used with assumed breathing
rates and ingested volumes to calculate concentration guides. The concentration
guides (CG's) in Table D-l were derived in this manner and yield the committed
effective dose equivalent (50 year) of 100 mrem/yr for members of the public.
EPA DRINKING WATER GUIDE
In 40 CFR 141 the EPA set allowable concentrations for continuous con-
trolled releases of radionuclides to drinking water sources. Any single or
combination of beta and gamma emitters should not lead to exposures exceeding
4 mrem/yr. For tritium this is 20,000 pCi/L (740 Bq/L) and for strontium is
8 pCi/L (0.3 Bq/L).
D-l
-------
TABLE D-l. ROUTINE MONITORING FREQUENCY, SAMPLE SIZE, MDC AND CONCENTRATION GUIDES
o
I
ro
Nuclide
Air Surveillance
Be-7
Zr-95
Nb-95
Mo-99
Ru-103
1-131
Te-132
Cs-137
Ba-140
La-140
Ce-141
Ce-144
Pu-239
Gross Beta
Sampl i ng
Frequency
Network
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
Locations
all
all
all
all
all
all
all
all
all
all
all
all
all
all
Sample
Size
m3
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
1120
160-240
Count
Time
minutes
30
30
30
30
30
30
30
30
30
30
30
30
1000
30
Concentration Guide*
Bq/tn3
2000
20
100
100
60
4
18
10
100
100
50
1
9E-4
2E-2
nCi/m3 i
50
0.6
3
3
2
0.1
0.5
0.4
3
3
1
0.03
2E-5
0.4E-4
MDC
mBq/m3
17
4.1
1.8
1.5
1.8
1.8
1.8
1.8
4.8
2.6
3.0
12
1.48E-3
0.11
MDC as
% CG
8E-4
2E-2
2E-3
2E-3
3E-3
4E-2
1E-2
2E-2
5E-3
3E-3
6E-3
1.2
2E-1
6E-1
(continued)
-------
TABLE D-l. Continued
Sampl i ng
Nuclide Frequency
Sample
Locations Size
Noble Gas Tritium in Air m3
H-3
Kr-85
Xe-133
Xe-135
Water Surveillance
H-3
o
i> H-3 (Enrich)
Sr-89
Sr-90
Cs-137
Ra-226
U-234
U-235
U-238
Pu-238
1/wk
1/wk
1/wk
1/wk
Network
1/mo
1/mo
1st time
1st time
1/mo
1st time
1st time
1st time
1st time
1st time
17
17
17
17
(LTHMP)
all
all
all
all
all
all
all
all
all
all
5
0.4
0.4
0.4
Liters
1
0.1
1
1
1
1
1
1
1
1
Count
Time
Minutes
200
200
200
200
Minutes
200
200
50
50
100
1000
1000
1000
1000
1000
Concentration Guide* MDC
Bq/m3
7000
2E5
2E4
2E3
Bq/L
7E2
7E2
600
0.3
160
5
20
20
20
10
nCi/m3
190
6000
480
60
pCi/L
2E4
2E4
2E4
8
3E3
100
500
600
600
400
mBq/m3
148
148
148
148
Bq/L
12
0.37
0.18
0.074
0.33
NA
NA
NA
NA
0.003
MDC as
% CG
2E-3
7E-5
7E-4
7E-3
1.7
5E-2
0.03
25
0.3
0.03
(continued)
-------
TABLE D-l. Continued
o
I
Sampl i ng
Nuclide Frequency
Water Surveillance
Pu-239
Gamma
Milk Surveillance
H-3
Cs-137
Sr-89
Sr-90
Gamma
Dosimetry Network
TLD (Personnel)
TLD (Station)
Ion Chamber
Network
1st time
1/mo
Network
1/mo
1/mo
1/mo
1/mo
1/mo
1/mo
1/qtr
weekly
Locations
(LTHMP)
all
all
all
all
all
all
all
50
130
23
Sampl e
Size
Liters
1
3.5
3.5
3.5
3.5
3.5
3.5
Number
2
6
2016
: = = === = =: = = =
: = = = = = = = = = = = ==:
Count
Time
Minutes
1000
30
200
100
50
50
50
—
—
Concentration Guide* MDC
Bq/L
10
—
8E4
100
600
40
—
Exposure
Guide
lOOmR
—
—
pCi/L Bq/L
300 0.002
0.18
2E6 12
3E3 0.33
2E4 0.18
1E3 0.074
0.18
MDA
2mR
2mR
2yR/hr
MDC as
% CG
0.02
<0.2
2E-2
0.3
3E-2
0.2
<0.2
2
—
—
Na - Not Available
*ALI and DAC values from ICRP-30 modified to 1 mSv annual effective dose equivalent for continuous
exposure. Te and I data corrected to 2 g thyroid, greater milk intake, and smaller volume of air
breathed annually (1 year-old infant).
-------
APPENDIX E
DATA SUMMARY FOR THE MONITORING NETWORKS
-------
APPENDIX E
DATA SUMMARY FOR THE MONITORING NETWORKS
TABLE E-l. SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
CONTINUOUSLY OPERATING STATIONS - 1985
SAMPLING LOCATION
DEATH VALLEY JCT CA
FURNACE CREEK CA
SHOSHONE CA
ALAMO NV
AUSTIN NV
BEATTY NV
STONE CABIN RANCH NV
CURRANT NV - BLUE EAGLE RANCH
ELY NV
GOLDFIELO NV
GROOM LAKE NV
HIKO NV
INDIAN SPRINGS NV
LAS VEGAS NV
LATHROP WELLS NV
NY ALA NV
NO. DAYS
DETECTED
/SAMPLED
35.3/352.2
67.1/355.3
61.4/346.9
15.0/364.0
26.4/360.8
21.4/360.2
4.8/341.9
16.0/348.7
3.0/358.8
26.3/359.4
34.0/352.3
20.0/364.2
38.3/362.5
19.4/376.9
34.6/361.7
26.0/354.9
RAD 10-
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
RADIOACTIVITY
(PCI/M3)
MAX
0.79
0.70
0.45
0.46
0.64
0.80
0.78
0.87
0.48
0.70
0.89
0.60
0.69
0.72
0.67
0.79
MIN
0.24
0.16
0.23
0.33
0.42
0.32
0.34
0.34
0.48
0.40
0.24
0.38
0.33
0.26
0.30
0.29
CONC.
AVG*
0.043
0.058
0.055
0.016
0.038
0.027
0.0072
0.023
0.0040
0.042
0.037
0.026
0.051
0.024
0.039
0.033
(continued)
E-l
-------
TABLE E-l. Continued
RADIOACTIVITY CONC.
NO. DAYS (PCI/M3)
SAMPLING LOCATION
OVERTON NV
PAHRUMP NV
PIOCHE NV
SCOTTY'S JCT NV
SUNNYSIDE NV
RACHEL NV - ROBINSON TRAILER P
TONOPAH NV
TTR NV
FALLINI'S (TWIN SP6S) RANCH NV
CEDAR CITY UT
DELTA UT
MILFORD UT
ST GEORGE UT
SALT LAKE CITY UT
a;a=! = aia!a»s3=±as=52:ssss = 3ssssaaas3 =
UL. | UO 1 L.U
/SAMPLED
24.3/362.7
17.1/347.2
17.2/232.4
9.0/365.0
24.9/351.7
25.3/364.1
18.0/359.0
149.2/335.9
6.0/353.8
35.5/355.1
11.5/181.0
17.2/360.5
19.0/365.9
104.3/339.2
==2====SSSS=3
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
;ss = s = = ss
MAX
0.89
0.65
1.4
0.51
0.67
0.57
1.1
0.76
0.36
0.63
0.65
0.89
0.50
0.67
MIN
0.35
0.42
0.37
0.27
0.33
0.29
0.46
0.15
0.24
0.24
0.34
0.35
0.35
0.16
AVG*
0.036
0.026
0.043
0.0090
0.031
0.027
0.032
0.15
0.0051
0.037
0.031
0.027
0.022
0.11
=========
*AVG MEANS TIME-WEIGHTED AVERAGE OVER SAMPLING TIME.
E-2
-------
TABLE E-2. SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
STANDBY STATIONS OPERATED 1 OR 2 WEEKS PER QUARTER - 1985
NO. DAYS
RADIOACTIVITY CONC.
(PCI/M3)
SAMPLING LOCATION
KINGMAN AZ
LITTLE ROCK AR
ALTURAS CA
BAKER CA
RIDGECREST CA
GRAND JUNCTION CO
NAMPA ID
IOWA CITY IA
DODGE CITY KS
GREAT FALLS MT
KALISPELL MT
CALIENTE NV
CURRIE NV
ELKO NV
FALLON NV
ALBUQUERQUE NM
SHIPROCK NM
WILLISTON ND
RAPID CITY SD
LOGAN UT
PAROWAN UT
UL. 1 1_O 1 UU
/SAMPLED
2.0/22.1
6.8/34.2
5.3/28.2
3.5/26.0
3.1/26.7
7.3/37.4
3.0/37.0
4.8/46.0
3.0/40.0
3.0/27.9
7.0/41.9
3.1/32.9
10.4/45.5
5.0/29.2
3.0/26.4
2.1/29.0
5.0/17.9
6.9/32.8
2.0/27.9
3.1/28.2
6.8/35.9
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
MAX
0.63
0.66
0.51
0.41
0.47
0.65
0.49
0.21
0.42
0.56
0.19
0.42
0.33
0.51
0.33
0.65
0.62
0.16
0.73
0.25
0.32
MIN
0.63
0.33
0.28
0.41
0.47
0.29
0.49
0.21
0.42
0.56
0.19
0.42
0.33
0.40
0.33
0.65
0.42
0.16
0.73
0.25
0.32
(conti
AVG
0.058
0.085
0.068
0.055
0.054
0.086
0.039
0.021
0.031
0.061
0.032
0.040
0.076
0.075
0.037
0.047
0.14
0.034
0.052
0.028
0.060
nued)
E-3
-------
SAMPLING LOCATION
TABLE E-2. Continued
NO. DAYS
DETECTED RADIO
/SAMPLED NUCLIDE
RADIOACTIVITY CONC.
(PCI/M3)
MAX
MIN
AVG
WENDOVER UT
5.0/26.8
7BE
0.82
0.20
0.084
SPOKANE WA 3.0/28.1 7BE 0.37 0.37 0.040
==============================================================================3=
THE FOLLOWING STATIONS HAD NEGLIGIBLE GAMMA-SPECTRA:
GLOBE AZ
TUCSON AZ
WINSLOW AZ
YUMA AZ
BISHOP CA
CHICO CA
INDIO CA
LONE PINE CA
NEEDLES CA
SANTA ROSA CA
CORTEZ CO
DENVER CO
MOUNTAIN HOME ID
POCATELLO ID
FORT DODGE IA
MONROE LA
MINNEAPOLIS MN
CLAYTON MO
JOPLIN MO
ST JOSEPH MO
MILES CITY MT
NORTH PLATTE NE
ADAVEN (CANFIELD'S RANCH) NV
BATTLE MOUNTAIN NV
BLUE JAY NV
CURRANT NV - ANGLE WORM RANCH
DUCKWATER NV
EUREKA NV
FRENCHMAN STATION NV
GEYSER RANCH NV
LOVELOCK NV
LUND NV
MESQUITE NV
RENO NV
ROUND MOUNTAIN NV
WELLS NV
WINNEMUCCA NV
CARLSBAD NM
BISMARK ND
FARGO ND
MUSKOGEE OK
MEDFORD OR
BURNS OR
AMARILLO TX
AUSTIN TX
MIDLAND TX
TYLER TX
BRYCE CANYON UT
ENTERPRISE UT
GARRISON UT
VERNAL UT
SEATTLE WA
ROCK SPRINGS WY
WORLAND WY
TABLE E-3. SUMMARY OF GROSS BETA ANALYSES FOR AIR SURVEILLANCE NETWORK - 1985
============================================================================:===:
RADIOACTIVITY CONC.
