NERC-LV-539-39 NERC-LV-539-39
ENVIRONMENTAL MONITORING REPORT FOR THE NEVADA TEST SITE
AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS
January through December 1974
by the
Monitoring Applications Laboratory
National Environmental Research Center
U. S. ENVIRONMENTAL PROTECTION AGENCY
Las Vegas, Nevada
Published May 1975
This work performed under a Memorandum of
Understanding No. AT(26-l)-539)
for the
U. S. ENERGY RESEARCH & DEVELOPMENT ADMINISTRATION
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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
United States Energy Research and Development Administration,
nor any of their employees, nor any of their contractors, sub-
contractors, or their employees, make any warranty, express or
implied, or assume any legal liability or responsibility for
the accuracy, completeness or usefulness of any information,
apparatus, product or process disclosed, or represent 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 $5.45; microfiche $2.25
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NERC-LV-539-39 NERC-LV-539-39
ENVIRONMENTAL MONITORING REPORT FOR THE NEVADA TEST SITE
AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS
January through December 1974
by the
Monitoring Applications Laboratory
National Environmental Research Center
U. S. ENVIRONMENTAL PROTECTION AGENCY
Las Vegas, Nevada
Published May 1975
This work performed under a Memorandum of
Understanding No. AT(26-l)-539)
for the
U. S. ENERGY RESEARCH & DEVELOPMENT ADMINISTRATION
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PREFACE
The Atomic Energy Commission (AEC) has used the Nevada Test Site (NTS)
from January 1951 through January 19, 1975, as an area for conducting nuclear
detonations, nuclear rocket-engine development, nuclear medicine studies, and
miscellaneous nuclear and non-nuclear experiments. Beginning on January 19,
1975, these responsibilities were transferred to the newly formed Energy
Research and Development Administration (ERDA). Atmospheric nuclear tests
were conducted periodically from 1951 through October 30, 1958, at which time
a testing moratorium was implemented. Since September 1, 1961, in accordance
with the limited test ban treaty, 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 and five nuclear
earth-cratering experiments conducted under the Plowshare program.
The U. S. Public Health Service (PHS) from 1953 through 1970 and, since
1970, the U. S. Environmental Protection Agency (EPA) have maintained facili-
ties at the NTS or in Las Vegas, Nevada, for the purpose of providing an Off-
Site Radiological Safety Program for the nuclear testing program. Prior to
1953, this program was performed by the Los Alamos Scientific Laboratory and
by U. S. Army personnel. Although off-site surveillance has been provided by
the Las Vegas facility for nuclear explosive tests at places other than the
NTS, the primary surveillance effort has been centered around the NTS.
The objective of the Program since 1953 has been to measure levels and
trends of radioactivity in the off-site environment surrounding testing areas
to assure that the testing is in compliance with existing radiation protection
standards. To assess off-site radiation levels, routine sampling networks for
milk, water, and air are maintained along with a dosimetry network and special
sampling of food crops, soil, etc., as required.
In general, analytical results showing radioactivity levels above
naturally occurring levels have been published in reports covering a test
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series or test project. Beginning in 1959 for reactor tests, and in 1962 for
weapons tests, surveillance data for each individual test which released
radioactivity off-site were reported separately. Commencing in January 1964,
and continuing through December 1970, these individual reports for nuclear
tests were also summarized and reported every six months with the analytical
results for all routine or special milk samples.
In 1971, the AEC implemented a requirement (ERDA Manual, Chapter 0513)1
for a comprehensive radiological monitoring report from each of the several
contractors or agencies involved in major nuclear activities. The compilation
of these various reports since that time and their entry into the general
literature serve the purpose of providing a single source of information con-
cerning the environmental impact of nuclear activities. To provide more
rapid dissemination of data, the monthly reports of analytical results of all
air data collected since July 1971, and all milk and water samples collected
since January 1972, are submitted to the appropriate state health departments
involved, and were also published in Radiation Data and Reports a monthly
publication of the EPA, which was discontinued at the end of 1974.
Since 1962, PHS/EPA aircraft have also been used during nuclear tests to
provide rapid monitoring and sampling for releases of radioactivity. Early
aircraft monitoring data obtained immediately after a test are used to posi-
tion mobile radiation monitors, and the results of cloud sampling are used
to quantitate the inventories, diffusion and transport of the radionuclides
released. Beginning in 1971, all monitoring and sampling results of aircraft
have been reported in effluent monitoring data reports in accordance with the
ERDA Manual, Chapter 0513.
ii
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TABLE OF CONTENTS
Page
PREFACE i
LIST OF FIGURES iv
LIST OF TABLES v
INTRODUCTION 1
NEVADA TEST SITE " 1
Site Location 1
Climate 2
Geology and Hydrology 3
Land Use of NTS Environs 3
Population Distribution 5
OTHER TEST SITES 6
SUMMARY , 7
MONITORING DATA COLLECTION, ANALYSIS, AND EVALUATION 9
AIR SURVEILLANCE NETWORK 10
NOBLE GAS AND TRITIUM SURVEILLANCE NETWORK 12
DOSIMETRY NETWORK 14
MILK SURVEILLANCE NETWORK 16
WATER SURVEILLANCE NETWORK 19
LONG-TERM HYDROLOGICAL MONITORING PROGRAM 21
NTS 22
Other Test Sites 23
WHOLE-BODY COUNTING 25
DOSE ASSESSMENT 27
REFERENCES 29
APPENDIX A. RADIATION PROTECTION STANDARDS FOR 1°2
EXTERNAL AND INTERNAL EXPOSURE
APPENDIX B. DOSE ASSESSMENT CALCULATIONS 104
iii
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LIST OF FIGURES
Figure
1. Nevada Test Site Location 30
2. Nevada Test Site Road and Facility Map 31
3. Ground Water Flow Systems - NTS 32
4. General Land Use, Nevada Test Site Vicinity 33
5. Population Distribution by Azimuth/Distance 34
6. Air Surveillance Network 35
7. Noble Gas and Tritium Surveillance Network 36
8. Dosimetry Network 37
9. Milk Surveillance Network 38
10. Water Surveillance Network 39
11. Water Surveillance Network, Las Vegas Valley 40
12. On-NTS Long-Term Hydrological Monitoring Program 41
13. Off-NTS Long-Term Hydrological Monitoring Program 42
14. Long-Term Hydrological Monitoring Locations, Carlsbad, NM, 43
Project Gnome/Coach
15. Long-Term Hydrological Monitoring Locations, Fallen, NV, 44
Project Shoal
16. Long-Term Hydrological Monitoring Locations, Project Dribble/ 45
Miracle Play (Vicinity of Tatum Salt Dome, MS)
17. Long-Term Hydrological Monitoring Locations, Project Dribble/ 45
Miracle Play (Tatum Salt Dome, MS)
18. Long-Term Hydrological Monitoring Locations, Rio Arriba 47
County, NM, Project Gasbuggy
19. Long-Term Hydrological Monitoring Locations, Rulison, CO, 48
Project Rulison
20. Long-Term Hydrological Monitoring Locations Central Nevada 49
Test Area, Faultless Event
iv
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LIST OF TABLES
Table Page
1. Underground Testing Conducted Off the Nevada Test Site 50
2. Summary of Analytical Procedures 52
3. 1974 Summary of Analytical Results for the Air Surveillance Network 55
4. 1974 Summary of Analytical Results for the Noble Gas and Tritium 67
Surveillance Network
5. 1974 Summary of Background Radiation Doses for the Dosimetry 70
Network
6. 1974 Summary of Analytical Results for the Milk Surveillance 73
Network
7. 1974 Summary of Analytical Results for the Water Surveillance 78
Network - Surface Water Samples
8. 1974 Summary of Tritium Results for the Water Surveillance Network 81
9. Analytical Criteria for Long-Term Hydrological Monitoring 82
Program Samples
10. 1974 Summary of Analytical Results for the NTS Monthly Long-Term 83
Hydrological Monitoring Program
11. 1974 Summary of Analytical Results for NTS Semi-Annual Long-Term 87
Hydrological Monitoring Program
12. 1973 Samples from NTS Monthly Long-Term Hydrological Monitoring 93
Program Not Previously Reported
13. 1974 Summary of Analytical Results for Off-NTS Long-Term 96
Hydrological Monitoring Program
14. 1973 Samples from Off-NTS Long-Term Hydrological Monitoring 101
Program Not Previously Reported
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INTRODUCTION
Under a Memorandum of Understanding, No. AT(26-l)-539, with the U. S.
Energy Research and Development Administration (ERDA), the U. S. Environmental
Protection Agency (EPA), National Environmental Research Center-Las Vegas
(NERC-LV), continued its Off-Site Radiological Safety Program within the
environment surrounding the Nevada Test Site (NTS) and at other sites desig-
nated by the ERDA during 1974. This report, prepared in accordance with the
ERDA Manual, Chapter 0513, contains summaries of NERC-LV sampling methodol-
ogies, analytical procedures, and the results of environmental samples col-
lected in support of ERDA nuclear testing activities. Where applicable,
sampling data are compared to appropriate guides for external and internal
exposures 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.
NEVADA TEST SITE
The major programs conducted at the NTS in the past have been nuclear
weapons development, proof-testing and weapons safety, testing for peaceful
uses of nuclear explosives (Project Plowshare), reactor/engine development
for nuclear rocket and ram-jet applications (Projects Rover and Pluto), 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, and Project Rover, which was termi-
nated in January 1973. No Plowshare nuclear tests were conducted at the NTS
or any other site during this period. All nuclear weapons tests were con-
ducted underground to minimize the possible 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
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large basins or flats about 900-1200 m above mean sea level (MSL) surrounded
by mountain ranges 1800-2100 m MSL.
The NTS is nearly surrounded by an exclusion area collectively named the
Nellis Air Force Range. The Range, particularly to the north and east, pro-
vides 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
public. Depending upon wind speed and direction, this provides a delay of
one half hour to more than 6 hours before any accidental release of air-
borne radioactivity could pass over public lands.
Climate
The climate of the NTS is variable, primarily due to altitude and the
rugged terrain. Generally, the climate is referred to as Continental Arid.
The 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 10 (-4 ) C in January and 35 (12 ) C in July,
with extremes of 44 and -26 C. Corresponding temperatures on the plateaus
are 2 (-4 ) C in January and 26 (18 ) C in July with extremes of 38 and
-29 C. Temperatures as low as -34 C and higher than 46 C have been observed
at the NTS.
The prevailing direction from which winds blow, as measured on a 30-m
tower at the Yucca observation station, is predominantly northerly except
for 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 north-
erly 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.2
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Geology and Hydrology
Geological and hydrological studies of the NTS have been in progress by
the U. S. Geological Survey and various other institutions since 1956.
Because of this continuing effort, including subsurface studies of numerous
boreholes, the surface and underground geological and hydrological charac-
teristics for much of the NTS are known in considerable detail. This is
particularly true for those areas in which underground experiments are con-
ducted. A comprehensive summary of the geology and hydrology of the NTS
was published in 1968 as Memoir 110 by the Geological Society of America,
entitled "Nevada Test Site."
There are two hydrologic systems on the NTS (Figure 3). Groundwater
in the Pahute Mesa system is believed to travel somewhere between 2 and 80 m
per year to the south and southwest toward the Amargosa Desert. It is
estimated that groundwater in the Ash Meadows system moves beneath the NTS
from north to south at a rate not less than 2 nor greater than 220 m per
year.3 Carbon-14 analyses of water from the Ash Meadows systems 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.
Depths to water on the NTS vary from about 100 m beneath the valleys in
the southeastern part of the site to more than 600 m beneath the 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.3
Land Use of NTS Environs
Figure 4 is a map of the off-NTS area showing general land use. A wide
variety of uses exists due to the variable terrain. For example, within a
320-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
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Joaquin) are included. The areas south of the NTS are more uniform since the
Mojave Desert ecosystem comprises most of this portion of Nevada, California,
and Arizona. The areas east of the NTS are primarily Basin-Range Desert
with some of the older river valleys, such as the Virgin River Valley,
supporting small-scale but intensive farming and production of a variety of
crops. Grazing is also common in this area, particularly to the northeast.
The area north of the NTS is also Basin-Range Desert where the major agri-
cultural-related activity is grazing of both cattle and sheep. Only areas
of minor agricultural importance, primarily alfalfa hay, are found in this
portion of the State within a distance of 320 km.
In the summer of 1974, a brief survey of home gardens around the NTS
found that a major portion of the residents grow or have access to locally
grown fruits and vegetables. Approximately two dozen of the surveyed gar-
dents within 30 km of the NTS were selected for sampling. These gardens
produce a variety of root, leaf, seed, and fruit crops.
The only major body of water close to the NTS is Lake Mead, a man-made
lake supplied by water from the Colorado River. Lake Mead is the source of
water for almost all domestic, recreational, and industrial purposes in the
Las Vegas Valley and for a portion of the water 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.
Dairy farming is not extensive within the 320-km-radius area under
discussion. From a survey of milk cows in the area during this report
period, a total of 12,721 dairy cows and 1,174 family cows were located.
The family cows are found in all directions around the test site,
while the dairy cows are primarily located southeast of the test site
(Moapa River Valley, Nevada; Virgin River Valley, Nevada; and Las Vegas,
Nevada), northeast (Hiko and Alamo, Nevada, area), west-northwest (near
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Bishop, California), and southwest (near Barstow, California) (Figure 5).
Population Distribution
Based upon a field survey during 1974, Figure 5 portrays the distribution
of people and milk cows within a 320-km radius of the Control Point, CP-1, at
the NTS. With the exception of Las Vegas and vicinity, there are no major
population centers within 320 km of the site. There are about 500,000 people
living in this total area, about one-half of whom live in the Las Vegas greater
metropolitan area. If the City of Las Vegas is not considered in determining
population density, there are about 0.8 people per km2 (2 people per mi2)
within the 320-km radius of the NTS Control Point. For comparison, the
United States (50 states) has a population density of 21 people per km2 and
the overall Nevada average is 1.7 people per km2.
The off-site areas within about 80 km of NTS are predominantly rural.
Several small communities are located in the area, the largest being in the
Pahrump Valley. This rural community, with an estimated population of about
3000, is located about 72 km south of the NTS. The Amargosa Farm area has a
population of about 200 and is located about 50 km southwest of the center of
the NTS. The Spring Meadows Farm area is a relatively new development con-
sisting of approximately 10,000 acres with a population of somewhat more than
100. This area is about 55 km south-southwest of the NTS. The largest town
in the near off-site area is Beatty with a population of about 1000; it is
located about 65 km to the west of the site.
In the adjacent states, the Mojave Desert of California, which includes
Death Valley National Monument, lies along the southwestern border of Nevada.
The population in the Monument boundaries varies considerably from season to
season with fewer than 200 permanent residents and tourists in the area during
any given period in the summer months. However, during the winter as many as
2000 tourists and campers can be in the area on any particular day during the
major holiday periods. The largest town in this general area is Barstow,
located 265 km south-southwest of the NTS, with a population of about 17,000.
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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 8500.
'"I
The extreme southwestern region of Utah is more developed than the
adjacent part of Nevada. The largest town, Cedar City,1 with a population of
approximately 8000, is located 282 km east-northeast of the NTS. The next
largest community is St. George, located 217 km east of the NTS, with a
population of slightly more than 7000.
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
6000.
OTHER TEST SITES
Table 1 lists the name, date, location, yield, depth, and purpose of all
underground nuclear tests conducted at locations other than the NTS. No off-
NTS nuclear tests were conducted during this report period. However, production
testing of a natural gas well at the Project Rio Blanco site near Rifle,
Colorado, was conducted in January, February, and December 1974,^s5*6 during
which time natural gas containing quantities of 85Kr and 3H was flared
(burned) in the open. CER Geonuclear Corporation, the contractor responsible
for the off-site radiological safety program for this operation, will report
separately the results of their environmental surveillance.
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SUMMARY
During 1974, 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 per-
tinent environmental media were also continuously or periodically monitored
by established air, milk and water sampling networks. Before each under-
ground nuclear detonation, mobile radiation monitors, equipped with radiation
monitoring instruments and sampling equipment, were on standby in off-NTS
locations to respond to an accidental release of airborne radioactivity.
A total of about 707 curies (Ci) of radioactivity, primarily radioxenon,
was reported by ERDA/NV as being released intermittently throughout the year.
The only off-NTS indications of this radioactivity from test operations were
concentrations of 133Xe measured in air samples collected at Beatty and Diablo,
Nevada. The concentrations at these locations when averaged over the year
were less than 0.008% of the Concentration Guide of 1 x 10 7 microcuries per
milliliter (yCi/ml) as listed in the ERDA Manual, Chapter 0524, for exposure
to a suitable sample of the population. Based upon time-integrated concen-
trations of 133Xe at these locations, dose calculations, and population infor-
mation, the dose commitment to persons within 80 km of the NTS Control Point
for test operations during this year was estimated to be 0.003 man-rem.
All other measurements of radioactivity within the Off-Site Radiological
Safety Program were attributed to naturally occurring radioactivity or
atmospheric fallout and not related to underground nuclear test operations
during this report period.
The Long-Term Hydrological Monitoring Program used for the monitoring
of radionuclide concentrations in surface and ground waters which are down-
gradient from sites of past underground nuclear tests was continued for the
NTS and for six other sites located elsewhere in Nevada, Colorado, New
Mexico, and Mississippi. Concentrations of naturally occurring radionuclides,
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such as isotopes of uranium and 226Ra, were detected in samples collected
at most locations at levels which were comparable to concentrations measured
for previous years. Except for a sample collected at Half Moon Creek Over-
flow, Mississippi (Project Dribble), and samples collected at wells known to
be contaminated by the injection of high concentrations of radioactivity for
waste disposal or tracer studies, no radioactivity related to past under-
ground tests or to the contaminated wells was identified. The annual surface
water sample collected at Half Moon Creek Overflow had a 3H concentration of
5.1 x 10 5 yCi/ml. Since the above background concentration for this year
is only 0.17% of the Concentration Guide for individuals in an uncontrolled
area, no further sampling was done prior to the next scheduled sampling in
1975.
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MONITORING DATA COLLECTION, ANALYSIS, AND EVALUATION
The major portion of the Off-site Radiological Safety Program for the NTS
consists of continuously-operated dosimetry and air sampling networks and sched-
uled collections of milk and water samples at locations surrounding the NTS.
Before each nuclear test, mobile monitors were positioned in the off-site areas
most likely to be exposed by a possible release of radioactive material. These
monitors, equipped with radiation survey instruments, gamma-rate recorders,
thermoluminescent dosimeters, portable air samplers, and supplies for collecting
environmental samples, were prepared to conduct a monitoring program directed
from the NTS Control Point 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 Co. monitors equipped with portable radiation survey instruments
was airborne near surface ground zero to detect and track any radioactive
effluent. Two NERC-LV cloud sampling and tracking aircraft were 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.
