EMSL-LV-0539-31
OFF-SITE ENVIRONMENTAL MONITORING REPORT FOR THE NEVADA TEST SITE
AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS
January through December 1978
by
Nuclear Radiation Assessment Division
Environmental Monitoring Systems Laboratory
U.S. ENVIRONMENTAL PROTECTION AGENCY
Las Vegas, Nevada 89114
October 1979
This work performed under a Memorandum of
Understanding No. EY-76-A-08-0539
for the
U.S. DEPARTMENT OF ENERGY
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This report was prepared as an account of work sponsored by the United States
Government. Neither the United States nor the Department of Energy, nor any
of their employees, nor any of their contractors, subcontractors, or their
employees, makes any warranty, express or implied, or assumes any legal
liability or responsibility for the accuracy, completeness or usefulness of
any information, apparatus, product or process disciosedj or represents that
its use would not infringe privately owned rights.
AVAILABLE FROM THE NATIONAL TECHNICAL INFORMATION SERVICE
U.S. DEPARTMENT OF COMMERCE
SPRINGFIELD, VA 22161
PRICE: PAPER COPY $ MICROFICHE $
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EMSL-LV-0539-31
OFF-SITE ENVIRONMENTAL MONITORING REPORT FOR THE NEVADA TEST SITE
AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS
January through December 1978
by
R. F. Grossman
Nuclear Radiation Assessment Division
Environmental Monitoring Systems Laboratory
U.S. ENVIRONMENTAL PROTECTION AGENCY
Las Vegas, Nevada 89114
This work performed under a Memorandum of
Understanding No. EY-76-A-08-0539
for the
U.S. DEPARTMENT OF ENERGY
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PREFACE
The Atomic Energy Commission (AEC) used the Nevada Test Site (NTS) from
January 1951 through January 19, 1976, for conducting nuclear weapons tests,
nuclear rocket-engine development, nuclear medicine studies, and miscellaneous
nuclear and non-nuclear experiments. Beginning on January 19, 1976, these
activities became the responsibility of the newly-formed U.S. Energy Research
and Development Administration (ERDA), which was later merged with other
energy-related agencies to form the U.S. Department of Energy on October 1,
1977. Atmospheric nuclear tests were conducted periodically from January 27,
1951 through October 30, 1958, at which time a testing moratorium was imposed
until September 1, 1961. After 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.
The U.S. Public Health Service (PHS), from 1954 through 1970, and the U.S.
Environmental Protection Agency (EPA), from 1970 to the present, have
maintained facilities at the NTS or in Las Vegas, Nevada, to provide an
Off-Site Radiological Safety Program for nuclear testing. In addition,
off-site surveillance has been provided by the PHS or EPA for nuclear
explosives tests at places other than the NTS. Prior to 1954, the
surveillance program was performed by the Los Alamos Scientific Laboratory and
U.S. Army personnel.
Since 1954, the objective of this surveillance program has been to measure
levels and trends of radioactivity in the off-site 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 deploying routine sampling networks for milk,
water, and air; a dosimetry network; and a special sampling of food crops,
soil, etc., when required. To implement protective actions, provide immediate
radiation monitoring, and obtain environmental samples rapidly after any
release of radioactivity, personnel with mobile monitoring equipment are also
placed in areas downwind from the NTS or other test areas prior to each test.
Published reports covering specific test series or test projects include
the analytical results for radioactivity originating from nuclear tests at the
NTS. Beginning in 1959 for reactor tests, and in 1962 for weapons tests,
surveillance data for each individual test which resulted in off-site
radioactivity was reported separately. Commencing in January 1964, and
continuing through December 1970, these individual reports for nuclear tests
iii
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were also summarized and reported every 6 months. Individual analytical
results for all routine and special milk samples were also included in these
semiannual summary reports.
In 1971, the AEC implemented a requirement, now referred to as the DOE
Manual, Chapter 0513, that each contractor or agency involved in major nuclear
activities provides a comprehensive radiological monitoring report. The entry
of these reports into the general literature provide a data base for the
environmental impact of nuclear activities.
To provide rapid dissemination of data, all analytical results of all air
data collected since July 1971, and all milk and water samples collected since
January 1972 were published in Radiation Data and Reports, a monthly
publication of the EPA that was discontinued at the end of 1974. During the
years 1976 and 1977, air and milk data were reported in quarterly interim
reports and distributed to State, Federal, and other organizations interested
in the information. Dosimetry data were also included beginning in the third
quarter of 1976. In 1978 the interim quarterly reports were discontinued.
Since 1962, PHS or EPA aircraft have also been used during nuclear tests
to provide rapid monitoring and sampling for releases of radioactivity.
Aircraft monitoring data obtained immediately after a test are used to
position mobile radiation monitoring personnel on the ground. The results of
airborne sampling are used to quantify the inventories, diffusion, and
transport of the radionuclides released. Beginning in 1971, all analytical
data from monitoring and aerial sampling have been reported in effluent
monitoring data reports in accordance with the DOE Manual, Chapter 0513.
iv
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CONTENTS
PREFACE iii
LIST OF FIGURES vi
LIST OF TABLES viii
ACKNOWLEDGMENT x
INTRODUCTION 1
DESCRIPTION NEVADA TEST SITE 1
AIRBORNE RELEASES AT THE NTS DURING 1978 16
DESCRIPTIONS OF OTHER TEST SITES 17
SUMMARY 18
MONITORING DATA COLLECTION, ANALYSIS, AND EVALUATION 20
QUALITY ASSURANCE 21
AIR SURVEILLANCE NETWORK 22
NOBLE GAS AND TRITIUM SURVEILLANCE NETWORK 25
DOSIMETRY NETWORK 30
MILK SURVEILLANCE NETWORK 33
LONG-TERM HYDROLOGICAL MONITORING PROGRAM 34
WHOLE-BODY COUNTING 54
DOSE ASSESSMENT 56
REFERENCES 58
APPENDIX A. TABLES 60
APPENDIX B. RADIATION PROTECTION STANDARDS FOR EXTERNAL AND
INTERNAL EXPOSURE 99
APPENDIX C. REPLICATE SAMPLING PROGRAM 102
APPENDIX D. DETECTION OF AIRBORNE RADIOACTIVITY FROM THE
ATMOSPHERIC NUCLEAR TESTS BY THE PEOPLE'S
REPUBLIC OF CHINA 106
APPENDIX E. LIST OF ABBREVIATIONS AND SYMBOLS .135
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FIGURES
Number Page
1 Nevada Test Site Location 2
2 Nevada Test Site Road and Facility Map 3
3 Groundwater Flow Systems - Nevada Test Site 8
4 General Land Use, Nevada Test Site Vicinity 9
5 Location and Number of Family Milk Cows and Goats 11
6 Location and Number of Dairy Cows 12
7 Distribution of Beef Cattle by County 13
8 Distribution of Sheep by County 14
9 Population of Arizona, California, Nevada, and Utah
Counties Near the Nevada Test Site 15
10 Air Surveillance Network - Nevada 23
11 Air Surveillance Network - Outside Nevada 24
12 Noble Gas and Tritium Surveillance Network 26
13 Trend in Annual Network Concentrations of
Krypton-85 1972-1978 28
14 Distribution of Network Concentrations of Krypton-85 29
15 Dosimetry Network 31
16 Milk Surveillance Network 35
17 On-Site Long-Term Hydrological Monitoring Program,
Nevada Test Site 37
18 Off-Site Long-Term Hydrological Monitoring Program,
Nevada Test Site .38
19 Long-Term Hydrological Monitoring Program, Project
Gnome/Coach, Carlsbad, New Mexico, 40
vi
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Number Page
20 Long-Term Hydrological Monitoring Program, Project
Shoal, Fallen, Nevada 41
21 Long-Term Hydrological Monitoring Program, Project
Dribble/Miracle Play, Vicinity of Tatum Salt Dome,
Mississippi 42
22 Long-Term Hydrological Monitoring Program, Project
Dribble/Miracle Play, Tatum Salt Dome, Mississippi 43
23 Long-Term Hydrological Monitoring Program, Project
Dribble/Miracle Play, Tatum Dome, Mississippi 44
24 Long-Term Hydrological Monitoring Program,
Rio Arriba County, New Mexico, Project Gasbuggy 45
25 Long-Term Hydrological Monitoring Program,
Project Rulison, Rulison, Colorado 46
26 Long-Term Hydrological Monitoring Program, Faultless
Event, Central Nevada Test Area 47
27 Long-Term Hydrological Monitoring Program, Project
Rio Blanco, Rio Blanco County, Colorado 48
28 Long-Term Hydrological Monitoring Program, Project
Cannikin, Amchitka Island, Alaska 49
29 Long-Term Hydrological Monitoring Program, Project
Milrow, Amchitka Island, Alaska 50
30 Long-Term Hydrological Monitoring Program, Project
Long Shot, Amchitka Island, Alaska 51
31 Long-Term Hydrological Monitoring Program, Background
Sampling, Amchitka Island, Alaska 52
D-l Gross Beta Radioactivity Concentrations in Air at
Pueblo, Colorado 107
D-2 Gross Beta Radioactivity Concentrations in Air at
Bishop, California 107
D-3 Infant Thyroid Dose Equivalents (mrem) Estimated from Air
Sampling Results of Air Surveillance Network (Nevada),
March-April 1978 133
D-4 Infant Thyroid Dose Equivalents (mrem) Estimated from Air
Sampling Results of Air Surveillance Network (Western
United States), March-April 1978 134
vii
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TABLES
Number Page
1 Characteristics of Climatic Types in Nevada 5
2 NTS Station 6 Surface Wind Summary 6
3 Total Airborne Radionuclide Releases at
the Nevada Test Site 17
4 Annual Average Krypton-85 Concentrations in air, 1972-1978 . . .27
5 Concentrations of Airborne Xenon-133 Detected
On and Off NTS 29
6 Dosimetry Network Summary for the Years 1971-1978 33
7 Summary of Radionuclide Concentrations for Milk
Surveillance Network and Standby Surveillance Network 36
8 Estimated Dose Commitment from Xenon-133 Concentrations 57
A-l Underground Testing Conducted off the Nevada Test Site 61
A-2 Summary of Analytical Procedures 62
A-3 1978 Quality Assurance Intercomparisons 64
A-4 1978 Summary of Analytical Results for the Noble Gas
and Tritium Surveillance Network 66
A-5 1978 Summary of Radiation Doses for the Dosimetry Network. . . .68
A-6 1978 Summary of Analytical Results for the Milk
Surveillance Network 70
A-7 Analytical Criteria for Long-Term Hydrological
Monitoring Program Samples 74
A-8 1978 Summary of Analytical Results for the NTS
Monthly Long-Term Hydrological Monitoring Program 75
A-9 1978 Analytical Results for the NTS Semi-Annual
Long-Term Hydrological Monitoring Program 76
viii
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Number Page
A-10 1978 Analytical Results for the NTS Annual Long-Term
Hydrological Monitoring Program 80
A-ll 1978 Analytical Results for the Off-NTS Long-Term
Hydrological Monitoring Program 81
A-12 1978 Special Analytical Results for the Off-NTS Long-Term
Hydrological Monitoring Program-Project Rio Blanco. . . . c"} . . 94
A-13 Special Analytical Results for the Long-Term Hydrological
Monitoring Program: Project Dribble 97
B-l DOE Annual Dose Commitment 100
B-2 DOE Concentration Guides (CG'S) 100
B-3 Average Annual Concentration Assumed to Produce a Total
Body or Organ Dose of 4 mrem/yr 101
C-l Samples and Analyses for Replicate Sampling Program 103
C-2 Upper Confidence Limits of Sampling and
Analytical/Counting Errors 105
D-l Air Sampling Stations Having Detectable Radionuclide
Concentrations 108
D-2 1978 Summary of Analytical Results for Air
Surveillance Network, Active Stations 109
D-3 1978 Summary of Analytical Results for Air
Surveillance Network, Standby Stations 119
IX
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ACKNOWLEDGMENT
I would*!ike to acknowledge the contribution of Ms. Jaci L. Hopper for the
section of this report pertaining to the Dosimetry Network, of James W.
Mull ins for his contribution to the Quality Assurance Section, and of Robert
G. Patzer for his preparation of the section on whole-body counting.
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INTRODUCTION
Under Memorandum of Understanding No. EY-76-A-08-0539* with the U.S.
Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA),
Environmental Monitoring and Support Laboratory-Las Vegas (EMSL-LV),
continued its Off-Site Radiological Safety Program within the environment
surrounding the Nevada Test Site (NTS) and at other sites designated by the
DOE during calendar year 1978. This report, prepared in accordance with the
DOE Manual, Chapter 0513, contains summaries of the EMSL-LV dosimetry and
sampling methods and analytical procedures, and the analytical results from
environmental samples collected in support of the DOE nuclear testing
activities. Where applicable, dosimetry and sampling data are compared to
appropriate guides for external and internal exposures of humans to ionizing
radiation. In addition, a brief summary of pertinent, and demographical,
features of the NTS and the NTS environs is presented for background
information.
DESCRIPTION OF NEVADA TEST SITE
The major programs conducted at the NTS in the past have been nuclear
weapons development, proof-testing and weapons safety, testing of peaceful
uses of nuclear explosives (Project Plowshare), reactor-engine development for
nuclear rocket and ram-jet applications (Projects Pluto and Rover), basic
high-energy nuclear physics research, and seismic studies (Vela Uniform).
During this report period, these programs were continued with the exception of
Project Pluto, discontinued in 1964; Project Rover, terminated in January
1973; Project Plowshare nuclear tests terminated in 1970; and Vela Uniform
studies ceased in 1973. All nuclear weapons tests since 1962 were conducted
underground to minimize the possibility of the release of fission products to
the atmosphere.
Site Location
The Nevada Test Site (Figures 1 and 2) is located in Nye County, Nevada,
with its southeast corner about 90 km northwest of Las Vegas. The NTS has an
area of about 3500 km2 and varies from 40-56 km in width (east-west) and from
64-88 km in length (north-south). This area consists of large basins or flats
about 900-1200 m above mean sea level (MSL) surrounded by mountain ranges
rising to 1800-2100 m above MSL.
The NTS is surrounded on three sides by exclusion areas collectively named
the Nell is Air Force Range. The Range, particularly to the north and east,
provides a buffer zone between the test areas and public lands. This buffer
zone varies from 24-104 km between the test area and land that is open to the
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! NELLIS^
AIR FORGET
RANGE n
Figure 1. Nevada Test Site Location,
2
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Experimental Farm
. Rainier Mesa
Sedan
Crater
'<*,. Pahute CP
Buckboard ^
Mesa
30116 ',
Nuclear Rocket Development
Station
. N.R.D.S.
Buffer Zone j
Desert Game
Range
Tonopah (240 km from Mercury)
Scale in Meters
Las Vegas
105 km from Mercury
0 5000 10000
Figure 2. Nevada Test Site Road and Facility Map.
3
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public. Depending upon wind speed and direction within the accepted range of
testing criteria, this provides a delay of from 1/2 to more than 6 hours
before any accidental release of airborne radioactivity could pass over public
lands.
Climate
The climate of the NTS and surrounding area is variable, primarily due to
altitude and the rugged terrain. Generally, the climate is referred to as
Continental Arid. Throughout the year, there is insufficient water to support
tree or crop growth without irrigation.
The climate may be classified by the types of vegetation which grow under
these conditions. According to Houghton et al. (1975), this method, developed
by Koppen's classification of dry conditions, is further subdivided on the
basis of temperature and severity of drought. Table 1, from Houghton et al.,
summarizes the different characteristics of these climatic types in Nevada.
As pointed out by Houghton et al., 90 percent of Nevada's population lives
in areas with less than 25 cm of rain per year or in areas which would be
classified as mid-latitude steppe to low-latitude desert regions.
According to Quiring (1968), the NTS average annual precipitation ranges
from about 10 cm at the 900-m altitude to around 25 cm on the plateaus.
During the winter months, the plateaus may be snow-covered for periods of
several days or weeks. Snow is uncommon on the flats. Temperatures vary
considerably with elevation, slope, and local air currents. The average daily
high (low) temperatures at the lower altitudes are around 50° (25°) F in
January and 95° (55°) F in July, with extreme daily averages of 110° F and
-15° F. Corresponding temperatures on the plateaus are 35° (25°) F in January
and 80° (65°) F in July with extremes of 100° and -20° F. Temperatures as low
as -30° F and higher than 115° F have been observed at the NTS.
The wind directions, as measured on a 30-m tower at an observation station
about 9 km NNW of Yucca Lake (Table 2), is predominantly northerly except
during the months of May through August when winds from the south-southwest
predominate. Because of the prevalent mountain/valley winds in the basins,
south to southwest winds predominate during daylight hours during 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 (Quiring, 1968).
Geology and Hydrology
Geological and hydrological studies of the NTS have been in progress by
the U. S. Geological Survey and various other organizations since 1956.
Because of this continuing effort, including subsurface studies of numerous
boreholes, the surface and underground geological and hydrological
characteristics for much of the NTS are known in considerable detail. This is
particularly true for those areas in which underground experiments are
conducted. A comprehensive summary of the geology and hydrology of the NTS
was edited and published by Eckel (1968).
4
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TABLE 1. CHARACTERISTICS OF CLIMATIC TYPES IN NEVADA
Climate
Type
Alpine
tundra
Humid
continental
Subhumid
continental
Mid-lati-
tude steppe
Mid-lati-
tude desert
Low-lati-
tude desert
Mean Temperature
°C
(°F)
Winter Summer
-18°
( 0°
-12°
(10°
-12°
(10°
-7°
(20°
-7°
(20°
-4°
(40°
- -9°
- 15°)
- -1°
- 30°)
- -1°
- 30°)
- 4°
- 40°)
- 4°
- 40°)
- 10°
- 50°)
4°
(40°
10°
(50°
10°
(50°
18°
(65°
18°
(65°
27°
(80°
- 10°
- 50°)
- 21°
- 70°)
- 21°
- 70°)
- 27°
- 80°)
- 27°
- 80°)
- 32°
- 90°)
Annual Precipitation
cm
(inches)
Total* Snowfall
38
(15
64
(25
30
(12
15
( 6
8
( 3
5
( 2
- 114
- 45)
- 114
- 45)
- 64
- 25)
- 38
- 15)
- 20
- 8)
- 25
- 10)
Medium to
heavy
Heavy
Moderate
Light to
moderate
Light
Negligible
Dominant
Vegetation
Alpine
meadows
Pine-fir
forest
Pine or scrub
woodland
Sagebrush,
grass, scrub
Greasewood,
shadscale
Creosote
bush
Percent
of Area
1
15
57
20
7
*Limits of annual precipitation overlap because
water balance.
of variations in temperature which affect the
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TABLE 2. NTS STATION 6 SURFACE WIND SUMMARY*
2.8 km SE BOY, NTS
Wind
Direction
360
350
340
330
320
310
300
290
280
270
260
250
240
230
220
210
200
190
180
170
160
150
140
130
120
110
100
90
80
70
60
50
40
30
20
10
Observed
Frequency
1778
2066
1825
1188
768
456
354
258
244
198
220
281
354
627
862
1055
1225
1415
1280
1219
993
800
678
529
414
356
388
358
361
374
415
649
813
1080
1414
1600
Percent
Frequency
5.9
6.8
6.0
3.9
2.5
1.5
1.2
0.9
0.8
0.7
0.7
0.9
1.2
2.1
2.8
3.5
4.0
4.7
4.2
4.0
3.3
2.6
2.2
1.7
1.4
1.2
1.3
1.2
1.2
1.2
1.4
2.1
2.7
3.6
4.7
5.3
Percent
Frequency
Within ±10°
17.9
18.7
16.7
12.5
7.9
5.2
3.5
2.8
2.3
2.2
2.3
2.8
4.2
6.1
8.4
10.4
12.2
12.9
12.9
11.5
9.9
8.1
6.6
5.3
4.3
3.8
3.6
3.6
3.6
3.8
4.7
6.2
8.4
10.9
13.5
15.8
Average
Wind
Speed
(m/s)
3.7
3.4
3.3
3.5
2.8
2.5
2.3
2.4
2.3
2.1
2.4
2.6
3.7
4.5
5.2
5.4
5.6
5.5
5.0
4.1
3.4
3.0
2.6
2.2
2.0
2.2
2.4
2.5
2.3
2.5
2.6
2.7
3.0
4.5
5.0
4.3
'All readings are taken 30 m above the surface, which is at an elevation of
1225 m above sea level (Quiring, 1979).
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There are two major hydrologic systems on the NTS (Figure 3). Groundwater
in the northwestern part of the NTS or in the Pahute Mesa area has been
reported to travel somewhere between 2 and 180 m per year to the south and
southwest toward the Ash Meadows discharge area in the Amargosa Desert
(ERDA-1551, September 1977). It is estimated that the groundwater to the east
of the NTS moves from north to south at a rate of not less than 2 nor greater
than 220 m per year. Carbon-14 analyses of this eastern groundwater indicate
that the lower velocity is nearer the true value. At Mercury Valley, in the
extreme southern part of the NTS, the groundwater flow direction shifts to the
southwest toward the Ash Meadows discharge area in the southeastern Amargosa
Valley.
The water levels below the NTS vary from depths of about 100 m beneath the
surface at valleys in the southeastern part of the site to more than 600 m
beneath the surface at highlands to the north. Although much of the valley
fill is saturated, downward movement of water is extremely slow. The primary
aquifer in these formations is the Paleozoic carbonates which underlie the
more recent tuffs and alluviums.
Land Use of NTS Environ^
Figure 4 is a map of the off-NTS area showing general land use. A wide
variety of uses, such as fanning, mining, grazing, camping, fishing, and
hunting, exist due to the variable terrain. For example, within a 300-km
radius west of the NTS, elevations range from below sea level in Death Valley
to 4420 m above MSL in the Sierra Nevada Range. Additionally, parts of two
valleys of major agricultural importance (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 small-scale but intensive farming of a variety of
crops by irrigation. Grazing is also common in this area, particularly to the
northeast. The area north of the NTS is also mid-latitude steppe where the
major agricultural-related activity is grazing of both cattle and sheep. Only
areas of minor agricultural importance, primarily the growing of alfalfa hay,
are found in this portion of the State within a distance of 300 km.
In the summer of 1974, a brief survey of home gardens around the NTS
showed that a majority of the residents grow or have access to locally grown
fruits and vegetables. Approximately two dozen of the surveyed gardens within
30-80 km of the NTS boundary were selected for sampling. These gardens
produce a variety of root, leaf, seed, and fruit crops (Andrews and
Vandervort, 1978).
The only industrial enterprises within the immediate off-NTS area are 31
active mines and mills, two oil fields at Trap Springs and Eagle Springs, as
shown in Figure 4, and several chemical processing plants located near
Henderson, Nevada (about 23 km south of Las Vegas). The number of employees
for these operations varies from one person at several small mines to several
hundred workers for the oil fields north of NTS and the chemical plants at
Henderson. Most of the individual mining operations involve less than 10
workers per mine; however, a few operations employ 100-250 workers.
7
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SCALE IN MILES
0 10 20 30 40
SCALE IN KILOMETERS
SILENT CANYON CALOERA
TIMBER MOUNTAIN CALOERA
FLOW DIRECTION
GROUND WATER
Figure 3. Groundwater Flow Systems - Nevada Test Site.
8
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CAMPIN6 & RECREATIONAL
AREAS
MINE
O HUNTING
FISHING
SCALE IN MILES
50 100
0 50 100 150
SCALE IN KILOMETERS
Figure 4. General Land Use, Nevada Test Site Vicinity.
9
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The major body of water close to the NTS is Lake Mead (100 km southeast) a
man-made 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, and a portion of the water is used by
southern California. Smaller reservoirs and lakes located in the area are
primarily for irrigation and for livestock. In California, the Owens River
and Haiwee Reservoir feed into the Los Angeles Aqueduct and are the major
sources of domestic water for the Los Angeles area.
As indicated in Figure 4, there are many places scattered in all
directions from the NTS where such recreational activities as hunting,
fishing, and camping are enjoyed by both local residents and tourists. 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 with the most extensive activities occurring
during all months except the hot summer months. All hunting is generally
restricted to various times during the last 6 months of the year.
Dairy farming is not extensive within the 300-km-radius area under
discussion. A survey of milk cows during the summer of 1977 showed 8800 dairy
cows, 419 family milk goats, and 464 family milk cows in the area. The family
cows and goats are distributed in all directions around the test site (Figure
5), whereas the dairy cows (Figure 6) are primarily located southeast of the
test site (Moapa River Valley, Nevada; Virgin River Valley, Nevada; and Las
Vegas, Nevada), northeast (Lund area), and southwest (near Barstow,
California).
Grazing of beef cattle and sheep is the most common use of the land in this
area. Approximately 350,000 beef cattle and 160,000 sheep (Utah Dept. of
Agriculture, 1978) were produced within the 300-km radius surrounding the test
site during this report period. The distribution of the beef cattle and sheep
by county are shown in Figures 7 and 8, respectively.
Population Distribution
The populated area of primary concern around the NTS which is sampled and
monitored by surveillance networks is shown in Figure 9 as the area within a
300-km radius of the NTS Control Point (CP-1), except for the areas west of
the Sierra Nevada Mountains and in the southern portion of San Bernardino
County. Based upon the projections for the year 1977 by the U.S. Bureau of
the Census and the 1978 projections for Washoe and Clark Counties by the
University of Nevada (Reno), Figure 9 shows the current population of counties
in Nevada and pertinent portions of the States of Arizona, California, and
Utah. Las Vegas and vicinity is the only major population center within the
inscribed area of Figure 9. With the assumption that the total populations of
the counties bisected by the 300-km radius lie within the inscribed area,
there is a population of about 548,100 people living within the area of
primary concern, about 70 percent of which lives in the Las Vegas urbanized
area. If the urbanized area is not considered in determining population
density, there are about 1.5 persons per mi2. For comparison, the United
States (50 states, 1970 census) has a population density of 57 persons per
10
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STOREY
HI
ORMSB
(0)
DOUGLAS
(49)
CHURCHILL
(202) / |33)
\ fLANDER
EUREKA
160)
WHITE PINE
197)
SAN BERNARDINO
(202)
7/79
Figure 5. Location and Number of Family Milk Cows and Goats,
11
-------
ORMSBY
|85|
MILK DAIRIES
GRADE A MILK COWS
* GRADE B MILK COWS
GRADE A&B MILK COWS
7/79
Figure 6. Location and Number of Dairy Cows.
12
-------
STORE
(200)
ORMSBY
(0)
DOUGLAS
(23,000)
7/79
SAN BERNARDINO
(11,500)
ARIZONA
Figure 7. Distribution of Beef Cattle by County.
13
-------
STOREY
(0)
ORMSBY
(0)
DOUGLAS
(10,000)
7/79
WHITE PINE
(24,000)
SAN BERNARDINO
(11,000)
ARIZONA I
N
Figure 8. Distribution of Sheep by County.
14
-------
SAN'BERNARDINO
(21,200)
BARSTOW
(25,200)
ORMSBV->
(27,400)
7/79
Figure 9. Population of Arizona, California, Nevada, and
Utah Counties Near the Nevada Test Site.
15
-------
square mile, and the overall Nevada average from the 1977 estimate is 6.2
persons per mi2.
The off-site areas within about 50 mi of the NTS are 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 3600, is located about 45 mi south of the NTS CP-1. The Amargosa Farm
area has a population of about 1000 and is located about 31 mi southwest of
CP-1. The Spring Meadows Farm area, located about 35 mi southwest of CP-1,
consists of approximately 4000 square miles with a total population of about
15. The largest town in the near off-site area is Beatty with a population of
about 600; it is located about 65 km to the west of CP-1.
In the adjacent states, the Mojave Desert of California, which includes
Death Valley National Monument, lies along the southwestern border of Nevada.
