NERC-LV-539-13
FINAL REPORT
5FF-SITE ENVIRONMENTAL SURVEILLANCE
)R THE XE PRIME NUCLEAR ROCKET ENGINE
TEST SERIES
^ .. ^
Environmental Surveillance
National Environmental Research Center
U.S. ENVIRONMENTAL PROTECTION AGENCY
4
ill
Published November 1972
This surveillance performed under a Memorandum of
Understanding No, AT(26-1)-539
for the
II. S. ATOMIC ENERGY COMMISSION
-------
This report was prepared as an account of work sponsored
by the United States Government. Neither the United States
nor the United States Atomic Energy Commission, nor any
of their employees, nor any of their contractors, subcon-
tractors, or their employees, makes any warranty, express
or implied, or assumes any legal liability or responsibility
for the accuracy, completeness or usefulness of any infor-
mation, apparatus, product or process disclosed, or repre-
sents that its use would not infringe privately-owned rights.
Available from the National Technical Information Service,
U. S. Department of Commerce,
Springfield, VA. 22151
Price: paper copy $3.00; microfiche $.95.
-------
NERC-LV-539-13
FINAL REPORT
OFF-SITE ENVIRONMENTAL SURVEILLANCE
FOR THE XE PRIME NUCLEAR ROCKET ENGINE
TEST SERIES
by
Environmental Surveillance
National Environmental Research Center*
U.S. ENVIRONMENTAL PROTECTION AGENCY
Las Vegas, Nevada
Published November 1972
This surveillance performed under a Memorandum of
Understanding No. AT(26-l)-539
for the
U.S. ATOMIC ENERGY COMMISSION
*At the time this work was performed, the Center was named the Southwestern
Radiological Health Laboratory.
-------
ABSTRACT
The National Environmental Research Center-Las Vegas performed radiological
monitoring in off-site areas after the testing of the XE Prime nuclear
rocket engine at the Nuclear Rocket Development Station during the period
December 1968 to September 1969. Fresh fission products were detected in
the off-site area after Experimental Plans (HP's) VC and IXA, conducted
respectively on June 11, 1969, and August 28, 1969.
Following EP-VC, the only indications of fresh fission products in the off-
site area were one air sample collected at Diablo Maintenance Station (10°,
75 miles from the test stand) and two precipitation samples collected from
puddles on the ground within six miles of Diablo. The postulated infant-
thyroid dose equivalent estimated from the airborne radioiodine concentra-
tions at Diablo was less than 1 mrem.
Following EP-IXA, peak radiation exposure rates of approximately twice
background were measured on GM survey instruments during cloud passage on
Highway 25 in the Koyne's Mill area. No deposition was detected following
cloud passage. Low levels of fresh fission products were detected in air
samples collected north-northeast of the test stand as far as Ely, Nevada
(25°, 184 miles). From all sampled locations, the highest potential
exposure to airborne radioiodine occurred at Koyne's Mill (28°, 55 miles),
where the maximum postulated infant-thyroid dose equivalent was 1.6 mrem.
No radioiodine was detected in milk samples.
-------
PREFACE
In accordance with Memorandum of Understanding No. AT(26-1)-539, the National
Environmental Research Center-Las Vegas (NERC-LV)provides an off-site ra-
diological safety program for the Atomic Energy Commission in support of
nuclear tests conducted at the Nevada Test Site (NTS) and at the Nuclear
Rocket Development Station (NRDS), which lies adjacent to the NTS. In
this capacity the NERC-LV is responsible for the following safeguards
during reactor tests: '
1. Documenting the radiological situation in off-site areas
through comprehensive environmental sampling and radiation
monitoring.
2. Assuring continuous protection of public health and safety
by determining potential and past exposures to radioactivity,
and by implementing protective measures as directed by the
Test Manager, AEG.
3. Conducting a public contact and information program in the
off-site area to assure local residents that all reasonable
safeguards are being employed to protect public health and
property from radiation hazards.
4. Collecting information regarding incidents which may be
attributed to radioactive releases to the off-site area.
Off-site areas are considered to be those outside the boundaries of the
NTS, the NRDS, the Tonopah Test Range, and the Nellis Air Force Range,
which together are referred to as the Test Range Complex.
ii
-------
The National Environmental Research Center-Las Vegas also represents the
Environmental Protection Agency* (EPA), and thereby maintains close working
relationships with other components of the EPA and the surrounding states.