During this report period, only underground nuclear detonations were con-
ducted. All detonations were contained. However, during re-entry drilling
operations, occasional inadvertent releases of airborne radioactivity, pri-
marily radioxenon, did occur. According to information provided by the Nevada
Operations Office, ERDA, the following quantities of radionuclides were
released into the atmosphere during CY 1974:
Quantity Released
Radionuclide (Ci)
133Xe 663
133mxe n
135Xe 31
3H < 2
238U < 0.0001
131,133,135]- < o.OOOOl
Contained within the following sections of this report are descriptions
for each surveillance network and interpretations of the analytical results
which are summarized (maximum, minimum, and average concentrations) in tables.
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Where appropriate, the average values in the tables are compared to the appli-
cable Concentration Guides (CG's) listed in Appendix A.
The Pu in Soil Survey has been a subject of this report for previous years;
however, it is actually a special study and not related to routine off-NTS
surveillance for current nuclear tests. Henceforth, the data derived from this
program will be published in progress reports of the Nevada Applied Ecology
Group, sponsored by the ERDA, Nevada Operations Office.
For "grab" type samples, radionuclide concentrations were extrapolated to
the appropriate collection date. Concentrations determined over a period of
time were extrapolated to the midpoint of the collection period. Concentration
averages were calculated assuming that each concentration less than the minimum
detectable concentration (MDC) was equal to the MDC. The only exception to this
was for the radionuclide measurements for the Air Surveillance Network. Due to
the lack of a statistically derived MDC, the concentrations of radionuclides
that could not be detected were assumed to be zero.
All radiological analyses referred to within the text are briefly described
in Table 2 and listed with the minimum detectable concentrations (MDC's). To
assure validity of the data, analytical personnel routinely calibrate equip-
ment, split selected samples (except for the Air Surveillance and Dosimetry
Networks) for replicate analyses, and analyze spiked samples prepared by the
Quality Assurance Branch, NERC-LV, on a quarterly basis. All quality assurance
checks for the year identified no problems which would affect the results of
this report.
AIR SURVEILLANCE NETWORK
The Air Surveillance Network, operated by the NERC-LV, consisted of 49
active and 72 standby sampling stations located in 21 Western States
(Figure 6). Samples of airborne particulates were collected continuously
at each active station on 10-cm-diameter, glass-fiber filters at a flow
rate of about 350 m^ of air per day. The filter collection frequency was
three times weekly, 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
10
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21 stations near the NTS. Charcoal cartridges could have been added to all
other stations, if desired, by a telephone request to station operators. All
air samples (filters and cartridges) were mailed to the NERC-LV for analysis.
Special retrieval could have been arranged at selected locations in the event
a release of radioactivity was believed to have occurred.
From gamma spectrometry results, small concentrations of 7Be, ^5Zr, 1"3Ru,
106Ru, llt0Ba, 141Ce and 14l+Ce in varying combinations were identified at all
Network stations except Currant and Geyser, Nevada. Table 3 lists the maximum,
minimum and average concentrations of these radionuclides for each station at
which radionuclides were detected. Since none of the radionuclides were attri-
buted to NTS testing operations, percentages of the concentration guides were
not calculated.
The sources of the radioactivity were considered to be the June 26, 1974,
nuclear detonation by the People's Republic of China and worldwide fallout from
previous atmospheric tests. The radionuclide ll+0Ba (12.8-day half-life), which
is not usually detected except during short periods following an atmospheric
detonation, was detected in 19 ASN stations only between June 28 and July
12. The other radionuclides were detected throughout the Network and year
within the ranges, shown below, which are comparable to the results of samples
collected within North America during the period January-November 1974 and
analyzed by HASL.7
Radionuclide Concentration, 10~12yCi/ml
Radionuclide
7Be
95Zr
103Ru
106Ru
lltlCe
lltltCe
Half-
Life
(days)
53.3
65.5
39.6
369
32.5
284
NTS Network
(Jan. -Dec. 1974)
Max Min
0.40
1.2
0.36
1.1
0.28
1.0
10.13
10.022
10.020
10.015
10.031
<0.13
North America
(Jan. -Nov. 1974)
CMax CMin
0.247 0.0249
0.0697 0.00170
Not Reported
Not Reported
Not Reported
0.144 0.00241
11
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The NTS concentration ranges were slightly higher than the concentration ranges
reported by HASL; however, the difference was not attributed to testing opera-
tions at the NTS.
NOBLE GAS AND TRITIUM SURVEILLANCE NETWORK
The Noble Gas and Tritium Surveillance Network, which was first estab-
lished in March and April 1972, was operated to monitor the airborne levels of
radiokrypton, radioxenon, and 3H in the forms HT, HTO, and CH3T. The Net-
work consisted of four on-NTS and six off-NTS stations (Figure 7).
The equipment used in this Network is composed of two separate systems,
a compressed air sampler and a molecular sieve sampler. The compressed air
equipment continuously samples air over a 7-day period. The air is then
compressed and stored in two pressure tanks, which together hold approximately
2 cubic meters of air at atmospheric pressure. The bottles are replaced
weekly and returned to the NERC-LV where the contents of one pressure tank
are separated and analyzed for 85Kr, radioxenons, and CE^T by gas chromatog-
raphy and liquid-scintillation counting techniques (Table 2). The molecular
sieve equipment samples air through a filter to remove particulates and then
through a series of molecular sieve columns. Approximately 5 cubic meters of
air are passed through each sampler over a 7-day sampling period. From the
HTO adsorbed on the first molecular sieve column, the concentration of 3H in
yCi/ml of recovered moisture and in pCi/ml of sampled air is determined by
liquid-scintillation counting techniques. The 3H, passing through the first
column as free hydrogen (HT), is oxidized and collected on the last molecular
sieve column. From the concentration of 3H in the moisture collected from
the last column, the 3H (in yCi/ml of sampled air) existing as HT is determined.
Table 4 summarizes the results of this Network by listing the maximum,
minimum, and average concentrations for 85Kr, total Xe or 133Xe, 3H as CHaT,
3H as HTO, and 3H as HT. The annual average concentrations for each station
were calculated over the time period sampled assuming that all values less
than the minimum detectable concentration (MDC) were equal to the MDC. All
12
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concentrations of 85Kr, Xe or 133Xe, 3H as CH3T, 3H as HTO, and 3H as HT are
expressed in the same unit, yCi per ml of air. Since the H concentration in
air varies by factors of 15-20 while the concentration in water varies by
factors up to about 4, the 3H concentration in yCi/ml of atmospheric moisture
is also given in the table as a more reliable indicator of when background
concentrations of HTO are exceeded.
As shown by Table 4, the maximum and average 85Kr levels at all stations
were essentially the same. The concentrations of 3H as HTO and as HT for the
year were generally the same at all locations except for the on-NTS stations
at BJY and Area 12, where the averages and ranges in concentrations were
significantly higher than those for all other stations. The higher concentra-
tions were generally associated with seepage from earlier NTS operations, such
as the Sedan cratering test and Area 12 tunnel tests. The total of the average
tritium concentrations (HTO+HT+CH3T) for either of these on-NTS stations was
less than 0.004% of the Concentration Guide for 3H in air, which is 5 x 10~6
yCi/ml for an exposure to a radiation worker. Small quantities of 3H in the
form CHsT were occasionally detected off-NTS. However, the concentration
averages and ranges for samples collected at all off-NTS locations were
generally the same. No definite correlation between CE^I and NTS testing
could be made.
Concentrations of radioxenon greater than the MDC were detected during
the year at all on-NTS sampling locations and at two off-NTS locations. The
radioxenon, identified as 33Xe, was measured with a maximum concentration
of 1.1 x 10~9 yCi/ml at the on-NTS station at Area 12. The applicable Con-
centration Guide (CG) for radiation workers is 1 x 10~5 yCi/ml. In the off-
NTS area, the highest concentration was at Beatty with 1.4 x 10~10 yCi/ml,
and the next highest concentration was at Diablo with 1.7 x 10"11 yCi/ml. At
either off-NTS location the 133Xe concentrations, when averaged over the total
sampling times for the year, were less than 0.008% of the CG for this nuclide,
which is 1 x 10 yCi/ml for a suitable sample of a population in an uncon-
trolled area.
13
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DOSIMETRY NETWORK
The Dosimetry Network during 1974 consisted of 69 locations surrounding
the Nevada Test Site which were monitored continuously with thermoluminescent
dosimeters (TLD's). The locations of these stations, shown in Figure 8, are
X - ?
all within a 270-km radius of the center of the NTS and include both inhabited
i
and uninhabited locations. Each Dosimetry Network station was routinely equip-
ped with three EG&G Model TL-12 dosimeters which were exchanged on a quarterly
basis. Within the general area covered by the dosimetry stations, between 45
and 52 cooperating off-site residents wore one or two dosimeters which were
exchanged at the same time as the station dosimeters. For the last two quarters
of 1974 (July - December), these off-site personnel were monitored using TLD-
200 dosimeters and a Harshaw Model 2271 TLD reader system which is presently
under evaluation.
The TL-12 dosimeter has an internal or self-exposure rate equivalent to
0.7 mR/d due to naturally occurring 40K in the glass envelope and TLD binder.
»
The TLD-200 dosimeters have no such self-exposure as :they consist of indi-
rectly-heated, monocrystalline calcium fluoride mounted on an aluminum card.
The smallest net exposure which may be determined by either type of dosimeter
is limited by the variations in the natural background radiation for a given
station location. Experience has shown these variations to be significant
from one monitoring period to another and much larger in magnitude than
variations due to the precision of the dosimeters. Typically, however, the
smallest net exposure observable for a 90-day monitoring period would be on
the order of 15 - 45 mR in excess of background. The term "background," as
used in this context, refers to naturally occurring radioactivity (including
that in the dosimeter itself) plus a contribution from residual man-made
fission products.
After appropriate corrections were made for the background exposure
accumulated during shipment between the laboratory and the monitoring loca-
tions, the three dosimeter readings for each station were averaged. This
average exposure value for each monitoring period and station was compared
14
-------
to values from the past three years to determine if the new value was within
the range of previous background values for that station. Any values signifi-
cantly greater than previous values would have led to calculations of net
exposure, while values significantly less than previous values would have been
examined to determine possible reader or handling errors producing invalid
data. The results from each of the personnel dosimeters were compared to the
background value of the nearest station to determine if a net exposure had
occurred.
Table 5 lists the maximum, minimum, and average dose equivalent rate
(mrem/d) measured at each station in the network during 1974. All doses are
from environmental background. The dose equivalent rates were determined by
dividing the total dose equivalent for each monitoring period by the number
of days in the monitoring period (typically about 90 days per quarter for
1974). The average daily rate for the year was simply the average of the
rates for the four quarters. The average annual dose for the year is the
product of the average daily rate and 365 days. As shown by this table, the
average annual station background doses ranged from 62 mrem to 160 mrem with
a network average of 114 mrem. Both the range and the average values for
1974 have decreased slightly from the two previous years. This trend seems
to be generally true for most network stations, but no explanation is offered
for the trend at this time. Among the off-site residents who wore dosimeters
continuously, no personnel doses greater than background were attributed to
nuclear testing at NTS.
The whole-body gamma dose equivalent values measured by the Dosimetry
Network generally agree well with those published by a special studies group
in the Office of Radiation Programs, EPA.8 This report estimates that gamma
exposures from terrestrial and .cosmic radiation for the United States range
from 75 mrem to 225 mrem per person per annum, with a mean of 115 mrem/a.
For the Dosimetry Network, the range was 60 mrem/a to 150 mrem/a with a
mean of 110 mrem/a. If considered on a state-by-state basis, however, even
better agreement is noted. For Nevada, the estimated average whole-body
15
-------
gamma dose equivalent from both terrestrial and cosmic radiation is 125 mrem/a,
while the average from the Dosimetry Network was 115 mrem/a. Similarly the
estimate for California is 90 mrem/a, compared to the Dosimetry Network average
of 95 mrem/a for the California stations. For Utah, the estimate of 155
mrem/a does not compare well with the Dosimetry Network average of 100 mrem/a.
However, the estimate includes a large component due to cosmic radiation which
would be less predominant in the lower, southwestern portion of the State
where the Dosimetry Network stations are located.
In the past years, there have occurred a number of unexplained high dosimeter
readings which have been regarded as anomalous and were suspected of being
caused by phenomena associated with the TLD material and not related to true
gamma exposure. Out of the more than 1,000 dosimeters issued for the NTS
Off-Site Dosimetry Network for 1974, only one unexplained high reading occur-
red. The dosimeter in question had a reading of 1800 mR and had been issued
to an off-site resident in Beatty, Nevada, during the first quarter of 1974.
A subsequent documented investigation revealed no explanation for the reading,
but it was not believed to represent a true gamma dose to the individual.
A network of 30 stationary gamma rate recorders placed at selected air
sampling locations was used to document gamma exposure rates at fixed loca-
tions (Figure 6). These recorders, designated as LSI's, use a 2.5- by 30.5-cm
constant-current ionization chamber detector filled with methane, and operate
on either 110 V a.c. or on a self-contained battery pack. They have a range
of 0.004 mR/h to 40 mR/h with an accuracy of about ±10% of a reading above
background. During this report period, no increase in exposure rates attrib-
utable to NTS operations was detected by the network of gamma rate recorders.
MILK SURVEILLANCE NETWORK
Milk is only one of the sources of dietary intake of environmental
radioactivity. However, it is a very convenient indicator of the general
population's intake of biologically significant radionuclide contaminants.
16
-------
For this reason it is monitored on a routine basis. Few of the fission pro-
duct radionuclides become incorporated into the milk due to the selective
metabolism of the cow. However, those that are incorporated are very impor-
tant from a radiological health standpoint. The amount transferred to milk
is a very sensitive measure of their concentrations in the environment. The
five most common fission product radionuclides which can occur in milk are
89-90Sr> 131I} 137Cs> and lt*0Ba> A sixth radionuclide, 40K, 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 was not included in the
analytical results summarized in this section.
The milk surveillance networks operated by the NERC-LV were the routine
Milk Surveillance Network (MSN) and the Standby Milk Surveillance Network
(SMSN). The MGN during 1974 (Figure 9) consisted of 25 different locations
where 3.8-litre milk samples were collected from 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 concen-
trations in milk, the radiation doses that could result from the ingestion of
the milk, and the need for protective action. Milk supplies and producers
beyond 480 km are sampled with the SMSN.
During 1974, 86 milk samples were collected from the MSN on a quarterly
collection schedule. Milk could not usually be obtained at all locations at
any one collection time. Cows not lactating, no one home, or no milk on the
day field personnel arrived at the ranch were some of the reasons why some
of the samples were not collected. During the year, milk sampling points
also changed as cows were sold or were otherwise unavailable for regular
milkings.
The SMSN consisted of about 175 Grade A milk processing plants in all
States west of the Mississippi River, which could be requested by telephone
to collect raw milk samples representing milk sheds supplying milk to the
17
-------
plants. Since there were no releases of radioactivity from the NTS or other
test locations, this network was not activated except to request an occasional
sample to check its readiness and reliability. No analytical results
are reported here for the SMSN because the samples were not associated with
any particular nuclear activity or installation.
Each milk sample was analyzed for gamma-emitters and 89~90sr. Samples
collected at six locations from the MSN were also analyzed for 3H. Table 2
lists the general analytical procedures and detection limits for these
analyses.
The analytical results of milk samples collected from the MSN during
1974 are summarized in Table 6. The maximum, minimum, and average concen-
trations of the 137Cs, 89~90Sr, and 3H in samples collected during the year
are shown for each sampling location. No radionuclides from NTS operations
were detected in any of the milk samples. Although *3'Cs and 89~90Sr were
observed in the samples, the concentrations of these radionuclides were
similar to levels found in samples collected for the Pasteurized Milk Net-
work (PMN). Therefore, they are attributed to world-wide fallout.
The PMN, sponsored jointly by the Environmental Protection Agency and
the Public Health Service, consists of 63 sampling stations in the United
States, one in Puerto Rico, and one in the Canal Zone. Sampling results are
summarized by monthly averages, running 12-month averages, and a 12-month
average for the whole network. Although the PMN results for the milk samples
collected throughout CY 1974 are not complete, one can use the latest infor-
mation on 12-month averages for comparison purposes since the period covers
a full year of seasonal variations.
Shown below are the ranges in the 12-month averages for network stations
and the network averages of 90Sr and 137Cs for both the PMN9 and the MSN.
For the PMN, concentrations which were equal to or less than the appropriate
minimum detectable concentration (1-5 pCi/1 for 89Sr; 1-2 pCi/1 for 90Sr;
18
-------
4-10 pCi/1 for 137Cs) were set equal to zero for averaging. For the MSN
they were set equal to the MDC. As indicated by this comparison, the con-
centrations of these radionuclides in the area surrounding the NTS and
other areas of North America are commensurate.
Radionuclide Concentrations
(10-9 yCi/ml)
Strontium-90
Cesium-137
Network
PMN
MSN
Period
June 1973-
May 1974
January-
December 1974
Range in
12-Month
Station
Averages
0-9
<1.0 - 4.5
12-Month
Network
Average
5
<1.7
Range in
12-Month
Station
Averages
0-9
<10.0 - <10.0
12-Month
Network
Average
2
<10.0
WATER SURVEILLANCE NETWORK
The Water Surveillance Network (WSN), operated in off-site areas around
the NTS during 1974, consisted of 59 locations (Figures 10 and 11) where
NERC-LV personnel collected 3.8-litre water samples. The samples were col-
lected from community water supplies, wells, open and closed springs, streams,
lakes, and ponds. If a release of radioactivity from NTS had occurred, spe-
cial sampling within the affected area would have been conducted to deter-
mine radionuclide concentrations.
During 1974, 233 water samples were collected from these locations on
a quarterly collection schedule. In some cases operational priorities,
frozen sources, etc., prevented the sampling of each location every time.
All water samples from the WSN were analyzed by gamma spectrometry and
counted for gross alpha and gross beta radioactivity. Network samples from
19
-------
approximately 13 locations west, south, and southeast of the NTS were also
routinely analyzed for 3H. For the purpose of identifying the source of the
gross radioactivity in all network samples and monitoring for concentrations
of strontium and plutonium in the environment, selected samples were given
special analyses at least once during the year. For surface water samples,
the special analyses included "-90Sr, 238~239Pu, U, and 226Ra. For drinking
water samples, the analyses included 89~90Sr, U, and 226Ra. Table 2 lists the
general analytical procedures and detection limits for each analysis.
The analytical results of all samples were published in Radiation Data
and Reports, a monthly periodical of the Environmental Protection Agency. For
the purpose of this report, only the analytical results for 89-90Sr and Pu
for the surface water samples and a summary of the 3H results for all water
samples are presented in Tables 7 and 8, respectively. No gamma-emitting
fission products were detected in any of the samples by gamma spectrometry.
As shown by Table 7, no 89~90Sr was detected above the appropriate MDC
for any of the samples. Levels of 238-239pu at some locations fluctuated
slightly above the detection limit. However, the levels above the MDC
appeared to be random fluctuations. The range and average concentrations
for the whole network are comparable to environmental levels, shown below,
observed in samples collected by other agencies1^ in off-site regional areas
during 1973.