According to the California Population Research Unit (1979), the population
within the Monument boundaries varies considerably from season to season from
a minimum of 1400 permanent residents in the area during the summer months to
as many as 15,000 tourists and campers in the area on any particular day
during the major holiday periods in the winter months. The largest town and
contiguous populated areas in this general area is Barstow, located 265 km
south-southwest of the NTS, with a population of about 25,200. The next
largest populated area is the Ridgecrest-China-Lake area (20,000), about
190 km Southwest of the NTS. The Owens Valley, where numerous small towns are
located, lies about 50 km west of Death Valley. The largest town in Owens
Valley is Bishop, located 225 km west-northwest of the NTS, with a population
of about 5300 including contiguous populated areas.
The extreme southwestern region of Utah is more developed than the
adjacent part of Nevada. The largest town, Cedar City, with a population of
10,711, is located 280 km east-northeast of the NTS. The next largest
community is St. George, located 220 km east of the NTS, with a population of
9051.
The extreme northwestern region of Arizona is mostly undeveloped range
land with the exception of that portion in the Lake Mead Recreation Area.
Several small retirement communities are found along the Colorado River,
primarily at Lake Mojave and Lake Havasu. The largest town in the area is
Kingman, located 280 km southeast of the NTS, with a population of about 8000.
AIRBORNE RELEASES OF RADIOACTIVITY AT THE NTS DURING 1978
During this report period, only underground nuclear detonations were
conducted. All detonations were contained. However, during re-entry drilling
operations, occasional low level releases of airborne radioactivity, primarily
radioxenon, did occur. According to information provided by the Nevada
Operations Office, DOE, the following quantities of radionuclides were
released into the atmosphere during CY 1978:
16
-------
TABLE 3. TOTAL AIRBORNE RADIONUCLIDE RELEASES
AT THE NEVADA TEST SITE
Quantity Released
Radionuclide (Ci)
3H
8SKr
131I
l83Xe
139Xe
1J3Xe
90.470
15.000
0.0001
8.213
1.44
0.369
Total 115.4921
There is a continuous low-level release of tritium and krypton-85 on the NTS.
Tritium is released primarily from the Sedan crater and by evaporation from
ponds formed by drainage of water from tunnel test areas in the Rainier Mesa.
Krypton-85 slowly seeps to the surface from underground test areas. The
quantity of radioactive seepage has not been quantified, but has been detected
at on-site sampling locations and occasionally at off-NTS locations.
DESCRIPTION OTHER TEST SITES
Table A-l lists the names, dates, locations, yields, depths, and purposes
of all underground nuclear tests conducted at locations other than the NTS.
No off-NTS nuclear tests were conducted during this report period.
For the purpose of this report a large body of data and ancillary
information which is too bulky for inclusion in the report has been placed in
the Appendices. Where possible this information has been summarized either in
some of the text tables or is discussed directly in the report. In some
instances, for the convenience of readers who require the more detailed
information, references to the appendices will be included in the text.
17
-------
SUMMARY
During 1978, the monitoring of gamma radiation levels in the environs of
the NTS was continued through the use of an off-site network of radiation
dosimeters and gamma-rate recorders. Concentrations of radionuclides in
pertinent environmental media were also continuously or periodically monitored
by established air, milk, and water sampling networks. Before each
underground nuclear detonation, mobile radiation monitors, equipped with
radiation monitoring instruments and sampling equipment, were on standby in
off-NTS locations to respond to any accidental release of airborne
radioactivity. An airplane was airborne near the test area at detonation time
to track and sample any release which might occur.
All radioactivity from the underground nuclear tests was contained except
for a total of about 115 curies (Ci) of radioactivity which was reported by
DOE/NV as being released intermittently throughout the year by post-shot
drilling operations, and small undetermined amounts of radioxenon, tritium,
and krypton-85 which slowly seep to the surface from the underground test
areas.
The only off-NTS indication of this radioactivity was xenon-133
(concentration, 6.5 x 10~n pCi/ml) in an air sample collected at Diablo,
Nevada, during the period April 19 to 26 and tritiated hydrogen (HT) in two
air samples collected at Indian Springs, Nevada, during the periods November
13 to 20 (2.4 x 10-11 yCi/ml) and November 27 to December 4 (1.8 x KT11
yCi/ml). The estimated whole-body dose equivalents estimated to a
hypothetical receptor at these locations were estimated to be 6.2 microrem
(yrem) at Diablo and 5.8 microrem (yrem) at Indian Springs. Based upon the
respective populations at these locations, 6 persons and 1500 persons, the
dose commitment(*) was estimated to be 0.000037 person-rem at Diablo and
0.0087 person-rem at Indian Springs. As Diablo is beyond the 80 km-radius of
the NTS Control Point, the 80-km dose commitment would be 0.0087 person-rem.
All other measurements of radioactivity made by the Off-Site Radiological
Safety Program were attributed to naturally occuring radioactivity or
worldwide fallout and not related to underground nuclear test operations
during this report period. Radioactivity from the atmospheric nuclear tests
by the People's Republic of China on March 15, 1978, at 0100 hours, EST, and
December 14, at 0100 hours, EST, was detected on filter samples of the Air
Surveillance Network collected in March, April, and December. The tests
resulted in increases of airborne radioactivity and the specific radionuclides
identified by the Air Surveillance Network were zirconium-95, moloybdenum-99,
ruthenium-103, iodine-131, tellurium-132, cesium-137, barium-140, cerium-141,
and curium-144.
(*) Product of estimated average dose equivalent and population.
18
-------
The Long-Term Hydrological Monitoring Program used to monitor radionuclide
concentrations in surface and groundwaters which are down the hydrologic
gradient from sites of past underground nuclear tests was continued for the
NTS and eight other sites located elsewhere in Nevada, Alaska, Colorado, New
Mexico, and Mississippi.
Radioactivity from past underground nuclear tests was observed only in
surface or well water samples at the Project Dribble site near Baxterville,
Mississippi, and at the Project Long Shot site on Amchitka Island, Alaska. At
Project Dribble site, the water sample collected from the Half Moon Creek
Overflow had a tritium concentration (2.7 x 10~6 pCi/ml) that was higher
than background. A special survey for tritium in subsurface soil moisture, at
this site during the periods September 12 to 19, 1977, and April 18 to 27,
1978, revealed significant tritium contamination below the ground surface;
the highest tritium concentration found was 1.0 x 10"3 yCi/ml in soil
moisture at a depth of 10 ft in a drilled hole 25 ft southeast of surface
ground zero. This value is 30 percent of the Concentration Guide (3.0 x 10~3
uCi/ml) for an individual in a controlled or uncontrolled area and is 50 times
the maximum permissible level for tritium set by the EPA Drinking Water
Regulations (2.0 x 10~5 yCi/ml), although the ground water in this area is
not used for drinking.
The source of tritium is believed to be the residual from the post-shot
drilling operations and not from leakage of radioactivity from the detonation
cavity at a depth of 2700 ft. All of the tritium contamination was confined
to the subsurface. None was detected in any surface water other than the Half
Moon Creek Overflow nor in any of the off-site well samples. No off-site
residents are suspected of being exposed to the waterborne tritium. The
nearest populated area to the site is a residence, which is about 1 mile
south-southwest of surface ground zero.
The above background concentrations of tritium found in several water
samples collected from shallow wells and surface waters at the Project Long
Shot site on Amchitka Island, Alaska, ranged from 2.8 x 10~7 uCi/ml to 7.3 x
10~6 yCi/ml. This range in concentrations is comparable to that found in
samples collected during 1977 by EPA and during previous years by the U.S.
Geological Survey and the University of Washington. The highest tritium
concentration was found to be only 0.24 percent of the Concentration Guide.
This water is not used for drinking purposes, therefore this tritium
contamination was found to pose no radiological hazard.
19
-------
MONITORING DATA COLLECTION, ANALYSIS, AND EVALUATION
The major portion of the Off-Site Radiological Safety Program for the NTS
consisted of continuously operated dosimetry and air sampling networks and
scheduled collections of milk and water samples at locations surrounding the
NTS. Before each nuclear test, mobile monitoring personnel were positioned in
the off-site areas most likely to be exposed to a possible release of
radioactive material. These monitors, equipped with radiation survey
instruments, gamma exposure-rate recorders, thermoluminescent dosimeters
(TLD's), portable air samplers, and supplies for collecting environmental
samples, were prepared to conduct a monitoring program directed from the NTS
Control Point (CP-1) via two-way radio communications. In addition, for each
event at the NTS, a U.S. Air Force aircraft with two Reynolds Electrical and
Engineering Company monitoring personnel equipped with portable radiation
survey instruments was airborne near surface ground zero to detect and track
any radioactive effluent. One EMSL-LV cloud sampling and tracking aircraft
was also available to obtain in-cloud samples, assess total cloud volume, and
provide long-range tracking in the event of a release of airborne
radioactivity.
This report contains descriptions for each surveillance network and
interpretations of the analytical results. These analytical results are
summarized (maximum, minimum, and arithmetic average concentrations) in
Appendix A. Where appropriate, the arithmetic averages in the tables are
compared to the applicable DOE Concentration Guides (CG's) listed in Appendix
B. Unless specifically stated otherwise, all concentration averages are
arithmetic averages.
For "grab" type samples, radionuclide concentrations were corrected for
radioactive decay by extrapolating to the appropriate collection date.
Concentrations determined over a period of time were extrapolated to the
mid-point of the collection period. Beginning in 1978, concentration averages
were calculated from each measured concentration including those less than the
minimum detectable concentration (MDC). During prior years, concentration
averages were calculated assuming that each concentration less than the MDC
was equal to the MDC. Due to the large number of radionuclides that can be
present below the MDC in air, those concentrations less than the MDC were
assumed to be zero for the computation of concentration averages, and only
those radionuclides detected during the year were averaged by the above new
method and reported.
Beginning in 1978, the definition of the minimum detectable concentration
for all analyses was redefined as the total counting error resulting from the
sum of a 5 percent Type I error (accepting the presence of radioactivity when
none is present) and a 5 percent Type II error (failure to recognize the
20
-------
presence of radioactivity when it is present). This essentially increased the
MDC's about a factor of two compared with the MDC values used in prior years,
defined as the two-sigma counting error for determinations that were equal to
or less than the two-sigma error.
QUALITY ASSURANCE
The quality assurance program for laboratory analyses consists of a
combination of instrumental quality control procedures, the analysis of
replicate samples to measure precision, and the analysis of cross-check
samples from an independent laboratory to measure the accuracy of analyses.
The instrumental quality control procedures consist of calibration,
background quality control, and reference standard quality control.
The counting systems are calibrated by using a standard radionuclide
solutions obtained from the Quality Assurance Branch at EMSL-LV or in some
cases directly from the National Bureau of Standards. These standards are
then made up into the appropriate counting standards; several different
geometries for gamma counting, planchets with varying thickness of solids for
gross alpha-beta and strontium analyses by gas proportional counting, liquid
scintillation vials with the appropriate scintillant for liquid scintillation
counting, and electroplated sources for alpha spectroscopy. These standards
are used to determine the counting efficiency of the various detectors using
the same conditions used to count the samples.
The dosimetry system used for measuring external gamma radiation exposures
with thermoluminescent dosimeters (TLD's) is calibrated by exposing TLD's to a
known amount of radiation and reading them out at timed intervals for
comparison with any given batch of TLD's being read out under normal operating
conditions. The TLD's exposed to a known quantity of radiation defines the
linear relationship between the exposure measured in mR and TLD
thermoluminescence in nanocoulombs. The known radiation exposure used to
calibrate the TLD's is determined from the theoretical estimate of the gamma
field from the radiation source and actual measurements of the gamma field by
using an ion chamber. Both the radiation source and the ion chamber are
calibrated by an independent organization in accordance with procedures that
are traceable to the National Bureau of Standards.
Background quality control for all laboratory systems is maintained by the
periodic background measurements for each system. The backgrounds are plotted
on control charts to check trends and to determine whether individual
measurements are within required limits. Background quality control is
especially important on instruments such as alpha spectrometers and germanium
diodes where the backgrounds are extremely low.
Quality control for reference standards, is basically the same for all
laboratory instruments although the details of application are different. A
reference standard is one which produces a consistent response for the
instrument with which it is used. The idea is to plot on a quality control
chart the reproducibility (within limits) of instrument response versus time.,
21
-------
The response for planchet and liquid scintillation counters is a count rate of
the standard. For gamma and alpha spectrometers several responses are
plotted, i.e., count rate, energy for each peak location from a multi-peaked
standard, difference(s) in energy between peaks, and resolution of the peaks.
For the dosimetry system, the response is the luminescence, measured in
coulombs, from a constant light source.
The precision of the laboratory analyses as influenced by sampling,
analytical errors, and counting errors, is estimated through a program of
replicate analysis and sampling. About 10 percent of the routine samples are
split, and the pairs are both analyzed individually to obtain an estimate of
the analytical and counting errors combined. The total error, the above
errors plus any sampling error, is estimated from replicate sampling. About
10 percent of the sampling workload is collected in duplicate, except for the
dosimetry network, in which six replicate exposures are assessed for each
location. The results of the replicate sampling program (Appendix C) are then
used to identify those results that are significantly different than those
obtained in the past.
Accuracy checks are made by the analyzing laboratory intercomparison
samples provided by the Quality Assurance Branch, EMSL-LV (EPA 1979). These
intercomparison samples are simulated environmental samples containing known
amounts of one or more radionuclides. The intercomparison samples are
analyzed by the laboratory and the results are sent to the Quality Assurance
Branch for statistical analysis and comparison with the known value and
analytical values obtained by other participating laboratories. The
intercomparisons are performed bimonthly, quarterly, and semiannually,
depending upon the type of sample. A report and a control chart for each type
of analysis are returned to each participant. The identities of the
participants are coded with each participant knowing his own code, but not
those of the other participants. The report sent to each participant lists
the individual results (analyses are done in triplicate), the mean and the
experimental standard deviation of the three results, the mean range plus the
standard deviation of the range, the known value, and the number of standard
deviations of each participant's mean value from the grand average of all
results and from the known value.
In general, the 1978 analyses were within acceptable limits, except for
the strontium-89 and strontium-90 analyses in milk and water. However, none
of the analytical results were different from the known values by more than 25
percent. Intercomparison results for 1978 are summarized in the Appendix
(Table A-3).
AIR SURVEILLANCE NETWORK
The Air Surveillance Network (ASN) was operated by the EMSL-LV to monitor
environmental levels of radioactivity and to detect any airborne release of
radioactivity from NTS operations. The Network consisted of 49 active and 73
standby sampling stations located in 21 Western States (Figures 10 and 11).
Samples of, airborne particulates were collected at each active station on
10-cm diameter, glass-fiber filters from air volumes totaling 500 to 1200 m
22
-------
>»} CURRANT
DUCKWATER
ANGLEWORM RN
BLUE JAY
HOT CREEK RN B/*-x- BLUE EAGLE RN
STONE CABIN RN*
S N.Lfl / SUNNYSIOE
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NELLIS AIR FORCE
RANGE ROBINSONS
CALIENTE
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FLEURiOE LIS RN
\DC(
ACTIVE ASN STATION
STAND-BY STATION WITH TELEPHONE
STAND-BY STATION WITHOUT TELEPHONE
SO 100 150
SCALE IN KILOMETERS
Figure 10. Air Surveillance Network - Nevada.
23
-------
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A STAND-BY STATION WITH TELEPHONE
Figure 11. Air Surveillance Network - Outside Nevada.
-------
of air at standard pressure. The filters, which are 99.9 percent efficient
for particles £0.3 ym in diameter, were collected three times per week,
resulting in 48- or 72-hour samples from each active station. Activated
charcoal cartridges directly behind the glass-fiber filters were used
regularly for the collection of gaseous radioiodines at 21 stations near the
NTS. Charcoal cartridges could have been added to all other stations and all
standby stations could have been activated, if necessary, by telephone request
to station operators or by field personnel. All air samples (filters and
cartridges) were mailed to the EMSL-LV for analysis. Special retrieval could
have been arranged at selected locations in the event of a radioactive
release.
During the year, the standby stations were activated quarterly to check
the operation of the samplers and to maintain the expertise of Network station
operators. In anticipation of airborne radioactivity from the atmospheric
nuclear tests by the People's Republic of China on March 15, 1978, at 0100
hours and on December 14, 1978, at 0100 EST, 66 of the standby stations were
activated with filters and charcoal cartridges during the periods March 17
through April 7 and December 15, 1978, through January 5, 1979.
During this report period, no airborne radioactivity related to the
underground nuclear testing program at the Nevada Test Site was detected on
any sample from the ASN. However, radioactivity from the nuclear tests by the
People's Republic of China was detected on the filters and charcoal
cartridges. Appendix D summarizes the analytical results of those samples
containing radioactivity from Chinese tests.
NOBLE GAS AND TRITIUM SURVEILLANCE NETWORK
The Noble Gas and Tritium Surveillance Network, which was first
established in April 1972, monitors the airborne levels of radiokrypton,
radioxenon, and three forms of tritium (3H)tritiated hydrogen (HT),
tritiated water (HTO), and tritiated methane (CH3T). The Network consists of
four stations on and seven off-NTS shown in Figure 12. Area 51, which appears
to be off NTS, is considered to be on NTS as it is an access-controlled area
with radiological safety support provided by NTS personnel.
The equipment used in this Network is composed of two separate systems, a
compressor-type air sampler and a molecular sieve sampler. The
compressor-type equipment continuously samples air over a 7-day period and
stores it in two pressure tanks. The tanks together hold approximately 2
cubic meters of air at atmospheric pressure. They are replaced weekly and
returned to the EMSL-LV where the contents of the tanks are analyzed for
krypton-85, radioxenons, and. tritiated methane by gas chromatography and
liquid-scintillation counting techniques (Table A-2).
A molecular sieve is used to collect water samples from air. A prefilter
is used to remove the particulates prior to passage of the air through a
series of molecular sieve columns. Approximately 5 cubic meters of air are
passed through each sampler over a 7-day sampling period. The HTO absorbed on
the first molecular sieve column is recovered and the concentration of tritium
in yCi/ml of sampled air is determined by liquid-scintillation counting
25
-------
FURNACE CREEK
' DEATH VALLEY JCT
LOCATIONS NOBLE GAS & TRITIUM SAMPLING LOCATIONS
Figure 12. Noble Gas and Tritium Surveillance Network.
26
-------
techniques. The tritium which passes through the first column as free
hydrogen (HT) is oxidized to water and collected on the last molecular sieve
column. The HT concentration is calculated from the tritium concentration in
the oxidized tritium (water) recovered from the last column.
Table A-4 summarizes the results of this Network by listing the maximum,
minimum, and average concentrations for krypton-85, xenon-133, and tritium as
methane, as tritiated water or as tritiated hydrogen. The annual average
concentrations for each station were calculated over the time period sampled
using all values less than the MDC. All concentrations of krypton-85,
xenon-133, tritium as tritiated methane, tritium as tritiated water, and
tritium as HT are expressed in the same unit, yCi/ml of air. Since the
tritium concentration in air may vary by factors of 15-20 while the
concentration in yCi/ml of atmospheric water varies by factors up to about 7,
the tritium concentration in yCi/ml of atmospheric moisture is also given in
the table as a more reliable indicator in cases when background concentrations
of HTO are exceeded.
As shown in Table 4, the average concentration of krypton-85 for the year
at all stations was the same (2.0 x 10~u uCi/ml), except for BJY (2.2 x
10~11 yCi/ml), which is significantly different than the Network average at
the 95% and 99% confidence levels. The average concentration at this station
has been the highest in the Network more often than at any other station.
This probably results from its central location on the NTS where seepage of
the noble gases from past underground nuclear detonations is suspected. As
shown in Table 4 and Figure 13, the average concentration of krypton-85 for
the whole Network has gradually increased since sampling was initiated in
TABLE 4. ANNUAL AVERAGE KRYPTON-85 CONCENTRATIONS IN AIR, 1972-1978
Concentration, 1Q"11 uCi/ml
Locations
1972 1973 1974 1975 1976 1977 1978
Death Valley Jet., Calif.
Beatty, Nev.
Diablo, Nev.
Hiko, Nev.
Indian Springs, Nev.
Las Vegas, Nev.
Mercury, NTS, Nev.
Area 51, NTS, Nev.
BJY, NTS, Nev.
Area 12, NTS, Nev.
Tonopah, Nev.
Network Average
1.6
1.6
1.6
1.6
-
1.6
1.6
1.6
1.7
1.6
1.6
1.62
1.5
1.6
1.6
1.6
-
1.6
1.6
1.6
1.8
1.6
1.6
1.61
1.8
1.7
1.7
1.7
-
1.7
1.8
1.7
1.9
1.8
1.8
1.76
1.7
1.9
1.8
1.7
2.0
1.8
1.8
1.8
1.9
1.8
1.7
1.81
2.0
2.0
1.9
1.7
2.0
1.8
1.9
2.0
2.0
2.0
1.9
1.93
2.0
2.0
1.9
1.9
2.0
2.0
2.0
1.9
2.1
1.9
1.9
1.96
2.0
2.0
2.0
2.0
2.0
2.0
2.0
2.0
2.2
2.0
2.0
2.02
27
-------
70
__
1980
1990
Year
Trend in Annual Network Concentrations of
Krypton-85 1972-1978.
1972. This increase observed at all stations probably reflects the worldwide
increase in ambient concentrations resulting from the proliferation of nuclear
technology.
The maximum concentration of krypton-85 for all stations ranged from 2.4 x
10"n uCi/ml to 2.9 x 10"n uCi/ml (Table A-4). As shown by the Figure
14, these higher concentrations and all the other concentrations for the
Network stations combined followed a log-normal distribution with a geometric
mean of 2.01 x 10'11 pCi/ml and a geometric standard deviation of 1.1. As
the expected geometric standard deviation of the krypton-85 measurements
attributed to sampling/analytical/counting errors was determined to be 1.2
from the duplicate sampling program (Appendix C), the variation in the
krypton-85 concentrations throughout the Network appears to be caused
primarily by the errors in its measurement.
Xenon-133 was detected above its MDC of about 4 x 10~12 yCi/ml at the
locations, during the periods, and at the concentrations shown in the
following table:
28
-------
1 10.0
\ 8.0
O
_=! 6.0
ro 5.0
4.0
O
«
0)
o
o
o
-9.0
-7.0
3.0
2.0
8 1.0
Geometric Mean = 2.01 * 10-11 uci/ml
Geometric Standard Deviation = 1.1
0.01 I 0.1 I 0.5
0.051 0.2
I I I
i
_l_
10 | 30 | 50 | 70 | 90 | 98
5 I 20 I 40 I 60 80 I 95 I 99
i I I I I I I I I I I II
Cumulative Frequency, %
99.8
|99.£
99.99
Figure 14. Distribution of Network Concentrations of Krypton-85.
TABLE 5. CONCENTRATIONS OF AIRBORNE XENON-133 DETECTED ON AND OFF NTS
Location
Diablo, Nev.
Mercury, NTS, Nev.
Area 51, NTS, Nev.
BJY, NTS, Nev.
Sampling
Period
4/19-26
2/27-3/6
5/8-15
2/21-27
2/27-3/6
2/21-27
2/27-3/6
4/3-10
5/1-8
Xenon-133 Concentration
± 2 Sigma Counting Error
(X10-12pCi/ml)
65 ± 4.0
29 ± 5.4
170 ± 3.0
45 ± 5.2
16 ± 4.4
14,000 ± 30*
100 ± 5.4
26 ± 4.2
10 ± 3.8
* This high value resulted from post-shot drilling operations.
As shown in Table 5, xenon-133 was detected on the NTS and at only one
location off the NTS, namely Diablo, NV. This concentration measured at
Diablo, if it had persisted throughout the year, would have been only 0.065
percent of the CG (Appendix B).
As in the past, tritium as HTO in atmospheric moisture samples was
generally at background concentrations, below the MDC of 3 to 4 x 10"6
pCi/ml at all off-NTS stations and at the on-NTS stations at Mercury and
29
-------
Area 51. Occasional increases in concentrations appear to be a part of the
normal fluctuations in background. The on-NTS stations at BJY and Area 12
continued to have concentrations consistently above background; the
concentration averages for these stations were factors of 7 to 15 times the
averages for all off-NTS stations.
The average concentrations of trituim as HT (Table A-4) at the off-NTS
stations were comparable to those observed in 1977. During 1978 the averages
ranged from <6 x 10'13 yCi/ml to 1.8 x 10~12 yCi/ml. whereas in 1977 the
averages ranged from <6 x 10~13 yCi/ml to <2 x 10~12 pCi/ml. From a
review of the cumulative frequency distributions of the data for each station,
two samples collected at Indian Springs had concentrations of 2.4 x 10~n
yCi/ml and 1.8 x 10-11 yCi/ml during the respective periods November 13 to
20 and November 27 to December 4, which did not appear to be a part of the
background. If the highest of these concentrations had persisted for the
year, the exposure of off-NTS residents would have,been 0.036 percent of the
CG.
The concentrations of tritium as tritiated methame were generally below
the MDC of 4 x 10"12 yCi/ml at all locations as normally observed.
Detectable concentrations were observed in two samples collected at Beatty,
Nevada; however, based upon the cumulative frequency distribution for the
tritiated methane concentrations for the total Network, the concentrations
appeared to be part of the background.
DOSIMETRY NETWORK
The Dosimetry Network is comprised of thermoluminescent dosimeters placed
at 78 locations and gamma exposure rate recorders placed at 31 locations
around the NTS for the purpose of measuring environmental background levels of
gamma radiation (Figure 15). From an accurate measurement of the
environmental background radiation rate at each monitoring location, any
exposure in excess of background due to NTS testing operations can be
determined.
Thermoluminescent Dosimeters
At locations within a 270-km radius of the center of the NTS,
thermoluminescent dosimeters were placed at inhabited and uninhabited
locations. Each Dosimetry Network station was equipped with three Harshaw
Model 2271-G2 (TLD200) dosimeters, which were routinely exchanged on a
quarterly basis. Within the general area covered by the dosimetry stations,
25 cooperating off-site residents each wore a dosimeter, which was exchanged
at the same time as the station dosimeters.
The Model 2271-G2 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
30
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KIRKEBYRN
GARRISON
DUCKWATER
ROUND MTN
MANHATTAN* ,HOT CREEK RN /^ ^
STONE CABIN A
TONOPAHT^-^cTARK'S STA
CASEY'S RN
EN*' ^COMPLEX I
\.tPINE CREEK RN
» rTWINSPGS
TTR»
QUEEN CITY SMT
NEVADA FARMS
ROBINSON'S
HIKO
OYOTE SMT
"^HANCOCK SMT
ELGIN
4CARP
HERRI'S RN
NEVADA iNELLIS AIR
TEST " FORCE
SITE I RANGE
INDEPENDENCE
LONE
TENNECO
DEATH VALLEY JCT* X
PAHRUMP
SCALE IN MILES
50 100
TLO STATION ONLY
A ACTIVE GAMMA RATE RECORDER WITH TLO STATION
STAND-BY GAMMA RATE RECORDER WITH TLO STATION
* STAND-BY GAMMA RATE RECORDER ONLY
100 150
SCALE IN KILOMETERS
Figure 15. Dosimetry Network.
31
-------
dosimeters are placed in a secured, rugged plastic housing 1 meter above
ground level at each station to standardize the exposure geometry.
After appropriate corrections were made for background exposure
accumulated during shipment between the laboratory and the monitoring
location, the dosimeter readings for each station were averaged. The average
value for each station was then compared to the value for the past year to
determine whether the new value was within the range of previous background
values for that station. Any values significantly greater than previous
values would have led to net exposure calculations. Values significantly less
than the previous year would have been examined to determine possibility of
reading or handling errors. The results from each of the personnel dosimeters
were compared to the background value of the nearest station to determine
whether a net exposure had occurred.
The smallest exposure in excess of background radiation which may be
determined from these dosimeter readings depends primarily on variations in
the natural background exposure rate at the particular station. In the
absence of other independent exposure rate measurements, it is necessary to
compare the present exposure rate with past data which have been accepted as
representing the natural background. Typically, the smallest net exposure
observable for a 90-day monitoring period would be 5 to 15 mR in excess of
background, which ranges from 15 to 35 mR depending on location. The term
"background," as used in this context, refers to naturally occurring
radioactivity plus a contribution from residual man-made fission products.