When any off-site radiological safety operation is conducted, all appro-
priate parties are kept advised and state and federal surveillance networks
are alerted, as appropriate, to assist in documenting levels of radio-
activity.
* At the time this work was performed the NERC-LV was part of the Bureau of
Radiological Health, Environmental Control Administration, Consumer Protec-
tion and Environmental Health Service, Department of Health, Education, and
Welfare. Since then, the Consumer Protection and Environmental Health
Service was reorganized as the Environmental Health Service on February 1,
1970, and on December 2, 1970, the NERC-LV was transferred to the newly-
formed Environmental Protection Agency and the Laboratory name has since
been changed from Southwestern Radiological Health Laboratory to National
Environmental Research Center-Las Vegas.
iii
-------
TABLE OF CONTENTS
Page
ABSTRACT i
PREFACE ii
LIST OF FIGURES v
LIST OF TABLES v
INTRODUCTION 1
PROCEDURES 3
EP-VC RESULTS . 4
EP-IXA RESULTS 8
SUMMARY 12
APPENDIX A. Equipment and Analytical Techniques 13
APPENDIX B. Calculations of Thyroid Dose Equivalent 18
APPENDIX C. XE Prime EP-VC Printouts of Sampling Results 22
APPENDIX D. XE Prime EP-IXA Printouts of Sampling Results 29
DISTRIBUTION
IV
-------
LIST OF FIGURES
Figure Page
1. Air Surveillance Network Stations ' 6
2. Permanent Gamma Rate Recorder Locations 7
3. Natural Vegetation Sampling Locations EP-VC 8
4. Air Sampling and Ground Monitoring Locations EP-IXA 10
5. Film Badge and Thermoluminescent Dosimeter (TLD) Network 15
LIST OF TABLES
Table
1. XE Prime Test Series 2
2. Positive Sampling Results - EP-VC 4
3. Positive Air Sampling Results - EP-IXA 11
-------
INTRODUCTION
The XE Prime nuclear rocket engine, rated at 1100-Mw design power, was
tested through 14 experimental plans during the period December 1968
through September 1969. The test series was conducted at the Engine
Test Stand-1 (ETS-1) on the Nuclear Rocket Development Station (NRDS),
Jackass Flats, Nevada. Airborne radioactivity was released from
Experimental Plans (EP's) VC and IXA and detected beyond the boundaries of
the Test Range Complex (NRDS, Tonopah Test Range, Nellis Air Force Range
and Nevada Test Site combined). Table 1 lists the date, time, and inte-
grated power for each experimental plan.
The National Environmental Research Center-Las Vegas (NERC-LV) conducted
radiological monitoring and sampling in off-site areas. This report sum-
marizes the monitoring and sampling techniques which were used and pre-
sents the results. The results of aircraft monitoring and sampling
missions are reported separately.
The testing of the Experimental Engine, XE Prime, concluded the testing
of integrated engine systems begun with the so-called "breadboard" testing
of the NRX-A4/EST at NRDS in 1966. Other engine systems were NRX-A5 and
NRX-A6. With the exception of XE Prime, all engine components essential
for a simulated flight test were arranged for convenience in the engine
systems, not in a flight configuration. The nozzles of the engines were
directed upward, ejecting the hot hydrogen propellant containing radio-
activity several thousands of feet above the ground. The XE Prime engine
differed in that the engine components were placed in a flight configuration
with a partially evacuated compartment around the reactor to simulate
conditions in space, and the engine was fired downward with the effluent
directed into a duct which ejected the hot gases and radioactivity at an
angle of 45 degrees above the ground.
-------
Table I. XE Prime Test Series
EP
I
SLII
IA
IB
II
IIA
me
VC
IVA
VIA
VI IA
VIIIA
IXA
XA
Date
4 Dec 68
6 Dec 68
20 Feb 69
27 Feb 69
13 Mar 69
20 Mar 69
17 Apr 69
11 Jun 69
26 Jun 69
10 Jul 69
24 Jul 69
13 Aug 69
28 Aug 69
11 Sep 69
Run Time
1038-21453
1234-21423
1208-1542a
1249-18313
1619-16433
1001-13433
1512-1525a
1042-1053b
1308-1701b
1201-1244b
1154-1241b
1546-1631b
1618-1651b
1139-1227b
Maximum Maximum Total
Power Chamber Temperature0 integrated Pot
(Mw) (°R) (Mw-sec.