Location
No. of
Samples
Radioactivity Concentration (10~9 yCi/ml)
238pu 239pu
Pu Total
Min Max Avg Min Max Avg Min Max Avg
LASL
Albuquerque, NM 19
Rocky Flats
(Great Western
Reservoir)
Golden, CO 15
WSN (all loca-
tions) NTS, NV 12
0.009 0.12 0.04 0.007 0.82 0.14
<0.01 0.31 <0.08
<0.031 0.12 <0.037 <0.040 0.088 <0.052
20
-------
Since levels of 3H in surface water samples (Table 8) were consistent
throughout the WSN and similar to levels observed by other agencies, shown
below, all levels were attributed to world-wide fallout and natural sources.
3H Concentrations
Location
LASL
Albuquerque, NM
LLL
Livermore, CA
WSN (all locations)
NTS, NV
No.
Samples
19
99
53
(10-9 uCi/ml)
Min
<300
52
<210
Max
1300
1100
1200
Avg
600
236
340
The levels of 3H in samples collected at Vegas Wash and NERC-LV
(Table 8) were generally higher than all other WSN locations. These
two locations have a common source of water, the Colorado River, which has
3H concentrations higher than other locations surrounding the NTS. This is
due to the large fraction of flow resulting from surface runoff from water-
sheds of the Colorado River having higher rates of rainfall than the off-
NTS area.
LONG-TERM HYDROLOGICAL MONITORING PROGRAM
During this report period, NERC-LV personnel continued the collection
and analysis of water samples collected from wells, springs, and spring-fed
surface water sources which are down-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 into ground water. The water samples
were collected from well heads or spring discharge points wherever possible.
If pumps were not available, an electrical-mechanical water sampler capable
of collecting 3-litre samples at depths to 1800 m was used.
21
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NTS
For the NTS, attempts were made to sample 10 stations monthly and 18
ftations semi-annually (Figures 12 and 13). Not all stations could be sam-
pled with the desired frequency because of inclement weather conditions and
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 3H. Portions of the filtered and acidified samples were given
radiochemical analyses. Portions of the filtered samples and the filtered and
acidified samples received stable chemical analyses. Table 9 summarizes the
criteria which were observed for analyzing the water samples. Each filter
was also analyzed by gamma spectroscopy. Table 2 summarizes the analytical
techniques used.
Tables 10 and 11 list the analytical results of all samples collected
during this report period. Many of the 1973 monthly samples could not
be analyzed in time for last year's report. Therefore, Table 12 is an up-
dated listing of analytical results for these samples.
The only radionuclide unusual to well water that was detected was 3H
in NTS Wells C and C-l. The 3H in these two wells was introduced as part of
a tracer experiment. Both wells had concentrations which were less than
0.0001% of the Concentration Guide (CG) for a radiation worker.
Tables 10, 11, and 12 show concentrations of 90Sr, 238Pu, and 239Pu that
were above their respective MDC. These concentrations with two-
sigma counting errors and percentages of CG's for individuals in an un-
controlled area are as follows:
22
-------
Location
NTS Well C
NTS Well C (1973)
NTS Well UE 19G-S
NTS Well UE 5c
Indian Springs
Sewer Co. Inc.
Well No. 1
Shoshone Spring
Radio-
nuclide
9°Sr
90Sr
90Sr
239pu
238pu
9°Sr
Cone.
(10-9yCi/ml)
2.5 ± 1.3
5.0 ± 1.8
1.9 ± 1.6
0.050 ± 0.030
0.018 ± 0.016
0.92 ± 0.91
% of Cone.
Guide
0.83
1.7
0.63
0.001
0.0003
0.31
The first two concentrations are considered to be anomalies. All other
samples from each location during the year had concentrations below the MDC's
or had concentrations with relatively large counting errors. The other con-
centrations listed above have error terms too large for one to say that the
concentrations are real and not a result of statistical error.
Due to the absence of information on background levels of 3H in deep
wells, the % concentrations measured by this program can only be compared
to previous determinations for the same locations. Such a comparison for
each location indicated that there are no significant trends in concentra-
tions.
Other Test Sites
The annual collection and radiological analysis of water samples was
continued for this program at all off-NTS sites of underground nuclear
detonations except for Amchitka, Alaska, and Project Rio Blanco near Meeker,
Colorado. The latter two sites are the responsibility of other agencies.
The sites at which samples were collected are located near Rifle, Colorado
(Project Rulison); at Tatum Dome, Mississippi (Project Dribble/Miracle Play);
in Central Nevada (Faultless Event); near Fallen, Nevada (Project Shoal); in
Rio Arriba County, New Mexico (Project Gasbuggy); and near Carlsbad, New
Mexico (Project Gnome/Coach). Figures 14 through 20 identify the sampling
23
-------
locations, and Table 1 lists additional information on the location of each
site and tests performed at these locations.
All samples were analyzed by the same criteria (Table 9) and procedures
(Table 2) as samples for the NTS Program. The analytical results of all water
samples collected during 1974 are summarized in Table 13. Table 14 lists the
results of three samples collected in 1973 from the Project Shoal site which
were not reported previously.
The only sample results showing radioactivity concentrations significantly
over background levels were for Half Moon Creek Overflow (Project Dribble)r
for USGS Well No. 1 at Malaga, New Mexico (Project Gnome);, for USGS Wells Nos.
4 and 8 at Malaga (Project Gnome); and for Well HT-2M at Tatum Salt Dome,
Mississippi (Project Dribble). As explained in the 1973 report, the latter
three wells, which are fenced, posted, and locked to prevent their use by
unauthorized personnel, were contaminated by the injection of high concen-
trations of radioactivity for the purpose of waste disposal or radioactive
tracer studies. Therefore, samples from the three contaminated wells are
not used to monitor the movement of radionuclides from the underground tests.
The sample from Half Moon Creek Overflow, a surface water sample, had a
3H concentration of 5.1 x 10~6 yCi/ml, whereas for previous years the 3H con-
centrations have been 4.3 x 10~7 yCi/ml (1972) and 2.7 x 10~7 yCi/ml (1973).
Since the high concentration for the year is only 0.17% of the Concentration
Guide for individuals in an uncontrolled area, no further sampling was done
prior to the next scheduled sampling in CY 1975. The concentrations of 3H
in all other surface waters were below 2.5 x 10~6 yCi/ml, a level considered
from past experience to be the highest one would expect from atmospheric
fallout.
The concentration of 90Sr reported for the well sample collected at
USGS Well No. 1, Malaga, New Mexico (Project Gnome), is considered to be a
statistical error and not a valid value. The concentration with its two-
sigma error term was 1.4 x 10~9 yCi/ml ± 0.85 x 10~9 yCi/ml.
24
-------
The concentrations of 90Sr measured in surface water samples were
attributed to atmospheric fallout.
The 3H concentrations measured in well samples were compared to the
analytical results of samples collected previously at each location. No
significant trends in concentrations were apparent.
WHOLE-BODY COUNTING
During 1974, the measurements of the body burdens of radioactivity in
selected off-site residents who might have been exposed to radioactivity
released from the NTS was continued. The whole-body counting facility was
described in the 1973 report (NERC-LV-539-31, May 1974).
Ninety-five individuals from 14 locations were examined. These locations
were Pahrump, Springdale, Beatty, Moapa, Caliente, Pioche, Nyala, Diablo,
Goldfield, Lathrop Wells, Ely, Tonopah, Twin Springs, and Spring Meadows
Farms, Nevada.
The minimum detectable concentration for Cs was 5 x 10~^ pCi/g for a
body weight of 70 kg and a 40-minute count. Each individual was also given
a complete hematological examination and a thyroid profile; from each
individual a urine sample was collected for 3H and 238-239pu analyses.
From the results of whole-body counting, the fission product 137Cs was
detected above the detection limit in 25 individuals. The maximum, minimum,
and average concentrations for this radionuclide were 4.1 x 10~8 yCi/g,
5.0 x 10~9 pCi/g, and 1.2 x 10~8 yCi/g body weight, respectively.
These concentrations are comparable to those reported by the Health
Services Laboratory, Idaho National Engineering Laboratory, Energy Research
and Development Administration.11 This facility examines about 400 workers
per annum at the National Reactor Testing Station, near Idaho Falls, Idaho.
25
-------
For the past year, 137Cs has not been measured above their detection limit of
0.002 yCi for a 10-minute count in any of the radiation workers except those
known to be occupationally exposed. Based upon the 70 kg body weight of a
standard man, this is equivalent to 3 x 10~8 yCi/g.
26
-------
DOSE ASSESSMENT
The only radioactivity detected from NTS operations was 133Xe at Beatty
and Diablo, Nevada. Based upon the sampling results for these .locations and
the dose calculations described in Appendix B, the whole-body doses to off-
NTS residents were calculated. Since 133Xe made up 94% of the total airborne
radioactivity reported as released from the NTS during 1974, the contribution
to the total dose received by off-NTS residents by all other reported radio-
nuclides was considered negligible. No release of airborne H was reported
by EKDA/NV and no 3H was detected off the NTS above its MDC. Therefore, no dose
estimate from 3H was calculated.
The largest population group within 80 km of the NTS Control Point
(CP-1 in Figure 5) is located at Indian Springs, Nevada. Since a noble gas
sampler is not operated at Indian Springs, a dose estimate for this location
was also made, based upon the 133Xe concentrations measured at Desert Rock, an
on-NTS station which would normally intercept NTS night-time "drainage" winds
headed for Indian Springs. The Desert Rock location is located close to the
southern NTS boundary and serves as a fence-line monitor for that location.
The following table summarizes the results of all calculations.
Location
Beatty, NV
Indian Springs, NV
Diablo, NV
Dose Calculated
from Actual
133Xe Concentrations
(yrem)
2
0.5
0.1
Percent of
Radiation
Protection
Standard
0.001
<0.0003
0.00005
Total =
Dose
Commitment
Within 80 km
(man-rem)
0.002
<0.001
0*
<0.003
*No people reside within an 80-km radius of CP-1 in this direction. Dose
commitment at Diablo was 2 x 10~6 man-rem.
27
-------
The dose estimates for all three locations were equal to or less than
0.001 percent of the radiation protection standard (Appendix A). In fact,
the estimates were <0.002 percent of the dose one would receive from environ-
mental background radiation, which ranges between 83-150 mrem/a for these
locations.
These estimates are about 1/10 of more conservative dose estimates based
upon atmospheric diffusion equations (Appendix B). Calculations with the
latter, under the assumption that the total 663 Ci of 133Xe from all sources
during the year was released at a continuous rate over a period of several
hours under atmospheric conditions which would maximize exposures, resulted
in the following estimates:
Beatty 11 vrem
Indian Springs 11 yrem
Diablo 0.4 yrem
28
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REFERENCES
1. "Effluent and Environmental Monitoring and Reporting," Energy Research and
Development Administration Manual, Chapter 0513. Energy Research and
Development Administration, Washington, D. C.
2. Quiring, Ralph E., "Climatological Data, Nevada Test Site, Nuclear
Rocket Development Station (NRDS)," ERLTM-ARL-7. ESSA Research
Laboratories. August 1968.
3. "Environmental Statement, Underground Nuclear Testing Program Nevada
Test Site," WASH-1562 Draft Copy, U. S. Atomic Energy Commission.
October 1972.
4. "Project Rio Blanco Data Report," NVO-148. U. S. Atomic Energy Commission
and Continental Oil Co. National Technical Information Service, U. S.
Department of Commerce, Springfield, VA. September 1974. p. 1.
5. AEC News Release, NV-74-69. Nevada Operations Office, Atomic Energy
Commission, Las Vegas, NV. December 12, 1974.
6. AEC News Release, NV-74-71. Nevada Operations Office, Atomic Energy
Commission, Las Vegas, NV. December 17, 1974.
7. "Health and Safety Laboratory Environmental Quarterly," HASL-291. Health
and Safety Laboratory, U. S. Energy Research and Development Administra-
tion, NY, NY 10014. April 1, 1975.
8. "Estimates of Ionizing Radiation Doses in the United States, 1960-2000,"
ORP/CSD 72-1. Environmental Protection Agency, Rockville, MD 20952.
pp. 7-11.
9. "Milk Surveillance, May 1974." Radiation Data and Reports, U. S.
Environmental Protection Agency, Washington, D. C. 20460. Vol. 15,
No. 10. October 1974. pp. 661-663.
10. "Environmental Monitoring at Major U. S. Atomic Energy Commission Contractor
Sites, Calendar Year 1973." U. S. Atomic Energy Commission, Washington,
D. C. 20545. pp. 40, 220.
11. Telephone Conversation on February 11, 1975, between R. F. Grossman,
Environmental Protection Agency, NERC-LV, Las Vegas, NV, and C. W. Sill,
Energy Research and Development Administration, Idaho Falls, ID.
29
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AIR FORCE
RANGE
Figure 1. Nevada Test Site Location
30
-------
Nuclear Rocket Development
Station
Figure 2. Nevada Test Site Road and Facility Map
31
-------
Figure 3. Ground Water Flow Systems - NTS
32
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Figure 4. General Land Use, Nevada Test Site Vicinity
33
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A- ADULTS
C- CHILDREN
F- FAMILY COWS
D- DAIRY COWS
A- NO SURVEY CONDUCTED
Figure 5. Population Distribution by Azimuth/Distance
34
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I ° kl7_ i *""/'
1EXICO j
LSB.O© I Aa,LENie «
• «M^^J
TEXAS > ,nillSANA~l
tei..^CHARTS ) SCALE IN KILOMETRES
e«usi.~ F r*[woRi.E.NsO* o iso sal
SPfiiH
MEXICO
Figure 6. Air Surveillance Network
35
-------
DUCKWATERfe
CURRANT MAINT. STA:
® ROUND MTN
GEYSER
MAINT. STA
1
BLUE JAY
MAINT STA
SUNNYSIDE
CLARK'S STA.
WARM
SPGS.
4ADAVEN
TONOPAH
DIABLOO
MAINT.
STA
TEMPIUTE /
GOLDFIEi-D
COYOTE SMT.
HANCOCK SMT. >
I
I
SCOTTY'S JCT
_ GATE TOO
O I NELLIS
BJY | AIR FORCE
j RANGE j
SPRINGDALE
LATHROP WELLS
INDIAN SPRINGS
CACTUS SPRINGS
FURNACE
CREEK
DEATH
VALLEY JCT.
PAHRUMP
LAS VEGAS
SAMPLING STATIONS
SCALE IN MILES SCALE IN KILOMETERS
0 10 2.0 3.0 4.0 50 0 10 20 30 40 50
Figure 7. Noble Gas and Tritium Surveillance Network
36
-------
-I \ I I
ASHIHF..SBM j r&~**~*'
r' \ I / si 01 o
NEVADA
TEST SITE|AIR FnR«,
I RANGE
SCALE IN KILOMETRES
0 10 20 30 40 50
Figure 8. Doslmetry Network
37
-------
NELLIS
NTS AIR FORCE
! RANGE
1 PO BOX 10027
LAS VEGAS NEVADA 89T14
Figure 9. Milk Surveillance Network
38
-------
SCALE IN KILOMETRES X .
\
Figure 10. Water Surveillance Network
39
-------
MUNICIPAL GOLF COURSE
•£
• NERC-LV
HARMON
SCALE IN KILOMETRES
O1 2345
O 1 2 3
SCALE IN MILES
• VEGAS ESTATES
SAMPLING
LOCATION
Figure 11. Water Surveillance Network, Las Vegas Valley
40
-------
MONTHLY
SEMI-ANNUAL
WELL UE19gs
WATERTOWN NO. 3
WELL U2Oa2
EXPERIMENTAL FARM
WELL UE15d
WELL U3CN5
A WELL C
• I
WELL C1
\ I
BUFFER ZONE
WELL UE5c
• I
Nuclear Rocket Development
Station /
ARMY WELL
SCALE IN FEET
MHJBsqBB^gss
10000 O 30000
SCALE IN METRES
Figure 12. On-NTS Long-Term Hydrological Monitoring Program
41
-------
ROAD D WINDMILL
SPRINGDALE •_
GOSS SPGS 1
BEATTY
NELLIS
AIR FORCE
RANGE
NRDS
LATHROP WELLS
TO FURNACE CREEK
A MONTHLY
• SEMI-ANNUAL
SCALE OF KILOMETRES
10 12 I
SCALE OF MILES
• FAIRBANKS SPGS
• 17S/50E-WCAC
CRYSTAL POOL
INDIAN SPGS. j
AFB /
SEWER CO #1
\
\
'X
DEATH VALLEY
JUNCTION
ASH MEADOWS
\
SHOSHONE
Figure 13. Off-NTS Long-Term Hydrological Monitoring Program
42
-------
CARLSBAD
CITY WELL #2 _
' •
MALAGA
CARLSBAD, SCALE IN MILES
5 10
SGZ
PHS-6B
PHS-9BL m
PHS-10 PHS-8
SCALE IN KILOMETRES PECOS RIVER
PUMPING
STATION-1
I Xl_V_
V
OFF-SITE SAMPLING LOCATIONS
1.6 KILOMETRES
1 MILE
USGS TEST WELLS-4&8
8
SGZ
f J
x
.'\
USGS TEST WELL 1
Figure 14.
ON-SITE SAMPLING LOCATION
Long-Term Hydrological Monitoring Locations, Carlsbad, NM,
Project Gnome/Coach
43
-------
FALLON
FRENCHMAN
FLOWING WELL -2
• H-3
HUNTS STATION!
SGZ
HS-1
SCALE IN MILES
0 5
SCALE IN KILOMETRES
0 8
CHURCHILL COUNTY
MINERAL COUNTY
Figure 15. Long-Term Hydrological Monitoring Locations, Fallen, NV,
Project Shoal
44
-------
COLUMBIA
\
T. SPEIGHTSB j« H R. L. ANDERSON
XM. LOWE* "N /^PURVIS
LOWER LITTLE CREEK
SGZ
W. DANIELS JR.
R. READY
BAXTERVILLE
LUMBERTON
SCALE IN KILOMETRES
O 5 1O 15 2O 25 3O 35 4O
SCALE IN MILES
Figure 16. Long-Term Hydrological Monitoring Locations, Project Dribble/
Miracle Play (Vicinity of Tatum Salt Dome, MS)
45
-------
HALF MOON CREEK
x OVERFLOW
LAMAR
CO.
TATUM DOME
HT-2C
SCALE IN METRES
0 100 200 300 400 500 600
LAMAR
COUNTY
LOCATION MAPS
Figure 17. Long-Term Hydrological Monitoring Locations, Project Dribble/
Miracle Play (Tatum Salt Dome, MS)
46
-------
~
TO DULCE CITY WATER
RIO ARRIBA COUNTY
LOCATION MAPS
• BIXLER RN.
TO LA JARA LAKE
BUBBLING SPG.
EPNG WELL 10-36
TO BLANCO "0 SGZ
(SAN JUAN RIVER)
WINDMILL #2
-N-
• CAVE SPG.