NO. (PCI/M3)
SAMPLING LOCATION
SHOSHONE CA
LAS VEGAS NV
DELTA UT
MILFORD UT
ST GEORGE UT
=====================================
um j
SAMPLED
346.9
375.0
181.0
357.5
363.9
MAX
0.14
0.17
0.10
0.19
0.084
MIN
-0.0022
0.0017
0.00045
0.0016
0.00075
==========
AVG
0.016
0.015
0.015
0.018
0.016
E-4
-------
TABLE E-4. PLUTONIUM-239 CONCENTRATION IN COMPOSITED AIR SAMPLES* - 1985
SAMPLING LOCATION
WINSLOW/TUCSON, AZ
BISHOP/RIDGECREST, CA
DENVER AND CORTEZ, CO
MT HOME/NAMPA, ID
JOPLIN/CLAYTON, MO
GREAT FALLS/MILES CITY, MT
LAS VEGAS, NV
LATHROP WELLS, NV
RACHEL, NV
BISMARCK/ FARGO, ND
ALBUQUERQUE/ CARLSBAD, NM
MEDFORD/BURNS, OR
AUSTIN/ AMARILLO, TX
VERNAL/LOGAN, UT
SALT LAKE CITY, UT
SEATTLE/SPOKANE, WA
WORLAND/ROCK SPRINGS, WY
FIRST
QUARTER
11.5
-9.79
-18.5
-11.8
-11.9
-14.7
-3.5
-1.8
-8.3
-2.01
-6.64
-10.4
-9.92
-
-0.32
-3.61
-13.4
SECOND
QUARTER
-13.6
-38.0
-6.45
-7.73
-19.7
0.0
1.0
0.16
-1.8
0.0
.
-10.2
-14.8
-20
-0.88
-17.0
0.0
THIRD
QUARTER
17.8
-14.4
-2.94
-18.9
-15.8
-9.06
2.7
-12
-10
-3.72
-
-11.8
0.0
-9.0
-26
-9.78
0.0
FOURTH
QUARTER
0.00117
-4.76
-10.3
-8.76
-4.49
0.0
-6.0
3.7
-4.7
-22.9
-
0.0
-4.23
-9.2
-3.1
7.20
--
ANNUAL
AVERAGE
3.9
-14
-8.4
-13
-13
-8.1
-0.68
-2.8
-5.8
-
-6.64
-8.5
-5.2
-12
-8.1
-3.5
-3.6
*ALL DATA ARE EXPRESSED IN ACI/M^ AND ARE LESS THAN THE MDC WHICH VARIED FROM
10 TO 100 ACI/M^. ALL PLUTONIUM-238 RESULTS WERE ALSO LESS THAN MDC.
E-5
-------
TABLE E-5. SUMMARY OF ANALYTICAL RESULTS FOR THE NOBLE GAS AND TRITIUM
SURVEILLANCE NETWORK - 1985
NUMBER RADIOACTIVITY CONC.
SAMPLES (PCI/M3)* PERCENT
.jnrir uniu
LOCATION
SHOSHONE CA
ALAMO NV
AUSTIN NV
BEATTY NV
ELY NV
GOLDFIELD NV
INDIAN SPRINGS
LAS VEGAS NV
ruoi i i v i_/
NEGATIVE
48/4
46/6
51/0
51/0
46/6
44/8
53/0
53/0
41/11
40/12
53/0
53/0
38/15
38/15
53/0
53/0
47/6
44/9
53/0
53/0
46/6
42/10
52/0
52/0
N 48/4
47/5
51/0
51/0
45/7
43/9
52/0
52/0
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
46
18
0.56
4.5
36
58
0.52
3.4
35
19
0.42
2.6
36
47
0.33
1.9
37
48
0.43
3.8
61
30
0.53
4.7
40
41
0.41
3.1
37
66
1.4
•15
MIN
22
-7.2
-0.29
-1.3
20
-2.1
-0.30
-3.4
24
-31
-0.32
-2.3
24
-25
-0.32
-1.5
22
-14
-0.42
-2.3
24
-5.8
-0.31
-3.4
22
-8.5
-0.40
-2.4
21
-12
-0.34
-2.7
AVG
29
4.5
0.097
0.78
29
9.1
0.039
0.21
30
4.2
0.020
0.13
30
6.5
0.045
0.27
29
6.9
0.047
0.29
30
6.6
0.056
0.26
29
5.0
0.032
0.21
30
7.1
0.18
2.1
VrVJIIO.
GUIDE+
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
(continued)
E-6
-------
TABLE E-5. Continued
NUMBER
SAMPLES
SAMPLING POSITIVE/
LOCATION NEGATIVE RADIONUCLIDE
LATHROP WELLS NV
OVERTON NV
PAHRUMP NV
PIOCHE NV
RACHEL NV - ROB I
TONOPAH NV
CEDAR CITY UT
ST GEORGE UT
49/4
47/6
53/0
53/0
48/4
47/5
51/1
51/1
47/5
46/6
51/0
51/0
10/0
10/0
32/0
32/0
45/7
45/7
53/0
53/0
49/4
48/5
52/1
52/1
47/5
44/8
52/0
52/0
49/3
45/7
50/1
50/1
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
RADIOACTIVITY CONC.
(PCI/M3)*
MAX
42
29
0.55
5.8
36
17
0.68
4.2
38
24
0.56
11
34
22
0.58
3.4
38
24
0.56
5.1
40
47
0.53
3.4
40
27
0.52
3.0
35
24
0.48
3.3
MIN
21
-7.2
-0.39
-2.0
19
-4.7
-0.39
-3.3
25
-8.3
-0.37
-3.5
29
-4.1
-0.38
-1.9
23
-10
-0.30
-2.1
23
-16
-0.32
-2.2
21
-12
-0.44
-2.0
20
-3.2
-0.34
-3.1
AVG
(con
29
6.6
0.062
0.40
29
4.4
0.032
0.13
30
4.4
0.0087
0.37
31
8.0
0.036
0.35
30
4.3
0.057
0.33
30
4.8
0.051
0.20
29
4.6
0.058
0.31
29
5.5
0.057
0.39
PERCENT
CONC.
GUIDE+
tinued)
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
0.03
<0.01
-
<0.01
(continued)
E-7
-------
TABLE E-5. Continued
:=====================================================:
SAMPLING
LOCATION
SALT LAKE CITY
==============
NUMBER
SAMPLES
POSITIVE/
NEGATIVE
U 9/15
8/16
44/7
44/7
===========
RADIOACTIVITY CONC.
(PCI/M3)*
RADIONUCLIDE
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
MAX
36
16
0.42
4.9
MIN
27
-31
-0.21
-2.0
AVG
30
4.2
0.084
0.54
PERCENT
CONC.
GUIDE+
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
POPULATION IN AN UNCONTROLLED AREA.
E-8
-------
TABLE E-6.
SUMMARY OF TRITIUM RESULTS FOR THE NTS NETWORK LONG-TERM
HYDROLOGICAL MONITORING PROGRAM - 1985
SAMPLING
LOCATION
NO.
SAMPLES
TRITIUM CONCENTRATION
(PCI/L)
MAX
MIN
AVG
============
PERCENT
CONC.
GUIDE
WELL 1 ARMY 12
WELL 2 12
WELL 3 12
WELL 4 12
WELL 4 CP-1* 12
WELL 5C 9
WELL 8 12
WELL 20* 5
WELL A 12
WELL B TEST 12
WELL C 12
WELL J-13 12
WELL U19C 12
WELL UE7NS 6
*Radiochemistry results:
WELL 4 CP-1
226RA 0.082 ± 0.049 PCI/L
234U 5.6 ± 0.23 PCI/L
235U 0.14 ± 0.034 PCC/L
238U 1.6 ± 0.12 PCI/L
14
9.7
12
14
9.7
5.4
15
5.5
15
170
34
5.6
12
3100
:============:
-5.4
-12
-7.8
-6.3
-7.9
-12
-7.4
-10
-7.2
140
8.2
-14
-5.1
2000
1.9
0.32
3.4
3.0
1.2
-0.78
3.2
-1.6
4.0
160
21
-1.8
2.4
2600
<0.01
<0.01
<0.02
<0.02
<0.01
<0.01
<0.02
<0.01
<0.02
0.8
0.1
<0.01
0.01
10
WELL 20
90SR
226RA
234U
235U
238PU
238U
239PU
0.040
0.036
3.7
0.038
0.0084
0.87
0.0084
1.0
0.053
0.3
0.030
0.073
0.11
0.048
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
E-9
-------
TABLE E-7. TRITIUM RESULTS FOR THE LONG-TERM HYDROLOGICAL MONITORING
PROGRAM - 1985
c
SAMPLING LOCATION
NEVADA TEST SITE NETWORK*
SHOSHONE CA
SHOSHONE SPRING
ADAVEN NV
ADAVEN SPRING
ALAMO NV
CITY WELL 4
ASH MEADOWS NV
CRYSTAL POOL
FAIRBANKS SPRINGS
WELL 17S-50E-14CAC
WELL 18S-51E-7DB
BEATTY NV
CITY SUPPLY 12S-47E-7DBD
COFFERS WELL 11S-48-1DD
ROAD D WELL SPICERS
SARCOBATUS FLAT TOLICHA
PEAK
USECOLOGY
:OLLECTION
DATE
1985
01/11
06/03
06/05
10/02
04/10
09/09
02/04
07/09
03/05
08/09
01/25
02/04
07/09
02/04
07/09
03/05
08/08
02/14
07/08
03/01
07/08
02/07
07/08
01/03
06/06
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
-100 ± 180*
-2.9 ± 8.3*
69 ± 7
-220 ± 230*
3.7 ± 7.5*
-42 ± 320*
-1.1 ± 5.0*
70 ± 180*
0.22 ± 5.4*
-16 ± 190*
-0.39 ± 4.6*
-2.9 ± 4.9*
47 ± 180*
-2.9 ± 4.8*
-23 ± 180*
6.6 ± 5.2*
74 ± 190*
4.7 ± 4.7*
70 ± 180*
0 ± 170*(a)
-14 ± 4*
-0.88 ± 4.6*(b)
-6.1 ± 4.5*
-0.22 ± 4.7*
-62 ± 180*
PCT OF
CONC.
GUIDE
<0.01
<0.01
0.3
<0.01
0.02
<0.01
<0.01
0.4
<0.01
<0.01
<0.01
<0.01
0.2
<0.01
<0.01
0.03
0.4
0.02
0.4
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
(continued)
E-10
-------
TABLE E-7.
Continued
SAMPLING LOCATION
BOULDER CITY NV
LAKE MEAD INTAKE
CLARK STATION NV
TTR WELL 6
HIKO NV
CRYSTAL SPRINGS
INDIAN SPRINGS NV
SEWER CO INC WELL 1
USAF WELL 2
LAS VEGAS NV
WATER DISTRICT WELL 28
LATHROP WELLS NV
CITY 15S 50E-18CDC
NYALA NV
SHARP'S RANCH
OASIS VALLEY NV
GOSS SPRINGS
PAHRUMP NV
CALVADA WELL 3
RACHEL NV
PENOYER WELLS 7 AND 8
PENOYER WELL 13
COLLECTION
DATE
1985
03/07
08/08
06/04
10/01
04/10
09/09
01/07
06/03
01/03
06/03
01/22
06/10
01/03
06/06
09/10
03/05
08/07
06/03
10/01
08/07
08/07
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
120 ± 6
74 ± 190*
7.8 ± 8.1*
-45 ± 230*
7.5 ± 7.6*
-14 ± 320*
-0.32 ± 4.7*
-120 ± 180*
3.8 ± 4.7*
-69 ± 180*
-17 ± 180*
120 ± 8
-0.66 ± 4.6*
50 ± 180*
-120 ± 320*
0.46 ± 5.3*
-29 ± 190*
0.71 ± 8.3*
-160 ± 230*
-7.2 ± 7.3*(c)
-2.6 ± 7.5*(d)
PCT OF
CONC.