Table A-5 lists the maximum, minimum, and average dose equivalent rate
(mrem/day) measured at each station in the Network during 1978 due to
penetrating gamma radiation. No allowance was made for the small additional
dose due to the neutron component of the cosmic ray spectrum. As shown by
Table A-4, no station exhibited an exposure in excess of background, which
under present criteria is defined as the 99 percent upper confidence limit of
the environmental background.
Station changes were made in the Network due to unusually high background
levels found at Caliente and Stone Cabin as shown in Table A-5. A cesium-137
calibration source for an LSI recorder was discovered near the Caliente TLD
station. The station was moved away from the recorder so that the TLD's were
no longer exposed to the calibration source. A radiation survey was performed
at Stone Cabin Ranch, which had the highest dose rate in 1977, and it was
determined that the stone building contributed significantly to the exposure
of the TLD's. When this station was moved away from the cabin, the background
rate decreased substantially. The station at Desert Oasis was abandoned at
the end of first quarter 1978 and a new station at Glendale was established 3
miles east of the Desert Oasis location. The Pine Creek station could not be
reached during January 1979 due to unusually heavy snowfall; the TLD's will
remain on station until the first quarter exchange in April 1979.
Table 6 shows the average annual dose rate for the Dosimetry Network to be
consistent with the Network average established in 1975 with the exception of
the 1977 average. Mechanical problems in readout procedures during the second
quarter of 1977 caused a high bias in the data which increased the Network
32
-------
TABLE 6. DOSIMETRY NETWORK SUMMARY
FOR THE YEARS 1971-1978
Environmental Radiation Dose Rate (mrem/y)
Year Maximum Minimum Average
1971
1972
1973
1974
1975
1976
1977
1978
250
200
180
160
140
140
170
150
102
84
80
62
51
51
60
50
160
144
123
114
94
94
101
95
average. The data for second quarter 1977, could not be adjusted to
compensate for these problems. The general decreasing trend from 1971 to 1975
and the leveling off since 1975 shown by the Network average is indicative of
the trend exhibited by individual stations.
Gamma Exposure Rate Recorders
A network of 13 full-time and 18 standby stationary gamma exposure rate
recorders (Figure 15) was also used at selected air sampling locations to
document any changes in the ambient exposure rate. The detector consists of a
2.5 by 30.5 cm constant-current ionization chamber (filled with methane) and
operates on either 115 V a.c. or a self-contained battery pack. Data are
recorded on a paper strip chart. These instruments have a range from 0.004
mR/h to 40 mR/h with an accuracy of about ±10 percent. The standby recorders
were activated on a routine quarterly basis to ensure the recorders were
functional. No increase in exposure rates attributable to current NTS
operations was detected by the routine recorders.
MILK SURVEILLANCE NETWORK
Milk is only one source for the dietary intake of environmental
radioactivity. However, it is a very convenient indicator of the general
population's intake of biologically significant radionuclide contaminants.
For this reason it is monitored on a routine basis. Few fission product
radionuclides become incorporated into the milk as a result of the selective
metabolism of the cow. However, those that are incorporated are very
important from a radiological health standpoint and are a very sensitive
measure of their concentrations in the environment. The six most common
fission product radionuclides which can occur in milk are tritium,
strontium-89, strontium-90, iodine-131, cesium-137 and barium-140. A seventh
radionuclide, potassium-40, also occurs in milk at a reasonably constant
concentration of about 1.2 x 10~6 yCi/ml. Since this is a naturally
occurring radionuclide, it has not been included in the analytical results
summarized in this section.
33
-------
The ililk surveillance networks operated by the EMSL-LV were the routine
Milk Surveillance Network (MSN) and the Standby Milk Surveillance Network
(SMSN). The MSN, during 1978 (Figure 16), consisted of 23 different locations
where 3.8-liter milk samples were collected to represent family cows,
commercial pasteurized milk producers, Grade A raw milk intended for
pasteurization, and Grade A raw milk for local consumption. In the event of a
release of activity from the NTS, intensive sampling would have been conducted
in the affected area within a 480-km radius of CP-1, NTS, to assess the
radionuclide concentrations in milk, the radiation doses that could result
from the ingestion of the milk, and the need for protective action. Samples
are collected from milk suppliers and producers beyond 480 km within the SMSN.
During 1978, 75 milk samples were collected from the MSN on a quarterly
collection schedule. As samples of milk could not be collected at the
Manzanie Ranch, another sampling location is being sought. Samples could not
be collected at all of the other locations due to the unavailability of milk
or cows.
Each MSN milk sample was analyzed for gamma-emitters, strontium-89, and
strontium-90. Samples collected at six locations from the MSN were also
analyzed for tritium. Table A-2 lists the general analytical procedures and
detection limits for these analyses.
The SMSN consisted of about 150 Grade A milk processing plants in all
States west of the Mississippi River. Managers of these facilities could be
requested by telephone to collect raw milk samples representing milk sheds
supplying milk to the plants. Since there were no releases of radioactivity
from the NTS or other test locations, this network was not activated except to
request one sample from most of the locations to check the readiness and
reliability of the network. During the months of May and June, 120 milk
samples were collected and analyzed by gamma spectrometry. Samples selected
from each of the Western States were also analyzed for tritium, strontium-89,
and strontium-90.
The analytical results of milk samples collected from the MSN during 1978
are summarized in Table A-6, where the maximum, minimum, and average
concentrations of the tritium, strontium-89, strontium-90, iodine-131, and
cesium-137 in samples collected during the year are shown for each sampling
location. As shown in Table 7, the average radionuclide concentrations for
the whole Network are comparable to those for the SMSN, if not slightly lower.
As mentioned in the Quality Assurance Section, the strontium-90 analyses for
both networks were found to be biased low by 25 percent.
LONG-TERM HYDROLOGICAL MONITORING PROGRAM
During this reporting period, EMSL-LV personnel continued the collection
and analysis of water samples from wells, springs, and spring-fed surface
water sources which are down the hydrologic gradient of the ground water at
the NTS and at off-NTS sites of underground nuclear detonations to monitor for
any migration of test-related radionuclides through the movement of ground
water. The water samples were collected from wellheads or spring discharge
34
-------
KIRKEBYRN
SHOSHONE
-( r
BLUE EAGLERN I"
TTR
LIDA LIVESTOCK C
KEOUGH HOT SPGS
YRIBARREN RN
NEVADA | NELLIS
TEST i AIR FORCE
SITE ! RANGE
SPRINGOALE
'sifDENTOPF
\xv
LATHROP WELLS
KIRKER RN
.MOAPA
AGMAN
SEVENTY FIVE
MESQUITE
HUGHES BROS DAIRY
LOGANDALE
VEGAS'VALLEY DAIRY
OXBORROW RN
IBURSON RN
TRONA
STANFORD RN.
BILL NELSON DAIRY
HINKLEY*
I MILK SAMPLING LOCATIONS
SCALE IN MILES
D SO 100
NOTE: WHEN SAMPLING LOCATION OCCURRED IN CITY OR TOWN:
THE SAMPLING LOCATION SYMBOL WAS USED FOR SHOWING
BOTH TOWN AND SAMPLING LOCATION.
0 SO 100 ISO
2/77 SCALE IN KILOMETERS
Figure 16. Milk Surveillance Network.
35
-------
TABLE 7. SUMMARY OF RADIONUCLIDE CONCENTRATIONS FOR MILK SURVEILLANCE
NETWORK AND STANDBY SURVEILLANCE NETWORK
No. of
Network Radionuclide Samples
Concentrations (10~9 uCi'/ml)
CM in C/\Vg
MSN
SMSN
3H
89Sr
/"Sr
137Cs
3H
89Sr
9°Sr
137Cs
24
75
75
75
21
21
21
108
1400
< 6
4.0
16
700
4.3
5.9
20
<400
< 3
< 1
2.9
<400
< 2
< 2
< 3
<400
< 3
1.2
< 3
390
1.6
2.6
4.9
points wherever possible. Prior to each sampling at a wellhead, water was
pumped from the aquifer to assure the collection of representative samples. If
pumps were not available, an electrical-mechanical water sampler capable of
collecting 3-liter samples at depths to 1800 m was used.
Nevada Test Site
For the NTS, attempts were made to sample 10 locations monthly and 20
locations semi-annually (Figures 17 and 18). Additionally, samples were
collected annually from 12 locations. Not all stations could be sampled with
the desired frequency because of inclement weather conditions or inoperative
pumps.
For each sampled location, samples of raw water, filtered water, and
filtered and acidified water were collected. The raw water samples were
analyzed for tritium. Portions of the filtered and acidified samples were
given radiochemical analyses by the criteria summarized in Table A-7. Table
A-2 summarizes the analytical techniques used. Each filter was also analyzed
by gamma spectrometry.
The analytical results for all samples collected and analyzed during this
reporting period are shown in Appendix A and were compared with the CG's in
Appendix B. The analyses for strontium-89, strontium-90, radium-226,
uranium-234, uranium-235, uranium-238, plutonium-238, and plutonium-239,
which were normally done at least once during the year on a sample from each
location, were not made unless the levels of gross alpha and gross beta
radioactivity in any sample showed an unexpected increase (See Table A-7).
No increases were observed in the gross alpha and gross beta radioactivity
during the year; therefore, no additional analyses were required. The ranges
in radioactivity were <2 x 10'9 yCi/ml to 1.6 x lO'8 yCi/ml and <4 x 10"9
36
-------
A MONTHLY
SEMI-ANNUAL
.- <%'v /, j jUweinjE15dj
\! ''~*iif~\^ ipy^ I
/t **A A K /Sedan ',
Nuclear Rocket Development
Station
Las Vegas
(105 km from Mercury
Figure 17. On-Site Long-Term Hydrological Monitoring Program,
Nevada Test Site.
37
-------
; TTR WELL #6
MERCURY
FAIRBANKS SPGS
INDIAN SPGS AFB
SEWER CO WELL* 1
WELLI7S/50E-14CA6"
\ I CRYSTAL POOL
WELL18S/51E-7db«^.SHMEADOWS
SCALE IN KILOMETERS
0 10 20 30 40
SCALE IN MILES
Figure 18. Off-Site Long-Term Hydrological Monitoring Program,
Nevada Test Site.
38
-------
yCi/ml to 4.6 x 10"8 yCi/ml, respectively. (See Appendix Tables A-7, A-10
and Appendix B).
As shown in previous years, the tritium detected in NTS Wells C and C-l is
attributed to tracer experiments conducted prior to the commencement of this
surveillance program. All tritium concentrations were below 0.01 percent of
the Concentration Guide for an occupational ly exposed person. (See Appendix
Tables A-8 and A-9).
The concentrations of tritium in the water samples collected from Well
U3CN-5 (ranged from <9 x 10'9 yCi/ml to 2.8 x 10~7 yCi/ml), Well B (ranged
from 1.7 x 10~7 yCi/ml to 2.5 x 10'7 yCi/ml), Sharp Ranch (1.8 x 10'7
yCi/ml) and Adaven Spring (1.2 x 10~7 yCi/ml) were greater than the
concentration range of all the other sampled wells on and around the NTS (<9 x
10~9 yCi/ml to 4.7 x 10~8 yCi/ml). As the higher tritium concentrations
were comparable to the range in concentrations observed in surface water,
which can be a possible contaminant of ground water, no further investigation
was warranted. The concentration of tritium in a major surface water in
Southern Nevada, the Colorado River, as reported by the EPA Office of
Radiation Programs, ranged from 5 x 10~7 yCi/ml to 7 x 10~7 yCi/ml.
Other Test Sites
The annual collection and radiological analysis of water samples were
continued for this program at all off-NTS sites of underground nuclear
detonations. The project sites at which samples were collected are Project
Gnome near Carlsbad, New Mexico; Project Faultless in Central Nevada; Project
Shoal near Fallen, Nevada; Project Gasbuggy in Rio Arriba County, New Mexico;
Project Rulison near Rifle, Colorado; Project Dribble at Tatum Dome,
Mississippi; Project Rio Blanco near Meeker, Colorado; and Projects Long
Shot/Mil row/Cannikin on Amchitka Island, Alaska. Figures 17 through 31
identify the sampling locations, and Table A-l lists additional information on
the location of each site and tests performed at these locations. The
sampling locations at these project sites remained the same except for the
Project Mil row site and the background locations on Amchitka Island, Alaska.
At the Project Mil row site, Wells W-4, W-7, W-13, and W-18 were added to the
sampling schedule. For the background locations, the sampling location Army
Well No. 1 was added and Mile 27 Stream and the Base Camp Maintenance Building
were omitted.
All samples were analyzed in accordance with the same criteria (Table A-7)
as for samples collected on and around the NTS. The results of all analyses
are listed or summarized in Table A-ll and compared to the appropriate CG's
(Appendix B). As the special analyses (strontium-89 and -90, radon-226,
uranium-234,- 235 and -238, plutonium-238 and -239) on samples from Project
Rio Blanco were not completed in time for last year's report, the results for
these analyses are listed in Table A-12. The only radioactivity detected by
these analyses was the naturally occurring isotopes of uranium and
strontium-90 (1.7 x 10~9 yCi/ml} in the surface water sample collected from
Fawn Creek, 8400 ft Downstream. The strontium-90 was attributed to worldwide
atmospheric fallout.
39
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CARLSBAD CITY WELL #1
I
NEW MEXICO
EDDY COUNTY
LOVING CITY
WELL #2
A ON-SITE WATER SAMPLING LOCATIONS
OFF-SITE WATER SAMPLING LOCATIONS
SCALE IN MILES
O 5 10
SCALE IN KILOMETERS
0 8 16
PHS WELL 9
PHS WELL 10
2/77
PECOS RIVER
PUMPING STATION WELL #1
Figure 19. Long-Term Hydrological Monitoring Program, Project
Gnome/Coach, Carlsbad, New Mexico.
40
-------
CHURCHILL COUNTY
WATER SAMPLING LOCATIONS
Figure 20. Long-Term Hydrological Monitoring Program, Project
Shoal, Fall on, Nevada.
41
-------
LOWER LITTLE CREEK ft
W DANIELS JR
R READY
BAXTERVILLE
WELL ASCOT 2
NORTH LUMBERTO
LUMBERTON
WATER SAMPLING LOCATIONS
SCALE IN KILOMETERS
5 1O 15 2O 25 3O 35 4O
SCALE IN MILES
2/77
LAMAR
CO
SGZ©
TATUM DOME L ^ LAMAR
"~~ \^__C
LOCATION MAPS
Figure 21. Long-Term Hydrological Monitoring Program, Project
Dribble/Miracle Play, Vicinity of Tatum Salt Dome,
Mississippi.
42
-------
WELL HT-1
HALF MOON CREEK
.,.
LOCATION MAPS
WATER SAMPLING LOCATIONS
SCALE IN FEET
SCALE IN METERS
0 100 200 300 400 500 400
Z/77
Figure 22. Long-Term Hydrological Monitoring Program, Project
Dribble/Miracle Play, Tatum Salt Dome, Mississippi.
43
-------
\
Half Moon Creek '
Overflow /
HMH-9
J
\
\
I
7/79
Location Maps
Scale in feet
Scale in meters (_
Water Sampling Locations
O 1OO 2OO
50
100
J
Figure 23. Long-Tenn Hydrological Monitoring Program, Project
Dribble/Miracle Play, Tatum Dome, Mississippi.
44
-------
TO DULCE-
RIO ARRIBA COUNTY
LOCATION MAPS
BUBBLING SPG.
EPNG WELL 1O-36
WINDMILL «2
TO BLANCO
SGZ
CAVE SPG.
ARNOLD RN
LOWER BURRO
CANYON
APACHE RESERVATION
WELL SOUTH
I WATER SAMPLING LOCATIONS
SCALE IN KILOMETERS
0
SCALE IN MILES
0 5
2/77
Figure 24. Long-Term Hydro!ogical Monitoring Program, Rio Arriba
County, New Mexico, Project Gasbuggy.
45
-------
GRAND VALLEY
CITY^ WATER
GRAND
VALLEY y--r~*"lT
A GARDNER RN
SEFCOVIC RN
L. HAYWARD RN
"l
I
mlBATTLEMENT CREEK
'CER TEST WELL
SPRING
SGZ
WATER SAMPLING LOCATIONS
SCALE IN KILOMETERS
8
SCALE IN MILES
0 i
2/77
VE6A RES
QARFIELD COUNTY
X SGZ
Figure 25. Long-Term Hydrological Monitoring Program, Project
Rulison, Rulison, Colorado.
46
-------
NEVADA
RENO
^TONOPAH
0SGZ
CENTRAL NEVADA
AREA
LAS VEGAS
SGZ/
HTH 2
' HTH 1
I
I
I
\
WATER CAMPLING LOCATIONS /
/
SCALE IN KILOMETERS
O1 2345678
SCALE IN MILES
O 1 2 3 4 5
2/77
SIX-MILE WELL
JIM BIAS WELL
BLUE JAY
MAINT STA
Figure 26. Long-Term Hydrological Monitoring Program, Faultless
Event, Central Nevada Test Area.
47
-------
FAWN CR No. 1
Emplacement
Well
FAWN CR No. 3
O ARTESIAN WELL
WINDMILL
O WATER WELL (SAMPLED)
SPRING (FLUMED & SAMPLED)
STREAM
RIO BLANCO COUNTY
GARFIELD COUNTY"
SCALE IN KILOMETERS
Figure 27. Long-Term Hydrological Monitoring Program, Project
Rio Blanco, Rio Blanco County, Colorado.
48
-------
Sampling Locations
Figure 28. Long-Term Hydrological Monitoring Program^ Project
Cannikin, Amchitka Island, Alaska.
49
-------
179°10'46"
179° 11 "30"
en
o
5.698.500 -
5.698.000
- 51°25'00"
652,000
652,500
51°25'22"
Figure 29. Long-Tenn Hydrological Monitoring Program, Project Milrow, Amchitka Island, Alaska.
-------
179°10'57"
51°26'17"
5.701,000
7/79
\
Sampling Location
0 150 300 Feet
Q 25 50 75100 Meters
51°26'13'
652,000
5,700,500
651,500
Figure 30. Long-Term Hydrological Monitoring Program, Project Long Shot,
Amchitka Island, Alaska.
-------
BERING SEA
PACIFIC OCEAN
Sampling Locations
0 12345 Miles
1O Kilometers
1/79
PACIFIC OCEAN
Figure 31. Long-Term Hydro!ogical Monitoring Program, Background
Sampling, Amchitka Island, Alaska.
52
-------
As reported in previous annual reports, concentrations of radioactivity
above background levels were observed in samples collected from USGS Wells 4
and 8 near Malaga, New Mexico (Table A-ll, Project Gnome). These wells, which
are fenced, posted, and locked to prevent their use by unauthorized personnel,
were contaminated by the injection of higher concentrations of tritium,
strontium-90 and cesium-137 (USGS Well 8 only) for a tracer study.
All of the other sampled wells showed no unexplained increase in gross
alpha or gross beta radioactivity. The water sample collected at Flowing Well
near Frenchman, Nevada, (Table A-ll, Project Shoal) had a higher than normal
beta concentration of 1.6 x 10'7 yCi/ml; however, the gamma spectrometry
analysis on this sample identified naturally occurring potassium-40 and '
radon-222 daughter products as the sources of radioactivity. Except for the
anomalous low gross beta concentration i.n 1976 (<5 x 10~9 yCi/ml), the gross
beta concentration in the annual samples collected from this location since
1972 have ranged from 3.8 x 10'8 yCi/ml to 9.4 x 10~8 yCi/ml. With the
exclusion of the Flowing Well sample, the gross alpha and gross beta
concentration ranges for all the off-NTS sites were, respectively, <2 x 10"9
yCi/ml to <4.0 x 10-8 yCi/ml and <6 x 1CT9 yCi/ml to 4.5 x 1CT8 pCi/ml.
The concentrations of tritium in samples collected at all locations were
similar to those observed in samples collected in the past. The concentration
of tritium (2.7 x 10~6 yCi/ml) in the surface water sample collected from
the Half Moon Creek Overflow at the Project Dribble site, Tatum Dome,
Mississippi, was again higher than background levels observed in Off-site
surface water samples (6.2 x 10~8 yCi/ml to 7.6 x 10~8 yCi/ml).
Exploratory surveys in April 1977 found the tritium to be coming from
subsurface soil contaminated with tritium which was suspected to be the
residual from post-shot drilling operations following two underground nuclear
detonations, Salmon in 1964 and Sterling in 1966.
To determine the extent to which the subsurface soil was contaminated,
soil and water samples were collected from four-inch-diameter holes augered to
the water table on 25-, 50-, and 100-foot grids around surface ground zero.
Each sample was analyzed on-site for conductivity, pH, and tritium. The
results of this investigation, conducted during the September 12 to 19, 1977,
and April 18 to 27, 1978, were reported in detail (DOE, 1978). As cited in
this report (DOE, 1978), the area contaminated by tritium at the water table
measures about 1,225 ft north to south and 960 ft east to west. The surface
ground zero is located slightly east of the center of the contaminated area.
Within the contaminated area, there are five areas (totalling 2 acres) that
had tritium concentrations in soil moisture or ground water that were equal to
or exceeded 2.0 x 10~5 yCi/ml.
The highest concentration of tritium observed, 10~3 yCi/ml, was obtained
from soil moisture recovered from a soil sample collected in Hole 67, at a
depth of 10 ft. This hole was located approximately 25 ft southeast of Well
PS-1 (Figure 23), which was sealed during post-shot drilling operations.
Although this water is not used as drinking water, this concentration is 30
percent of the CG for an individual in a controlled or uncontrolled area and
50 times the maximum contaminant level at the EPA Drinking Water Regulations
(Appendix B).
53
-------
To determine the distribution of tritium with depth to the water table, a
well (PS-3) was drilled and sampled to 142 ft; however, the water table was
never reached (DOE, 1978). As the soil moisture samples collected from the
upper 43 ft of the formation overlying Tatum Dome in this well contained all
of the tritium contamination (2.5 x 10~5 yCi/ml to 9.7 x Id'4 yCi/ml),
except for a few low level samples (5.0 x 10"7 yCi/ml to 9.0 x 10~6
yCi/ml) collected at depths between 93 ft and 142 ft, the source of the
tritium is believed to be from drilling operations and is not suspected to be
caused by upward leakage of radioactivity from the event cavity at a depth of
2700 ft (DOE 1978).
For the purpose of monitoring the tritium concentrations in the on-site
subsurface soil moisture, 11 holes 4 inches in diameter were augered by EPA
personnel at the locations shown in Figure 23, lined with 4-inch-diameter
plastic casing, and capped above the ground surface. Beginning in April 1978,
water samples from these locations will be collected and analyzed for tritium
quarterly for 1 year. If no significant increase in radioactivity
concentration is observed in samples collected at any of the locations, the
locations will be sampled annually. The analytical results for the samples
collected from the HMH locations and Well PS-3 are listed in Appendix A-13.
As shown by the table, the highest tritium, concentration was 4.5 x 10"^
yCi/ml in the sample collected from HMH-1. All of the tritium contamination
was confined to the subsurface. None was detected in any surface water or
offsite well other than the on-site Half-Moon Creek Overflow. No off-site
residents are suspected of being exposed to the waterborne tritium. As
mentioned earlier, the nearest populated area is a single residence which is
about 1 mile south-southwest of surface ground zero. To make certain that the
subsurface tritium contamination had not entered an aquifer which is used by
off-site residents, arrangements are being made between representatives of the
Department of Energy, Nevada Operations Office, the State of Mississippi and
the EPA to extend Well PS-3 to the local aquifer and to implement further
changes to the environmental surveillance program for the Project Dribble
site.
The concentration of tritium in several water samples collected from
shallow wells and surface waters at the Project Long Shot site on Amchitka
Island, Alaska, were also above background levels. These samples, which had
tritium concentrations ranging from 2.8 x 10 yCi/ml to 7.3 x 10~6
yCi/ml, were collected from every location at the project site except for Reed
Pond (Table A-ll). The observed concentrations are comparable to those
reported earlier by the U.S. Geological Survey (Ballance, 1974; Thordarson and
Ballance, 1976) and the University of Washington (Nelson and Seymour, 1977).
The highest tritium concentration was found to be only 0.24 percent of the CG.
The water in this area is not used for drinking purposes, therefore the
contamination was found to pose no radiological hazard.
WHOLE-BODY COUNTING
Eighteen families consisting of 59 residents from 12 locations near the
NTS were examined twice during the year to determine individual body burdens
of radioactivity for each individual and to monitor for any physical changes
54
-------
attributable to the effects of acute or chronic exposure to radiation or
radioactivity. When possible, all members of a family were included in the
examinations. The home locations of these individuals were Pahrump, Lund,
Beatty, Pioche, Nyala, Round Mountain, Ely, Tempiute, Goldfield, Lathrop
Wells, Tonopah, and Spring Meadow Farms, Nevada.
Each examination consisted of a measurement of the body burden of
radioactivity using the whole-body counting facility described previously
(NERC-LV, 1974), a complete hematological examination, and a thyroid profile.
A urine sample was also collected from each individual for tritium analysis,
and a composite of urine samples from each family was analyzed for
plutonium-238 and plutonium-239.
From the results of the whole-body counting, the fission product
cesium-137 was detected above the detection limit in 86 out of 97
measurements. The maximum, minimum, and average body burdens for this
radionuclide were 3.4 x 10"8, <5 x 10'9, and 1.3 x 10~8 yCi/g body
weight, respectively, which were similar to last year's concentrations
(maximum of 3.9 x 10~8 yCi/g; minimum of <5 x 10"^; and average of 1.4 x
10~8 yCi/g body weight).
In regard to the hematological examinations and thyroid profiles, no
abnormal results were observed which could be attributed to past or present
NTS testing operations.
The concentrations of plutonium-238 and plutonium-239 in all composite
urine samples were below the minimum detectable concentration of 2 x 10~10
yCi/ml, which was higher than the MDC reported in Table A-2. (4 to 8 x 10"]1
yCi/1) due to the fact that the composite urine sample from each family was
often less than the desired one liter.
As the concentration of plutonium-238 and plutonium-239 in the urine of
individuals exposed only to worldwide atmospheric fallout would not result in
a concentration in urine above the MDC, the five composite urine samples
reported last year to contain plutonium-238 or plutonium-239 above the MDC
were re-evaluated. From the evaluation, all four of the composites having
plutonium-238 were calculated to have a concentration less than the MDC. The
composites were calculated in accordance with the new definition, which
allows for both Type I and Type II decision errors at the 95% confidence
level. The plutonium-239 concentration reported in the fifth composite (2.9
x 10~n ± 1.8 x 10~n yCi/ml) was found to be above the newly defined
MDC; however, this is believed to be a statistical anomally, because no
plutonium was detected in the 1978 composite of urine samples collected from
members of this same family.
55
-------
DOSE ASSESSMENT
The only radioactivity which was detected off-NTS and ascribed to test
operations was xenon-133 detected in an air sample collected at Diablo,
Nevada, during the period April 19-26 and tritiated hydrogen (HT) in air
samples collected at Indian Springs, Nevada, during the periods November 13 to
20 and November 27 to December 4.
The estimated dose equivalent to the whole body of a hypothetical receptor
at Diablo from the exposure to the airborne xenon-133 would be
(6.5 x 10-n uCi/ml) (7 days) (500 mrem/year)
= 6.2
(10-7 yCi/ml) (365 days/year) (1 mrem/1000 yrem)
Based upon an estimated population of six people, the dose commitment at
Diablo was estimated to be 0.000037 person-rem.
At Indian Springs, the concentrations of HT in air minus an ambient HT
concentration of 7.6 x 10"13 yCi/ml, estimated from all other off-NTS,
resulted in a calculated dose equivalent of
[2.4 x icr11 yCi/ml] + [1.8 x 10'11 pCi/ml] - [(2)(7.6 x 10"13 yCi/ml)(7 d)(500 mrem/y)]
-- : -- = 5_
[(6.7 x lO"8 uCi/ml)(365 d)(l mrem/1000 prem)]
Based upon a population of 1500 at Indian Springs, the estimated dose
commitment for the area would be 0.0087 person-rem.