ARNOLD RN.
LOWER BURROW
CANYON
SCALE IN KILOMETRES
0
SCALE IN MILES
0 5
Figure 18. Long-Term Hydrological Monitoring Locations, Rio Arriba
County, NM, Project Gasbuggy
-------
POTTER RN.
_
SCHWAB
GRAND VALLEY
CITY WATER
GRAND
VALLEY
A. GARDNER RN.l
4 RULJ[SON/
L. HAYWARD RN.
' \s
\
• \BATTLEMENT CREEK
•'CER TEST WELL
SPRING fe SQZ
IBERNKLAU RN.
I
I
t
I
I
\
K..
-N-
SCALE
VEGA RES
SCALE IN MILES
0 5
Figure 19. Long-Term Hydrological Monitoring Locations, Rulison, CO,
Project Rulison
48
-------
NEVADA
RENO
TONOPAH
CENTRAL NEVADA
>TEST AREA
LAS
"\>T
Asb
SGZ/
%|HTH 2
i
I
I
I
I
i
I
X /
•' /
HOT CREEK RANCH ''
"v/
6 MILE WELL
BLUE JAY SPRING
SCALE IN KILOMETRES
O 1 2345678 /
SCALE IN MILES^
012345 *X
BLUE JAY
MAINT. STA.
Figure 20. Long-Term Hydrological Monitoring Locations Central Nevada
Test Area, Faultless Event
49
-------
Table 1. Underground Testing Conducted Off the Nevada Test Site
Name of Test,
Operation or
Project
Project Gnome/
Coach3
Project Shoal
Project Dribble
(Salmon Event)
Operation Long
Shot
Project Dribble
(Sterling Event)
o
Project Gasbuggy
Faultless Event
Date
12/10/61
10/26/63
10/22/64
10/29/65
12/3/66
12/10/67
1/19/68
Location
48 km (30 mi) SE of
Carlsbad, NM
45 km (28 mi) SE of
Fallen, NV
34 km (21 mi) SW of
Hattiesburg, MI
Amchitka Island, AK
34 km (21 mi) SW of
Hattiesburg, MI
88 km (55 mi) E of
Farmington, NM
Central Nevada Test
Area 96 km (60 mi) E
Yieldd
3.1 ktf
~12 kt
5.3 kt
~80 kt
380 t
29 kt
200 kt-
1 Mt
Depth
m
(ft)
360
(1184)
366
(1200)
823
(2700)
716
(2350)
823
(2700)
1292
(4240)
914
(3000)
d e
Purpose of the Event '
Multi-purpose experiment.
Nuclear test detection
research experiment.
Nuclear test detection
research experiment.
DOD nuclear test detection
experiment .
Nuclear test detection
research experiment .
Joint Government- Indus try
gas stimulation experiment
Calibration test.
Project Miracle 2/2/69
Play (Diode Tube)
of Tonopah, NV
34 km (21 mi) SW of
Hattiesburg, MI
Non- 823
nuclear (2700)
explosion
Project Rulison 9/10/69 19 km (12 mi) SW of
Rifle, CO
Operation MilrowC 10/2/69 Amchitka Island, AK
40 kt
~1 Mt
Project Miracle
Play (Humid
Water)b
Operation
Cannikinc
4/19/70 34 km (21 mi) SW of
Hattiesburg, MI
11/6/71 Amchitka Island, AK
Non-
nuclear
explosion
2568
(8425)
1219
(4000)
823
(2700)
<5 Mt 1829
(6000)
Detonated in Salmon/
Sterling cavity.
Seismic studies.
Gas stimulation experiment,
Calibration test.
Detonated in Salmon/
Sterling cavity.
Seismic studies.
Test of warhead for
Spartan missle
50
-------
Table 1. (continued)
Name of Test,
Operation or
Project
Project Rio
Blanco3
Date Location
5/17/73 48 km (30 mi) SW of
Meeker, CO
Depth
A m
YielcT (ft)
3x30 kt 1780
to
2040
(5840
to
6690)
Purpose of the Event '
Gas stimulation experiment
Plowshare events
Vela Uniform Events
Weapons tests
Information from "Revised Nuclear Test Statistics," distributed on January 15, 1973,
by Henry G. Vermillion, Director, Office of Information Services, U.S. Atomic Energy
Commission, Las Vegas, Nevada.
Q
News release AL-62-50, AEC Albuquerque Operations Office, Albuquerque, New Mexico.
December 1, 1961.
"The Effects of Nuclear Weapons" Rev. Ed. 1964.
51
-------
Table 2. Summary of Analytical Procedures
Counting
Type of Analytical Period
Analysis Equipment (Min)
Gamma Gamma spectro-
Spectroscopy3 meter with
10-cm-thick
by 10-cm-diam-
eter Nal (Tl-
activated)
crystal with
input to 200
channels (0-2
MeV) of 400-
channel, pulse-
height analyzer.
89-90Src Low-background
thin-window,
gas-flow pro-
portional
counter with a
5.7-cm diameter
window (80 yg/cm )
40-100 for
milk and
water sam-
ples; 10-40
for air
filters or
charcoal
cartridges ;
100 for
Long-Term
Hydro .
Water
filters.
50
.
Analytical
Procedures
Radionuclide
concentra-
tions quan-
titated from
gamma spec-
trometer
data by com-
puter using
the matrix
technique.
Chemical
separation by
ion exchange.
Separated sam-
ple counted
successively;
activity cal-
culated by
simultaneous
equations.
Sample
Size
(Litre)
0.4-3.5 for
routine milk
and water
samples ;
350m3 for
air filter
samples ;
7.3 litre
for Long-
Term Hydro.
Water
through
filter.
1.0
Detection
Limitb
For routine milk
and water gen-
erally = lxlO~8
yCi/ml for most
common fallout
radionuclides in
a simple spectrum.
For air filters,
= 1x10- 13 yCi/ml.
For Long-Term
Hydro, sus-
pended solids,
= 3.0xlO~9 '
yCi/ml.
89Sr = 2xlO~9 yCi/ml
90Sr = lxlO~9 yd/ml
3H Enrichment
(Long-Term
Hydrological
Samples)
238,239Pu
234,235,238^
Automatic 200
liquid
scintillation
counter with
output printer.
Automatic 200
scintillation
counter with
output printer.
Alpha spectro- 1000
meter with 45 1400
mm2, 300-ym
depletion depth
silicon surface
barrier detectors
operated in
vacuum chambers.
Sample pre- 0.005
pared by
distillation.
Sample concen- 0.25
trated by
electrolysis
followed by
distillation.
Sample is 1
digested with
acid, separated
by ion exchange,
electroplated on
stainless steel
planchet and count-
ed by alpha spec-
trometer.
yCi/ml
=6.0xlO~9 yCi/ml
238Pu= 4xlO-n
yCi/ml
239Pu, 23"U, 235U
~ 2xlO-n
yCi/ml
52
-------
Table 2. (continued)
Type of
Analysis
Analytical
Equipment
Counting
Period
(Min)
Analytical
Procedures
Sample
Size
(Litre)
Detection
Limitb
226RaC
Gross alpha
Gross beta
in liquid
samples
Gross beta
on air
filters3
Single channel
analyzer
coupled to
P.M. tube
detector.
30
Low-background
thin-window,
gas-flow pro-
portional
counter with a
5.7-cm-diameter
window (80 yg/cm2)
Low-level end
window, gas
flow
proportional
counter with a
12.7-cm-diam-
eter window
(100 mg/cm2)
50
Precipitated 1.5
with Ba, con-
verted to
chloride.
Stored for
30 days for
222Ra 226Ra to
equilibrate.
Radon gas
pumped into
scintillation
cell for alpha
scintillation
count ing.
Sample eva- 0.2
porated;
residue
counted.
=1x10"10 yCi/ml
a = 3xlO~9 yCi/ml
0 = 2xlO~9 uCi/ml
Filters
counted upon
receipt and
at 5 and 12
days after
collection;
last two
counts used
to extra-
polate con-
centration
to mid-col-
lection time
assuming T"1 •2
decay or using
experimentally
derived decay.
10-cm
diameter
glass fiber
filter; sam-
ple collected
from -350 m3.
--• 6 x 10"
yCi/ml
53
-------
Table 2. (continued)
Type of
Analysis
Analytical
Equipment
Counting
Period
(Min)
Analytical
Procedures
Sample
Size
(Litre)
Detection
Limitb
85Kr
Xe
CH3TC
Automatic
liquid scintil-
lation counter
with output
printer.
200
Physical
separation by
gas chroma-
tography; dis-
solved in
toluene "cock-
tail" for count-
ing.
400-
1000
85Kr = 2x10-!2
pCi/ml
Xe = 2x10~12
pCi/ml
CH3T = 2x10"12
uCi/ml
2
Lem, P. N. and Snelling, R. N. "Southwestern Radiological Health Laboratory Data
Analysis and Procedures Manual," SWRHL-21. Southwestern Radiological Health Laboratory,
Environmental Protection Agency, Las Vegas, NV. March 1971.
The detection limit for all samples other than air is defined as that radioactivity which
equals the 2-sigma counting error. The detection limit for gross beta radioactivity
on air filters is defined as that concentration which produces a ±25% counting deviation
at the 95% confidence level. The detection limit for gamma spectroscopy analyses on
air filters is based upon that quantity of radioactivity which can be recognized in a
gamma spectrum.
"Johns, F. B. "Handbook of Radiochemical Analytical Methods," EPA 680/4-75-001.
Environmental Protection Agency, NERC-LV, Las Vegas, NV. February 1975.
54
-------
Table 3. 1974 Summary of Analytical Results
for the Air Surveillance Network
Radioactivity Concentration
Sampling
Location
Kingman, AZ
Seligman, AZ
Death Valley Jet., CA
Furnace Creek, CA
No . Days
Sampled
3.0
50.0
22.0
26.0
19.0
22.0
17.0
11.0
6.0
11.0
6.0
41.0
16.0
25.0
16.0
22.0
39.0
11.0
28.0
3.0
11.0
25.0
Type of
Radioactivity
7Be
95Zr
103Ru
106Ru
lltlCe
l**Ce
95Zr
103Ru
106Ru
141Ce
l**Ce
95Zr
103Ru
106Ru
lltlCe
l**Ce
95Zr
103Ru
106Ru
11+0Ba
lltlCe
1IflfCe
\j.\j
CMax
0.17
1.2
0.10
0.59
0.12
0.54
0.46
0.072
0.36
0.086
0.50
0.43
0.098
0.60
0.081
0.59
0.52
0.12
0.64
0.050
0.13
0.51
p \j j- / m j. /
CMin
0.17
0.058
0.036
0.020
0.041
0.18
0.22
0.053
0.34
0.048
0.36
0.088
0.060
0.32
0.060
0.31
0.099
0.046
0.25
0.050
0.052
0.28
Avg
0.0014
0.042
0.0040
0.023
0.0039
0.022
0.016
0.0018
0.0058
0.0020
0.0071
0.038
0.0035
0.031
0.0035
0.027
0.032
0.0022
0.033
0.00043
0.0021
0.028
55
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Sho shone, CA
Needles, CA
Bar stow, CA
Bishop, CA
No . Days
Sampled
22.0
11.0
11.0
11.0
11.0
21.0
21.0
4.0
17.0
18.0
6.0
12.0
6.0
9.0
54.0
13.0
41.0
7.0
13.0
27.0
Type of
Radioactivity
95Zr
103Ru
106Ru
141Ce
l^Ce
95Zr
l°6Ru
14°Ba
l^Ce
95Zr
103Ru
106Ru
141Ce
^"Ce
95Zr
103Ru
106Ru
14°Ba
^Ce
^"Ce
\-i_vy
CMax
0.50
0.081
0.73
0.090
0.53
0.40
0.58
0.044
0.52
0.28
0.056
0.30
0.055
0.35
0.76
0.11
1.1
0.058
0.11
1.0
yi\sJ*/ 1UJ.>
CMin
0.21
0.046
0.30
0.065
0.23
0.077
0.25
0.044
0.17
0.054
0.028
0.088
0.044
0.14
0.10
0.047
0.21
0.046
0.066
0.17
cb
Avg
0.021
0.0018
0.012
0.0024
0.012
0.030
0.049
0.0010
0.041
0.0084
0.00071
0.0068
0.00083
0.0064
0.040
0.0029
0.049
0.00095
0.0030
0.032
56
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Lone Pine, CA
Ridgecrest, CA
Baker, CA
Alamo, NV
No . Days
Sampled
21.0
9.0
12.0
9.0
12.0
2.0
19.0
9.0
8.0
9.0
8.0
38.0
17.0
21.0
17.0
21.0
6.0
41.0
17.0
19.0
3.0
11.0
13.0
Type of
Radioactivity
95Zr
103Ru
106Ru
i^Ce
l"*Ce
7Be
95Zr
103Ru
106Ru
1£tlCe
l*"Ce
95Zr
103Ru
106Ru
1(tlCe
l**Ce
7Be
95Zr
103Ru
106Ru
ll*°Ba
141Ce
llfltCe
V.J.U
CMax
0.39
0.075
0.52
0.080
0.49
0.28
0.42
0.062
0.66
0.063
0.64
0.44
0.10
0.60
0.080
0.55
0.21
0.36
0.36
0.49
0.052
0.28
0.45
H\_>j-/ uij_>
CMin
0.23
0.062
0.28
0.050
0.34
0.28
0.12
0.049
0.17
0.046
0.28
0.18
0.034
0.32
0.051
0.31
0.17
0.032
0.038
0.025
0.052
0.044
0.27
Avg
0.023
0.0021
0.017
0.0021
0.017
0.0015
0.013
0.0014
0.0077
0.0014
0.0083
0.032
0.0034
0.024
0.0032
0.025
0.0032
0.023
0.0041
0.018
0.00043
0.0029
0.013
57
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Beatty, NV
Caliente, NV
Diablo, NV
Ely, NV
No . Days
Sampled
35.0
19.0
14.0
19.0
14.0
6.0
42.0
22.0
17.0
22.0
14.0
35.0
16.0
19.0
3.0
16.0
16.0
14.0
3.0
11.0
3.0
3.0
8.0
Type of
Radioactivity
95Zr
103Ru
106Ru
1!tlCe
l**Ce
7Be
95Zr
103Ru
106Ru
lltlCe
l**Ce
95Zr
103RU
106Ru
1It0Ba
llflCe
l**Ce
95Zr
103Ru
106Ru
^Ofia
ll+1Ce
llflfCe
\ JLW
CMax
0.47
0.076
0.41
0.10
0.43
0.17
0.37
0.080
0.39
0.082
0.38
0.66
0.096
0.41
0.055
0.087
0.42
0.48
0.048
0.37
0.043
0.045
0.64
H\^j_/ iiij_j
CMin
0.10
0.028
0.25
0.033
0.25
0.13
0.026
0.039
0.015
0.036
0.13
0.068
0.042
0.24
0.055
0.031
0.21
0.074
0.048
0.23
0.043
0.045
0.17
cb
Avg
0.027
0.0030
0.013
0.0034
0.014
0.0026
0.025
0.0036
0.012
0.0037
0.011
0.028
0.0028
0.018
0.00045
0.0025
0.014
0.0091
0.00042
0.0084
0.00037
0.00039
0.0084
58
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Fallini's Rch., NV
(Twin Springs)
Goldfield, NV
Hiko, NV
Indian Springs, NV
No . Days
Sampled
5.0
55.0
25.0
31.0
3.0
22.0
23.0
18.0
9.0
9.0
9.0
9.0
3.0
50.0
23.0
25.0
3.0
23.0
19.0
8.0
8.0
8.0
Type of
Radioactivity
7Be
95Zr
103Ru
106Ru
14°Ba
lltlCe
i^Ce
95Zr
103Ru
106Ru
141Ce
14t*Ce
7Be
95Zr
103Ru
106Ru
11+0Ba
141Ce
l^ce
95Zr
103Ru
141Ce
VO.V/
CMax
0.40
0.93
0.072
0.66
0.47
0.088
0.65
0.42
0.057
0.35
0.084
0.54
0.17
0.50
0.094
0.50
0.060
0.090
0.54
0.28
0.056
0.061
p \J J- / Ul-L ^
CMin
0.21
0.051
0.021
0.024
0.47
0.033
0.16
0.20
0.032
0.29
0.056
0.29
0.17
0.082
0.028
0.019
0.060
0.040
0.18
0.17
0.047
0.036
cb
AVK
0.0041
0.044
0.0036
0.029
0.0041
0.0040
0.024
0.015
0.0013
0.0085
0.0017
0.011
0.0014
0.035
0.0035
0.025
0.00051
0.0041
0.018
0.0055
0.0011
0.0012
59
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Las Vegas, NV
Lathrop Wells, NV
Lund, NV
Mesquite, NV
No . Days
Sampled
36.0
15.0
20.0
5.0
15.0
15.0
24.0
13.0
11.0
13.0
11.0
35.0
19.0
16.0
3.0
19.0
13.0
16.0
13.0
3.0
13.0
3.0
Type of
Radioactivity
95Zr
103Ru
106Ru
140Ba
141Ce
l**Ce
95Zr
103RU
106Ru
141Ce
lttl*Ce
95Zr
103Ru
106Ru
11+0Ba
141Ce
l**Ce
95Zr
103Ru
106Ru
ll+1Ce
lkkCe
\j.\j
CMax
0.44
0.10
0.46
0.049
0.095
0.44
0.35
0.064
0.34
0.079
0.37
0.38
0.072
0.48
0.033
0.075
0.52
0.32
0.078
0.37
0.071
0.30
[l^i J./ U1J./
CMin
0.065
0.038
0.15
0.048
0.059
0.16
0.022
0.049
0.25
0.051
0.27
0.099
0.034
0.24
0.033
0.032
0.30
0.21
0.036
0.37
0.042
0.30
Avg
0.025
0.0028
0.018
0.00066
0.0032
0.014
0.016
0.0020
0.0090
0.0022
0.0091
0.024
0.0030
0.016
0.00028
0.0029
0.013
0.011
0.0017
0.0030
0.0020
0.0025
60
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Pahrump , NV
Pioche, NV
Tonopah, NV
TTR, NV
No . Days
Sampled
42.0
19.0
13.0
2.0
11.0
9.0
37.0
16.0
21.0
3.0
13.0
18.0
50.0
16.0
34.0
6.0
