United States
Environmental Protection
Agency
vvEPA
Environmental Monitoring
Systems Laboratory
P.O. Box 93478
Las Vegas NV 89193-3478
EPA/600/4-88/021
DOE/DP/00539/060
June 1988
Research and Development
Off-Site
Environmental
Monitoring Report
Radiation Monitoring
Around United States
Nuclear Test Areas
1987
prepared for the
United States Department of Energy
under Interagency Agreement
Number DE-AI08-86NV10522
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NOTICE
Readers of this report should be aware of some nonuniformity in lettering,
graphics, spacing and style. These nonuniformities are a result of format
changes, scheduling and graphic delays. These nonuniformities are expected
to be resolved in subsequent annual reports.
ERRATA
Page 2 Under Special Test Support, "...support of the
15 announced nuclear tests...", should read:
"...support of all nuclear tests..."
Page 6 Under Population Distribution the reference to
Figure A. 2 should be to Figure A.3
Page 31 Second column, second paragraph "23 stations"
should read "26 stations"
Page A-9 . Beaver County, Utah number should be 3,200
Page E-39 Cedar City, UT Brent Jones Dairy. The minimum radio-
activity concentration in picocuries per liter of
strontium-90 in milk should be 7.1E-1
-------
EPA-600/4-88-021
DOE/DP/00539-060
May 1988
OFF-SITE ENVIRONMENTAL MONITORING REPORT
Radiation Monitoring Around United States
Nuclear Test Areas, Calendar Year 1987
contributors
C. A. Fontana, N. R. Sunder!and
S. C. Black, B. B. Dicey, A. N. Jarvis
D. D. Smith, D. J. Thome A. A. Mullen, and
Nuclear Radiation Assessment Division
prepared for the
U.S. Department of Energy
under Interagency Agreement
Number DE-AI08-86NV10522
ENVIRONMENTAL MONITORING SYSTEMS LABORATORY
OFFICE OF RESEARCH AND DEVELOPMENT
U.S. ENVIRONMENTAL PROTECTION AGENCY
LAS VEGAS, NEVADA 89193-3478
U.S. Environmental Protection Agency
I'o^lon 5, Library (5PL-16)
250 S. Dearborn Street, Koom 1670
Chicago, 'Hi -60604
-------
NOTICE
report has been reviewed in accordance with the U.S. Environmental
Protection Agency s peer and administrative review policies and approved for
publication. Mention of trade names or commercial products does not constitute
endorsement or recommendation for use.
11
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PREFACE
The U.S. Atomic Energy Commission (AEC) used the Nevada Test Site (NTS)
from January 1951 through January 19, 1975, for conducting nuclear weapons
tests, nuclear rocket-engine development, nuclear medicine studies, and other
nuclear and non-nuclear experiments. Beginning January 19, 1975, these activ-
ities became the responsibility of the newly formed U.S. Energy Research and
Development Administration (ERDA). On October 1, 1977 the ERDA was merged with
other energy-related agencies to form the U.S. Department of Energy (DOE).
Atmospheric nuclear tests were conducted periodically from January 27, 1951,
through October 30, 1958, after which a testing moratorium was in effect until
September 1, 1961. Since then all nuclear detonations have been conducted
underground with the expectation of containment, except for four slightly
above-ground or shallow underground tests of Operation Dominic II in 1962 and
five nuclear earth-cratering experiments conducted under the Plowshare program
between 1962 and 1968.
Prior to 1954, an off-site surveillance program was performed by the Los
Alamos Scientific Laboratory and the U.S. Army. From 1954 through 1970 the
U.S. Public Health Service (PHS), and from 1970 to the present the U.S. Envi-
ronmental Protection Agency (EPA) have provided an Off-Site Radiological Safety
Program under an Interagency Agreement. The PHS or EPA has also provided
off-site surveillance for U.S. nuclear explosive tests at places other than the
NTS.
Since 1954, an objective of this surveillance program has been to measure
levels and trends of radioactivity, if present, in the environment surrounding
testing areas to ascertain whether the testing is in compliance with existing
radiation protection standards. Off-site levels of radiation and radioactivity
are assessed by sampling milk, water, and air; by deploying dosimeters; and by
sampling food crops, soil, etc., as required. Personnel with mobile monitoring
equipment are placed in areas downwind from the test site prior to each test
in order to implement protective actions, provide immediate radiation monitor-
ing, and obtain environmental samples rapidly after any release of radioactiv-
ity. Since 1962, aircraft have also been deployed to rapidly monitor and sam-
ple releases of radioactivity during nuclear tests. Monitoring data obtained
by the aircraft crew immediately after a test are used to position mobile
radiation monitoring personnel on the ground. Data from airborne sampling are
used to quantify the amounts, diffusion, and transport of the radionuclides
released.
Beginning with Operation Upshot-Knothole in 1953, a report was published
by the PHS summarizing the surveillance data for each test series. In 1959
for reactor tests, and in 1962 for weapons and Plowshare tests, such data were
published for those tests that released radioactivity detectable off the NTS.
iii
-------
Order^l1,' tKat ^L^co'tractor orTgencyTnVolJed /nnCOrp.°rated into DOE
activities of the EPA during CY 1987 ' summarizes the off-site
IV
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CONTENTS
. ........ ill
Preface ......................... vii
Figures ....... ....... ................ ^
Tables ................. ........ ...... ,
Abbreviations, Symbols and Conversions . . ............... *'
Prefixes, Conversions. ... ......................
1. Introduction ........................ ' ' '
2
2. Summary ...................... .......
3. Description of the Nevada Test Site ..... ...........
Airborne Releases of Radioactivity
at the NTS During 1987 ................... °
4. Quality Assurance .........................
5. Radiological Safety Activities
Special Test Support ...... .
Pathways Monitoring . . .
Air Surveillance Network
Noble Gas and Tritium Surveillance Network
Long-Term Hydrological Monitoring Program
Milk Surveillance Network
Biomonitoring Program . .
External Exposure Monitoring
Thermoluminescent Dosimetry Network
Results of TLD Monitoring
Pressurized Ion Chamber (PIC) Network
Internal Dosimetry .......
6. Public Information and Community Assistance Programs ....... 35
Community Monitoring Stations . . ...............
38
7. Dose Assessment ...... . . . . ................
40
8. References ............ ...............
Appendices
A. Site Data ........... .................. A"1
B. Sample Analysis Procedures .................... B"1
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CONTENTS (Continued)
C. Quality Assurance Procedures
" <-»"" 1
D. Radiation Protection Standards for External and Internal
Exposure
D-l
E. Data Summary for the Monitoring Networks E_!
Addenda
1. REECO^Nonradiological Supplement to the NTS Environmental
Monitoring Report Add-1
VI
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FIGURES
Page
Number
1 Location of the Nevada Test Site (NTS) ............. 5
2 Air Surveillance Network stations (1987) ......... ..... 10
3 Standby Air Surveillance Network stations (1987) .......... n
4 Monthly average gross beta in air samples, 1981-1987 ........ 12
5 Noble Gas and Tritium Surveillance Network ^
sampling locations ........................
6 Weekly average krypton-85 concentration in air, 1987 data ..... 15
7 Trend in annual average krypton-85 concentration .......... 15
18
8 LTHMP sampling locations on the NTS .................
9 LTHMP sampling locations near the NTS ...............
10 Milk sampling locations within 300 km of the NTS .......... 20
11 Standby milk surveillance network stations ............. 21
12 Strontium-90 concentration in Pasteurized Milk Network ^
samples .............................
2*3
13 Collection sites for animals sampled, 1987. ... .........
14 Average strontium-90 concentration in animal bone ......... 24
OQ
15 Locations monitored with TLD's ...................
16 Average annual TLD exposure as a function of station ^
altitude ................ ............
17 Location of families in the Off-Site Human Surveillance ^
Program .......... ...................
VI 1
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FIGURES (Continued)
Number
Page
A.I Ground-water flow systems around the
Nevada Test Site . .
..................... A-4
A. 2 General land use within 300 km of the
Nevada Test Site ...
..................... A-5
A. 3 Population of Arizona, California, Nevada, and Utah
Counties near the Nevada Test Site (1986) ........ A_6
A. 4 Distribution of family milk cows and qoats
by county (1987) ......... !..'
A. 5 Distribution of dairy cows, by county (1987) ........... A_9
A. 6 Distribution of beef cattle, by county (1987) ........... A_10
A. 7 Distribution of sheep, by county (1987) .............. A_n
E.I Amchitka Island and background sampling locations
for the LTHMP ..... _ ,_
..................... E-16
E.2 LTHMP sampling locations for Project Cannikin ........... E-17
E.3 LTHMP sampling locations for Projects Milrow and Long Shot .... E-19
E.4 LTHMP sampling locations for Project Rio Blanco .......... E-21
E.5 LTHMP sampling locations for Project Rulison ...... ... E-23
E.6 LTHMP sampling locations for Project Dribble -
towns and residences r-
26
E.7 LTHMP sampling locations for Project Dribble - near GZ ...... E-
E.8 LTHMP sampling locations for Project Dribble -
near Salt Dome .................... E_28
E.9 LTHMP sampling locations for Project Faultless .......... E-30
E.10 LTHMP sampling locations for Project Shoal . .......... E-32
E.ll LTHMP sampling locations for Project Gasbuggy .......... E-33
E.12 LTHMP sampling locations for Project Gnome ............ E-34
vi i i
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TABLES
Page
Number
1 Total Airborne Radionuclide Emissions at the NTS During 1987. ... 6
2 Annual Average Krypton-85 Concentrations in Air, 1977-1987 ..... 16
3 Water Sampling Locations Where Samples Contained ^ _ n
Manmade Radioactivity - 1987 ..............
4 Network Annual Average Concentrations of Tritium _ 22
and Strontium-90 in Milk, 1975-1987.. . .. .........
5 Radionuclide Concentrations in Desert Bighorn Sheep ^ ^ ^
Samples - 1986 ....................
6 Radionuclide Concentrations in Tissues From Mule Deer
Collected on the Nevada Test Site, 198 /
7 Radionuclides Concentrations in Tissues Collected ^ 28
from NTS CHUKARS ......................
29
8 Annual Off-Site Personnel Dose 1987 TLD Results . .........
9 Dosimetry Network Summary for the Years 1971-1987 .........
10 Pressurized Ion Chamber Readings, 1987 ...............
Appendices
A 1 Characteristics of Climatic Types in Nevada ............
... B-l
B.I Sample Analysis Procedures ...............
C.I Samples and Analyses for Duplicate Sampling Program - 1987. .... C-2
C-3
C.2 Sampling and Analytical Precision - 1987 ..............
C.3 EPA Quality Assurance Intercomparison Results - 1987 ........
C.4 Quality Assurance Results from DOE Program - 1987 . ........ C'6
C.5 Quality Assurance Results for the Bioenvironmental Program - 1987 . C-9
ix
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TABLES (Continued)
Number
E.I
r o o "' E~l
Standby Stations Operated 1 or ? WP ic 'snce Network
..,-*. ^ ^ E_3
Summary of Gross Beta Analyses for
Air Surveillance Network - 1987.
E.3 ea nayses for
Air Surveillance Network - 19
E~5
E.4 F _ o.M^Mtr-dnon i
E.5 Summary of Analytical Results for the Noble Gas
and Trmum Surveillance Network - 1987. .
E.6 Summary of Tritium Results for the NTS Network
Long-Term Hydrological Monitoring Progra^ 1987 E_n
E-7 Tritium Results for the Long-term Hydrological
Monitoring Program - 1987 "'ugicai
_ 0 E-12
E.8 Summary of Analytical Results for the Milk
Surveillance Network - 1987
_ n E-38
t.y Analvtiral RocuH-c- f~~ J.U- oj_
11 Ik Surveillance
_ 1n E-40
' fro.
E-44
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ABBREVIATIONS, SYMBOLS AND CONVERSIONS
ASN
AVG
Bq
CG
Ci
CP-1
CY
d
DOE
DOE/NV
EMSL-LV
EPA
eV
9
Gy
GZ
h
HTO
L
LTHMP
m
MDC
MSL
MSN
NGTSN
NTS
Pa
PIC
QA
R
rad
rem
SD
Sv
TLD
Air Surveillance Network
Average
Becquerel , one disintegration per second
Concentration Guide
Curie
Control Point One
Calendar Year
day
U.S. Department of Energy n**-^
Department of Energy, Nevada Operations Office
Environmental Monitoring Systems Laboratory, Las Vegas
U.S. Environmental Protection Agency
electron volt
gram ,., -,/, \
Gray, equivalent to 100 rad (1 J/kg)
Ground Zero
hour
tritiated water
-
Long-Term Hydrological Monitoring Program
meter
Minimum Detectable Concentration
Mean Sea Level
Milk Surveillance Network
Noble Gas and Tritium Surveillance Network
Nevada Test Site
Pascal - unit of pressure
Pressurized ion chamber
Quality Assurance
Roentgen
unit of absorbed dose, 100 ergs/g
the rad adjusted for biological effect
Standard deviation
Si evert, equivalent to 100 rem
thermoluminescent dosimeter
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PREFIXES
a atto = 10"18
f femto = 10"15
P Pico = 10"12
n nano = 10"9
u micro = 10"6
m mi Hi = 10"3
k kilo = lo3
M mega = lo6
Multiply
Concentration Guides
uCi/mL
MCi/mL
SI Units
rad
rem
pCi
CONVERSIONS
by
109
1012
10-2
10-2
0.037
To Obtain
pCi/L
pCi/m3
Gray (Gy = 1 Joule/kg)
Si evert (Sv)
BecquereT
XI 1
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SECTION 1
INTRODUCTION
The E«SL-LV oper»es Off-Site
SSTA
sures of humans to ionizing radiation.
standard
expo-
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SECTION 2
SUMMARY
PURPOSE
Protect the genera! public and the
of the biosphere and concomitant raXtZ^ T^lh'0"^ contami'natl'°"
ment with U.S. Department of Enerav fnnn nnnV- f ., population. To this end and in agree-
Locations
Most of the radiological safety effort is
applied in the areas around the Nevada Test
Site (NTS) in south-central Nevada This
portion of Nevada is sparsely settled, 0 5
person/km^, and has a continental arid cli-
mate. The largest town in the near off-site
area is Beatty, located about 65 km west of
the NTS with a population of about 1,000.
Underground tests have been conducted in
several other States for various purposes
At these sites in Alaska, Colorado, New Mex-
ico, and Mississippi, a long-term hydrolog-
ical monitoring program is conducted to de-
tect any possible radioactive contamination
of potable water and aquifers near these
sites.
Special Test Support
During CY87, personnel were deployed in
support of the 15 announced nuclear tests at
the NTS. No radioactivity of NTS oriqin was
detected off site.
Pathways Monitoring
The pathways leading to human exposure to
radionuclides (air, water, and food) are mon-
itored by networks of sampling stations. The
networks are designed not only to detect
radiation from DOE/NV nuclear test areas but
also to measure population exposure from
other sources. No positive results were ob-
tained by these networks this year that could
be attributed to NTS activities.
In 1987 the air surveillance network (ASN)
consisted of 30 continuously operating sta-
tions surrounding the NTS and 83 standby
stations (operated 1 or 2 weeks each quarter)
in all States west of the Mississippi River.
Other than naturally occurring beryllium-?'
the only activity detected by this network
was plutonium-239 from worldwide fallout.
The noble gas and tritium sampling network
(NGTSN) consisted of 17 stations off site
(off the NTS and exclusion areas) in 1987.
No NTS-related radioactivity was detected at
any off-site station by this network. Trit-
ium concentrations in air remained below Min-
imum Detectable Concentration (MDC) levels
and krypton-85 concentrations continued the
upward trend, reflecting the worldwide in-
crease in the use of nuclear technology.
The long-term monitoring of wells and sur-
face waters near sites of nuclear tests
showed only background radionuclide concen-
trations except for those wells that had
detectable activity in previous years or
those that had been spiked with radionuclides
for hydrological tests.
The milk surveillance network consisted of
28 sampling locations within 300 km of the
NTS and about 122 standby locations in the
Western U.S. The tritium concentration in
milk was at background levels, and strontium-
90 from worldwide fallout continued the slow
downward trend observed in recent years.
Other foods analyzed have been mainly meat
from domestic or game animals. The radionu-
clide most frequently found in the edible
portion of the sampled animals is cesium-137.
However, its concentration has been near the
MDC since 1968. Strontium-90 in samples of
-------
animal bone remain at very low levels as does
plutonium-239 in both bone and liver samples.
External Exposure
External exposure is monitored by a net-
work of thermoluminescent dosimeters (TLD s)
at 132 fixed locations surrounding the NTb
and by TLD's worn by 58 off-site residents.
In a few cases, small exposures of a few
millirem (mrem) above the average for the
person were measured. Except for several
occupational exposures, all such net expo-
sures were very low and were not related to
NTS activities. The range of exposures meas-
ured varying with altitude and soil constit-
uents, is similar to the range of such expo-
sures found in other areas of the U.S.
Internal Exposure
Internal exposure is assessed by whole-
body counting supplemented by semi-planar and
intrinsic detectors to measure lung burdens
of radioactivity. In 1987, counts were made
on 230 individuals from the off-siteareas
around the Nevada Test Site, the EMSL-LV
Laboratory, EG8.G facilities throughout the
United States and members of the general pub-
lic concerned about possible radiation expo-
sure No nuclear test related radioactivity
was detected. In addition, physical examin-
ations of the off-site residents revealed a
normally healthy population consistent with
the age and sex distribution of that popula-
tion.
Community Monitoring Stations
The 15 Community Monitoring Stations be-
came operational in 1982. Each station is
operated by a resident of the community who
is trained to collect samples and interpret
some of the data. Each station is an inte-
qral part of the ASN, NGTSN and TLO networks
and is also equipped with a pressurized ion
chamber system and recording barograph.
Samples and data from the stations are ana-
lyzed by EMSL-LV and are also interpreted
and reported by the Desert Research Insti-
tute, University of Nevada. Data from these
stations are reported herein as part of the
networks in which they participate.
Dose Assessment
Doses were calculated for an average adult
living in Nevada using the radionuclides
measured in samples collected by the monitor-
ing networks. Using conservative assump-
tions, the estimated dose would have been
about 0.16 mrem (1.6 uSv) for 1987. No
radioactivity originating on the NTS was de-
tectable by the monitoring networks; there-
fore, no dose assessment can be made. How-
ever based on the NTS releases reported in
Table 1, atmospheric dispersion calculations
(AIRDOS/EPA) indicate that the highest indi-
vidual dose would have been 0.2 ureni (0.002
uSv), and the dose to the population within
80 km of Control Point One (CP-1) would have
been 5.9 x 10'4 person-rem (5.9 x 10 ° per-
son-Sv).
In the unlikely event that a certain mule
deer had been collected by a hunter rather
than by EPA personnel, that hunter could have
received a dose equivalent of 29 mrem (0.29
mSv) if he ate all the liver and meat from
the deer.
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SECTION 3
DESCRIPTION OF THE NEVADA TEST SITE
.. Jr T1eai; "eapons '
Site Location
The NTS is located in Nye County, Nevada,
with its southeast corner about 90 km north-
west of Las Vegas (Figure 1). It has an area
of about 3,500 square km and varies from 40
to 56 km in width (east-west) and from 64 to
88 km in length (north-south). This area
consists of large basins or flats about 900
to 1,200 m above mean sea level (MSL) sur-
rounded by mountain ranges rising 1,800 to
2,300 m above MSL.
The NTS is surrounded on three sides by
exclusion areas, collectively named the Nel-
lis Air Force Base Range Complex, which pro-
vide a buffer zone between the test areas
and public lands. This buffer zone varies
from 24 to 104 km between the test area and
land that is open to the public. Depending
upon wind speed and direction at the time of
testing, from 2 to more than 6 hours will
elapse before any release of airborne radio-
activity could pass over public lands.
Climate
The climate of the NTS and surrounding
area is variable, due to its variations in
altitude and its rugged terrain. Generally,
the climate is referred to as continental
and. Throughout the year, there is insuf-
ficient precipitation to support the growth
of common food crops without irrigation.
As Houghton et al. (Ho75) point out, 90
percent of Nevada's population lives in areas
with less than 25 cm of rainfall per year or
in areas that would be classified as mid-
latitude steppe to low-latitude desert
regions.
The wind direction, as measured on a 30 m
tower at an observation station about 9 km
NNW of Yucca Lake near CP-1, is predominantly
northerly except during May through August
when winds from the south-southwest predomi-
?Sn/(5i?8)- -I6""56 °f the Prevalent moun-
tain/valley winds in the basins, south to
southwest winds predominate during daylight
hours of most months. During the winter
months southerly winds have only a slioht
edge over northerly winds for a few hours
during the warmest part of the day. Wind
patterns are often quite different at other
locations on the NTS because of local terrain
effects and differences in elevation.
Geology and Hydrology
Geological and hydrological studies of the
NTS have been in progress by the U.S. Geolog-
ical Survey and various other organizations
since 1956. Because of this continuing ef-
* u \ e surface and underground geological
and hydrologlcal characteristics for much of
the NTS are known in considerable detail (see
Figure A-l). This is particularly true for
those areas in which underground experiments
are conducted. A comprehensive summary of
the geology and hydrology of the NTS was pub-
lished in 1975 (Wi75).
The aquifers underlying the NTS vary in
depth from about 200 m beneath the surface
of valleys in the southeastern part of the
site to more than 500 m beneath the surface
of highlands to the north. Although much of
the valley fill is saturated, downward move-
ment of water is retarded by various tuffs
and is extremely slow. The primary aquifer
in these formations consists of Paleozoic
carbonates that underlie the more recent
tuffs and alluviums.
Land Use of NTS Environs
Industry within the immediate off-NTS area
includes approximately 40 active mines and
mills, oil fields in the Railroad Valley
area, and several industrial plants in Hen-
derson, Nevada. The number of employees for
-------
Fallen Austin
^^-
50
[ Cedar City
St. George
Scale in Miles
50 1QO
150
100 150 200
Scale in Kilometers
5/88
Figure
1. Location of the Nevada Test Site (NTS)
5
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several ti°nS "^ V?ry fr°m One Person «*
u^I 2f ^u Sma11 nilnes to several hundred
?*% °r* the Oil fields north of 'he NTS
and the industrial plants in Henderson. Most
fl« th,1fldinVJdUaJ nrfn1n9 °Perati°ns involve
less than 10 workers per mine; however, a few
operations employ 100 to 250 workers.
The major body of water close to the NTS
is Lake Mead (120 km southeast, Figure A 2)
a man-made lake supplied by water from 'the
Colorado River. Lake Mead supplies about 70
percent of the water used for domestic, rec-
reational, and industrial purposes in the Las
Vegas Valley. Some Lake Mead water is used
in Arizona, southern California, and Mexico
Smaller reservoirs and lakes located in the
area are used primarily for irrigation, for
watering livestock, and for wildlife refuges.
tm Da1!2 faur.?cn9 1>S not extensive within 300
A Mh fa \ AS Sh°Wn in Fl'9ures A'4 a"d
A. 5 the family cows and goats are distributed
in all directions around the NTS, whereas
most dairy cows are located to the southeast
along the Muddy and Virgin River valfeys and
n thS V*9?S> Nevada)' northeast (Lund), and
southwest (near Barstow, California).
inntm \l the.most col°n land use within
300 km of the site. Approximately 600,000
cattle and 200,000 sheep are distributed
within the area as shown in Figures A. 6 and
A.7. respectively. The estimates are based
on information supplied by the California
LVestock ^Porting service (CA85).
H ^ 198? agHCUl tUral Statistics
by the Nevada Department of Agricul-
ture (NV86) and 1987 estimates based on 1982
census information supplied by the Utah
Department of Agriculture (UT87).
Population Distribution
Excluding Clark County, the major popula-
tion center (approximately 569,500 in 1986),
the population density within a 150 km radius
of CP-1 pn the NTS is about 0.5 persons per
square kilometer. For comparison, the 48
contiguous states (1980 census) had a popula-
tion density of approximately 29 persons per
square kilometer. The estimated average pop-
ulation density for all of Nevada in 1980 was
2.8 persons per square kilometer.
The off-site area within 80 km of the NTS
(the area in which the dose commitment must
be determined for the purpose of this report)
is predominantly rural, Figure A. 2. Several
small communities are located in the area
the largest being in the Pahrump Valley.'
This growing rural community, with an esti-
mated population of about 6,000, is located
about 72 km south of the NTS CP-1 The
Amargosa Farm Area, which has a population of
about 850 is located about 50 hf uutZ£t
of CP-1. The largest town in the near off-
site area is Beatty, which has a population
« K tVe JVi.r*' 'W""">?*
AIRBORNE RELEASES OF RADIOACTIVITY
AT THE NTS DURING 1987
All nuclear detonations during 1987 were
Ai?d,nMthd "nder9round and were contained.
Although releases of low-level radioactivity
occurred during re-entry drilling, seepage
through fissures in the soil or purging of
tunnel areas. Table 1 shows the total quan-
tities of radionuclides released to the at-
mosphere, as reported by the DOE Nevada
Operations Office (DOE88). Because these
releases occurred throughout the year and
because of the distance from the points of
releases to the nearest sampling station
?h°?^ t°Lthe rad1oact1ve material listed in
this table was detected off site.
TABLE 1. TOTAL AIRBORNE RADIONUCLIDE
EMISSIONS AT THE NTS DURING 1987
Half-Life
Radionuclide (days)
Tritium
Krypton-85
Xenon-127
Xenon-133
Xenon-133 m
Xenon-135
Xenon-131 m
Xenon (Isotopic
Cesium-137 11
Argon-37
Iodine (Isotopic
4500
3990
36.4
5.24
2.2
0.38
11.92
mixture unknown)
,030.6
34.8
mixture unknown)
Quantity
Released
(Ci)
126 4
5 042
0.0003
44 02
2 no
0 005
1 0
29.0
0.000017
1 0
0.101
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SECTION 4
QUALITY ASSURANCE
^ra.^.J?-KCi3!rtri."d«S'>i..«
and
ance procedures.
Sample Collection
The collection of samples is governed by
a detailed set of Standard Operating Proce-
dures (SOP's). These SOP's prescribe the
fluency and method of collection, the type
of Collection media, sample containment and
transport, sample preservation, sample iden-
tification and labeling, and operating param-
eters for the instrumentation. Sample con-
trol is an important segment of these activ-
ities as it enables tracking from collection
to analysis for each sample and governs the
selection of duplicate samples for analysis
and the samples chosen for replicate anal
ysis.
These procedures provide assurance that
sample collection, labeling and handling are
standardized to minimize sample variabi ity
due to inconsistency among these variables.
Sample Analysis
All of the networks operated by the EMSL-
LV have individual Quality Assurance Project
olans The procedures required by these
SMS assure that the results of analyse
will be of known quality and will be compar-
ab e to results obtained elsewhere with
equivalent procedures. These Plans are sum-
marized in the following sections.
External Quality Assurance
External QA provides the data from which
the accuracy of analysis (a combination of
bias and precision) can be determined Bias
is assessed from the results obtained on
ntercomparison study samples and on samples
"soiked" with known amounts of radionuclides.
The Off-Site Radiological Safety Program par-
ticipates in intercomparison Study Programs
that include environmental sample analysis
TLD dosimetry, and whole-body counting.
Also, samples which are undisclosed to the
analyst a?e spiked by adding known.amounts of
radionuclides and then entered into the nor
mal chain of analysis.
Data for precision are collected from dup-
licate and replicate analyses. At least lu
percent of all samples are collected in dup
11 cite. When analyzed, the data indicate the
precision of both sample collection and anal-
ysIS Replicate counting of at least 10 per-
cent of all samples yield data from.which the
precision of counting can be determined.
If the bias and precision data are of suf-
ficient quality (i.e., normalized deviation
in TableqC.3 Is less.than 3). then compar-
ability, i.e., comparison of the data witn
those of other analytical laboratories, can
Ee assessed with confidence The .results of
external QA procedures are shown in Appendix
C.