As Diablo is beyond 80 km of the center of the NTS, the 80 km dose
commitment would be 0.0087 person-rem. Due to the greater population density
within the Las Vegas area, the highest dose commitment (0.36 person-rem) was
for this area, which is approximately 100 km from the NTS. This dose
commitment is small compared to the 26,000 person-rem, which residents of Las
Vegas and nearby communities received from natural background radiation during
this report period.
urem
56
-------
TABLE 8. ESTIMATED DOSE COMMITMENT FROM
XENON-133 CONCENTRATIONS
Location
Beatty, Nev.
Diablo, Nev.
Hiko, Nev.
Las Vegas, Nev
Tonopah, Nev.
Total
Population
500
6
60
. 370,500*
2,000
Estimated
Dose
Equivalent
(wrem)
2.5
1.2
1.1
0.96
1.4
Dose
Commitment
(person-rem)
0.0013
0.0000072
0.000066
0.36
0.0028
0.36
Dose
Commitment
With in 80km
(person-rem)
0.0013
0.0
0.0
0.0
0.0
0.0013
^Population is for Las Vegas and nearby communities within Clark County.
57
-------
REFERENCES
Andrews, V. E., and J. C. Vandervort. "Fruit and Vegetable Radioactivity
Survey, Nevada Test Site Environs." EMSL-LV-0539-13. U.S. Environmental
Protection Agency, Las Vegas, Nevada. April 1978.
Ballance, W. C. "Radiochemical Monitoring of Water After the Cannikin Event,
Amchitka Island, Alaska, August 1973." USGS-474-205. Available from Dept. of
Commerce, NTIS, Springfield, VA. October 1974.
DOE. "Special Study Tatum Dome Test Site, Lamar County, Mississippi, Final
Report," NVO-200. U.S. Department of Energy, Nevada Operations Office.
October 1978.
Eckel, E. B., ed. Nevada Test Site. Memoir 110. The Geological Society of
America, Inc. Boulder, Colorado.1968.
EMSL-LV. "Environmental Monitoring Report for the Nevada Test Site and Other
Test Areas Used for Underground Nuclear Detonations." EMSL-LV-0539-12. U.S.
Environmental Protection Agency, Las Vegas, Nevada. May 1977.
EPA. "Environmental Radioactivity Laboratory Intercomparison Studies Program
1978-1979", Environmental Monitoring and Support Laboratory, Environmental
Protection Agency, Las Vegas, Nevada. Available from U.S. Dept. of Commerce,
NTIS, Springfield, VA 22161. 1979.
ERDA Manual, Chapter 0513. "Effluent and Environmental Monitoring
and Reporting." U.S. Energy Research and Development Administration.
Washington, D.C. March 20, 1974.
ERDA. "Final Environmental Impact Statement, Nye County Nevada." ERDA-1551.
Nevada Operations Office, U.S. Energy Research and Development Administration,
Las Vegas, Nevada. Available from U.S. Dept of Commerce, NTIS, Springfield,
VA, 22161. September 1977.
Houghton, J. G., C. M. Sakamoto, and R. 0. Gifford. Nevada's Weather and
Climate. Special Publication 2. Nevada Bureau of Mines and Geology, Mackay
School of Mines, University of Nevada-Reno, Reno, Nevada, pp 69-74. 1975.
Nelson, V. A., and A. H. Seymour. "Amchitka Radiological Program Progress
Report January 1976 to December 1976." NVO-269-31. University of Washington,
Seattle, Washington. Available through U.S. Dept. Of Commerce, NTIS,
Springfield, VA, 22161. May 1977.
NERC-LV. "Environmental Monitoring Report for the Nevada Test Site and Other
Test Areas Used for Underground Nuclear Detonations." NERC-LV-539-31. U.S.
Environmental Protection Agency, Las Vegas, Nevada. May 1974.
58
-------
Office of Radiation Programs. "Environmental Radiation Data". Reports 13,
14, and 15. Environmental Protection Agency, Eastern Environmental Radiation
Facility. Montgomery, Alabama. July 1978. October 1978. January 1979.
Population Research Unit. Population estimates for Death Valley, Barstow,
Bishop, and Ridgecrest, California, according to telephone conversation
between R. F. Grossman, U.S. Environmental Protection Agency, and Nelson
Rasmussen, California Department of Finance, Sacramento, California. April
27, 1979.
Quiring, Ralph E. "Climatological Data, Nevada Test Site, Nuclear Rocket
Development Station (NRDS)." ERLTM-ARL-7. ESSA Research Laboratories.
August 1968
University of Nevada (Reno). Population projections for Washoe and Clark
Counties and the State of Nevada for 1978, personal communication with Dr.
Chu, Bureau of Business and Economic Research. April 26, 1979.
U.S. Bureau of the Census. "Estimates of the Population of California
Counties and Metropolitan Areas, July 1, 1976 and 1977." Federal-State
Cooperative Program for Population Estimates. Series P-26. No. 77-5. U.S.
Department of Commerce. Washington, D.C. March 1979.
U.S. Bureau of the Census. "Estimates of the Population of Nevada Counties
and Metropolitan Areas, July 1, 1976, and July 1, 1977." Federal-State
Cooperative Program for Population Estimates. Series P-26. No. 77-28. U.S.
Department of Commerce. Washington, D.C, December 1978.
U.S. Bureau of the Census. "Estimates of the Population of Arizona Counties
and Metropolitan Areas, July 1, 1976, and July 1, 1977." Federal-State
Cooperative Program for Population Estimates. Series P-25. No. 730. U.S.
Department of Commerce. Washington, D.C. September 1978.
U.S. Bureau of the Census. "Estimates of the Population of Utah Counties and
Metropolitan Areas, July 1, 1976, and July 1, 1977." Federal-State
Cooperative Program for Population Estimates. Series P-26. No. 77-44. U.S.
Department of Commerce. Washington, D.C. December 1978.
U.S. Bureau of the Census. "Current Population Reports. Population Estimates
and Projectsions" for cities within the States of Arizona, California, Nevada,
and Utah. P-25 Series, No. 742, 744, 767, and 783. U.S. Department of
Commerce. Washington, D.C. January 1979.
Thordarson, W., and W. C. Ballance. "Radiochemical Monitoring of Water After
the Cannikin Event, Amchitka Island, Alaska, May 1974." USGS-474-225 and
USGS-474-226. Geological Survey. Available from U.S. Department of Commerce,
DTIS, Springfled, VA, 22161. March 1976.
Utah Department of Agriculture. "Utah Agricultural Statistics, 1978." 147
North 200 West, Salt Lake City, Utah.
59
-------
APPENDIX A. TABLES
60
-------
TABLE A-l. UNDERGROUND TESTING CONDUCTED OFF THE NEVADA TEST SITE
Name of Test,
Operation or
Project
Project/Gnome
Coach1
Project Shoal2
Project Dribble2
(Salmon Event)
Operation Long
Shot2
Project Dribble2
(Sterling Event)
Project Gasbuggy1
Faultless Event3
Project Miracle
Play (Diode Tube)3
Project Rulison1
Operation Mil row3
Project Miracle1
Play (Humid
Water)2
Operation
Cannikin3
Project Rio
Blanco1
Date
12/10/61
10/26/63
10/22/64
10/29/65
12/03/66
12/10/67
01/19/68
02/02/69
09/10/69
10/02/69
04/19/70
11/06/71
05/17/73
Location
48 km (30 mi) SE of
Carlsbad, N. Mex.
45 km (28 mi) SE of
Fallon, Nev.
34 km (21 mi) SW of
Hattiesburg, Miss.
Amchitka Island,
Alaska
34 km (21 mi) SW of
Hattiesburg, Miss.
88 km (55 mi) E of
Farmington, N. Mex.
Central Nevada Test
Area 96 km (60 mi) E
of Tonopah, Nev.
34 km (21 mi) SW of
Hattiesburg, Miss.
19 km (12) SW of
Rifle, Colo.
Amchitka Island,
AUska
34 km (21 mi) SW of
Hattiesburg, M1ss.
Amchitka Island,
Alaska
48 km (30 mi) SW of
Meeker, Colo.
Yield*
(kt)
3.l6
12
5.3
80
0.38
29
200-
1000
Non-
nuclear
explosion
40
1000
Non-
nuclear
explosion
<5000
3x30
Depth
m
(ft)
360
(1184)
366
(1200)
823
(2700)
716
(2350)
823
(2700)
1292
(4240)
914
(3000)
823
(2700)
2568
(8425)
1219
(4000)
823
(2700)
1829
(6000)
1780
to
2040
(5840
to
6690)
Purpose of
the event4-5
Multi-purpose
experiment.
Nuclear Test
detection re-
search experi-
ment.
Nuclear test
detection re-
search experi-
ment.
000 nuclear
test detection
experiment.
Nuclear test
detection re-
search experi-
ment.
Joint Government-
Industry gas
stimulation ex-
periment.
Calibration
test.
Detonated 1n
Salmon/Sterling
cavity. Seismic
studies.
Gas Stimulation
experiment.
Calibration test.
Detonated in
Salmon/Sterling
cavity. Seismic
studies.
Test of war-
head for
Spartan
missile.
Gas stimula-
tion experi-
ment.
'Plowshare Events
2Vela Uniform Events
^Weapons Tests
4Information from "Revised Nuclear Test Statistics," dated September 20, 1974, and "Announced
United States Nuclear Test Statistics," dated June 30, 1976, distributed by David 6. Jackson,
Director, Office of Public Affairs, Energy Research Administration, Nevada Operations Office,
Las Vegas. Nevada.
5News release Al-62-50, ABC Albuquerque Operations Office, Albuquerque, New Mexico.
December 1, 1961.
6"The Effects of Nuclear Weapons," Rev. Ed. 1964.
61
-------
TABLE A-2. SUMMARY OF ANALYTICAL PROCEDURES
Type of
Analysis*
Nal(Tl)
Spectrometry
Ge(Li) gamma
Spectrometry
89-90Sr
3H
3H Enrichment
(Long-Term
Hydrological
Samples)
238,239Pu
234.235.238u
Analytical
Equipment
Gamma spectro-
meter with
10-cm-thick
by 10-cm-di-
ameter Nal
detector cali-
brated at 10
keV per
channel (0-2
MeV range).
Gamma spectro-
meter with Ge(Li)
detector cali-
brated at 1/2
keV/channel
(0-2 MeV range)
individual i so-
top ic efficiencies
ranging from
~15% - 22%.
Low-background
thin-window,
gas- flow pro-
portional
counter with a
5.7-cm diameter
window (80 yg/
cm2).
Automatic
liquid
scintillation
counter with
output printer.
Automatic
scintillation
counter with
output printer.
Alpha spectro-
meter with 450
Counting
Period
(Min)
100 min for
milk, water,
Long-Term
Hydro, sus-
pended sol-
ids; 10 min.
for air
charcoal
cartridges
and air
filters.
Individual
air filters
30 min
air filter
composites.
~1200 min.
50
200
;
TOO
1000-1400
Analytical
Procedures
Radionucllde
concentra-
tions quan-
tified from
gamma spec-
tral data by
computer
using a least
squares
technique.
Radionuclide
concentration
quantified
from gamma
spectral data
by on-line
computer pro-
gram. Radlo-
nuclides in air
filter composite
samples are
identified only.
Chemical
separation by
ion exchange.
Separated sam-
ple counted
successively;
activity cal-
culated .by
simultaneous
equations.
Sample pre-
pared by
distillation.
Sample concen-
trated by
electrolysis
followed by
distillation.
Sample Is
digested with
Sample
Size
(Liter)
3.5 for
routine milk
and water
samples;
800-1200 m3
for air fil-
ter samples;
7.3 for Long-
Term Hydro.
Water sus-
pended solids.
Composite air
filters
-15000 m3
Same as
above.
1.0
0.005
0.25
1.0
Approximate
Detection
Limit**
For routine milk
and water gen-
erally, IxlO"8
yCl/ml for most
common fallout
radlonuclides in
a simple spec-
trum. For air
filters,
4xlO-l4pCi/ml.
For Long-Term
Hydro, sus-
pended solids,
6.0xlO-9wd/ml.
Same as
above
89|r = 5x10-9
uCi/ml
90sr - 2x10-9
pC1/ml.
4xlO-7 yd /ml
1x10-8 wCI/ml
238Pu > 8x10-11
uCi/ml
*iOrt ooji
mnr, 300-um
depletion depth,
silicon surface
barrier detectors
operated in
vacuum chambers.
add, separated
by Ion exchange,
electroplated
on stainless
steel planchet
and counted by
alpha spectro-
meter.
4x10-11 iid/ml
(continued)
62
-------
TABLE A-2. (Continued)
Type of
Analysis*
226Ra
Gross alpha
Gross beta
in liquid
samples
Gross beta
on air
filters
Counting
Analytical Period
Equipment (Min)
Single channel 30
analyzer
coupled to
P.M. tube
detector.
Low-background 50
thin-window,
gas-flow pro-
portional
counter with a
5. 7 -cm-diameter
window (80 ug/
Low- level end 20
window, gas
flow propor-
tional counter
with a 12.7-
cm-di ameter
window (100
mg/cm2).
Sampl e
Analytical Size
Procedures (Liter)
Precipitated 1.5
with Ba, con-
verted to
chloride.
Stored for
30 days for
222Rn 226Ra to
equilibrate.
Radon gas
pumped into
scintillation
cell for alpha
scintillation
counting.
Sample eva- 0.2
porated;
residue
weighed and
counted;
corrected for
sel f-attenu-
ation.
Filters 10-cm
counted at 7 diameter
and 14 days glass fiber
after col- filter; sam-
lection; two pie collected
counts can from 500-
be used to 1200m3.
extrapolate
concentration
to mid-col-
lection time
assuming T~I*2
decay or using
experimentally
derived decay.
Approximate
Detection
Limit**
2x1 O"10 uCi/ml
o = 6xlO'9 uC1/ml
6 = 4xlO-9 iiC1/ml
4xl015uCi/ml
85Kr, 133Xe
CH3T
Automatic 200
liquid scintil-
lation counter
with output
printer.
Physical 400-1000
separation by
gas chroma-
tography; dis-
solved in
toluene "cock-
tail" for count-
Ing.
85Kr = 4x10-12
wC1/ml
!33Xe = 4x10-12
uC1/ml
CH3T » 4x10-12
tiCi/ml
*Johns, F. B., P. B. Hahn, D. J. Thome, and E. W. Bretthauer. Radiochemical Analytical Procedures for
Analyses of Environmental Samples, EMSL-LV-0539-17, U.S. Environmental Protection Agency, EMSL-LV, Las
Vegas. 1979.
**The detection limit for all samples received after January 1, 1978 is defined as 3.29 sigma where
sigma equals the counting error of the sample and Type I error Type II error = 5 percent. (Corley,
J. P., D. H. Denham, D. E. Micheles, A. R. Olsen and D. A. Maite, A Guide for Environmental
Radiological Surveillance at EROA Installations," EROA 77-24 pp. 3.19-3.22, March, 1977, Energy
Research and Development Administration, Division of Safety, Standards and Compliance, Washington, D.C.)
63
-------
TABLE A-3. 1978 QUALITY ASSURANCE INTERCOMPARISONS
Analysis
Gross o
in water
Gross &
in water
3H
in water
239pu
in water
90Sr
in water
"Sr
in water
226Ra
in water
3H
in urine
Month
Jan.
Mar.
May
July
Sept.
Jan.
Mar.
May
July
Feb.
Apr.
June
Aug.
Jan.
July
Jan.
May
Sept.
Jan.
May
Sept.
Mar.
June
Mar.
June
Sept.
Mean of
Replicate
Analyses
±/0
(10-9 pCi/ml)
7 ± 0
21 ± 1
13 ± 1
20 ± 1
6 ± 1
31 ± 1
34 ± 1
20 ± 3
25 ± 2
1800 ± 100
2230 ± 149
2300 ± 400
1178 ± 219
1.5 ± 0.1
3.1 ± 0.2
35 ± 1
23 ± 1
12 ± 1
27 ± 1
12 ± 2
14 ± 4
4.8 ± 0.1
3.8 ± 0.4
760 ± 26
3767 ± 153
930 ± 214
Mean Range
+ Standard
Error of
Range
0.0
0.12
0.24
0.20
0.24
0.24
0.24
0.59
0.35
0.35
0.47
1.67
0.76
0.30
0.47
0.74
0.39
0.39
0.24
0.47
0.83
0.15
0.79
0.09
0.43
0.74
Known
Value
(10-9 yCi/ml)
7
20
13
22
5
39
29
18
30
1680
2220
2270
1230
1.7
3.6
31
27
16
25
16
19
5.5
3.7
1050
4150
1120
Normal i
Grand
-0.1
1.4
-0.0
1.0
0.1
-2.1
1.6
-0.1
-2.5
0.3
0.2
0.2
-0.4
0.1
0.4
5.6
-0.6
-3.8
1.0
-2.4
-0.1
0.1
0.5
-1.2
-0.4
-1.3
zed Deviation
from
Avg. Cone.
0.0
0.5
0.0
-0.5
0.3
-2.7
1.8
-0.7
-1.8
0.6
0.0
0.1
-0.3
-2.0
-1.5
4.3
-4.2
-4.2
0.8
-1.4
-1.8
-1.5
0.3
-1.5
-1.6
-1.0
(continued)
64
-------
TABLE A-3. (Continued)
Analysis
137Cs
in water
19il
in milk
l37Cs
in milk
1%0Ba
in milk
90Sr
in milk
89Sr
in milk
K
in milk
Gross B
on air
filters
"7Cs
on air
filters
pCi/filter
Month
Feb.
Apr.
June
Aug.
Oct.
Apr.
July
Apr.
July
Apr.
July
Apr.
July
Apr.
July
Apr.
July
Mar.
June
Mar.
June
Mean of
Replicate
Analyses
±/o
(10-9 yCi/ml)
< 3
< 4
29 ± 3
16 ± 2
123 ± 5
82 ± 3
< 3
24 ± 2
54 ± 1
< 2
< 3
7 ± 1
38 ± 1
78 ± 1
50 ± 5
1529 ± 6
1527 ± 28
38 ± 2
36 ± 3
25 ± 2
17 ± 1
Mean Range
+ Standard Known
Error of Value
Range (10~9 yCi/ml)
-
0.71
0.35
0.89
0.59
0.47
0.12
.
"
0.79
0.24
0.24
1.35
0.09
0.39
0.47
0.59
0.35
0.24
0
0
30
15
125
82
0
23
53
0
0
9
49
101
41
1500
1560
38
36
22
18
Normalized Deviation
from
Grand. Avg.
-
-1.0
-0.0
-1.2
0.0
"
-0.5
-0.0
-1.8
-5.5
-4.8
5.1
-0.3
-0.4
-0.5
-0.9
0.6
-1.2
Cone.
-
-0.5
0.3
-0.7
-0.1
-0.2
0.2
.
-1.9
-7.9
-7.9
3.1
-0.7
-0.7
0.1
0.0
1.0
-0.3
65
-------
TABLE A-4. 1978 SUMMARY OF ANALYTICAL RESULTS FOR THE
NOBLE GAS AND TRITIUM SURVEILLANCE NETWORK
Sampling
Location
No.
Oays
Sampl ed
Radio-
nuclide
Radioactivity Concentrations
Units cMax cM1n
cAvg
* of
Cone.
Guide*
(uC1/ml air)
Death
Valley
Jet. ,
Calif.
Beatty,
Nev.
Diablo,
Nev.
Hiko,
Nev.
Indian
Springs,
Nev.
Las Vegas,
Nev.
342.6
342.6
308.9
342.6
308.9
285.7
343.6
343.6
296.7
343.6
296.7
295.7
344.7
336.7
322.9
344.7
322.9
307.0
357.7
357.7
321.8
357.7
321.8
293.0
344.4
363.6
334.6
356.5
334.6
300.5
329.7
336.6
321.6
336.7
321.6
285.7
85Kr
133xe
3H as HT
3H as CH3T
3H as HTO
3H as HT
85Kr
133Xe
3H as HTO
3H as CH3T
3H as HTO
3H as HT
85Kr
133Xe
3H as HTO
3H as CH3T
3H as HTO
3H as HT
St
3H as HTO
3H as CHjT
3H as HTO
3H as HT
85Kr
1
3H as HTO
3H as CH3T
3H as HTO
3H as HT
85Kr
»&
3H as HTO
3H as CH3T
3H as HTO
3H as HT
10-l2tid/ml air
10-12uCi/ml air
lO-6yC1/ml water
lO-l2iiC1/ml air
10-l2iiCi/nl air
10-l2uCi/ral air
lC-l2ud/ml air
10-12uCi/ml air
10-6uCi/ml water
10-12uci/nl air
10-12uCi/ml air
10-12uCi/ml air
lO-l2wC1/ml air
10-l2uC1/ml air
10-6HC1/ml water
10-12wCi/ml air
10-12uci/ml air
10-12uC1/ml air
10-12nC1/nl air
10-12uC1/ml air
10-6uCi/ml water
lO-l2yC1/nl air
10-l2ud/ml air
10-12ud/ml air
!0-l2uC1/ml air
10-6uCi/ml water
lO-lzyC1/ml air
10-12uC1/ml air
10-12yCi/ml air
10-12HCi/ml air
10-6HC1/ml water
10-12uCi/ml air
10-l2yCi/ml air
10-12uC1/ml air
24 x 10-12
<20
0.93
<20
4.9
4.1
25
< 30
1.9
<20
13
< 3
26
65
1.4
<20
8.6
6.0
26
<20
0.75
<20
< 5
4.0
25
< 5
0.85
20
< 4
24
24
<20
1.1
<30
< 7
7.9
17 x 10-12
< 3
< 0.3
< 2
< 0.6
< 0.3
17
< 3
< 0.3
< 2
< 0.3
< 0.5
17
< 2
< 0.3
< 2
< 1
< 0.6
14
< 3
< 0.3
< 2
< 0.8
< 0.4
16
< 3
< 0.4
< 2
< 0.8
< 0.5
16
< 3
< 0.3
< 2
< 0.7
< 0.6
20
< 3
< 0.3
< 2 I
1.4 }
0.77)
20
< 3
0.29
< 2 )
1.5 >
< 0.5 )
20
3.1
< 0.3
< 2 )
1.5 1
0.97)
20
< 3
< 0.3
< 2 )
0.73>
0.94)
20
< 3
< 0.4
< 2 \
0.83 >
1.8 )
20
< 3
0.29
< 2 )
1.6 }
0.89)
0.02
< 0.01
..
< 0.01
0.02
< 0.01
< 0.01
0.02
< 0.01
..
< 0.01
0.02
< 0.01
< 0.01
0.02
< 0.01
< 0.01
0.02
< 0.01
..
< 0.01
(continued)
66
-------
Table A-4 (Continued)
Sampl i ng
Location
No.
Days
Sampl ed
Radio-
nuclide
Radioactivity Concentrations
Units cMax cM1n cAvg
"» of
Cone.
Guide"
(iid/ml air)
NTS, Nev.
Mercury
NTS, Nev.
Area 51 #
NTS, Nev.
BJY
NTS, Nev.
Area 12
Tonopah,
Nev.
350.5
363.5
323.6
356.5
323.6
303.7
363.5
363.5
356.5
363.5
356.5
349.5
335.6
356.5
329.6
356.5
329.6
322.6
363.6
363.5
329.8
363.6
329.8
322.8
336.6
349.6
329.7
349.6
329.7
315.5
»5J,
3H as HTO
3H as CH3T
3H as HTO
3H as HT
85Kr
133xe
3H as HTO
3H as CHjT
3H as HTO
3H as HT
85Kr
I33xe
3H as HTO
3H as CH3T
3H as HTO
3H as HT
85|(r
133Xe
3H as HTO
3H as DhT
3H as HTO
3H as HT
Sje
3H as HTO
3H as CH3T
3H as HTO
3H as HT
10-12uCi/ml air
10-12uCi/ml air
10-6uCi/ml water
lO-^Ci/ml air
10-12uCi/ml air
lO-l2wC1/ml air
10-12t)C1/ml air
10-«uCi/inl air
iO-6uCi/ml water
10-l2yCi/ml air
10-12HCi/ml air
10-12pC1/ml air
10-12uCi/m] air
10-12gCi/ml air
!0-6uC1/ml water
10-l2pC1/ml air
10-12uCi/ml air
10-12yC1/ml air
10-12uCi/ml air
10-l2uCi/ml air
!0-6uC1/ml water
10-12uCi/ml air
iO-!2uC1/ml air
10-12uCi/ml air
lO-l2wC1/ml air
10-12uCi/ml air
!0-6uC1/ml water
10Tl2uC1/ml air
10-l2wC1/nil air
10-12uCi/ml air
28
170
2.3
<20
32
6.4
27
45
3.2
<20
20
< 3
29
14,000
12
<20
110
37
25
17
<20
120
57
27
<20
0.73
<20
4.2
<20
15
< 3
< 0.3
< 2
< 0.7
< 0.6
16 .
< 3
< 0.3
< 2
< 0.7
< 0.7
19
< 2
0.32
< 2
. 1.2
< 0.2
17
< 3
< 0.5
< 2
1.9
< 0.2
15
< 4
< 0.3
< 2
< 0.9
< 0.5
20
5.7
0.33
< 2 )
1.8 >
0.8 )
20
3.4
0.29
< 2 )
1.2 >
< 0.7 )
22
240
2.2
< 2 )
13
2.7 )
20
< 3
4.5
< 2 )
18 }
6.9 J
20
< 3
< 0.3
< 2 )
1.1 [
0.5 )
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
..
< 0.01
< 0.01
< 0.01
-_
< 0.01
< 0.01
< 0.01
_
< 0.01
0.02
< 0.01
..
< 0.01
Concentration Guides used for NTS Stations are those applicable to exposures to radiation workers. Those
used for off-NTS stations are for exposure to a suitable sample of the population in an uncontrolled area.
See Appendix 8 for Concentration Guides.
#Also known as Groom Lake.
67
-------
TABLE A-5. 1978 SUMMARY OF RADIATION DOSES FOR THE DOSIMETRY NETWORK
Station
Location
Adaven, Nev.
Alamo, Nev.
Area 51-NTS, Nev.
Austin, Nev. -
Baker, Calif.
Barstow, Calif.
Beatty, Nev.
Bishop, Calif.
Blue Eagle Ranch, Nev.
Blue Jay, Nev.
Cactus Springs, Nev.
Caliente, Nev.
Carp, Nev.
Casey's Ranch, Nev.
Cedar City, Utah
Clark Station, Nev.
Complex I, Nev.
Coyote Summit, Nev.
Currant, Nev.
Death Valley Oct., Calif.
Desert Game Range, Nev.
Desert Oasis, Nev. l
Diablo Maint. Sta., Nev.
Duckwater, Nev.
Elgin, Nev.
Ely, Nev.
Enterprise, Utah
Eureka, Nev.
Furnace Creek, Calif.
Garrison, Utah
Geyser Maint. Sta., Nev.
Glendale, Utah2
Goldfield, Nev.
Hancock Summit, Nev.
Hiko, Nev.
Hot Creek Ranch, Nev.
Independence, Calif.
Indian Springs, Nev.
Kirkeby Ranch, Nev.
Koynes, Nev.
Las Vegas (Airport), Nev.
Measurement
Period
01/10/78
01/09/78
01/09/78
01/11/78
01/09/78
01/09/78
01/31/78
01/10/78
01/11/78
01/10/78
01/16/78
01/10/78
01/10/78
01/11/78
02/01/78
01/10/78
01/10/78
01/09/78
01/11/78
01/12/78
01/16/78
01/31/78
01/12/78
01/11/78
01/10/78
01/11/78
02/01/78
01/11/78
01/12/78
01/09/78
01/09/78
03/27/78
01/09/78
01/09/78
01/09/78
01/10/78
01/10/78
01/16/78
01/09/78
01/12/78
02/06/78
.