GUIDE
0.6
0.4
0.04
<0.01
0.04
<0.01
<0.01
<0.01
0.02
<0.01
<0.01
0.6
<0.01
0.2
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
(continued)
E-ll
-------
TABLE E-7. Continued
SAMPLING LOCATION
RACHEL NV
PENOYER CULINARY WELL
TEMPIUTE NV
UNION CARBIDE WELL
TONOPAH NV
CITY WELL
WARM SPRINGS NV
TWIN SPRINGS RANCH
NTS NV
WELL 5B
WELL C-l
TEST WELL D
WELL U16D
WELL UE1C
WELL UE5C
WELL UE15D
COLLECTION
DATE
1985
.08/07
01/22
06/04
06/04
10/01
04/09
09/10
02/04
07/09
02/05
07/10
03/06
08/06
02/06
07/10
03/06
08/06
02/04
07/09
01/12
06/14
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
-7.0 ± 7.3*(e)
-17 ± 180*
-6.4 ± 8.0*
-5.1 ± 8.3*
-170 ± 230*
-45 ± 190*
5.6 ± 320*
-97 ± 180*
-5.3 ± 7.5*
74 ± 190* -
0.25 ± 7.2*
-22 ± 170*
-7.7 ± 7.5*
-100 ± 180*
-11 ± 7*
61 ± 190*
-6.6 ± 7.4*
7.1 ± 180*
-7.9 ± 7.1*
78 ± 180*
93 ± 8
PCT OF
CONC.
GUIDE
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.03
<0.01
<0.01
0.4
<0.01
<0.01
<0.01
<0.01
<0.01
0.3
<0.01
0.04
<0.01
0.4
0.5
(continued)
*FOR ALL LOCATIONS EXCEPT PENOYER WELL 7 AND 8 AND PENOYER WELL 13, SAMPLES
COLLECTED DURING THE MONTHS NOT LISTED WERE GAMMA-SCANNED ONLY, AND NO GAMMA-
EMITTERS WERE DETECTED. SAMPLES WERE COLLECTED FROM THE PENOYER WELLS ONLY
ON THE DATE LISTED.
E-12
-------
Mile 27 Stream
Bering SeaSS
Pacific Ocean
Constantine Harbor
Scale m Miles
0 5
=Duck Cove Cr.
=5=~=s====ss= M i I ro w
0 5 10
3/83 Scale in Kilometers
Base Camp Area
Surface Ground Zero
Sampling Locations
Bering Sea=
=Constantme HarborSS
Constamine Spring
Clevenger LakeV \^--< /''Camp
Scale in Miles
0 1
Baker Runway
South Hangar
Maintenance Building
0 1
Scale in Kilometers
Sampling Locations
~5pacific Ocean
Figure E-l. Amchitka Island and background sampling locations for the LTHMP.
E-13
-------
TABLE E-7. Continued
COLLECTION
DATE
SAMPLING LOCATION 1985
BACKGROUND SAMPLES - AMCHITKA
ARMY WELL 1
ARMY WELL 2
ARMY WELL 3
ARMY WELL 4
CONSTANTINE SPRING
DUCK COVE CREEK
JONES LAKE
RAIN SAMPLE
SITE D HYDRO EXPLOR HOL
PROJECT CANNIKIN - AMCHITKA,
NORTH END CANNIKIN LAKE
SOUTH END CANNIKIN LAKE
DK-45 LAKE
ICE BOX LAKE
PIT S OF CANNIKIN GZ
WELL HTH-3
WHITE ALICE CREEK
, AK
10/12
10/12
10/12
10/13
10/12
10/12
10/12
10/29
10/17
AK
10/13
10/13
10/17
10/13
10/13
10/13
10/13
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
42 ± 7
20 ± 7
56 ± 7
53 ± 7
62 ± 7
31 ± 7
24 ± 7
LOST
78 ± 8
39 ± 8
36 ± 7
31 ± 6
33 ± 7
20 ± 7
43 ± 6
24 ± 7
PCT OF
CONC.
GUIDE
0.2
0.1
0.3
0.3
0.3
0.2
0.1
0.4
0.2
0.2
0.2
0.2
0.1
0.2
0.1
(continued)
E-14
-------
Surface Ground Zero
Sampling Locations
Figure E-2. LTHMP sampling locations for Project Cannikin.
E-15
-------
Surface Ground Zero
Sampling Locations
Long Shot
Pond #3
/ Long Shot
•[ Pond #^
Long Shot SGZ
EPA-1
Surface Ground Zero
Sampling Locations
Figure E-3. LTHMP sampling locations for Projects Mil row and Long Shot.
E-16
-------
TABLE E-7. Continued
SAMPLING LOCATION
PROJECT LONGSHOT - AMCHITKA
STREAM EAST OF LONGSHOT
EPA WELL-1
LONG SHOT POND 1
LONG SHOT POND 2
LONG SHOT POND 3
MUD PIT 1
MUD PIT 2
MUD PIT 3
REED POND
WELL GZ 1
WELL GZ 2
WELL WL-1
WELL WL-2
PROJECT MILROW - AMCHITKA,
CLEVENGER CREEK
HEART LAKE
WELL W-2
WELL W-3
WELL W-4
WELL W-6
WELL W-7
COLLECTION
DATE
1985
T AK
10/14
10/14
10/14
10/14
10/14
10/14
10/14
10/14
10/14
10/14
10/14
10/14
10/14
AK
10/14
10/14
10/14
10/14
10/14
10/14
10/14
•CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
130 ± 7(J)
320 ± 9
22 ± 6
27 ± 7
34 ± 7
380 ± 8
540 ± 11
500 ± 10
28 ± 6
2800 ± 220
170 ± 8
25 ± 7
240 ± 8
30 ± 8
21 ± 6
24 ± 8
25 ± 7
31 ± 7
41 ± 7
30 ± 7
PCT OF
CONC.
GUIDE
0.6
2
0.1
0.1
0.2
2
3
2
0.1
10
0.9
0.1
1
0.1
0.1
0.1
0.1
0.2
0.2
0.2
(continued)
E-17
-------
Johnson
Artesian
CER-1 A ifFawn Cr. No. 1
Fawn Cr.
8400' Downstream
Fawn Cr. 500 Downstream
RB-D-01
SGZ
awn Cr. 500' Upstream
Fawn Cr. 6800'
Upstream
Fawn Cr. No. 3
Rio Blanco County
Garfield County
Rio Blanco County
Seal* in Kilometers
Surface Ground Zero
Artesian Well
O Windmill
Water Well
A Spring
• Stream
Location Maps
Figure E-4. LTHMP sampling locations for Project Rio Blanco.
E-18
-------
TABLE E-7. Continued
COLLECTION
DATE
SAMPLING LOCATION 1985
PROJECT MILROW - AMCHITKA, AK
WELL W-8
WELL W-10
WELL W-ll
WELL W-13
WELL W-14
WELL W-15
WELL W-17
WELL W-18
PROJECT RIO BLANCO - COLORADO
RIO BLANCO CO
B-l EQUITY CAMP
BRENNAN WINDMILL
CER 1 BLACK SULPHUR
CER 4 BLACK SULPHUR
FAWN CREEK 1
FAWN CREEK 6800FT UPSTR
FAWN CREEK 500FT UPSTRE
FAWN CREEK 500FT DNSTR
FAWN CREEK 8400FT DNSTR
JOHNSON ARTESIAN WELL
WELL RB-D-01
10/14
10/14
10/14
10/14
10/14
10/14
10/14
10/14
06/24
06/24
06/24
06/24
06/21
06/21
06/21
06/21
06/21
06/21
06/25
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
31 ± 7
34 ± 7
93 ± 7
53 ± 7
26 ± 7
22 ± 6
26 + 7
49 ± 7
100 ± 7
12 ± 7
63 ± 7
110 ± 8
67 ± 7
86 ± 7
70 ± 7
81 ± 7
76 ± 7
4.9 ± 8.1*
1.0 ± 4.3*
PCT OF
CONC.
GUIDE
0.2
0.2
0.5
0.3
0.1
0.1
0.1
0.2
0.5
0.06
0.3
0.5
0.3
0.4
0.4
0.4
0.4
0.02
<0.01
(continued)
E-19
-------
Grand Valle
City Water
G. Schwab
Rn.
Rulison
Potter
Rn.
Rifle
Grand ValleyrfdTjC" J»Sefcovic Rn.
~ I I *L Hayward Rn.
J Battlement Creek
A.U
Gardner
Rn.
kCER Test Well
Spring^ SGZ
Scale in Miles
0 5
Scale in Kilometers
i
Surface Ground Zero
Water Sampling Locations
Colorado
Garfield
County
3/86
Location Maps
Figure E-5. LTHMP sampling locations for Project Rulison.
E-20
-------
TABLE E-7. Continued
COLLECTION
DATE
SAMPLING LOCATION 1985
PROJECT RULISON - COLORADO
GRAND VALLEY CO
CITY SPRING
ALBERT GARDNER RANCH
RULISON CO
LEE HAYWARD RANCH
POTTER RANCH
ROBERT SEARCY RANCH
(G. SCHWAB)
FELIX SEFCOVIC RANCH
GRAND VALLEY CO
BATTLEMENT CREEK
SPRING 300 YRDS NW OF GZ
CER TEST WELL
PROJECT DRIBBLE - MISSISSIPPI
BAXTERVILLE MS
BAXTERVILLE CITY WELL
COLUMBIA MS
CITY WELL 64B
LUMBERTON MS
CITY WELL 2
PURVIS MS
CITY SUPPLY
BAXTERVILLE MS
HALF MOON CREEK
06/20
06/19
06/20
06/20
06/20
06/20
06/19
06/19
06/19
04/23
04/23
04/23
04/22
04/22
04/22
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
-6.2 ± 7.7*
200 ± 8
280 ± 9
150 ± 8
170 ± 9
210 ± 8
130 ± 8
130 ± 8
210 ± 9
55 ± 7
30 ± 7
22 ± 7
18 ± 7
78 ± 7
70 ± 7
PCT OF
CONC.
GUIDE
<0.01
1
1
0.8
0.9
1
0.6
0.6
1
0.3
0.2
0.1
0.09
0.4
0.3
LOWER LITTLE CREEK
04/23
69 ± 8
0.3
(continued)
E-21
-------
B. Chambliss •
T. Speights!
M. Lowe
Baxterville
Well Ascot 2
Lower Little Creek
Salt Dome Timber Co.
I.Anderson /
I.R. Anderson*
GZ •R.L.Anderson
•w. Daniels Jr. ^Purvis
R. Ready
Scale in Mile*
5 10
B 10 15 20
Scale in Kilometers
25
3/88
Surface Ground Zero
Water Sampling Locations
Location Maps
Figure E-6.
LTHMP sampling locations for Project Dribble
towns and residences.
E-22
-------
TABLE E-7. Continued
SAMPLING LOCATION
BAXTERVILLE MS
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
HALF MOON CREEK OVRFLW
WELL E-7
WELL HM-1
WELL HM-2A
WELL HM-2B
WELL HM-3
WELL HMH-1
COLLECTION
DATE
1985
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/23
04/22
04/22
04/22
04/23
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/22
04/21
04/22
====================
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
97 ± 7
150 ± 8
110 ± 7
36 ± 7
120 ± 7
37 ± 7
NO SAMPLE; PUMP
23 ± 7
49 ± 7
88 ± 7
71 ± 7
13 ± 7
760 ± 160
350 ± 9
20 ± 7
16 ± 7
21 ± 7
5.6 ± 7.6*
4.4 ± 7.3*
-1.2 ± 7.3*
-6.9 ± 7.6*
-3.5 ± 7.1*
9.1 ± 7.4*
31000 ± 350
35000 ± 360
:=================
PCT OF
CONC.
GUIDE
0.5
0.7
0.5
0.2
0.6
0.2
OUT
0.1
0.2
0.4
0.4
0.06
4
2
0.1
0.08
0.1
0.03
0.02
<0.01
<0.01
<0.01
0.05
200
200
(continued)
E-23
-------
HMH-6 HMH-5 \
• I
HMH-4
Half
-~
Scale in Feet
100 200 300
50 100
Scale in Meters
Half Moon
Creek /
Overflow j
SGZ \
HMH-2 |
•I • HMH-9 (
Lamar
County
Tatum
Dome
Surface Ground Zero
• Water Sampling Locations
3/86
Mississippi
/
I
V.
Location Maps
® SGZ
Figure E-7. LTHMP sampling locations for Project Dribble - near GZ.