Internal Quality Assurance
Internal QA consists of those Procedures
used by the analyst to assure proper sample
Separation and analysis. The principal pro-
cedures used are the following:
Instrument background determinations
Blank and reagent analyses
Instrument calibration with known nu-
Laboratory control standards analysis
Performance check-source analysis
Maintenance of control charts for back-
ground and check-source data
0 Scheduled instrument maintenance.
These procedures ensure that the instrumenta-
tion is not contaminated, is operating prop-
erly and that calibration 1s correct, and
that samples carried through the total ana-
lytical procedure are accurately analyzed.
Validation
After the results are produced, supervi-
sory personnel examine the data to determine
whether or not the analysis is valid. Th s
includes checking all procedures from sample
receipt to analytical result with particular
attention to the internal QA data and^compar-
ison of the results with previous data from
similar samples at the same location.
Any variant result °r failure to follow
internal QA procedures during sample analysis
-------
will trigger an internal audit of the analyt-
ical procedures and/or a re-analysis of the
sample or its duplicate
Audits
All analytical data are reviewed by per-
sonnel of the Dose Assessment Branch for
completeness and consistency. Investigations
are conducted to resolve any inconsistencies
sarv C°snP' 1V6H nfti0ns 3re taken 1f neces-
lly' H 5 * ,?"d QA project plans are reused
ffth S ? Allowing review of procedures and
methodology. The EMSL-LV QA Officer audits
the operations periodically
-------
SECTION 5
RADIOLOGICAL SAFETY ACTIVITIES
described in the following portions of this report.
Special Test Support
Before each nuclear test, monitoring per-
sonnel are positioned in the off-site areas
most likely to be affected should a release
of radioactive material occur. They ascer-
tain the locations of residents, work crews
and domestic animal herds and obtain infor-
mation relative to residents in communities
and remote areas. These monitors, equipped
with radiation survey instruments, gamma
exposure-rate recorders, thermoluminescent
dosimeters (TLD's), portable air samplers,
and supplies for collecting environmental
samples, are prepared to conduct a monitoring
program as directed from the NTS Control
Point (CP-1) via two-way radio communica-
tions.
For those tests which might cause ground
motion detectable off site, EPA monitors are
stationed at locations where hazardous situ-
ations might ensue such as underground mines.
At these locations, occupants are notified of
potential hazards so they can take precau-
tionary measures.
Professional EPA personnel serve as mem-
bers of the Test Controller's Advisory Panel
to provide advice on possible public and
environmental impact of each test and on
feasible protective actions in case acciden-
tal releases of radioactivity should occur.
An EG&G cloud sampling and tracking air-
craft is'always flown over the NTS to obtain
samples, assess total cloud volume, and pro-
vide long-range tracking in the event of a
release of airborne radioactivity. A second
aircraft is also flown to gather meteorolog-
ical data and to perform cloud tracking.
Information from these aircraft can be used
in positioning the radiation monitors.
During CY 1987, EMSL personnel were de-
ployed for all underground tests, none of
which released radioactivity which could be
detected off site.
PATHWAYS MONITORING
The off-site radiation monitoring program
includes a pathways monitoring system con-
sisting of air, water and milk surveillance
networks surrounding the NTS and a limited
animal sampling project. These are explained
in detail below.
AIR SURVEILLANCE NETWORK (ASN)
Network Design
The ASN monitors an important route of
human exposure to radionuclides, inhalation
of airborne materials. The concentration and
the source must both be determined if appro-
priate corrective actions are to be taken.
The ASN is designed to monitor the areas
within 350 km of the NTS with some concentra-
tion of stations in the prevailing downwind
direction (Figure 2). The coverage Is con-
strained to those locations having available
electrical power and a resident willing to
operate the equipment. This continuously
operating network is supplemented by a stand-
by network which covers the contiguous States
west of the Mississippi River (Figure 3).
Methods
During 1987 the ASN consisted of 31 con-
tinuously operating sampling stations and 83
standby stations. The air sampler at each
station was equipped to collect both partic-
ulate radionuclides and reactive gases.
Samples of airborne particulates were col-
lected at each active station on 5-cm diam-
eter glass-fiber filters at a flow rate of
about 82 m3 per day. Filters were changed
after sampler operation periods of 2 or 3
days (163 to 245 m3). Activated charcoal
cartridges placed directly behind the filters
to collect gaseous radioiodine were changed
at the same time as the filters. The standby
network was activated for 1 to 2 weeks per
quarter at most locations. The standby sam-
-------
\J Pyramid Lake
Sunnyside
o* ^ L-
Stone Cabm Rn.
Tonopah
Goldfield
B|uEag|e Rn
Nyala
Twin Springs Rn.
N
Scotty's Jet.
Rachel
Pioche
> Hiko^Caliente
Alamo
Salt Lake City
Delta
> Milford
I
i Cedar City |
Beatty
Lathrop Wells*1
x
c _ X Springs
Furnace Creek* pahrumPB .
Death Valley Jet.
* \^ Vegas
Shoshone
Community Monitoring Stations (15)
Other Locations (16)
\ I
Nevada
JTest
[Site
i1 %r
Groom
Lake
^ In^-li'^v^
St. George I
Arizona s/aa
,Overton
Lake Mead
Figure 2. Air Surveillance Network stations (1987).
10
-------
CANADA
North Dakota \ Minnesota
A A I
Arizona I New Mexico
Scale in Miles
100
^^ i i i i i
100 300 500 700
Scale in Kilometers
A Stand-by ASN Station
Figure 3. Standby Air Surveillance Network stations (1987),
11
-------
piers are identical to those used in the ASM
and are operated by State and municipal
health department personnel or by local resi-
dents. All air filters and charcoal car-
tridges were analyzed at the EMSL-LV.
Results
During 1987, no airborne radioactivity re-
lated to nuclear testing at the NTS was de-
tected on any sample from the ASM. Through-
out the network, beryllium-7 was the only
nuclide detected by gamma spectroscopy. The
principal means of beryl!ium-7 production is
from spallation of oxygen-16 and nitrogen-14
in the atmosphere by cosmic rays. Appendix
Tables E.I and E.2, summarize the data from
the ASN samples. All time-weighted averages
(Avg in the tables) are less than 1 percent
of the Concentration Guide (Appendix D) for
exposure to the general public, however,
these guides do not apply to naturally occur-
ring radionuclides.
Two additional analyses are performed on
the samples from the ASN: a gross beta
analysis of the filters from 5 stations, and
plutonium-238 and plutonium-239 analysis of
composited filters from 15 states. The re-
sults from the plutonium-239 analyses are
shown in Appendix Table E.4; plutonium-238
results were all less than the MDC.
The gross beta analysis is used to detect
trends in atmospheric radioactivity since
this analysis is more sensitive than gamma
spectrometry. For this study, three stations
north and east of the NTS, and two stations
south and west of the NTS are used. The
three filters per week from each station are
analyzed for gross beta activity after a
7-day delay to decrease the contribution from
thoron daughter activity. The data suggest
little significant difference among stations
and indicate a relatively stable concentra-
tion compared to previous years (Figure 4).
The maximum concentration measured was 0.053
pCi/mJ, the minimum was <0.001 pCi/m3, and
the arithmetic average was 0.0094 pCi/m3
10.35 mBq /mj). A summary of the data is
shown in Appendix Table E.3.
.1-1
co
o
a
.01-
CD
m
M
.001
«
1981
ii'Miii
1982
1983
n
I I I Ml Ml I Illl I [III || I | mi [inn I ||
1984 | 1985 I 1986 1987
*Elevated concentration attributed to April 1986 accident at Chernobyl,
U.o.o.K. *
Figure 4. Monthly average gross beta in air samples, 1981-1987.
12
-------
NOBLE GAS AND TRITIUM SURVEILLANCE NETWORK
(NGTSN)
Network design
There are several sources for the radionu-
clides monitored by this network. Noble
gases are emitted from nuclear power plants,
propulsion reactors, reprocessing facilities
and nuclear explosions. Tritium is emitted
from the same sources and is also produced
naturally. The monitoring network will be
affected by all these sources, but must be
able to detect NTS emissions. For this pur-
pose some of the samplers are located close
to the NTS and particularly in drainage-wind
channels leading from the test areas. In
1987 this network consisted of 17 stations as
shown in Figure 5.
Methods
Samples of air are collected by directly
compressing air into pressure tanks. The
equipment continuously samples air over a 7-
day period and stores approximately 1 m° of
air in the pressure tanks. The tanks are
exchanged weekly and returned to the EMSL-LV
where their contents are analyzed. Analysis
starts by condensing the samples at liquid
nitrogen temperature and using gas chroma-
tography to separate the gases. The separate
fractions of radioxenon and radiokrypton are
dissolved in scintillation cocktails and
counted in liquid scintillation counter (see
Appendix B).
For tritium sampling, a molecular sieve
column is used to collect water from air
after it passes through a particulate filter.
Up to 10 m3 of air are passed through the
column over a 7-day sampling period. Water
adsorbed on the molecular sieve is recovered,
and the concentration of tritium in the water
(HTO) is determined by liquid scintillation
counting (see Appendix B).
Results
The results from the samples collected by
the NGTSN are shown in the Appendix (Table
E.5) as the maximum, minimum and average con-
centration for each station. The krypton-85
concentrations ranged from 19 to 34.2 pCi/m-3.
A paper presented by Bernhardt et al., (Be73)
in a 1973 symposium contained a curve that
predicted krypton-85 concentration for the
future. This information was used as the
basis for an ongoing study of krypton-85
concentrations in air. This actual meas-
urement system began in 1972, so the Bern-
hardt values for the years 1960, 1965, and
1970 were used to provide a historical ref-
erence for the time period preceding the
actual measurement of krypton-85 concentra-
tions in air.
Because actual data for the period 1972-
1987 have been collected, it is no longer
necessary to include the Bernhardt values.
These actual data were used to generate a
least squares linear regression line. Com-
paring this equation to the same equation in
prior annual reports shows a difference.
This is due to the fact that the new equation
is based on sixteen consecutive years of
actual data (1972-1987) and does not include
values given by Bernhardt for 1960, 1965, and
1970.
The concentration over the whole network
appeared to have a normal distribution with a
mean of 25.5 pC1/m3 (0.94 Bq/m3) and a stand-
ard deviation of 0.4. The weekly averages
plus and minus one standard deviation for the
network are shown in Figure 6. This network
average concentration, as shown in Table 2
has gradually increased since sampling began
in 1972. This increase, observed at all
stations, reflects the worldwide increase In
ambient concentrations resulting from the
increased use of nuclear technology. The
increase in ambient krypton-85 concentration
was projected by Bernhardt et al., (Be73),
However/the measured network average in 1985
is only about 13 percent of the 250 pCi/nr> (9
Bq/m3) predicted by Bernhardt. Since nuclear
fuel reprocessing is the primary source of
krypton-85, the decision of the United States
to defer fuel reprocessing may be one reason
why krypton-85 levels have not increased as
fast as predicted.
Using data from our network (Table 2), the
change over time was plotted as shown in Fig-
ure 7. Linear regression analysis indicates
that the krypton concentration/time relation
is pCi/m3 = 15.49 + 0.66t where t is number
of years after 1970. The correlation coef-
ficient, R, is 0.95.
As in the past, tritium concentrations in
atmospheric moisture samples from the off-NTS
stations were generally below the minimum de-
tectable concentration (MDC) of about 400
pCi/L water (Appendix Table E.5). Negative
numbers were statistically derived and are
only representative of values which are less
than the minimum detectable concentration
(MDC). The tritium concentrations observed
at off-NTS stations were considered to be
representative of environmental background.
The mean of the tritium concentrations for
all off-site stations was 0.62 pCi/mJ (23
mBq/tn3) of air. Only six of the 815 collec-
ted samples were above the MDC.
13
-------
I
0)
Q.
tt
N
Ely I
Pioche
Rachel
Caliente
Alamo
C
sr
Salt Lake City
Cedar City
St. George
Arizona 5/88
Lathrop Wells,__ _ _
v" Indian g Overton
X Springs A |
_ . X I/Laki
Pahrump g ^-<^L /t
Las \f^\lf
Shoshone X Ve9as i
Lake Mead
Figure 5. Noble Gas and Tritium Surveillance Network sampling locations.
14
-------
70-
65-
60-
55-
50-
45-
40
35
30
25
20
15
10
Jan
'I'JJJ K 'lV;>V i 'VsVs1 5 'I'B'M' 5 'is'^S1 5 'Vs' 251 5 'l'5 25 5 15 25 5 15 25 5 15 25 5 15 .
F?b25 M., Apr M.y Jun JU, Aug Sep, Oc, Nov Dec
1987
Figure 6. Weekly average krypton-85 concentration in air, 1987 data.
30-i
25-
u
a
c
o
c
a
u
o
O
20-
15-
= 15.49 + 0.66t
R = 0.95
1970
1975
I
1980
1
1985
I
1990
Figure 7.
Time-Calendar Years
Trend in annual average krypton-85 concentration
15
-------
TABLE 2. ANNUAL AVERAGE KRYPTON-85 CONCENTRATIONS IN AIR, 1977-1987
Sampling
Locations
Alamo, JJV
Austin, NY
Beatty, NV
Diablo and
Rachel, NY**
Ely, NV
Gold Held, NV
Hiko, NY*
Indian Springs,
HV
Mammoth Lakes, CA
NTS, Mercury, NV*
NTS, Groom Lake, NV*
NTS, BJY, NV*
NTS, Area 12, NV*
Tonopah, NV
Las Vegas, NV
Death Valley Jet.,
CA*
NTS, Area 15, NV*
NTS, Area 400, NV*
Lathrop Hells, NV
Pahrump, NV
Overton, Nev.
Cedar City, Ut.
St. George, Ut.
Salt Lake City, Ut.*
Shoshone, CA
NETWORK AVERAGE
. _
^
Kr-85 Concentrations
1977
20
19
19
20
20
19
21
19
19
20
20
~
20
1978
20
20
20
20
20
20
22
20
20
20
20
20
1979
~m« «»«.
19
19
19
19
19
19
21
19
18
19
19
18
19
--
19
1980
21
21
21
21
21
21
23
21
21
..
21
21
22
--
«
21
1981
27
"*~
24
24
24
24
23
24
26
24
25
24
25
23
24
23
26
._
24
1982
24
24
25
26
24
25
26
24
::
24
24
24
24
24
25
24
25
25
24
1983
25
25
24
24
25
24
25
-
25
24
26
24
25
24
25
25
25
25
(pC1/m3)
1984
24
23
23
22
22
24
22
--
~
23
23
__
22
23
23
22
23
25
23
23
1985
^m^^MMm
24
25
25
24
24
24
24
25
25
,._
24
25
24
24
24
25
24
24
1986
^MHM
24
25
26
25
26
25
26
«
25
25
--
^_
25
25
25
24
24
25
25
1987
i^^ wvw^_^_
26
25
26
25
25
25
26
26
--
26
25
~
v«
25
26
25
26
25
26
26
*Stat1ons discontinued
**Stat1on at Diablo was moved to Rachel In March 1979.
LONG-TERM HYDROLOGICAL MONITORING PROGRAM
Tritium and gamma-spectral analysis were
done on samples taken from 157 wells, springs,
and other sources of water at locations where
underground nuclear explosives tests have
been conducted. Gamma radioactivity was
found in only two sampled locations where
cesium-137 had been used in a hydro!ogic
study. The tritium concentrations found dur-
ing this sampling year were consistent with
the levels found in previous years. In only
four samples were the tritium concentrations
greater than the Drinking Water Standards,
and those samples were from wells not acces-
sible to the general public.
16
-------
Background
Surface- and ground-water sampling and
analysis from water sources around the Nevada
Test Site (NTS) have been performed for many
years. As underground nuclear tests occurred
in other states, water sampling programs were
instituted. Finally, in 1972, all of the
water sampling programs were combined to con-
stitute the Long-Term Hydrological Monitoring
Program (LTHMP). At each of the sites of
underground nuclear tests, water sampling
points were established by the U.S. Geolog-
ical Survey so that any migration of radio-
activity from the test cavities to potable
water sources could be detected by radio-
analysis.
The 22 wells on the NTS and the 31 wells
in areas around the NTS which are part of
this program are shown in Figures 8 and 9
respectively. The locations of the sampling
points at other than NTS locations in Nevada,
Alaska, Colorado, Mississippi, and New Mexico
are shown in Figures E.I through E.12, in
Appendix E.
Methods
At nearly all locations, the standard op-
erating procedure is to collect four samples.
Two samples are collected in 500-mL glass
bottles to be analyzed for tritium. The
results from analysis of one of these is re-
ported while the other sample serves as a
backup in case of loss, or if the tritium is
at detectable concentration, as a duplicate
sample. The remaining two samples are col-
lected in 4 L plastic containers (cubit-
ainers). One of these is analyzed by gamma
spectrometry and the other is stored as a
backup or for duplicate analysis. For wells
with operating pumps, the samples are collec-
ted at the nearest convenient outlet. If the
well has no pump, a truck-mounted sampling
rig is used. With this rig it is possible to
collect 3-liter samples from wells as deep as
1800 meters. The pH, conductivity, and tem-
perature of the water is measured when the
sample is collected.
The tritium and gamma spectrometric anal-
yses are described in the Appendix. For
those samples in which the tritium concentra-
tion is less than 700 pCi/L (26 Bq/L), an
enrichment procedure is performed which re-
duces the MDC to 10 pCi/L (0.37 Bq/L) from
about 300 pCi/L (11 Bq/L). Also, for the
first time a water source is sampled, the
sample is analyzed for strontium-89 and -90,
radium-226, uranium isotopes, and plutonium-
238, -239.
For those operations conducted in other
states, samples for the LTHMP are collected
annually. For the locations on the NTS lis-
ted in Table E.6 in Appendix E, the samples
are collected monthly, when possible, and
analyzed by gamma spectrometry as well as for
tritium. For a few NTS wells and for all the
water sources around the NTS a sample for
tritium analysis is collected twice per year
at about a 6-month interval. During the
other 10 months, only a cubitalner of water
is collected for analysis by gamma spectrom-
etry. One of the two samples collected for
tritium analysis is analyzed by the conven-
tional method, the other by the enrichment
method.
Results
The locations at which the water samples
were found to contain man-made radioactivity
are shown in Table 3 along with the analyt-
ical results. For tritium concentrations,
only those samples in which the concentration
exceeded 0.01 of the Drinking Water Standard
(i.e. >200 pCi/L) are shown. The radioactiv-
ity in the samples collected from those loca-
tions has been reported before.
The results of analysis for all collected
samples are shown in Appendix Tables E.6 and
E.7 together with the percent of the relevant
concentration guide that is listed in Appen-
dix D. There were 11 new sampling locations
this year. Only some of the radiochemical
results are available at present, as shown
in the notes to the tables in the Appendix.
None of the samples from the new locations
had a detectable concentration of strontium-
89 or -90.
Discussion
Although some positive results, that is
detectable amounts of man-made radionuclides,
are shown for some of the water samples, none
of them are expected to result in measurable
radiation exposures to residents in the areas
where the samples were collected. Specifi-
cally, these were as follows:
NTSWell UE7ns is located on the NTS, a
restricted area, and the well is not used as
a culinary water source.
Project GnomeWells USGS 4 and 8 were
used for a hydrological tracer study many
years ago so the radionuclides detected were
consistent with previous results. These
wells are capped and locked to prevent use.
Well LRL-7 is expected to show elevated lev-
els of radionuclides as it was used for
disposal of contaminated soil and salt. It
is also guarded to prevent access.
17
-------
4\ / Test Well D
WellUE16d \ L \ \
V \ i
\\-i4Well C
AWellC-1
4CP-1A
Nuclear Rocket
Development Station
Desert Game
Range
Figure 8. LTHMP sampling locations on the NTS.
18
-------
Twin Springs Rn.
Tonopah
Nyala
Adaven Springs
»TTR Well #6
Nellis AFB
Range Complex
Spicer
Springdale
Goss Springs
Beatty
\
Nevada
Test Site
Coffer's
,11S/48-1dd
Younghans Ranch(2)
Specie Springs
US Ecology
X.
NRDS Mercury
I
N
Lathrop Wells £
X
V «
Well17S/50E-14CaCi
X
Well 18S/51E-7db<
Death Valley Jet *
£ Tempiute
iPenoyer(S) .Hiko
Crystal Springs
A Alamo
1 Fairbanks Springs
9 Crystal Pool
| *Ash Meadows
Indian Springs
Sewer Co. Well #1
Calvada Well
Scale in Miles
10 20 30
40
Shoshone
Spring
Nevada
X
10 20 30 40 50 60
Scale in Kilometers
Nevada Test Site &
Nellis AFB Range
_ Las Vegas
9 Well #28
Lake Mead(
Intake
Location Map Nj 5/88
Figure 9. LTHMP sampling locations near the NTS.
19
-------
Winnemucca
Wells
Elko
I
Q.
01
Larsen Rn I
> Reno
Austin
Young Rn.
McGill
Burdick Rn. I
Ely
Round Mtn. _
Berg Rn.
Warm Springs
Twin Spgs. Rn.l
Manzonie Rn
Currant
Penoyer
>Farms |
Blue Eagle Rn.
Nyala
1 Sharp's Rn.
Rachel
Darrel Hanson
H Harbecke Rn.
Shoshone
| Lund
McKenzie Dairy
June Cox Ce£r CitV
_
Caliente
Alamo
Whipple Rn.
Moapa 0
^-
Indian Spgs. Decade Corp
50 100 150
Scale in Kilometers
I Milk Sampling Locations
Pahrump «
Rn.
Brent Jones
Dairy
I St. George
'Cannon Farm
NOTE: When sampling location occured
in city or town, the sampling location
symbol was used for showing both town
and sampling location
Ridgecrest
Cedarsage Farm
|* Barstow
Bill Nelson Dairy
Hinkley
Mesquite
SF and K Dairy
Knudsen Corp
Logandale
LDS Dairy Farm
5/88
'9
\\
Figure 10. Milk sampling locations within 300 km of the NTS.
20
-------
TABLE 3. WATER SAMPLING LOCATIONS WHERE
SAMPLES CONTAINED MAN-MADE
RADIOACTIVITY - 1987
Sampling Location
Type of
Radioactivity
Cone.
(pd/L)
NTS, NV
Well UE7NS
PROJECT GNOME, NM
USGS Well 4
USGS Well 8
Well LRL-7
Hydrogen-3 2400-3500
Hydrogen-3
Hydrogen-3
Cesium-137
Hydrogen-3
Cesium-137
200,000
150,000
90
16,000
200
PROJECT RULISON,
HAYWARD RANCH
PROJECT DRIBBLE, MS
Well HMH-1
through 11
Well HM-S
Well HM-L
REECo Pit
Drainage-B
REECo Pit
Drainage-C
PROJECT LONG
SHOT, AK
Stream E of GZ
Well GZ, No. 1
Mud Pit No. 1
Mud Pit No. 2
Mud Pit No. 3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
Hydrogen-3
220
25-33,000
11,000
1.100-1,400
7,800
550
230
2,400
250
310
470
cow-milk chain. This pathway is monitored by
EMSL-LV through analysis of milk. The design
of the network is based on collections from
areas likely to be affected by accidental
releases from the NTS as well as from areas
unlikely to be so affected. Additional con-
siderations are: 1) a complete ring of sta-
tions to cover any NTS release, and 2) sam-
ples from major milksheds as well as from
family cows. The availability of milk cows
or goats sometimes restricts sample collec-
tion in certain areas.
Methods
The network consists of two major por-
tions, the MSN at locations within 300 km of
the NTS from which samples are collected
monthly (Figure 10) and the standby network
(SMSN) at locations in all major milksheds
west of the Mississippi River (Figure 11)
Project DribbleWells at this location
are on private land, about one mile from the
nearest resident and are not sources for
drinking water.
Project AlaskaThe shallow wells at Pro-
ject Longshot on Amchitka Island are in an
isolated location and are not sources of
drinking water.
MILK SURVEILLANCE NETWORK (MSN)
An important
radionuclides to
pathway for transport of
humans is the air-forage-
5/88 ' ,,
Figure 11. Standby milk surveillance network stations.
from which samples are collected annually.
One exception to the latter portion of the
network is Texas; the State Health Department
performs the surveillance of the milksheds in
that State.
The monthly raw milk samples are collec-
ted by EPA monitors in 4 L cubitalners and
preserved with formaldehyde. The annual milk
samples are also collected in cubitainers and
preserved with formaldehyde but they are col-
lected by contacting State Food and Drug
Administration representatives, after notifi-
cation of the Regional EPA offices, who ar-
range for the samples to be mailed to EMSL-
LV.
All the milk samples are analyzed first
for gamma-emitting nuclides by high-resolu-
21
-------
tion gamma spectrometry and periodically for
stront1um-89 and strontium-90 by the methods
outlined in Appendix B, after a portion of
milk is set aside for tritium analysis. Oc-
casionally a milk sample will sour, thus
preventing its passage through the ion ex-
change column and its subsequent strontium
analysis; however, the other analyses can
generally be performed satisfactorily. For
tne SMSN, two locations in each State are
selected for tritium and strontium analyses.
The analytical results from the 1987 MSN
samples are summarized in Appendix Table E.8
where the maximum, minimum, and average con-
centrations of tritium, strontium-89 and
strontium-90 are shown for each sampling lo-
cation. As shown in Table 4, the average
concentrations of tritium and strontium-90
for the whole network are consistent with
the network averages for previous years. The
results obtained from the standby network are
listed in Table E.9. Other than naturally
occurring potassium-40, radionuclides were
not detected by gamma spectrometry in either
the MSN or SMSN samples.
The tritium and strontium-90 concentra-
tions for the whole milk network were plotted
versus probits. The tendency of the data to
fit one straight Hne Indicates that the data
represent a single source, which appears to
be atmospheric deposition. These results are
consistent with the results obtained for the
Pasteurized Milk Network, operated by the
Eastern Environmental Radiation Facility in
Montogmery, Alabama, shown in Figure 12. The
consistently higher results from New Orleans
reflect the higher rainfall in that area.
.0
ra
BIOMONITORING PROGRAM
The pathways for transport of radionu-
clides to man include air, water, and food.
Monitoring of air, water, and milk are dis-
cussed above. Meat from local animals Is a
food component that may be a potential route
of exposure to off-site residents.
Methods
Samples of muscle, lung, liver, kidney,
blood, and bone are collected periodically
from cattle purchased from commercial herds
TABLE 4. NETWORK ANNUAL AVERAGE
CONCENTRATIONS OF TRITIUM AND
STRONTIUM-90 IN MILK, 1975-1987
Year
Average Concentrations - pd/L
H-3 Sr-90
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<400
<3
<2
<2
1.2
<3
<2
1.9
1.2
0.8
0.5
0.7
0.6
0.5
A New Orleans
Salt Lake City
Las Vegas
E
3 O
1960 19G5 1970 1975 1980 1985
Figure 12. Strontium-90 concentration in Pasteurized Milk Network samples.
22
-------
ro
CO
IQ
c
CO
fD
O
O
3
n>
o
-s
O)
0>
o
oo
-------
that graze areas northeast of the NTS. The
soft tissues are analyzed for gamma-emitters.
Bone and liver are analyzed for strontium and
Plutonium and blood/urine or soft tissue is
analyzed for tritium. Each November and De-
cember, bone and kidney samples from desert
bighorn sheep collected throughout southern
Nevada (see Figure 13) are donated by li-
censed hunters and are analyzed. These kinds
of samples have been collected and analyzed
for up to 30 years to determine long-term
trends. During 1987, five NTS mule deer were
collected and sampled in the same manner as
the cattle.