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
-
_
-
-
-
-
-
_
-
01/07/79
01/08/79
01/08/79
01/09/79
01/08/79
01/08/79
01/03/79
01/10/79
01/09/79
01/11/79
01/02/79
01/09/79
01/09/79
01/10/79
01/16/79
01/14/79
01/10/79
01/12/79
01/09/79
01/11/79
01/02/79
03/27/79
01/11/79
01/09/79
01/09/79
01/25/79
01/10/79
01/10/79
01/11/79
01/08/79
01/08/79
01/15/79
01/08/79
01/12/79
01/08/79
01/11/79
01/09/79
01/02/79
01/08/79
01/12/79
01/19/79
Dose
Equivalent Rate
(mrem/d)
Max. Min. Avg.
0,
0,
0,
0.
0,
0,
0,
0,
0,
0,
0,
0,
0,
0,
0,
0.
0,
0,
0,
0,
0,
0,
0.
0,
0.
0.
0.
0,
0.
0.
0.
0.
0,
0,
0.
0.
0,
0.
0,
0.
0.
.39
.29
.20
.43
.24
.27
.28
.28
.21
.35
.18
.38
.31
.22
.23
.33
.30
.35
.31
.23
.16
.17
.38
.33
.35
.23
.30
.34
.19
,22
.32
.17
.27
.42
.22
,27
.29
.19
,24
.27
,15
0.
0,
0,
0,
0,
0.
0,
0,
0,
0.
0,
0,
0,
0,
0,
0,
0,
0,
0,
0.
0,
0,
0,
0,
0,
0.
0,
0.
0,
0,
0,
0,
0,
0,
0,
0.
0.
0.
0.
0.
0.
.33
.26
.19
.40
.23
.27
.32
.27
.17
.34
.17
.31
.30
.20
.22
.32
.29
.34
.29
.22
.15
.17
.36
.29
.35
.21
.27
.31
.18
.20
.30
.17
.25
.39
.22
.26
.27
.16
.21
.24
,14
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
.
36
28
20
41
23
27
30
28
19
34
18
34
30
20
22
33
29
34
30
22
16
17
37
30
35
22
29
33
18
21
31
17
26
41
22
26
27
18
23
26
15
Annual
Adjusted
Dose
Equiv-
alent
(mrem/y)
130
100
72
150
84
96
100
100
67
120
60
120
110
77
77
120
110
130
110
81
55
5
130
110
130
83
96
120
67
76
110
50
95
150
80
96
100
61
82
95
51
(continued)
68
-------
TABLE A-5. (Continued)
Station
Location
Las Vegas (Placak), Nev.
Las Vegas (USDI), Nev.
Lathrop Wells, Nev.
Lida, Nev.
Lone Pine, Calif.
Lund, Nev.
Mammoth Mtn., Calif.
Manhattan, Nev.
Mesquite, Nev.
Nevada Farms, Nev.
Nuclear Eng. Co., Nev.
Nyala, Nev.
Olancha, Calif.
Pahrump, Nev.
Pine Creek Ranch, Nev.3
Pioche, Nev.
Queen City Summit, Nev.
Reed Ranch, Nev.
Ridgecrest, Calif.
Robinson's Tr. Park, Nev.
Round Mountain, Nev.
Rox, Nev.
Scotty's Junction, Nev.
Selbach Ranch, Nev.
Sherri's Bar, Nev.
Shoshone, Calif.
Springdale, Nev.
Spring Meadows, Nev.
St. George, Utah
Stone Cabin Ranch, Nev.
Sunnyside, Nev.
Tempi ute, Nev.
Tenneco, Nev.
Tonopah, Nev.
Tonopah Test Range, Nev.
Twin Springs Ranch, Nev.
Warm Springs, Nev.
Young's Ranch, Nev.
Measurement
Period
02/06/78 -
02/06/78 -
01/16/78 -
01/09/78 -
01/10/78 -
01/10/78 -
01/11/78 -
01/10/78 -
01/31/78 -
01/12/78 -
01/31/78 -
01/11/78 -
01/10/78 -
01/17/78 -
01/10/78 -
01/11/78 -
01/09/78 -
01/09/78 -
01/10/78 -
01/12/78 -
01/10/78 -
01/31/78 -
01/09/78 -
01/31/78 -
01/09/78 -
01/12/78 -
02/01/78 -
01/17/78 -
02/02/78 -
01/11/78 -
01/10/78 -
01/12/78 -
01/17/78 -
01/09/78 -
01/10/78 -
01/12/78 -
01/11/78 -
01/10/78 -
01/19/79
01/19/79
01/03/79
01/08/79
01/09/79
01/10/79
01/10/79
01/09/79
01/15/79
01/12/79
01/03/79
01/10/79
01/09/79
01/02/79
10/05/78
01/10/79
01/12/79
01/11/79
01/09/79
01/12/79
01/09/79
01/15/79
01/08/79
01/03/79
01/08/79
01/11/79
01/03/79
01/02/79
01/16/79
01/12/79
01/10/79
01/12/79
01/02/79
01/08/79
01/09/79
01/11/79
01/11/79
01/09/79
Dose
Equivalent Rate
(mrem/d)
Max. Min. Avg.
0.15
0.18
0.28
0.29
0.28
0.25
0.38
0.34
0.18
0.34
0.47
0.24
0.26
0.19
0.33
0.25
0.39
0.32
0.24
0.33
0.32
0.28
0.31
0.34
0.22
0.30
0.35
0.20
0.19
0.48
0.22
0.34
0.30
0.33
0.30
0.32
0.33
0.26
0.14
0.17
0.25
0.28
0.26
0.23
0.24
0.24
0.18
0.32
0.35
0.23
0.25
0.18
0.31
0.24
0.37
0.30
0.23
0.33
0.30
0.26
0.28
0.31
0.21
0.28
0.31
0.17
0.19
0.31
0.20
0.28
0.29
0.30
0.27
0.31
0.32
0.25
0.15
0.17
0.26
0.28
0.27
0.24
0.29
0.31
0.18
0.33
0.39
0.23
0.26
0.18
0.32
0.24
0.38
0.31
0.23
0.33
0.31
0.27
0.29
0.32
0.21
0.29
0.33
0.18
0.19
0.39
0.21
0.31
0.29
0.31
0.29
0.31
0.32
0.25
Annual
Adjusted
Dose
Equiv-
alent
(mrem/y)
51
60
93
100
99
88
100
110
64
120
130
85
94
64
77
88
140
110
85
120
110
95
100
110
77
110
110
65
66
140
76
110
100
110
100
120
120
92
'Monitoring at this location discontinued after first quarter 1978.
2Station established second quarter 1978.
'Fourth quarter 1978 exchange not possible due to weather conditions.
69
-------
TABLE A-6. 1978 SUMMARY OF ANALYTICAL RESULTS FOR THE
MILK SURVEILLANCE NETWORK
Sampling Sample
Location Type1
Hinkley, Calif. 12
Bill Nelson Dairy
Keough Hot Spgs. , 13
Calif.
Yribarren Ranch
Trona, Calif. 13
Stanford Ranch
Alamo, Nev. 14
A. J. Sharp
Austin, Nev. 14
Young's Ranch
Caliente, Nev 13
June Cox Ranch
Radioactivity Cone.
(10- 9 uCi/ml)
No. of Radio-
Samples nuclide cMax cMin cAvg
4
4
4
4
4
4
3
3
3
3
3
3
4
4
4
4
4
4
4
89Sr
90Sr
lS7Cs
89Sr
"Sr
lJ7Cs
9Sr
90Sr
IJ7Cs
$9Sr
90Sr
1J7Cs
SH
89Sr
90Sr
1S7Cs
89Sr
90Sr
lJ7Cs
< 5
< 2
4.0
< 5
2.0
6.0
< 6
< 2
5.5
< 3
< 2
7.1
620
< 3
2.3
< 5
< 3
1.6
< 4
< 3
< 2
< 3
< 2
< 2
< 3
< 3
< 2
< 3
< 2
< 2
< 3
<400
< 2
1.3
< 4
< 2
< 2
< 3
<
<
<
2
<
<
<
<
<
<
<
5
3
2
3
.0
2
3
3
2
3
2
2
.2
<400
<
1
<
<
<
<
2
.8
4
2
2
3
(continued)
70
-------
TABLE A-6. (Continued)
Sampling Sample
Location Type1
Currant, Nev. 13
Blue Eagle Ranch
Currant, Nev. 13
Manzonie Ranch
Hiko, Nev. 13
Darrel Hansen Ranch
Las Vegas, Nev. 12
LDS Dairy Farm
Lathrop Wells, Nev. 13
Kirker Ranch
Lida, Nev. 13
Lida Livestock Co.
No. of Radio-
Samples nuclide
3
3
3
0
4
4
4
4
4
4
4
4
3
3
3
1
1
1
"Sr
90Sr
l37Cs
89Sr
"Sr
lJ7Cs
'H
"Sr
90Sr
lS7Cs
SH
89Sr
90Sr
IS7Cs
89Sr
"Sr
l37Cs
89Sr
9 0
Sr
I37Cs
Radioactivity Cone.
(10-9 yCi/ml)
^Max ^Mi n ^Avg
< 3
3.5
16
._
--
--
<600
< 4
< 2
5.9
<600
< 3
< 2
5.4
< 3
< 2
< 5
< 2
< 2
8.9
< 2
< 2
< 4
«
--
--
<400
< 2
< 2
< 4
<400
< 2
< 2
< 3
< 2
< 2
< 4
< 2
< 2
8.9
< 2
2.0
7.1
*m w
<400
< 2
< 2
< 4
<400
< 2
< 2
< 3
< 2
< 2
< 4
< 2
< 2
8.9
(continued)
71
-------
TABLE A-6. (Continued)
Sampl i ng Sampl e
Location Type1
Logandale, Nev. 12
Vegas Valley Dairy
Lund, Nev. 12
McKenzie Dairy
Mesquite, Nev. 12
Hughes Bros. Dairy
Moapa, Nev. 12
Agman Seventy-Five, Inc.
Nyala, Nev. 13
Sharp's Ranch
Radioactivity Cone.
(1(T9 yCi/ml)
No. of Radio-
Samples nuclide cMax cMin cAvg
4
4
4
4
4
4
4
4
4
4
4
4
4
4
4
4
4
4
89Sr
90Sr
lS7Cs
SH
89Sr
"Sr
1J7Cs
SH
89Sr
90Sr
IJ7Cs
8sSr
"Sr
1J7Cs
'H
"Sr
90Sr
ls?Cs
< 4
< 2
< 5
<600
< 4
< 3
4.9
1400
< 4
< 2
4.9
< 3
1.5
< 5
<600
< 3
1.7
< 5
< 2
< 1
< 3
<400
< 2
< 2
2.9
<400
< 2
< 1
3.8
< 2
< 2
< 4
<400
< 2
< 2
< 3
< 2
< 1
< 3
<400
< 2
< 2
< 3
450
< 2
< 1
< 4
< 2
< 2
< 4
<400
< 2
< 2
< 3
(continued)
72
-------
TABLE A-6. (Continued)
Radioactivity Cone.
Sampl i ng Sampl e
Location Type1
Pahrump, Nev. 13
Oxborrow Ranch
Round Mountain, 13
Nev.
Berg Ranch
Shoshone, Nev. 13
Kirkeby Ranch
Springdale, Nev. 13
Boiling Pot Ranch
Cedar City, Utah 12
Western General Dairy
St. George, Utah 12
R. Cox Dairy
No. of
Samples
3
3
3
1
1
1
4
4
4
2
2
2
4
4
4
4
4
4
Radio-
nuclide
89Sr
90Sr
137Cs
89Sr
90Sr
lJ7Cs
89Sr
9*Sr
1J7Cs
8JSr
"Sr
lJ7Cs
"Sr
90Sr
1S7Cs
89Sr
90Sr
1J7Cs
(io-9
cMax
< 3
< 2
5.2
< 2
4.0
< 4
< 3
2.8
7.3
< 3
1.4
< 4
< 4
2.8
< 5
< 4
< 2
5.7
yCi/ml)
cMin
< 2
< 2
< 4
< 2
4.0
< 4
< 2
1.6
< 3
< 3
< 2
< 3
< 2
< 2
< 3
< 2
< 1
< 4
'Avg
< 2
< 2
< 4
< 2
4.0
< 4
< 2
1.9
3.8
< 3
< 2
< 3
< 2
< 2
< 3
< 2
< 1
< 4
42 = Raw Milk from Grade A Producer(s)
13 = Raw Milk from family
cow(s)
14 = Other than Grade A Producer (Raw)
73
-------
TABLE A-7. ANALYTICAL CRITERIA FOR LONG-TERM HYDROLOGICAL
MONITORING PROGRAM SAMPLES
Gross alpha
Gross beta
Gamma scan
»H*
89,90
226Ra
U
Sr
All samples
All samples
All samples
All samples
Only samples collected at locations for the first time
during CY78.
Only samples collected at locations for the first time
during CY78 if gross alpha exceeded 3 x 10~9 uCi/ml.
Only samples collected at locations for the first time
during CY78.
Only samples collected at locations for the first
time during CY78.
*A11 samples were first analyzed by the more rapid conventional
technique (MDC of about 4 x 10"7 yCi/ml). Those samples having tritium
concentrations
-------
TABLE A-8. 1978 SUMMARY OF ANALYTICAL RESULTS FOR THE NTS MONTHLY
LONG-TERM HYDROL06ICAL MONITORING PROGRAM
No.
Sampling Samples
Location Collected1
NTS
Well 8
NTS
Well U3CN-5
NTS
Well A
NTS
Well C
NTS
Well 5c
NTS
Army Wei 1
No. 1
NTS
Well 2
NTS
Test Well B
NTS
Well J-13
NTS
Well J-12
(Alternate for
NTS
Well U19c
10
11
11
11
11
11
10
7
10
1
J-13
9
No. Type of
Samples Radio-
Analyzed activity
10
10
10
11
11
11
11
11
11
11
11
11
11
11
11
11
11
11
10
10
10
7
7
6
10
10
10
1
9
9
9
Gross a
Gross 0
'H
Gross a
Gross 0
SH
Gross a
Gross 0
SH
Gross a
Gross 0
SH
Gross a
Gross 0
3H
Gross a
Gross 0
3H
Gross a
Gross 0
3H
Gross a
Gross 0
JH
Gross a
Gross 0
3H
Gross a
Gross 0
3H
Gross a
GRoss 0
SH
Radioactivity Cone.
(10-9 yCi/ml)
Max Min Avg
< 4
< 6
<20
9.0
10
280
13
7.2
21
27
12
100
11
46
<30
5.8
< 6
<16
7.6
< 6
47
< 5
< 6
250
6.1
< 6
16
< 3
< 6
<13
< 3
< 6
<17
< 2
< 4
< 9
< 3
< 6
< 9
< 3
< 6
< 9
< 6
< 6
38
< 5
< 6
< 9
< 4
4.9
< 9
< 3
4.1
< 9
< 3
< 4
170
< 3
< 4
< 9
< 3
< 6
<20
< 2
< 4
< 9
< 2
< 4
< 9
4.9
< 6
45
5.7
< 6
< 9
11
6.8
56
6.1
5.8
< 9
3.8
< 5
< 9
2.6
< 5
< 9
< 3
< 4
190
< 3
< 4
< 9
< 3
< 6
< 3
< 2
< 4
< 9
% of
Cone.
Guide2
--
<0.01
__
--
<0.01
-_
<0.01
__
-_
<0.01
__
_-
<0.01
__
--
<0.01
._
<0.01
__
__
<0.01
__
-_
<0.01
__
__
<0.01
__
_
<0.01
'Samples could not be collected every month
inoperative pumps.
2Concentration Guides for drinking water at
those for off-NTS locations. See Appendix
due to weather conditions or
on-NTS locations are the same as
B for Concentration Guides.
75
-------
TABLE A-9. 1978 ANALYTICAL RESULTS FOR THE NTS SEMI-ANNUAL
LONG-TERM HYDROLOGICAL MONITORING PROGRAM
Sampl i ng
Location
NTS
Well
NTS
Well
NTS
Test
NTS
Test
NTS
Well
NTS
Well
NTS
Well
NTS
Well
NTS
Well
NTS
Well
NTS
Well
UE15d
UE15d
Well D
Well D
UElc
UElc
C-l
C-l
UE5C
UE5C
UE18r"
Depth
Date (m) '
2/02
7/19
1/31 571
7/20 571
2/02 500
7/20 500
2/02
7/19
2/01
8/01
2/02 507
Sampl e
Type2
23
23
23
23
23
23
23
23
23
23
23
Type of
Radio-
activity
Gross a
Gross 3
JH
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Gross a
Gross 3
3H
Radioactivity
Cone.
(10-9 uCi/ml)
9.2
10
<20
10
8.6
<30
< 4
< 6
<20
< 4
< 6
<20
3.9
< 6
<20
< 4
< 6
<20
5.8
7.5
24
8.7
9.4
<20
3.8
< 6
<20
8.6
< 6
<20
7.8
< 6
<20
% of
Conc.s
Guide*
..
<0.01
_ _
--
<0.01
~«
--
<0.01
_-
<0.01
__
<0.01
_.
_.
<0.01
,.
<0.01
__
--
<0.01
*.
--
<0.01
.«
__
<0.01
^ ^
--
<0.01
(continued)
76
-------
TABLE A-9. (Continued)
Sampling Depth
Location Date (m)1
NTS 2/01
Well 5B
NTS 7/18
Well 5B
NTS 2/03 1006
Test Well F
NTS 7/21 1006
Test Well F
Ash Meadows, 1/04
Nev.
Crystal Pool
Ash Meadows, 7/27
Nev.
Crystal Pool
Ash Meadows, 1/04
Nev.
Well 18S/51E-7DB
Ash Meadows, 7/27
Nev.
Well 18S/51E-7DB
Ash Meadows, 1/04
Nev.
Well 17S/50E-14CAC
Ash Meadows, 7/27
Nev.
Well 17S/50E-14CAC
Sample
Type2
23
23
23
23
27
27
23
23
23
23
Type of
Radio-
activity
Gross a
Gross 0
SH
Gross a
Gross 8
3H
Gross a
Gross 3
8H
Gross a
Gross 3
JH
Gross a
Gross 3
»H
Gross a
Gross 3
SH
Gross a
Gross 3
3H
Gross a
Gross 8
3H
Gross a
Gross 8
3H
Gross a
Gross 3
'H
Radioactivity
Cone.
(10-9 yCi/ml)
< 4
5.7
<20
5.7
< 6
<20
13
10
<20
11
7.8
<20
15
10
<20
7.0
12
<20
5.4
< 6
<20
4.1
< 6
<20
8.9
19
<20
< 4
< 6
<20
% of
Cone.
Guide*
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
(continued)
77
-------
TABLE A-9. (Continued)
Sampl i ng Depth
Location Date (m)1
Ash Meadows, 1/04
Nev.
Fairbanks
Springs
Ash Meadows, 7/27
Nev.
Fairbanks
Springs
Beatty, 1/05
Nev.
City Supply
Beatty, 8/02
Nev.
City Supply
Beatty, 1/03
Nev.
Nuclear
Engineering Co.
Beatty, 8/02
Nev.
Nuclear
Engineering Co.
Beatty, 1/05
Nev.
Coffers Well
Beatty, 8/01
Nev.
Coffers Well
Indian Springs, 1/03
Nev.
USAF No. 2
Indian Springs 8/01
Nev.
USAF No. 2
Sample
Type2
27
27
23
23
23
23
23
23
23
23
Type of
Radio-
activity
Gross a
Gross B
3H
Gross a
Gross B
SH
Gross a
Gross B
SH
Gross a
Gross B
SH
Gross a
Gross B
JH
Gross a
Gross B
SH
Gross a
Gross B
3H
Gross a
Gross B
JH
Gross a
Gross B
SH
Gross a
Gross B
3H
Radioactivity
Cone.
(10-* yCi/ml)
< 4
< 6
<20
< 4
< 6
<20
16
< 6
<20
9.3
< 6
<20
8.3
5.9
<20
8.1
< 6
<20
9.4
< 6
<20
11
< 6
16
< 5
< 6
<20
< 5
< 6
25
% of
Cone.
Guide*
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
(continued)
78
-------
TABLE A-9. (Continued)
Sampling Depth
Location Date (m) l
Indian Springs, 1/03
Nev.
Sewer Co. Inc.
Well No. 1
Indian Springs, 8/01
Nev.
Sewer Co. Inc.
Well No. 1
Lathrop Wells, 1/03
Nev.
City Supply
Lathrop Wells, 8/02
Nev.
City Supply
Springdale, 1/05
Nev.
Goss Springs
Springdale, 8/02
Nev.
Goss Springs
Springdale, 1/05
Nev.
Road D Windmill
'If depth not shown, water was
223 - Well
27 - Spring
Sample
Type2
23
23
23
23
27
27
23
Type of
Radio-
activity
Gross a
Gross 0
SH
Gross a
Gross a
'H
Gross a
Gross 3
SH
Gross a
Gross 3
'H
Gross o
Gross p
SH
Gross a
Gross 0
>H
Gross a
Gross e
JH
Radioactivity
Cone.
(10-9 yCi/ml)
5.5
< 6
<20
< 4
< 6
<20
< 4
< 6
<20
< 4
< 6
<20
< 5
6.0
<20
< 5
< 6
<20
< 5
< 6
<20
% of
Cone.
Guide'
--
<0.01
__
__
<0.01
__
--
<0.01
__
--
<0.01
_-
__
<0.01
__
<0.01
_
--
<0.01
collected at surface
'Concentration Guides for drinking water at on-NTS locations are the same
as those for off-NTS locations. See Appendix B.
"Second sample during the year could not be collected.
79
-------
TABLE A-10. 1978 ANALYTICAL RESULTS FOR THE
NTS ANNUAL LONG-TERM HYDROLOGICAL MONITORING PROGRAM
Sampling
Location
Shoshone, Calif.
S ho shone Spring
Hiko, Nev.
Crystal Springs
Alamo, Nev.
City Supply
Warm Springs, Nev.
Twin Springs Ranch
Diablo, Nev.
Highway Maint.
Stat i on
Nyala, Nev.
Sharp Ranch
Adaven, Nev.
Adaven Spring
Pahrump, Nev.
Calvada Well 3
Tonopah, Nev.
City Supply
Clark Station,
Nev.
Tonopah Test
Range Well 6
Las Vegas, Nev.
Water District
Well No. 28
Tempi ute, Nev.
Union Carbide Well
'23 - Well
Date
7/27
6/19
6/19
6/19
6/19
6/20
6/20
6/21
6/21
6/20
6/22
6/19
Sampl e
Type1
27
27
23
27
23
23
27
23
23
23
23
23
27 - Spring
2See Appendix B for Concentration
Type of
Radio-
activity
Gross a
Gross 8
3H
Gross a
Gross B
JH
Gross a
Gross B
JH
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a .
Gross B
3H
Gross a
Gross B
3H
Gross o
Gross B
3H
Gross a
Gross B
JH
Gross a
Gross B
SH
Guides.
80
Radioactivity
Cone.
(10-9 yCi/ml)
< 6
12
<20
6.2
< 6
<20
< 5
6.0
<20
7.7
< 6
<20
< 4
< 6
<20
< 5
< 6
180
< 3
< 6
120
< 5
< 6
<20
< 3
< 6
<30
< 4
< 6
<20
< 3
< 6
<20
< 3
< 6
<20
% of
Cone.
Guide2
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
*
<0.01
<0.01
<0.01
-------
TABLE A-ll. 1978 ANALYTICAL RESULTS FOR THE OFF-NTS
LONG-TERM HYDROLOGICAL MONITORING PROGRAM
Sampl i ng
Location
Malaga,
N. Mex.
USGS Well
No. 1
Malaga,
N. Mex.
USGS Well
No. 4
Malaga,
N. Mex.
USGS Well
No. 8
Malaga,
N. Mex.
PHS Well No. 6
Malaga,
N. Mex.
PHS Well No. 8
Malaga,
N. Mex.
PHS Well No. 9
Malaga,
N. Mex.
PHS Well No. 10
Malaga,
N. Mex.
Pecos River
Depth Sample
Date (m)1 Type2
PROJECT
5/20 161 23
5/20 148 23
5/20 144 23
23
5/21 23
5/21 23
5/21 23
5/21 23
Type of
Radio-
activity
GNOME
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross W
3H
Radioactivity
Cone.
(10-9 yd /ml)
< 8
<20
14
19,000
640,000
< 9
21,000
710,000
(not collected
broken pump)
< 9
< 7
<20
< 3
< 6
<20
<2Q4
<204
<20
< 7
< 6
<20
% of
Cone.
Guide3
< 0.01
21
21
due to
< 0.01
< 0.01
< 0.01
<0.01
Pumping Stations
(continued)
81
-------
TABLE A-ll. (Continued)
Sampl i ng
Location
Lovi ng ,
N. Mex.
City Well No. 2
Carlsbad,
N. Mex.
City Well No. 7
Frenchman,
Nev.
Frenchman
Station
Frenchman,
Nev.
Well HS-1
Frenchman,
Nev.
Well H-3
Frenchman,
Nev.
Flowing Well
Frenchman,
Nev.
Hunts Station
Baxterville,
Miss.
City Supply
Date
5/21
5/22
3/01
3/02
3/01
3/01
3/02
4/12
Depth Sample
(m)1 Type2
23
23
PROJECT
23
23
23
23
23
PROJECT
23
Type of
Radio-
activity
Gross a
Gross 3
5H
Gross a
Gross 3
SH
SHOAL
Gross a
Gross 3
SH
Gross a
Gross 3
3H
Gross a
Gross 3
SH
Gross a
Gross 3
3H
Gross a
Gross 3
JH
DRIBBLE
Gross a
Gross 3
SH
Radioactivity
Cone.
(10- f uCi/ml)
< 4
< 6
<20
< 4
< 6
<20
22
11
<20
3.9
< 6
<20
< 7
< 6
<20
<204
1605
<20
< 5
< 6
<20
< 2
< 6
77
% of
Cone.
Guide'
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
--
< 0.01
< 0.01
< 0.01
(continued)
82
-------
TABLE A-ll. (Continued)
Sampl i ng
Location
Baxterville,
Miss.
Lower Little
Creek
Baxterville,
Miss.
Well HT-1
Baxterville,
Miss.
Well HT-2c
Baxterville,
Miss.
Well HT-4
Baxterville,
Miss.
Well HT-5
Baxterville,
Miss.
Well E-7
Baxterville,
Miss.
Well Ascot
No. 2
Baxterville,
Miss.
Half Moon
Creek
Baxterville,
Miss.
Half Moon
Creek Overflow
Depth Sample
Date (m) l Type2
4/12 22
4/10 378 23
4/10 108 23
4/14 122 23
4/14 183 23
4/10 280 23
4/17 651 23
4/17 22
4/14 22
Type of
Radio-
activity
Gross a
Gross $
3H
Gross a
Gross W
3H
Gross a
Gross B
3H
Gross a
Gross e
3H
Gross a
Gross B
SH
Gross a
Gross 0
3H
Gross a
Gross e
SH
Gross a
Gross B
3H
Gross a
Gross 6
SH
Radioactivity
Cone.
(10-» uCi/ml)
< 2
< 6
63
< 5
< 6
15
< 3
< 6
24
< 4
< 6
<20
< 2
< 6
<20
< 4
< 6
<20
<404
<304
<20
< 2
< 6
62
< 4
< 6
2700
% of
Cone.
Guide3
--
< 0.01
__
< 0.01
__
< 0.01
< 0.01
__
< 0.01
__
< 0.01
--
< 0.01
__
< 0.01
__
0.09
(continued)
83
-------
TABLE A-ll. (Continued)
Sampl i ng
Location
Baxterville,
Miss.
T. Speights
Residence
Baxterville,
Miss.
R. L. Anderson
Residence
Baxterville,
Miss.
Mark Lowe
Residence
Baxterville,
Miss.