E-24
-------
\ ( REECO Pit-C
*'\>*REECOPit-B
*•
Half Moon /
Creek
* **• REECO Pit-A
'HM-2A
Half Moon Creek
Overflow
Scale in Feet
0 400 1200 2000
0 200 400 600
Scale in Meters
Lamar
County
/—} /TT_
Mississippi / / Tatum
i /' Dome
Surface Ground Zero
Water Sampling Locations
3/86
Figure E-8. LTHMP sampling locations for Project Dribble - near Salt Dome,
E-25
-------
TABLE E-7. Continued
SAMPLING LOCATION
BAXTERVILLE MS
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
WELL HM-L2
WELL HM-S
HT-2C
WELL HT-4
WELL HT-5
COLLECTION
DATE
1985
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/21
04/22
04/22
04/22
04/22
04/23
04/23
04/23
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
13000 ± 250
14000 ± 260
35 ± 7
83 ± 8
-7.4 ± 7.8*
63 ± 7
2500 ± 180
2700 ± 180
170 ± 8
200 ± 8
160 ± 8
220 ± 8
1.6 ± 7.9*
35 ± 7
1.7 ± 8.3*
73 ± 7
-6.7 ± 7.7*
12 ± 7
2900 ± 180
1400 ± 170
1600 ± 170
2.6 ± 7.9*
16000 ± 270
29 ± 7
29 ± 7
18 ± 7
PCT OF
CONC.
GUIDE
60
70
0.2
0.4
<0.01
0.3
10
10
0.8
1
0.8
1
<0.01
0.2
<0.01
0.4
<0.01
0.06
10
7
8
0.01
80
0.1
0.1
0.09
(continued)
E-26
-------
SGZ
HTH 2
HTH 1
N
Scale in Miles
Hot Creek »
Ranch
0 5
3/85 Scale in Kilometers
Surface Ground Zero
Water Sampling Locations
Six-Mile WellB*
I Jim Bias Well
(Blue Jay Springs)
I Blue Jay
Mamt Sta
Location Maps
Figure E-9. LTHMP sampling locations for Project Faultless.
E-27
-------
Failon
Spring
Windmill Frenchman
Flowing Well
Hunts!
Station
• H-3
©
SGZ
HS-1
Scale in Miles
B 10
Churchill County
Mineral County
i
0 5 10 16
3/86 Scale in Kilometers
N
0 Surface Ground Zero
• Water Sampling Locations
Churchill
County
Location Maps
Figure E-10. LTHMP sampling locations for Project Shoal
E-28
-------
TABLE E-7. Continued
c
SAMPLING LOCATION
BAXTERVILLE MS
POND WEST OF GZ
REECO PIT DRAINAGE-A
REECO PIT DRAINAGE-B
REECO PIT DRAINAGE-C
SALT DOME TIMBER CO
PROJECT FAULTLESS - NEVADA
BLUE JAY NV
BIAS WELL
MAINTENANCE STATION
SIX MILE WELL
HTH-1 WELL
HTH-2 WELL
HOT CREEK RANCH
PROJECT SHOAL - NEVADA
FRENCHMAN STATION NV
HUNTS STATION
FLOWING WELL
FRENCHMAN STATION
WELL H-3
WELL HS-1
lOLLECTION
DATE
1985
04/22
04/22
04/22
04/22
04/22
04/22
07/15
07/15
07/15
07/15
07/15
07/15
02/20
02/21
02/21
02/20
02/21
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
51 ± 7
57 ± 7
70 ± 7
2500 ± 170
1600 ± 170
42 ± 7
-3.7 ± 7.3*
-13 ± 7*
NO SAMPLE; PUMP
-12 ± 8*
-7.1 ± 7.3*
0 ± 7.4*
-3.0 ± 5.2*
2.6 ± 5.1*
0.79 ± 5.7*
-3.9 ± 5.2*
2.7 ± 5.2*
PCT OF
CONC.
GUIDE
0.3
0.3
0.4
10
8
0.2
<0.01
<0.01
OUT
<0.01
<0.01
<0.01
<0.01
0.01
<0.01
<0.01
0.01
FALLON NV
SPRING WINDMILL
02/20
0.12 ± 5.3*(f)
<0.01
(continued)
E-29
-------
To Dulce
Bixler Rn.
To Blanco &
Gobemador
Bubbling
Spring
EPNG Well 10-36
La Jara Creek
• Windmill #2
SGZ
•Jicarilla
Well #1
Cave Spring!
Arnold Rn. •
Lower Burro I
Canyon
Scalo in Kilometers
0 8
0 5
Scale in Miles
i
3/88
Surface Ground Zero
Water Sampling Locations
New
Mexico
y I
JSSGZ^
Rio Arriba
County
Location Maps
Figure E-ll. LTHMP sampling locations for Project Gasbuggy.
E-30
-------
TABLE E-7. Continued
COLLECTION
DATE
SAMPLING LOCATION 1985
PROJECT GASBUGGY - NEW MEXICO
GOBERNADOR NM
ARNOLD RANCH
BIXLER RANCH
BUBBLING SPRINGS
CAVE SPRINGS
LA JARA CREEK
LOWER BURRO CANYON
WELL 30.3.32.343 NORTH
JICARILLA WELL 1
WINDMILL 2
EPNG WELL 10-36
PROJECT GNOME - NEW MEXICO
CARLSBAD NM
CARLSBAD CITY WELL 7
LOVING NM
CITY WATER WELL 2
MALAGA NM
PECOS PUMPING STATION
PHS WELL 6
PHS WELL 8
PHS WELL 9
PHS WELL 10
USGS WELL 1
05/21
05/22
05/19
05/22
05/19
05/20
05/23
05/20
05/22
05/23
05/17
05/17
05/17
05/15
05/15
05/15
05/15
05/15
CONC. ± 2 SIGMA
TRITIUM
(PCI/L)
1.6 ± 6.9*
21 ± 6
75 ± 7
80 ± 7
90 ± 7
63 ± 7
54 ± 7(9)
7.2 ± 6.8*
NO SAMPLE; PUMP
390 ± 9
-2.2 ± 7.3*
6.3 ± 7.2*
3.3 ± 7.1*
72 ± 7
21 ± 7
7.6 ± 7.0*
5.8 ± 7.4*
6.3 ± 6.9*
PCT OF
CONC.
GUIDE
<0.01
0.1
0.4
0.4
0.4
0.3
0.3
0.04
OUT
2
<0.01
0.03
0.02
0.4
0.1
0.04
0.03
0.03
(continued)
E-31
-------
Carlsbad
Carlsbad City
Well #7
Loving
N
Scale in Miles
5 10
USGS 4 8
Wells AA
1A
Loving City
Well #2
0 5 10 15
Scale in Kilometers
PHS Well #6 •
PHS Well #9.1 _
>• •
PHS Well #8
Pecos River
Pumping Station
Well#1
0 Surface Ground Zero
A On-Site Water Sampling Locations
Off-Site Water Sampling Locations
New
Mexico s
Eddy County
»
'SGZ1
3/86
Location Maps
Figure E-12. LTHMP sampling locations for Project Gnome.
E-32
-------
TABLE E-7. Continued
SAMPLING LOCATION
COLLECTION CONC. ± 2 SIGMA PCT OF
DATE TRITIUM CONC.
1985 (PCI/L) GUIDE
MALAGA NM
USGS WELL 4
USGS WELL 8
WELL LRL-7
05/16 260000 ± 910
05/16 190000 ± 780(")
05/16 17000 ± 280(0
1000
900
90
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
FOOTNOTES
ANALYSIS RESULT 2SIGMA UNITS
90SR
226RA
234U
235U
238PU
238U
239PU
90SR
226RA
234U
235U
238PU
238U
239PU
90SR
226RA
234U
235U
238PU
238U
239PU
90SR
226RA
234U
235U
238PU
238U
239PU
0.26
0.036
3.9
0.075
-0.052
1.9
-0.026
0.28
0.097
2.7
0.019
-0.039
0.80
-0.016
-0.019
0.094
3.4
0.044
-0.015
1.1
-0.0038
-0.051
0.038
2.0
0.033
-0.034
0.99
-0.0098
1.7*
0.056*
0.2
0.026
0.076*
0.2
0.050*
1.5*
0.061
0.2
0.019*
0.068*
0.09
0.045*
2.2*
0.3
0.046*
0.033*
0.2
0.022*
1.4*
0.064*
0.2
0.018
0.043*
0.10
0.028*
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
(continued)
E-33
-------
TABLE E-7. Continued
====================
SAMPLING LOCATION
e 90SR
226RA
234U
235U
238PU
238U
239PU
f 90SR
226RA
234U
235U
238PU
238U
239PU
9 226RA
234U
235U
238U
238PU
239PU
h 137CS
i 137CS
J 226RA
234U
235U
238U
238PU
239PU
COLLECTION CONC. ± 2 SIGMA PCT OF
DATE TRITIUM CONC.
1985 (PCI/L) GUIDE
0.0076
0.14
1.6
0.011
0.010
0.54
1.5E-06
-0.011
0.086
0.037
0.0037
-0.021
0.079
-0.021
0.054
5.9
0.15
3.5
0.11
0.081
58
210
0.019
0.12
0.026
0.055
-0.005
0.0
0.86*
0.07
0.2
0.033*
0.043*
0.10
0.028*
0.98*
0.074*
0.058*
0.038*
0.090*
0.040
0.059*
0.058*
0.4
0.05
0.3
0.22*
0.15*
11
17
0.076*
0.039
0.033*
0.025
0.032*
0.014*
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
PCI/L
E-34
-------
TABLE E-8. SUMMARY OF ANALYTICAL RESULTS FOR THE MILK SURVEILLANCE
NETWORK - 1985
SAMPLING
LOCATION
BENTON, CA,
IRENE BROWN RANCH
BISHOP, CA,
WHITE MOUNTAIN RANCH
HINKLEY, CA,
BILL NELSON DAIRY
RIDGECREST, CA,
CEDARSAGE FARM
AUSTIN, NV,
YOUNG'S RANCH
CURRANT, NV,
BLUE EAGLE RANCH
CURRANT, NV,
MANZONIE RANCH
DYER, NV,
OZEL LEMON
GOLDFIELD, NV,
FRAYNE RANCH
HIKO, NV,
JAY WRIGHT RANCH
LAS VEGAS, NV,
LDS DAIRY FARMS
LATHROP WELLS, NV,
JOHN DEER RANCH
SAMPLE
TYPE
10
13
12
10
13
13
13
13
10
13
12
10
NO. OF
SAMPLES
1
2
1
1
5
5
5
3
3
3
5
5
5
2
1
1
4
4
4
3
1
1
1
1
1
1
6
5
5
2
1
1
RAD 10-
NUCLIDE
3H
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
RADIOACTIVITY CONC.
(PCI/L)
MAX
130
310
1.3
1.3
380
0.41
1.6
260
-0.26
0.94
440
9.2
1.6
310
0.72
0.81
460
-0.13
1.4
290
-0.065
1.2
180
290
0.34
0.22
510
0.74
1.1
240
-1.7
1.5
MIN
130
270
1.3
1.3
140
-2.8
-0.021
-34
-0.93
0.34
130
-0.66
0.38
100
0.72
0.81
130
-3.4
0.35
180
-0.065
1.2
180
290
0.34
0.22
91
-0.59
-0.021
220
-1.7
1.5
AVG
130
290
1.3
1.3
240
-1.2
0.85
150
-0.55
0.65
270
2.9
0.80
210
0.72
0.81
260
-1.2
0.89
240
-0.065
1.2
180
290
0.34
0.22
260
0.15
0.46
230
-1.7
1.5
E-35
-------
TABLE E-8. Continued
SAMPLING SAMPLE NO. OF
LOCATION TYPE SAMPLES
LOGANDALE, NV,
KNUDSEN DAIRY
LUND, NV,
MCKENZIE DAIRY
MCGILL, NV,
LARSEN RANCH
MESQUITE, NV,
SF AND K DAIRY
MOAPA, NV,
ROCKVIEW DAIRIES, INC
NYALA, NV,
SHARP'S RANCH
CALIENTE, NV,
JUNE COX RANCH
ROUND MT, NV,
BERG'S RANCH
SHOSHONE, NV,
HARBECKE RANCH
CEDAR CITY, UT,
WESTERN GEN DAIRIES
ST GEORGE, UT,
GENTRY DAIRY
12
12
13
12
12
13
13
13
13
12
12
5
3
3
6
4
4
6
6
6
5
3
3
5
4
4
4
3
3
3
4
4
4
3
3
2
1
1
7
5
6
5
4
4
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 CONC.