16.0
18.0
25.0
9.0
16.0
3.0
9.0
13.0
Type of
Radioactivity
95Zr
103Ru
106Ru
llf0Ba
1(tlCe
l**Ce
95Zr
103Ru
106Ru
llt0Ba
lltlCe
l*«Ce
"Zr
103Ru
106Ru
llt0Ba
i^Ce
l^Ce
95Zr
103Ru
106Ru
1£t°Ba
lltlCe
lf+t|Ce
\JLU
CMax
0.34
0.085
0.95
0.079
0.072
0.48
0.35
0.087
0.45
0.036
0.091
0.48
0.72
0.078
0.63
0.064
0.10
0.51
0.42
0.054
0.72
0.053
0.072
0.61
|J \-» JL / 111 J. /
CMin
0.026
0.020
0.25
0.079
0.036
0.25
0.066
0.037
0.18
0.036
0.048
0.26
0.062
0.051
0.18
0.040
0.050
0.22
0.078
0.040
0.21
0.053
0.034
0.28
cb
Avg
0.020
0.0026
0.016
0.00044
0.0018
0.0090
0.026
0.0026
0.020
0.00030
0.0025
0.018
0.038
0.0029
0.032
0.00086
0.0030
0.020
0.019
0.0013
0.017
0.00049
0.0016
0.014
61
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Warm Springs, NV
Pedersen Valley
View Rch., NV
Eureka, NV
Currant, NV
Blue Eagle Ranch
No . Days
Sampled
12.0
8.0
4.0
5.0
4.0
28.0
12.0
16.0
9.0
16.0
26.0
10.0
16.0
7.0
16.0
25.0
7.0
18.0
7.0
18.0
Type of
Radioactivity
95Zr
103Ru
106Ru
1!tlCe
l**Ce
95Zr
103Ru
106Ru
lltlCe
i^Ce
95Zr
103Ru
10GRu
l^lCe
l**Ce
103Ru
106Ru
lftlCe
1[tttCe
\ J. V
CMax
0.37
0.071
0.41
0.076
0.48
0.40
0.080
0.46
0.082
0.42
0.46
0.093
0.65
0.073
0.69
0.55
0.12
0.67
0.11
0.58
(JV^J./ LUJ-S
CMin
0.19
0.037
0.41
0.071
0.48
0.18
0.060
0.25
0.044
0.24
0.18
0.043
0.28
0.044
0.32
0.14
0.056
0.20
0.065
0.21
Avg
0.026
0.0034
0.012
0.0028
0.014
0.022
0.0024
0.015
0.0016
0.015
0.020
0.0018
0.018
0.0011
0.018
0.022
0.0017
0.018
0.0016
0.019
62
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Blue Jay, NV
Groom Lake, NV
Sunnyside, NV
Lida, NV
No . Days
Sampled
3.0
51.0
24.0
27.0
24.0
21.0
39.0
20.0
19.0
20.0
19.0
17.0
5.0
11.0
5.0
11.0
23.0
7.0
16.0
7.0
16.0
Type of
Radioactivity
7Be
95Zr
103Ru
106Ru
11+1Ce
^Ce
95Zr
103Ru
106Ru
lltlCe
l**Ce
95Zr
103RU
106Ru
11+1Ce
l**Ce
"Zr
103Ru
106Ru
11+1Ce
lkkCe
VJ-vy
CMax
0.23
0.45
0.077
0.65
0.079
0.71
0.35
0.081
0.58
0.067
0.57
0.35
0.057
0.44
0.058
0.50
0.45
0.090
0.65
0.11
0.48
)JVs-L/ Lll.L>
CMin
0.23
0.059
0.027
0.026
0.035
0.25
0.10
0.039
0.29
0.030
0.22
0.13
0.040
0.24
0.047
0.23
0.19
0.065
0.19
0.036
0.27
Avg
0.0019
0.036
0.0034
0.023
0.0040
0.025
0.030
0.0034
0.023
0.0029
0.021
0.013
0.00081
0.011
0.00090
0.014
0.019
0.0015
0.016
0.0015
0.016
63
-------
Table 3. (continued)
Sampling
Location
Round Mountain, NV
Austin, NV
Nyala, NV
Scotty's Jet. , NV
Duckwater, NV
No . Days
Sampled
32.0
7.0
25.0
3.0
7.0
22.0
9.0
11.0
4.0
32.0
11.0
21.0
5.0
11.0
16.0
3.0
44.0
17.0
27.0
14.0
25.0
11.0
11.0
8.0
Type of
Radioactivity
95Zr
103RU
106Ru
11+0Ba
1[tlCe
^Ce
95Zr
106Ru
llt°Ba
95Zr
103Ru
106Ru
^^Ba
1£t*Ce
l^Ce
7Be
95Zr
103Ru
106Ru
1JtlCe
l^Ce
95Zr
106Ru
1£tt*Ce
Radioactivity Concentration
(10 ^yCi/ml) ,
C C C
Max Min Avg
0.54
0.074
0.81
0.051
0.11
0.81
0.86
0.24
0.028
0.56
0.12
0.59
0.084
0.14
0.86
0.28
0.41
0.089
0.73
0.083
0.54
0.48
0.60
0.62
0.076
0.057
0.24
0.051
0.072
0.15
0.045
0.097
0.028
0.10
0.035
0.26
0.068
0.039
0.40
0.28
0.15
0.028
0.035
0.038
0.028
0.13
0.20
0.33
0.025
0.0014
0.026
0.00046
0.0018
0.022
0.0073
0.0063
0.00038
0.027
0.0018
0.021
0.0011
0.0021
0.022
0.0024
0.033
0.0027
0.027
0.0023
0.024
0.0081
0.011
0.0094
64
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Stone Cabin Rch., NV
St. George, UT
Garrison, UT
Cedar City, UT
Milford, UT
No . Days
Sampled
11.0
11.0
11.0
24.0
17.0
8.0
17.0
8.0
34.0
15.0
19.0
3.0
15.0
16.0
3.0
3.0
3.0
19.0
6.0
13.0
6.0
13.0
Type of
Radioactivity
95Zr
106Ru
l**Ce
S5Zr
103Ru
106Ru
1!tlCe
l**Ce
95Zr
103Ru
106Ru
1 l+0g-
^ ** ^Ce
l**Ce
9 ^Zr
103Ru
l«Ce
95Zr
103Ru
106Ru
l^Ce
l^Ce
\j.»j
Max
0.49
0.75
0.57
0.47
0.077
0.41
0.091
0.67
0.35
0.075
0.46
0.050
0.075
0.38
0.20
0.072
0.036
0.33
0.064
0.36
0.064
0.36
H\-*-i-/ mj_>
CMin
0.21
0.25
0.29
0.21
0.055
0.33
0.047
0.34
0.082
0.049
0.19
0.050
0.053
0.18
0.20
0.072
0.036
0.16
0.060
0.20
0.060
0.18
Avg
0.0081
0.012
0.011
0.024
0.0030
0.0079
0.0033
0.012
0.023
0.0027
0.019
0.00042
0.0026
0.014
0.0024
0.00087
0.00043
0.013
0.0011
0.012
0.0011
0.0100
65
-------
Table 3. (continued)
Radioactivity Concentration
Sampling
Location
Delta, UT
No . Days
Sampled
12.0
6.0
6.0
6.0
6.0
Type of
Radioactivity
95Zr
103Ru
106Ru
l^Ce
!^Ce
VJ.U
CMax
0.31
0.055
0.40
0.059
0.34
|a vi a. / ui-i- ,
CMin
0.16
0.022
0.31
0.039
0.33
Avg
0.0084
0.00066
0.0061
0.00083
0.0057
Represents the number of sampling days of the year during which the radionuclide was
detected.
All averages were computed over the total operating time of each station during the
year. The total times for the stations were slightly less than 365 days due to equipment
failure etc.; however, the concentration averages were considered to be representative
for the full year. Due to the lack of statistically derived MDC's, the averages were
calculated assuming that concentrations were zero when the nuclides could not be detected.
66
-------
Table 4. 1974 Summary of Analytical Results
for the Noble Gas and Tritium Surveillance Network
Sampling
Location
Death Valley
Jet., CA
Beatty, NV
Diablo, NV
Hiko, NV
No . Days
Sampled
328
328
344
344
352
356
363
363
363
363
363
356
356
357
349
357
357
348
348
298
341
298
298
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
Type of
Radio-
activity
85Kr
Total
3H as
3H as
3H as
3H as
85Kr
133Xe
3H as
3H as
3H as
3H as
85Kr
133Xe
3H as
3H as
3H as
3H as
85Kr
Total
3H as
3H as
3H as
3H as
Xe
HTO
CH3T
HTO
HT
HTO
CH3T
HTO
HT
HTO
CH3T
HTO
HT
Xe
HTO
CH3T
HTO
HT
10"
10"
10"
10"
10"
10"
10"
10"
10~
10"
10"
10"
10"
10"
10"
10"
10"
10"
10"
10"
10~
10~
10"
10"
Units
12yCi/ml
12yCi/ml
6yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
6yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
6yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
12yCi/ml
air
air
H20
air
air
air
air
air
H20
air
air
air
air
air
H20
air
air
air
air
air
6yCi/ml H20
12yCi/ml
12yCi/ml
12yCi/ml
air
air
air
CMax
29
< 5.4
< 1.6
9.4
6.2
12
27
140
< 2.1
< 5.0
6.1
10
29
17
0.98
5.6
7.2
5.7
22
< 6.2
< 1.6
< 5.0
4.4
2.7
C C
Min Avg
13
< 2.
< 0.
< 1.
< 0.
< 0.
12
< 2.
< 0.
< 1.
< 0.
< 0.
13
< 2.
< 0.
< 1.
< 0.
0.
12
< 2.
< 0.
< 1.
< 0.
< 0.
18
0 < 3.3
21 < 0.46
3 < 3.1
23 < 2.0
14 < 2.6
17
0 < 7.4
22 < 0.51
7 < 3.0
56 < 2.5
42 < 2.3
17
0 < 3.7
21 < 0.44
4 < 3.0
82 < 2.3
25 < 1.5
17
0 < 3.2
21 < 0.39
7 < 3.0
48 < 1.8
37 < 0.88
% of
Cone.
Guide*
a
0.018
<0.0033
-
<0.011
0.017
<0.0074
-
<0.012
0.017
<0.0037
-
<0.010
0.017
<0.0032
-
<0.0086
67
-------
Table 4. (continued)
Sampling
Location
Las Vegas, NV
NVOO
NTS, NV
Desert Rock
NTS, NV
BJY
NTS, NV
Gate 700
No . Days
Sampled
295
.0
290.0
342
297
342
342
355
368
368
361
368
368
327
340
355
340
355
355
348
348
356
342
356
356
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
.0
Type of
Radio-
activity
85Kr
Total
3H as
3H as
3H as
3H as
85Kr
133Xe
3H as
3H as
3H as
3H as
85Kr
133Xe
3H as
3H as
3H as
3H as
85Kr
Total
3H as
3H as
3H as
3H as
Xe
HTO
CH3T
HTO
HT
HTO
CH3T
HTO
HT
HTO
CH3T
HTO
HT
Xe
HTO
CH3T
HTO
HT
Units
10~12yCi/ml
10~12yCi/ml
10~6yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~6yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~6yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~12yCi/ml
10~6yCi/ml
10"12yCi/ml
10~12yCi/ml
10~12yCi/ml
air
air
H20
air
air
air
air
air
H20
air
air
air
air
air
H20
air
air
air
air
air
H20
air
air
air
CMax
21
< 6.9
1.2
< 5.0
5.9
<18
31
53
3.0
< 8.8
15
9.2
32
1000
13
20
59
34
22
6.3
8.3
6.3
35
<14
C C
Min Avg
13
< 2
< 0
< 1
< 0
< 0
12
< 2
< 0
< 1
< 0
< 0
13
< 2
0
< 1
10
< 0
12
< 2
< 0
< 1
0
0
17
.0 < 3.4
.21 < 0.40
.7 < 2.8
.45 < 2.0
.28 < 1.2
18
.0 < 4.2
.21 < 0.50
.5 < 3.0
.74 < 2.6
.36 < 1.4
19
.0 <44
.26 3.0
.7 < 3.5
13
.34 < 4.1
17
.0 < 3.3
.21 < 0.78
.7 < 3.1
.64 < 3.6
.58 < 3.7
% of
Cone.
Guide*
0.017
<0.0034
-
<0.0089
0.00018
<0. 000042
-
<0. 00014
0.00019
<0. 00044
-
<0. 00041
0.00017
<0. 000033
-
<0. 00021
68
-------
Table 4. (continued)
Sampling
Location
NTS, NV
Area 12
No . Days
Sampled
334.
361.
354.
361.
353.
353.
0
0
0
0
0
0
Type of
Radio-
activity
85Kr
*33Xe
3H
3H
3H
3H
as HTO
as CH3T
as HTO
as HT
Units
10"12yCi/ml
10~12yCi/ml
10"6yCi/ml
10~12yCi/ml
10"12yCi/ml
10~12yCi/ml
air
air
H20
air
air
air
Max
23
1100
93
< 8.5
600
36
€„. C.
Mm Avg
10
< 2
< 0
< 1
2
0
18
.0 <16
.26 <13
.7 < 3.2
.0 <59
.34 < 4.0
% of
Cone.
Guide*
0.00018
<0. 00016
-
<0.0013
Tonopah, NV
344.0 85Kr 10~12yCi/ml air 25 11 18 0.018
356.0 Total Xe 10~12yCi/ml air <6.9 <2.0 <3.7 <0.0037
357.0 3H as HTO 10~6yCi/ml H20 1.0 < 0.21 < 0.42
350.0 3H as CH3T 10~12yCi/ml air < 5.0 < 1.7 < 2.8
357.0 3H as HTO 10~12yCi/ml air 5.2 < 0.59 < 2.0 <0.010
364.0 3H as HT 10~12yCi/ml air 4.5 < 0.41 < 1.9
* 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.
69
-------
Table 5. 1974 Summary of Background Radiation Doses for the Dosimetry Network
Station
Location
Adaven, NV
Alamo, NV
Baker, CA
Bars tow, CA
Beatty, NV
Bishop, CA
Blue Eagle Rch., NV
Blue Jay, NV
Cactus Springs, NV
Caliente, NV
Casey's Ranch, NV
Cedar City, UT
Clark Station, NV
Coyote Summit, NV
Currant, NV
Death Valley Jet . , CA
Desert Game Range, NV
Diablo Maint. Sta. , NV
Duckwater, NV
Elgin, NV
Ely, NV
Enterprise, UT
Furnace Creek, CA
Geyser Maint. Sta., NV
Goldfield, NV
Groom Lake, NV
Measurement
Period
1/16/74 -
1/07/74 -
1/14/74 -
1/14/74 -
1/08/74 -
1/16/74 -
1/16/74 -
1/17/74 -
1/07/74 -
1/10/74 -
1/08/74 -
1/16/74 -
1/17/74 -
1/07/74 -
1/16/74 -
1/17/74 -
1/07/74 -
1/09/74 -
1/16/74 -
1/11/74 -
1/15/74 -
1/16/74 -
1/08/74 -
1/14/74 -
1/08/74 -
1/17/74 -
1/08/75
1/06/75
1/06/75
1/06/75
1/14/75
1/08/75
1/07/75
1/08/75
1/13/75
1/08/75
1/07/75
1/15/75
1/08/75
1/06/75
1/07/75
1/15/75
1/13/75
1/09/75
1/07/75
1/08/75
1/06/75
1/15/75
1/08/75
1/06/75
1/13/75
1/06/75
Background Dose
Equivalent Rate (mrem/d)
Max . Min . Avg .
0.46
0.36
0.34
0.36
0.38
0.35
0.33
0.40
0.26
0.43
0.29
0.28
0.38
0.40
0.40
0.34
0.21
0.43
0.40
0.49
0.38
0.37
0.27
0.35
0.40
0.31
0.35
0.23
0.24
0.28
0.36
0.26
0.14
0.34
0.19
0.26
0.23
0.22
0.32
0.30
0.21
0.24
0.17
0.36
0.26
0.27
0.31
0.31
0.21
0.30
0.26
0.11
0.41
0.32
0.29
0.33
0.37
0.30
0.24
0.38
0.22
0.34
0.26
0.26
0.36
0.36
0.31
0.28
0.19
0.40
0.35
0.40
0.34
0.33
0.24
0.32
0.32
0.23
Annual
Adjusted
Background
Dose
Equivalent
(mrem/a)
150
120
110
120
140
110
86
140
80
120
96
95
130
130
110
100
68
150
130
150
130
120
87
120
120
83
70
-------
Table 5. (continued)
Station
Location
Hancock Summit, NV
Hiko, NV
Hot Creek Ranch, NV
Independence, CA
Indian Springs, NV
Kirkeby Ranch, NV
Koynes , NV
Las Vegas (McCarran) , NV
Las Vegas (Placak) , NV
Las Vegas (USDI), NV
Lathrop Wells, NV
Lida, NV
Lone Pine, CA
Lund, NV
Manhattan, NV
Mesquite, NV
Nevada Farms, NV
Nuclear Eng. Co., NV
Nyala, NV
Olancha, CA
Pahrump, NV
Pine Creek Ranch, NV
Pioche, NV
Queen City Summit, NV
Reed Ranch, NV
Ridgecrest, CA
Round Mountain, NV
Measurement
Period
1/07/74
1/07/74
1/17/74
1/16/74
1/07/74
1/14/74
1/09/74
1/14/74
1/14/74
1/14/74
1/09/74
1/07/74
1/16/74
1/16/74
1/10/74
1/15/74
1/07/74
1/09/74
1/08/74
1/15/74
1/10/74
1/16/74
1/10/74
1/07/74
1/07/74
1/15/74
1/09/74
- 1/06/75
- 1/06/75
- 1/08/75
- 1/07/75
- 1/13/75
- 1/06/75
- 1/09/75
- 1/10/75
- 1/10/75
- 1/10/75
- 1/15/75
- 1/13/75
- 1/07/75
- 1/08/75
- 1/14/75
- 1/13/75
- 1/06/75
- 1/15/75
- 1/07/75
- 1/07/75
- 1/16/75
- 1/08/75
- 1/07/75
- 1/06/75
- 1/06/75
- 1/07/75
- 1/14/75
Background Dose
Equivalent Rate (mrem/d)
Max. Min. Avg.
0.46
0.32
0.36
0.38
0.25
0.30
0.36
0.21
0.26
0.33
0.37
0.45
0.37
0.33
0.51
0.28
0.42
0.39
0.31
0.32
0.34
0.38
0.35
0.46
0.40
0.27
. 0.41
0.32
0.21
0.27
0.28
0.22
0.23
0.27
0.09
0.13
0.13
0.28
0.32
0.26
0.23
0.37
0.18
0.32
0.33
0.25
0.26
0.24
0.34
0.30
0.37
0.32
0.23
0.30
0.41
0.28
0.31
0.33
0.23
0.27
0.32
0.17
0.20
0.24
0.32
0.37
0.31
0.28
0.43
0.25
0.36
0.36
0.29
0.29
0.29
0.37
0.34
0.42
0.37
0.25
0.37
Annual
Adjusted
Background
Dose
Equivalent
(mrem/a)
150
100
110
120
83
100
120
62
74
86
120
130
110
100
160
90
130
130
110
100
100
140
120
150
130
92
140
71
-------
Table 5. (continued)
Station
Location
Scotty's Junction, NV
Selbach Ranch, NV
Sherri's Bar, NV
Sho shone, CA
Spring Meadows, NV
Springdale, NV
St. George, UT
Sunnyside, NV
Tempiute, NV
Tenneco, NV
Tonopah Test Range, NV
Tonopah, NV
Twin Springs Ranch, NV
Valley View Ranch, NV
Warm Springs, NV
Young's Ranch, NV
Measurement
Period
1/07/74 -
1/09/74 -
1/07/74 -
1/17/74 -
1/10/74 -
1/10/74 -
1/17/74 -
1/16/74 -
1/09/74 -
1/10/74 -
1/08/74 -
1/08/74 -
1/10/74 -
1/15/74 -
1/17/74 -
1/09/74 -
1/10/75
1/16/75
1/06/75
1/15/75
1/16/75
1/14/75
1/13/75
1/08/75
1/06/75
1/16/75
1/09/75
1/09/75
1/08/75
1/13/75
1/08/75
1/14/75
Background Dose
Equivalent Rate (mrem/d)
Max. Min. Avg.