R. Ready
Residence
Baxterville,
Miss.
W. Daniels
Residence
Lumberton ,
Miss.
City Supply
Well No. 2
Purvis,
Miss.
City Supply
Columbia,
Miss.
City Supply
Depth Sample
Date (m) l Type2
4/13 23
4/13 23
4/13 23
4/12 23
4/13 23
4/11 23
4/11 23
4/12 23
Type of
Radio-
activity
Gross a
Gross B
3H
Gross a
Gross B
»H
Gross a
Gross B
3H
Gross a
Gross B
3H
Gross a
Gross B
Gross a
Gross B
SH
Gross a
Gross B
SH
Gross a
Gross B
SH
Radioactivity
Cone.
(10- yCi/ml)
< 2
< 6
99
< 2
< 6
55
< 2
< 6
55
< 3
< 6
46
< 2
< 6
38
< 3
< 6
<20
< 3
< 6
<20
< 2
< 6
<20
% of
Cone.
Guide3
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
(continued)
84
-------
TABLE A-ll. (Continued)
Sampl i ng
Location
Lumberton,
Miss.
North Lumberton
City Supply
Baxterville,
Miss.
Pond W of GZ
Gobernador,
N. Mex.
Arnold Ranch
Gobernador,
N. Mex.
Apache Reservation
Well South
Gobernador,
N. Mex.
Lower Burro
Canyon
Gobernador,
N. Mex.
Fred Bixler
Ranch
Gobernador,
N. Mex.
Cave Springs
Gobernador,
N. Mex.
Windmill No. 2
Date
4/11
4/11
5/18
5/18
5/18
5/18
5/18
5/16
Depth Sample
(m) l Type 2
23
21
PROJECT
27
23
23
23
27
23
Type of
Radi o-
activity
Gross a
Gross 8
SH
Gross a
Gross 8
H
GASBUGGY
Gross a
Gross 8
!H
Gross a
Gross 8
SH
Gross a
Gross 8
3H
Gross a
Gross 8
3H
Gross a
Gross 0
3H
Gross a
Gross 8
SH
Radioactivity % of
Cone. Cone.
(10-9 yCi/ml) Guide'
< 3
< 6
<20
< 2
< 2
76 < 0.01
< 9
< 7
<20 < 0.01
< 7
< 6
67
< 8
< 7
<20 < 0.01
< 6
< 6
<20 < 0.01
< 3
< 6
<20
< 7
< 7
<20
(continued)
85
-------
TABLE Aril. (Continued)
Sampl i ng
Location
Gobernador,
N. Mex.
Bubbling Springs
Gobernador,
N. Mex.
La Jara Creek
Gobernador,
N. Mex.
EPNG Well 10-36
Rulison,
Colo.
Lee L. Hay ward
Ranch
Rulison,
Colo.
Glen Schwab
Ranch
Grand Valley,
Colo.
Albert Gardner
Ranch
Grand Valley,
Colo.
City Water
Supply
Grand Valley
Colo.
Spring 300 Yds.
Type of
Depth Sample Radio-
Date (m) * Type2 activity
5/16 27 Gross a
Gross e
JH
5/16 22 Gross a
Gross 0
SH
5/17 1097 23 Gross a
Gross 0
8H
PROJECT RULISON
5/19 23 Gross a
Gross 0
3H
5/19 23 Gross a
Gross 0
SH
5/19 23 Gross a
Gross 0
SH
5/19 27 Gross a
Gross 0
JH
5/20 27 Gross a
Gross 0
»H
Radioactivity
Cone.
(10-9 yCi/ml)
< 6
< 6
120
< 8
< 7
170
<404
45
16
12
< 6
710
4.8
< 6
690
< 4
< 6
650
< 4
< 6
<20
< 4
< 6
730
% of
Cone.
Guide'
< 0.01
< 0.01
0.02
0.02
0.02
< 0.01
0.02
NW of GZ
(continued)
86
-------
TABLE A-ll. (Continued)
Sampling
Location Date
Rulison, 5/19
Colo.
Felix Sefcovic
Ranch
Grand Valley, 5/20
Colo.
Battlement Creek
Grand Valley, 5/20
Colo.
CER Well
Rulison, 5/18
Colo.
Potter Ranch
Blue Jay, 6/14
Nev.
Highway Ma int.
Station
Blue Jay, 6/15
Nev.
Sixmile Well
Blue Jay, 6/19
Nev.
Jim Bias Well
Blue Jay, 6/12
Nev.
Well HTH-1
Type of
Depth Sample Radio-
(m) l Type2 activity
23 Gross a
Gross 3
SH
22 Gross a
Gross 3
SH
23 Gross a
Gross 3
SH
27 Gross a
Gross 3
JH
PROJECT FAULTLESS
23 Gross a
Gross 3
SH
23 Gross a
Gross 3
»H
27 Gross a
Gross 3
3H
259 23 Gross a
Gross 3
SH
Radioactivity
Cone.
(10- 9 yCi/ml)
< 3
< 6
880
< 3
< 6
850
< 3
< 6
580
3.7
< 6
680
3.9
< 6
<20
< 4
< 6
<20
7.5
< 6
<20
< 4
< 6
<20
% of
Cone.
Guide'
0.03
__
--
0.03
_
0.02
__
0.02
«*
--
< 0.01
__
__
< 0.01
__
< 0.01
(continued)
87
-------
TABLE A-ll. (Continued)
Sampl i ng
Location Date
Blue Jay, 6/12
Nev.
Well HTH-2
Rio Blanco, 5/17
Colo.
Fawn Creek
6800 ft Upstream
Rio Blanco,
Colo.
Fawn Creek
500 ft Upstream
Rio Blanco, 5/17
Colo.
Fawn Creek
500 ft Downstream
Rio Blanco, 5/17
Colo.
Fawn Creek
8400 ft Downstream
Rio Blanco, 5/17
Colo.
Fawn Creek No. 1
Rio Blanco, 5/17
Colo.
Fawn Creek No. 3
Rio Blanco, 5/18
Colo.
CER No. 1
Black Sulphur
Type of
Depth Sample Radio-
(m)1 Type2 activity
184 23 Gross a
Gross 3
SH
PROJECT RIO BLANCO
22 Gross a
Gross 3
JH
22 Gross a
Gross 3
SH
22 Gross a
Gross 3
3H
22 Gross a
Gross 6
9H
27 Gross a
Gross 0
SH
27 Gross a
Gross 3
SH
27 Gross a
Gross 3
SH
Radioactivity
Cone.
(10- 8 MCi/ml)
3.4
< 6
<20
< 6
< 6
80
% of
Cone.
Guide3
< 0.01
< 0.01
(Sample not collected)
< 6
< 6
63
< 6
< 6
49
< 6
< 6
51
< 6
< 6
48
< 6
< 6
67
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
(continued)
88
-------
TABLE A-ll. (Continued)
Sampl i ng
Location Date
Rio Blanco, 5/18
Colo.
CER No. 4
Black Sulphur
Rio Blanco, 5/18
Colo.
B-l Equity Camp
Rio Blanco, 5/16
Colo.
Brennan Windmill
Rio Blanco, 5/16
Colo.
Johnson Artesian Well
Rio Blanco,
Colo.
Well RB-D-01
Rio Blanco,
Colo.
Well RB-S-03
Amchitka, Alas. 8/20
South End of
Cannikin Lake
Amchitka, Alas. 8/20
North End of
Cannikin Lake
Amchitka, Alas. 8/20
Well HTH-3
Type of
Depth Sample Radio-
(m) ' Type2 activity
27 Gross a
Gross 3
SH
27 Gross a
Gross e
5H
23 Gross a
Gross B
3H
23 Gross a
Gross 3
JH
23 Gross a
Gross 3
3H
23 Gross a
Gross 8
'H
PROJECT CANNIKIN
21 Gross a
Gross 0
SH
21 Gross o
Gross 0
3H
42.7 23 Gross a
Gross 8
SH
Radioactivity
Cone.
(10- 9 yCi/ml)
< 6
< 6
590
< 5
< 6
130
7.5
< 6
<20
< 7
< 7
<20
(Sample not col
to inoperative
(Sample not col
to inoperative
< 4
< 6
64
< 5
< 6
68
< 4
< 6
84
% of
Cone.
Guide'
0.02
< 0.01
< 0.01
< 0.01
lected due
pump)
lected due
pump)
< 0.01
< 0.01
< 0.01
(continued)
89
-------
TABLE Aril. (Continued)
Sampl i ng
Location
Amchitka, Alas.
Ice Box Lake
Amchitka, Alas.
White Alice
Creek
Amchitka, Alas.
Pit South of
Cannikin GZ
Amchitka, Alas.
Heart Lake
Amchitka, Alas.
Well W-5
Amchitka, Alas.
Well W-6
Amchitka, Alas.
Well W-8
Amchitka, Alas.
Well W-15
Amchitka, Alas.
Well W-10
Amchitka, Alas.
Well W-ll
Date
8/20
8/20
8/20
8/21
8/21
8/21
8/21
8/21
8/21
8/21
Depth Sample
(m) l Type2
21
22
21
PROJECT
21
0.83 23
0.94 23
1.6 23
1.1 23
2.0 23
1.5 23
Type of
Radio-
activity
Gross a
Gross 0
'H
Gross a
Gross e
3H
Gross a
Gross 0
3H
MILROW
Gross o
Gross 0
3H
SH
SH
9H
3H
3H
SH
Radioactivity
Cone.
(10-» nCi/ml)
< 2
< 6
100
< 2
< 6
95
< 3
< 6
96
2.0
< 6
89
120
110
210
88
75
110
% of
Cone.
Guide*
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
(continued)
90
-------
TABLE A-ll. (Continued)
Sampl i ng
Location
Amchitka,
Well W-3
Amchitka,
Well W-2
Clevenger
Creek
Amchitka.
Well W-4*
Amchitka,
Well W-76
Amchitka,
Well W-136
Amchitka,
Well W-186
Amchitka,
Well WL-2
Amchitka,
EPA Wei 1-1
Reed Pond
Alas.
Alas.
Alas.
Alas.
Alas.
Alas.
Alas.
Alas.
Depth
Date (m)1
8/21 1.1
8/21 0.30
8/22
8/21 0.46
8/21 0.31
8/22 0.74
8/22 0.20
8/22 3.5
8/22 7.7
8/22
Sampl e
Type2
23
23
22
23
23
23
23
PROJECT
23
23
21
Type of
Radio-
activity
SH
SH
Gross a
Gross B
SH
SH
JH
JH
JH
LONG SHOT
Gross a
Gross B
3H
Gross a
Gross B
SH
Gross a
Gross B
SH
Radioactivity
Cone.
(10-9 yCi/ml)
100
130
< 3
< 6
99
100
96
70
91
< 3
< 6
1000
< 3
< 6
280
< 2
< 6
97
% of
Cone.
Guide3
< 0.01
< 0.01
__
--
< 0.01
< 0.01
< 0.01
< 0.01
< 0.01
--
0.03
__
--
< 0.01
__
--
< 0.01
(continued)
91
-------
TABLE A-ll. (Continued)
Sampling
Location
Well GZ No. 1
Well GZ No. 2
Well WL-1
Mud Pit No. 1
Mud Pit No. 2
Mud Pit No. 3
Amchitka, Alas.
Constantine
Spring
Amchitka, Alas.
Army Well No. 1
Amchitka, Alas.
Jones Lake
Type of Radioactivity % of
Depth Sample Radio- Cone. Cone.
Date (m)1 Type2 activity (ICT9 yCi/ml) Guide3
8/22 27.4 23 Gross a
Gross 3
SH
8/22 12.2 23 Gross a
Gross 6
SH
8/22 1.7 23 Gross a
Gross 3
SH
8/22 21 Gross a
Gross 3
3H
8/22 21 Gross a
Gross 3
SH
8/22 21 Gross a
Gross 3
3H
AMCHITKA BACKGROUND SAMPLES
8/20 27 Gross a
Gross 3
SH
8/21 36.6 23 Gross a
Gross 3
SH
8/20 21 Gross a
Gross 3
SH
< 4
< 6
7300
< 3
< 6
900
< 3
< 6
400
< 3
< 6
1800
< 3
< 6
2300
< 3
< 6
2300
< 3
< 6
110
< 3
< 6
110
< 3
< 6
85
0.24
0.03
0.06
0.08
0.08
< 0.01
< 0.01
< 0.01
(continued)
92
-------
TABLE Aril. (Continued)
Type of Radioactivity % of
Sampling Depth Sample Radio- Cone. Cone.
Location Date (m)' Type2 activity (10~9yCi/ml) Guide8
Duck Cove 8/25 22 SH 110 < 0.01
Creek
llf depth not shown, water was collected at surface
221 - Pond, lake, reservoir, stock tank, or stock pond
22 - Stream, river, or creek
23 - Well
26 - Rain
27 - Spring
Concentration Guides (CG) for drinking water at on-site locations
are the same as those for off-site locations. See Appendix B for
Concentration Guides. As gross a and gross 3 radioactivity con-
centrations were used only for identifying gross radioactivity
concentration increases and as more complete radionuclide analyses
were made in the past, the calculation of % CG.'s was not considered
appropriate.
"High MDC due to high concentration of dissolved solids.
'Based upon gamma spectrometry analysis, the source of this radioactivity
was naturally occurring *°K and daughter products of 222Rn. Actual
quantities could not be determined due to complex gamma spectra.
6These sampling locations were added during this year. The samples
collected from these locations are to be analyzed only for 3H.
93
-------
TABLE A-12. 1978 SPECIAL ANALYTICAL RESULTS FOR THE OFF-NTS
LONG-TERM HYDROLOGICAL MONITORING PROGRAM - PROJECT RIO BLANCO
Sampl i ng
Location
Date
Depth
Sampl e
Type2
Type of
Radio-
activity
Radioactivity
Cone.
(10-9 yCi/ml)
% of
Cone.
Guide3
PROJECT RIO BLANCO
Rio Blanco,
Colo.
Fawn Creek
6800 ft Upstream
5/17
22
89Sr
»°Sr
2S»U
23SU
2J8(J
239f>U
<40
0.7
1.7
0.084
1.2
0.05
0.03
<2
< .30
< .01
< .01
< .01
< .01
< .01
Rio Blanco,
Colo.
Fawn Creek
500 ft Upstream
5/17
22
89Sr
90Sr
239Pu
<50
< 0.7
1.2
0.024
0.77
< 0.04
< 0.030
<2
< .30
< .01
< .01
< .01
< .01
< .01
Rio Blanco, 5/17
Colo.
Fawn Creek
500 ft Downstream
22
§9Sr
90Sr
2J*IJ
2S5U
2J«y
28«Pu
2S9PU
<50
< 0.7
1.4
0.022
0.76
< 0.03
< 0.02
<2
< .30
< .01
< .01
< .01
< .01
< .01
Rio Blanco, 5/17
Colo.
Fawn Creek
8400 ft Downstream
22
"Sr
"Sr
2S5U
2S8U
2S8Pu
2
1.7
1.5
0.032
0.91
0.03
0.02
< .07
.56
< .01
< .01
< .01
< .01
< .01
(continued)
94
-------
TABLE A-12. (Continued)
Sampl i ng Depth
Location Date (m)1
Rio Blanco, 5/18
Colo.
Fawn Creek No. 1
Rio Blanco, 5/17
Colo.
Fawn Creek No. 3
Rio Blanco 5/18
Colo.
CER No. 1
Black Sulphur
Rio Blanco 5/18
Colo.
CER No. 4
Black Sulphur
Rio Blanco 5/18
Colo.
B-l Equity Camp
Type of
Sample Radio-
Type* activity
27 S9Sr
"Sr
2S*U
23SU
2S8U
238Pu
239pu
27 "Sr
"Sr
23-y
23SU
2S8U
238Pu
239f>u
27 "Sr
"Sr
23-u
23SU
238U
238Pu
239Pu
27 "Sr
"Sr
23%u
23SU
2S8U
238Pu
239pu
27 "Sr
"Sr
2»»U
2JSU
2S8U
2"Pu
239pu
Radioactivity
Cone.
(10-9 yCi/ml)
<40
< 0.6
1.8
0.043
0.91
< 0.04
< 0.03
<40
< 0.7
1.4
0.029
0.77
< 0.04
< 0.03
<40
< 0.61
3.0
0.067
1.8
< 0.04
< 0.04
<45
< 0.7
2.2
0.043
1.4
< 0.03
< 0.03
< 2.1
< 0.6
2.0
0.054
1.2
< 0.03
< 0.02
% of
Cone.
Guide3
<2
<0.2
< .01
< .01
< .01
< .01
< .01
<2
<0.3
<0.01
<0.01
<0.01
<0.01
<0.01
<2
<0.20
0.01
<0.01
0.036
<0.01
<0.01
<2
<0.30
<0.01
<0.01
0.028
<0.01
<0.01
<0.10
<0.2
<0.01
<0.01
<0.01
<0.01
<0.01
(continued)
95
-------
TABLE A-12. (Continued)
Sampling Depth Sample
Location Date (m) l Type2
Rio Blanco, 5/18 23
Colo.
Brennan Windmill
t
Rio Blanco, 5/18 23
Colo.
Johnson Artesian Well
Rio Blanco 5/18 23
Colo.
Well RB-D-01
Rio Blanco 5/18 23
Colo.
Well RB-S-03
Type of
Radio-
activity
8»Sr
»°Sr
226Ra
28MJ
23sy
2SiU
2J»pu
219Pu
"Sr
98Sr
2S*U
2SSU
238U
2S8PU
2S9Pu
"Sr
9oSr
2'*U
2SSU
2S8U
238pu
2'9Pu
89Sr
90Sr
2'*U
2JSU
2S.y
2"Pu
2S9Pu
Radioactivity
Cone.
(10-9 yCi/ml)
<35
< 0.6
0.24
9.9
0.16
3.9
< 0.04
< 0.03
< 2.1
< 0.6
0.044
< 0.008
0.022
< 0.04
< 0.04
<40
< 0.7
0.67
0.015
0.30
< 0.03
< 0.02
<41
< 0.7
< 0.03
< 0.01
< 0.02
< 0.03
< 0.02
% of
Cone.
Guide'
<2
<0.2
-
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.2
< .01
< .01
< .01
< .01
< .01
<2
<0.30
<0.01
<0.01
<0.01
<0.01
<0.01
<2
<0.30
<0.01
<0.01
<0.01
<0.01
<0.01
llf depth not shown, water was collected at surface.
222 - Stream, river, or creek
23 - Well
27 - Spring
'Concentration Guide (CG) for drinking water at on-site locations are the
same as those for off-site locations.
See Appendix B for CG's.
96
-------
TABLE A-13. SPECIAL ANALYTICAL RESULTS FOR THE LONG-TERM
HYDROLOGICAL MONITORING PROGRAM - PROJECT DRIBBLE1
Sampl i ng
Location
HMH-1
HMH-2
HMH-3
HMH-4
HMH-5
HMH-6
HMH-7
HMH-8
Date
4/27
7/13
10/11
4/27
7/13
10/11
4/27
7/13
10/11
4/27
7/13
10/11
4/27
7/13
10/11
4/27
7/13
10/11
4/26
7/13
10/11
4/27
7/13
10/11
3H Concentration %
(m) (10-» yd/ml) CG
3.5 450,000
12,000
86,000
3.4 230,000
190,000
190,000
2.7 330
2.7 1,100
2.7 510
1.5 58
120
66
2.4 4,100
2,000
5,000
1.5 260
340
1,800
1.8 4,200
330
1,300
2.7 98
67
69
(continued)
97
-------
TABLE A-13. (Continued)
Sampl i ng
Location
HMH-9
HMH-10
HMH-11
PS-3
Date
4/27
7/13
10/11
4/27
7/13
10/11
4/27
7/13
10/11
4/2
7/13
10/11
*H Concentration %
(m) (10-9 jiCi/ml) CG
1.5 50
61
79
2.4 640
96
150
2.4 98,000
3,700
78,000
33.4
75
420
*Each sample was also analyzed by gamma spectrometry. No gamma-emitting
radionuclides were detected above the MDC of 1 x 10~8 yCi/ml.
2Sample was not collected in April.
98
-------
APPENDIX B. RADIATION PROTECTION STANDARDS
FOR EXTERNAL AND INTERNAL EXPOSURE
99
-------
APPENDIX B. RADIATION PROTECTION STANDARDS
FOR EXTERNAL AND INTERNAL EXPOSURE
TABLE B-l. DOE ANNUAL DOSE COMMITMENT'
Type of Exposure
Dose Limit to Critical
Individuals in Uncontrolled
Area at Points of Maximum
Probable Exposure (rem)
Dose Limit to Suitable
Sample of the Exposed
Population in an
Uncontrolled Area (rem)
Whole Body, gonads
or bone marrow
Other organs
0.5
1.5
0.17
0.5
'Radiation Protection Standards," DOE Manual, Chapter 0524.
TABLE B-2. DOE CONCENTRATION GUIDES (CG'S)1
Sampl i ng
Network or Program Medium
Air Surveillance Network air
Noble Gas and Tritium air
Surveillance Network,
On-NTS
Noble Gas and Tritium air
Surveillance Network,
Off-NTS
Long-Term Hydro! ogical water
Program
Radio-
nuclide
7 Be
9SZr
131!
132Te
IS7Cs
1 *°Ba
""Ce
"Kr
3H
33Xe
8SKr
3H
issXe
3H
89Sr
90Sr
13'Cs
*2SRa
23i»U
235U
2S8U
2 3 B P 1 1
239 Pi 1
CG
(yCi/ml)
l.lxlO-8
3. 3x10-'
3.3xlO-11
l.OxlO-9
1.7x10-"
3.3xlO-»o
l.OxlO-10
l.OxlO-s
5.0x10-*
l.OxlO-'
1.0x10-'
6.7xlO-8
1.0x10-'
3.0x10-3
3.0x10-"
3.0x10-'
2.0x10-
3.0x10-
3.0x10-
3.0x10-
4.0x10-
5.0x10-
5.0x10-
Basis of Exposure
Suitable sample
of the exposed
population in
uncontrolled area
Individual in
controlled area.
Suitable sample
of the exposed
population in
uncontrolled area
Individual in a
controlled or an
uncontrolled area
"'Radiation Protection Standards," DOE Manual, Chapter 0524.
100
-------
EPA DRINKING WATER REGULATIONS FOR RADIONUCLIDES1
Maximum Contaminant Levels for Beta Particles and Photon Radioactivity
from Man-Made Radionuclides in Community Water Systems2
(a) The average annual concentration of beta particle and
photon radioactivity from man-made radionuclides in
drinking water shall not produce an annual dose
equivalent to the total body or any internal organ
greater than 4 millirem/yr.
(b) Except for the radionuclides listed in Table B-3, the
concentration of man-made radionuclides causing 4
mrem total body or organ dose equivalents shall be
calculated on the basis of a 2-liter per day drinking
water intake using the 168 hour data listed in
"Maximum Permissible Body Burdens and Maximum
Permissible Concentration of Radionuclides in Air or
Water for Occupational Exposure," NBS Handbook 69 as
amended August 1963, U.S. Department of Commerce. If
two or more radionuclides are present, the sum of
their annual dose equivalent to the total body or to
any organ shall not exceed 4 millirem/year.
TABLE B-3. AVERAGE ANNUAL CONCENTRATION ASSUMED TO PRODUCE
A TOTAL BODY OR ORGAN DOSE OF 4 MREM/YR
Radionuclide Critical Organ pCi per liter
Tritium Total body 20,000
Strontium-90 Bone marrow 8
'"Drinking Water Regulations Radionuclides." Title 40 Code of Federal
Regulations, Chapter 1, Part 141. Federal Register, Vol. 41, No. 133. U.S.
Government Printing Office, Washington, D. C. July 9, 1976.
Community water system is a public water system which serves a population
of which 70 percent or greater are residents. A public water system is a
system for the provision to the public of piped water for human consumption,
if such system has at least 15 service connections or regularly serves an
average of 25 individuals daily at least 3 months out of the year.
101
-------
APPENDIX C. REPLICATE SAMPLING PROGRAM
102
-------
APPENDIX C. REPLICATE SAMPLING PROGRAM
Purpose
The program was initiated for the purpose of routinely assessing the
errors due to sampling replication and analytical/counting associated with the
collection and analysis of samples obtained from the surveillance networks
maintained around the Nevada Test Site and other sites designated by the
Nevada Operations Office, Department of Energy.
Procedure
The program involved the collection and analysis of replicate samples from
the Air Surveillance Network (ASN), the Noble Gas and Tritium Surveillance
Network (NG & TSN), the Dosimetry Network and the Standby Milk Surveillance
Network (SMSN). Due to difficulties anticipated in obtaining sufficient
quantities of milk for duplicate samples from the Milk Surveillance Network,
duplicate samples were collected during the annual activation of the SMSN.
At least 30 duplicate samples from each network were collected and
analyzed over the report period. Since three thermoluminescent (TLD) cards
consisting of two TLD chips each are used at each station of the Dosimetry
Network, no additional samples were necessary. The following table summarizes
the sampling information for each surveillance network.
TABLE C-l. SAMPLES AND ANALYSES FOR REPLICATE SAMPLING PROGRAM
Surveil-
lance
Network
ASN
NG & TSN
Dosimetry
SMSN
LTHMP
Number of
Sampling
Locations
121
11
78
150
134
Sampl es
Collected
Per Year
8,300
572
312
150
254
Sets of
Replicate
Samples
Collected
533
52
312
-30
-35
Number of
Replicates
Per Set
2
2
4-6
2
2
Sample
Analysis
Gross 3
Y Spectrometry
85Kr, 3H, HTO,
HT,H20
External Y
""K
Gross a, Gross e,
3H
103
-------
There were other analyses for air, milk and water samples that could not
be included in this evaluation due to the fact that there were not a
sufficient number of analytical results available at the time of this report.
Since the sampling distributions of each sample type appeared to be log-normal
from the review of cumulative frequency plots of the results, the variance of
each set of replicate sample results was estimated from the logarithms of the
results in each set.
The variance, s2, of each set of replicate TLD results (n=6) was estimated
from the logarithms of the results by the standard expression,
Since duplicate samples were collected for all other sample types, the
variances, s2, for these types were calculated from s2 = (0.886R)2, where R is
the absolute difference between the logarithms of the duplicate sample
results. For small sample sizes, this estimate of the variance is
statistically efficient (i) and certainly more convenient in calculating than
the standard expression.
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
confidence interval of the expected population geometric variance for each
type of sample analysis. The expressions used are as follows:(2)
n n
i i i
i=l 1=1
n n
Lower Confidence Limit (LCL) =Y^(n -1) (s2)/x2|o.995,V\n -1)}
ii »
Upper Confidence Limit (UCL) = V](n -1) (s2)/x2|0.005,V\n -I)}
*-~i i L-J .j
1=1 1=1
104
-------
LCL <.o2<. UCL
where o2 = the true value of the population geometric variance
n.-l = the degrees of freedom for n samples collected for the ith
replicate sample
s.j2 = the expected geometric variance of the ith replicate sample
s2 = the best estimate of sample geometric variance derived from the
variance estimates of all replicate samples (the expected value
of s2 is a2).
The 99% upper confidence limit for the total error (sampling + analytical/
counting errors) of the geometric mean of any group of samples collected from
a given network was then determined as the geometric mean +2.57s.
The following table lists the expected geometric standard deviation and
its 99% upper confidence limit (UCL) for most analyses.
TABLE C-2. UPPER CONFIDENCE LIMITS OF SAMPLING AND ANALYTICAL/
COUNTING ERRORS
Surveillance
Network
ASN
NG & TSN '
Dosimetry
SMSN
LTHMP
*Snedecor, G.
Analysis
Gross 3
7Be
31I
S2Te
*°Ba
*"Ce
5Kr
H
HTO
HT
Y (TLD)
*°K
Gross a
Gross 3
3H (conv.)
3H (enrich.)