(PCI/L)
MAX
520
0.36
2.7
400
1.6
2.3
520
5.7
2.3
320
0.44
1.7
500
3.0
1.4
260
4.5
1.5
390
2.0
1.4
440
4.4
3.5
390
3.4
3.1
530
9.9
2.2
450
5.1
0.61
MIN
130
-9.6
0.15
200
-3.7
-0.39
47
-2.0
6.5E-04
120
-4.6
0.12
80
-1.8
-0.076
140
-0.43
0.022
98
-0.44
0.18
160
-10
-1.4
310
3.4
3.1
130
-1.8
-4.0
87
-0.90
-2.3
AVG
250
-3.3
1.1
300
-1.5
1.1
310
0.89
0.97
220
-1.5
0.72
330
0.33
0.37
200
1.4
0.98
210
0.74
0.69
300
-0.62
0.50
350
3.4
3.1
270
1.6
-0.075
290
1.2
0.41
E-36
-------
TABLE E-9. ANALYTICAL RESULTS FOR THE STANDBY MILK SURVEILLANCE NETWORK -
1985
COLLECTION CONC. ± 2 SIGMA
DATE 3H 89SR 90SR
SAMPLING LOCATION 1985 (PCI/L) (PCI/L) (PCI/L)
GAMMA SPECTROMETRY AND STRONTIUM ANALYSES
LITTLE ROCK AR
BORDENS 07/15 350 ± 270* -2.4 ± 7.1* 4.4 ± 2.5
GRAND JCT CO
COLORADO WEST DAIRIES 06/18 410 ± 230 -3.8 ± 9.3* 1.4 ± 1.9*
PUEBLO CO
HYDE PARK DAIRY CO 06/20 410 ± 240 4.6 ± 2.1* 1.8 ± 1.1
DAVENPORT IA
SWISS VALLEY FARMS CO 06/03 230 ± 270* 13 ± 10* 1.7 ± 1.1*
GARDEN CITY KS
MYERS MILK PROD 06/03 190 ± 270* -0.41 ± 11* 1.7 ± 1.3*
MANHATTAN KS
KANSAS STATE UNIVERSITY 06/03 160 ± 260* 7.3 ± 6.7* 1.7 ± 0.9
BATON ROUGE LA
LA STATE UNIV 07/18 200 ± 270* 3.9 ± 11* 0.49 ± 4.3*
MONROE LA
BORDEN'S 07/22 69 ± 280* -4.0 ± 2.8* 3.4 ± 1.2
FOSSTON MN
LAND 0' LAKES INC 05/29 330 ± 260* -0.54 ± 1.2* 3.5 ± 1.2
ROCHESTER MN
ASSOC. MILK PRODUCERS 07/05 286 ± 254* 1.4 ± 4.15* 2.0 ± 1.54*
AURORA MO
MID-AMERICA DAIRY INC 06/05 380 ± 270* -2.8 ± 2.9* 3.4 ± 1.4
CHILLICOTHE MO
MID-AMERICA DAIRYMEN 06/06 390 ± 240 1.2 ± 9.6* 1.6 ± 2.1*
NORFOLK NE
GILLETTE DAIRY 06/06 360 ± 270* 5.7 ± 16* 2.1 ± 1.5
(continued)
E-37
-------
TABLE E-9. Continued
SAMPLING LOCATION
COLLECTION CONC. ± 2 SIGMA
DATE 3H 89SR 90SR
1985 (PCI/L) (PCI/L) (PCI/L)
NO PLATTE NE
MID-AMER DAIRYMEN-R A N 06/04
ALBUQUERQUE NM
BORDEN VALLEY GOLD 07/12
LA PLATA NM
ROTHLISBERGER DAIRY 07/13
GRAND FORKS ND
MINNESOTA DAIRY 06/17
ENID OK
AMPI GOLDSPOT DIVISION 07/15
MCALESTER OK
OK STATE PENITENTIARY 07/16
PROVO UT
BYU DAIRY PRODUCTS LAB 06/19
370 ± 270* 6.1 ± 18* 4.1 ± 1.6
210 ± 280* 0.81 ± 3.1* 1.4 ± 1.3*
340 ± 270* 3.4 ± 3.4* 0.40 ± 1.4*
230 ± 270* -4.6 ± 3.7* 2.2 ± 1.5
380 ± 230
4.1 ± 6.5* 2.2 ± 2.4*
310 ± 270* 4.2 ± 9.7* 0.16 ± 3.5*
210 ± 270* -1.1 ± 2.3* 1.2 ± 1.0
(continued)
E-38
-------
TABLE E-9. Continued
SAMPLING LOCATION
COLLECTION
DATE
1984
SAMPLING LOCATION
COLLECTION
DATE
1984
GAMMA SPECTRAL ANNALYSES ONLY**
PIMA AZ
SMITH HUNT DAIRY
TAYLOR AZ
SUNRISE DAIRY
08/06
08/12
TEMPE AZ
UNITED DAIRYMEN OF AZ 08/06
TUCSON AZ
SHAMROCK DAIRY (PIMA CO) 08/08
YUMA AZ
GOLDEN WEST DAIRY 08/07
FAYETTEVILLE AR
UNIVERSITY OF ARK 07/15
PARAGOULD AR
FOREMOST FOODS INC 07/16
RUSSELLVILLE AR
ARKANSAS TECH UNIV 07/17
BAKERSFIELD CA
CARNATION DAIRY 08/05
CHINO CA
CALIF INST FOR MEN 08/05
FERNBRIDGE CA
HUMBOLDT CREAMERY 08/06
FRESNO CA
STATE UNIV CREAMERY 08/12
MANTECA CA
DEJAGER DAIRY 2 NORTH 08/07
MODESTO CA
FOSTER FARMS DAIRY
OXNARD CA
CHASE BROS DAIRY
REDDING CA
MCCOLL'S DAIRY PROD
SAN LUIS OBISPO CA
CAL STATE POLY
SEBASTOPOL CA
WM MILLER DAIRY
SMITH RIVER CA
COUNTRY MAID DAIRY
SOLEDAD CA
CTF DAIRY
TRACY CA
DEUEL VOC INST
WEED CA
MEDO-BEL CREAMERY
COLORADO SPGS CO
SINTON DAIRY CO
FT COLLINS CO
POUDRE VALLEY DAIRY
08/05
08/07
08/06
08/05
08/06
08/05
08/19
08/13
WILLITS CA
RIDGEWOOD RANCH DAIRY 08/08
WILLOWS CA
FOREMOST FOODS COMPANY 08/15
06/20
DELTA CO
ARDEN MEADOW GOLD DAIRY 06/23
06/20
08/07
BOISE ID
MEADOW GOLD DAIRIES 08/26
(continued)
E-39
-------
TABLE E-9. Continued
SAMPLING LOCATION
COLLECTION
DATE
1984
SAMPLING LOCATION
COLLECTION
DATE
1984
GAMMA SPECTRAL ANNALYSES ONLY**
TWIN FALLS ID
YOUNGS DAIRY
CALDWELL ID
OCA RECEIVING STA
08/26
08/28
IDAHO FALLS ID
WESTERN GENERAL DAIRY 08/26
LEWISTON ID
GOLDEN GRAIN DAIRY PROD 08/26
POCATELLO ID
ROWLAND'S DAIRY
KIMBALLTON IA
AMP I RECEIVING STA
08/26
06/04
LAKE MILLS IA
LAKE MILLS COOP CRMY 06/04
LEMARS IA
WELLS DAIRY
ELLIS KS
MID-AMERICA DAIRY
06/03
06/04
HAMMOND LA
SOUTHEASTERN LA COLLEGE 07/23
LAFAYETTE LA
UNIV SOUTHWESTERN LA 07/19
LAKE CHARLES LA
BORDEN'S
SHREVEPORT LA
MIDWEST FARMS
07/24
07/22
DALTON MN
DALTON CO-OP CREAMERY 05/31
FLENSBURG MN
FLENSBURG CO-OP CMRY 05/29
NICOLLET MN
WALTER SCHULTZ FARM 05/31
JACKSON MO
MID-AMERICA DAIRYMEN IN 06/10
JEFFERSON CITY MO
CENTRAL DAIRY CO
BILLINGS MT
MEADOW GOLD DAIRY
GREAT FALLS MT
MEADOW GOLD DAIRY
FALLON NV
CREAMLAND DAIRY
DEVILS LAKE ND
LAKE VIEW DAIRY
06/03
06/17
06/17
MISSOULA MT
BEATRICE DAIRY PRODUCTS 06/18
06/20
GERING NE
4-STATES DAIRY-D SCHILL 06/04
GO ISLAND NE
MID-AMER DAIRYMN-JIM SA 06/04
OMAHA NE
ROBERTS DAIRY-MARSHALL 06/04
SUPERIOR NE
MID-AMER DAIRYMN-D FRIT 06/04
08/06
06/20
FARGO ND
CASSCLAY CREAMERY 06/13
(continued)
E-40
-------
TABLE E-9. Continued
COLLECTION
DATE
SAMPLING LOCATION 1985
GAMMA SPECTRAL
JAMESTOWN ND
COUNTRY BOY DAIRY
WILLISTON ND
PETERSONS CREAMERY
CLAREMORE OK
SWAN BROS DAIRY
STILLWATER OK
OSU DAIRY
CORVALLIS OR
SUNNY BROOK DAIRY
MEDFORD OR
DAIRYGOLD FARMS
TILLAMOOK OR
TILLAMOOK CO CRMY
MITCHELL SO
CULHANES DAIRY
RAPID CITY SO
BROWN SWISS DAIRY
06/17
06/17
07/15
07/15
08/27
08/27
08/26
06/17
06/18
COLLECTION
DATE
SAMPLING LOCATION 1985
ANNALYSES ONLY**
SIOUX FALLS SD
TERRACE PARK DAIRY
VOLGA SD
LAND 0' LAKES INC
RICHFIELD UT
IDEAL DAIRY
MOSES LAKE WA
SAFEWAY STORES INC
SEATTLE WA
CONSOLIDATED DAIRY PROD
SPOKANE WA
CONSOLIDATED DAIRY
CHEYENNE WY
DAIRY GOLD FOODS
POWELL WY
CREAM OF THE VALLEY DAI
RIVERTON WY
ALBERTSON'S PLANT
06/17
06/19
06/20
08/26
08/26
08/26
06/18
06/22
06/17
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
** POTASSIUM-40 WAS THE ONLY GAMMA-EMITTER DETECTED.
E-41
-------
TABLE E-10. SUMMARY OF RADIATION DOSE EQUIVALENTS FROM TLD DATA - 1985
-==========================-===================================================
ADJUSTED
DOSE EQUIVALENT RATE DOSE
MEASUREMENT PERIOD (MREM/D) EQUIVALENT
o i n i IUH
LOCATION
ADAVEN, NV
ALAMO, NV
AMERICAN BORATE, NV
ATLANTA MINE, NV
AUSTIN, NV
BAKER, CA
BARSTOW, CA
BATTLE MOUNTAIN, NV
BEATTY, NV
BISHOP, CA
BLUE EAGLE RANCH, NV
BLUE JAY, NV
BOULDER, UT
BRYCE CANYON, UT
CACTUS SPRINGS, NV
CALIENTE, NV
CARP, NV
CASEY'S RANCH, NV
CEDAR CITY, UT
CHERRY CREEK, NV
CLARK STATION, NV
COALDALE, NV
COLORADO CITY, AZ
COMPLEX 1, NV
CORN CREEK, NV
CORTEZ RD/HWY 278, NV
COYOTE SUMMIT, NV
CRESCENT VALLEY, NV
CRYSTAL, NV
CURRANT, NV
CURRIE, NV
DEATH VALLEY JCT, CA
DELTA, UT
DIABLO MAINT. STA. , NV
DUCHESNE, UT
DUCKWATER, NV
ELGIN, NV
ELKO, NV
ELY, NV
ENTERPRISE, UT
EUREKA, NV
FALLON, NV
FERRON, UT
ISSUE
01/09/85
01/09/85
01/10/85
01/16/85
01/17/85
01/07/85
01/07/85
01/08/85
01/07/85
01/08/85
01/08/85
01/15/85
01/15/85
01/15/85
01/07/85
01/10/85
01/10/85
01/15/85
01/08/85
01/10/85
01/16/85
01/16/85
01/15/85
01/09/85
01/07/85
01/09/85
01/15/85
01/08/85
01/07/85
01/08/85
01/09/85
01/10/85
01/22/85
01/16/85
01/23/85
01/08/85
01/10/85
01/09/85
01/08/85
01/09/85
01/17/85
01/07/85
01/24/85
COLLECT
12/10/85
11/07/85
11/07/85
12/09/85
01/08/86
12/13/85
12/12/85
12/11/85
11/07/85
12/11/85
12/10/85
01/15/86
12/10/85
12/10/85
11/04/85
11/06/85
11/06/85
01/15/86
11/05/85
12/10/85
01/13/86
12/11/85
11/05/85
12/10/85
11/08/85
12/11/85
01/13/86
12/11/85
11/08/85
12/11/85
12/10/85
11/07/85
01/13/86
01/13/86
01/15/86
12/11/85
11/06/85
12/10/85
12/11/85
11/05/85
01/07/86
12/11/85
11/06/85
MAX.