0.2
1.2
0.9
0.01
0.05
0.2
445
1070
58
200
160
440
610
50
-
-
-
-
_
1710
3100
4100
1700
1700
1800
3100
4090
1220
39
23
876
117
41
9.28 x 103
1.48 x 105
4.25 x 105
4. 9 x 105
1.01 x 105
5.41 x 104
4.36 x 105
3.38 x 105
1.71 x 104
Pacific Standard Time
Pacific Daylight Time
Temperature of gases exiting the reactor core
Information obtained from NERVA Test Operations
-------
PROCEDURES
Prior to a reactor test at the NRDS, NERC-LV mobile monitors were po-
sitioned at populated locations and on existing roads and highways crossing
the predicted effluent trajectory to measure radiation levels and collect
environmental samples should airborne radioactivity be released. The
monitors were equipped with radiation survey instruments, gamma-rate
recorders, thermoluminescent dosimeters, portable air samplers and supplies
for collecting environmental samples. All personnel were in two-way radio
contact with personnel in a control center who directed their activities.
Following a release of radioactivity, pertinent characteristics of the
effluent were determined by aerial monitoring. A U. S. Air Force U-3A air-
craft was used to define the boundaries and hot-line of the radioactive
cloud, and an EPA Turbo-Beech was used to perform cloud sampling, monitoring
and other documentative missions, as required. All tracking data were
radioed immediately to the control center. This information, in conjunction
with meteorological and on-site monitoring information, was used in directing
the placement of portable air samplers, portable recorders, TLD's and ground
monitors.
During the passage of the effluent, levels of environmental radioactivity
were documented by air sampling and radiation monitoring. Following cloud
passage, monitors obtained radiation readings in the affected areas and
collected vegetation, milk, cow feed, and water samples. Filters from se-
lected stations of the Air Surveillance Network were collected for immediate
analysis at the NERC-LV. Highways crossing the effluent trajectory were
also monitored after EP-VC by a mobile scanner with high sensitivity for
gamma radiation to measure the boundaries of any radioactive deposition on
the ground.
Further details on equipment, procedures, and analytical techniques are
given in Appendix A.
-------
EP VC RESULTS
According to aerial monitoring results during and following EP-VC
conducted on June 11, 1969j the radioactive effluent moved north from
the test stand. Since the movement of the effluent was slow and the
radiation levels within the cloud were less than 1.5 mR/h as the cloud
moved beyond 10 miles of the test stand^ no special radiation monitoring
or special air sampling was conducted off-site on the ground during cloud
passage.
The only indications of fresh fission products in the off-site area from
EP-VC were one air sample collected at Diablo Maintenance Station (a
continuously operating ASN station located at 10 , 75 miles from the test
stand) and two precipitation samples collected from puddles on the ground
near Diablo. These results are shown in Table 2.
Based upon a population survey conducted in the area during the summer
months; four adults and one infant lived in Diablo, which is located
in a sparsely populated area.
Table 2. Positive Sampling Results - EP-VC
AIR
— H- «™« Postulated"
Meter Gross Beta (pCi/m ) Infant
Date/Time
On
Location Off
Diablo
Maintenance 11/0645
Station 12/0645
Operating
Time
fhr) (u<
24.0
{ „. / 3\ . . 3 a Thyroid
(pCi/m ) CuCi-sec/m ) „/. .,
, 3. a 131
Si-sec/m ) I
2.4 0.7
0.21 0.06
132 133 *4uj.v«i«
Te I (mrem]
2.7 3.7 <1
0.23 0.32
Dose
mt
>
PRECIPITATION
Location
5 mi NW Diablo
Sample
Source
Rain Puddle
Collection
Date
6/12/69
Isotopic Results
(pCi/1)
131I 132Te
380 2000
133I
3400
on Highway 25
6 mi E Junction
Highway 25 &
Nyala Road
Rain Puddle
6/12/69
330
1600
2100
Based on meter time and not operator on/off times.