Sets of
Replicate
Samples
Evaluated
533
86
23
13
28
21
44
51
20
21
331
32
38
27
36
50
W. and W. G. Cochran. Statistical
Expected
Geometric
Stnd. Dev.
s
2.03
1.46
1.48
1.53
1.50
1.52
1.088
1.42
2.29
2.84
1.044
1.086
1.55
1.29
1.12
1.34
Methods.
99% UCL
of
Total Error
6.2
2.6
2.8
3.0
2.8
2.9
1.2
2.4
8.4
15
1.1
1.2
3.1
1.9
1.3
2.1
The Iowa State
University Press, Ames, Iowa. 6th ed. 1967.pp. 39-47
105
-------
APPENDIX D. DETECTION OF AIRBORNE RADIOACTIVITY FROM
ATMOSPHERIC NUCLEAR TESTS BY THE PEOPLE'S REPUBLIC OF CHINA
Following the atmospheric nuclear tests by the People's Republic of China
on March 15, 1978, at 0100 hours EST and on December 14, 1978, at 0100 EST,
samples of airborne radioactivity within the Western United States were
obtained from the Air Surveillance Network. Samples were collected to
determine the effect of the Chinese test on the ambient levels of airborne
radioactivity, which are routinely monitored around the Nevada Test Site in
support of underground nuclear tests. From the concentration of radioiodine
observed in the air samples, an estimate of the radiation dose equivalent to
the thyroid gland of a hypothetical infant receptor via inhalation at each
sampling location was calculated. The following is a summary of the
procedures and results.
Procedure
In addition to the 49 active stations of the Air Surveillance Network
(ASN), 67 of the 73 standby stations were activated for the periods March 17
through April 7, 1978, and December 15 through January 5, 1979. All operators
of the active and standby stations were requested to use a charcoal cartridge
behind the particulate filter.
The particulate filters were counted for gross beta radioactivity at 7
days and 14 days after collection to allow for the decay of naturally
occurring radioactivity and for the purpose of extrapolating the concentration
to the midtime of collection. Those samples having a gross beta count greater
than 50 cpm (~1.0 x 10"11 yCi/ml) were analyzed by gamma spectrometry.
Immediately upon receipt and about five days after collection, the filters
selected from 14-21 stations running along a north and south line in the
Network were analyzed for gamma-emitting radionuclides by gamma spectrometry
techniques. The charcoal cartridges were initially counted for gross gamma
radioactivity; those cartridges having a count rate greater than 300 cpm were
then quantified for specific radionuclides.
Results
The airborne concentrations of gross beta radioactivity resulting from the
March Chinese test was more significant than the December Chinese test.
Typical time series plots of the gross beta radioactivity concentrations in
air are shown in Figures D-l and D-2 for Pueblo, Colorado, and Bishop,
California. The standby station at Pueblo had the highest concentration
(1.70 x 10~10 yCi/ml) within the Network. The continuously operating
106
-------
170
12 -.
11-
10-
9-
8-
7 _
x 6-
t 5-
4-
3-
2-
1-
0
54
4
22
V,
v
Jan ' Feb1 Mar' Apr'May'Jun' Jul' Aug'Sep1 Oct 'Nov'Dec1
1978
Figure D-l. Gross Beta Radioactivity Concentrations in
Air at Pueblo, Colorado.
12-
11-
10-
9-
8-
\ 6-
% 5-
4-
3-
2-
1-
n
A
,
L^_
Jan'Feb'Mar'Apr'May'Jun1 Jul 'Aug'Sep1 Oct'Nov'Dec
1978
Figure D-2. Gross Beta Radioactivity Concentrations in
Air at Bishop, California.
107
-------
station with the highest gross beta radioactivity concentration (1.2 x 10~n
yCi/ml) within the Network was at Bishop, California.
As indicated by the results of gamma spectrometry on air samples, fresh
fission products (95Zr, "Mo, 103Ru, 131I, 132Te, 137Cs, llt0Ba, UlCe, and
mCe) and naturally occurring 7Be were detected in various combinations on
the filters. Only ^31I was detected on the charcoal cartridges. Due to
interferences within the gamma spectra, only the radionuclides 7Be, 95Zr,
131I, 132Te, 137Cs, llt0Ba, and lUCe were quantified. Tables D-2 and D-3
summarize the radionuclide concentrations detected in samples collected at all
sampling locations during the year. The locations and sampling periods during
which the maximum concentration of each radionuclide was detected are shown in
the following table:
TABLE D-l. AIR SAMPLING STATIONS HAVING DETECTABLE
RADIONUCLIDE CONCENTRATIONS
Location
Norland, Wyo.
Casper, Wyo.
Casper Wyo.
Seligman, Ariz.
Casper, Wyo.
Tonopah, Nev.
Sampling
Period
3/21-22
3/20-21
3/20-21
5/10-12
3/20-21
5/31-6/2
Radio-
nuclide
95Zr
131 1
132-,-g
l37Cs
111 °Ba
u*Ce
Half-
Life
(days)
65
8.04
3.3
30.1(y)
13
284
Maximum
Cone.
(10- 12 jiCi/ml)
2.1
37
71
0.32
29
0.61
Average
Cone.
(10- 12 viCi/ml)
0.036
1.2
1.8
0.013
0.84
0.028
%
CG*
0.01
4
0.2
0.008
0.3
0.03
*Percent of the Concentration Guide (CG), as specified in DOE Manual, Chapter
0524, for a suitable sample of the exposed population. See Appendix B.
The dates on which these maximum concentrations occurred are indicative that
the 137Cs and the lkkCe concentrations in the troposphere were probably
affected more by the annual increase in airborne radioactive fallout
concentrations resulting from the mixing that occurs at the boundary of the
stratosphere and troposphere during the spring season.
From the concentrations of l31I and 132Te determined in the samples from
each air sampling location, the radiation dose equivalent (D.E.) to the
thyroid gland of an hypothetical, 1-year-old infant receptor was calculated
108
-------
TABLE D-2. 1978 SUMMARY OF ANALYTICAL RESULTS FOR
AIR SURVEILLANCE NETWORK
ACTIVE STATIONS
Sampl i ng
Location
Kingman, Ariz.
Seligman, Ariz.
Baker, Calif.
Bars tow, Calif.
Bishop, Calif.
No.
Days
Detected
312.0
75.9
6.2
7.2
30.0
13.2
47.0
75.0
63.0
7.0
5.0
23.0
10.0
21.0
120.0
77.1
7.1
6.0
27.9
17.2
48.9
58.9
67.9
7.0
6.0
13.0
9.0
20.0
112.0
85.9
13.9
5.0
35.0
16.9
53.0
Type of
Radio-
activity
7Be
95Zp
1S1I
l32Te
lJ7Cs
^°Ba
'"Ce
7Be
95Zr
S1I
3ZTe
37Cs
*°Ba
"Ce
'Be
9SZr
lsll
l32Te
137Cs
'"fea
1%te
I3e
2r
S1
J2Te
3ts
*fea
*te
^e
*Zr
SII
S2Te
37Cs
"Ba
*te
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
0.60
0.16
0.26
0.21
0.035
0.034
0.38
0.70
0.10
0.12
0.16
0.32
0.30
0.35
0.52
0.071
0.16
0.24
0.023
0.26
0.23
0.47
1.2
0.18
0.24
0.023
0.30
0.26
0.61
0.077
1.4
1.6
0.033
1.9
0.32
0.15
0.014
0.057
0.059
0.010
0.017
0.083
0.22
0.021
0.032
0.12
0.013
0.044
0.025
0.078
0.011
0.050
0.068
0.010
0.027
0.031
0.11
0.013
0.029
0.077
0.010
0.036
0.062
0.15
0.019
0.026
0.065
0.012
0.028
0.083
0.19
0.0067
0.0029
0.0029
0.0015
0.0046
0.022
0.01
0.0074
0.0019
0.0024
0.0035
0.0043
0.014
0.084
0.0067
0.0021
0.0024
0.0013
0.0054
0.019
0.042
0.013
0.0024
0.0035
<0.001
0.0041
0.0094
0.10
0.0082
0.0086
0.0079
0.0021
0.012
0.026
(continued)
109
-------
TABLE D-2. (Continued)
Sampl i ng
Location
Death Valley Jet.,
Calif.
Furnace Creek, Calif.
Lone Pine, Calif.
Needles, Calif.
Ridgecrest, Calif.
No.
Days
Detected
132.2
91.9
13.0
6.0
43.9
17.0
32.8
159.1
51.3
9.0
6.0
28.8
11.0
36.9
56.9
44.0
2.0
6.0
32.0
6.0
33.0
84.4
48.5
8.2
6.1
22.1
13.1
26.6
93.4
71.9
7.0
3.0
27.9
10.0
42.9
Type of
Radio-
activity
7 Be
95Zr
131!
132Te
137Cs
^"Ba
^"Ce
7 Be
95Zr
131!
132Te
137Cs
»*«Ba
1%*Ce
7 Be
9SZr
131!
132Te
137Cs
1HOBa
»**Ce
7 Be
95Zr
131!
132Te
1S7Cs
ll|0Ba
»*»Ce
7 Be
9sZr
31!
J2Te
J7Cs
""Ba
**Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
0.59
0.094
0.19
0.32
0.035
0.26
0.35
0.52
0.043
0.17
0.12
0.017
0.17
0.26
0.79
0.11
1.2
0.73
0.060
0.88
0.29
0.51
0.063
0.16
0.18
0.023
0.30
0.19
0.57
0.066
0.3
0.32
0.028
0.54
0.36
0.12
0.012
0.02
0.078
0.012
0.026
0.077
0.071
0.012
0.021
0.077
0.013
0.043
0.069
0.11
0.017
1.2
0.12
0.010
0.050
0.065
0.12
0.014
0.032
0.076
0.010
0.024
0.043
0.11
0.014
0.074
0.14
0.011
0.037
0.063
0.097
0.0074
0.0020
0.0027
0.0021
0.0043
0.016
0.10
0.0036
0.0025
0.0020
0.0012
0.0036
0.016
0.11
0.0096
0.016
0.013
0.0036
0.013
0.032
0.061
0.0039
0.0023
0.0023
<0.001
0.0038
0.010
0.078
0.0066
0.0034
0.0023
0.0016
0.0072
0.019
(continued)
110
-------
TABLE D-2. (Continued)
Sampl i ng
Location
Shoshone, Calif.
Alamo, Nev.
Austin, Nev.
Beatty, Nev.
Blue Eagle Ranch, Nev.
No.
Days
Detected
79.6
51.1
7.0
6.0
23.0
15.2
33.5
111.5
95.2
8.0
5.0
28.3
16.3
46.9
95.9
54.0
4.0
4.9
28.0
6.9
41.0
119.6
81.9
7.0
3.0
30.7
12.0
47.7
121.8
73.9
9.9
5.9
35.0
10.0
39.0
Type of
Radio-
activity
7 Be
ssZr
1S1I
is2Te
1S7Cs
^"Ba
^"Ce
7 Be
9SZr
lsll
1S2Te
137Cs
i»°Ba
^"Ce
7 Be
95Zr
31I
S2Te
S7Cs
»°Ba
""Ce
7 Be
8*Zr
131J
iszje
l»7Cs
""Ba
'"Ce
7 Be
sZr
jij
S2Te
S7Cs
»«Ba
»*Ce
Radioactivity
Concentration (lO"9 uCi/ml)
Max Min Avg
0.52
0.079
0.35
0.21
0.033
0.35
0.23
0.59
0.089
0.34
0.22
0.026
0.20
0.40
0.73
0.055
0.65
0.70
0.036
0.75
0.33
0.59
0.054
0.37
0.37
0.036
0.30
0.31
0.82
0.11
0.13
0.60
0.036
0.36
0.39
0.11
0.019
0.082
0.11
0.010
0.040
0.78
0.12
0.016
0.024
0.13
0.010
0.030
0.065
0.19
0.013
0.070
0.090
0.012
0.055
0.074
0.12
0.014
0.023
0.096
0.013
0.045
0.065
0.12
0.013
0.031
0.061
0.014
0.021
0.11
0.072
0.0055
0.0033
0.0025
0.0013
0.0063
0.014
0.10
0.0086
0.0022
0.0022
0.0014
0.0038
0.020
0.15
0.0058
0.0030
0.0041
0.0023
0.0049
0.0026
0.10
0.0063
0.0022
0.0017
0.0017
0.0036
0.022
0.14
0.0077
0.0020
0.0034
0.0022
0.0030
0.021
(continued)
111
-------
TABLE D-2. (Continued)
Sampl i ng
Location
Blue Jay, Nev.
Caliente, Nev.
Currant Ranch, Nev.
Diablo, Nev.
Duckwater, Nev.
No,
Days
Detected
102.2
87.9
4.0
3.0
15.0
9.2
34.1
121.6
80.6
4.0
5.0
27.9
13.5
22.9
117.0
79.3
4.8
2.9
42.0
13.0
55.1
101.3
84.2
9.1
5.2
36.9
15.1
31.5
105.7
62.9
4.0
6.0
27.0
18.0
31.0
Type of
Radio-
activity
7Be
9sZr
nij
132Te
lJ7Cs
"Ba
ll"Ce
7Be
95Zr
titj
132Te
l97Cs
11M)Ba
ll"Ce
7 Be
95Zr
lsll
132Te
J37Cs
'""Be
""Ce
7 Be
95Zr
131I
132Te
137Cs
l"°Ba
1%*Ce
7 Be
9sZr
iii!
132Te
137Cs
lit0Ba
""Ce
Radioactivity
Concentration (10"9 yCi/ml)
Max Win Avg
1.0
0.089
0.23
0.34
0.026
0.26
0.41
0.78
0.061
0.061
0.055
0.031
0.19
0.27
0.87
0.073
0.15
0.24
0.036
0.36
0.45
0.96
0.14
0.18
0.089
0.047
0.34
0.28
0.55
0.083
0.17
0.20
0.046
0.16
0.26
0.16
0.016
0.094
0.11
0.014
0.041
0.093
0.15
0.017
0.034
0.043
0.014
0.018
0.086
0.15
0.019
0.10
0.13
0.012
0.045
0.087
0.16
0.014
0.061
0.080
0.010
0.064
0.091
0.12
0.017
0.049
0.075
0.012
0.031
0.078
0.097
0.0084
0.0015
0.0020
<0.001
0.0030
0.020
0.11
0.0070
<0.001
<0.001
0.0018
0.0020
0.011
0.14
0.0085
0.0018
0.0014
0.0025
0.0050
0.032
0.095
0.0081
0.0028
0.0013
0.0022
0.0055
0.016
0.099
0.0073
<0.001
0.0028
0.0015
0.0047
0.015
(continued)
112
-------
TABLE D-2. (Continued)
Sampl i ng
Location
Ely, Nev.
Eureka, Nev.
Fallini's Ranch, Nev.
Geyser Ranch, Nev.
Glendale, Nev.
No.
Days
Detected
108.3
60.1
9.0
6.0
38.7
11.0
35.0
110.0
81.6
9.0
5.0
25.0
14.0
56.0
122.0
82.2
11.0
4.0
43.9
12.1
37.9
31.6
74.0
7.0
3.0
18.0
4.0
17.0
91.5
55.2
7.9
7.1
38.9
17.1
38.8
Type of
Radio-
activity
7 Be
95Zr
131!
is2Te
l37Cs
i*oBa
1%"Ce
7 Be
95Zr
1S1I
1S2Te
1S7Cs
111 °Ba
^"Ce
7Be
95Zr
131!
is2Te
1S7Cs
l»«Ba
J**Ce
7Be
95Zr
131!
i32Te
1S7Cs
*»«Ba
""Ce
7 Be
5Zr
31!
s2Te
S7Cs
*°Ba
"Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
1.1
0.088
0.25
0.28
0.045
0.46
0.33
0.84
0.080
0.090
0.11
0.052
0.19
0.54
0.74
0.10
0.17
0.22
0.032
0.24
0.40
1.0
0.14
0.29
0.32
0.035
0.35
0.39
0.81
0.062
0.21
0.21
0.039
0.24
0.23
0.15
0.020
0.030
0.10
0.016
0.035
0.096
0.16
0.015
0.028
0.055
0.014
0.053
0.076
0.17
0.016
0.018
0.15
0.011
0.063
0.095
0.19
0.017
0.031
0.14
0.014
0.10
0.12
0.13
0.012
0.024
0.039
0.012
0.023
0.069
0.12
0.0075
0.0026
0.0026
0.0029
0.0055
0.016
0.13
0.0089
0.0014
0.0011
0.0018
0.0045
0.030
0.14
0.0089
0.0020
0.0020
0.0021
0.0043
0.019
0.087
0.014
0.0043
0.0037
0.0023
0.0054
0.022
0.096
0.0056
0.0023
0.0031
0.0027
0.0052
0.020
(continued)
113
-------
TABLE D-2. (Continued)
Sampling
Location
Goldfield, Nev.
Area 51, NTS, Nev. l
Hiko, Nev.
Indian Springs, Nev.
Las Vegas, Nev.
No.
Days
Detected
114.3
71.9
5.1
0.9
30.0
11.5
37.1
121.6
64.1
2.9
2.0
18.9
2.9
26.3
95.7
100.0
9.0
3.0
32.0
8.0
31.0
117.4
86.0
8.0
6.1
30.0
11.0
33.0
71.7
81.0
8.0
8.0
21.0
8.0
38.9
Type of
Radio-
activity
7 Be
9SZr
ISlj
132Te
137Cs
llM)Ba
'"Ce
7 Be
95Zr
i s i j
l32Te
137Cs
""Ba
^"Ce
7 Be
95Zr
3 *I
32Te
37Cs
*°Ba
**Ce
7 Be
95Zr
13 1 j
132Te
137Cs
'""Ba
'""Ce
7 Be
95Zr
13 1 j
132Te
137Cs
'""Ba
1%*Ce
Radioactivity
Concentration (1Q-9 pCi/ml)
Max Min Avg
0.71
0.092
0.16
0.13
0.062
0.26
0.23
0.64
0.52
0.19
0.25
0.041
0.21
0.30
0.53
0.072
0.16
0.16
0.038
0.29
0.30
0.79
0.10
0.53
0.53
0.040
0.42
0.19
0.88
0.17
0.41
0.40
0.021
0.49
0.20
0.15
0.016
0.029
0.13
0.013
0.023
0.079
0.17
0.014
0.10
0.19
0.012
0.099
0.087
0.13
0.013
0.022
0.096
0.010
0.031
0.10
0.14
0.014
0.030
0.036
0.010
0.032
0.090
0.12
0.012
0.028
0.066
0.011
0.067
0.070
0.098
0.0064
<0.001
<0.001
0.0022
0.0019
0.017
0.14
0.0067
0.0015
0.0016
0.0016
0.0017
0.014
0.084
0.0085
0.0016
<0.001
0.0018
0.0027
0.014
0.11
0.0090
0.0033
0.0032
0.0016
0.0049
0.014
0.060
0.0072
0.0046
0.0044
0.0010
0.0056
0.014
(continued)
114
-------
TABLE D-2. (Continued)
Sampl i ng
Location
Lathrop Wells, Nev.
Lida, Nev.
Lund, Nev.
Mesquite, Nev.
Moapa, Nev.
No.
Days
Detected
92.0
81.0
7.0
5.0
26.0
7.0
29.0
111.9
82.0
9.0
7.0
30.0
11.0
31.0
107.9
87.5
5.0
2.0
30.9
8.9
35.7
132.0
61.0
4.0
3.0
7.0
7.0
17.0
1.9
9.0
0.0
0.0
0.0
0.0
0.0
Type of
Radio-
activity
7Be
9SZr
13 1 j
132Te
lS7Cs
""Ba
^"Ce
7Be
9SZr
13 lj
1J2Te
137Cs
""Ba
'"'Ce
7Be
9SZr
13 lj
132Te
137Cs
111 °Ba
"'Ce
7Be
95Zr
IS lj
132Te
137Cs
ll|0Ba
1%*Ce
7Be
95Zr
IS lj
1S2Te
137Cs
111 °Ba
l**Ce
Radioactivity
Concentration (10~9 jjCi/ml)
Max Min Avg
0.51
0.070
0.17
0.19
0.027
0.28
0.37
0.66
0.19
0.15
0.18
0.032
0.22
0.33
1.8
0.064
0.29
0.22
0.034
0.42
0.30
0.69
0.34
0.11
0.14
0.021
0.19
0.20
0.41
0.043
_-
__
__
--
--
0.14
0.015
0.028
0.048
0.012
0.029
0.082
0.17
0.018
0.086
0.068
0.011
0.070
0.12
0.11
0.015
0.036
0.11
0.011
0.034
0.11
0.14
0.013
0.057
0.11
0.011
0.024
0.069
0.41
0.014
_-
__
__
--
--
0.083
0.0075
0.0013
0.0018
0.0015
0.0033
0.016
0.12
0.0084
0.0030
0.0027
0.0018
0.0054
0.014
0.12
0.0087
0.0018
<0.001
0.0019
0.0034
0.018
0.11
0.0072
0.0011
0.0012
<0.001
0.0019
0.0071
0.072
0.018
--
'__
__
(continued)
115
-------
TABLE 0-2. (Continued)
Sampl i ng
Location
Nyala, Nev.
Pahrump, Nev.
Pioche, Nev.
Round Mountain, Nev.
Scotty's Junction, Nev.
No.
Days
Detected
94.0
61.0
6.0
5.0
24.0
6.0
15.0
140.3
84.4
6.0
6.0
54.2
12.0
47.6
88.8
86.8
8.0
8.0
30.0
8.2
31.0
98.3
78.9
8.9
3.9
35.4
7.9
43.5
114.8
79.7
7.1
7.1
17.0
10.0
31.1
Type of
Radio-
activity
7Be
9sZr
131 j
132Te
l37Cs
"Ba
lH"Ce
7Be
95Zr
13 Ij
l92Te
l37Cs
llt0Ba
l*"Ce
7Be
5Zr
3 Ij
32Te
37Cs
"°Ba
l**Ce
7Be
95Zr
13 Ij
l32Te
l37Cs
l<"Ba
l*-Ce
7Be
95Zr
13 Ij
1S2Te
l37Cs
'* °Ba
'""Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Mi n Avg
0.96
0.094
0.15
0.27
0.032
0.16
0.34
0.62
0.078
0.41
0.45
0.028
0.43
0.31
0.71
0.068
0.12
0.20
0.035
0.25
0.29
1.0
0.12
0.36
0.40
0.047
0.31
0.30
0.53
0.080
0.18
0.25
0.031
0.31
0.27
0.17
0.018
0.076
0.069
0.011
0.075
0.11
0.12
0.014
0.096
0.16
0.010
0.030
0.091
0.13
0.016
0.032
0.070
0.013
0.067
0.068
0.091
0.016
0.033
0.13
0.013
0.026
0.12
0.13
0.013
0.062
0.081
0.014
0.054
0.066
0.010
0.0062
0.0017
0.0019
0.0014
0.0023
0.0076
0.12
0.0071
0.0034
0.0042
0.0027
0.0057
0.019
0.11
0.0092
0.0019
0.0025
0.0021
0.0034
0.016
0.10
0.0086
0.0032
0.0023
0.0022
0.0028
0.22
0.096
0.0068
0.0027
0.0031
0.0010
0.0047
0.013
(continued)
116
-------
TABLE D-2. (Continued)
Sampling
Location
Stone Cabin Ranch, Nev.
Sunnyside, Nev.
Tempi ute, Nev.
Tonopah, Nev.
Tonopah Test Range,
Nev.
No.
Days
Detected
94.6
82.4
4.9
4.0
39.9
12.8
37.9
99.7
95.5
9.0
4.0
35.5
12.0
49.7
80.8
52.7
7.8
4.0
19.7
10.6
19.5
96.0
88.8
7.0
3.0
52.0
10.0
46.0
107.2
71.0
10.1
4.3
36.6
18.3
36.2
Type of
Radio-
activity
7Be
95Zr
1S1J
lS2jg
1S7Cs
1%0Ba
'""Ce
7Be
95Zr
S1I
S2Te
S7Cs
*«Ba
""Ce
7Be
sZr
l!
2Te
7Cs
°Ba
%Ce
7Be
95Zr
13 \l
1S2Te
1J7Cs
^"Ba
*» "Ce
7Be
95Zr
i j n
1S2Te
IS7Cs
111 °Ba
""Ce
Radioactivity
Concentration (10~9 pCi/ml)
Max Min Avg
0.99
0.080
0.18
0.46
0.041
0.39
0.42
0.78
0.083
0.10
0.14
0.045
0.23
0.38
0.64
0.057
0.13
0.53
0.051
0.26
0.36
0.83
0.15
0.15
0.30
1.040
0.24
0.61
1.2
0.11
0.15
0.096
0.041
0.23
0.34
0.19
0.018
0.086
0.18
0.016
0.049
0.097
0.21
0.013
0.030
0.053
0.013
0.052
0.11
0.096
0.015
0.038
0.094
0.010
0.074
0.081
0.071
0.017
0.032
0.25
0.011
0.051
0.11
0.10
0.016
0.025
0.071
0.012
0.022
0.094
0.11
0.0095
0.0018
0.0035
0.0027
0.0052
0.022
0.12
0.0093
0.0014
0.0011
0.0023
0.0037
0.026
0.10
0.0067
0.0023
0.0039
0.0014
0.0058
0.013
<0.1
0.0094
0.0015
0.0023
0.0034
0.0033
0.029
0.14
0.0077
0.0023
0.0013
0.0027
0.0057
0.024
(continued)
117
-------
TABLE D-2. (Continued)
Sampl i ng
Location
Cedar City, Utah
Delta, Utah
Garrison, Utah
Mil ford, Utah
St. George, Utah
No. Type of
Days Radio-
Detected activity
109.7
66.0
4.0
1.0
21.9
4.0
26.1
67.3
68.3
3.0
3.0
25.2
5.5
39.3
129.0
80.0
6.0
4.0
24.0
10.0
41.0
53.6
53.7
7.6
10.2
13.2
10.2
17.2
119.0
88.5
9.0
4.9
33.8
14.0
47.3
7 Be
9SZr
131 I
1S2Te
137Cs
""Ba
'""Ce
7 Be
9SZr
i»M
132Te
137 Cs
»»°Ba
l»»Ce
7 Be
95 Zr
13M
132Te
137 Cs
1%0Ba
^"Ce
7 Be
sZr
31 J
32Te
37 Cs
*0Ba
**Ce
7 Be
95 Zr
IBlj
192 Te
157 Cs
1%0Ba
l"Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
0.82
0.087
0.091
0.21
0.032
0.098
0.29
2.6
0.16
0.076
0.13
0.034
0.13
0.51
0.63
0.12
0.15
0.15
0.026
0.24
0.27
0.99
0.073
0.11
0.17
0.028
0.14
0.51
0.74
0.079
0.12
0.25
0.081
0.19
0.32
0.15
0.018
0.042
0.21
0.014
0.036
0.098
0.19
0.012
0.076
0.13
0.010
0.10
0.075
0.14
0.014
0.053
0.060
0.013
0.039
0.092
0.12
0.017
0.059
0.041
0.010
0.047
0.15
0.13
0.016
0.050
0.055
0.012
0.040
0.081
0.13
0.0073
<0.001
<0.001
0.0013
<0.001
0.012
0.12
0.013
<0.001
0.0016
0.0020
0.0026
0.030
0.14
0.0095
0.0014
<0.001
0.0013
0.0031
0.020
0.13
0.012
0.0035
0.0054
0.0013
0.0058
0.024
0.11
0.0078
0.0018
0.0015
0.0025
0.0037
0.023
'Also known as Groom Lake.
118
-------
TABLE D-3. 1978 SUMMARY OF ANALYTICAL RESULTS FOR
AIR SURVEILLANCE NETWORK
STANDBY STATIONS
Sampl i ng
Location
Phoenix, Ariz.
Winslow, Ariz.
Little Rock, Ark.
Indio, Calif.
Denver, Colo.