0.45
0.36
0.30
0.41
0.25
0.42
0.30
0.34
0.36
0.39
0.35
0.52
0.43
0.32
0.38
0.38
0.34
0.30
0.21
0.32
0.23
0.37
0.18
0.26
0.16
0.34
0.27
0.34
0.31
0.21
0.30
0.29
0.39
0.33
0.26
0.35
0.24
0.39
0.25
0.30
0.30
0.36
0.31
0.40
0.37
0.25
0.35
0.32
Annual
Adjusted
Background
Dose
Equivalent
(mrem/a)
140
120
93
130
89
140
91
110
110
130
110
150
130
91
130
120
72
-------
Table 6. 1974 Summary of Analytical Results for the Milk Surveillance Network
No. Type of
Radioactivity Cone.
Sampling
Location
Bishop , CA
Sierra Creamery
Hinkley, CA
Bill Nelson Dairy
Olancha, CA
Hunter Ranch
Alamo, NV
Williams Dairy
Austin, NV
Young's Ranch
Currant, NV
Blue Eagle Ranch
Sample of
Type Samples
11 4
4
4
12 4
4
4
13 3
3
. 3
12 3
3
3
13 4
4
4
4
13 4
4
4
Radio
activity
137Cs
89Sr
90Sr
137Cs
89Sr
9°Sr
137Cs
89Sr
. 9°Sr
137Cs
89Sr
9°Sr
137Cs
89Sr
90Sr
3H
137CS
89Sr
90Sr
\ Ju \J \A\SJ~flUJ.J
CMax CMin
<10 <10 •
< 2.7 < 1.4
2.2 < 1.2
<10 <10
< 2.6 < 1.4
1.5 < 0.88
<10 <10
< 1.9 < 1.3
< 1.1 < 0.92
<10 <10
< 1.8 < 1.6
1.9 < 1.0
<10 <10
< 3.4 < 1.4
2.2 < 1.5
910 560
25 <10
< 2.4 < 1.4
< 2.0 < 1.0
Avg
<10
< 1.9
< 1.7
<10
< 1.8
< 1.3
<10
< 1.5
< 1.0
<10
< 1.7
< 1.3
<10
< 2.1
< 1.8
768
<14
< 1.8
< 1.4
73
-------
Table 6. (continued)
No. Type of
Radioactivity Cone.
Sampling
Location
Currant, NV
Manzonie Ranch
Hiko, NV
Schofield Dairy
Indian Springs, NV
Indian Springs Rch.
Las Vegas, NV
LDS Dairy Farm
Lathrop Wells, NV
William J. Kirker
Lida, NV
Lida Livestock Co.
Sample of
Type Samples
13 4
4
4
12 4
4
4
4
13 1
' 1
1
12 4
4
4
4
13 3
3
3
13 4
4
4
Radio
activity
137Cs
89Sr
90Sr
137Cs
89Sr
9°Sr
3H
!37Cs
89Sr
90Sr
!37Cs
89Sr
90Sr
3H
137CS
89Sr
90Sr
137Cs
89Sr
90Sr
V.J.V/ ^IOJL./ UIJLJ
C C C
Max Min Avg
<10 <10 <10
< 2.7 < 1.2 < 1.9
2.0 < 1.0 < 1.5
<10 <10 <10
< 4.2 < 1.5 < 2.3
3.8 < 1.1 < 2.1
430 <240 <340
<10 <10 <10
< 2.9 < 2.9 < 2.9
< 1.1 < 1.1 < 1.1
<10 <10 <10
< 2.9 < 1.1 < 1.7
1.7 < 0.98 < 1.2
350 <260 <290
<10 <10 <10
< 3.3 < 1.3 < 2.2
1.5 < 1.1 < 1.3
<10 <10 <10
< 3.7 < 1.4 < 2.2
2.6 < 0.87 < 1.4
74
-------
Table 6. (continued)
Sampling
Location
Logandale, NV
Vegas Valley Dairy
Lund, NV
McKenzie Dairy
Mesquite, NV
Hughes Bros. Dairy
Moapa , NV
Searles Dairy
Nyala, NV
Sharp ' s Ranch
Pahrump, NV
Burson Ranch
No.
Sample of
Type Samples
12 4
4
4
12 4
4
4
4
12 4
' 4
4
4
12 4
4
4
13 3
4
V
4
13 4
4
4
Type of
Radio
activity
137Cs
89Sr
90Sr
137Cs
89Sr
9°Sr
3H
137Cs
89Sr
90Sr
3H
137Cs
89Sr
90Sr
89Sr
90Sr
3H
137Cs
89Sr
90Sr
J.XCLU JtW
(10
CMax
< 5.5
3.6
< 2.4
2.0
790
< 3.2
2.6
240
< 3.6
2.8
< 3.6
2.9
340 '
< 3.2
1.5
aw *- J. v J. t- j vjv
~9MCi/ml)
CMin
< 1.5
< 1.2
< 1.3
1.1
<220
< 1.3
< 0.96
<230
< 1.4
< 0.97
< 1.5
< 0.97
<210
< 1.2
< 0.82
Avg
< 2.8
< 2.3
< 1.8
< 1.5
<370
< 1.9
< 1.4
<230
< 2.1
< 1.7
< 2.1
< 2.0
<260
< 1.8
< 1.1
75
-------
Table 6. (continued)
Sampling
Location
Panaca, NV
Kenneth Lee Ranch
Round Mountain, NV
Russell Berg Ranch
Round Mountain, NV
Karl Berg Ranch
Sho shone, NV
Kirkeby Ranch
Springdale, NV
Seidentopf Ranch
Gedar City, UT
Western Gold Dairy
No.
Sample of
Type Samples
13 3
4
4
13 1
1
1
13 1
1
' 1
13 4
4
4
13 4
4
4
12 4
4
4
Type of
Radio
activity
137Cs
89Sr
90Sr
137Cs
89gr
90Sr
137Cs
89Sr
9°Sr
!37Cs
89Sr
90Sr
137Cs
89Sr
90Sr
137Cs
89Sr
90Sr
I\.dUJ-Ucn_ i_j-v .ki-y v>u
(10~9uCi/ml)
CMax CMin
<10 <10 *
< 3.3 < 1.2
1.8 < 0.93
<10 <10
< 3.5 < 3.5
< 1.3 < 1.3
<10 <10
< 1.8 < 1.8
4.5 4.5
<10 <10
< 2.8 < 1.8
3.8 < 1.2
<10 <10
< 3.3 < 1.6
< 1.8 < 1.2
<10 <10
< 3.2 < 1.2
3.3 < 1.4
iic .
AVR
< 2.1
< 1.4
<10
< 3.5
< 1.3
<10
< 1.8
4.5
<10
< 2.2
< 2.6
<10
< 2.2
< 1.4
<10
< 2.1
< 2.0
76
-------
Table 6. (continued)
No. Type of
Radioactivity Cone.
St
R.
Sampling
Location
. George, UT
Cox Dairy
Sample
Typea
12
of
Samples
4
4
4
Radio
activity
89Sr
90Sr
V.J.U
Max
<10
< 3.1
1.3
M o J_ / UIJ.J
CMin
< 1.3
< 0.98
AVR
< 2.1
< 1.2
11 = Pasteurized Milk
12 = Raw Milk from Grade A Producer(s)
13 = Raw Milk from family cow(s)
77
-------
Table 7. 1974 Summary of Analytical Results for the Water Surveillance Network -
Surface Water Samples
% of
Sampling Sample Collection
Location Type Date
Ely, NV 21 04/08/74
Comins Lake
Hiko, NV 27 01/10/74
Crystal Springs
Las Vegas, NV 21 01/14/74
Lake Mead Vegas
Wash
Las Vegas, NV 21 01/17/74
Tule Springs Pond
Type of
Radioactivity
89Sr
9°Sr
226Ra
238pu
239PU
89gr
9°Sr
226Ra
238pu
239pu
89Sr
90Sr
226Ra
238pu
239pu
89Sr
90Sr
226Ra
238pu
239pu
i^uuceui_Lcii-.LULi
(10~9 yCi/ml)
< 2.7
< 1.2
0.16
< 0.037
0.073
< 2.5
< 0.98
0.67
< 0.048
< 0.066
< 2.1
< 1.4
0.23
0.048
< 0.085
< 3.0
< 0.99
0.32
< 0.042
< 0.067
Cone.
Guide
< 0.27
< 1.2
1.6
< 0.0022
0.0043
< 0.25
< 0.98
6.7
< 0.0028
< 0.0039
< 0.21
< 1.4
2.3
0.0028
< 0.0050
< 0.30
< 0.99
3.2
< 0.0025
< 0.0039
78
-------
Table 7. (continued)
of
Sampling Sample Collection
Location Type3 Date
Furnace Creek, CA 21 01/08/74
Pond
Olancha, CA 21 01/15/74
Haiwee Reservoir
Alamo, NV 21 01/07/74
Pahranagat Lake
Diablo, NV 21 01/07/74
Reed Ranch
Type of
Radioactivity
89Sr
90Sr
226Ra
238pu
239pu
89Sr
9°Sr
226Ra
238pu
239pu
89Sr
90Sr
226Ra
238pu
239pu
89Sr
90Sr
226Ra
238pu
239pu
Ol/Ll^CLLL. J. CL U -LULL
(10"9 yCi/ml)
< 1.4
< 0.82
0.16
0.12
0.088
< 3.5
< 1.4
0.32
< 0.039
< 0.051
< 2.9
< 1.1
0.45
< 0.038
< 0.068
< 2.6
< 1.0
0.089
< 0.031
< 0.064
Cone.
Guide
< 0.14
< 0.82
1.6
0.0071
0.0052
< 0.35
< 1.4
3.2
< 0.0023
< 0.0030
< 0.29
< 1.1
4.5
< 0.0022
< 0.0040
< 0.26
< 1.0
0.89
< 0.0018
< 0.0038
79
-------
Table 7. (continued)
of
Sampling Sample
Location Type
Lida, NV 21
Pond at Storage Tank
Springdale, NV 21
Pond
Sunnyside, NV 21
Adam McGill
Reservoir
Warm Springs, NV 21
Fallini's Pond
Collection Type of
Date Radioactivity
_ 01/07/74 89Sr
90Sr
226Ra
238PU
239pu
01/08/74 89Sr
90Sr
226Ra
238pu
239pu
01/16/74 89Sr
90Sr
226Ra
238pu
239pu
04/03/74 89Sr
90Sr
226Ra
238pu
239pu
\J\J 1&WX»1L l_ J. U V, .L.W kk
(10~9 pCi/ml)
< 3.5
< 1.3
0.31
< 0.035
< 0.066
< 2.6
< 1.1
0.11
< 0.062
< 0.083
< 2.4
< 1.1
1.4
< 0.041
< 0.083
< 4.8
< 0.91
0.17
< 0.038
< o.o/to
Cone.
Guide
< 0.35
< 1.3
3.1
< 0.0021
< 0.0039
< 0.26
< 1.1
1.1
< 0.0036
< 0.0049
< 0.24
< 1.1
14
< 0.0024
< 0.0049
< 0.48
< 0.91
1.7
< 0.0022
< 0.0024
21 = Pond, Lake, Reservoir, Stock Tank, Stock Pond
80
-------
Table 8. 1974 Summary of Tritium Results for the Water Surveillance Network
Sampling
Location
Death Valley Jet, CA
Lila's Cafe
Blue Diamond, NV
Post Office
Cactus Springs, NV
Mobil Ser. Sta.
Las Vegas , NV
Craig Rch. Golf Course
Las Vegas, NV
Desert Game Range
Las Vegas, NV
Lab I, NERC-LV
Las Vegas, NV
Lake Mead Vegas Wash
Las Vegas, NV
L.V. Water Dist. Well 28
Las Vegas, NV
Municipal Golf Course
Las Vegas, NV
Tule Springs
Las Vegas, NV
Vegas Estates
Mt. Charleston, NV
Kyle Cnyn. Fire Sta.
Scotty's Jet. , NV
Holloway Ranch
Sample
Type3
23
23
27
23
23
24
21
23
23
23
23
27
No. of
Samples
4
4
4
4
4
4
4
4
4
4
4
4
23 5
a21 = Pond, Lake, Reservoir, Stock Tank, Stock
23 = Well
24 = Multiple Supply - Mixed (A water sample c
11
1
CMax
430
390
<240
290
<240
1000
1200
<260
<260
350
<260
330
450
Pond
:onsis
l^UlLV^Cll L.J. d U -
0~9 uCi/ml
CMin
<210
<210
<210
<210
<210
550
680
<210
<210
<210
<210
<230
LW 11
Avg
<280
<270
<230
<250
<230
750
910
<230
<230
<260
<230
<270
<220 <290
ting of mixed or
% of
Cone.
Guide
<0.028
<0.027
<0.023
<0.025
<0.023
0.075
0.091
<0.023
<0.023
<0.026
<0.023
<0.027
<0.029
multiple
sources of water, such as well and spring.)
27 = Spring
81
-------
Table 9. Analytical Criteria for Long-Term Hydrological Monitoring
Program Samples
Monthly
Samples
Semi-Annual
Samples
Annual
Samples
Gross alpha
Gross beta
Gamma scan
89-90
Sr
226
Ra
U
238-239
'Pu
All samples
All samples
All samples
All samples
Each quarter in CY 1973
Jan. and July samples
in CY 1974. Any other
sample if gross beta
exceeds 1 x 10~8
yCi/ml.
Jan. and July samples.
Any other sample if
gross alpha exceeds
3 x 1(T9 yCi/ml.
Each quarter in 1973.
Jan. and July samples
in 1974.
Each quarter in 1973.
Jan. and July samples
in 1974.
All samples
All samples
All samples
All samples
Jan. and July samples
in 1973. Jan. sample
only in 1974. Any other
sample if gross beta
exceeds 1 x 10~8
yCi/ml.
Jan. samples. Any other
sample if gross alpha
exceeds 3 x 10"~9
yCi/ml.
Jan. and July samples
in 1973. Jan. only in
1974.
Jan. and July samples
in 1973. Jan. only in
1974.
All samples
All samples
All samples
All samples
Only if gross beta
exceeds 1 x 10 8
yCi/ml.
Only if gross alpha
exceeds 3 x 10~9
yCi/ml.
Not performed.
Not performed.
Starting in January 1974, all samples were analyzed by the 3H enrichment technique.
(MDC~6 x 10~9 yCi/ml) except for the HT-2M well at the Project Dribble Site and
USGS Wells #4 and 8 at the Project Gnome Site. The samples from these three con-
taminated wells were analyzed by conventional techniques (MDC~2.2 x 10~7 yCi/ml).
82
-------
Table 10. 1974 Summary of Analytical Results for the NTS Monthly Long-Term
Hydrological Monitoring Program
No.
Sampling Samples
Location Collected
NTS 12
Well 5C
NTS 12
Army Well No . 1
Beatty, NV 11
Well HS/48-ldd
No.
Samples
Analyzed
12
2
2
2
2
2
2
2
9
12
2
2
2
2
2
2
2
6
11
2
2
2
2
2
2
2
9
Type of
Radio-
activity
3H
89Sr
9°Sr
238PU
239PU
234u
235u
238U
226Ra
3H
89Sr
90Sr
238pu
239pu
23tu
235u
238U
226Ra
3H
89Sr
90Sr
238pu
239pu
234u
235u
238u
226Ra
ISxtUJ-U_ 1
CMax
<11
<5.1
<1.2
<0.040
<0.055
3.9
0.084
2.0
0.39
<11
<6.1
<1.2
<0.039
<0.078
2.1
0.025
0.69
0.55
<9.9
<7.1
<1.4
<0.054
<0.072
8.4
0.060
1.7
0.49
_ J.V -L»-y V»V,
' yCi/ral
CMin
<5.7
<1.6
<1.0
<0.030
<0.036
3.0
0.047
1.6
0.083
<6.4
<1.3
<0.93
<0.036
0.036
1.8
0.019
0.62
0.24
<5.7
<2.5
<1.1
<0.020
<0.011
4.5
0.037
0.95
0.089
Avg
<8.0
<3.4
<1.1
<0.035
<0.046
3.5
0.066
1.8
0.14
<8.2
<3.7
<1.1
<0.038
<0.057
2.0
0.022
0.66
0.46
<7.7
<4.8
<1.3
<0.037
<0.042
6.5
0.049
1.3
0.17
% of
Cone.
Guide3
<0.0001
<0.0011
<0.011
<0.0001
<0.0001
0.00039
<0.0001
0.00018
0.035
<0.0001
<0.0012
<0.011
<0.0001
<0.0001
0.00022
<0.0001
<0.0001
0.115
-------
Table 10. (continued)
Sampling
Location
NTS
Well U3CN-5
NTS
Well A
NTS
Well C
No . No .
Samples Samples
Collected Analyzed
7 7
5
5
1
1
1
1
1
6
12 12
3
3
2
2
2
2
2
10
12 12
11
11
2
2
2
2
2
2
Type of
Radio-
activity
3H
89Sr
9°Sr
238pu
239pu
23
-------
Table 10. (continued)
Sampling
Location
NTS
Well 20A-2
NTS
Well 8
NTS
Well J-12
No . No .
Samples Samples
Collected Analyzed
2 2
1
1
1
1
1
1
1
2
12 12
2
2
2
2
2
2
2
6 6
3
3
1
1
1
1
1
1
Type of
Radio-
activity
3H
89Sr
9°Sr
238pu
239PU
23^
235u
238u
226Ra
3H
89Sr
9°Sr
238pu
239pu
23«*u
235u
238u
3H
89Sr
90Sr
238pu
239pu
231+u
235u
238u
226Ra
LXCIU J.VJQ.
10
Max
<7.0
<2.0
<1.2
<0.017
<0.015
3.3
0.039
0.88
0.22
<10
<5.8
<1.1
<0.045
<0.086
0.44
<0.015
0.10
<9.9
<5.5
<1.0
<0.043
<0.038
0.93
<0.014
0.19
0.16
\- L. JL V J. L. J \J
~9 yCi/ml
CMin
<7.0
<2.0
<1.2
<0.017
<0.015
3.3
0.039
0.88
0.12
<6.4
<1.5
<1.1
<0.021
0.023
0.33
<0.0074
0.071
<7.3
<1.0
<0.080
<0.043
<0.038
0.93
<0.014
0.19
0.16
Avg
<7.0
<2.0
<1.2
<0.017
<0.015
3.3
0.039
0.88
0.17
<8.1
<3.7
<1.1
<0.033
<0.055
0.39
<0.011
0.085
<8.2
<2.7
<0.69
<0.043
<0.038
0.93
<0.014
0.19
0.16
% of
Cone.