Calculation method shown in Appendix B.
-------
The air sampling results are for activity collected on both the particulate
filter and charcoal cartridge. The proportion of activity collected by the
charcoal cartridge was 57% for I and 6570 for I.
The air sampler at Warm Springs was not working between 2100 hours on the
llth to 1130 hours on the 12th. All other Air Surveillance Network
Stations (Figure 1) and the permanent network of gamma-rate recorders
(Figure 2) within the anticipated path of the reactor effluent showed
background activity.
The EP-VC effluent was not detected on samples of natural vegetation
collected at five-mile intervals along Highway 25 from Coyote Summit to
Warm Springs and along Highway 6 from Warm Springs to about 30 miles east
of Tonopah (Figure 3). The analytical results for the samples are shown
in Appendix C. The same route was traveled by a mobile scanner, described
in Appendix A. There was no detectable increase in scanner readings
taken the morning after the full-power test from those taken before the
run.
Milk, water, and the cow feed samples were collected at Sharp's Ranch
in Nyala on June 12 and 13. No fresh fission products were detected.
The sampling information and results are shown in Appendix C.
-------
0>
W'V I \ •'*« I
—-J ? ""••""• !
) '• *
G°ui"<
Figure 1. Air Surveillance Network Stations
-------
Figure 2. Permanent Gamma Rate Recorder Locations
-------
~ Natural vegetation sample with background activity
»! I
GOLDFIELD
QUEEN CITY SMT.
NELLIS AIR FORCE RANGE
\ NEVADA TEST SITE
v BEATTYi I |
LT
•.INDIAN SPRINGS
• WARM SPRINGS RN.
0 10 20
f^^m^m^
SCALE IN MILES
Figure 3. Natural Vegetation Sampling Locations, EP-VC.
8
-------
EP LXA RESULTS
From early aerial monitoring readings for EP-IXA conducted on August 28,
the movement of the radioactive effluent was found to be northeast from
the test stand. In addition to the Air Surveillance Network Stations
(Figure 1), five temporary air samplers were operated on Highway 25 at
Hancock Summit, 11 miles west of Hancock Summit, Coyote Summit, Koyne's
Mill, and Queen City Summit (Figure 4). Seven of the ASN stations and
three .of the temporary samplers collected activity from the EP-IXA effluent.
The combined results of analyses on the filters and charcoal cartridges from
these air samplers are presented in Table 3. Analytical results for the
individual filters and charcoal cartridges are shown in Appendix D. The
remainder of the ASN stations showed background results. The air filter
samples from Duckwater and Caliente were not received for the periods
August 28 through August 29 and August 28 through September 4, respectively.
The two temporary samplers at Hancock Summit (51 , 65 miles) and 11 miles
west of Hancock Summit (43 , 64 miles), showed no reactor-related radioactivity.
On Highway 25, monitors detected gamma activity associated with cloud
passage at Queen City Summit, Koyne's Mill, and Coyote Summit (Figure 3).
Peak radiation levels were about twice background on GM survey instruments.
No radiation levels above background were detected by gamma-rate recorders
at the other locations shown in Figure 3 or by the permanent network of
gamma-rate recorders (Figure 2). The mobile scanner was not used following
this test.
Analytical results for environmental samples other than air showed only
background activity. Natural vegetation samples collected next to the
temporary air samplers showed no activity from fresh fission products.
Milk, water, and cow feed samples were collected during the period August 30
to September 3 at ranches in Nyala, Duckwater, Lund, and Shoshone, Nevada.
No fresh fission products were detected. The sampling dates and results
for these samples are listed in Appendix D.
The affected area in the immediate off-site area is sparsely populated.
In addition to the five persons residing at Diablo as shown by the
population survey during the summer months, two adults lived at
Koyne's Mill. Queen City, Coyote, and Hancock Summits were unpopulated
except for NERC-LV monitors.
9
-------
Air sampler with reactor activity
Air sampler with background activity
Gamma-rate recorder showing background.
Monitor readings above background
EAGLE RN. WJ SUN £
QUEEN CITY SMT.