0.31
0.25
0.28
0.24
0.33
0.23
0.28
0.23
0.32
0.27
0.19
0.35
0.24
0.23
0.18
0.29
0.29
0.22
0.20
0.30
0.31
0.28
0.25
0.31
0.15
0.31
0.34
0.24
0.22
0.28
0.28
0.21
0.22
0.38
0.22
0.26
0.33
0.30
0.24
0.33
0.27
0.21
0.20
MIN.
0.27
0.21
0.27
0.20
0.30
0.20
0.24
0.20
0.27
0.24
0.16
0.29
0.21
0.19
0.15
0.23
0.25
0.18
0.15
0.24 .
0.27
0.24
0.18
0.28
0.10
0.24
0.28
0.21
0.19
0.23
0.23
0.16
0.17
0.30
0.18
0.22
0.29
0.20
0.19
0.25
0.26
0.19
0.17
AVG.
0.30
0.23
0.28
0.21
0.31
0.22
0.26
0.21
0.29
0.26
0.17
0.32
0.23
0.22
0.17
0.27
0.27
0.20
0.18
0.26
0.29
0.25
0.19
0.30
0.13
0.27
0.31
0.22
0.20
0.26
0.25
0.19
0.20
0.35
0.19
0.24
0.31
0.24
0.21
0.30
0.27
0.20
0.19
(MREM/Y)
110
84
102
77
113
80
95
77
106
95
62
117
84
80
62
99
99
73
66
95
106
91
69
110
47
99
113
80
73
95
91
69
73
128
69
88
113
88
77
110
99
73
69
(continued)
E-42
-------
TABLE E-10. Continued
STATION
LOCATION
FLYING DIAMOND, CP, NV
FURNACE CREEK, CA
GABBS, NV
GARRISON, UT
GEYSER RANCH, NV
GOLDFIELD, NV
GRANTSVILLE, UT
GREEN RIVER, UT
GROOM LAKE-NTS, NV
GUNNISON, UT
HANCOCK SUMMIT, NV
HIKO, NV
HOT CK RNCH, NV
IBAPAH, UT
INDEPENDENCE, CA
•INDIAN SPRINGS, NV
JACOB'S LAKE, AZ
KANAB, UT
KIRKEBY RANCH, NV
KOYENS RANCH, NV
LAS VEGAS, NV (AIRPT)
LAS VEGAS, NV (PLACAK)
LAS VEGAS, NV (UNLV)
LAS VEGAS, NV (USD I)
LATHROP WELLS, NV
LAVADA'S MARKET, NV
LIDA, NV
LOA, UT
LOGAN, UT
LONE PINE, CA
LOVELOCK, NV
LUND, NV
LUND, UT
MAMMOTH MOUNTAIN, CA
MANHATTAN, NV
MESQUITE, NV
MILFORD, UT
MINA, NV
MOAPA, NV
MONTICELLO, UT
NASH RANCH, NV
NEPHI, UT
NYALA, NV
MEASUREMENT PERIOD
ISSUE
01/08/85
01/10/85
01/16/85
01/07/85
01/07/85
01/15/85
01/23/85
01/23/85
01/15/85
01/21/85
01/15/85
01/09/85
01/21/85
01/22/85
01/08/85
01/07/85
01/15/85
01/15/85
01/07/85
01/15/85
01/02/85
01/02/85
01/02/85
01/02/85
01/07/85
01/09/85
01/15/85
01/16/85
01/24/85
01/08/85
01/08/85
01/10/85
01/17/85
01/09/85
01/17/85
01/07/85
01/16/85
01/16/85
01/07/85
01/16/85
01/15/85
01/22/85
01/16/85
COLLECT
12/12/85
11/06/85
12/11/85
12/09/85
12/09/85
01/06/86
01/14/86
11/05/85
01/07/86
11/06/85
01/13/86
11/07/85
01/15/86
12/09/85
12/11/85
11/04/85
11/04/85
11/04/85
12/09/85
01/15/86
12/31/85
12/31/85
12/31/85
12/31/85
11/04/85
11/08/85
01/07/86
12/10/85
01/06/86
12/11/85
12/11/85
12/10/85
12/11/85
12/11/85
01/08/86
11/04/85
12/09/85
12/11/85
11/04/85
11/05/85
12/12/85
01/13/86
01/15/86
DOSE EQUIVALENT
(MREM/D)
\ MAX.
0.21
0.17
0.21
0.21
0.27
0.24
0.22
0.20
0.22
0.19
0.42
0.20
0.27
0.29
0.25
0.17
0.28
0.19
0.22
0.26
0.15
0.16
0.13
0.18
0.25
0.23
0.30
0.35
0.17
0.24
0.20
0.23
0.30
0.33
0.35
0.16
0.26
0.29
0.18
0.26
0.22
0.20
0.24
MIN.
0.17
0.14
0.17
0.17
0.23
0.21
0.19
0.17
0.17
0.16
0.36
0.16
0.21
0.24
0.22
0.13
0.26
0.16
0.18
0.22
0.12
0.12
0.10
0.14
0.24
0.22
0.23
0.33
0.13
0.22
0.19
0.20
0.28
0.22
0.29
0.12
0.23
0.23
0.15
0.22
0.17
0.17
0.19
RATE
AVG.
0.20
0.16
0.18
0.19
0.25
0.22
0.20
0.18
0.19
0.18
0.39
0.19
0.24
0.27
0.24
0.15
0.27
0.17
0.20
0.24
0.14
0.14
0.11
0.16
0.25
0.22
0.27
0.33
0.15
0.23
0.19
0.22
0.29
0.28
0.32
0.15
0.24
0.25
0.16
0.24
0.21
0.18
0.22
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
73
58
66
69
91
80
73
66
69
66
142
69
88
99
88
55
99
62
73
88
51
51
40
58
91
80
99
120
55
84
69
80
106
102
117
55
88
91
58
88
77
66
80
(continued)
E-43
-------
TABLE E-10. Continued
STATION
LOCATION
OLANCHA, CA
OVERTON, NV
PAGE, AZ
PAHRUMP, NV
PAROWAN, UT
PENOYER FARMS, NV
PINE CREEK RANCH, NV
PIOCHE, NV
PRICE, UT
PROVO, UT
QUEEN CITY SMT, NV
RACHEL, NV
REED RANCH, NV
RIDGECREST, CA
ROSE RANCH, NV
ROUND MT, NV
RUBY VALLEY, NV
S. DESERT COR CENTR, NV
SALT LAKE CITY, UT
SCHURZ, NV
SCOTTY'S JCT, NV
SHERI'S RANCH, NV
SHOSHONE, CA
SPRINGDALE, NV
ST. GEORGE, UT
STONE CABIN RNCH, NV
SUNNYSIDE, NV
TEMPIUTE, NV
TIKABOO VALLEY, NV
TONOPAH TEST RNG, NV
TONOPAH, NV
TROUT CREEK, UT
TWIN SPRGS RNCH, NV
US ECOLOGY, NV
VALLEY CREST, CA
VERNAL, UT
VERNON, UT
WARM SPRINGS, NV
WELLS, NV
WENDOVER, UT
WILLOW SPR LDGE, UT
WINNEMUCCA, NV
YOUNG'S RANCH, NV
MEASUREMENT PERIOD
ISSUE
01/08/85
01/07/85
01/16/85
01/07/85
01/17/85
01/16/85
01/10/85
01/09/85
01/23/85
01/22/85
01/15/85
01/15/85
01/15/85
01/07/85
01/16/85
01/17/85
01/10/85
01/07/85
01/04/85
01/07/85
01/15/85
01/11/85
01/11/85
01/08/85
01/07/85
01/15/85
01/09/85
01/15/85
01/15/85
01/16/85
01/15/85
01/22/85
01/16/85
01/07/85
01/10/85
01/23/85
01/23/85
01/16/85
01/09/85
01/09/85
01/23/85
01/08/85
01/17/85
COLLECT
12/12/85
11/04/85
11/05/85
11/07/85
12/10/85
01/13/86
12/10/85
12/09/85
01/16/86
01/14/86
01/13/86
01/15/86
01/13/86
12/12/85
12/09/85
01/08/86
12/10/85
11/08/85
11/08/85
12/11/85
01/06/86
11/07/85
11/07/85
11/06/85
11/05/85
01/14/86
12/12/85
01/15/86
01/13/86
01/07/86
01/07/86
12/09/85
01/14/86
11/07/85
11/07/85
01/15/86
01/14/86
01/13/86
12/10/85
12/09/85
01/14/86
12/11/85
01/08/86
DOSE EQUIVALENT
(MREM/D)
MAX.
0.25
0.15
0.18
0.16
0.22
0.34
0.32
0.22
0.22
0.22
0.38
0.32
0.33
0.22
0.30
0.30
0.32
0.15
0.33
0.28
0.30
0.25
0.20
0.33
0.15
0.33
0.18
0.33
0.33
0.35
0.33
0.22
0.33
0.34
0.17
0.26
0.23
0.38
0.29
0.20
0.19
0.23
0.24
MIN.
0.22
0.11
0.15
0.13
0.21
0.27
0.30
0.15
0.18
0.19
0.30
0.26
0.26
0.20
0.17
0.28
0.23
0.13
0.20
0.24 •
0.26
0.21
0.16
0.29
0.11
0.25
0.14
0.27
0.26
0.25
0.28
0.19
0.27
0.29
0.12
0.23
0.20
0.30
0.22
0.17
0.17
0.20
0.22
RATE
AVG.
0.23
0.13
0.16
0.14
0.21
0.30
0.31
0.21
0.20
0.20
0.35
0.29
0.30
0.21
0.26
0.30
0.27
0.14
0.23
0.25
0.27
0.23
0.19
0.31
0.13
0.29
0.15
0.30
0.29
0.28
0.30
0.20
0.30
0.30
0.16
0.24
0.21
0.34
0.25
0.18
0.18
0.21
0.23
ADJUSTED
DOSE
EQUIVALENT
(MREM/Y)
84
47
58
51
77
110
113
77
73
73
128
106
110
77
95
110
99
51
84
91
99
84
69
113
47
106
55
110
106
102
110
73
110
110
58
88
77
124
91
66
66
77
84
===================================================:==========================
E-44
-------
TABLE E-ll. SUMMARY OF RADIATION DOSES FOR OFF-SITE RESIDENTS - 1985
RES-
I- BACKGROUND
DENT STATION
NO. LOCATION
2
6
7
8
9
10
11
13
14
15
18
19
21
22
24
25
28
29
30
33
34
35
CALIENTE, NV
INDIAN SPRINGS, NV
GOLDFIELD, NV
TWIN SPRINGS RANCH, NV
BLUE EAGLE RANCH, NV
COYOTE SUMMIT, NV
COYOTE SUMMIT, NV
KOYENS RANCH, NV
TIKABOO VALLEY, NV
TIKABOO VALLEY, NV
NYALA, NV
GOLDFIELD, NV
BEATTY, NV
ALAMO, NV
LAS VEGAS, NV (USD I)
CORN CREEK, NV
HOT CREEK RANCH, NV
STONE CABIN RANCH, NV
RACHEL, NV
LATHROP WELLS, NV
FURNACE CREEK, CA
DEATH VALLEY JCT. , CA
MEASUREMENT PERIOD
ISSUE
01/10/85
01/08/85
01/15/85
01/16/85
01/08/85
01/09/85
01/09/85
01/15/85
01/15/85
01/15/85
01/16/85
01/15/85
01/08/85
01/09/85
01/04/85
01/02/85
01/15/85
01/15/85
01/21/85
01/09/85
01/10/85
01/10/85
COLLECT
01/08/86
01/17/86
01/06/86
01/14/86
01/07/86
01/08/86
01/08/86
01/15/86
01/13/86
01/13/86
01/15/86
01/06/86
01/16/86
01/08/86
12/31/85
12/31/85
11/06/85
01/14/86
08/05/85
01/15/86
01/14/86
07/01/85
DOSE EQUIVALENT RATE NET
(MREM/D) EXPOSURE
MAX.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
31
15
24
29
19
29
30
24
26
26
20
21
25
20
15
16
28
30
33
25
16
19
MIN.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
30
13
21
25
16
27
26
17
22
23
19
19
22
17
12
14
24
25
23
22
12
18
AVG.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
30
14
22
27
18
28
28
20
24
24
20
20
24
18
13
15
26
27
26
23
15
19
(MREM)
1.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
11.