Guide3
<0.0001
<0. 00067
<0.012
<0.0001
<0.0001
0.00037
<0.0001
<0.0001
0.043
<0.0001
<0.0012
<0.011
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0. 00090
<0.0069
<0.0001
<0.0001
0.0001
<0.0001
<0.0001
0.040
85
-------
Table 10. (continued)
Sampling
Location
NTSd
Well J-13
NTS
Well UE 19G-S
No . No .
Samples Samples
Collected Analyzed
2 2
1
1
1
1
1
1
1
5 4
1
1
1
1
1
1
1
5 .
Type of
Radio-
activity
3H
89Sr
9°Sr
238pu
239pu
23«tu
235u
238u
3H
89Sr
9°Sr
238pu
239pu
23
-------
Table 11. 1974 Summary of Analytical Results
for the NTS Semi-Annual Long-Term Hydrological Monitoring Program
Sampling
Location
NTS
Well UE 15d
NTS
Well UE 15d
NTS
Well 2
NTS
Well 2
NTS
Well C-l
Type of
Sample Radio-
Date Type3 activity
1/8 23 3H
89Sr
9°Sr
238pu
239pu
231*U
235U
238jj
226Ra
7/9 23 3H
89Sr
9°Sr
226Ra
1/8 23 3H
89gr
90Sr
238pu
239pu
23«*u
235D
238u
7/10 23 3H
1/8 23 3H
89Sr
9°Sr
238PU
239pu
23^
235u
238jj
Radioactivity
Cone.
(10-9yCi/ml)
<13
< 6.5
< 1.3
< 0.057
< 0.080
4.3
0.055
1.1
1.1
< 8.3
< 1.8
< 1.3
1.9
<11
< 5.0
< 1.0
< 0.051
< 0.089
1.7
< 0.015
0.34
< 8.3
38
< 5.2
< 1.1
< 0.049
< 0.085
7.3
0.10
2.0
% of
Cone.
Guideb
<0.0001
<0.0022
<0.013
<0.0001
<0.0001
0.00048
<0.0001
0.00011
0.28
<0.0001
<0. 00060
<0.013
0.48
<0.0001
<0.0017
<0.010
<0.0001
<0.0001
0.00019
<0.0001
<0.0001
<0.0001
<0.0001
<0.0017
<0.011
<0.0001
<0.0001
0.00081
<0.0001
0.00020
87
-------
Table 11. (continued)
Sampling
Location
NTS
Well C-l
NTS
Well UE 5c
NTS
Well UE 5c
NTS
Well 5B
NTS
Well 5B
Type of
Sample Radio-
Date Type3 activity
7/10 23 3H
89Sr
90Sr
226Ra
1/17 23 3H
89Sr
90Sr
238pu
239pu
234U
235U
238u
7/10 23 3H
89Sr
90Sr
226Ra
1/9 23 3H
89Sr
9°Sr
238pu
239PU
231*u
235U
238U
226Ra
7/30 23 3H
®9Sr
90Sr
226Ra
Radioactivity
Cone.
(10~9yCi/ml)
16
< 3.0
< 1.4
1.4
< 7.4
< 6.9
< 1.0
< 0.020
0.050C
3.0
0.060
1.0
< 8.6
< 1.9
< 1.4
0.22
<10
< 5.6
< 1.1
< 0.052
< 0.084
2.7
0.088
1.9
0.20
< 6.4
< 2.0
< 0.97
0.078
% of
Cone.
Guideb
<0.0001
<0.0010
<0.014
0.35
<0.0001
<0.0023
<0.010
<0.0001
<0.0001
0.0003
<0.0001
0.0001
<0.0001
<0. 00063
<0.014
0.055
<0.0001
<0.0019
<0.011
<0.0001
<0.0001
<0. 00030
<0.0001
0.00019
0.050
<0.0001
<0. 00067
<0.0097
0.020
88
(Revised 5/75)
-------
Table 11. (continued)
Sampling Sample
Location Date Type
NTS 1/10 23
Watertown No. 3
NTS 7/10 23
Watertown No. 3
Ash Meadows, NV 1/15 27
Crystal Pool
Ash Meadows, NV 7/2 27
Crystal Pool
Ash Meadows, NV 1/22 23
Well 17S/50E-14CAC
Ash Meadows, NV 7/2 23
Well 17S/50E-14CAC
Type of
Radio-
activity
3H
89Sr
90Sr
238pu
239pu
23l*u
23 5U
238y
226Ra
3H
3H
89Sr
90Sr
238pu
239pu
23^
235U
238U
226Ra
3H
89Sr
9^Sr
226Ra
3H
89Sr
9°Sr
238pu
239pu
23ttu
235U
238U
3H
226Ra
Radioactivity
Cone.
(lO-9pCi/ml)
< 6.7
< 5.7
< 1.1
< 0.037
< 0.061
1.3
0.052
0.54
0.10
< 9.3
< 7.7
< 4.9
< 0.88
< 0.094
< 0.15
14
0.23
6.1
0.095
< 8.0
< 3.3
< 1.4
0.12
< 7.0
< 7.8
< 1.2
< 0.042
< 0.067
2.4
0.048
0.93
< 7.3
0.70
% of
Cone.
Guideb
<0.0001
<0.0019
<0.011
<0.0001
<0.0001
0.00014
<0.0001
<0.0001
0.025
<0.0001
<0. 00026
<0.16
<0.29
<0.0019
<0.0030
0.047
0.00077
0.015
0.32
<0. 00027
<0.11
<0.47
0.40
<0. 00023
<0.26
<0.40
<0. 00084
<0.0013
0.0080
0.00016
0.0023
<0. 00024
2.3
89
(Revised 5/75)
-------
Table 11. (continued)
Sampling Sample
Location Date Type3
Ash Meadows, NV 1/15 27
Fairbanks Springs
Ash Meadows, NV 7/2 27
Fairbanks Springs
Beatty, NV 1/16 23
City Supply
Beatty, NV 7/1 23
City Supply
Beatty, NV 1/15 23
Nuclear
Engineering Co.
Beatty, NV 7/1 23
Nuclear
Engineering Co.
Type of
Radio-
activity
3H
89Sr
9°Sr
238pu
239pu
23^U
235u
238u
3H
3H
"Sr
9°Sr
238pu
239pu
234U
235u
238u
226Ra
3H
89Sr
90Sr
3H
89Sr
9°Sr
238pu
239pu
234u
235u
238U
226Ra
3H
89Sr
9°Sr
226Ra
Radioactivity
Cone.
(10"9yCi/ml)
< 9.3
< 5.1
< 0.91
< 0.043
< 0.069
2.1
0.051
0.79
22
< 6.4
< 5.5
< 0.98
< 0.052
< 0.080
9.3
0.11
2.8
0.089
< 7.7
< 1.5
< 1.1
< 7.7
< 4.8
< 0.86
< 0.045
< 0.083
5.6
0.067
1.7
0.22
< 7.7
< 1.4
< 1.1
0.072
% of
Cone.,
Guide
<0. 00031
<0.17
<0.30
<0. 00086
<0.0014
0.0070
0.00017
0.0020
<0. 00073
<0. 00021
<0.18
<0.33
<0.0010
<0.0016
0.031
0.00037
0.0070
0.30
<0. 00026
<0.050
<0.37
<0. 00026
<0.16
<0.29
<0. 00090
<0.0017
0.019
0.00022
0.0043
0.73
<0. 00026
<0.047
<0.37
0.24
90
(Revised 5/75)
-------
Table 11. (continued)
Sampling Sample
Location Date Type
Indian Springs, NV 1/23 23
USAF No. 1
Indian Springs, NV 7/3 23
USAF No. 1
Indian Springs, NV 1/31 23
Sewer Co. Inc.
Well No. 1
Indian Springs, NV 7/3 23
Sewer Co. Inc.
Well No. 1
Lathrop Wells, NV 1/15 23
City Supply
Type of
Radio-
activity
3H
89Sr
90Sr
238Pu
239pu
23«tu
235u
238u
226Ra
3H
"Sr
90Sr
3H
89Sr
90Sr
238pu
239pu
23^
235D
238u
226Ra
3H
226Ra
3H
89Sr
90Sr
238pu
239pu
23«tu
235u
238u
Radioactivity
Cone.
(10-9yCi/ml)
20
< 7.3
< 1.1
< 0.048
< 0.099
4.3
0.037
0.76
0.45
31
< 1.6
< 1.2
<13
< 6.6
< 1.1
0.018d
< 0.0092
3.0
0.028
0.68
0.25
<10
0.28
< 7.3
< 4.8
< 0.86
< 0.040
< 0.052
1.2
0.022
0.43
% of
Cone.
Guide
0.00067
<0.24
<0.37
<0. 00096
<0.0020
0.014
0.00012
0.0019
1.5
0.0010
<0.053
<0.40
<0. 00043
<0.22
<0.37
<0. 00036
<0. 00018
0.010
<0.0001
0.0017
0.83
<0. 00033
0.93
<0. 00024
<0.16
<0.29
<0. 00080
<0.0010
0.0040
<0.0001
0.0011
91
(Revised 5/75)
-------
Table 11. (continued)
Sampling Sample
Location Date Type3
Lathrop Wells, NV 7/1 23
City Supply
Shoshone, CA 1/18 27
Shoshone Spring
Shoshone, CA 7/8 27
Shoshone Spring
Springdale, NV 1/14 27
Goss Springs
Springdale, NV 7/2 27
Goss Springs
Springdale, NV 7/2 23
Road D Windmill
a23 - Well
27 - Spring
Type of
Radio-
activity
3H
89Sr
90Sr
3H
89Sr
9°Sr
238pu
239pu
23l*u
23 5u
238u
3H
89Sr
90Sr
3H
89Sr
90Sr
238pu
239pu
231+u
235U
238u
226Ra
3H
89Sr
9°Sr
3H
89Sr
9°Sr
238Pu
239pu
23**u
235u
238u
226Ra
Radioactivity
Cone.
(10-9yCi/ml)
< 9.6
< 1.4
< 1.0
< 7.7
< 5.8
0.92e
< 0.043
< 0.074
3.6
0.042
1.2
< 8.3
< 2.6
< 1.2
< 7.7
< 4.7
< 0.83
< 0.048
< 0.072
5.0
0.050
1.3
0.29
< 7.3
< 1.5
< 1.1
< 7.3
< 1.7
< 1.1
< 0.024
< 0.011
1.3
0.016
0.55
0.01
% of
Cone.,
Guide
<0. 00032
<0.047
<0.33
<0. 00026
<0.19
<0.31
<0. 00086
<0.0015
0.012
0.00014
0.0030
<0. 00028
<0.087
<0.40
<0. 00026
<0.16
<0.28
<0. 00096
<0.0014
0.017
0.00017
0.0033
0.97
<0. 00024
<0.050
<0.37
<0. 00024
<0.057
<0.37
<0. 00048
<0. 00022
0.0043
<0.0001
0.0014
0.033
All on-NTS percentages are for radiation workers.
for an individual in an uncontrolled area.
GTwo-sigma error is ± 0.030 x 10~9yCi/ml.
Two-sigma error is ± 0.016 x 10~9yCi/ml.
eTwo-sigma error is ± 0.91 x 10-9pCi/ml.
92
All off-NTS percentages are
(Revised 5/75)
-------
Table 12. 1973 Samples From NTS Monthly Long-Term
Hydrological Monitoring Program Not Previously Reported
Sampling
Location
NTS
Well 20A-2
NTS
Well 8
NTS
Well J-12
No . No .
Samples Samples
Collected Analyzed
4 3
2
2
2
2
2
2
2
3
12 11
4
4
4
4
4
4
4
1
9 9
3
3
3
3
3
2
3
0
Type of
Radio-
activity
3H
89Sr
90Sr
238pu
239PU
23^
235u
238u
226Ra
3H
89Sr
90Sr
238pu
239pu
231HJ
235u
238u
226Ra
3H
89Sr
90Sr
238pu
239pu
23fu
235u
238u
226Ra
93
RdU _LUd>_ U -LV.Ll-y l^ULU- .
(10~9 yCi/ml)
CMax
<8.6
<1.0
<1.1
<0.034
<0.028
3.1
0.040
0.70
0.33
17.6
<2.0
<1.1
<0.061
<0.020
0.47
<0.010
0.20
0.16
<9.2
<2.0
<1.1
<0.04
<0.021
0.99
0.016
0.22
—
CMin
<7.6
<1.0
<1.0
<0.030
<0.014
2.9
0.036
0.70
<0.13
<5.1
<1.0
<0.90
<0.021
<0.010
0.010
<0.0040
0.10
0.16
<6.4
<1.0
<0.9
<0.02
<0.010
0.94
0.013
0.10
—
Avg
<8.3
<1.0
<1.1
<0.032
<0.021
3.0
0.038
0.70
<0.20
<8.4
<1.5
<1.0
<0.036
<0.016
0.35
<0.0076
0.13
0.16
<7.6
<1.3
<1.0
<0.027
<0.017
0.96
0.015
0.16
—
% of
Cone.
Guide
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.05
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.04
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
—
(Revised 5/75)
-------
Table 12. (continued)
Sampling
Location
NTS
Well U3CN-5
NTS
Well A
NTS
Well C
No . No .
Samples Samples
Collected Analyzed
7 7
5
5
2
2
2
2
2
6
12 11
5
5
4
4
4
4
4
8
12 9
9
9
4
4
4
4
4
10
Type of
Radio-
activity
3H
89Sr
9°Sr
238PU
239pu
234u
235u
238u
226Ra
3H
89Sr
90Sr
238pu
239pu
234U
235u
238u
226Ra
3H
89Sr
9°Sr
238pu
239pu
23^
2 3 STT
2 3 BIT
226Ra
Radioactivity Cone.
(10~9 yCi/ml)
CMax
<8.3
<8.7
<1.2
<0.030
<0.020
4.6
0.042
1.3
2.6
<11
<2.0
<1.2
<0.040
<0.040
5.7
0.081.
1.7
2.4
120
<7.7
5.0a
<0.048
<0.020
8.6
0.10
2.3
1.8
CMin
<6.7
<2.0
<0.86
<0.020
<0.020
2.8
0.015
0.73
0.87
<5.7
<1.0
<1.0
<0.020
<0.020
4.8
0.033
1.4
0.010
58
<1.0
<0.90
<0.020
<0.010
4.2
0.050
1.1
0.20
Avg
<7.2
<3.8
<1.1
<0.025
<0.020
3.7
0.029
1.0
2.0
<7.5
<1.6
<1.1
<0.031
<0.029
5.2
0.054
1.5
0.46
90
<3.0
<1.6
<0.036
<0.018
7.2
0.080
1.9
1.2
% of
Cone.
Guide
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.5
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.12
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.5
94
(Revised 5/75)
-------
Table 12. (continued)
Sampling
Location
NTS
Well 5C
NTS
Army Well No. 1
Beatty, NV
Well llS/48-ldd
No . No .
Samples Samples
Collected Analyzed
12 10
4
4
4
4
4
4
4
4
12 11
4
4
4
4
4
4
4
6
9 7
4
4
4
4
4
4
4
7
Type of
Radio-
activity
3H
89Sr
90gr
238pu
239pu
23fu
235u
238u
226Ra
3H
89Sr
9°Sr
238pu
239pu
23«tu
235u
238u
226Ra
3H
89Sr
90Sr .
238pu
239pu
23"u
235u
238u
226Ra
Radioactivity Cone.
(10~9 yCi/ml)
CMax
12.8
<2.0
<1.1
<0.049
<0.062
4.7
0.10
2.4
0.52
<8.6
<2.0
<1.1
<0.047
<0.020
2.5
0.031
0.88
0.97
<9.0
<2.0
<1.1
<0.044
<0.024
7.9
0.076
1.7
1.4
CMin
<6.1
<1.0
<0.90
<0.020
<0.020
3.5
0.080
1.5
0.30
<3.8
<1.0
<0.9
<0.020
<0.010
0.81
0.014
0.64
0.37
<7.0
<1.0
<1.0
<0.030
<0.010
0.81
0.035
1.1
0.17
C.
Avg
<8.4
<1.8
<0.98
<0.032
<0.029
4.2
0.095
2.0
0.38
<7.3
<1.5
<1.0
<0.032
<0.016
1.9
0.025
0.77
0.72
<8.1
<1.3
<1.1
<0.037
<0.017
5.2
0.054
1.4
0.46
% of
Cone.
Guide
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.10
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.18
<0.01
' <0.01
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.15
aTwo-sigma error term is ± 1.8 x 10~9yCi/ml.
95
-------
Table 13. 1974 Summary of Analytical Results
for Off-NTS Long-Term Hydrological Monitoring Program
Type of
Sampling
Location
Malaga, NM
USGS Well No. 1
Malaga, NM
USGS Well No. 4
Malaga, NM
USGS Well No. 8
Malaga, NM
PHS Well No. 6
Malaga, NM
PHS Well No. 8
Malaga, NM
PHS Well No. 9
Malaga, NM
PHS Well No. 10
Malaga, NM
Pecos River
Pumping Station
Loving , NM
City Well No. 2
Carlsbad, NM
Sample Depth Radio-
Date Type (m) activity
PROJECT GNOME
4/25 23 161 3H
89gr
90Sr
226Ra
4/25 23 148 3H
89Sr
90Sr
226Ra
4/25 23 144 3H
89Sr
90Sr
226Ra
137Cs
4/27 23 — 3H
89gr
90Sr
4/27 23 — 3H
89Sr
90Sr
4/27 23 — 3H
4/27 23 — 3H
226Ra
4/26 23 — 3H
4/26 23 — 3H
4/26 23 — 3H
Radioactivity
(10~9yCi/ml)
17
l!4c
3.8
990,000
<190
8100
12
990,000
<290
13,000
2.4
23
320
<0.91
<8.0
<2.0
<0.89
<7.0
<7.7
0.32
<8.0
<7.3
29
Cone. % of Cone.