NELLIS AIR FORCE RANGE
COYOTE SMT
I \
-------
Table 3. Positive Air Sampling Results - EP-IXA
Location
Currant (ASN)
21 , 144 mi
Diablo (ASN)
10 , 75 mi
Ely, (ASN)**
25 , 184 mi
Lund (ASN)
27 , 158 mi
a
Blue Eagle Ranch (ASN)
19 , 123 mi
Sunnyside (ASN)
33 , 131 mi
Nyala (ASN)
18 , 103 mi
Kovne's Mill (Temp)
28 , 55 mi
Covote Summit (Temp)
34 , 62.5 mi
Queen City Summit (Temp)
8 , 67 mi
Date-Time Meter
On Operating
Off Time
(hr)
8/28-0630
8/29-0630 24.0
8/28-0625
8/29-0625 23.9
8/28-1140
8/29-1025 22.8
8/28-0758
8/29-0814 24.2
8/29-0814
8/30-0625 22.2
8/28-0655
8/29-0620 21.3
8/28-1700
8/29-1930 25.5
8/28-0700
8/29-0700 21.4
8/28-1854
8/28-2054 2.0
8/28-1850
8/28-2045 1.9
8/28-1925
8/28-2050 1.4
Airborne Activity Concentrations (pCi/m ) 0
; and Integrated Exposures (juCi
Gross Beta
3.9
0.34
1.0
0.086
6.5
D.54
9.6
6.84
0.9
0.07
11
0.81
1.1
0.098
11
0.85
5000
36
800
5.5
5700
29
131I
0.4
0.03
ND
0.9
0.07
0.9
6.68
0.2
0.02
1.3
0.10
0.1
0.009
1.7
0.13
62
0.45
8.4
0.060
55
0.28
132Te
1.1
0.095
ND
2.5
"D.20
2.1
0.18
0.4
U.03
2.9
0.22
0.4
0.04
3.0
0.23
150
1.1
27
0.18
170
0.86
133
ND
1.3
0.11
ND
ND
ND
ND
ND
5.5
0.42
280
2.0
67
0.46
320
1.6
• sec/nry-
135
ND
ND
ND
ND
ND
ND
ND
ND
560
4.1
67
0.46
550
2.8
Postulated"
Infant
— 91 — inyroia
Sr Dose
Equivalent
(mrem)
ND <1
ND <1
ND <1
ND <1
ND <1
ND <1
ND <1
ND <1
120 1.6
0.86
26 <1
0.18
190 1.1
0.96
No charcoal cartridge run.
Extrapolated to end of collection.
Based on meter time and not operator on/off times.
Calculation method shown in Appendix B.
ND = Not detected.
-------
SUMMARY
The testing of the XE Prime nuclear rocket engine resulted in low levels
of fresh fission product activity in the off-site area following Experimental
Plans (EP) VC and IXA. Radioactivity from the EP-VC effluent was detected
in an air sample collected north-northeast of ETS-1 at the Diablo Main-
tenance Station (10 } 75 miles) and in two precipitation samples collected
along Highway 25 five miles northwest of Diablo and six miles eas't of
Highway 25 on Nyala Road. From the time-integrated concentrations of
airborne radioiodine determined from the air sampling results at Diablo,
the estimated radiation dose to the thyroid of a postulated infant receptor
was less than 1 mrem. Following EP-KA, the effluent traveled from ETS-1
to the northeast where activity was detected off-site with GM survey
meters and collected by air samplers. Radiation levels of about twice
background were measured during cloud passage at distances of 55-67 miles
from the test stand. No deposition was detected. At ten locations within
the effluent trajectory, air samplers at distances of 55-184 miles collected
radioiodine. The location at which the potential inhalation exposure was
highest was at Koyne's Mill (28 , 55 miles), where the estimated infant
thyroid dose was 1.6 mrem. All milk, water, cow feed, and vegetation
samples collected for both EP-VC and BCA showed no activity from fresh
fission products.
According to the radiation protection standards listed in Atomic
Energy Commission Manual, Chapter 0524, radiation doses to the thyroids
of a population sample should not exceed an average exposure of 500 mrem
over a period of one year. If one considers the air sampling results at
Koyne's Mill to be for a population sample, which would be conservative
for the area, the estimated infant thyroid dose at this location would
be only 0.3 percent of the AEC radiation protection standard.