No. Type of
Days Radio-
Detected activity
13.9
19.1
9.0
7.0
0.0
7.0
0.0
8.7
6.4
8.0
3.0
0.0
8.0
0.0
8.8
7.1
9.1
8.1
4.0
9.1
0.0
8.0
15.4
7.0
7.0
5.1
10.0
2.0
12.0
8.0
14.0
8.0
0.0
22.0
0.0
7Be
9 Zr
1 'I
1 2Te
1 7Cs
1 °Ba
""Ce
7Be
9sZr
13 lj
132Te
137Cs
1%0Ba
l**Ce
7Be
95Zr
IS 1 j
132Te
137Cs
ll"Ba
""Ce
7 Be
Zr
ll
2Te
7Cs
°Ba
"Ce
7 Be
93Zr
13 1 j
132Te
137Cs
"'Ba
1%*Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
0.40
0.061
0.23
0.19
__
0.33
0.51
0.074
0.15
0.24
«._
0.33
0.77
0.083
7.9
9.8
0.030
5.8
0.45
0.12
0.31
0.31
0.019
0.84
0.12
0.82
0.094
18
25
__
18
--
0.16
0.014
0.038
0.097
__
0.14
--
0.19
0.046
0.038
0.17
__
0.035
0.18
0.037
0.10
0.047
0.013
0.046
0.068
0.018
0.056
0.074
0.011
0.025
0.12
0.23
0.035
0.051
0.093
__
0.021
--
0.060
0.011
0.020
0.017
__
0.031
--
0.041
0.0062
0.011
0.0095
.._
0.020
--
0.059
0.0068
0.23
0.29
0.0012
0.18
0.037
0.011
0.018
0.022
0.0013
0.029
0.0046
0.084
0.0075
0.61
0.81
__
0.60
--
(continued)
119
-------
TABLE D-3. (Continued)
Sampl i ng
Location
Durango, Colo.
Grand Junction,
Colo.
Pueblo, Colo.
Boise, Idaho
Idaho Falls,
Idaho
No. Type of
Days Radio-
Detected activity
8.9
9.9
6.4
1.9
2.4
6.4
3.2
14.1
4.1
8.0
2.9
0.0
8.0
0.0
3.0
4.1
8.0
8.0
0.0
9.2
0.0
13.1
7.0
2.0
0.0
0.0
5.0
0.0
14.1
14.9
9.3
4.0
2.3
11.2
0.0
7Be
95Zr
131!
132Te
1S7Cs
l"°Ba
*^Ce
7Be
9!Zr
131!
132Te
1J7Cs
»*0Ba
»»*Ce
^e
*Zr
S1I
S2Te
37Cs
"B3
"Ce
Be
9SLr
IS1
1S2Te
I3£s
11HBa
"te
7Be
sZr
S1I
32Te
S7Cs
*°Ba
""Ce
Radioactivity
Concentration (10"9 yCi/ml)
Max Min Avg
1.2
0.13
0.90
1.8
0.013
1.4
0.087
0.35
0.052
0.15
0.14
--
0.14
1.6
0.095
21
34
--
18
0.50
0.070
0.037
_-
0.18
0.46
0.13
0.33
0.83
0.021
0.40
0.24
0.022
0.043
0.29
0.013
0.077
0.087
0.21
0.043
0.030
0.12
--
0.055
0.28
0.027
0.071
0.12
--
0.13
--
0.16
0.022
0.037
--
--
0.074
0.13
0.020
0.022
0.11
0.021
0.065
--
0.081
0.011
0.022
0.036
<0.001
0.041
0.0051
0.061
0.0031
0.0092
0.0059
--
0.011
0.046
0.0040
0.74
1.1
--
0.66
--
0.069
0.0043
0.0014
_-
--
0.0089
--
0.073
0.013
0.019
0.022
<0.001
0.028
--
(continued)
120
-------
TABLE D-3. (Continued)
Sam pi i ng
Location
Mountain Home,
Idaho
Pocatello, Idaho
Preston, Idaho
Twin Falls, Idaho
Iowa City, Iowa
No. Type of
Days Radio-
Detected activity
12.0
8.0
9.8
9.8
5.0
13.9
0.0
15.8
16.4
7.0
4.9
2.0
12.0
3.0
15.0
8.0
8.1
2.0
2.0
9.1
0.0
3.0
15.0
13.0
9.0
0.0
20.0
3.0
8.0
2.7
8.9
4.0
3.0
10.9
3.0
7 Be
9sZr
1S1I
132Te
1S7Cs
""Ba
*** Ce
7 Be
9sZr
131]
192Te
l97Cs
""Ba
1H*Ce
7 Be
95Zr
i.i!
192Te
l37Cs
l"°Ba
""Ce
7 Be
95Zr
131!
192Te
197Cs
""Ba
"*Ce
7 Be
9sZr
131!
i32Te
1S7Cs
^'Ba
l%*Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Mi n Avg
0.42
0.041
0.25
0.36
0.017
0.29
--
0.72
0.088
0.082
0.11
0.023
0.15
0.094
0.45
0.053
0.048
0.056
0.017
0.097
0.26
0.036
0.47
0.11
-_
0.12
0.092
0.26
0.077
0.59
0.90
0.013
0.56
0.076
0.23
0.014
0.046
0.080
0.016
0.055
0.13
0.022
0.048
0.058
0.023
0.035
0.094
0.22
0.047
0.038
0.056
0.017
0.065
0.26
0.018
0.028
0.063
--
0.029
0.092
0.11-
0.031
0.022
0.044
0.013
0.027
0.076
0.062
0.0040
0.015
0.022
0.0014
0.028
0.11
0.012
0.0080
0.0073
<0.001
0.020
0.0054
0.076
0.0072
0.0065
0.0020
<0.001
0.014
0.012
0.0068
0.017
0.011
0.018
0.0043
0.028
0.0023
0.030
0.030
<0.001
0.032
0.0044
(continued)
121
-------
TABLE D-3. (Continued)
Sampl i ng
Location
Sioux City, Iowa
Dodge City, Kans.
Lake Charles, La.
Monroe, La.
New Orleans, La.
No. Type of
Days Radio-
Detected activity
10.8
6.0
12.0
5.0
2.0
12.0
0.0
24.0
6.0
12.0
12.0
0.0
17.0
2.0
9.3
17.1
9.9
7.9
0.0
11.9
2.9
22.9
11.8
9.5
6.8
2.0
12.0
0.0
5.1
13.7
11.0
8.9
2.0
17.8
2.0
7Be
95Zr
13 lj
13 Me
lS7Cs
111 °Ba
'""Ce
7Be
95Zr
13 Ij
132Te
l37Cs
111 °Ba
111 *Ce
7Be
95Zr
3 *I
32Te
37Cs
*°Ba
""Ce
7Be
95Zr
13 Ij
l32Te
l37Cs
""63
""te
7Be
95Zr
1S1J
132Te
1S7Cs
111 °Ba
111 te
Radioactivity
Concentration (10~9 pCi/ml)
Max Min Avg
0.39
0.027
1.9
3.3
0.019
2.1
0.37
0.11
1.6
0.24
__
1.5
0.16
0.33
0.038
0.29
0.24
__
0.42
0.093
0.59
0.032
3.6
4.1
0.016
3.1
0.22
0.11
0.84
0.93
0.014
0.73
0.12
0.14
0.022
0.014
0.084
0.019
0.025
0.16
0.030
0.045
0.042
__
0.027
0.16
0.19
0.016
0.045
0.046
__
0.022
0.093
0.13
0.018
0.027
0.069
0.016
0.045
0.15
0.013
0.027
0.031
0.014
0.034
0.12
0.065
0.0028
0.055
0.078
<0.001
0.058
--
0.088
0.0044
0.054
0.063
__
0.053
0.0051
0.046
0.0094
0.026
0.020
__
0.04
0.0056
0.085
0.0046
0.065
0.073
0.00051
0.074
0.019
0.012
0.046
0.037
<0.001
0.058
0.0050
(continued)
122
-------
TABLE D-3. (Continued)
Samp! i ng
Location
Minneapolis, Minn.
Clayton, Mo.
Joplin, Mo.
St. Joseph, Mo.
Bil lings, Mont.
No. Type of
Days Radio-
Detected activity
9.0
1.0
4.8
1.9
0.0
7.8
0.0
14.2
19.0
13.0
5.0
0.0
17.0
3.0
13.0
7.0
12.9
6.3
0.0
11.1
4.9
13.4
9.1
14.1
11.1
0.0
13.1
3.0
0.0
1.9
1.9
0.0
2.0
1.9
0.0
'Be
5Zr
31!
s2Te
"Cs
*°Ba
">Ce
7Be
95Zr
131!
132Te
ls'Cs
""Ba
»»*Ce
'Be
*Zr
31J
32Te
"Cs
»°Ba
""Ce
'Be
9sZr
31!
JZTe
"Cs
*°Ba
»*Ce
'Be
*Zr
31!
"Te
"Cs
*"Ba
»*ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
0.29
0.059
1.1
1.9
--
1.0
0.37
0.033
2.7
2.8
--
2.1
0.060
1.7
0.064
11
10
--
8.2
0.10
0.45
0.16
0.64
1.1
--
0.92
0.068
__
0.046
0.062
--
0.025
0.092
--
0.19
0.059
0.055
0.28
0.021
0.10
0.019
0.030
0.053
--
0.034
0.060
0.18
0.040
0.062
0.085
__
0.13
0.096
0.11
0.025
0.054
0.061
0.095
0.068
_
0.046
0.062
__
0.025
0.092
_-
0.037
0.0010
0.027
0.037
0.026
--
0.051
0.0088
0.093
0.0086
--
0.074
0.0030
0.92
0.0066
0.020
0.25
__
0.24
0.0097
0.039
0.010
0.052
0.045
--
0.075
0.0027
0.0035
0.0046
__
0.0020
0.0069
--
(continued)
123
-------
TABLE D-3. (Continued)
Samp] i ng
Location
Bozeman, Mont.
Missoula, Mont.
North Platte,
Nebr.
Battle Mountain,
Nev.
Currant Maint.
Sta., Nev.
No. Type of
Days Radio-
Detected activity
5.1
7.7
13.0
7.1
2.0
12.1
0.0
16.1
12.3
14.0
9.8
0.0
17.0
0.0
13.0
11.1
14.0
8.0
0.0
14.0
0.0
16.1
6.0
4.0
1.9
3.1
12.9
0.0
2.3
17.2
8.0
5.0
0.0
8.0
0.0
7Be
95Zr
131!
132Te
1S7Cs
""Ba
'"Ce
7Be
9SZr
131J
1S2Te
1S7Cs
l"0Ba
l-"»Ce
7Be
9SZr
131J
132Te
lS7Cs
i-oBa
i^Ce
7Be
95Zr
131!
nzTe
l37Cs
1 * «Ba
'"Ce
7Be
95Zr
13 1J
132Te
1S7Cs
""Be
'"Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
0.35
0.032
9.2
6.9
0.016
2.3
0.39
0.055
4.1
5.0
2.9
0.31
0.032
12
14
--
8.2
0.42
0.062
0.058
0.040
0.016
0.15
0.56
0.092
0.14
0.23
__
0.28
--
0.010
0.020
0.073
0.043
0.016
0.079
0.23
0.026
0.029
0.032
0.048
0.16
0.020
0.030
0.057
--
0.032
0.37
0.042
0.054
0.040
0.016
0.050
--
0.56
0.026
0.067
0.11
.. .
0.057
0.017
0.0034
0.29
0.21
<0.001
0.12
0.076
0.0058
0.12
0.11
__
0.089
0.060
0.0056
0.28
0.33
--
0.21
--
0.12
0.0052
0.0040
0.0013
<0.001
0.019
0.041
0.025
0.024
0.030
_ _
0.035
__
(continued)
124
-------
TABLE D-3. (Continued)
Sampl i ng
Location
Currie, Nev.
Elko, Nev.
Fall on, Nev.
Frenchman Sta. ,
Nev.
Lovelock, Nev.
No. Type of
Days Radio-
Detected activity
5.9
16.4
8.0
6.0
3.0
7.0
7.0
7.0
15.9
4.9
1.9
0.0
8.1
0.0
16.8
14.0
7.2
5.2
0.0
5.2
2.0
17.9
11.8
8.0
6.9
2.9
12.9
0.0
28.7
11.3
6.0
4.1
3.5
7.0
2.0
7 Be
95Zr
131!
i32Te
lS7Cs
l*°Ba
""Ce
7 Be
9SZr
131!
1S2Te
1)7Cs
1%0Ba
»"Ce
7Be
9sZr
131!
J2Te
S7Cs
*°Ba
">Ce
Be
5Zr
31!
132Te
lS7Cs
111 °Ba
l"Ce
7Be
9 Zr
1 ll
1 2Te
1 7Cs
1 °Ba
'"Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Win Avg
0.51
0.085
0.053
0.13
0.012
0.15
0.15
0.27
0.073
0.16
0.11
_-
0.22
0.47
0.042
0.21
0.25
__
0.27
0.13
0.70
0.082
0.24
0.32
0.013
0.29
0.61
0.13
0.18
0.15
0.015
0.32
0.16
0.14
0.013
0.023
0.050
0.012
0.034
0.080
0.21
0.024
0.049
0.11
--
0.084
0.23
0.018
0.035
0.091
--
0.098
0.13
0.21
0.020
0.063
0.081
0.013
0.046
0.18
0.023
0.060
0.11
0.015
0.11
0.16
0.028
0.012
0.0056
0.011
<0.001
0.012
0.016
0.036
0.015
0.011
0.0048
0.026
0.092
0.0066
0.011
0.012
--
0.015
0.0043
0.12
0.0086
0.014
0.019
<0.001
0.025
0.15
0.0077
0.0092
0.0072
<0.001
0.017
0.0043
(continued)
125
-------
TABLE D-3. (Continued)
Sampling
Location
Reno, Nev.
Warm Springs, Nev.
Wells, Nev.
Winnemucca, Nev.
Albuquerque,
N. Hex.
No. Type of
Days Radio-
Detected activity
12.0
0.0
0.0
0.0
0.0
0.0
0.0
3.0
17.2
6.0
3.0
0.0
13.8
0.0
19.0
9.0
5.0
3.0
0.0
11.0
3.0
12.1
10.0
1.0
0.0
5.0
1.0
0.0
13.1
14.9
5.9
6.1
0.0
16.0
0.0
7 Be
95Zr
IS 1 j
132Te
l37Cs
""Ba
'""Ce
7Be
95Zr
IS Ij
132Te
1S7Cs
""Ba
ll"Ce
7Be
95Zr
13 lj
l32Te
l37Cs
" °Ba
""Ce
7Be
95?r
13 I
13 *Te
»'7£S
1 * V.
Ce
'Be
5Zr
3 'I
32Te
37Cs
""tea
"Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
0.42
_-
--
__
__
_ _
0.52
0.092
0.19
0.24
._
0.24
1.0
1.1
0.36
0.22
--
1.1
0.10
2.7
0.052
0.089
--
0.016
0.21
1.2
0.10
0.12
0.19
--
0.35
--
0.18
__
_-
__
__
__
0.28
0.028
0.046
0.090
__
0.021
0.037
0.033
0.12
0.10
--
0.067
0.10
0.21
0.026
0.089
--
0.014
0.21
0.18
0.014
0.033
0.054
--
0.024
--
0.10
--
__
__
__
0.021
0.015
0.011
0.011
__
0.026
0.16
0.024
0.016
0.0074
--
0.052
0.0053
0.14
0.0077
0.0018
--
0.0015
0.0041
0.060
0.0086
0.0046
0.0071
0.019
--
(continued)
126
-------
TABLE D-3. (Continued)
Sampl i ng
Location
Carlsbad, N. Mex.
Muskogee, Okla.
Norman, Okla.
Burns, Oreg.
Medford, Oreg.
No. Type of
Days Radio-
Detected activity
14.2
16.6
10.8
12.8
0.0
9.7
0.0
28.7
16.0
15.0
10.0
0.0
18.0
0.0
7.0
14.1
14.9
9.0
0.0
15.9
0.0
18.0
7.0
6.0
3.0
0.0
5.0
2.0
9.1
14.7
3.0
0.0
0.0
3.0
0.0
7Be
9SZr
31I
32-j-g
37Cs
%0Ba
"Ce
7Be
9 Zr
1 IT
1 2Te
1 7Cs
1 °Ba
»»»Ce
7Be
9SZr
13 l!
132jg
1S7Cs
1%0Ba
l%l>Ce
7Be
9SZr
131!
1S2Te
lS7Cs
^'Ba
"*Ce
7Be
95Zr
lsll
1 32Jg
1$7Cs
l%0Ba
l"Ce
Radioactivity
Concentration (10~9 yCi/ml)
Max Min Avg
0.41
0.094
0.33
0.25
--
0.31
--
0.34
0.16
8.9
11
--
6.9
0.2'i
0.069
4.5
4.0
3.2
1.3
0.070
0.083
0.22
__
0.17
0.12
0.37
0.049
0.035
_-
0.055
0.10
0.016
0.027
0.056
--
0.036
0.081
0.019
0.028
0.12
--
0.026
0.23
0.024
0.041
0.097
0.061
0.078
0.034
0.073
0.11
__
0.068
0.12
0.020
0.027
0.035
--
0.055
0.062
0.013
0.026
0.023
--
0.036
0.094
0.012
0.19
0.22
0.17
--
0.041
0.014
0.14
0.14
0.16
0.11
0.0050
0.0073
0.0072
__
0.011
0.0037
0.038
0.0073
0.0014
--
--
0.0022
--
(continued)
127
-------
TABLE D-3. (Continued)
Sampl i ng
Location
Aberdeen, S. Dak.
Rapid City, S. Dak.
Abilene, Tex.
Amarillo, Tex.
Austin, Tex.
No. Type of
Days Radio-
Detected activity
18.0
5.0
4.0
2.0
0.0
5.0
0.0
7.7
16.7
13.6
5.9
0.0
9.5
0.0
13.2
11.9
13.0
12.0
3.1
18.1
0.0
20.8
12.0
7.0
7.0
0.0
7.0
0.0
16.3
18.7
12.0
8.0
3.7
17.0
1.7
7 Be
9SZr
131!
132Te
1S7Cs
""63
""Ce
7 Be
95Zr
i3ij
lsaTe
137Cs
1I>0Ba
^-Ce
7 Be
9SZr
1S1I
M2Te
137Cs
"Ba
l*%Ce
7 Be
95Zr
ISII
132Te
1S7Cs
l*°Ba
'""Cc
7 Be
95Zr
1J1I
132je
137Cs
"Ba
111 *Ce
Radioactivity
Concentration (10"9 yCi/ml)
Max Mi n Avg
0.53
0.11
0.50
1.0
--
0.62
0.69
0.082
12
13
--
7.7
0.42
0.15
5.2
6.0
0.010
3.9
0.72
0.068
1.9
1.5
__
1.3
0.39
0.11
0.46
0.36
0.020
0.71
0.088
0.14
0.026
0.058
0.61
--
0.039
0.16
0.018
0.027
0.15
0.054
0.094
0.022
0.14
0.13
0.010
0.043
0.13
0.018
0.095
0.086
0.063
0.16
0.025
0.087
0.18
0.015
0.065
0.088
0.068
0.0036
0.016
0.024
--
0.017
--
0.035
0.0081
0.30
0.30
0.19
0.045
0.011
0.14
0.15
<0.001
0.15
0.13
0.0078
0.180
0.064
__
0.057
0.064
0.013
0.047
0.027
<0.001
0.069
0.0020
(continued)
128
-------
TABLE D-3. (Continued)
Sampl i ng
Location
Fort Worth, Tex.
Bryce Canyon, Utah
Capitol Reef, Utah
Dug way, Utah
Enterprise, Utah
No. Type of
Days Radio-
Detected activity
13.0
6.0
3.0
3.0
0.0
5.9
0.0
16.1
3.0
5.0
5.0
0.0
5.0
0.0
28.8
11.0
6.0
4.0
2.0
10.0
0.0
4.0
13.7
5.0
2.5
0.0
10.5
0.0
21.0
12.0
5.0
2.0
0.0
9.0
0.0
7Be
95Zr
114
132Te
1S7Cs
1%0Ba
'"Ce
7Be
95Zr
11 IT
lS2-|-e
lS7Cs
"°Ba
l"Ce
7Be
9SZr
131T
ls2Te
lS7Cs
"°Ba
1%*Ce
7Be
"Zr
13 IT
132je
1S7Cs
l*'Ba
'"Ce
7Be
95Zr
131T
lS2Te
lS7Cs
l*°Ba
l"Ce
Radioactivity
Concentration (10"* yCi/ml)
Max Mi n Avg
0.27
0.036
3.8
7.2
--
4.4
0.41
0.053
0.11
0.12
__
0.30
0.55
0.082
0.30
0.18
0.035
0.28
0.39
0.096
0.13
0.058
--
0.20
0.85
0.12
0.12
0.13
_-
0.29
0.18
0.018
0.092
0.12
0.040
0.30
0.053
0.053
0.091
_-
0.18
0.28
0.028
0.056
0.060
0.035
0.048
0.33
0.024
0.028
0.058
--
0.075
0.18
0.050
0.058
0.13
__
0.12
--
0.070
0.0032
0.17
0.27
--
0.17
0.14
0.0041
0.011
0.014
_-
0.029
0.16
0.0092
0.014
0.0061
0.0011
0.016
0.045
0.017
0.0078
0.0042
--
0.031
0.15
0.014
0.0077
0.0041
--
0.025
(continued)
129
-------
TABLE D-3. (Continued)
Sam pi i ng
Location
Logan, Utah
Monticello, Utah
Parowan, Utah
Provo, Utah
Salt Lake City,
Utah
No. Type of
Days Radio-
Detected activity
13.2
14.0
7.9
2.9
0.0
13.0
3.0
9.2
9.8
5.0
1.0
0.0
7.0
0.0
15.1
5.0
0.0
0.0
0.0
2.0
0.0
15.1
12.0
3.8
0.0
6.1
6.8
2.0
17.1
7.8
7.1
0.0
0.0
9.0
0.0
7Be
9SZr
131J
132Jg
137Cs
11>0Ba
""Ce
'Be
95Zr
ls ll
132-J-g
137Cs
111 °Ba
'""Ce
7Be
*Zr
3 4
S2Te
S7Cs
%0Ba
**Ce
7Be
9sZr
1*4
132Te
1S7Cs
1%0Ba
'""Ce
7Be
95Zr
134
1S2Te
lS7Cs
1*°Ba
ll">Ce
Radioactivity
Concentration (10~9 uCi/ml)
Max Min Avg
0.49
0.068
0.10
0.13
0.19
0.079
0.82
0.099
0.13
0.13
--
0.23
0.45
0.091
--
--
--
0.068
0.87
0.094
0.13
_-
0.025
0.25
0.180
0.70
0.67
0.15
_-
--
0.13
0.23
0.021
0.033
0.071
0.076
0.079
0.19
0.030
0.053
0.13
--
0.049
0.12
0.021
--
--
0.068
0.36
0.094
0.083
_-
0.013
0.075
0.180
0.28
0.025
0.053
--
--
0.041
--
0.08
0.011
0.0091
0.0046
0.025
0.0041
0.063
0.0093
0.0086
0.0025
_-
0.013
0.097
0.0034
_-
--
--
0.0027
0.095
0.0080
0.0036
0.0014
0.014
0.0043
0.13
0.0075
0.011
__
__
0.018
(continued)
130
-------
TABLE D-3. (Continued)
Sampling
Location
Rock Springs, Wyo.
Worland, Wyo.
No. Type of
Days Radio-
Detecttd activity
7.0
6.0
6.0
6.0
8.1
12.0
0.0
20.7
11.0
15.0
6.0
0.0
20.0
5.0
7Be
9SZr
IS Ij
13 ^Te
137Cs
111 °Ba
l*te
7Be
95Zr
13 lj
ls*Te
l37Cs
111 °Ba
"te
Radioactivity
Concentration (10~9yCi/ml)
Max Min Avg
0.82
0.090
0.92
1.8
0.024
0.79
0.73
2.1
27
43
__
20
0.17
0.20
0.025
0.063
0.078
0.013
0.045
0.11
0.023
0.030
0.12
__
0.019
0.11
0.065
0.0054
0.046
0.063
0.0029
0.056
--
0.081
0.036
0.47
0.70
__
0.36
0.0099
for each sampling location*. The calculated D.E.'s for each sampling location
are shown in Figures D-3 and D-4 with isopleth lines for the D.E.'s of 0.01
mrem and 0.1 mrem. The highest infant thyroid dose equivalent was estimated
to be 4.0 mrem for the samples collected at Casper, Wyoming. This dose is 0.8
percent of the Radiation Protection Standard of 500 mrem for the general
population, as specified by the DOE Manual, Chapter 0524.
*Calculational procedures were the same as those specified in Appendix B,
"Final Report of Off-Site Surveillance for the Baneberry Event," Report No.
SWRHL-107r. Available from National Technical Information Service, U.S.
Dept. of Commerce, Springfield, VA 22161. Feb. 1972.
132
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0.051
0.029
0.012
0.021
0.031
0.026
f\ f\
W
§
0.057
S
0.066
,/^U
0.047 o
0.037 °
5 0.037 UUOD
0,048 °-044
0.035 n noo
0.045 °-022
0.039 0.038
0.036 0.035
0.054 0.040 I
°-017 0.039 |
0.041 °'°33 0.012
0.049
0.025
0.062
0.047 v
0.048
^0.078
0.063s
0.063
Numbers represent estimated thyroid
dose equivalent (mrem) to the thyroid
gland of hypothetical infant receptor
with one-gram thyroid weight.
* represents results which are low
due to incomplete sampling.
Q
i
Scale in Miles
50 100
150
50 100 150
Scale in Kilometers
200
Figure D-3. Infant Thyroid Dose Equivalents (mrem) Estimated from Air
Sampling Results of Air Surveillance Network, (Nevada),
March-April 1978.
133
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0.047 0.039 0.025 V
Numbers represent estimated
close equivalent (mrem) to the
thyroid gland of a hypothetical
infant receptor with one-gram
thyroid weight. * represents
results which are low due to
incomplete sampling.
I I \
010 200 400
Kilometers
Figure D-4. Infant Thyroid Dose Equivalents (mrem) Estimated from Air
Sampling Results of Air Surveillance Network (Western
United States), March-April 1978.
134
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APPENDIX E. LIST OF ABBREVIATIONS AND SYMBOLS
urn micrometer
yrem micro-rotgen-equivalent-man
uCi/g microcurie per gram
uCi/ml microcurie per milliliter
AEC Atomic Energy Commission
ASN Air Surveillance Network
C temperature in Celsius
CG Concentration Guide
Ci Curie
cm centimeter
CP-1 Control Point One
CY Calendar Year
D.E. Dose Equivalent
DOE U.S. Department of envergy
EMSL-LV Environmental Monitoring and Support Laboratory-
Las Vegas
EPA U.S. Environmental Protection Agency
ERDA Energy Research and Development Administration
ERDA/NV Energy Research and Development Administration/
Nevada Operations Office
ft feet
GZ Ground Zero
h hour
kg kilogram
km kilometer
kt kiloton
LCL lower confidence limit
LLL Lawrence Livermore Laboratory
LTHMP Long-Term Hydrological Monitoring Program
m meter
MDC minimum detectable concentration
mm millimeter
mrem/y milli-rontgen-equivalent-man per year
mrem/d milli-rpntgen-equivalent-man per day
mR milli-rpntgen
mR/h milli-rbntgen per hour
MSL Mean Sea Level
MSM Milk Surveillance Network
nCi nanocurie
NTS Nevada Test Site
135
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PHS Public Health Service
pCi picocurie
SMSN Standby Milk Surveillance Network
TLD thermoluminescent dosimeter
UCL Upper Confidence Limit
USGS United States Geological Survey
WSN ' Water Surveillance Network
y year
3H tritium or hydrogen-3
HT tritiated hydrogen
HTC tritiated water
CHaT tritiated methane
Ba barium
Be berylium
Cs cesium
I iodine
K potassium
Kr krypton
Pu plutonium
Ra radium
Ru ruthenium
Sr strontium
Te tellurium
U uranium
Xe xenon
Zr zirconium
136
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