0.
0.
0.
0.
0.
0.
2
0
0
0
0
0
0
0
0
0
0
0
0
0
0
8
0
0
0
0
0
0
(continued)
E-45
-------
RES-
I- BACKGROUND
TABLE E-ll. Continued
DOSE EQUIVALENT
MEASUREMENT PERIOD (MREM/D)
RATE NET
EXPOSURE
UL.I1 1
NO.
36
37
38
40
42
44
45
47
49
50
51
52
54
55
56
57
59
60
223
232
233
235
j i r\ i iun
LOCATION
PAHRUMP, NV
INDIAN SPRINGS, NV
BEATTY, NV
GOLDFIELD, NV
TONOPAH, NV
CEDAR CITY, UT
ST. GEORGE, UT
ELY, NV
LAS VEGAS, NV (UNLV)
HOT CREEK RANCH, NV
TONOPAH, NV
SALT LAKE CITY, UT
RACHEL, NV
RACHEL, NV
CORN CREEK STATION, NV
OVERTON, NV
CEDAR CITY, UT
SHOSHONE, CA
LAS VEGAS, NV (USDI)
HIKO, NV
ELY, NV
CALIENTE, NV
ISSUE
01/08/85
01/10/85
01/08/85
01/15/85
01/15/85
01/08/85
01/07/85
01/08/85
01/02/85
01/15/85
01/16/85
01/04/85
01/15/85
01/21/85
01/02/85
01/07/85
01/08/85
01/18/85
01/02/85
01/09/85
01/08/85
01/10/85
COLLECT
01/15/86
01/17/86
01/16/86
01/06/86
01/07/86
01/07/86
01/06/86
01/07/86
12/31/85
11/06/85
01/08/86
01/03/86
01/15/86
01/15/86
12/31/85
01/06/86
04/09/85
01/14/86
12/31/85
01/08/86
01/06/86
06/06/85
MA
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0,
0,
0,
0,
0,
0
X.
16
18
35
22
26
22
24
25
20
28
29
70
30
27
,18
,20
,19
.21
,14
,24
.21
.24
MI
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0,
0,
0,
0,
0,
0,
0,
0,
0
N.
11
11
27
21
23
20
18
23
18
24
23
32
24
24
,12
,19
,19
,16
,10
,21
.20
.23
AVi
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0,
0,
0,
0,
0,
0,
0,
G.
13
15
31
21
24
22
20
24
19
26
26
45
27
25
,15
,15
,19
,18
,12
,23
,21
.23
(MRE
0.
4.
0.
0.
0.
0.
8.
0.
27.
0.
0.
70.
0.
0.
9,
15,
0.
0,
0,
9,
0,
0
M)
0
0
0
0
0
0
0
0
7
0
0
9
0
,0
,3
,3
,0
,0
.0
.9
.0
.0
(continued)
E-46
-------
TABLE E-ll. Continued
RES-
I-
DENT
NO.
239
247
248
249
258
262
263
264
BACKGROUND
STATION
LOCATION
TONOPAH, NV
CALIENTE, NV
PENOYER FARMS, NV
AUSTIN, NV
PIOCHE, NV
CORN CREEK, NV
DEATH VALLEY JCT, CA
RACHEL, NV
MEASUREMENT PERIOD
ISSUE
01/16/85
01/10/85
01/16/85
01/17/85
05/07/85
07/01/85
07/01/85
08/05/85
COLLECT
01/15/86
01/08/86
01/13/86
01/08/86
01/06/86
12/02/85
01/14/86
01/15/86
DOSE EQUIVALENT RATE NET
(MREM/D) EXPOSURE
MAX.
0.34
0.20
0.25
0.28
0.26
0.16
0.17
0.31
MIN.
0.26
0.17
0.23
0.21
0.24
0.13
0.17
0.26
AVG.
0.29
0.19
0.24
0.24
0.24
0.15
0.17
0.29
(MREM)
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
E-47
-------
ADDENDUM 1
NONRADIOLOGICAL SUPPLEMENT TO THE NTS ENVIRONMENTAL MONITORING REPORT
Prepared by:
Industrial Hygiene
Reynolds Electrical and Engineering Co., Inc.
Report Period: Calendar Year, 1985
INTRODUCTION
Environmental compliance activities which are the subject of this report
are regulated under Chapter 445 of the State of Nevada Administrative Codes.
Chapters 445.131, 445.361, and 445.401 respectively address water pollution
control, public water systems, and air pollution. There were a total of 21
facilities which had State of Nevada operating permits or approval in 1985.
For common information including site description, geology, land use, etc.,
reference the EPA Annual Report.
SUMMARY
Water Pollution
No effluent monitoring is required.
Air Pollution
There was one Notice of Violation of the 18 State air pollution operating
permits. This violation was issued March 26, 1986 on the basis of State inspec-
tions made at the NTS November 5 and 6, 1985. Details of the violation are
given below under the evaluation of the permits.
No effluent monitoring is required and none was performed. The allowable
emissions are established by State-determined operating constraints which were
not exceeded.
Ground-water Monitoring
Composite quarterly samples were taken from two wells to monitor changes
in nitrate concentration.
Add-1
-------
MONITORING DATA COLLECTION, ANALYSIS, AND EVALUATION
A1r Pollution Control
a. Area 1 Shaker Plant--
Operating restrictions to Permits 922 and 923 were not violated
during this period. The facilities were not operated in excess of the
allowable hours and an annual production report as transmitted to the
State on March 24, 1986.
b. Area 12 Concrete Batch Plant—
The plant did not exceed the permit restriction of 8 hours per
day, nor more than 296 hours per year. An annual report was transmitted
to the State on March 24, 1986.
c. Area 3 Aggregate Plant—
The restrictions to Operating Permit 919 were not exceeded. The
plant did not operate in excess of 8 hours per day, nor more than 280
hours per year. An annual production report was submitted to the State on
March 24, 1986.
d. Area 5 Aggregate Plant—
The restrictions to Operating Permit 920 were not exceeded. The
plant did not operate in excess of 8 hours per day, nor more than 650
hours per year. An annual production report was be submitted by March 24,
1986.
This Aggregate Plant was relocated in Area 1-and the crusher was
replaced without notifying the State. These two items were part of the
violation issued March 26, 1986. A permit application for the new Aggre-
gate Plant to operate in Area 1 was sent to the State on April 4, 1986 to
correct the situation.
e. Area 5 Surface Area Disturbance—
The restrictions to Permit 921 were not exceeded. A final
fugitive dust control plan will be submitted at least six months prior to
abandonment of the site.
f. Area 2 Stemming Systems—
The restrictions to Operating Permits 957 and 958 were not
exceeded.
g. NTS 4,000,000 BTU/hour or Greater Boiler Permits—
The restrictions to Permits 1035, 1036 and 925 were not exceeded.
The boilers were not operated in excess of 8,400 hours per year. All
boilers used Number 2 fuel oil. An annual analysis of fuel for sulfur and
BTU content was submitted on September 17, 1986.
h. Two fuel storage tanks in Area 6 and two in Area 23 were in use at the
time of the State inspections and were included in the violation. Operat-
ing Permits have been received for these four tanks since the inspection,
as noted on the violation report.
Add-2
-------
Ground-Water Monitoring
Monthly ground-water samples were collected from Wells Ue5C and Ue5B and
composited into calendar year quarterly samples to monitor changes in nitrate
concentration. The last sample analyzed from Well Ue5B was 31.0 milligrams of
nitrates per liter (mg/1) and the sample from Well Ue5C was 21.7 mg/1.
Add-3
-------
ADDENDUM
PART A
ENVIRONMENTAL PERMITS. ORDERS. AND NOTICES
Part A of this Addendum pertains to EG&G activities at the locations shown.
Air Quality permits are subject to yearly renewal. The North Las Vegas Waste
Water permit expires August 9, 1987, while Clark County is being issued and
will expire April 1, 1988. The hazardous waste permits have no expiration
dates, while the Santa Barbara Industrial Waste permit is renewed annually.
All EG&6 activities are in compliance with existing Federal, State, and County
regulations.
Permit/Notification Issue Issuing
EG&G Operations Type Date Agency
Santa Barbara
Operation
Kirtland Oper.
(Craddock Fac.)
Los Alamos
Washington Aerial
Measurements
San Ramon Oper.
Woburn Oper.
Notification of Hazardous
Waste Activity EPA ID
#CAD980813224
Extremely Hazardous Waste
Disposal Permit #3-6757
Industrial Waste Control
Permit #11-202
Notification of Hazardous
Waste Activity
EPA ID #NMD049986896
No Notifications or Permits
required
No Notifications or Permits
required
Notification of Hazardous
Waste Activity EPA ID
#CAD056196900
Waste Water Discharge
Permit #3672-101
Waste Water Discharge
Permit (no number)
Notification of Hazardous
Waste Activity EPA ID
#MAD980578983
Waste Water Permit
#43005732-0
Feb. 1985
April 1985
1973
Dec. 1985
State of
California
State of
California
Goleta Sanitary
Dist. California
State of New
Mexico
May 1983
Nov. 1985(1)
Jan. 1985(2)
Jan. 1982
Oct. 1984(3)
State of
California
Dublin/San Ramon
Sanitary Dist.
California
Central Contra
Costa Sanitary
Dist. California
State of
Massachusetts
State of
Massachusetts
(1) Expires September 1987.
(2) Operating with expired permit with CCCSD permission pending permit review.
(3) Expired October 31, 1985, applied for permit renewal.
Add-4
-------
ADDENDUM 2
PART A (Continued)
EG&G Operations
Las Vegas Open.
Permit/Notification
Type
Notification of Hazardous
Waste Activity EPA ID
#NVD09786873l
PCB Notification
NVT-PCB-137
Extremely Hazardous Waste
Disposal Permit #3-8520
Waste Water Contribution
Permit #85-1
Industrial Waste Water
Permit
Aug. 1980
Feb. 1986
Jan. 1986
Aug. 1985
April 1988
Air Pollution Control Operation
Permits
A06501
A06502
A06504
A06505
A06503
A06506
A06507
A06509
A06510
A06511
A06512
A06503
A06504
Issuing
Agency
State of Nevada
State of Nevada
State of
California
City of North
Las Vegas
Clark County
Clark County
Nov. 1981
Nov. 1981
Aug. 1976
Oct. 1976
Nov. 1981
May 1984
May 1984
May 1984
May 1984
May 1984
Feb. 1985
May 1984
May 1984
Clark County
Clark County
Clark County
Clark County
Clark County
Clark County
Clark County
Clark County
Clark County
Clark County
Clark County
Clark County
Clark County
Add-5
-------
ADDENDUM 2
PART B
Part B pertains to the status of the environmentally related facilities at the Nevada Test Site,
administered through the Reynolds Electrical & Engineering Co., Inc. (REECo). It includes actions
initiated in 1985 and pending. All REECo activities are in compliance with existing Federal, State, or
County requirements.
CLEAN AIR ACT
The State of Nevada Air Quality Regulations require a registration certificate before starting con-
struction, modification, or alterations of an air contaminant emission source. An operating permit is
required before initial operation of the emission source. A registration certificate or operating permit
is required before the surface disturbance of 20 acres or more accumulative total of land.