Guide
0.00057
<0.037
0.47
13
33
<6.3
2700
40
33
<9.7
4300
8.0
0.12
0.011
<0.070
<0.30
<0. 00027
<0.067
<0.30
<0. 00023
<0. 00026
1.1
<0. 00027
<0. 00024
0.00097
City Well No. 7
96
-------
Table 13. (continued)
Type of
Sampling Sample Depth
Location Date Type (m)
Radio- Radioactivity Con. % of Cone.
activity (10"9yCi/ml) Guide
PROJECT SHOAL
Frenchman, NV 4/02 23
Frenchman Station
Frenchman, NV 4/02 23
Well HS-1
Frenchman, NV 4/02 23
Well H-3
Frenchman, NV 4/02 23
Flowing Well No. 2
3H
226Ra
3H
226Ra
3H
22&Ra
3H
89Sr
9°Sr
226Ra
<5.7
0.13
<5.7
0.18
<5.7
1.0
<5.7
<2.9
<0.90
0.21
<0. 00019
0.43
<0. 00019
0.60
<0. 00019
3.3
<0. 00019
<0.097
<0.30
0.70
Frenchman, NV
Hunts Station
4/02
23
<5.7
<0.00019
Baxterville, MS
City Water
Baxterville, MS
Lower Little Creek
Tatum Salt Dome, MS
Well HT-2C
Tatum Salt Dome, MS
Well HT-2M
Tatum Salt Dome, MS
Well HT-4
Tatum Salt Dome, MS
Well HT-5
3/01
3/04
3/03
3/03
3/03
PROJECT DRIBBLE
23 — 3H
22
23
23
23
108
122
183
3H
3H
3H
3H
90
210
35
11
<8.6
0.0030
0.0070
0.0012
3/02
3/02
3/02
3/02
3/02
3/02
3/02
3/02
23
23
23
23
23
23
23
23
—
31
183
335
488
640
716
762
3H
3H
3H
3H
3H
3H
3H
3H
35,000
42,000
35,000
48,000
45,000
38,000
38,000
42,000
1.2
1.4
1.2
1.6
1.5
1.3
1.3
1.4
0.00037
<0.00029
97
(Revised 5/75)
-------
Table 13. (continued)
Type of
Sampling
Location
Tatum Salt Dome, MS
Well E-7
Baxterville, MS
Half Moon Creek
Half Moon Creek
Overflow
Baxterville, MS
T Speights Residence
Baxterville, MS
R. L. Anderson
Residence
Baxterville, MS
M. Lowe Residence
Baxterville, MS
R. Ready Residence
Baxterville, MS
W. Daniels, Jr.
Residence
Lumber ton, MS
City Water Well No. 2
Purvis, MS
City Water
Columbia, MS
Date
3/03
3/04
3/04
3/01
3/01
3/01
3/01
3/01
3/01
3/01
3/04
Sample Depth
Type3 (m)b
23 282
22
22
23
23
23
23
23
23
23
23
Radio- Radioactivity Cone. % of Cone.
activity (lO~9yCi/ml) Guide
3H
3H
3H
89Sr
90Sr
3H
3H
3H
3H
3H
3H
3H
3H
<8.3
150
5100
<4.7
1.4
110
290
230
38
90
<6.7
<9.6
25
<0. 00028
0.0050
0.17
<0.16
0.47
0.0037
0.0097
0.0077
0.0013
0.0030
<0. 00022
<0. 00032
0.00083
City Water Well No. 64B
Baxterville, MS
Pond W. of G.Z.
3/04 21
96
0.0032
Gobernador, NM
Arnold Ranch
PROJECT GASBUGGY
5/02 27
28
0.00093
98
(Revised 5/75)
-------
Table 13. (continued)
Type of
Sampling
Location
Gobernador, NM
Lower Burro Canyon
Gobernador, NM
Bixler Ranch
Blanco, NM
San Juan River
Gobernador, NM
Cave Springs
Gobernador, NM
Windmill No. 2
Gobernador , NM
Bubbling Springs
Dulce, NM
City Water
Dulce, NM
La Jara Lake
Gobernador , NM
EPNG Well 10-36
Rulison, CO
Lee L. Hayward Ranch
Rulison, CO
Glen Schwab Ranch
Grand Valley, CO
Albert Gardner Ranch
Grand Valley, CO
City Water
Date
5/01
5/02
5/02
5/01
5/02
4/30
5/01
5/01
4/30
5/14
5/13
5/13
5/13
Sample Depth Radio- Radioactivity Cone. % of Cone.
Type3 (m) activity (10~9yCi/ml) Guide
23 — 3H
23 — 3H
22 — 3H
27 — 3H
23 — 3H
27 — 3H
21 — 3H
21 ~ 3H
89Sr
9°Sr
23 1097 3H
89Sr
90Sr
226Ra
PROJECT RULISON
23 -- . 3H
23 — 3H
23 — 3H
226Ra
27 — 3H
226Ra
<7.6
21
420
27
<22d
240
380
260
<3.8
6.7
38
<1.5
<1.1
0.17
480
800
510
0.33
170
0.76
<0. 00025
0.00070
0.014
0.00090
<0. 00073
0.0080
0.013
0.0087
<0.13
2.2
0.0013
<0.050
<0.37
0.57
0.016
0.027
0.017
1.1
0.0057
2.5
99
-------
Table 13. (continued)
Type of
Sampling
Location
Grand Valley, CO
300 yds. N.W. of G.Z.
Anvil Points, CO
Bernklau Ranch
Grand Valley, CO
Battlement Creek
Grand Valley, CO
CER Water Well
Rulison, CO
Potter Ranch
Blue Jay, NV
Highway Maintenance
Station
Warm Springs, NV
Hot Creek Ranch
Blue Jay, NV
Blue Jay Spring
Blue Jay, NV
Six Mile Well
Site C, NV
Well HTH-2
Date
5/14
5/13
5/14
5/14
5/13
4/11
4/11
4/11
4/11
4/09
Sample Depth Radio- Radioactivity Cone. % of Cone.
Type3 (m) activity (10~9yCi/ml) Guide
27 — 3H
27 — 3H
22 -- 3H
23 13 3H
27 — 3H
226Ra
FAULTLESS EVENT
23 — 3H
226Ra
27 — 3H
89Sr
9°Sr
27 — 3H
226Ra
23 — 3H
23 184 3H
226Ra
450
350
580
610
540
0.094
<6.4
0.22
35
<2.3
<0.82
<6.4
0.25
<6.4
<5.7
0.15
0.015
0.012
0.019
0.020
0.018
0.31
<0. 00021
0.73
0.0012
<0.077
<0.27
<0. 00021
0.83
<0. 00021
<0. 00019
0.50
21 - Pond, Lake, Reservoir, Stock Tank, Stock Pond
22 - Stream, River, Creek
23 - Well
24 - Multiple Supply - Mixed (A water sample consisting of mixed or multiple sources
of water, such as well and spring.)
27 - Spring
If depth not shown, water was collected at surface.
Two-sigma counting error is ± 0.85 x 10~9yCi/ml.
Counting time was 100 minutes instead 200 minutes.
100
-------
Table 14. 1973 Samples From Off-NTS Long-Term
Hydrological Monitoring Program Not Previously Reported
Sampling
Location
Type of
Sample Depth Radio- Radioactivity Cone. % of Cone,
Date Type5 (m) activity 10~9yCi/ml Guide
Frenchman, NV
Well HS-1
Frenchman, NV
Well H-3
Frenchman, NV
Hunt's Station
PROJECT SHOAL
11/29 23
11/29 23
11/29 23
3H
<8.0
<0.00027
<0.00040
3H
89Sr
9°Sr
<7.0
<4.8
<1.1
<0. 00023
<0.16
<0.37
21 - Pond, Lake, Reservoir, Stock Tank, Stock Pond
22 - Stream, River, Creek
23 - Well
24 - Multiple Supply - Mixed (A water sample consisting of mixed or multiple sources
of water, such as well and spring.)
27 - Spring
If depth not shown, water was collected at surface.
101
-------
APPENDIX A. RADIATION PROTECTION STANDARDS
FOR OFF-NTS EXTERNAL AND INTERNAL EXPOSURE*
ANNUAL DOSE COMMITMENT
Type of Exposure
Whole body, gonads
or bone marrow
Other organs
Dose Limit to
Critical Individuals
at Points of Maximum
Probable Exposure (rem)
0.5
1.5
Dose Limit to
Suitable Sample
of the Exposed
Population (rem)
0.17
0.5
CONCENTRATION GUIDES (CG's)
Network or Program
Air Surveillance Network
Noble gas and Tritium
Surveillance Network,
On-NTS
Noble Gas and Tritium
Surveillance Network,
Off-NTS
Water Surveillance
Network
•
Sampling Radio-
Media nuclide
air 7Be
95Zr
103RU
106Ru
llt0Ba
141Ce
l**Ce
air 85Kr
3H
air 85Kr
3H
133Xe
water 3H
89Sr
90Sr
238pu
239pu
226Ra
CG
(yCi/ml)
l.lxlO'8
3.3xlO~10
l.OxlO'9
6.7xlO~n
3.3xlO~10
1.7xlO~9
6.7xlO~n
l.OxlO"5
S.OxlO'6
l.OxlO"5
l.OxlO-7
6.7xlO~8
1.0xlO~7
l.OxlO-3
l.OxlO-6
l.OxlO-7
1.7xlO-6
1.7xlO-6
l.OxlO-8
*"Radiation Protection Standards," Chapter 0524, ERDA Manual.
102
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.
Suitable sample of the
exposed population in an
uncontrolled area.
(Revised 5/75)
-------
CONCENTRATION GUIDES (CG's) continued
Sampling Radio-
Network or program Media nuclide
Long-Term Hydrological water 3H
Program 89gr
90Sr
238pu
239pu
23i*u
235u
238u
226Ra
137Cs
3H
89Sr
9°Sr
238pu
239pu
23«fu
235u
238u
226Ra
CG
(yCi/ml) Basis of Exposure
3. 0x10- 3 Individual in
o n m-6 uncontrolled area.
3. 0x10- 7
5. 0x10- 6
5. 0x10- 6
3. 0x10- 5
3. 0x10- 5
4. 0x10- 5
3. 0x10- 8
2. 0x10- 5
l.OxlO"1 Individual in
3.0x10-* Controlled area.
l.OxlO-5
1.0x10-*
l.OxlO-14
9.0x10-*
8.0x10-*
l.OxlO-3
4.0xlO-7
Since half of the reported Water Surveillance Network (WSN) samples were
collected from surface waters as opposed to wells, the CG's for a suitable sample
of the exposed population in an uncontrolled area was applied to all WSN samples
for convenience. The majority of the off-NTS 'Long-Term Program' samples were
from wells; therefore, the CG for an exposed individual in an uncontrolled area
was used. v
103
(Revised 5/75)
-------
APPENDIX B. DOSE ASSESSMENT CALCULATIONS
METHOD
Since 133Xe was the only radionuclide from NTS operations that was
detected off-NTS (Beatty and Diablo), the 80-km, man-rem dose was calculated
from the time-integrated concentrations of *33Xe at these locations, the
population information of Figure 5 and the dose equation D = 0.25 E fy, where
D = whole-body gamma dose in rem, assuming a quality factor of 1
rem/rad for the 133Xe radiations,
E = average gamma energy released per disintegration of 133Xe, 0.053
MeV/dis,2
ijj = time-integrated concentrations of 133Xe, Ci-sec/m3.
Indian Springs is the highest populated area within 80 km of the Control
Point (CP-1 in Figure 5) of all tests; however, a sampler for noble gas is
not operated there. Since Desert Rock is at a location which would be ex-
pected to intercept a ground-level release during night-time wind drainage
conditions, the radiation dose at Desert Rock was conservatively assumed to
be representative of the dose at Indian Springs. Lathrop Wells is another
populated area within 80 km of CP-1 and not equipped with a noble gas sampler;
however, the population there is less than Beatty or Indian Springs.
RESULTS
The results of these calculations, as follows, are less than more
conservative dose estimates calculated for these locations from an
atmospheric diffusion model suggested by Pasquill and modified by Gifford.
1 "Meteorology and Atomic Energy," U. S. Atomic Energy Commission, Division
of Technical Information, Oak Ridge, TN. July 1968. p. 339.
2 Crocker, G. R. and Connors, M. A. "Gamma Emission Data for the Calculation
of Exposure Rates From Nuclear Debris," USN RDL-TR-876. U. S. Naval
Radiological Defense Laboratory, San Francisco, CA 94135. June 10, 1965.
3 Turner, D. B. "Workbook of Atmospheric Diffusion." Environmental Protection
Agency, Research Triangle Park, NC. Revised 1970. pp. 5-16.
104
-------
Location
Beatty, NV
Indian Springs, NV
Diablo, NV
*
Time-Integrated
Concentration
(yCi-s/m3)
130
41*
10
Whole-Body
Dose
(yrem)
2
0.5
0.1
Dose
Commitment
Within 80 km
(man-rem)
0.002
<0.001
o**
Total =
<0.003
* TIC at Desert Rock was assumed to exist at Indian Springs.
**Diablo is beyond 80 km, and no population resides between CP-1 and Diablo.
Dose commitment at Diablo was 2 x 10"^ man-rem.
For comparison, the following table summarizes the results of the diffusion
calculations, which are based upon a continuous release over a few hours, a
total release of 663 Ci, and an average wind speed of 2 m/s.
Location
Stability
Category (m~2)
Dose
Whole-Body Commitment
iji Dose Within 80 km
(Ci-s/m3) (yrem)(man-rem)
Beatty, NV
Indian Springs, NV
Diablo, NV
F
F
D
2.4xlO~6
2.4xlO~6
2. 2x10- 7
9.0x10-'*
9.0xlO-4
3. 3x10- 5
11
11
0.4
0.01
0.02
0*
Total =
0.03
*Diablo is beyond 80 km, and no population resides between CP-1 and Diablo.
Dose commitment at Diablo would have been 6 x 10"6 Man-rem.
CONCLUSION
The calculated doses which off-NTS residents at Beatty, Diablo or Indian
Springs could have received from measured concentrations of 133Xe were equal
to or less than 0.001 percent of the radiation protection standard of 170
105
-------
mrem/a for a suitable sample of the population and less than 0.002 percent of
the dose one would receive from environmental background radiation, which
ranges between 83-150 mrem/a for these locations. The estimated dose commit-
ment within 80 km of the NTS was <0.003 man-rem, based upon the measured
concentrations of 133Xe. These dose estimates were about 1/10 of more con-
servative dose estimates based upon the reported quantity of 133Xe released
and atmospheric diffusion equations.
106
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DISTRIBUTION
1-25 National Environmental Research Center, Las Vegas, NV
26 Mahlon E. Gates, Manager, ERDA/NV, Las Vegas, NV
27 Robert H. Thalgott, ERDA/NV, Las Vegas, NV
28 David G. Jackson, ERDA/NV, Las Vegas, NV
29 - 30 Bruce W. Church, ERDA/NV, Las Vegas, NV
31 Roger Ray, ERDA/NV, Las Vegas, NV
32 Chief, NOB/DNA, ERDA/NV, Las Vegas, NV
33 Robert R. Loux, ERDA/NV, Las Vegas, NV
34 A. J. Whitman, ERDA/NV, Las Vegas, NV
35 Elwood M. Douthett, ERDA/NV, Las Vegas, NV
36 Shed R. Elliott, ERDA/NV, Las Vegas, NV
37 Ernest D. Campbell, ERDA/NV, Las Vegas, NV
38 Thomas M. Humphrey, ERDA/NV, Las Vegas, NV
39 Peter K. Fitzsimmons, ERDA/NV, Las Vegas, NV
40 Robert W. Newman, ERDA/NV, Las Vegas, NV
41 Harold F. Mueller, ARL/NOAA, ERDA/NV, Las Vegas, NV
42 Virgil Quinn, ARL/NOAA, ERDA/NV, Las Vegas, NV
43 - 44 Technical Library, ERDA/NV, Las Vegas, NV
45 Mail and Records, ERDA/NV, Las Vegas, NV
46 R. S. Brundage, CER Geonuclear Corporation, P. 0. Box 15090,
Las Vegas, NV 89114
47 Hattie Carwell, ERDA/SAN, San Francisco Operation Office,
1333 Broadway, Oakland, CA 94616
48 - 51 Martin B. Biles, DOS, ERDA, Washington, D. C.
52 Major General Ernest Graves, AGMMA, ERDA, Washington, D. C.
53 Edward Fleming, DAT, ERDA, Washington D. C.
54 Gordon Facer, MA (weapons facilities only) ERDA, Washington, D. C.
55 Andrew J. Pressesky, RDT, ERDA, Washington, D. C.
56 James Miller, BER, ERDA, Washington, D. C.
57 P. L. Randolph, El Paso Natural Gas Co., P. 0. Box 1492,
El Paso, TX 79978
58 Gilbert J. Ferber, ARL/NOAA, Silver Springs, MD
-------
59 Dr. Wilson K. Talley, Assistant Administrator for Research &
Development, EPA, Washington, D. C.
60 William D. Rowe, Deputy Assistant Administrator for Radiation
Programs, EPA, Washington, D. C.
61 Dr. William A. Mills, Director, Division of Criteria & Standards,
ORP, EPA, Washington, D. C.
62 Ernest D. Harward, Acting Director, Division of Technology
Assessment, ORP, EPA, Washington, D. C.
63 Bernd Kahn, Chief, Radiochemistry & Nuclear Engineering, NERC,
EPA, Cincinnati, OH
64 - 65 Floyd L. Galpin, Director, Field Operations Division, ORP, EPA,
Washington, D. C.
66 Dr. Gordon Everett, Director, Office of Technical Analysis, EPA,
Washington, D. C.
67 Regional Administrator, EPA, Region IV, Atlanta, GA
68 Regional Radiation Representative, EPA, Region IV, Atlanta, GA
69 State of Mississippi
70 Regional Administrator, EPA, Region VI, Dallas, TX
71 Regional Radiation Representative, EPA, Region VI, Dallas TX
72 State of New Mexico
73 Regional Administrator, EPA, Region VIII, Denver, CO
74 Regional Radiation Representative, EPA, Region VIII, Denver, CO
75 State of Colorado
76 State of Utah
77 Regional Administrator, EPA, Region IX, San Francisco, CA
78 Regional Radiation Representative, EPA, Region IX, San Francisco, CA
79 State of Arizona
80 State of California
81 State of Nevada
82 Eastern Environmental Radiation Facility, EPA, Montgomery, AL
83 Library, EPA, Washington, D. C.
84 Kenneth M. Oswald, LLL, Mercury, NV
85 Roger E. Batzel, LLL, Livermore, CA
86 James E. Carothers, LLL, Livermore, CA
-------
87 Charles I. Browne, LASL, Los Alamos, NM
88 Jerome E. Dummer, LASL, Los Alamos, NM
89 Arden E. Bicker, REECo, Mercury, NV
90 A. W. Western, REECo, Mercury, NV
91 Savino W. Cavender, REECo, Mercury, NV
92 Carter D. Broyles, Sandia Laboratories, Albuquerque, NM
93 George Tucker, Sandia Laboratories, Albuquerque, NM
94 Albert E. Doles, Eberline Instrument Co., Santa Fe, NM
95 Robert H. Wilson, University of Rochester, Rochester, NY
96 Richard S. Davidson, Battelle Memorial Institute, Columbus, OH
97 J. P. Corley, Battelle Memorial Institute, Richland, WA
98 John M. Ward, President, Desert Research Institute, University of
Nevada, Reno, NV
99 ERDA/HQ Library, Attn: Charles Sherman, ERDA, Washington, D. C.
100 - 126 Technical Information Center, Oak Ridge, TN (for public availability)
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