Results
Analytical data from bones and kidneys
collected from desert bighorn sheep during
the late Fall of 1986 are presented in Table
5. Tritium was not detected in any of the
kidneys. Other than the naturally occurring
potassium-40 the only gamma-emitting radionu-
clide detected was cesium-137 (30 pCi/kg) in
the kidneys of two of the sheep. Strontium-
90 levels in the bones (average 2.0 pCi/g
ash,) are consistent with those reported in
recent years (Figure 14).
Counting errors exceeded the reported concen-
trations of plutonium-238 in all samples of
bone ash. Plutonium-239 concentrations in
the ash ranged from -0.8 to 18 fCi/g. Only
the 18 fCi/g value exceeded the MDC.
Eight beef cattle were sampled during
1987; four from the Sharp Brothers Ranch of
Nyala collected in May and four from the
Steve Medlin Ranch of Alamo collected in
October. Tritium was not detected in any of
the blood samples. A muscle sample from one
of the Sharp cattle contained 30±10 pCi of
Cesium-137 per kilogram. Only naturally oc-
curring gamma-emitters (potassium-40 and
beryllium-7) were found in other cattle tis-
sue samples. Strontium-90 in bone ash sam-
ples from the Sharp cattle averaged 0.6 pCi
per gram of ash. None of the bone or liver
samples contained concentrations of pluton-
ium-238 that exceeded the counting error
Plutonium-239 concentrations in the bone ash
ranged from 0.0 to 4.2 fCi per gram of ash
with a median of 1.9 fCi/g ash and in the
liver ash ranged from 6.2 to 13 fCi per gram
of ash with a median of 9.4 fCi/g ash
Radiochemical analyses of tissues from the
Medlin cattle were not completed at the time
of this report.
Bighorn sheep
Deer
EH Cattle
Numbers at top of columns indicate
the number of bone samples in each
category. Numbers prior to 1964
are unknown
56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 87
Year (1956 - 1987) 5/88
Figure 14. Average strontium-90 concentration in animal bone.
24
-------
TABLE 5.
RA010NUCLIDE CONCENTRATIONS IN DESERT BIGHORN SHEEP SAMPLES - 1986
Bighorn Sheep
(Collected
Winter 1985)
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
Median
Range
Bone
90 Sr
(pC1/g Ash)
2.1 1 0.3
1.8 1 0.2
1.6 +.0.2
1.6 1 0.2
2.1 ±0.3
1.6 1 0.2
1.2 1 1.0
2.1 ±0.3
1.4 1 0.3
1.4 1 0.2
1.3 + 0.2
1.6 1 0.2
2.2 1 0.3
1.6 1 0.2
1.0 + 0.1
0.6 1 0.1
0.7 1 0.1
0.9 1 0.1
0.6 1 0.1
1.6
0.6 i 12
Bone
238 Pu
(fd/g Ash)
1.0 1 4.0*
0.6 1 4.0*
-1.3 1 3.2*
0.8 1 4.0*
0.6 1 4.0*
0 1 8.0*
-0.6 1 4.0*
-2.6 1 2.6*
-0.9 1 3.0*
-1.0 1 1.7*
-1.7 1 2.8*
0.5 1 3.0*
1.0 + 3.3*
-0.8 1 1.4*
-1.7 1 2.7*
2.5 1 3.6*
-0.7 1 3.0*
-0.5 +.3. 2*
1.913.2*
-0.5
-2.6 - 2.5
Bone
239 Pu
(fd/g Ash)
1.0 1 2.0*
0.81 1.9*
2.1 +2.1*
-0.8 1 1.3*
0.3 1 1.7*
18 1 5
1.2 1 1.9*
0.7 1 1.3*
2.6 1 2.0*
-0.6 1 0.9*
-0.2 1 1.1*
0.9 1 1.4*
-0.5 +. 1.0*
0.2 1 0.9*
1.3 + 1.5*
0.5 1 1.0*
0.511.3*
0.5 1 0.7*
-0.2 1 0.9*
0.5
-0.8 - 18
Kidney
K(g/kg)«
3H(pC1/L)t
i
190 1 900*
NS
-100 1 900* §
-70 1 900* §
-200 1 900* §
-90 1 900* §
30 + 15
230 1 900*
190 1 900* §
110 1 900* §
30 + 20
550 1 900*
380 + 900* §
NS
-240 1 900* §
90 1 900* §
360 1 940* §
140 1 940*
-400 1 940* §
140 1 940* §
260 1 940* §
30
110
30 - 30
-400 - 550
* Wet weight
.
«.
NS Not sampled
§ Sarana spectrum negligible
25
-------
During 1987, wildlife that drank from the
waters draining from the tunnel complexes in
area 12 of the Nevada Test Site were sampled
on a limited basis. Animals sampled included
five deer, two chukar and one horse.
Analytical data from the five deer are
presented in Table 6. All of the deer except
number 3 were collected in the vicinity of
the tunnels and the fact that the tritium
levels in the four animals ranged from .006
to 41 uCi/L (The highest level was in deer
number 4) indicate that they had used the
tunnel waters as a water source. Tissues
from deer number 3 and its fetus (collected
in Echo Peak area of Area 19) did not contain
detectable levels of tritium or gamma-emit-
ters other than naturally occurring potasium-
40. A wide variety of gamma-emitting radio-
nuclides were found in the rumen contents of
deer number 4 (collected while drinking at
the T-tunnel ponds). Detectable levels of
cesium-137 were also found in the tissues of
deer number 4.
The contract laboratory had not completed
radiochemical analyses of tissue from deer 4
and 5 in time for this report. Strontium-90
values in the bone ash of the first three
animals ranged from 0.5 to 0.7 pCi per gram.
None of the tissues contained concentrations
of plutonium-238 that exceeded the counting
error. None of the bone ash samples con-
tained plutonium-239 concentrations that
exceeded the counting errors. Concentrations
of plutonium-239 in soft tissues (see Table 6)
ranged from 2.8 fCi/g ash in deer number 1
muscle to 26 fCi/g ash in deer number 3
muscle.
The composited internal organs and muscle
from the two chukars collected at the T-tun-
nel ponds (see Table 7) contained a wide
variety of gamma-emitting radionuclides.
Muscle from a horse in Area 17 did not con-
tain detectable concentrations of gamma-
emitting radionuclides other than potassium-
40. Tritium concentrations did not exceed
the counting error. Radiochemical analyses
are still in process.
The tritium and cesium-137 levels found in
tissues from wildlife collected in the tunnel
areas indicate that the drainage waters are a
potential source of exposure to the off-site
population which may consume meat from mule
deer or migratory fowl. The potential exists
that deer may drink from the drainage water
as long as the area is unfenced. In the un-
likely event that a certain mule deer had
been collected by a hunter rather than EPA
personnel, that hunter could have received a
dose equivalent of 29 mrem (0.29 mSV) if he
ate all the meat from the deer.
EXTERNAL EXPOSURE MONITORING
Contributors to "normal background" radia-
tion exposure include medical and dental
radiation, naturally occurring radioactivity
in soil and building materials, cosmic radia-
tion and radioactive material naturally oc-
curring in our bodies. Many studies indicate
that the total background radiation exposure
from all sources in the United States ranges
from approximately 150 to 300 millirem (mrem)
or more per year.
THERMOLUMINESCENT DOSIMETRY NETWORK
The primary method of measuring external
radiation exposures is the thermoluminescent
dosimeter (TLD). Prior to 1987, a TLD system
manufactured by Harshaw was used. In 1987
this system was replaced with a TLD dosimetry
system developed by Matsushita Electronics
(Panasonic). The current system provides
much greater sensitivity and precision than
was possible using previous TLD systems or
film. This system has an added advantage of
tissue-equivalence, which facilitates cor-
relation of measured exposures with the ab-
sorbed biological dose equivalent an individ-
ual would have received were he continually
present at the monitoring locations.
Network Design
The TLD network is designed to measure
environmental radiation exposures at a loca-
tion rather than exposures to a specific in-
dividual. This method is generally preferred
because of the multiple uncontrollable vari-
ables associated with personnel monitoring
Measuring environmental radiation exposures
in fixed locations provides a reproducible
index which can then be correlated to the
maximum exposure an individual would have
received were he continually present at that
location. In addition to the fixed loca-
tions, several individuals residing within
and outside estimated fallout zones from past
nuclear tests at the NTS have been monitored.
These individuals are monitored in part to
confirm the validity of correlations between
fixed-site environmental radiation measure-
ments and projected exposures to individuals.
A network of environmental stations and
monitored personnel has been established in
locations encircling the NTS. Monitoring
locations are somewhat concentrated in areas
corresponding to estimated fallout zones
26
-------
TABLE 6.
RADIONUCLIDE CONCENTRATION IN TISSUES FROM MULE DEER COLLECTED ON THE NEVADA TEST SITE - 1987
124-Sb
Tissue (pCI/g)
Thyroid
Kidney
Liver
Lung
Muscle
Blood
Rumen
Contents
Bone
Muscle
Bone
Thyroid
Kidney
Liver
Lung
Muscle
Blood
Rumen
Contents
Bone
Thyroid
Kidney
Muscle
Liver
Lung
Rumen
Contents
Blood
Bone
Thyroid
Kidney
Muscle
Liver
Lung
Rumen
Contents
Blood
Bone
Gamma
ND
ND
ND
ND
NA
ND
NA
Gamma
NA
ND
ND
ND
ND
NO
NA
ND
NA
ND
ND
ND
ND
ND
0.87*0
NA
NA
Gamma
ND
ND
ND
ND
ND
NA
NA
125-Sb
(pC1/g)
.^ ^^ ^-^
Spectrum
ND
ND
ND
ND
NA
ND
NA
103-Ru
(pCI/g)
Mule [
Negligible
ND
ND
ND
ND
NA
ND
NA
nuie
Spectrum Negligible
NA NA
ND
ND
ND
ND
ND
NA
ND
NA
ND
ND
ND
ND
ND
.1 1.5*0.
NA
NA
Spectrum
ND
ND
ND
ND
ND
NA
NA
nuie
ND
ND
ND
ND
NO
NA
ND
NA
Mule
ND
ND
ND
ND
ND
2 0.7±0.4
NA
NA
Mull
Negligible
ND
ND
ND
ND
ND
NA
NA
137-Cs 106-Ru
(pC1/g) (pC1/g)
)eer No. 1 Collected (
ND ND
ND ND
ND ND
ND NO
NA NA 0
ND ND
NA NA
Deer No. 2 Road Kill
0
NA NA
Deer No. 3 Collected
ND ND
ND ND
ND ND
ND NO
ND ND
NA NA
ND ND
NA NA
Deer No. 4 Collected
ND ND
0.27±0.04 ND
0.0910.02 NO
0.09±0.02 NO
0.12*0.03 NO
0.83±0.04 50±0.1
NA NA
NA NA
; Deer No. 5 Collectei
ND ND
ND ND
ND ND
ND ND
ND ND
NA NA
NA NA
H3 239 Pu
(uCI/L) fC1/g/ash
31/21/87
NA
NA
NA
NA
.006510.0007
NA
ND
02/05/87
.0069±0.0005
NA
05/21/87
NA
NA
NA
NA
NA
ND
NA
NA
07/28/87-
NA
NA
NA
NA
NA
NA
41.4*0.08
NA
1 11/02/87 --
NA
NA
NA
NA
NA
0.23±0.002
NA
NA
4.212.8
17±17
2.8*2.1
NA
29*4
ND
26*7
ND
NA
NA
ND
14*5
4.4*3.1
NA
150*40
ND
NA
NA
IA
IA
IA
IA
NA
IA
NA
IA
IA
IA
IA
NA
IA
238 Pu
fd/g/ash
NA
ND
ND
ND
NA
7.8*4.4
ND
ND
ND
NA
NA
ND
ND
ND
NA
240*100
ND
NA
NA
IA
IA
IA
IA
NA
IA
NA
IA
IA
IA
IA
NA
IA
90 Sr
pd/g/ash
NA
NA
0.7*0.1
NA
0.5*0.1
NA
NA
NA
NA
NA
NA
NA
0.7*0.1
NA
NA
NA
NA
NA
NA
NA
IA
NA
NA
NA
NA
NA
NA
IA
ND
Not Detected; NA » Not Analyzed; IA - In Analysis
27
-------
TABLE 7. RADIONUCLIDE CONCENTRATIONS IN
TISSUES COLLECTED FROM NTS CHUKARS
Radionuclide
Co-60 (pCi/Kg)
Ru-106 (pCi/Kg)
Sb-125 (pCi/Kg)
Cs-137 (pCi/Kg)
Internal Organs
170±50
42,900±940
16,000±240
460±11
Muscle
500*250
140±40
(Figure 15). This arrangement permits both
an estimate of average background exposures
UTS "10" °f any
The Panasonic TLD monitoring system uti-
lizes two distinct types of dosimeters, one
for personnel, the other for environmental
(i.e. stations) monitoring.
Monitoring of EMSL and off-site personnel
is accomplished with the Panasonic UD-802
dosimeter. This device contains two elements
of Li2B407:Cu and two of CaS04:Tm phosphors
Scale in Mile
Figure 15. Locations monitored with TLD's.
28
-------
TABLE 8. ANNUAL OFF-SITE PERSONNEL DOSE 1987 TLO RESULTS
NV
. NV
NV
Background
Resident Station
Number Location
2 Callente, NV
3 Blue Jay, NV
6 Indian Springs, NV
7 Goldfleld, NV
8 Twin Springs Ranch, NV
9 Blue Eagle Ranch, NV
10 Complex 1, NV
11 Complex 1, NV
13 Koyen's Ranch,
14 Medlln's Ranch
15 Medlln's Ranch
18 Nyala, NV
19 Goldfleld, NV
21 Beatty, NV
22 Alamo, NV
25 Corn Creek, NV
29 Stone Cabin Ranch, NV
33 Lathrop Wells, NV
34 Furnace Creek, CA
36 Pahrump, NV
37 Indian Springs, NV
38 Beatty, NV
40 Goldfleld, NV
42 Tonopah, NV
44 Cedar City, UT
45 St. George, Ut
47 Ely. NV
49 Las Vegas (UNLV), NV
52 Salt Lake City, UT
.Hone of the reported exposures apparent
nlflcant Increase above background.
Net
Exposure* Resident
(wrem) Number
Background
Station
Location
Net
Exposure*
(mrem)
7.9
0.0
6.4
0.0
0.0
2.5
0.0
0.0
3.6
0.0
0.0
2.5
0.0
3.4
3.1
0.0
0.0
0.0
17.6
4.5
6.8
9.1
0.0
0.0
5.1
4.9
0.0
16.7
8.4
54
55
56
57
60
223
232
233
248
249
264
280
292
293
295
297
299
300
301
302
303
304
305
307
326
327
329
331
332
Rachel. NV
Rachel, NV
Corn Creek, NV
Overton, NV
Shoshone, CA
Corn Creek, NV
H1ko, NV
Ely, NV
Penoyer Farms, NV
Austin, NV
Rachel, NV
Alamo, NV
Death Valley Junction, CA
Ploche, NV
Currant, NV
Las Vegas (USDI), NV
Round Mountain, NV
Koyen's Ranch, NV
Crystal, NV
Gabbs, NV
Tonopah, NV
Death Valley Junction, CA
Gabbs, NV
Mlna, NV
Las Vegas (USDI), NV
Tonopah, NV
Austin, NV
Death Valley Junction, CA
Lathrop Hells, NV
2.3
0.0
8.0
8.2
0.0
0.0
8.9
3.3
0.0
0.0
2.2
10.0
11.1
0.0
0.0
0.0
0.0
0.0
3.0
0.0
0.0
0.0
6
0.0
0.0
0.0
0.0
0.0
0.0
1
ly greater than zero represent a
The four elements are behind 14, 300, 300,
and 1000 mg/cm2 filtration, respectively.
Three of the filters are plastic and one is
plastic and lead. This filter arrangement
and combination of very thin phosphors facil-
itates characterization of radiation incident
to the dosimeter by energy and type. in
addition, because Li2B407:Cu is tissue equiv-
alent, a properly calibrated UD-802 dosimeter
makes possible a direct correlation between
an individual's radiation exposure and the
absorbed dose equivalent.
Monitoring of EMSL and off-site stations
Is accomplished with the Panasonic UD-814
dosimeter. This device contains one element
of Li28407:Cu and three replicate CaS04:Tm
phosphors. One element has a filter of 14
mg/cm2 of plastic. The other three are fil-
tered by 1000 mg/cm2 of plastic and lead.
The UD-814 dosimeter is designed primarily to
monitor ambient radiation exposure levels at
a fixed station. Therefore, three replicate
CaSO/i:Tm phosphors are used to provide excel-
lent statistics and extended response range.
Limited energy discrimination and radiation
type characterization is possible with this
dosimeter. Element number 1 does make pos-
sible some discrimination of beta or low
enerqy photon radiation in the presence of
high energy photon (gamma) fields. Unlike
the UD-802 personnel dosimeter, exposures
measured with the UD-814 are normally not
converted into an absorbed dose equTvalent.
RESULTS OF TLD MONITORING
Off-Site Personnel
During 1987 a total of 58 individuals liv-
ing 1n areas surrounding the Nevada Test Site
were provided with personnel TLD dosimeters.
As noted, these dosimeters serve both to
monitor the absorbed dose equivalent received
29
-------
by a specific individual in the course of
o^f1?t1ay*aCt-V1'tie,S 3nd t0 confl'rm that ^
off-site station (environmental) TLDs are
providing a valid estimate of the radiation
exposure an individual would receive if i0°-
specified
Annual doses decreased from 1971 to 1975 with
£
r;
t« j"f~S1*e*Pers0nnel exP°sures are corrected
to account for known natural background radi-
ation levels at the off-site environmental
monitoring station closest to each individ-
Va].s.res,1 fence. As shown in Table 8 each
individual's net annual exposure above back-
ground is calculated. Following prior con-
vention, energy and type of radiation is not
reported. All exposures are in effect ore-
sumed to be due to gamma and henc ?«£?-
cally equivalent to absorbed dose.
The mean net dose to monitored off-site
R^rH1 f?P 1987 W" 3'6 mniirem <«*«.)
Reported values ranged from zero to 16 7
mrem All reported net exposures were with-
iJtrih,,^96*^ average MPosures received
attributable to natural background radiation.
Off-Site Stations
- u stations, al-
this average is also affected by the
a1titudes
ai * i« 9reat range in tne re-
-. «»i 10 ibb mrem, an average for thp
who e area monitored may be inappropriate for
estimating individual exposure This would
be particularly true if the exposure of a
particular resident were desired Sinr*
environmental radiation exposure can varv
markedly with both altitude and ?he natural
TABLE 9. DOSIMETRY NETWORK SUMMARY FOR THE
YEARS 1971 - 1987
^ Environmental Radiation Dose Rate (mrem/y)
Year Maximum Minimum Average
rf-f 13,2 Off-Slte stations were mon-
during all or part of 1987 The
environmental radiation levels at these sta-
tions was measured using Panasonic UD-814
dosimeters. The following table summarizes
the results obtained from these TLDs.
The annual reported adjusted dose equiva-
lent (mrem/year) was calculated by multiply-
incrthe average daily rate for each station
. *A 1eview of the measurement periods
fS*ti ?L CW statl'ons were monitored for
exactly 365 days. When an annual exposure is
calculated from measured daily rates correc-
ted for actual exposure time, there is excel-
lent correlation with the nominal 365-day
exposure rate reported in Table E.10 of
Appendix E.
Comparison with Direct
Exposure Measurements
When calculated TLD exposures are compared
with results obtained from the Pressurized
lomzation Chamber network a 21% difference
Is found. This difference is attributed pri-
marily to the energy response of the two
systems. PIC's have greater sensitivity to
lower energy gamma radiation; therefore,
PIC s normally record higher apparent ex-
posure rates than do TLD's.
Table 9 shows that the average annual dose
rate for the Dosimetry Network is consistent
with the Network average established in 1975
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
250
200
180
160
140
140
170
150
140
140
142
139
140
133
142
135
166
102
84
80
62
51
51
60
50
49
51
40
42
42
35
40
40
41
160
144
123
114
Q4
J "
Q4
.7*+
101
95
92
90
90
00
oo
07
o /
85
DC.
\J J
85
89
110
Station Altitude
4 6,000 ft
75 76 77
79 80 81 82
Calendar Year 19--
T
83
T
84
85
86
87
Figure 16. Average annual
TLD exposure as a function of station altitude.
30
-------
radioactivity in the soil, and since the
altitude of the TLD station location is rela
tively easy to obtain, the measured dose
rates for 1975 to 1987 were plotted as a
function of altitude. As most of Nevada lies
between 2,000 and 6,000 feet above mean _sea
level, this range was split into two sections
for plotting purposes. The results, shown in
Figure 16, indicate that the average exposure
at altitudes between 4,000 and 6,000 feet is
about 17 mrem/yr (0.17 mSv/yr) higher than
that at altitudes between 2,000 and 4,000
feet, although both curves follow the same
trend as the overall averages listed in Table
7 Thus, if an individual does not live near
a'monitored location, an estimate of exposure
could be based on the altitude of his resi-
dence rather than on the average for the
whole area monitored.
PRESSURIZED ION CHAMBER (PIC) NETWORK
These gamma-ray ratemeters are located at
the 15 Community Monitoring Stations identi-
fied on Figure 2 plus stations at Caliente
Complex I, Furnace Creek, Lathrop Wells, Mam-
moth Lake, Medlin's Ranch, Nyala Pioche,
Stone Cabin Ranch, Tikaboo Valley, Twin
Springs, and Uhaldes1 Ranch. The output of
each PIC is displayed on both a paper tape
and a digital readout, so the station manager
can observe the response. The data is also
stored on cassette tapes, which are read into
a computer at EMSL-LV each week. The com-
puter output consists of tables containing
hourly, daily, and weekly summaries of the
maximum, minimum, average, and standard devi-
ation of the gamma exposure rate.
The data for 1987 are displayed in Table
10 as the average pR/hr and annual mrem from
each station. When these data are compared
to th TLD results for the same 23 stations
H is found that the PIC exposure is about
21% higher than the TLD exposure. This is
rtJrlbSS primarily to the differences in
energy response of the two systems. Pic s
live greater sensitivity to lower energy
gamma fadlatlon; therefore, PIC's normally
?ecord higher apparent exposure rates than do
TLD's.
TABLE 10. PRESSURIZED ION CHAMBER READINGS - 1987
Station Location
. ~~
Alamo, NV
Austin, NV
Beatty, NV
Caliente, NV
Cedar City, UT
Complex 1, NV
Ely, NV
Furnace Creek, CA
Goldfield, NV
Indian Springs, NV
Las Vegas, NV (UNLV)
Lathrop Wells, NV
Mammoth Lake, CA
Medlins Ranch, NV
Nyala, NV
Overton, NV
Pahrump, NV
Pioche, NV
Rachel, NV
Salt Lake City, UT
Shoshone, CA
St. George, UT
Stone Cabin Ranch, NV
Tonopah, NV
Twin Sprgs Ranch, NV
Uhaldes Ranch, NV
No. of
Hourly
Values
_
7914
6804
7275
1126
8730
7586
8117
6487
8055
7788
6920
7970
3964
7572
5542
7787
6876
7975
6375
6901
6783
8064
5990
7802
6771
6256
1 '-
1
Max
_....
18.1
26.3
20.7
19.8
21.6
26.5
17.5
14.3
24.1
15.7
q 7
.7 /
18.5
22.0
24.1
18.7
16.3
16.4
18.8
23.4
19.9
23.0
18.8
21.3
21.9
20.7
22.4
__
Exposure Rate,
Win
-
11.1
14.7
11.0
13.4
7.7
12.2
10.0
5.0
7.7
5.9
5.0
10.0
10.0
11.1
9.0
7.3
4.6
10.0
10.1
7.4
11.0
5.5
15.9
12.2
11.1
8.5
' '
MR/H*
Avg ± 1 Sd mrer
, . ~
13.2 ± 0.17 1
19.6 ± 0.89 1
17.0 ± 0.20 1
14.7 ± 0.25 1
10.7 ± 0.27
16.2 ± 0.30 1
12.5 ± 0.21 1
9.4 ± 1.41
16.1 ± 1.18 1
9.2 ± 0.15
6.4 ± 0.20
14.2 ± 0.13 1
17.7 ± 0.21 ]
16.0 ± 0.18
13.0 ± 0.29 :
9.4 ± 0.29
7.8 ± 0.17
12.9 ± 0.24 :
17.1 ± 0.25
10.1 ± 1.21
11.8 ± 0.29
9.0 ± 0.27
17.5 ± 0.43
17.2 ± 0.32
16.8 ± 0.33
17.3 ± 0.32
94
42
110
82
141
80
56
124
155
140
114
82
68
116
150
88
103
79
153
151
147
152
*The MAX and MIN values are obtained from the instantaneous readings.
31
-------
INTERNAL DOSIMETRY
Internal exposure was monitored in 230
individuals from the off-site areas around
rrt fad-a -T*St Slte' the EMSL'LV Laboratory,
EG&G facilities throughout the U.S. and mem-
bers of the general public concerned about
possible radiation exposure. No significant
gamma radiation was detected in whole body
counts although trace amounts of fission pro-
ducts, attributable to the Chernobyl-4 acci-
dent in the U.S.S.R., were found in individ-
uals returning from extended stays in Europe
No low energy gamma-emitting radionuclides
with energies ranging from 10 to 300 KeV were
detected in lung counts. Nearly all bioassy
determinations for tritium showed concentra-
tions in the range of background levels meas-
ured in water, and reflected only natural
exposure.
Internal Exposure Monitoring
Internal exposure is caused by ingested or
inhaled radionuclides that remain in the body
either temporarily or for longer times be-
cause of storage in tissues. At EMSL-LV two
methods are used to detect such body-burdens:
whole-body counting and urinalysis.
The whole-body counting facility has been
maintained at EMSL-LV since 1966 and is
equipped to determine the identity and quan-
tity of gamma-emitting radionuclides which
may have been inhaled or ingested. Routine
examination consists of a 2000 second count
in each of two shielded examination vaults,
in one vault a single intrinsic coaxial de-
tector positioned over an adjustable chair
allows detection of gamma radiation with en-
ergies ranging from 60 KeV to 2.5 MeV in
the whole body. The other vault contains an
adjustable chair with two detectors mounted
above the chest area, two intrinsic planar
detectors were used until the latter part of
the year when they were replaced by two
intrinsic semi-planar detectors.
Network Design
This activity consists of two portions,
an Off-Site Human Surveillance Program and a
Radiological Safety Program. The design for
the Off-Site Human Surveillance Program is to
measure radionuclide body-burdens in a repre-
sentative number of families who reside in
areas that were subjected to fallout during
the early years of nuclear weapons tests and
to act as a biological monitoring system for
present nuclear testing activities. A few
families who reside in areas not affected by
such fallout were also selected for compara-
tive study.
Methods
n<*rf. H,uman Surveil 1ance Program
mtiated in December 1970 to determine
tl'Ve nUClides in «>« of IK
in communities and ranches
surrounding the NTS. Biannual counting "
performed in the spring and fall. This pro-
years. When the Community Monitoring Station
Network was started in 1982, the families of
tne station managers were added to the pro-
gram. These families are counted in the
winter and summer of each year. The geo-
nS?r"V2"t1
-------
at this facility. He makes visits to a lim-
ited number of whole-body counting facilities
for intercalibration of low energy gamma
emitting radionuclides each year.
Results
During 1987, a total of 246 germanium, and
500 planar/semi-planar spectra were obtained
from 230 individuals, of whom 81 were par-
ticipants on the Off-Site Human Surveillance
Program. Also, 1665 spectra for calibrations
and background were generated. Cesium-137 is
generally the only fission product detected.