2
ex
Location/Facility
1. Area 1 Shaker
Plant
2. Area 1 Shaker
Plant
3. Area 12 Concrete
Batch Plant
4. Area 3 Portec
Aggregate
and Hopper
Item(s)
Simplicity Screen
Pioneer Screen
Cedarapids Screen
Conveyors
Baghouse
Bins
CMI Rotary Dryer
Baghouse
Bins
Ideal Mfg. Co.
Bacon-Western
Dust Filters
Reason
Process weight
rate 50 pounds/
hour or more
Process weight
rate 50 pounds/
hour or more
Process weight
rate 50 pounds/
hour or more
Process weight
rate 50 pounds/
hour or more
Expiration
Permit #/Issue Date Date Permittee
OP922 12/3/84 12/3/89
OP923 12/3/84 12/3/89
OP928 12/3/84 12/3/89
OP919 12/3 84 12/3/89
DOE
DOE
DOE
DOE
-------
ADDENDUM 2
PART B (Continued)
CLEAN AIR ACT (cont.)
Location/Facility
5. Area 5 Aggregate
Plant
6. Area 5 Aggregate
Plant
7. Area 2 LLNL
Portable Stem-
ming System
g 8. Area 2 LLNL
f- Portable Stem-
"*' ming System
9. Area 23,
Bldg. 753
10. Area 6
Decon Facility
11. Portable Boiler
Item(s)
Crusher
Wet Screen
Surface
Disturbance
Barber-Greene
Conveyor
Atlas
Conveyors (2)
Barber-Greene
Conveyor
Atlas
Conveyors (2)
Nordberg Conveyor
Ajax Boiler
#83-35651
York-Shipley
Boiler
Serial #82-14857
Superior #2
Boiler
Serial #1342-1576
Reason
Process weight
rate 50 pounds/
hour or more
20 acres or more
Process weight
rate 50 pounds/
hour or more
Process weight
rate 50 pounds/
hour or more
Rated capacity
4,000,000 Btu/
hour or more
Rated capacity
4,000,000 Btu/
hour or more
Rated capacity
4,000,000 Btu/
hour or more
Expiration
Permit #/Issue Date Date Permittee
OP920 12/3/84 12/3/89
OP921 12/3/84 12/3/89
OP957 12/3/84 12/3/89
OP958 12/3/84 12/3/89
OP925 12/3/84 12/3/89
OP1036 10/20/80 10/20/90
OP1035 10/20/80 10/20/90
DOE
DOE
DOE
DOE
DOE
REECo
REECo
-------
a.
a.
i
oo
ADDENDUM 2
PART B (Continued)
CLEAN AIR ACT (cont.)
Location/Facility
12. Area 6
13. Open Burning
14. Area 1
Shaker Plant
15. Area 3 Portable
Stemming System
16. Mercury
Gasoline Tank
17. Mercury Diesel
Tank
18. Area 6
Gasoline Tank
19. Area 6
Diesel Tank
20. Area 1 Concrete
Batch Plant
Item(s)
Concrete Batch
Plant
Fire Dept. and
Env. Sci. Training
Surface
Disturbance
4 Double Hoppers
1 Conveyor Belt
420,000 gallons
420,000 gallons
42,000 gallons
105,000 gallons
Rex Lo-Go Plant
Reason
Process weight
rate 50 pounds/
hour or more
Training
20 acres or
more
Process weight
rate 50 pounds/
hour or more
40,000 gallons
or more
40,000 gallons
or more
40,000 gallons
or more
40,000 gallons
or more
Process weight
rate 50 pounds/
hour or more
Expiration
Permit ft/Issue Date Date Permittee
OP918 11/21/84 11/21/89
86-3 9/4/85
8/23/86
OP1082 1/30/86 1/30/91
OP1089 2/25/86 2/25/91
OP1086 2/25/86 2/25/91
OP1087 2/25/86 2/25/91
OP1090 2/25/86 2/25/91
OP1085 2/25/86 2/25/91
OP1082 1/30/86 1/30/91
F&S
REECo
REECo
REECo
REECo
REECo
REECo
REECo
REECo
-------
ADDENDUM 2
PART B (Continued)
CLEAN AIR ACT RECENT AND PENDING ACTIONS
AREA/FACILITY
1. Area 14 Surface Disturbance
Rocket Propel 1 ant Burn
2. Area 6 OAF Surface Disturbance
3. Area 3 Mud Plant
4. Area 19 & 20 Portable Mud Plant
5. Area 5 Burn Permit Fire
Stack Test
WATER POLLUTION
STATUS
Registration Certificate
RC 1122 received pm 1/30/86.
Application submitted by
DOE/NV. Fees sent to DOE/NV,
12/20/84. (RC action waiting
final design; DOE action.)
Application information being
gathered; not yet submitted to
State.
Application information being
gathered; not yet submitted to
State.
Approved 12/11/85 to conduct
using NTS Burn Permit #86-3.
State of Nevada Water Pollution Control Regulations require a permit for con-
struction, installation, or significant modification of sewage collection and
treatment facilities and review of plans and specifications for sewage treat-
ment works.
The State of Nevada inspected the sewage treatment systems (lagoons) in Areas 6,
12, and 23 in November 1985. Applications for permits resulting from this
inspection have been made and will be shown in next year's report.
The Area 30 Exploratory Shaft Sanitary Waste System Plan was reviewed by the
State and approved 3/2/84.
CLEAN WATER
State of Nevada water supply regulations require review and approval of plans
and specifications for construction of public (potable) water systems and for
any substantial addition to or alteration of existing systems and periodic
sampling for bacteriological, chemical, and radiological analyses.
Add-9
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ADDENDUM 2
PART B (Continued)
Permits received:
System Permit No. Expiration Date Permittee
NTS-Area 23 NY-360-12C 9/30/86 REECo (D. M. Bullock)
NTS-Area 1 NY-5024-12NC 9/30/86 REECo/NTS
NTS-Area 2 & 12 NY-4099-12C 9/30/86 REECo/NTS
NTS-Area 6 NY-5000-12NC 9/30/86 REECo/NTS
NTS-Area 3 NY-4097-12NC 9/30/86 REECo/NTS
NTS-Area 25 NY-4098-12NC 9/30/86 REECo/NTS
Periodic sampling for bacteriological, chemical, and radiological analyses is
being done.
SOLID WASTE
State of Nevada Regulations governing solid waste require review and approval
of solid waste management plans.
There is a salvage yard in Area 23; sanitary landfills in Areas 6, 10, and 23;
and construction landfills in Areas 3, 19, and 25. DOE/NV instructed REECo on
April 4, 1985 to obtain the necessary State permits or approvals for these
facilities.
RCRA WASTE
REECo has an EPA Identification Number, NV3890090001, for hazardous waste
activities. A Part B permit application for the Radioactive Waste Management
Site Landfill in Area 5 was submitted to EPA Region IX by DOE/NV November 1985,
PCBS
REECo has been issued PCB Generator I.D. No. NVG-PCB-006 by the State.
Add-10
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ADDENDUM 2
PART C
Part C pertains to the status of the environmentally related facilities at the
Tonopah Test Range, administered through the REECo. All activities currently
comply with Federal, State, and County requirements.
CLEAN AIR ACT
1. REECo was issued Operating Permit #1083 for the Ross Concrete Batch Plant
on 1/30/86. This permit expires 1/30/91.
2. REECo was issued Operating Permit #1081 for the C. S. Johnson Batch Plant
on 1/30/86. This permit expires 1/30/91.
3. A permit for open burning at the Fire Department Training Facility in the
TTR was issued 3/19/86. This permit (#86-16) expires 9/17/86.
4. Permit applications for the five large Fuel Storage Tanks are near comple-
tion and should be sent to the State by 4/4/86.
WATER POLLUTION
1. The sewage lagoons are complete and in operation, replacing the 100,000 gpd
Sewage Treatment Package Plant. Plans for this modification and for by-
passing the 50,000 gpd Package Plant to the sewage lagoons were submitted
to the State for review and approval on 9/17/85. A permit will be issued.
2. Plans for the Sewage Treatment Package Plant to be installed at Site 4 were
submitted to the State for review and approval on 10/31/85. Approval is
expected after State receipt of additional requested information. A permit
will not be issued (less than 10,000 gpd inflow).
CLEAN UATER
1. Public Water Supply Operating Permits:
Permits Received:
System
TTR-Sandia-
Area 6
TTR-Site 3
TTR-Site O&M
(Air Force Well)
TTR-Site 1A
Permit No.
NY-3014-12NC
NY-5001-12NC
NY-5002-12NC
NY-4068-12NC
Expiration Date
9/30/86
9/30/86
9/30/86
9/30/86
Permittee
REECo (D. M. Bullock)
REECo/TTR
REECo/TTR
REECo/TTR
Add-11
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ADDENDUM 2
PART C (Continued)
SOLID WASTE
Operation and maintenance plan for the sanitary landfill was submitted to the
State on December 19, 1981.
RCRA WASTE
TTR has an EPA Identification Number, NV N3570090016, for hazardous waste
activities.
Add-12
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ADDENDUM 2
PART D
Part D of this Addendum pertains to Fenix & Scisson, Inc. (F&S), located at the
Nevada Test Site. F&S activities are in compliance with Federal, State, and
County requirements.
F&S Location Permit Type Permit No. Issued Expires
NTS-ATI Areas Air Quality 918 11/21/84 11/21/85*
(Portable Silos)
Undergoing renewal
Add-13
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ADDENDUM 3
ENVIRONMENTAL IMPACT STATEMENTS AND ENVIRONMENTAL ASSESSMENTS
The following Environmental Assessments were completed in CY 1985:
1. United States Geological Survey (USGS) Drill Holes and Trenches -
Yucca Mountain and Crater Flats
2. The Liquid Gas Fuel Spill Test Facility at Frenchmen Flat, Nevada
Test Site
No Environmental Impact Statements were written in CY 1985.
Add-14
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TECHNICAL REPORT DATA
(Please read Instructions on the reverse before completing)
REPORT NO.
DQE/DP/00539-056
2.
3. RECIPIENT'S ACCESSION NO.
TITLE AND SUBTITLE
OFFSITE ENVIRONMENTAL MONITORING REPORT
Radiation Monitoring Around U.S. Nuclear Test Areas,
Calendar Year 1985
8. REPORT DATE
8. PERFORMING ORGANIZATION CODE
AUTHOR(S)
R. F. Grossman, S. C. Black, R. E. Dye, A. A. Mullen,
D. J. Thome1, and D. D. Smith
8. PERFORMING ORGANIZATION REPORT NO.
EPA 600/4-86-022
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-AI08-76DP00539
2. SPONSORING AGENCY NAME AND ADDRESS
U. S. Department of Energy
Nevada Operations Office
P. 0. Box 14100
Las Vegas, NV 89114
13. TYPE OF REPORT AND PERIOD COVERED
Response - 1985
14. SPONSORING AGENCY CODE
EPA 600/07
5. SUPPLEMENTARY NOTES
Prepared for the U. S. Department of Energy under Interagency Agreement No.
DE-AI08-76DP00539
6. ABSTRACT
This report covers the routine radiation monitoring activities conducted by the
Environmental Monitoring Systems Laboratory-Las Vegas in areas which may be affected
by nuclear testing programs of the Department of Energy. This monitoring is conducted
to document compliance with standards, to identify trends in environmental radiation,
and to provide such information to the public. It summarizes activities for calendar
year 1985.
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 radionuclides released yield an estimated
dose of 0.0002 person-rem to the population within 80 km of the Nevada Test Site dur-
ing 1985. World-Wide fallout of Kr-85, Sr-90, HTO, and Pu-239 detected by the mon-
itoring networks would cause maximum exposure to an individual of less than 0.14 mrem
per year. Plutonium in air was still detectable along with krypton-85, which contin-
ued its gradual increase, as has been reported previously. Strontium in milk was
near the detection limit. 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.
KEY WORDS AND DOCUMENT ANALYSIS
DESCRIPTORS
b.lDENTIFIERS/OPEN ENDED TERMS
COS AT I Field/Group
18. DISTRIBUTION STATEMENT
RELEASE TO THE PUBLIC
19. SECURITY CLASS (This Report)
UNCLASSIFIED
21. NO. OF PAGES
20. SECURITY CLASS (This page)
UNCLASSIFIED
22. PRICE
EPA Form 2220.1 (R«v. 4-77) PRKVIOU* EDITION n OBSOLETE
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