As a result of worldwide fallout following
the Chernobyl accident, trace amounts of
cesium-137, cesium-134, and cobalt-60 were
detected in a limited number of individuals,
mainly those contractor personnel flown in
from California or people stationed in
Europe. Several ranchers actively involved
in farming also showed a trace of these
rad onuclides. In general, the spectra were
representative of normal background for
pebpleand showed only naturally occurring
potassium-40. No transuramc nuclides were
\.\Pyramid Lake
Nevada
Austin
Round Mt.OOO
Ely
Salt Lake City
.c
CO
Currant Q Lund
O
Blue Jay O Q Blue Eagle Ranch
0 Nyala Eagle Valley
^ AJ O
Goldfield O Adaven
b
Tonopah^-j
Racrii
Beatt$>
Lathrop Wells
Elgin
O
(Alamo
BunkervilleO
ilndian
Springs
Cedar City
(St. George
Arizona
Shoshone
O Offsite Family
Community Monitoring Sta Family
^Overton
Lake Mead
Figure 17. Location of families in the Off-Site Human Surveillance Program.
33
-------
detected in any lung counting data. The
subject from AERE, Harwell, England had a
fntake^n ,Q°irad-'Um"226 from an a«idental
h£?5 « I' intravenously administered
Jn£ ?« and- stronti-85, plus cesium-134
and -137 received from travel in Yugoslavia
prior to coming to the U.S. Our result?
showed good correlation with the results from
other whole-body counting facilities and we
were able to detect radionuclide concentra-
tion in some areas of the body with better
sensitivity than the other facilities. The
subject gave us the opportunity to investi-
gate levels in bones of the skull, wrists
ankles, and pelvis as well as in the soft
tissue of the liver and lungs. The radionu-
clides were found to have been deposited
assymetrically in bone. It is not clear why
this occurred but it is possible that because
?i«-a?*' uhe is fn his eighties, the blood
flow might have been less in some areas.
ultrasound studies were not able to explain
these anomalies. If the pattern of deposi-
tion is not unique then the positioning of
detectors is very critical and the ability to
position detectors reproducibly at various
altitudes is essential. The present state-
of-the-art detectors and analyzer systems
allow reliable measurements and results at
which we could only conjecture a few years
390 .
Whole-body and lung counts were performed
on subjects from the Southern California
Edison Nuclear Power Plant at San Onofre
The new semi-planar detectors were installed
for these counts and calibrated with tissue
equivalent lung calibration sets impregnated
with various uranium enrichments. These lung
sets were obtained from Lawrence Livermore
National Laboratory and were used in our
tissue equivalent lung phantom. The use of
these detectors, in this instance tested
their use in the Off-Site Human Surveil-
lance Program.
Bioassay results for the Off-Site Human
Surveillance Program showed that the concen-
tration of tritium in urine samples from the
off-site residents varied from 0 to 1840
pCi/L (0 to 68 Bq/L) with an average value of
184 pCi/L (6.8 Bq/L). Nearly all the concen-
trations measured were in the range of back-
ground levels measured in water and reflect
only natural exposure. The source for the
high value (a Las Vegas, Nevada resident) is
unknown but is not attributed to NTS activi-
ties. The tritium concentrations in urine
samples from EPA employees had a range of 0
to 1190 pCi/L (0-44 Bq/L). The highest trit-
ium concentration was found in urine from an
employee at the San Onofre Nuclear Power
Plant but it was below the maximum permis-
sible body burden.
34
-------
SECTION 6
PUBLIC INFORMATION AND COMMUNITY ASSISTANCE PROGRAMS
In addition to its .any -itoring and data
sive program designed to provide .informat1n°"1^ieYn the environs of the NTS. During
lions and local government agencies in commun ;ties in Xwn hall" meetings; a high school
activities included: participation i" Public he^S?ing of emergency response; continuec ^ sup-
> «* otion,.
allegedly due to radiation originating from
NTS activities. A veterinarian, qualified by
education and experience in the field of ra-
diobiology, investigates problems with domes-
tic animals and wildlife to determine whether
or not radiation exposure may be involved.
Several animal investigations were con-
ducted during 1987, by the NRD veterinarian,
in response to requests from citizens. These
included evaluations of: a skin condition,
symptomatic of a mange mite infestation, ob-
served on a number of dogs at a breeding
kennel; a growth on the eyelid of a year ing
bull- and a necrotic mass, tentatively diag-
nosed as a melanoma or squamous cell carcin-
oma on a horse. In each case, the owners
were advised to take their animals to a prac-
ticing veterinarian for confirmatory diagno-
sis or additional treatment. None of the
conditions observed was related to nuclear
radiation.
NTS Tours
To complement the "town-hall" meetings and
to familiarize Nevada citizens with both the
DOE testing program at the NTS and the Envi-
ronmental Monitoring Program conducted by the
EPA, tours are arranged for business and
community leaders from towns in the environs
of the NTS, as well as for government employ-
ees and the news media. Between January and
October 1987, the following tours were spon-
sored by the EPA:
Public Hearings
A Congressional Oversight Hearing on the
Health Effects of Underground Nuclear Testing
was held by the House Subcommittee on Energy
and Environment in Salt Lake City, Utah on
September 25, 1987. Testimony was given by
two NRD staff members. They described the
criteria that must be met prior to testing a
nuclear device as well as the extensive mon-
itorinq, surveillance, and analytical activ-
ities carried out by the EMSL-LV to ensure
that releases of radioactivity from the NTS
will be detected and reported.
Town Hall Meetings
The "town hall" meetings, which have been
conducted since 1982, were continued in 1987.
These meetings provide an ?PP°rrtunity r
attendees to meet directly with EPA and DOE
personnel, ask questions, and express their
concerns concerning nuclear testing. During
a typical meeting, the procedures used and
the safeguards taken during any test are
described, the monitoring and surveillance
networks are explained, and the proposed High
Level Waste Repository at Yucca Mountain dis-
cussed. During 1987, meetings were held in
the 10 communities listed below. Attendance
varied from 8 to 100 with an average of 30
participants per meeting.
Town Hall Meetings
Bridgeport, California
Hawthorne, Nevada
Leeds, Utah
Minersville, Utah
Round Mountain, Nevada
Austin, Nevada
Goldfield, Nevada
Logandale, Nevada
Ivins, Utah
Bloomington, Utah
Animal Investigations
One of the public service functions of the
EMSL-LV is to investigate claims of injury
March 18
March 19
April 22
April 23
May 14
July 13
July 16
September 16
November 18
November 19
Citizens of Beatty
National Park Service
EPA Newcomers
EPA Newcomers
Ely Residents
Alamo, Rachel,
and Las Vegas
Goldfield Residents
Utah News Media
EPA Employees
and Family Members
January 14
January 29
February 12-13
February 25-26
May 19-20
May 27-28
August 31-September 1
September 17-18
October 29
35
-------
High School Science
Program
The High School Radiation Science Program
was conceived by the NRD staff In 1986 S
provide a service to schools in communities
in the environs of the NTS. The aim of this
program being to supplement the high school
program with an activity involving the inter-
action between students, teachers and NRD
personnel. Following the reactor accident at
Chernobyl, USSR in April 1986, the need for
such a program became obvious as indicated bv
recurring indications of misunderstanding of
ionizing radiation by both the media and the
public. In response, the NRD staff put to-
gether a program designed to help students
better understand radiation and radioactivity
and to provide them with some of the basic
knowledge required to make sound decisions
concerning the many societal issues arising
USe an °f radl'oactive
th.on October 1986> and continuing
through 1987, an NRD staff member began
teaching radiation concepts to students in
Jl^ *? ho°l. chemistry, biology, physics, and
f~ * A c" classes- e instructor
spends 4 or 5 days in each school. During
this time he presents lecture-demonstrations
and conducts several laboratory exercises,
designed to introduce students to background
radiation measurement techniques. During
1987, the program was presented in the
schools listed below:
Beatty High School,
Beatty, NV
Tonopah High School,
Tonopah, NV
Death Valley High School,
Shoshone, CA
Indian Springs High School,
Indian Springs, NV
White Pine High School,
Ely, NV
January 20-23
February 20-23
April 20-24
November 2-6
December 7-11
Other Activities
Personnel from the EMSL-LV addressed other
groups during 1987, as listed below:
March 11
March 19
A talk about radiation was given
to students at the Twin Springs
Ranch Elementary School.
A lecture, concerning the Nu-
clear Waste Problem and the
Nuclear Waste Policy Act, was
presented to an American Govern-
ment class at Bonanza High
School.
September 1 Deer migration study slides were
shown at the Soil Conservation
Office in Caliente, NV.
December 9 A slide presentation describing
the deer migration studies was
presented at the meeting of the
Caliente Sportsmen's Club.
Emergency Response
°f Cont1nued Population growth
,f comw^^> there is an in-
natnn with K l°J assistance fn and coordi-
nation with both state and local agencies in
Jhat^mav0 ^T* the protectlU ac"o
tell aariLinrded1lf an "Aground nuclear
rel-eased radioactive contam-
100, *u envir°ent. Therefore, dur-
n, K\ there has been a continuing dia-
logue between the EMSL-LV staff and the
State of Nevada's Division of Emergency Man-
agement as well as with the local aVcounty
A » r!lSi*eSP*°Kns1ble f°r emer9e"cy Planning.
As a result, the radiological appendicies to
the emergency response plans of Clark Es-
1101"/ Nyvnd White Pl'ne cou>nti«
* Inyo County' California were
into the DOE Master Plan for emer-
gency response.
In a continuing effort to provide and im-
prove personal dosimetry to citizens Hv no
in communities in the environs of the NevadI
Test Site, plans were developed to replace
S ' '
tr
dosimeters. The necessary TLDs were ordered
and are currently being calibrated prior to
their distribution to communities in Califor-
nia, Nevada, and Utah. The dosimeters will
nni]tf!iied by +°m$y °r state Personnel in the
unlikely event of a significant release of
radioactive materials from the NTS.
COMMUNITY MONITORING STATIONS
In 1981 DOE and EPA established a network
L .4.Cornmunity Monitoring Stations in the
off-site areas in order to increase public
awareness about radiation monitoring activ-
ities. The DOE, through an interagencv
agreement with EPA, sponsors the program and
tS Wlth Desert Research Institute
f°,^!e the stations> and the Univer-
of Utah to train station managers. Each
station is operated by a local resident, in
?nSraHaS?S ? "n^"" teacher, who is trained
in radiological surveillance methods by the
University of Utah. These stations continued
^o,e f intamed by NRD personnel during
thf PMC, I"S " nwnerre c°11ected and analyzed at
the EMSL-LV. DRI provides data interpreta-
tion to the communities involved and pays the
station operators for their services.
36
-------
Each station contains one of the samplers
for the ASM, NGTSN and Dosimetry networks
discussed earlier, plus a pressurized ion
chamber (PIC) and recorder for ^mediate
readout of external gamma exposure, and _a
recording barograph. All of.the equipment is
mounted on a stand at a prominent location in
each community so the residents are aware of
the surveillance and, if interested, can have
ready access to the data. The data from
thlse stations are included in the tables in
Appendix E with the other data from the ap-
propriate networks. Table 10 contains a sum-
mary of the PIC data.
Experimental telemetry equipment was in-
stalled at three monitoring stations during
1987 in an attempt to expedite environmental
measurement data acquisition and '"prove en-
vironmental monitoring activities. With tnis
electronic equipment gamma exposure measure-
mpnts acauired by the pressurized ion cnam-
Ss'can Transmittedi via satellite direc-
tly to the EMSL-LV and to the NTS. Since
tests with the experimental equipment proved
successful, plans call for the installation
of satellite telemetry equipment at all of
the Community Monitoring Stations plus9
other locations in Nevada and Utah by mid-
1988.
37
-------
SECTION 7
DOSE ASSESSMENT
Estimated Dose from NTS Activities
assteinTae ~«» «' "dlo-
origm was detectable off site by the vario,,V « -. -n° S19nif'cant radioactivity of recent NTS
population living around the NT/ iS be expected""1 S nret*?rks;lln.0 '^IflcantVpisIe £ !E
" * t
During calendar year 1987 there were four
sources for possible radiation exposure to
the population of Nevada, all of which
duced negligible exposures. The°
* re.lea1s". of ^ioactivity from
NTS including that from drillback
and purging activities;
Radioactivity in migratory animals that
was accumulated during residence on the
World-wide distributions such as stron-
tium-90 in milk, krypton-85 in a7r
etc. ; and
h radtat*°n due to natural
sources such as cosmic radiation, natu-
ral radioactivity in soil, and beryf-
num-7 in air.
The estimated dose equivalent exposures
from these sources to people living near the
S
Estimated Dose from
Worldwide Fallout
From the monitoring networks described in
previous sections of this report, the follow-
°f ^dioactivi were
Tritium (.62 pCi/m3 of air [23 mBq/m3!)
Krypton-85 (25.5 pCi/m3 Of air
[0.9 Bq/m3])
Strontium-90 (1.8 pCi/L in milk
[67 mBq/L]}
Xenon-133 (1 pCi/m3 of air [37 mBq/m3])
Cesium-137 (30 PCi/kg beef muscle
[1.1 Bq/kg])
Plutonium-239 (110 fCi/kg beef liver
[4.1 fBq/kg])
The dose is estimated from these
Liver consumption is 0.5 Ib/week =
11.8 kg/yr,
Meat consumption 248 g/day, when
consumption is subtracted this is
1 i ver
78.7
th0T4,eTd0/e.5onversi'on Actors are based on
the ALT divided by 5000 to convert to bee
querels/mrem, then converted to mrem/pCi :
Hydrogen-3 (6.2 x 1Q-8 mrem/pCi)
Strontium-90 (1.8 x lp-4 mrem/pCi)
Cesium-137 (4.5 x 1Q-S mrem/pCi)
Plutonium-239 (9 x 10;4 mrem/pC }
Krypton-85 (1.5 x 10~3 mrem/yr per
Xenon-133 (6.2 x IQ'4 mrein//r
As an example calculation, the fol lowing is
the result for tritium: 9
0 62 pCi/m3 x 8400 m3/yr x 6.2 x
10 « mrem/pCi x 103 urem/mrem = 0.32 Mrem
Also:
78'7
4-5
Plutonium-239 (110 fCi/kg x 11 8 ka x
ID"3 pCi/fCi x 9 x 10§3 = 1.1 X?
These sum to an annual dose equivalent of
u.lo mrem.
Estimated Dose from
Radioactivity in NTS Deer
38
-------
The highest measured concentrations of
radionuclides in mule fleer tissues occurred
in deer collected on the NTS. These were.
Tissue Hi3 ^137 Pu^
LTPci/kg) i x io7 90 0.05
Muscle 7 n 1 n
(pCi/kg) 1 x 10? 90 0.113
Based on past data, in the unlikely event
that one such deer was collected by a hunter
in off-site areas. With 3 pounds of liver
and 100 pounds of meat and the radionuclide
concentrations listed above, the dose equiva-
lents could be:
Liver: 1.36 kg ([IxlO? x 6..2xlO-8]+[90 x
4.5xlO-5]+[0.5 x 9x10-4]) =0.85 mrem and for
muscle, a similar calculate yields 28.4
mrem. Thus, approximately 29 mrem would be
delivered to one individual consuming the
stated quantity of meat and assuming no
radioactivity was lost in food preparation.
Dose from Background
Radiation
In addition to external radiation exposure
due to cosmic rays and that due to the gamma
radiation from naturally occurring radionu-
clides in soil (potassium-40, uranium and
thorium daughters, etc.), there is a contri-
bution from beryl1ium-7 that is formed in the
atmosphere by cosmic ray interactions with
oxygen and nitrogen. The annual average Be-7
concentration measured by our air surveil-
lance network was 0.07 pCi/ir.3 Wlth a dose
conversion factor for inhalation of 2.6 x
10-7 mrem/pCi, this equates to 0.15 urem a
negligible quantity when compared with the
PIC measurements that vary from 56 to 172
mrem, depending on location.
Summary
For an individual with the highest expo-
sure to NTS effluent, that is someone living
at the Medlin's Ranch, the NTS exposure, plus
that due to world-wide fallout plus back-
ground would add to: 2 x 10'3 mrem + 0.16
mrem + 140 mrem =140.2 mrem (1.4 mSv). Both
the NTS and worldwide distributions contri-
bute a negligible amount of exposure compared
to background. If that same individual used
the NTS deer meat without sharing it with
someone else, the exposure would increase to
140.16 + 29 = 169 mrem (1.69 mSv).
39
-------
SECTION 8
REFERENCES
!!atl'onal Standards Institute,
, American National Standard
Performance Testing and Procedural Spec-
fi cations for Thermoluminescent Dosimetry
APP1 ications> ' " ANSI
Be73 Bernhardt, D. E., A. A. Moghissi and
J. A Cochran, 1973, Atmospheric Concen-
trations of Fission Product Noble Gases
PP. 4-19, m Noble Gases, CONF-730915.
B184 Black ,S. C. and D. D. Smith, 1984
Nevada Test Site Experimental Farm Sum-
Protection Agency, Environmental Monitor-
ing Systems Laboratory, Las Vegas, Nevada.
m
from
personal communication
county agents.
DOE85a U.S. Department of Energy 1985 A-
StatS *? D°DE °rder 5480-1A> R«««1on
Standards for Protection of the Public in
the Vicinity of DOE Facilities.
DOE85 U.S. Department of Energy, 1985, Envi-
ronmental Protection, Safety, and Health
Protection Information Reporting Require-
ments. Order DOE 5484.1. eMuire
DOE88 U.S. Department of Energy, 1988, per-
sonal communication from Health Physics
Division, DOE/NV, Las Vegas, NV.
'S»r Envi'ronmental Protection Agency,
1981, Environmental Radioactivity Labora-
?2 Intercomparison Studies Program
1978-1979." EPA-600/4-81-004. Environ-
mental Monitoring and Support Laboratory
Las Vegas, Nevada. (Available from U s'
Department of Commerce, NTIS, Springfield,
» A tclol * )
EPA86U.S Environmental Protection Agency,
1986, Off-Site Monitoring for the Mighty
Oak_ Nuclear Test." EPA 600/4-86-030
Environmental Monitoring Systems Labora-
*>ry,', ^s Vegas, Nevada. (Available from
the U.S. Environmental Protection Agency.)
ERDA77 U.S. Energy Research and Development
Administration, 1977, "Final Environmental
Impact Statement, Nye County, Nevada "
Nevada Operations Office, Las Veqas NV
Report ERDA-1551. (Available from ' U s'
Department of Commerce, NTIS, Springfield,'
VA ct ID 1 . }
Laboratory, Las Vegas, Nevada.
Gi85 Giles, _K. R. and J. Cooper, 1985, "Char-
acteristics and Migration Patterns of Mule
Deer on the Nevada Test Site," U.S Envi-
ronmental Protection Agency, Environmental
SA /J"L Systems ^oratory Report
EPA-60/4-85-030 (DOE/DP/00539-054) .
Ho75 Houghton J G., C M. Sakamoto, and R.
0 Gifford, 1975, "Nevada's Weather and
Climate. Special Publication 2. Nevada
Bureau of Mines and Geology, Mackay School
of Mines, University of Nevada, Reno,
Nevada, pp. 69-74.
ICRP75 International Commission in Radiolog-
ical Protection, 1975, Report of the Task
broup on Reference Man, Report ICRP-23.
ICRP77 International Commission in Radiolog-
th TrDDtention> 1977« ^commendations of
the ICRP, Report ICRP-26.
ICRP79 International Commission in Radiolog-
ical Protection, 1979, Radionuclide Sf-
rv!aSe+ 2 the Env1ronn«nt: Assessment of
Dose to Man, Report ICRP-29.
ICRP79 International Commission in Radiolog-
ical Protection, 1979, Limits for Intake
of Radionuclides by Workers, Report ICRP-
JO, 3 parts.
ntD'- ' - Siu' 1981' nvi>°r,-
mental Radioactivity Laboratory Intercom-
pan son Studies Program - FY 1981-82
EPA-600/4-81-004, U.S.9 EPA, Environmental
Nevada""1"9 ystems Laboratory, Las Vegas,
NPS80 National Park Service, 1980, personal
communication with Chief Ranger R Rainer
Death Valley National Monument, Death Val-
ley, California.
NCRP71 National Council on Radiation Protec-
tion and Measurements, 1971, Basic
Radiation Protection Criteria NCRP
Report No. 39.
NCRP75 National Council on Radiation Protec-
tion and Measurements, 1975, Natural
Background Radiation in the United States
NCRP Report No. 45.
40
-------
NV86 Nevada Department of Agriculture, 1986,
"Nevada Agricultural Statistics 1985.
Nevada Crop and Livestock Reporting Ser-
vice, Reno, Nevada.
Pi8? Patzer R G. and M. E. Kaye, 1982,
"Results'of a Human Surveillance Program
in the Off-Site Area Surrounding the
Nevada Test Site." Health Phys. 43:791-
801.
Ou68 Quiring, R. E., 1968, "Climatological
Data Nevada Test Site, Nuclear Rocket
SomeS Station (NRDS)." "LTM-ARL-7.
ESSA Research Laboratories, Las Vegas,
Nevada.
Sm81 Smith, D. D. and V. E. Andrews,1981.
Selected Radioisotopes in Animal Tissues.
90$r and 137Cs Measurements from 1956 to
1977 u s Environmental Protection
Agency Report EPA-600/3-81-027 {DOE/DP/
00539-040). Las Vegas, Nevada.
Sm84 Smith, D. D. and S. C. Black, 1984,
Animal Investigation Program for the
Nevada Test Site 1957-1981, U.S. Environ-
mental Protection Agency, Environmental
Monitoring Systems Laboratory Report EPA
600/6-84-020, Las Vegas, Nevada.
UT87 Utah Department of Agriculture, 1987,
"Utah Agricultural Statistics, 1987.
State of Utah Department of Agriculture,
Salt Lake City, Utah.
Wi75 Winograd, I. J. and W. Thordarson, 1975,
Hvdroqeologic and hydrochemical framework,
south-central Great Basin, Nevada-Califor-
nia, with special reference to the Nevada
Test Site, USGS Professional Paper 71^-t,
Denver, Colorado.
41
-------
-------
APPENDIX A
SITE DATA
SITE DESCRIPTION
A snmmarv of the uses of the NTS and its immediate environs is included
in Sections of this report. More detailed data and descriptive maps are
contained in this Appendix.
Location
The NTS is located in Nye County, Nevada, with it\.sou^ea^^CO;nnearreaab°^
i
ranges rising 1,800 to 2,300 m above MSL.
borne radioactivity could pass over public lands.
Climate
The climate of the NTS and surrounding area 1s variabl
support the growth of common food crops without ir
teri sties of climatic types for Nevada.
A-l
-------
TABLE A.I. CHARACTERISTICS OF CLIMATIC TYPES
(from Houghton et al. 1975)
IN NEVADA
Mean Temperature
°C
Climate Type Winter
Summer
Annual
Precipitation
.. cm . % Percent
(inches) Dominant of
Total* Snowfall Vegetation Area
Alpine
tundra
-18°
( 0°
to
to
-9°
15°)
4°
(40°
to
to
10°
50°)
38
(15
to
to
114
45)
Medium
to
heavy
Alpine
meadows
"Snenta, & l°0 £, & <° £, « to m Heavy
Pine-fir
forest
'SSsit.i jg: g & ,is: s £, $ g g, «--
X?etn* .ijrg^ ."igjj:, «*..» ^t
i
Mid-latitude -7° to 4° 18° to 27° 8 to 20 I inht
desert (20° to 40°) (65° to 80°) ( 3 to 8) 9
Low-latitude -4° to 10° 27° to 32° 5 tn K
desert ,40- to so', (& \l |§., , | *° « »gn
'ihKh'.?^""^1 WPateeC/Pb,ra"°e" OV"laP beCaUSe °f "rt«««' '" ^-atu.e
ider-
ite
ght
0
erate
ght
glig-
ble
Pine or
scrub
woodland
Sagebrush,
grass,
scrub
Grease-
wood,
shadscale
Creosote
bush
15
57
20
7
January and 95°F
July, with extremes nf i?n°F ann n:-,- .
A-2
-------
Geology and Hydrology
^^^
fhe NTS moves from north to south at a rate of not less than 2 m nor greater
than 220 m per year Carbon-14 analyses of this eastern ground water indicate
thX the Tower velocity is nearer the true value. At Mercury Valley in the
extreme southern "part of the NTS, the eastern ground water flow shifts south-
westward toward the Ash Meadows Discharge Area.
Land Use of NTS Environs
Fioure A 2 is a map of the off-NTS area showing a wide variety of land
uses such as farming, mining, grazing, camping, fishing, and hunting within a
300-km radius of the NTS. For example, west of the NTS, elevations range from
85 m below MSL in Death Valley to 4.420 m above MSL in the Sierra Nevada Range.
?arts of t* major agricultural valleys (the Owens and San Joaquin) are included.
The aVeas south of the NTS are more uniform since the Mojave Desert ecosystem
Imid-Utitude desert) comprises most of this portion of Nevada, California, and
Ar zona The areas east If the NTS are primarily mid-latitude steppe with some
of the older rTver valleys, such as the Virgin River Valley and Moapa Valley
supporting irrigation for small-scale but intensive farming of a variety of
crops Grazing is also common in this area, particularly to the northeast.
The area north of the NTS is also mid-latitude steppe, where the major agricul-
tural IctlJltv 1s grazing of cattle and sheep. Minor agriculture, primarily
t he rowi nj of alfalfa haj. is found in this portion of the State within 300 km
of the NTS Control Point-1 (CP-1). Many of the residents grow or have access
to locally grown fruits and vegetables.
Many recreational areas, in all directions around the NTS (Figure A 2) are
used for such activities as hunting, fishing, and camping In ge jneral the
camoina and fishing sites to the northwest, north, and northeast of the NTS are
utll zed throughout the year except for the winter months. Camping and fishing
locations to the southeast, south, and southwest are utilized throughout the
year. The hunting season is from September through January.
Population Distribution
Figure A. 3 shows the current popul-ation of counties surrounding the NTS
based on 1980 census figures. Excluding Clark County, the major population
center (approximately 536,000 in 1984) , .the population density within a 150 km
raSius ofThe NTS is" about 0.5 persons per square kilometer For comparison
the 48 contiguous states (1980 census) had a population density of approximately
29 persons per square kilometer. The estimated average population density for
Nevada in 1980 was 2.8 persons per square kilometer.
The off-site area within 80 km of the NTS (the area in^ which the dose
commitment must be determined for the purpose of this report) ^predominant y
rural. Several small communities are located in the area, the largest being in
the Pahrump Valley. This growing rural community, with an estimated population
A-3
-------
Ash Meadows
Ground Water System
\
X
)
Pahute Mesa
Ground Water
System
)
\ ;
10 20 30 40
Scale in Kilometers
Flow Direction
Ground Water System Boundaries
Silent Canyon Caldera
Timber Mountain Caldera
5/88
Figure A.I. Ground-water flow systems around the Nevada Test Site.
A-4
-------
to
in
c
O)
o
(U
S-
3
en
-------
Humboldt
10,600
Box Elder
36,800
Pershing
3,700
Vashoe
224.600
Churchill
15,300
White Pine
7.600
Millard
14,200
Douglas
23.200
Mineral
6.100
Esmeralda
1.300
Washington
38,600
Scale in Miles
0 25 50 75 100
0 50 100 150
Scale in Kilometers
Clark
569.500
8 75,800
01
San Bernardino
1,139,100
6/88
Figure A.3.
Population of Arizona, California, Nevada, and Utah Counties
near the Nevada Test Site (1980).
A-6
-------
of about 5,500, is located about 72 km south of the NTS CP-1. The Amargosa
Farm Area which has a population of about 1,200, is located about 50 km south-
west of CP-1 The largest town in the near-offsite area is Beatty, which has a
population of about 1,000 and is located approximately 65 km to the west of
CP-1 A Report by Smith and Coogan was published in 1984 which summarizes the
population distribution within selected rural areas out to 200 kilometers from
the Control Point on the NTS.
TheMojave Desert of California, which includes Death Valley National
Monument lies along the southwestern border of Nevada. The National KarK
Service (NPS80) estimated that the population within the Monument boundaries
ranges from a minimum of 200 permanent residents during the summer months to as
man? as 5 000 tourists and campers on any particular day during the major hol-
iday periods in the winter months, and as many as 30.000 during Death Valley
Days" in the month of November. The largest town and contiguous populated area
(about 40 square miles) in the Mojave Desert is Barstow, located 265 km south
outhwest of the NTS, with a 1983 population of about 36,000. The next largest
opumdarea is the Ridgecrest-China Lake area which has ; a current popula-
tion of about 25,000 and is located about 190 km southwest of the NTS. The
Owens Valley, where numerous small towns are located, lies about 50 km west of
Death Valley The largest town in Owens Valley is Bishop, located 225 km
wes?-north-west of the NTS, with a population of about 5,300 including contigu-
ous populated areas.
The extreme southwestern region of Utah_ is more developed ' than *he
cent part of Nevada. The largest community is St. George located 220 km east
of the NTS, with a population of 11,300. The next largest town, Cedar City,
with a population of 10,900, is located 280 km east northeast of the NTS.
The extreme northwestern region of Arizona is mostly range land except for
that portion in the Lake Mead Recreation Area. In addition, several small com-
munities lie along the Colorado River. The largest town in the area js King-
man ocated 280 km southeast of the NTS, with a population of about 9 300
Figures A. 4 through A. 7 show the domestic animal populations in the counties
near the NTS.
A-7
-------
Nellit AFB
ange Complex
50 100 150
Scale in Kilometers
San Bernardino
21(297)
XX - Cows
(XX) - Goat
5/88
Figure A.4. Distribution of family milk cows and goats, by county (1987)
A-8
-------
Nellis AFB
anaa Complex
0 50 100 150
Scale in Kilometers
San Bernardino
158,000
5/88
Figure A.5. Distribution of dairy cows, by county (1987)
A-9
-------
Storey.
100
Carson
City
1,200
(Washoe
130,000
*Lyon
341,000s
Humboldt
63,000
L
L- J
Pershing /
24,000 /
Y Lander
Churchill V7'000
50,000 )
!k {.
\
Eureka
25,000
f
Elko
170,000
^ i
Douglas
17,000
N
Mineral
4,700
Mono^
L 2,500
'Esmeralda
12,000
Scale in Miles
25 50 75 100
" ,
50 100 150
Scale in Kilometers
Kern
53,000
^
Inyo
13,000
White Pine
28,000
IMye
23,000
n?R I
"if ' Lincoln
(Complex 19,000
I NTS
OCP-1
Clark
15,000
£J*
< " -'
0) .
%\
San Bernardino
5,500
Box Elder
29,000
£ Tooele
=r 14,900
Juab
8,400
Millard
17,000
Beaver
10,200
Iron
9,600
Washington
9,500
5/88
Figure A.6. Distribution of beef cattle, by county (1987).
A-10
-------
Carson
City
3,000
Nellii AFB
ange Complex
0 50 100 15C
Scale in Kilometers
5/88
Figure A.7. Distribution of sheep, by county 1987.
A-ll
-------
-------
APPENDIX B
SAMPLE ANALYSIS PROCEDURES
ANALYTICAL PROCEDURES
B.I.
TABLE B.I. SUMMARY OF ANALYTICAL PROCEDURES
Type of
Analysis
IG Ge(Li)
Gamma
Spec
trometry**
Gross beta
on air
filters
Analytical
Equipment
IG or Ge(Li)
detector cali-
brated at 0.5
keV/channel
(0.04 to 2
MeV range)
individual
detector
efficienceis
ranging from
15% to 35%.
Low-level end
window, gas
flow propor-
tional counter
with a 12.7 cm
diameter win-
dow (80 M9/
cm2)
Vlll /
Counting
Period
(min)
Air charcoal
cartridges
and individual
air filters,
30 min; air
filter com-
posites, 1200
min. 100 min
for milk,
water, sus-
pended solids.
30
Analytical Sample
Procedures Size
Radionuclide
concentration
quantified
from gamma
spectral data
by on-line
computer pro-
gram. Radio-
nuclides in
air filter
composite
samples are
identified
only.
Samples are
counted after
decay of
naturally-
occuring
radionuclides
and , i f
necessary,
extrapolated
to midpoint
of collection
in accordance
with t-"1-2
decay or an
experimentally-
derived
decay.
120-370 m3
for air
filters;
and char-
coal car-
tridges;
3-1/2
liters for
milk and
water.
120-370 m3
Approximate
Detection
Limit*
For routine milk
and water gen-
erally, 5 pCi/L
for most common
fallout radio-
nuclides in a
simple spectrum.
Filters for LTHMP
suspended solids,
6 pCi/L. Air
filters and char-
coal cartridges,
0.04 pCi/m3.
0.5 pCi/sample.
B-l
-------
TABLE B.I. (Continued)
Type of
Analysis
Sr-89-90
H-3
H-3
Enrichment
(Long-Term
Hydro-
logical
Samples)
Pu-238,239
Kr-85,
Ke-133,
Xe-135
Analytical
Equipment
Low-background
thin-window,
gas-flow
proportional
counter.
Automatic
liquid
scintillation
counter with
output printer.
Automatic
scintillation
counter with
output printer.
Alpha spectro-
meter with
450 mm, 300-um
depletion depth,
depth, silicon
surface barrier
detectors
operated In
vacuum chambers.
Automatic
liquid scintil-
lation counter
with output
printer.
Counting
Period Analytical
(min) Procedures
50 Chemical sep-
aration by
ion exchange.
Separated
sample counted
successively;
activity
calculated by
simultaneous
solution of
equations.
200 Sample
prepared by
distillation.
200 Sample con-
centrated
by
electrolysis
followed by
distillation.
1000-1400 Water sample
or acid-
digested
filter or
tissue
samples
separated by
Ion exchange,
electro-
plated on
stainless
steel
planchet.
200 Separation by
by gas
chromatography ;
dissolved in
toluene
"cocktail"
for counting.
Sample
Size
1.0 liter
for milk
or water.
0.1-1 kg
for
tissue.
4 ml
for
water.
250 ml
for
water.
1.0 liter
for water;
0.1-1 kg
for
tissue;
5,000-
10,000 m3
for air.
0.4-1.0
1.0 m3
for
air.
_
Approximate
Detection
Limit*
Sr-89 = 5 pd/L
Sr-90 - 2 pCi/L
400 pCi/L
10 pCI/L
Pu-238 = 0.08 pCi/L
Pu-239 =0.04 pCi/L
for water. For
For tissue
samples,
0.04 pCi per
total sample for
all isotopes;
5-10 ad/m3
for plutonlum
on air
filters.
Kr-85, Xe-133,
Xe-135 =
4 pC1/m3
? " ^l* ?? 3'29 Slgma wherG s19ma ec'uals the counting error of the
R F ii n TT : !yPVInerr°r = 5 Percent. (J. P. Corley, D. H. Oenham,
;t M I' K1Ct ^ c' ° SCn' D< A" Wa1te> A Guide for Environmental Radiological
' July 1981> Off1ce of operational safe?y
**Gamm^Spectrometry using either an Intrinsic germanium (IG), or lithium-drifted germanium diode
B-2
-------
APPENDIX C
QUALITY ASSURANCE PROCEDURES
PRECISION OF ANALYSIS
The duplicate sampling program was initiated for the purpose of routinely
assessing the errors due to sampling, analysis, and counting of samples obtained
from the surveillance networks maintained by the EMSL-LV.
The program consists of the analysis of duplicate or replicate samples
from the ASM, the NGTSN, the LTHMP, and the Dosimetry Network. As the radio-
activity concentration in samples collected from the LTHMP and the MSN are
below detection levels, most duplicate samples for these networks are prepared
from spiked solutions. The NGTSN samples are generally split for analysis.
At least 30 duplicate samples from each network are normally collected and
analyzed over the report period. Since three TLD cards consisting of two TLD
chips each are used at each station of the Dosimetry Network, no additional
samples were necessary. Table C-l summarizes the sampling information for each
surveillance network.
To estimate the precision of a methodology, the standard deviation of
replicate results is needed. Thus, for example, the variance, ^, of each set
of replicate TLD results (n=6) was estimated from the results by the standard
expression,
s2 = Z (*i - x)/ (k - 1)
i = 1
where k = number of sets of replicates.
Since duplicate samples were collected for all other sample types, the
variances, s?, for these types were calculated from s2 = (0.886RK, where R is
the absolute difference between the duplicate sample results. For small sample
sizes, this estimate of the variance is statistically efficient* and certainly
more convenient to calculate than the standard expression. The standard devia-
tion is obtained by taking the square root.
*Snedecor, G. W., and W. G. Cochran. Statistical Methods. The Iowa State
University Press, Ames, Iowa, 6th Ed. 1967, pp. 39-47.
C-l
-------
TABLE C.I. SAMPLES AND ANALYSES FOR DUPLICATE SAMPLING PROGRAM - 1987
Sets of
Number of Samples Duplicate
Surveillance Sampling Collected Samples Number
Network Locations This Year Collected Per Set
ASN 113 8,627 288 2
NGTSN 19 810 (NG) 145 2
816 (H3) 97
Dosimetry 150 726 726 4-6
MSN 22 238 78 2
LTHMP 199 799 139 2
Sample
Analysis
Gross beta,
y Spectrometry
Kr-85, H-3,
H20, HTO
Effective dose
from gamma
K-40, Sr-89,
Sr-90, H-3
H-3
nnn, i . the variances of random samples collected from a normal
population follow a chi-square distribution (*2) waFs then used t estimate the
expected population standard deviation for each type of sample analysis The
expression used is as follows:* ~ y e
s =
If - 1)
Eq. 2
where n,--l
the degrees of freedom for n samples collected for the ith
replicate sample
c.
Sj = the expected variance of the ith replicate sample
s = the^best estimate of sample standard deviation derived from the
variance estimates of all, replicate samples (the expected value
Of S^ IS a'-) .
For expressing the precision of measurement in common units, the coeffi-
cient of variation (s/x) was calculated for each sample type. These are
displayed in Table C.2 for those analyses for which there were adequate data.
Statist1cs' Pl"entice Hall, Englewood, New Jersey,
C-2
-------
TABLE C.2. SAMPLING AND ANALYTICAL PRECISION - 1987
Surveillance
Network
ASN
NGTSN
Dosimetry
MSN
LTHMP
Analysis
Be-7
Gross B
Kr-85
HTO
H20
TLD
K-40
Sr-90
H-3
H-3+
Sets of
Replicate
Samples
Evaluated
6
29
46
*
97
511
55
11
45
76
Coefficient
of Variation
(%)
70
33
9.4
31
34
9.8
18
20
30
13
Estimate of precision was calculated from the errors in the H-3 conventional
analysis and the measurement of atmospheric moisture (H20).
To estimate the precision of counting, approximately 10 percent of all
samples are counted a second time. These are unknown to the analyst Since
alTsuch replicate counting gave results within the counting error, the preci-
sion data in Table C.2 represents errors principally in analysis.
ACCURACY OF ANALYSIS
Data from the analysis of intercomparison samples are statistically anal-
yzed and compared to known values and values obtained from other participating
laboratories. A summary of the statistical analysis is given in Table C 3,
which compares the mean of three replicate analyses with the known value The
normalized deviation is a measure of the accuracy of the analysis when compared
to the known concentration. The determination of this parameter is explained
in detail separately (Ja81). If the value of this parameter (in multiples of
standard normal deviate, unitless) lies between control limits of -3 and +3,
the precision or accuracy of the analysis is within normal statistical varia-
tion However, if the parameters exceed these limits, one must suspect that
there is some cause other than normal statistical variations that contributed
to the difference between the measured values and the known value. As shown by
this table, all of the analyses were within the control limit.
C-3
-------
TABLE C.3. EPA QUALITY ASSURANCE INTERCOMPARISON RESULTS - 1987
Analysis
Alpha
Beta
Chromium-51
Cobalt-60
Cesium-134
Cesium- 137
Tritium
Iodine-131
Potassium
Month
Apr
Aug
Oct
Nov
Apr
Aug
Oct
Nov
Jun
Oct
Feb
Apr
Jun
Oct
Feb
Apr
Jun
Oct
Feb
Apr
Jun
Aug
Oct
Feb
Apr
Jun
Oct
Feb
Apr
Jun
Aug
Dec
Jun
Mean of
Replicate
Analyses
(pCi/L)
15.4
10.5
28.5
6.3
45.3
30.3
75.2
18.6
39.2
68.8
50.4
9.0
64.8
16.4
54.8
18.2
36.7
24.4
87.3
9.2
79.5
10.7
51.8
4155.6
5620.6
2784.8
4386.3
8.5
7.2
62.0
47.2
26.6
1755.0
Known Value
(pCi/L)
14.0
10.0
28.0
7.0
43.0
30.0
72.0
19.0
41.0
70.0
50.0
8.0
64.0
15.0
59.0
20.0
40.0
25.0
87.0
8.0
80.0
10.0
51.0
4209.0
5620.0
2895.0
4492.0
9.0
7.0
59.0
48.0
26.8
1525.0
Normalized
Deviation from
Known Concentration
-1 6
J- 9 \J
-0. 1
NA
-0.3
0 9
\J j
0 9
\j * j
NA
-0.9
3 7
J /
NA
-0.3
0 3
\J
-------
TABLE C.3. Continued
Analysis
Plutonium-239
Radium -2 26
Radium- 2 28
Ruthenium-106
Strontium-89
Strontium-90
Uranium
Zinc-65
Month
Apr
Oct
Apr
Oct
Apr
Oct
Feb
Jun
Oct
Jan
Apr
Jun
Aug
Oct
Jan
Apr
May
Aug
Oct
Apr
Aug
Oct
Feb
Jun
Oct
Mean of
Replicate
Analyses
(pCi/L)
15.3
5.2
3.8
4.7
4.2
4.7
95.0
72.5
60.2
23.3
17.4
63.7
38.9
75.2
23.3
10.0
19.5
9.6
9.9
5.5
12.4
3.4
93.9
10.9
47.2
Known Value
(pCi/L)
16.7
5.3
3.9
4.8
4.0
4.8
100.0
75.0
61.0
25.0
19.0
69.0
41.0
72.0
25.0
10.0
20.0
10.0
10.0
5.0
13.0
3.0
91.0
10.0
46.0
Normal i zed
Deviation from
Known Concentration
NA
-1.5
-0.2
NA
NA
NA
-3.0
1.7
LI A
NA
-1.4
0.1
1.5
-0.8
NA
0.4
0.8
-0.8
NA
-1.2
0.0
-0.4
0.0
0.3
1.0
NA
C-5
-------
TABLE C.4. QUALITY ASSURANCE RESULTS FROM DOE PROGRAM - 1987
Analysis
Be-7
in air
Zr-95
in air
Sb-125
in air
Cs-137
in air
Ce-144
in air
Pu-239
in air
K-40
in soil
Cs-137
in soil
Pu-239
in soil
Cs-137
in tissue
K-40
in vegetation
Cs-137
in vegetation
H-3
in water
Mn-54
in water
Co-60
in water
Month
Sept
Sept
Sept
Sept
Sept
Sept
Sept
Sept
Sept
Sept
Sept
Sept
Sept
Sept
Sept
EMSL-LV
Results
0.873E+03
0.216E+03
0.610E+03
0.280E+03
0.356E+03
0.510E+01
0.239E+02
0.180E+00
0.240E-01
0.290E+00
0.169E+03
0.172E+01
0.184E+02
0.233E+01
0.230E+01
C-6
EML
Results
0.896E+03
0.188E+03
0.963E+03
0.290E+03
0.406E+03
0.523E+01
0.200E+02
0.211E+00
0.290E-01
0.190E+00
0.163E+03
0.182E+01
0.191E+02
0.228E+01
0.227E+01
Ratio
EPA/EML
0.97
1.15
0.63
0.97
0.88
0.98
1.19
0.85
1.17
1.53
1.04
0.95
0.96
1.02
1.01
(continued)
-------
TABLE C.4. Continued
Analysis
Sr-90
in water
Cs-137
in water
Pu-239
in water
Co-57
in water
Month
Sept
Sept
Sept
Sept
EMSL-LV
Results
0.261E+00
0.223E+01
0.150E+00
0.140E+00
EML
Results
0.252E+00
0.228E+01
0.266E+00
0.142E+00
Ratio
EPA/EML
1.04
0.98
0.56*
0.99
*Grand average for all laboratories was 0.185. Therefore, the EMSL-LV result
when compared to all other laboratories is 0.15/0.185 = 0.81.
The analytical methods were further checked on by Laboratory participation
in the semiannual Department of Energy Quality Assessment Program conducted by
the Environmental Measurements Laboratory, New York, N.Y. The results from
these tests (Table C.4) indicate that this Laboratory's results were of accept-
able quality.
To measure the performance of the contractor laboratory for analysis of
animal tissues, a known amount of activity was added to several samples. The
reported activity is compared to the known amount in Table C.5._ The average
bias for plutonium-239 was -24.5 percent. The bias for strontium-90 was a
percent for one sample and indeterminate for the other (activity reported
less than naturally present). The average precision
-44
was
determined from
sets of duplicate
strontium-90.
samples was 150 percent for plutonium-239 and 17 percent
two
for
C-7
-------
TABLE C.5. QUALITY ASSURANCE RESULTS FOR THE BIOENVIRONMENTAL PROGRAM - 1987
Sample Type
and
Shipment
Number
Bone Ash
Ash C
74
Ash D
74
Ash E
74
Ash F
74
Duplicate Samples
Bov-1
Bov-1 Dup
Bov-2
Bov-2 Dup
Nuclide
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239Pu
90Sr
239PU
90Sr
239Pu
90 Sr
Activity Added
pCi/g Bone Ash
Spiked Samples
0.082
11.2
0.086
11.6
0
0
0
0
Activity Reported
pCi/g Bone Ash
0.062
8.9
0.066
1.8
0.9**
2.3
-0.0003**
2.8
0.003
0.7
0.0003**
0.6
0.0004
0.4
0.003
0.5
% Bias+
or
Precision^
-25
-44
-24
Indeterminate
1.5
0.14
1.4
0.2
+ Bias (B) = Recovery -1; where recovery is xl
~u
and KI = net activity reported
u = activity added
Precision (C) = 2
.*! + x2
**Counting error exceeds reported activity
1
x where
1.128
Xj = first value
Xp = second value
C-8
-------
APPENDIX D
RADIATION PROTECTION STANDARDS FOR EXTERNAL AND INTERNAL EXPOSURE
DOE EQUIVALENT COMMITMENT
For stochastic effects in members of the public, the following limits are
used:
Effective Dose Equivalent*
mrem/yr mSv/yr
Occasional annual exposures** 500 5
Prolonged period of exposure 100 1
Includes both effective dose equivalent from external radiation and
committed effective dose equivalent from ingested and inhaled
radionuclides.
**0ccasional exposure implies exposure over a few years with the proviso
that over a lifetime the average exposure does not exceed 100 mrem
(1 mSv) per year (ICRP-39).
CONCENTRATION GUIDES
ICRP-30 lists Derived Air Concentrations (DAC) and Annual Limits of Intake
(ALI) The ALI is the secondary limit and can be used with assumed breathing
rates'and ingested volumes to calculate concentration guides. The concentration
guides (CG's) in Table D-l were derived in this manner and yield the committed
effective dose equivalent (50 year) of 100 mrem/yr for members of the public.
EPA DRINKING WATER GUIDE
In 40 CFR 141 the EPA set allowable concentrations for continuous con-
trolled releases of radionuclides to drinking water sources. Any single or
combination of beta and gamma emitters should not lead to exposures exceeding
4 mrem/yr. For tritium this is 20,000 pCi/L (740 Bq/L) and for strontium-90
is 8 pCi/L (0.3 Bq/L).
D-l
-------
TABLE D.I. ROUTINE MONITORING FREQUENCY, SAMPLE SIZE, MDC AND CONCENTRATION GUIDES
Nuclide
Air Surveillance
Be-7
Zr-95
Nb-95
Mo -99
Ru-103
1-131
Te-132
Cs-137
Ba-140
La-140
Ce-141
Ce-144
Pu-239
Gross Beta
Sampling
Frequency
Network
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
3/wk
Locations
all
all
all
all
all
all
all
all
all
all
all
all
all
all
Sample
Size
m3
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
160-240
1120
160-240
Count
Time
minutes
30
30
30
30
30
30
30
30
30
30
30
30
1000
30
Concentration Guide*
Bq/m3
2000
20
100
100
60
4
18
10
100
100
50
1
9E-4
2E-2
nCi/m3
50
0.6
3
3
2
0.1
0.5
0.4
3
3
1
0.03
2E-5
0.4E-4
MDC
mBq/m3
17
4.1
1.8
1.5
1.8
1.8
1.8
1.8
4.8
2.6
3.0
12
1.48E-3
0.11
MDC as
% CG
8E-4
2E-2
2E-3
2E-3
3E-3
4E-2
1E-2
2E-2
5E-3
3E-3
6E-3
1.2
2E-1
6E-1
(continued)
-------
TABLE D.I. Continued
Sampling Sample
Nuclide Frequency Locations Size
Noble Gas Tritium in Air m3
H-3
Kr-85
Xe-133
Xe-135
Water Surveillance
H-3
H-3 (Enrich)
Sr-89
Sr-90
Cs-137
Ra-226
U-234
U-235
U-238
Pu-238
1/wk
1/wk
1/wk
1/wk
17 5
17 0.4
17 0.4
17 0.4
Network (LTHMP) Liters
1/mo
1/mo
1st
1st
1/mo
1st
1st
1st
1st
1st
all 1
all 0.1
time all 1
time all 1
all 1
time all 1
time all 1
time all 1
time all 1
time all 1
Count
Time Concentration Guide*
Minutes
200
200
200
200
Minutes
200
200
50
50
100
1000
1000
1000
1000
1000
Bq/m3
7000
1E5
2E4
2E3
Bq/L
7E2
7E2
600
0.3
160
5
20
20
20
10
nCi/m3
190
3000
480
60
pCi/L
2E4
2E4
2E4
8
3E3
100
500
600
600
400
MDC
mBq/m3
148
148
148
148
Bq/L
12
0.37
0.18
0.074
0.33
NA
NA
NA
NA
0.003
MDC as
% CG
2E-3
2E-4
7E-4
7E-3
1.7
5E-2
0.03
25
0.3
0.03
(continued)
-------
TABLE D.I. Continued
Sampling
Nuclide Frequency
Water Surveillance
Pu-239
Gamma
Milk Surveillance
H-3
Cs-137
o
*> Sr-89
Sr-90
Gamma
Dosimetry Network
TLD (Personnel)
TLD (Station)
Ion Chamber
Na - Not Avail ahl
Network
1st time
1/mo
Network
1/mo
1/mo
1/mo
1/mo
1/mo
1/mo
1/qtr
weekly
Sample
Locations Size
(LTHMP)
all
all
all
all
all
all
all
50
130
23
Liters
1
3.5
3.5
3.5
3.5
3.5
3.5
Number
2
6
2016
Count
Time Concentration Guide* MDC
Minutes Bq/L pd'/L Bq/L
1000 10 300 0.002
30 -- - 0.18
200 8E4 2E6 12
100 100 3E3 0.33
50 600 2E4 0.18
50 40 1E3 0.074
50 0.18
Exposure
Guide MDA
lOOmR 2mR
2mR
2uR/hr
MDC as
% CG
0.02
<0.2
2E-2
0.3
3E-2
0.2
<0.2
2
*ALI and OAC values fro ICRP-30 modified to 1 mSv annual effective dose equivalent for continuous
bathed'annual "yei n^n". * 9 ^"^ gre*ter >rillc 1ntake- *"d ller TOl= °f
-------
APPENDIX E
DATA SUMMARY FOR THE MONITORING NETWORKS
TABLE E 1 SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
CONTINUOUSLY OPERATING STATIONS - 1987
SAMPLING LOCATION
DEATH VALLEY OCT CA
FURNACE CREEK CA
SHOSHONE CA
ALAMO NV
AUSTIN NV
BEATTY NV
STONE CABIN RANCH NV
ELY NV
GOLDFIELD NV
GROOM LAKE NV
HIKO NV
INDIAN SPRINGS NV
LAS VEGAS NV
LATHROP WELLS NV
NYALA NV
NO. DAYS
DETECTED
/SAMPLED
14.9/294.8
56.6/355.6
30.6/347.6
49.1/360.9
20.0/364.3
24.6/358.7
10.0/355.6
21.0/361.6
16.8/362.6
39.0/357.0
20.9/365.5
24.1/362.8
41.1/361.5
27.4/359.9
10.0/362.0
RAD 10-
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
RADIOACTIVITY CONC.
(pCi/m3)
MAX
0.81
1.9
0.87
1.5
0.64
1.2
0.76
1.2
0.73
0.92
1.2
0.96
1.2
2.1
1.8
MIN
0.31
0.22
0.17
0.19
0.41
0.23
0.29
0.28
0.31
0.11
0.29
0.32
0.18
0.14
0.60
AVG*
0.025
0.092
0.041
0.070
0.026
0.040
0.012
0.030
0.023
0.027
0.030
0.035
0.067
0.057
0.028
(CONTINUED)
E-l
-------
TABLE E.I. CONTINUED
SAMPLING LOCATION
OVERTON NV
PAHRUMP NV
PIOCHE NV
SCOTTY'S JCT NV
SUNNYSIDE NV
RACHEL NV - ROBINSON TRAILER P
TONOPAH NV
TTR NV
FALLINI'S (TWIN SPGS) RANCH NV
CEDAR CITY UT
DELTA UT
MILFORD UT
ST GEORGE UT
SALT LAKE CITY UT
NO. DAYS
DETECTED
/SAMPLED
23.6/356.9
35.5/359.7
16.0/361.4
43.0/366.0
19.6/361.2
28.3/350.3
10.9/362.0
156.6/346.0
26.8/353.9
48.1/364.6
24.2/355.2
20.5/350.6
39.6/365.9
66.0/363.9
RADIO-
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
RADIOACTIVITY
(pCi/m3)
MAX
0.79
0.97
0.63
0.91
0.79
0.95
2.6
0.45
1.8
1.2
0.58
2.0
1.4
1.6
MIN
0.28
0.092
0.35
0.25
0.29
0.14
0.14
0.053
0.19
0.27
0.17
0.43
0.22
0.25
CONC.
AVG*
0.032
0.037
0.022
0.055
0.026
0.035
0.030
0.092
0.047
0.063
0.022
0.041
0.058
0.11
* AVERAGE MEANS TIME WEIGHTED AVERAGE OVER SAMPLING TIME.
THE FOLLOWING STATIONS HAD NEGLIGIBLE GAMMA-SPECTRA-
CURRANT NV - BLUE EAGLE RANCH
E-2
-------
TABLE E 2 SUMMARY OF ANALYTICAL RESULTS FOR AIR SURVEILLANCE NETWORK
STANDBY STATIONS OPERATED 1 OR 2 WEEKS PER QUARTER - 1987
SAMPLING LOCATION
KINGMAN AZ
WINSLOW AZ
YUMA AZ
LITTLE ROCK AR
BAKER CA
BISHOP CA
RIDGECREST CA
DENVER CO
GRAND JUNCTION CO
IOWA CITY I A
MONROE LA
ST JOSEPH MO
KALISPELL MT
ADAVEN (CANFIELD'S RANCH) NV
CRYSTAL NV
CALIENTE NV
CURRIE NV
LOVELOCK NV
LUND NV
WINNEMUCCA NV
ALBUQUERQUE NM
NO. DAYS
DETECTED
/SAMPLED
2.0/26.2
2.0/28.0
2.1/37.6
2.2/28.2
3.0/29.0
4.0/24.1
2.1/33.6
3.0/28.1
2.1/30.2
3.0/34.7
2.0/27.9
8.8/35.3
3.0/28.1
1.8/37.1
1.1/23.3
24.4/135.7
3.0/28.6
2.0/26.7
3.1/26.3
3.1/30.2
2.0/28.6
RADIO-
NUCLIDE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
7BE
RADIOACTIVITY CONC,
(pCi/m3)
MAX
0.81
0.49
0.32
0.39
1.5
0.46
0.41
0.34
0.38
0.67
0.68
0.29
0.63
0.94
0.35
1.4
0.23
0.31
0.60
0.54
0.57
MIN
0.81
0.49
0.32
0.39
1.5
0.46
0.41
0.34
0.38
0.67
0.68
0.29
0.63
0.94
0.35
0.21
0.23
0.31
0.60
0.54
0.57
i rnNi
AVG*
0.062
0.035
0.017
0.030
0.15
0.077
0.025
0.036
0.027
0.057
0.049
0.071
0.066
0.045
0.017
0.10
0.025
0.023
0.070
0.056
0.040
TNIIFD)
E-3
-------
TABLE E.2. CONTINUED
NO. DAYS
RADIOACTIVITY CONC.
(pCi/m3)
SAMPLING LOCATION
CARLSBAD NM
MUSKOGEE OK
MIDLAND TX
BRYCE CANYON UT
PAROWAN UT
WENDOVER UT
/SAMPLED
8.9/27.9
4.0/28.0
2.1/27.9
1.9/24.1
2.0/33.0
5.0/32.0
NUCLIDE
'
7BE
7BE
7BE
7BE
7BE
7BE
MAX
0.30
0.17
0.66
0.30
0.73
0.57
MIN
0.26
0.17
0.66
0.30
0.73
0.34
AVG*
0.085
0.025
0.049
0.024
0.045
0.068
*AVG MEANS TIME-WEIGHTED AVERAGE OVER SAMPLING TIME.
THE FOLLOWING STATIONS HAD NEGLIGIBLE GAMMA-SPECTRA:
GLOBE AZ
TUCSON AZ
ALTURAS CA
CHICO CA
INDIO CA
LONE PINE CA
NEEDLES CA
SANTA ROSA CA
CORTEZ CO
MOUNTAIN HOME ID
NAMPA ID
POCATELLO ID
FORT DODGE IA
DODGE CITY KS
MINNEAPOLIS MN
CLAYTON MO
JOPLIN MO
GREAT FALLS MT
MILES CITY MT
BISMARK ND
FARGO ND
WILLISTON ND
NORTH PLATTE NE
SHIPROCK NM
AMARGOSA FARM AREA NV
BATTLE MOUNTAIN NV
BLUE JAY NV
CLARK STATION NV
CURRANT NV - ANGLE WORM RANCH
DUCKWATER NV
ELKO NV
EUREKA NV
FALLON NV
GEYSER RANCH NV
MESQUITE NV
RENO NV
ROUND MOUNTAIN NV
WARM SPRINGS NV
WELLS NV
MEDFORD OR
BURNS OR
RAPID CITY SD
AMARILLO TX
AUSTIN TX
TYLER TX
ENTERPRISE UT
GARRISON UT
LOGAN UT
VERNAL UT
SEATTLE WA
SPOKANE WA
ROCK SPRINGS WY
WORLAND WY
E-4
-------
TABLE E.3. 1987 SUMMARY OF GROSS BETA ANALYSES FOR AIR SURVEILLANCE NETWORK
SAMPLING LOCATION
SHOSHONE CA
LAS VEGAS NV
DELTA UT
MILFORD UT
ST GEORGE UT
NO.
DAYS
SAMPLED
347.6
361.5
355.2
336.9
365.9
RADIOACTIVITY CONC.
(pCi/m3)
MAX
MIN
AVG
0.030 0.00052 0.0090
0.026 0.00023 0.0090
0.030 0.00024 0.0097
0.053 0.00030 0.010
0.037 0.00020 0.0091
E-5
-------
TABLE E.4. SUMMARY OF PLUTONIUM CONCENTRATIONS AT SELECTED AIR
SURVEILLANCE NETWORK STATIONS - 1987
SAMPLING
LOCATION
WINSLOW/TUCSON, AZ
BISHOP/RIDGECREST, CA
DENVER/CORTEZ, CO
NAMPA/MOUNTAIN HOME, ID
CLAYTON/ JOPLIN, MO
GREAT FALLS/MILES CITY,
MT
MT
LAS VEGAS, NV
LATHROP WELLS, NV
RACHEL, NV - ROBINSON
TRAILER P
ALBUQUERQUE/CARLSBAD, NM
BISMARCK/ FARGO, ND
BURNS/MEDFORD, OR
A n
OR
AUSTIN/AMARILLO, TX
LOGAN/VERNAL, UT
NO.
DAYS
SAMPLED
48.7
48.7
57.7
57.7
57.2
57.2
57.5
57.5
37.2
37.2
60.2
60.2
361.6
361.6
360.9
360.9
354.0
354.0
56.5
56.5
58.7
58.7
53.3
53.3
60.8
60.8
63.9
63.9
RADIOACTIVITY
RAD 10-
NUCLIDE
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
238PU
239PU
CONC.
(aCi/m3)*
MAX
19
12
12
7.2
12
20
27
16
20
3.0
11
4.1
22
7.2
15
8.6
11
14
19
5.4
20
1.4
19
39
-0.92
12
-0.93
8.6
MIN
-17
-12
-8.5
-5.3
-14
-2.8
-6.9
-5.4
-6.3
-3.2
-1.9
-3.7
-10
-8.1
-10
-5.7
-14
-2.3
-8.9
-1.8
-6.3
-9.2
-10
-23
-25
-1.6
-17
-12
AVG
-3.2
2.2
0.36
2.4
-1.2
7.7
4.4
3.3
3.8
-0.67
4.3
1.6
-1.1
1.8
-0.59
-0.78
-2.9
2.9
3.5
1.1
0.72
-2.5
4.5
-3.6
-9.0
3.4
-11
-4.8
PERCENT
CONC.
GUIDE
<0.01
0.01
<0.01
0.01
<0.01
0.04
0.02
0.02
0.02
<0.01
0.02
<0.01
<0.01
<0.01
<0.01
<0.01
<0.01
0.01
0.02
<0.01
<0.01
<0.01
0.02
<0.01
<0.01
0.02
<0.01
<0.01
(CONTINUED)
E-6
-------
TABLE E.4. CONTINUED
SAMPLING
LOCATION
SALT LAKE CITY, UT
SEATTLE/ SPOKANE, WA
WORLAND/ROCK SPRINGS,
MO
DAYS
SAMPLED
338.1
338.1
56.0
56.0
WY 55.7
55.7
RADIOACTIVITY CONC.
(aCi/m3)* PERCENT
RAD 10-
NUCLIDE
238PU
239PU
238PU
239PU
238PU
239PU
MAX
_ _ i ^ i .
16
3.5
11
4.3
4.9
6.9
MIN
_
-7.6
-4.6
-7.6
-1.7
-5.6
-4.0
AVG
-0.023
-0.70
-0.39
2.3
-0.40
0.60
CONC.
GUIDE
<0.01
<0.01
<0.01
0.01
<0.01
<0.01
*ALL RESULTS LESS THAN MDC. DEPENDING UPON GEOMETRY OF ANALYSIS AND COUNTING
TIMES, MDC'S VARIED FROM -0.09 to 48 aCi/m-5.
E-7
-------
TABLE E.5.
TD,,cn- RESULTS FOR THE
TRITIUM SURVEILLANCE NETWORK - 1987
GAS AND
SAMPLING
LOCATION
MAMMOTH LAKES
CALIF.
SHOSHONE,
CALIF.
ALAMO,
NEV.
AUSTIN,
NEV.
BEATTY,
NEV.
CALIENTE,
NEV.
ELY,
NEV.
GOLDFIELD,
NEV.
INDIAN SPRINGS,
NEV.
NUMBER
SAMPLES
POSITIVE/
NEGATIVE RADIONUCLIDE
22/2
24/0
50/2
50/2
49/0
49/0
47/5
46/6
47/2
47/2
39/13
39/13
46/3
46/3
39/13
40/12
48/0
48/0
17/0
17/0
48/4
47/5
48/1
47/2
42/10
47/5
46/3
46/3
42/11
44/9
49/0
49/0
85KR
133XE
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
RADIOACTIVITY CONC.
(pCi/m3)*
MAX
29
8.3
31
7.1
0.65
6.7
30
9.3
0.80
7.5
31
15
0.75
3.2
30
33
0.84
6.1
1.3
7.0
30
20
0.77
14
29
26
0.65
3.9
34
27
0.64
8.4
MIN
22
-6.2
19
-7.8
-0.37
-5.3
21
-13
-0.86
-6.6
21
-10
-0.52
-3.1
21
-14
-0.46
-2.6
-0.43
-4.1
20
-11
-0.72
-6.6
21
-16
-0.87
-3.4
20
-7.0
-0.33
-2.3
AVG
26
1.5
26
0.77
0.095
0.63
26
1.1
0.076
0.63
25
0.89
0.10
0.50
26
1.1
0.10
0.64
0.032
-0.082
25
1.9
0.090
0.97
25
1.8
0.058
0.23
26
0.98
0.13
0.88
PERCENT
CONC.
GUIDE*
0.03
<0.01
0.03
<0.01
<0.01
0.03
<0.01
<0.01
0.02
<0.01
<0.01
0.03
<0.01
<0.01
<0.01
0.03
<0.01
<0.01
0.03
<0 01
^ *-J \J -L
<0.01
0.03
<0.01
<0.01
(CONTINUED)
E-8
-------
TABLE E.5. CONTINUED
NUMBER
SAMPLES
SAMPLING POSITIVE/
LOCATION NEGATIVE
LAS VEGAS,
NEV.
LATHROP WELLS,
NEV.
OVERTON,
NEV.
PAHRUMP,
NEV.
PIOCHE,
NEV.
RACHEL,
NEV.
TONOPAH,
NEV.
CEDAR CITY,
UTAH
47/5
48/4
49/0
49/0
46/6
44/8
47/2
47/2
47/5
48/4
47/2
47/2
50/1
49/2
49/0
49/0
9/0
9/0
48/1
48/1
44/7
47/4
46/3
46/3
45/6
43/8
48/1
48/1
42/10
44/8
48/1
48/1
RADIONUCLIDE
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
RADIOACTIVITY CONC.
(pCi/m3)* PERCENT
K rnKir
MAX
30
7.3
0.61
4.2
30
7.7
1.1
16
33
16
0.88
17
30
18
0.63
3.3
29
9.7
1.2
4.9
29
9.2
0.51
5.6
30
9.3
0.69
5.0
31
15
0.72
5.6
MIN
20
-6.9
-0.83
-6.2
20
-15
-0.56
-4.4
20
-12
-0.68
-11
21
-7.4
-0.42
-5.2
25
-5.4
-0.89
-4.7
20
-13
-0.76
-5.7
20
-9.5
-0.68
-3.5
21
-7.2
-1.0
-5.5
AVG GUIDE+
26
1.1
0.060
0.50
25
0.24
0.17
1.3
25
0.49
0.049
0.92
26
1.0
0.043
0.092
26
-0.18
0.12
0.82
25
0.35
0.050
0.29
26
1.8
0.078
0.77
26
1.5
0.036
0.30
0.03
<0.01
<0.01
0.02
<0.01
<0.01
0.03
<0.01
<0.01
0.03
<0.01
<0.01
0.03
<0.01
<0.01
0.03
<0.01
<0.01
0.03
<0.01
<0.01
0.03
<0.01
<0.01
(CONTINUED)
E-9
-------
TABLE E.5. CONTINUED
SAMPLING
LOCATION
ST GEORGE,
UTAH
SALT LAKE CITY,
UTAH
NUMBER
SAMPLES
POSITIVE/
NEGATIVE RADIONUCLIDE
41/10
42/9
41/8
41/8
43/9
43/9
85KR
133XE
3H IN ATM. M.*
3H AS HTO IN AIR
3H IN ATM. M.*
3H AS HTO IN AIR
RADIOACTIVITY CONC.
(pCi/m3)*
MAX
31
13
0.69
6.1
0.65
4.8
MIN
20
-11
-0.35
-3.1
-0.87
-8.9
AVG
25
0.41
0.078
0.60
0.12
0.70
PERCENT
CONC.
GUIDE*
0.02
<0.01
<0.01
<0.01
E-10
-------
TABLE E.6. LTHMP TRITIUM RESULTS FOR THE MONTHLY NTS NETWORK FOR 1987
SAMPLING
LOCATION
WELL 1 ARMY
WELL 2
WELL 3
WELL 4
WELL 4 CP-1
WELL 5C
WELL 8
WELL 20
WELL A
WELL B TEST
WELL C
WELL J-13
WELL U19C
WELL UE7NS
WELL UE18R
NO.
SAMPLES
10
12
12
12
11
10
12
11
12
8
12
11
11
9
9
TRITIUM CONCENTRATION
(pCi/L)
MAX
15
12
14
12
18
7.5
16
18
51
160
49
4.4
8.9
3500
8.6
MIN
-6.4
-4.2
-4.9
-7.5
-6.1
-4.0
-5.5
-3.0
13
120
7.2
-8.9
-5.7
2400
-3.8
AVG
0.43
1.8
3.8
0.44
1.9
0.42
2.2
4.7
27
140
23
-1.9
1.1
2800
2.6
PERCENT
CONC.
GUIDE
<0.01
<0.01
0.02
<0.01
<0.01
<0.01
0.01
0.02
0.1
0.7
0.1
<0.01
<0.01
10
<0.02
E-ll
-------
TABLE E.7. TRITIUM RESULTS FOR THE LONG-TERM HYDROLOGICAL MONITORING
PROGRAM - 1987
SAMPLING LOCATION
NEVADA TEST SITE NETWORK
SHOSHONE, CA
SHOSHONE SPRING
ADAVEN, NV
ADAVEN SPRING
ALAMO, NV
WELL 4 CITY
ASH MEADOWS, NV
CRYSTAL POOL
FAIRBANKS SPRINGS
WELL 17S-50E-14CAC
WELL 18S-51E-7DB
BEATTY, NV
SPECIE SPRINGS
TOLICHA PEAK
USECOLOGY
WELL 11S-48-1DD COFFERS
WELL 12S-47E-7DBD CITY
WELL ROAD D SPICERS
COLLECTION
DATE
1987
01/07
06/02
05/06
10/01
11/01
04/07
09/08
02/19
07/10
03/11
08/10
02/19
07/10
02/19
07/10
01/13
08/13
02/18
07/09
01/06
02/18
07/09
03/12
08/12
02/18
07/09
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
23 ± 210*
0 ± 7.8*
68 ± 8
41 ± 230*
67 ± 8
7.2 ± 8.3*
-250 ± 250*
3.7 ± 5.6*
86 ± 200*
4.5 ± 8.1*
260 ± 260*
-4.2 ± 8.6*
86 ± 200*
3.8 ± 8.8*
45 ± 200*
56 ± 8
180 ± 260*
-2.9 ± 8.3*
-9.6 ± 200*
4.1 ± 11*
-3.1 ± 9.3*
79 ± 200*
7.7 ± 8.1*
320 ± 260*
-1.7 ± 8.3*
-89 ± 200*
PCT OF
CONC.
GUIDE
" '
0.1
<0.01
0.3
0.2
0.3
0.04
<0.01
0.02
0.4
0.02
1
<0.01
0.4
0.02
0.2
0.3
0.9
<0.01
<0.01
0.02
<0.01
0.4
0.04
2
<0.01
<0.01
(CONTINUED)
E-12
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
COLLECTION
DATE
1987
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
PCT OF
CONC.
GUIDE
BEATTY, NV
YOUNGHANS RCH
BOULDER CITY NV
LAKE MEAD INTAKE
CLARK STATION NV
WELL 6 TTR
HIKO NV
CRYSTAL SPRINGS
INDIAN SPRINGS NV
WELL 1 SEWER COMPANY
WELL 2 US AIR FORCE
LAS VEGAS, NV
WELL 28 WATER DISTRICT
LATHROP WELLS, NV
CITY 15S-50E-18CDC
NYALA, NV
SHARP'S RANCH
OASIS VALLEY, NV
GOSS SPRINGS
PAHRUMP, NV
WELL 3 CALVADA
RACHEL, NV
HEIZER'S COMPLEX
04/07
05/06
06/02
07/10
08/13
10/07
11/06
03/19
08/14
05/15
10/14
04/08
09/02
01/07
06/02
01/07
06/02
01/12
06/08
01/09
06/04
04/01
09/08
03/12
08/13
05/07
10/16
06/16
160 ± 200*
48 ± 8
0.80 ± 8.1*
9.1 ± 8.9*
10 ± 10*
5.5 ± 9.6*
4.4 ± 9.1*
120 ±9
310 ± 260*
25 ± 8
99 ± 230*
0.67 ± 11*
-140 ± 250*
-2.7 ± 8.6*
-220 ± 250*
9.4 ± 12*
-82 ± 250*
98 ± 210*
0.80 ± 8.0*
3.0 ± 8.6*
330 ± 250*
6.9 ± 8.2*
-37 ± 250*
7.7 ± 8.3*
220 ± 260*
21 ± 8
70 ± 230*
31 ± 8
0.8
0.2
<0.01
0.05
0.05
0.03
0.02
0.6
2
0.1
0.5
<0.01
<0.01
<0.01
<0.01
0.05
<0.01
0.5
<0.01
0.01
2
0.03
<0.01
0.04
1
0.1
0.3
0.2 (1)
(CONTINUED)
E-13
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
~
RACHEL, NV
WELLS 7 AND 8 PENOYER
WELL 13 PENOYER
WELL PENOYER CULINARY
TEMPIUTE, NV
UNION CARBIDE WELL
TONOPAH, NV
CITY WELL
WARM SPRINGS, NV
TWIN SPRINGS RANCH
NTS, NV
WELL 5B
WELL C-l
WELL D TEST
WELL UE1C
WELL UE15D
WELL UE16D
COLLECTION
DATE
1987
04/13
04/13
02/03
07/08
01/13
06/02
05/14
10/15
04/01
09/08
02/06
07/09
02/05
07/08
03/10
08/19
03/10
08/18
02/05
06/10
02/05
07/08
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
.
3.5 ± 8.2*
2.1 ± 8.2*
-0.72 ± 8.4*
100 ± 200*
120 ± 210*
0.81 ± 8.0*
24 ± 8
130 ± 230*
3.1 ± 8.8*
89 ± 250*
35 ± 230*
-5.5 ± 9.5*
73 ± 230*
4.3 ± 9.3*
94 ± 200*
5.9 ± 10*
54 ± 200*
7.0 ± 9.9*
85 ± 230*
-3.2 ± 7.9*
-100 ± 230*
10 ± 9*
PCT OF
CONC.
GUIDE
-
0.01
0.6
<0.01
0.1
0.6
0.02
0.4
0.2
<0.01
0.4
0.02
0.5
0.03
0.3
0.04
0.4
<0.01
<0.01
0.05
E-14
(CONTINUED)
-------
TABLE E.7. CONTINUED
COLLECTION
PIATF
SAMPLING LOCATION
,.
BACKGROUND SAMPLES - AMCHITKA. AK
AMCHITKA AK
CLEVENGER LAKE
CONSTANTINE SPRING
DUCK COVE CREEK
JONES LAKE
RAIN SAMPLE
SITE D HYDRO EXPLORE HOLE
WELL ARMY 1
WELL ARMY 2
WELL ARMY 4
PROJECT CANNIKIN - AMCHITKA, AK
AMCHITKA AK
CANNIKIN LAKE (NORTH END)
CANNIKIN LAKE (SOUTH END)
DECON POND
DECON SUMP
DK-45 LAKE
ICE BOX LAKE
PIT SOUTH OF CANNIKIN GZ
WELL HTH-3
WHITE ALICE CREEK
is i \ i i-*
1987
08/27
08/27
08/27
08/27
08/29
08/29
09/01
08/28
08/27
08/28
08/28
08/28
08/28
08/31
08/31
08/28
08/28
08/28
08/28
08/28
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
_
35 ±8
56 ± 8
29 ± 8
25 ± 8
17 ± 8
15 ± 8
25 + 8
63 ± 8
44 ± 7
26 ± 7
63 ± 7
38 ± 8
37 ± 8
19 ± 9
18 ± 9
38 ± 8
27 ± 8
39 ± 9
29 ± 9
36 ± 8
PCT OF
CONC.
GUIDE
0.2 (2)
0.3
0.1
0.1
0.08
0.08
04
.1
0.3
0.2
0.1
0.3
0.2
0.2
0.09 (3)
0.09
0.2
0.1
0.1
0.1
0.2
(CONTINUED)
E-15
-------
Mile 27 Stream
>
Site E
Constantine Harbor
Duck Cove Cr
Milrow
0 5 10
Scale in Kilometers
Surface Ground Zero
Sampling Locations
Kirilof Point
Constantine Harbor
Engineer's Pit
Constantino Spring
Clevenger Lake\
Engineer Road
t. Makarius;
Bay
Main Camp
Baker Runway
xSouth Hangar
Maintenance Building De Con Pad SumP
De Con Pad Pond
Scale in Miles
0 1
0 1
Scale in Kilometers
Sampling Locations
5/88
Figure E-l. Amchitka Island and background sampling locations for the LTHMP.
E-16
-------
Banjo Point
Bering Sea
5/88 Scale in Kilometers
Surface Ground Zero
Sampling Locations
Figure E-2. LTHMP sampling locations for Project Cannikin.
E-17
-------
TABLE E.7. CONTINUED
~~ ' .
SAMPLING LOCATION
_
PROJECT LONGSHOT - AMCHITKA. AK
AMCHITKA AK
LONG SHOT POND 1
LONG SHOT POND 2
LONG SHOT POND 3
MUD PIT NO.l
MUD PIT NO. 2
MUD PIT NO. 3
REED POND
STREAM EAST OF LONGSHOT
WELL EPA-1
WELL GZ NO. 1
WELL GZ NO. 2
WELL WL-2
PROJECT MILROW - AMCHITKA, AK
AMCHITKA K
CLEVENGER CREEK
HEART LAKE
WELL W-2
WELL W-3
WELL W-4
WELL W-6
WELL W-7
-" _
COLLECTION
DATE
1987
08/28
08/28
08/28
08/28
08/28
08/28
08/28
08/28
08/28
08/28
08/28
08/28
08/27
08/27
08/27
08/27
08/27
08/27
08/27
r- i 1-1
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
25 ± 8
28 ± 8
41 ± 8
250 ± 9
310 ± 9
470 ± 10
28 ± 8
230 ± 9
67 ± 10
2400 ± 230
22 ± 9
76 ± 9
36 ± 9
22 ± 8
26 ± 8
29 ± 8
46 ± 9
41 ± 8
48 ± 8
PCT OF
CONC.
GUIDE
0.1
0.1
0.2
1
2
2
0.1
1
0.3
10
0.1
0.4
0.2
0.1
0.1
0.1
0.2
0.2
0.2
(CONTINUED)
-------
Collapse
Boundary /
\/
/ vx^ j^m vv ^> VJi'-'VJii" v
Sampling Locations
^^i^-ii
Long Shot
/ Long Shot
' Pond #1
Long Shot SGZ
EPA-1
Figure E-3.
6 100
Scale in Meters
^Surface Ground Zero
Sampling Locations
LTHMP sampling locations for Projects Mi Trow and Long Shot,
E-19
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
PROJECT MILROW - AMCHITKA. AK
AMCHITKA K
WELL W-8
WELL W-10
WELL W-ll
WELL W-13
WELL W-14
WELL W-15
WELLS W-5, W-9, W-12 AND
W-16, to W-19 NOT SAMPLED
PROJECT RIO BLANCO - COLORADO
RIO BLANCO CO
B-l EQUITY CAMP
BRENNAN WINDMILL
CER NO.l BLACK SULPHUR
CER NO. 4 BLACK SULPHUR
FAWN CREEK 1
FAWN CREEK 3
FAWN CREEK 6800FT UPSTR
FAWN CREEK 500FT UPSTRE
FAWN CREEK 500FT DOWNST
FAWN CREEK 8400FT DOWNS
WELL JOHNSON ARTESIAN
COLLECTION
DATE
1987
(CONT)
08/27
08/27
08/27
08/27
08/27
08/27
07/25
07/26
07/25
07/25
07/26
07/26
07/26
07/26
07/26
07/26
07/26
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
43 ± 8
33 ± 9
100 ±9
53 ± 8
18 ± 8
18 ±8
96 ± 8
11 ± 8*
90 ± 8
77 ± 8
70 ± 10
56 ± 7
62 ± 8
61 ± 7
120 ± 8
56 ± 8
3.6 ± 8.3*
"* . .- _
PCT OF
CONC.
GUIDE
0.2
0.2
0.5
0.3
0.09
0.09
0.5
0.05
0.5
0.4
0.4
0.3
0.3
0.3
0.6
0.3
0.2
(CONTINUED)
E-20
-------
Johnson
Artesian
awn Cr.
8400' Downstream
Fawn Cr. 500' Downstream
RB-D-01
SGZ
Fawn Cr. 500' Upstream
Fawn Cr. No. 3
Fawn Cr. 6800'
Upstream
Rio Blanco County
Garfield County
Scale in Kilometers
Rio Blanco County
I Surface Ground Zero Q Water Well
Artesian Well A Spring
Windmill Stream
Location Maps
5/88
Figure E-4. LTHMP sampling locations for Project Rio Blanco.
E-21
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
PROJECT RIO BLANCO - COLORADO
RIO BLANCO CO
WELL RB-D-01
WELL RB-D-03
WELL RB-S-03
PROJECT RULISON - COLORADO
GRAND VALLEY, CO
BATTLEMENT CREEK
CITY SPRINGS
ALBERT GARDNER RANCH
SPRING 300 YRDS NW OF G
WELL CER TEST
RULISON, CO
LEE HAYWARD RANCH
POTTER RANCH
ROBERT SEARCY RANCH
FELIX SEFCOVIC RANCH
PROJECT DRIBBLE - MISSISSIPPI
BAXTERVILLE, MS
HALF MOON CREEK
HALF MOON CREEK OVERFLOW
LOWER LITTLE CREEK
POND WEST OF GZ
COLLECTION
DATE
1987
(CONT)
07/25
07/29
07/29
07/27
07/27
07/27
07/27
07/27
07/27
07/27
07/27
07/27
05/07
05/07
05/07
05/07
05/06
05/07
05/07
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
2.8 ± 9.7*
3.3 ± 9.1*
14 ± 8
100 ± 8
-0.13 ± 8.2*
170 ± 8
87 ± 8
160 ± 9
220 ±8
120 ± 8
160 ± 9
170 ± 8
39 ± 8
48 ± 8
46 ± 8
36 ± 8
53 ± 8
34 ± 8
41 ± 8
PCT OF
CONC.
GUIDE
0.01
0.02 (4)
0.07 (5)
0.5
<0.01
0.8
0.4
0.8
1
0.6
0.8
0.8
0.2
0.2
0.2
0.2
0.3
0.2
0.2
(CONTINUED)
E-22
-------
G. Schwab
Rn.
Grand Valley
City Water'
Potter
;Rn.
Rifle
Grand Valley^-
\ 1
A. mJ
Gardner
Rn.
2V
Rulison*
"'J' ^B-Sefcovic R n.
Rn.
Battlement Creek
cER Test Well
Spring© SGZ
Scale in Miles
0 5
N
8
Scale in Kilometers
0 Surface Ground Zero
Water Sampling Locations
Colorado
Garfield
County
Location Maps 5/88
Figure E-5. LTHMP sampling locations for Project Rulison.
E-23
-------
Lower Little Creek
P/. / Salt Dome Timber Co.
. Anderson /
R.King
. Kelly
T. Saucier
B. Chambliss
P.
A
. Anderson
W. Daniels Jr. Purvis
R. Ready
Baxterville
Well Ascot 2
Lumberton
Mississippi / /
5 10 15 20
Scale in Kilometers
Surface Ground Zero
Water Sampling Locations
Location Maps
5/88
Figure E-6. LTHMP sampling locations for Project Dribble
towns and residences.
E-24
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
PROJECT DRIBBLE - MISSISSIPPI
BAXTERVILLE, MS
REECO PIT DRAINAGE A
REECO PIT DRAINAGE-B
REECO PIT DRAINAGE-C
SALT DOME HUNTING CLUB
SALT DOME TIMBER CO.
ANDERSON, B. R.
ANDERSON, H.
ANDERSON, R. L.
CHAMBLISS, B.
DANIELS, W. JR.
KELLY, G.
KING, RHONDA
LEE, P. T.
MILLS, A. C.
MILLS, R.
READY, R.
SAUCIER, T. S.
WELL ASCOT 2
WELL CITY
WELL E-7
COLLECTION
DATE
1987
(CONT)
05/06
05/06
05/06
05/07
05/06
05/07
05/07
05/06
05/06
05/06
05/06
05/06
05/06
05/06
05/06
05/06
05/06
05/06
05/07
05/08
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
27 ± 9
7800 ± 260
550 ± 10
44 ± 8
28 ± 8
29 ± 8
34 ± 8
44 ± 8
7.0 ± 9.6*
38 ± 8
7.3 ± 8.5*
26 ± 8
49 ± 9
1.9 ± 8.4*
45 ± 8
75 ± 8
44 ± 8
39 ± 8
46 ± 8
12 ± 9*
PCT OF
CONC.
GUIDE
0.1
40
3
0.2 (6)
0.1
0.1
0.2
0.2
0.04
0.2
0.04
0.1 (7)
0.2
<0.01
0.2
0.4
0.2
0.2
0.2
0.06
(CONTINUED)
E-25
-------
HMH-5\
Scale in Feet
0 100 200 300
'xlr 4-,
"vk
Half Moon
Creek /
Overflow j
HMH-9
\
/^Ta;
La mar
County
0 50 100
Scale in Meters
Surface Ground Zero
Water Sampling Locations
Tatum
Dome
0SGZ
Location Maps B/BB
Figure E-7. LTHMP sampling locations for Project Dribble - near GZ.
E-26
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
PROJECT DRIBBLE - MISSISSIPPI
BAXTERVILLE, MS
WELL HM-1
WELL HM-2A
WELL HM-2B
WELL HM-3
WELL HM-L
WELL HM-L2
WELL HM-S
WELL HMH-1
WELL HMH-2
WELL HMH-3
WELL HMH-4
WELL HMH-5
WELL HMH-6
WELL HMH-7
WELL HMH-8
WELL HMH-9
WELL HMH-10
COLLECTION
DATE
1987
(CONT)
05/07
05/07
05/07
05/07
05/07
05/07
05/07
05/07
05/07
05/07
05/07
05/07
05/07
05/07
05/06
05/06
05/06
05/06
05/06
05/06
05/06
05/06
05/06
05/06
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
-0.63 ± 9.1*
-1.6 ± 10*
4.6 ± 9.1*
3.3 ± 9.8*
7.1 ± 9.5*
-2.0 ± 9.3*
1.1 ± 9.2*
-2.3 ± 9.1*
1100 ± 210
1400 ±210
-4.2 ± 9.3*
2.5 ± 9.8*
11000 ± 290
11000 ± 43
23000 ± 360
33000 ± 410
58 ± 9
25 ± 8
4700 ± 240
200 ± 10
86 ± 9
120 ± 7
47 ± 9
100 ± 8
PCT OF
CONC.
GUIDE
<0.01
<0.01
0.02
0.02
0.04
<0.01
<0.01
<0.01
6
7
<0,01
0.01
60
60
100
200
0.3
0.1
20
1
0.4
0.6
0.2
0.5
(CONTINUED)
E-27
-------
\( REECOPit-C
fREECOPit-B
iREECOPit-A
Half Moon f \
nt.t
^
Scale in Feet
0 400 1200 2000
HM-2A
Half Moon Creek
Overflow
I
\WellE-7l
0 200 400 600 N
Scale in Meters
0 Surface Ground Zero j£
Water Sampling Locations
WellHT-2C
. j^ vi an »
WellHT-5 ..'* "Cre'ek
WellHT-4..-'*
....'..' Lamar
/ County
*( r~} A~\
Mississippi / / Tatum
1 /x Dome
I0SGZ
/ j
^"\"" 5/88
Location Maps
>./
Figure E-8. LTHMP sampling locations for Project Dribble - near Salt Dome.
E-28
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
PROJECT DRIBBLE - MISSISSIPPI
BAXTERVILLE, MS
WELL HMH-11
WELL HT-2C
WELL HT-4
WELL HT-5
COLUMBIA, MS
WELL 64B CITY
LUMBERTON MS
WELL 2 CITY
PURVIS MS
CITY SUPPLY
PROJECT FAULTLESS - NEVADA
BLUE JAY NV
HOT CREEK RANCH SPRING
MAINTENANCE STATION
WELL BIAS
WELL HTH-1
WELL HTH-2
COLLECTION
DATE
1987
(CONT)
05/06
05/08
05/07
05/08
05/06
05/07
05/06
10/20
10/20
10/20
10/20
10/20
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
410 ± 11
27 ± 8
22 ± 8
-3.4 ± 9.3*
16 ± 9
3.1 ± 9.6*
11 ± 9*
5.2 ± 9.8*
3.7 ± 9.6*
2.8 ± 9.1*
3.6 ± 8.8*
0.68 ± 8.9*
PCT OF
CONC.
GUIDE
2
0.1
0.1
<0.01
0.08
0.02
0.06
0.03
0.03
0.01
0.02
<0.01
(CONTINUED)
E-29
-------
Location Maps
Hot Creek T
Ranch
Scale in Miles
5 10
Scale in Kilometers
Surface Ground Zero
Water Sampling Locations /
5/88
SGZ
HTH 2
|"HTH 1
/
/
I
\
Six-Mile Well
I Jim Bias Well
(Blue Jay Springs)
Blue Jay
Maint Station
Figure E-9. LTHMP sampling locations for Project Faultless,
E-30
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
PROJECT SHOAL - NEVADA
FRENCHMAN STATION NV
HUNT'S STATION
SMITH/ JAMES SPRGS
SPRING WINDMILL
WELL FLOWING
WELL HS-1
PROJECT GASBUGGY - NEW MEXICO
GOBERNADOR NM
ARNOLD RANCH
BIXLER RANCH
BUBBLING SPRINGS
CAVE SPRINGS
CEDAR SPRINGS
LA JARA CREEK
WELL EPNG 10-36
WELL JICARILLA 1
WELL 28.3.33.233 (SO)
POND 30.3.32 (NO)
WINDMILL 2
COLLECTION
DATE
1987
03/03
03/04
03/03
03/03
03/03
07/23
07/23
07/21
07/22
07/22
07/22
07/21
07/22
07/22
07/23
07/22
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
4.4 ± 8.5*
74 ± 8
-0.15 ± 8.3*
1.3 ± 8.3*
0.34 ± 9.3*
9.5 ± 8.7*
23 ± 8
82 ± 10
38 ± 8
73 ± 8
62 ± 8
34 ± 8
-0.96 ± 8.9*
73 ± 8
59 ± 8
8.0 ± 9.4*
PCT OF
CONC.
GUIDE
0.02
0.4
. <0.01
<0.01
<0,01
0.05
0.1
0.4
0.2
0.4
0.3
0.2
<0.01
0.4
0.3
0.04
(8)
(9)
(10)
(CONTINUED)
E-31
-------
Fallen
Scale in Miles
5
Spring
^Windmill
Flowing Well
Hunts
Station
H-3
0
SGZ
HS-1
Smith/James Spring
Churchill County
Mineral County
I
N
0 5 10 15
Scale in Kilometers
Surface Ground Zero
Water Sampling Locations
Churchill
County
5/88
Location Maps
Figure E-10. LTHMP sampling locations for Project Shoal.
E-32
-------
To Dulce
Bixler Rn.
To Blanco &
Gobernador
/
Bubbling
Spring
EPNGWell 10-36
Cedar Spring
Cave Spring
La Jara Creek
m Windmill #2
Jicarilla
Well #1
SGZ
Arnold Rn.
Scale in Kilometers
0 8
0 5
Scale in Miles
N
Lower Burro I
Canyon
Well 28.3.33.233
Surface Ground Zero
Water Sampling Locations
New
Mexico
0SGZ
Rio Arriba
County
Location Maps 5/ss
Figure E-ll. LTHMP sampling locations for Project Gasbuggy.
E-33
-------
Carlsbad
Carlsbad City
Well #7
Loving City
Well #2
Scale in Miles
0 5 10
0 5 10 15
Scale in Kilometers
USGS 4 8
Wells AA
1A
DD-1
LRL-7
PHS Well #6
PHS Well #9|
PHS Well #10r
PHS Well #8
Pecos River
Pumping Station
Well
0 Surface Ground Zero
A On-Site Water Sampling Locations
Off-Site Water Sampling Locations
Eddy County
5/88
Location Maps
Figure E-12. LTHMP sampling locations for Project Gnome.
E-34
-------
TABLE E.7. CONTINUED
SAMPLING LOCATION
PROJECT GNOME - NEW MEXICO
COLLECTION
DATE
iN 1987
"
CONC. ± 2 SIGMA
TRITIUM
(pCi/L)
PCT OF
CONC.
GUIDE
LAKUiDH
WELL
LOVING,
WELL
MALAGA,
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
WELL
U , Nl'l
7 CITY
NM
2 CITY
NM
1 PECOS PUMPING ST
LRL-7
PHS 6
PHS 8
PHS 9
PHS 10
USGS 1
USGS 4
USGS 8
, 05/18
05/18
05/18
05/17
05/16
05/16
05/16
05/16
05/16
05/17
05/17
13
9.7
6.2
16000
64
22
9.9
0.44
1.3
150000
200000
± 9*
±9.1*
± 9.7*
± 320
± 8
± 8
± 10*
± 9.3*
± 9.9*
± 780
± 900
0.
0.
06
05
0.03
80
0
0
0
-------
TABLE E.7. CONTINUED
ANALYSIS
FOOTNOTES (CONT)
RESULT 2SIGMA
(3) 89SR
90SR
238PU
239PU
234U
235U
238U
(4) 89SR
90SR
234U
235U
238U
238PU
239PU
(5) 89SR
90SR
234U
235U
238U
238PU
239PU
(6) 89SR
90SR
238PU
239PU
(7) 89SR
90SR
238PU
239PU
(8) 89SR
90SR
226RA
234U
235U
238U
238PU
239PU
-4.9
1.4
0.007
-0.005
0.012
0.001
0.008
1.5
-0.87
35.5
0.9
9.8
-4.9
-2.4
5.0
-0.80
87
6.2
34
0
-6.4
-35
3.6
0.16
-0.02
-25
1.3
0.009
0.001
-39
2.0
0.15
26
1.3
20
-0.014
-0.009
4.3*
1.8*
0.014*
0.012*
0.012*
0.003*
0.009*
7.4*
2.6*
17.5*
2.5*
9.1*
14.2*
11.6*
8.6*
2.9*
26
7.2*
16
18*
15*
27*
3.1*
0.06
0.05*
26*
2.8*
0.079*
0.065*
57*
2.7*
0.06
1
0.1
0.8
0.026*
0.022*
UNITS
pCi/L
pCi/L
pCi/L
PCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCiVL
fCi/L
fCi/L
fCi/L
fCi/L
fCi/L
pCi/L
pCi/L
fCi/L
fCiVL
fCi/L
fCi/L
fCi/L
pCi/L
pCi/L
pCiVL
pCiVL
pCi/L
pCi/L
pCI/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pdVL
pCiVL
(CONTINUED)
E-36
-------
TABLE E.7. CONTINUED
ANALYSIS
(9) 89SR
90SR
238U
234U
238PU
239PU
(10) 89SR
90SR
234U
235U
238U
238PU
239PU
(11) 137CS
(12) 137CS
FOOTNOTES (CONT)
RESULT 2SIGMA
9.8
-0.4
0.2
0.02
-0.007
0.009
4.7
-0.3
2
0.01
0.8
-0.008
-0.006
200
90
12*
3.9*
0.04*
0.01*
0.013*
0.011*
8.2*
2.6*
0.2*
0.01*
0.8*
0.016*
0.013*
22
15
UNITS
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
pCi/L
E-37
-------
TABLE E.8. SUMMARY OF ANALYTICAL RESULTS FOR THE
MILK SURVEILLANCE NETWORK - 1987
RADIOACTIVITY CONC.
SAMPLING
LOCATION
HINKLEY, CA,
BILL NELSON DAIRY
RIDGECREST, CA,
CEDARSAGE FARM
AUSTIN, NV,
YOUNG'S RANCH
CURRANT, NV,
BLUE EAGLE RANCH
CURRANT, NV,
MANZONIE RANCH
DYER, NV,
OZEL LEMON
GOLDFIELD, NV,
FRAYNE RANCH
LAS VEGAS, NV,
HEIN HETTINGA DRY (LDS)
LATHROP WELLS, NV,
JOHN DEER RANCH
LOGANDALE, NV,
KNUDSEN DAIRY
LUND, NV,
MCKENZIE DAIRY
NO. OF
SAMPLES
4
2
2
4
2
2
4
1
1
2
1
2
3
1
1
RADIO-
NUCLIDE
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
MAX
240
0.15
0.83
170
2.8
0.83
420
-0.78
0.91
300
-2.0
2.0
390
-0.35
0.92
\ p v-» i / l_ /
MIN
37
0.021
0.66
-31
1.7
0.25
170
-0.78
0.91
270
-2.0
1.6
300
-0.35
0.92
AVG
120
0.086
0.74
110
2.3
0.54
280
-0.78
0.91
280
-2.0
1.8
350
-0.35
0.92
3H
3H
420
220
24
190
170
210
4
3
3
2
2
2
6
3
4
4
3
3
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
340
2.8
0.75
340
3.2
-0.12
340
4.7
1.1
120
2.4
0.32
-7.4
0.54
0.37
210
-0.86
-0.94
41
2.0
-1.2
-180
1.7
0.0051
140
2.0
0.57
270
1.2
-0.53
170
3.0
0.038
14
2.0
0.20
(CONTINUED)
E-38
-------
TABLE E.8. CONTINUED
SAMPLING
LOCATION
MCGILL, NY,
LARSEN RANCH
MESQUITE, NV,
SPEDA BROTHERS DAIRY
MOAPA, NV,
ROCKVIEW DAIRIES, INC
NYALA, NV,
SHARP'S RANCH
CALIENTE, NV,
JUNE COX RANCH
ROUND MT, NV,
BERG'S RANCH
SHOSHONE, NV,
HARBECKE RANCH
RACHEL, NV,
PENOYER FARM
CEDAR CITY, UT,
BRENT JONES DAIRY
ST GEORGE, UT,
CANNON FARMS
NO. OF
SAMPLES
1
1
1
4
3
3
6
2
2
5
4
4
4
2
2
3
1
1
4
2
3
5
1
2
3
1
2
3
2
2
RADIO-
NUCLIDE
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
3H
89SR
90SR
RADIOACTIVITY CONC.
(pCi/L)
MAX
550
-5.5
1.6
180
1.8
1.7
420
1.7
0.64
290
2.5
1.2
330
7.6
0.54
250
6.3
-1.2
540
0.70
0.47
360
-0.53
0.82
390
1.1
0.74
310
2.4
0.85
MIN
550
-5.5
1.6
4.9
-8.2
0.010
0.0
0.93
0.60
79
-1.6
0.54
87
-0.35
-1.3
94
6.3
-1.2
150
-0.55
0.40
-48
-0.53
0.21
AVG
550
-5.5
1.6
91
-1.6
0.67
190
1.3
0.62
140
0.83
0.74
190
3.6
-0.35
170
6.3
-1.2
310
0.074
0.44
110
-0.53
0.52
100 230
1.1 1.1
7.1E-10 0.37
68
0.013
0.38
210
1.2
0.62
E-39
-------
TABLE E.9. ANALYTICAL RESULTS FOR THE STANDBY MILK SURVEILLANCE
NETWORK - 1987
COLLECTION
SAMPLING LOCATION 1937
GAMMA SPECTROMETRY
TAYLOR AZ
SUNRISE DAIRY
TUCSON AZ-SHAMROCK FOODS-
LITTLE ROCK AR
BORDENS
RUSSELLVILLE AR
ARKANSAS TECH UNIV
BAKERSFIELD CA
CARNATION DAIRY
WEED CA
MEDO-BEL CREAMERY
WILLOWS CA-GLENN MILK PRO
GRAND JCT CO
COLORADO WEST DAIRIES
CANON CITY CO-JUNIPER VAL
BURLINGTON IA
MISS VALLEY MILK PRO
DAVENPORT IA
SWISS VALLEY FARMS CO
ATWOOD KS-ATWOOD-CHEESE C
AURORA MO
MTn-AMFPTPA nflTDV TMr
08/10
08/10
08/03
08/03
08/10
08/10
08/24
07/23
08/07
07/22
08/11
08/10
07/20
-"- - ._
CONC. ± 2 SIGMA
3H 89SR
(pCi/L) (pCi/L)
- _._
90SR
(pCi/L)
AND RADIOCHEMICAL ANALYSES
340 ± 260* NA
78 ±
79 ±
64 ±
180 ±
160 ±
190 ±
190 ±
430 ±
30 ±
110 ±
250 ±
170 ±
270* -1.3 ± 6.6*
280* NA
280* NA
270* NA
260* 0.56 ± 4.4*
280* NA
270* NA
230 NA
260* NA
260* NA
270* NA
270* NA
NA
0.74 ± 2.1*
NA
NA
NA
0.25 ± 1.4*
NA
NA
NA
NA
NA
NA
NA
CHILLICOTHE MO 07/21 390 ± 240 NA NA
MID-AMERICA DAIRYMEN NA
(CONTINUED)
E-40
-------
TABLE E.9. CONTINUED
SAMPLING LOCATION
COLLECTION
DATE
1987
CONC. ± 2 SIGMA
3H 89SR
(pCi/D (pCi/L)
GAMMA SPECTROMETRY AND RADIOCHEMICAL ANALYSES
NORFOLK NE 07/29 210 ± 270* NA
GILLETTE DAIRY
FALLON NV 08/10
CREAMLAND DAIRY
ENID OK 08/10
AMPI GOLDSPOT DIVISION
MCALESTER OK 08/11
OK STATE PENITENTIARY
CORVALLIS OR 07/27
SUNNY BROOK DAIRY
PROVO UT 08/04
BYU DAIRY PRODUCTS LAB
SEATTLE WA 08/06 210 ± 280* NA
CONSOLIDATED DAIRY PROD
NA 0.088 ± 3.9*
180 ± 270* -1.9 ± 6.0*
220 ± 260* NA
340 ± 270* NA
98 ± 260* -1.6 ± 4.8*
90SR
(pCl/L)
NA
0.51 ± 1.3*
1.6 ± 1.8*
NA
NA
0.97 ± 1.5*
NA
COLLECTION
DATE
SAMPLING LOCATION 1987 SAMPLING LOCATION
COLLECTION
DATE
1987
PIMA AZ
PIMA DAIRY
POTASSIUM-40 WAS THE ONLY GAMMA EMITTER DETECTED
AT THE FOLLOWING LOCATIONS
08/10
TEMPE AZ 08/10
UNITED DAIRYMEN OF AZ
BATESVILLE AR
HILLS VALLEY FOODS
FAYETTEVILLE AR
UNIVERSITY OF ARK
08/03
08/03
(CONTINUED)
E-41
-------
TABLE E.9. CONTINUED
SAMPLING LOCATION
COLLECTION
DATE
1987
SAMPLING LOCATION
POTASSIUM-40 HAS THE ONLY GAMMA EMITTER DETECTED
AT THE FOLLOWING LOCATIONS
YUMA AZ-COMBS DAIRY 08/11
08/11
FERNBRIDGE CA
HUMBOLDT CREAMERY
MANTECA CA-EAST STAR DAIRY 08/10
08/10
MODESTO CA
FOSTER FARMS DAIRY
OXNARD CA 08/12
CHASE BROS DAIRY
REDDING CA 08/10
MCCOLL'S DAIRY PROD
SAN LUIS OBISPO CA 08/10
CAL STATE POLY
SEBASTOPOL CA 08/10
WM MILLER DAIRY
SMITH RIVER CA 08/10
COUNTRY MAID DAIRY
SOLEDAD CA-CORRECTION TRA 08/10
TRACY CA 08/12
DEUEL VOC INST
COLORADO SPGS CO 07/29
SINTON DAIRY CO
FT COLLINS CO 07/22
POUDRE VALLEY DAIRY
KIMBALLTON IA 07/27
AMPI RECEIVING STA
LAKE MILLS IA
LAKE MILLS COOP CRMY
LEMARS IA
WELLS DAIRY
FOSSTON MN
LAND 0' LAKES INC
NICOLLET MN
DOUG SCHULTZ FARM
ROCHESTER MN
ASSC MILK PRODUCERS
JACKSON MO
MID-AMERICA DAIRYMEN IN
JEFFERSON CITY MO
CENTRAL DAIRY CO
BOZEMAN MT
DARIGOLD FARMS
GREAT FALLS MT
MEADOW GOLD DAIRY
MISSOULA MT
BEATRICE DAIRY PRODUCTS
GD ISLAND NE
MID-AMER DAIRYMN-JIM SA
NO PLATTE NE
MID-AMER DAIRYMEN-R A N
OMAHA NE
ROBERTS DAIRY-MARSHALL
COLLECTION
DATE
1987
07/28
07/27
08/26
08/26
08/26
07/22
07/20
07/27
07/29
07/21
08/05
07/31
09/02
(CONTINUED)
E-42
-------
TABLE E.9. CONTINUED
SAMPLING LOCATION
COLLECTION
DATE
1987
SAMPLING LOCATION
COLLECTION
DATE
1987
POTASSIUM-40 HAS THE ONLY GAMMA EMITTER DETECTED
AT THE FOLLOWING LOCATIONS
SUPERIOR NE
MID-AMER DAIRYMN-D FRIT
08/11
LAS VEGAS NV 08/10
ANDERSON DAIRY
RENO NV 08/10
MODEL DAIRY
YERINGTON NV 08/12
VALLEY DAIRY
CLAREMORE OK 08/03
SWAN BROS DAIRY
STILLWATER OK 08/03
OSU DAIRY
EUGENE OR 07/27
ECHO SPRINGS DAIRY
GRANTS PASS OR 07/27
VALLEY OF ROGUE DAIRY
KIAMATH FALLS OR-KLAMATH 07/27
MEDFORD OR 07/29
DAIRYGOLD FARMS
MILTON-FREEWATER OR 07/27
PARENTS DAIRY
MYRTLE POINT OR 08/03
SAFEWAY STORES INC
PORTLAND OR 07/29
DARIGOLD FARMS
REDMOND OR 07/28
EBERHARD'S CREAMERY INC
TILLAMOOK OR 07/20
TILLAMOOK CO CRMY
RAPID CITY SD-GILLETTE DA 08/05
BEAVER UTAH-WESTERN DAIRY 07/23
RICHFIELD UT 07/28
IDEAL DAIRY
MOSES LAKE WA 08/24
SAFEWAY STORES INC
SPOKANE WA 08/24
CONSOLIDATED DAIRY
CHEYENNE WY 08/05
DAIRY GOLD FOODS
RIVERTON WY-CREME 0'WEBER 07/29
* CONCENTRATION IS LESS THAN THE MINIMUM DETECTABLE CONCENTRATION (MDC).
E-43
-------
TABLE E.10. SUMMARY OF RADIATION DOSE EQUIVALENTS FROM TLD DATA - 1987
STATION
LOCATION
ALAMO, NV
AMERICAN BORATE, NV
ATLANTA MINE, NV
AUSTIN, NV
BAKER, CA
BARSTOW, CA
BATTLE MOUNTAIN, NV
BEATTY, NV
BISHOP, CA
BLUE EAGLE RANCH, NV
BLUE JAY, NV
BOULDER, UT
BRYCE CANYON, UT
CACTUS SPRINGS, NV
CALIENTE, NV
CARP, NV
CEDAR CITY, UT
CHERRY CREEK, NV
CLARK STATION, NV
COALDALE, NV
COLORADO CITY, AZ
MEASUREMENT PERIOD
ISSUE COLLECT
11/06/86
11/06/86
12/01/86
01/15/87
12/01/86
12/01/86
12/03/86
11/04/86
12/02/86
12/02/86
01/15/87
12/09/86
12/09/86
11/03/86
11/06/86
11/06/86
11/05/86
12/02/86
01/14/87
12/04/86
11/04/86
10/30/87
01/07/88
12/07/87
02/03/88
11/03/87
11/03/87
12/15/87
01/05/88
11/04/87
01/05/88
01/06/88
12/08/87
12/08/87
11/02/87
10/27/87
10/27/87
12/07/87
12/10/87
01/04/88
02/09/88
10/27/87
E-44
DOSE
EQUIVALENT RATE
(mrem/D)
MAX. MIN. AVG.
0.30 0.24 0.27
0.38 0.17 0.28
0.26 0.16 0.23
0.44 0.27 0.35
0.32 0.21 0.26
0.33 0.23 0.27
0.25 0.17 0.22
0.40 0.19 0.30
0.33 0.22 0.28
0.24 0.13 0.19
0.40 0.28 0.35
0.26 0.16 0.21
0.25 0.14 0.19
0.23 0.12 0.18
0.33 0.25 0.29
0.34 0.20 0.26
0.22 0.18 0.20
0.33 0.24 0.29
0.38 0.22 0.29
0.32 0.23 0.27
0.24 0.17 0.20
ANNUAL
DOSE
EQUIVALENT
(mrem/Y)
98
102
84
127
93
100
82
109
101
70
126
78
71
64
107
95
73
106
106
99
75
(CONTINUED)
-------
TABLE E.10. CONTINUED
DOSE
MEASUREMENT PERIOD
STATION
LOCATION
COMPLEX 1, NV
CORN CREEK, NV
CORTEZ RD/HWY 278, NV
COYOTE SUMMIT, NV
CRESCENT VALLEY, NV
CRYSTAL, NV
CURRANT, NV
CURRIE, NV
DEATH VALLEY JCT, CA
DELTA, UT
DIABLO MAINT STA, NV
DUCHESNE, UT
DUCKWATER, NV
ELGIN, NV
ELKO, NV
ELY, NV
ENTERPRISE, UT
EUREKA, NV
FALLON, NV
PERRON, UT
FLYING DIAMND CP, NV
ISSUE
-
12/03/86
11/03/86
12/03/86
12/28/86
12/03/86
11/06/86
12/02/86
12/02/86
11/06/86
01/08/87
01/13/87
01/06/87
12/02/86
11/06/86
12/02/86
12/02/86
11/05/86
01/15/87
12/03/86
11/06/86
12/04/86
COLLECT
10/28/87
11/02/87
12/15/87
10/28/87
12/15/87
11/05/87
01/06/88
12/10/87
01/07/88
01/05/88
01/04/88
01/07/88
01/06/88
10/27/87
12/15/87
12/09/87
12/07/87
01/06/88
12/14/87
10/29/87
10/30/87
EQUIVALENT RATE
(mrem/D)
MAX. MIN.
0.33
0.17
0.33
0.37
0.27
0.27
0.35
0.33
0.28
0.23
0.40
0.20
0.33
0.42
0.24
0.25
0.37
0.35
0.24
0.26
0.23
0.26
0.08
0.25
0.32
0.19
0.20
0.26
0.24
0.07
0.13
0.26
0.10
0.25
0.31
0.17
0.17
0.33
0.20
0.15
0.16
AVG.
- "-
0.30
0.13
0.30
0.35
0.24
0.23
0.30
0.29
0.20
0.20
0.35
0.17
0.29
0.36
0.22
0.22
0.35
0.28
0.21
0.20
0.15 0.20
ANNUAL
DOSE
EQUIVALENT
(mrem/Y)
_
108
48
110
128
86
85
111
107
74
71
127
62
106
132
79
82
128
104
77
74
72
(CONTINUED)
E-45
-------
TABLE E.10. CONTINUED
STATION
LOCATION
FURNACE CREEK, CA
GABBS, NV
GARRISON, UT
GEYSER RANCH, NV
GOLDFIELD, NV
GRANTSVILLE, UT
GREEN RIVER, UT
GROOM LAKE-NTS, NV
GUNNISON, UT
HANCOCK SUMMIT,NV
HIKO, NV
HOT CK RNCH, NV
IBAPAH, UT
INDEPENDENCE, CA
INDIAN SPRINGS, NV
JACOB'S LAKE, AZ
KANAB, UT
KIRKEBY RANCH, NV
KOYEN'S RANCH, NV
LAS VEGAS (UNLV), NV
LAS VEGAS (USDI), NV
MEASUREMENT PERIOD
ISSUE
11/06/86
12/04/86
12/01/86
12/01/86
01/12/87
01/08/87
11/06/86
12/28/86
11/06/86
12/28/86
11/06/86
01/15/87
12/01/86
12/02/86
11/03/86
11/04/86
11/04/86
12/01/86
12/28/86
12/31/86
12/31/86
COLLECT
-.
01/07/88
02/09/88
12/08/87
12/07/87
02/08/88
01/06/88
10/28/87
11/05/87
12/08/87
10/29/87
10/29/87
01/06/88
12/08/87
11/04/87
11/02/87
10/27/87
10/27/87
12/07/87
10/28/87
01/04/88
01/04/88
DOSE
EQUIVALENT RATE
(mrem/D)
MAX.
_
0.26
0.24
0.22
0.32
0.30
0.22
0.28
0.28
0.25
0.43
0.25
0.30
0.33
0.30
0.19
0.39
0.20
0.24
0.28
0.16
0.22
MIN.
0.03
0.15
0.13
0.22
0.16
0.12
0.17
0.19
0.16
0.41
0.17
0.17
0.15
0.20
0.14
0.28
0.15
0.13
0.24
0.10
0.16
AVG.
0.16
0.19
0.19
0.28
0.23
0.18
0.22
0.25
0.20
0.42
0.21
0.24
0.28
0.27
0.17
0.32
0.17
0.20
0.26
0.13
0.18
.
ANNUAL
DOSE
EQUIVALENT
(mrem/Y)
. .
58
69
70
104
84
67
79
91
73
154
77
89
101
98
61
116
63
73
96
49
67
(CONTINUED)
E-46
-------
TABLE E.10. Continued
MEASUREMENT PERIOD
STATION
LOCATION
LAS " VEGAS(AIRPRT),NV
LATHROP WELLS, NV
LAVADA'S MARKET, NV
LIDA, NV
LOA, UT
LOGAN, UT
LONE PINE, CA
LOVELOCK, NV
LUND, NV
LUND, UT
MAMMOTH LAKES, CA
MANHATTAN, NV
MESQUITE, NV
MILFORD, UT
MINA, NV
MOAPA, NV
MONTICELLO, UT
MTN MEADOWS RNCH, NV
NASH RANCH, NV
NEPHI, UT
NYALA, NV
ISSUE
12/31/86
11/03/86
11/07/86
01/14/87
12/09/86
01/06/87
12/02/86
12/03/86
12/02/86
12/01/86
12/02/86
01/15/87
11/04/86
12/01/86
12/04/86
11/04/86
11/05/86
01/14/87
12/04/86
01/05/87
01/14/87
COLLECT
01/04/88
01/05/88
01/05/88
02/11/88
12/08/87
01/05/88
11/04/87
12/15/87
12/09/87
12/07/87
11/05/87
02/03/88
10/30/87
12/09/87
02/09/88
10/27/87
10/28/87
01/05/88
10/30/87
01/05/88
01/05/88
DOSE
EQUIVALENT RATE
(mrem/D)
MAX. MIN. AVG.
0.18
0.35
0.33
0.30
0.37
0.24
0.32
0.23
0.28
0.33
0.35
0.42
0.20
0.27
0.29
0.22
0.34
0.24
0.25
0.20
0.27
0.14
0.11
0.09
0.17
0.27
0.20
0.19
0.22
0.17
0.24
0.19
0.27
0.13
0.17
0.22
0.16
0.22
0.11
0.18
0.10
0.15
0.16
0.24
0.23
0.23
0.32
0.22
0.27
0.23
0.24
0.28
0.30
0.34
0.17
0.22
0.25
0.20
0.27
0.18
0.22
0.16
0.23
ANNUAL
DOSE
EQUIVALENT
(mrem/Y)
'
58
88
82
85
117
79
97
83
87
104
110
124
63
82
92
73
97
66
79
59
82
(CONTINUED)
E-47
-------
TABLE E.10. CONTINUED
STATION
LOCATION
OLANCHA, CA
OVERTON, NV
PAGE, AZ
PAHRUMP, NV
PAROWAN, UT
PENOYER FARMS, NV
PINE CREEK RANCH, NV
PIOCHE, NV
PRICE, UT
PROVO, UT
QUEEN CITY SMT, NV
RACHEL, NV
REED RANCH, NV
RENO, NV
RIDGECREST, CA
ROSE RANCH, NV
ROUND MT, NV
RUBY VALLEY, NV
S DESERT COR CTR, NV
SALT LAKE CITY, UT
SCHURZ, NV
MEASUREMENT PERIOD
ISSUE
"
12/01/86
11/04/86
12/28/86
11/06/86
12/02/86
12/28/86
12/03/86
12/04/86
12/28/86
01/06/87
01/13/87
12/28/86
01/13/87
10/19/87
12/01/86
12/01/86
01/15/87
12/02/86
11/03/86
11/06/86
12/04/86
COLLECT
... .
11/04/87
10/27/87
10/28/87
11/03/87
12/07/87
10/28/87
10/28/87
10/27/87
10/29/87
01/05/88
01/04/88
10/28/87
01/04/88
12/14/87
11/03/87
03/02/87
02/03/88
12/17/87
11/02/87
01/04/88
12/14/87
DOSE
EQUIVALENT RATE
(mrem/D)
MAX. MIN.
-
0.30 0.21
0.20 0.14
0.18 0.15
0.19 0.14
0.24 0.15
0.35 0.31
0.37 0.30
0.25 0.19
0.20 0.17
0.22 0.11
0.41 0.30
0.34 0.28
0.90 0.24
0.24 0.24
0.29 0.18
0.26 0.26
0.35 0.23
0.32 0.25
0.19 0.14
0.32 0.22
0.30 0.18
AVG.
0.26
0.18
0.17
0.16
0.20
0.33
0.33
0.22
0.19
0.18
0.37
0.32
0.45
0.24
0.24
0.26
0.29
0.30
0.16
0.25
0.26
ANNUAL
DOSE
EQUIVALENT
(mrem/Y)
97
64
60
58
71
121
122
82
69
66
133
115
166
88
89
94
106
110
59
92
97
(CONTINUED)
E-48
-------
TABLE E.10. CONTINUED
STATION
LOCATION
SCOTTY'S JCT, NV
SHERI'S RANCH, NV
SHOSHONE, CA
SILVER PEAK, NV
SPRINGDALE, NV
ST. GEORGE, UT
STEWARD RANCH, NV
STONE CABIN RNCH, NV
SUNNYSIDE, NV
TEMPIUTE, NV
TIKABOO VALLEY, NV
TONOPAH TEST RNG, NV
TONOPAH, NV
TROUT CREEK, UT
TWIN SPRGS RNCH, NV
UHALDE'S RNCH, NV
USECOLOGY, NV
VALLEY CREST, CA
VERNAL, UT
VERNON, UT
WARM SPRINGS, NV
MEASUREMENT PERIOD
ISSUE
01/12/87
11/07/86
11/06/86
04/09/87
11/05/86
11/05/86
03/02/87
01/14/87
12/04/86
12/28/86
12/28/86
01/13/87
01/15/87
12/01/86
01/14/87
12/03/86
11/07/86
11/06/86
01/06/87
01/08/87
01/14/87
COLLECT
01/06/88
10/30/87
11/03/87
02/09/88
01/06/88
12/09/87
12/07/87
01/05/88
12/09/87
10/29/87
10/28/87
02/10/88
02/09/88
12/08/87
01/05/88
10/28/87
01/06/88
01/07/88
01/07/88
01/06/88
01/04/88
DOSE
EQUIVALENT RATE
(mrem/D)
MAX.
0.36
0.34
0.26
0.26
0.40
0.18
0.35
0.38
0.19
0.33
0.33
0.39
0.36
0.25
0.35
0.34
0.43
0.20
0.22
0.24
1.11
MIN. AVG.
0.16
0.20
0.22
0.19
0.17
0.13
0.35
0.22
0.11
0.29
0.30
0.21
0.24
0.17
0.24
0.27
0.17
0.00
0.12
0.14
0.34
0.26
0.28
0.24
0.24
0.29
0.16
0.35
0.31
0.17
0.31
0.32
0.32
0.30
0.22
0.31
0.31
0.30
0.11
0.18
0.20
0.80
ANNUAL
DOSE
EQUIVALENT
(mrem/Y)
97
101
86
87
106
59
128
113
60
114
116
118
110
81
113
114
108
41
66
72
291
(CONTINUED)
E-49
-------
TABLE E.10. CONTINUED
STATION
LOCATION
WELLS, NV
WENDOVER, UT
WILLOW SPRGS LDGE,UT
WINNEMUCCA, NV
YOUNG'S RANCH, NV
MEASUREMENT PERIOD
ISSUE COLLECT
12/02/86
12/01/86
01/08/87
12/03/86
01/15/87
DOSE
EQUIVALENT RATE
(mrem/D)
MAX. MIN. AVG.
12/16/87 0.26 0.18 0.24
12/16/87 0.22 0.15 0.20
01/06/88 0.20 0.09 0.16
12/15/87 0.26 0.18 0.24
02/03/88 0.33 0.18 0.28
ANNUAL
DOSE
EQUIVALENT
(mrem/Y)
86
73
59
87
101
E-50
-------
ADDENDUM
NONRADIOLOGICAL SUPPLEMENT TO THE NTS ENVIRONMENTAL MONITORING REPORT
Prepared by
Industrial Hygiene
Reynolds Electrical and Engineering Co., Inc.
Calendar Year 1987
INTRODUCTION
Nonradiological environmental compliance is primarily the responsibility
of the Industrial Hygiene Section of the Environmental Sciences Department,
REECo. Among State and Federal regulations of concern are the Clean Water Act;
Safe Drinking Water Act (SDWA); Clean Air Act; Resource Conservation and
Recovery Act (RCRA); Comprehensive Environmental Response, Compensation and
Liability Act (CERCLA); Toxic Substances Control Act (TSCA); and The Solid
Waste Disposal Act. Many of the activities regulated by these laws require
a permit or notification to operate. The permits or notification to operate
are processed by the Industrial Hygiene Section.
Collecting and analyzing environmental samples is another very important
Industrial Hygiene Section environmental function. Many different types of
samples were collected during CY87, with most of them being analyzed by the
Industrial Hygiene Laboratory. However, some hazardous waste and drinking
water samples must be sent off site for analysis, because they must be per-
formed by an EPA or State approved laboratory. Several new laboratory instru-
ments purchased this last year should allow the Industrial Hygiene Environ-
mental Laboratory to perform all required environmental analyses by the end
of FY88 It is anticipated that EPA Contract Laboratory Equivalency and State
certification of the Industrial Hygiene Environmental Laboratory will be
achieved within a two year-period (1990).
This report provides CY87 information on the status of environmental
permits, environmental sampling performed, and the results of State and
Federal inspections.
SUMMARY
During 1987 the NTS was inspected by the State and Federal authorities
for compliance with the Clean Air Act and RCRA. No violations were issued by
the State as a result of their air pollution inspection, but four deficiencies
were noted during the EPA RCRA inspection.
Add-1
-------
a ! FoVrJee" "wage lagoon permit applications were submitted to the State
S HPW , lnf°r;rna,tlon on 41 existing septic tank and leachfield systems
Six new air pollution permits were obtained, to bring REECo's total to 25
The six drinking water systems were permitted for another year, and a current
Part A application for mixed waste disposal was amended. current
annnv * t0 lfuPP-ort the RCRA' CERCLA and TSCA programs, and
annual CY reports were submitted to the State for Air Pollution Permits
Hazardous Waste Generation, and polychlorinated biphenyl (PCB) activity.
CLEAN WATER ACT
Sewage Lagoons
for thpTl?il,P?11CJt10JS W6re pre?ared and submitted to the State of Nevada
tor the following fourteen sewage lagoon systems:
1. Area 2
2. Area 6, CP Compound
3. Area 6, Yucca Lake
4. Area 6, DAF
5. Area 6, CP-72
6. Area 11, Technical Support Facility
7. Area 12, Sewage Plant
8. Area 12, Fleet Operations
9. Area 23, Gate 100
10. Area 23, Mercury
11. Area 25, Central Support
12. Area 25, Engine Test Stand
13. Area 25, Test Cell C
14. Area 25, Reactor Control Point
Water samples were collected from the Area 11 and Area 12 Fleet Operations
systems and analyzed for lead, silver and PH (the hazardous waste threshold
for lead and silver is 5 mg/L or greater; the pH is hazardous if less than
2 or greater than 12.5). The pH for both samples was 7.5. Concentrations
0.02 '' S
Septic Tank's and Leachfields
ioa,-?n WaS Provi'ded to the state < 41 existing septic tanks and
leachfield systems. The State will now advise through DOE/NV which, if any
systems will require permit applications. An application for a permit must
be made for all new systems to be constructed; however, most existing systems
will_be permitted by "grandfather action" without a specific application for
permit. No applications for new septic tank systems were submitted.
Permit Status
_No permits were issued by the State for either the sewage lagoons for the
septic tank systems, and there are no previously permitted systems.
Add-2
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DRINKING WATER
Drinking Water Systems Overview
There are currently six drinking water systems, which utilize eleven
wells. The Areas 2, 12, and 23 systems are community systems; while Area 2, 3,
6, and 25 are non-community systems. Community systems sypply residential
populations, while non-community systems supply non-residential workplace
areas. These systems are all chlorinated by automatic equipment. New or
repaired water lines are superchlorinated before being put into service in
accordance with American Water Works Association Standards and the Uniform
Plumbing Code. Each system is tested monthly for pH, residual chlorine, and
bacteria content by Industrial Hygiene Section personnel; and daily chlorine
levels are logged by Site Maintenance personnel (Site Maintenance operates
the water systems). A water sample for chemical analysis is collected from
each well by the Nevada State Health Division at approximately three-year
intervals. These chemical analyses were last performed August 1984, and are
scheduled again for March 1988.
Permit Status
Each of the six systems has a permit from the State of Nevada which is
renewed annually. There were no new permits issued this year, and no amend-
ments were made to any of the existing permits.
Sample Results and Standards Comparison
All systems are sampled monthly for pH, chlorine residual, and bacteria.
In all cases the sample results were within the limits prescribed by the SDWA
and State of Nevada regulations.
residual chlorine - at least 0.02 ppm
pH - between 6.5 and 8.5
coliform bacteria - <2.2 colonies/100 mL of sample
The table below gives the results of the August 1984 analysis of the
community systems wells, and compares the results to the SDWA standards where
one exists.
LAST CHEMICAL ANALYSIS OF COMMUNITY SYSTEMS, AUGUST 1984
Area 23 System
Chemical Analysis
Performed
Calcium
Magnesium
Maximum Level
Allowed
'
Army
Well
45.4
21.4
5B
7.4
2.2
5C
0.7
0.2
Areas
2, 8, 12
7.8
1.2
(continued)
Add-3
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LAST CHEMICAL ANALYSIS OF COMMUNITY SYSTEMS, AUGUST 1984 Continued
Area 23 System
Chemical Analysis
Performed
pH
Alkalinity
Sulfate
Chloride
Nitrate
Fluoride
Iron
Manganese
Total Dissolved
Solids
Arsenic
Lead
Selenium
Barium
Zinc
Copper
Mercury
Chromium
Cadmium
Silver
Turbidity
Color
Maximum Level
Allowed
V IB
--
250 mg/L
250 mg/L
10 mg/L
1.6 mg/L
0.3 mg/L
0.05 mg/L
500 units
.05 mg/L
.05 mg/L
.01 mg/L
1 mg/L
5 mg/L
1 mg/L
.002 mg/L
.05 mg/L
.01 mg/L
.05 mg/L
--
15 units
Army
Well
7.6
222
23.6
16
0.2
1.1
<.030
.024
310
.006
<.002
<.001
.08
<.007
<.007
<.0003
<.029
<.007
<.005
.15
<3
5B
8.5
152
28
23
2.8
0.9
.048
<.012
325
.006
<.002
.001
<.012
<.007
<.007
.0007
<.029
.003
.009
.35
<3
5C
8.9
262
13.5
9
1.6
1.0
<.030
<.012
374
.01
<.002
<.001
<.012
<.007
<.007
<.0003
<.029
<.003
<.005
.25
3
Areas
2, 8, 12
7.3
67
8.3
6
1.3
0.8
.043
.019
152
<.001
<.002
.002
<.012
.012
<.007
<.0003
<.029
.005
.010
0.2
<3
These sample results show that no analyte
allowed levels when the community systems were
Inspector.
exceeded the
last sampled
SDWA maximum
by the State
Non-community systems need only to meet the nitrate levels of no more
than 10 mg/L. All of the NTS systems were below that level when last tested
in 1984.
Quality Assurance
i^ua i i oj nooui uiiuc
The monthly samples are collected in containers supplied by the State and
are delivered to a State approved laboratory for analysis. Both the Collec-
tion and transportation of the samples are performed by a registration eligible
Sanitarian. Nevada does not currently have a registered Sanitarian program,
but is in the process of establishing one. REECo Sanitarians will become State
Registered when the program is in place.
The three-year chemical samples were collected by a State Environmental
Add-4
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Health Specialist and taken to a State approved laboratory. These laboratories
have approved QA programs as part of their State certification.
If any of the analytes are found to be outside the acceptable range,
prompt remedial action is taken to correct the problem. These remedial actions
and their results are then reported back to the State.
AIR POLLUTION
Permit Status
During CY87 two operating permits and four registration certificates were
obtained from the State of Nevada,. Three of the registration certificates
were for cafeteria boilers added to Area 12 (1) and Area 23 (2). One operat-
ing permit was a renewal of a one-year open burning permit for fire training
exercises, and the other was for the Area 1 Aggregate Plant, which was moved
from Area 5. .The fourth registration certification was for a NTS site-wide
surface disturbance permit. The surface disturbance permit requires an annual
report of all disturbances of five acres or greater. Notification prior to
starting the disturbance is not required. The following list gives all air
pollution permits which were active at the end of CY87 for which REECo had
responsibility for compliance with the permit restrictions.
Permit Number
Facility or Operation
Exp. Date
OP919
OP921
OP922
OP925
OP928
OP957
OP958
OP1035
OP1036
OP1082
OP1084
OP1085
OP1086
OP1087
OP1089
OP1090
OP1217
OP1287
OP88-3
RC 974
RC 1122
RC 1367
RC 1524
RC 1525
RC 1526
Area 3 Portec Aggregate Hopper
Area 1 Shaker Plant
Area 1 Rotary Dryer
Area 23, Bldg. 753 Boiler
Area 12 Concrete Batch Plant
Area 2 Portable Stemming
Area 2 Portable Stemming System
Portable Boiler
Area 6 Decon Boiler
Area 1 Concrete Batch Plant
Area 1 Shaker Surface
Area 6 Diesel Tanks
Mercury Gasoline Tank
Mercury Diesel Tank
Area 3 Portable Stemming System
Area 6 Gasoline Tank
Area 1 Portable Crusher
Area 1 Aggregate Plant
Open Burning for Training Exercises
Area 6 DAF Surface Disturbanc
Area 14 Surface Disturbance
NTS Surface Disturbance
Mercury Cafeteria Boiler
Mercury Cafeteria Boiler
Area 12 Cafeteria Boiler
12-03-89
12-03-89
12-03-89
12-03-89
12-03-89
12-03-89
12-03-89
10-20-90
10-20-90
01-30-91
01-30-91
02-25-91
02-25-91
02-25-91
02-25-91
02-25-91
12-03-89
02-12-92
09-30-88
_ _
_ _
_ _
_ _
_ .
--
Add-5
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A report was sent to the State of Nevada on April 15, 1987 which gave the
CY86 operating hours and cubic yards produced under those permits which have
that reporting requirement (permits number 919, 922, 923, 928, 1082, 1217, and
1287). None of the operating restrictions were exceeded. The CY87 report will
be sent in 1988, and will again indicate that no restrictions were exceeded.
Inspection Results
The State of Nevada conducted an inspection of the NTS facilities on
January 14 and 15, 1987. No violations were observed, and no Notice of
Violation was issued as a result of their inspection. However, the issue of
not using water to control the dust from downhole stemming material was raised
regarding the Shaker Plant and Area 3 Portable Stemming Facility. The question
will be resolved by the State during their next inspection in CY88.
RCRA ACTIVITIES
Permit Status and Inspection
REECo has been assigned EPA Generator Identification Number NV3890090001,
and is responsible for the offsite disposal of all hazardous waste generated at
the NTS. One off-site shipment of hazardous waste was made on June 16, 1987;
the required Hazardous Waste Generator Annual Report was sent to the State of
Nevada on February 27, 1987.
On February 11, the EPA conducted a RCRA compliance inspection of the NTS
and found four deficiencies:
1. Hazardous waste being temporarily stored greater than 90 days.
2. Insufficient separation between incompatible materials in storage.
3. Storage waste needs protection from the sun.
4. The Closure Plan for Area 23 Hazardous Waste Disposal Site had not
been completed.
Item 1 was corrected by obtaining a continuous use contract with a dis-
posal firm to ensure prompt off-site shipment. A proper facility for temporary
storage while awaiting off-site shipment is scheduled for construction in 1988
to correct items 2 and 3. The Closure -Plan in item 4 is scheduled for submit-
tal to the State of Nevada in January 1988.
Tunnel Pond Sampling
On August 7 water samples were collected from the effluent lines at
E, G, P, N, and T tunnels and from two holding ponds at both N and T tunnels.
Samples were also collected from the bottom of the holding ponds which contained
both soil and sediment. The samples were analyzed by an off site laboratory
for metals, volatile organics, and semi-volatile organics.
Add-6
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No volatile or semi-volatile organic primary pollutants were found that
are detectable by the EPA approved methods. The metal content of the liquid
and soil was normal; there were no metals near the hazardous threshold level.
The results indicate that there were no hazardous chemicals in the tunnel
effluents or in the tunnel ponds at the time the samples were taken.
Mixed Waste Disposal Permit Application
During 1987 the Part A application for mixed waste disposal at the NTS
was amended to include: (1) solid waste disposal at the Area 3 Radioactive
Waste Management Site, (2) liquid disposal in the Area 6 Decon Facility
Evaporative Pond and, (3) the Area 23 Building 650 leachfield.
Interim Status was granted by the State of Nevada for mixed waste dis-
posal on September 17, 1987. No mixed waste was disposed of during the
remainder of the year.
CERCLA ACTIVITIES
The only environmental sampling that was undertaken to comply with CERCLA
regulations were soil and swipe samples collected at Sugar Bunker in Area 25.
The samples were analyzed by the Industrial Hygiene Environmental Laboratory
for beryllium contamination. Swipe samples were taken inside the bunker and on
the exterior walls. The soil samples were collected outside around the bunker.
All the results were below the detectable limits of 0.2 ppm for the soil
samples and .01 g for the swipes.
TSCA ACTIVITIES
REECo has a PCB Identification Number, NVG-PCB-006, issued by the State of
Nevada, and is responsible for the off-site disposal of PCB oils and PCB trans-
formers at the NTS. On June 24 an annual report for CY86 was submitted^ the
State, as required by State Regulations. There was no State or Federal inspec-
tion of the NTS for TSCA Compliance during 1987.
During 1987, 141 oil samples were collected at the NTS and analyzed by
the Industrial Hygiene Environmental Laboratory for PCB concentration. These
oil samples were collected from transformers or barrels of oil awaiting dis-
posal An additional 56 standard samples were run for quality assurance.
Add-7
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TECHNICAL REPORT DATA
ff 'lease read Instructions on the reverse before completing)
2.
1. REPORT NO.
DOE/DP/0539-060
4. TITLE AND SUBTITLE
OFFSITE ENVIRONMENTAL MONITORING REPORT:
Radiation Monitoring Around U.S. Nuclear Test Areas,
Calendar Year 1987
6. PERFORMING ORGANIZATION CODE
7 AU,, N. sunderiand5 S. Black, C. Fontana, A. Mullen
D. Thome1, B. Dicey, A. Jarvis, D. Smith
9. PERFORMING ORGANIZATION NAME AND ADDRESS
Environmental Monitoring Systems Laboratory
Office of Research and Development
U. S. Environmental Protection Agency, PO Box 93478
Las Vegas, NV 89193-3478
8. PERFORMING ORGANIZATION REPORT NO.
EPA 600/4-88/021
12. SPONSORING AGENCY NAME AND ADDRESS
U. S. Department of Enerqv
Nevada Operations Office
PO Box 98518
Las Vegas, NV 89193-8518
15. SUPPLEMENTARY NOTES " ~~
Prepared for the U.
DE-AI08-86NV10522
3. RECIPIENT'S ACCESSION NO.
5. REPORT DATE
10. PROGRAM ELEMENT NO.
XLUF10
11. CONTRACT/GRANT NO.
IAG DE-AI08-86NV10522
. TYPE OF REPORT AND PERIOD COVERED {
Response - 1Q87 '
14. SPONSORING AGENCY CODE
EPA 600/07
S. Department of Energy under Interagency Agreement No.
16. ABSTRACT
This report covers the routine radiation monitoring activities conducted by the
Environmental Monitoring Systems Laboratory-Las Vegas in areas which may be affected
tn Hn^ mar, tirl? P*? of the Department of Energy. This monitoring is conducted
to document compliance with standards, to identify trends in environmental radiation,
and to provide such information to the public. It summarizes these activities for
calendar year 1987.
No radioactivity attributable to NTS activities was detectable offsite by the monitor-
d?L!!rXrkS'i V:? ^T^ W1'nd data and Pasqu111 Stabilit* categories, atmos eHc
dispersion calculations based on reported radionuclides releases yield an estimated
dose of 5.9x10-4 person-rem to the population within 80 km of the Nevada Test Site
during 1987. World-wide fallout of Kr-85, Sr-90, Cs-137, and Pu-239 detected by the
monitoring networks would cause maximum exposure to an individual of less than 0 16
mrem per year. Plutonium in air was still detectable along with Krypton-85, which
continued its gradual increase, as has been reported previously. Cesium and strontium
ilairuwerf nea!; ^eir detection limits. An occasional net exposure to offsite resi-
dents has been detected by the TLD network. On investigation, the cause of such net
exposures has been due to personal habits or occupational activities, not to NTS
activitiQS.
KEY WORDS AND DOCUMENT ANALYSIS
DESCRIPTORS
b.lDENTIFIERS/OPEN ENDED TERMS
c. COS AT I Field/Gr
RELEASE TO THE PUBLIC
19. SECURITY CLASS (ThisReport)
IINHI ASSTFTFR
21. NO. OF PAGES
137
20. SECURITY CLASS (Thispage)
UNCLASSIFIED
22. PRICE
EPA Form 2220-1 (Rev. 4-77) PREVIOUS EDITION is OBSOLETE
* U.S. GOVERNMENT PRINTING OFFICE:1988-581-137/70082
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