12
-------
APPENDIX A
Equipment and Analytical Techniques
Survey Instruments
The aircraft and ground monitors are equipped with Geiger-Mueller, gamma
scintillation, and ionization chamber survey instruments. The Geiger-
Mueller (GM) instrument has a range of 0-200 mR/h on three linear scales
with a range of 0-2000 mR/h provided by an internal GM detector. The
gamma scintillation instrument, used for low-level cloud passage measure-
ments, has a range of 0-3 mR/h on three linear scales. The ionization
chamber survey instrument is used for high radiation levels. It has a
range of 0.05 to 50,000 mR/h on two logarithmic scales. These instru-
137
ments are calibrated to ±20% with a Cs standard. Exposure-rate
readings are accurate to two significant digits.
Mobile Ground Scanner
The mobile ground scanner consists of a 4- by 4-inch Nal(Tl) crystal con-
nected to a battery-powered sealer. The scanner and crystal are placed
within a motor vehicle and operated by taking one-minute counts while the
vehicle moves along highways crossing the effluent trajectory. These data
are then compared with background levels determined prior to tests to
identify any deposition pattern.
Gamma-rate Recorders
A NERC-LV network of 27 continuously operated gamma-rate recorders (Eberline
RM-11) are located around the Test Range Complex at the locations shown in
Figure 2. These instruments measure radiation exposure rates over a range
of 0.01 to 100 mR/h with a GM detector and record the levels on a 30-hour
strip chart. The instrument is accurate to ±20% as calibrated with a
n
Cs source.
13
-------
Portable gamma-rate recorders carried by monitors utilize the same 0-2000
mR/h GM survey instrument mentioned above coupled to a battery-powered
strip-chart recorder. These recorders are used to supplement the routine
network of gamma-rate recorders and the radiation readings taken by
monitors. The enclosure for each recorder also contains two TLD's of
the type described below.
Dosimeters
The NERC-LV maintains a network of film badges and thermoluminescent
dosimeters (TLD's) which surrounds the Test Range Complex. The locations
of the dosimetry stations are shown in Figure 5. One hundred six stations
are equipped with five DuPont Type 545 film badges. Eighty-eight of these
stations also have three EG&G Model TL-12 TLD's. Film badges are also
issued to about 140 off-site residents. All dosimeters are exchanged
monthly to provide continuous monitoring.
Following nuclear reactor tests which release airborne radioactivity,
additional TLD's are used to supplement the dosimetry network. For
normal tests, TLD's are placed in gamma rate recorders which are placed
along highways and populated locations. If an accident or abnormal release
should occur, additional TLD's are available for handing out to off-site
residents.
The film badges have a lower detection limit of 30 mR with a reading
accuracy of ± 5070 from 30 mR to 100 mR and ± 10% from 100 mR to 2000 mR
for gamma radiation above 50 keV. The magnitude of a detectable exposure
depends upon the magnitude of the accumulated background exposure. Over
a four-day period or less, a net exposure of 1 mR can be detected, and
over a thirty-day period a 5 mR exposure can be detected. Reading accuracy
of the TLD system for gamma radiation above 50 keV is ± 10% from 10 mR to
the maximum readable exposure, 5000 R.
Air Samples
The routine network of 103 permanent air samplers of the Air Surveillance
Network (ASN) is used for measuring concentrations of airborne radioactivity
on a daily basis. These stations (Figure 1), sampling at about 10 cfm,
collect airborne particles on 4-inch-diameter glass-fiber filters.
14
-------
5 Film Badges
3 TLD and 5 Film Badges
Figure 5. Film Badge and Thermoluminescent Dosimeter (TLD) Network
15
-------
Twenty-two of the stations next to the Test Range Complex each operate
routinely with a 3 1/4-inch-diameter charcoal cartridge following the
particulate filter. By telephone request, charcoal cartridges can be
placed in additional stations and stand-by stations can be activated.
Portable air samplers carried by field monitors supplement the ASN stations
to cover cloud passage. These samplers also use 4-inch-diameter glass-
fiber filters and charcoal cartridges and operate at about 12 cfm.
All particulate filters are counted for gross beta radioactivity on a low
background, thin-window, proportional counter. Results are reported in
3 3
pCi/m and jzCi-sec/m , extrapolated to end of collection time. Those
particulate filters containing elevated gross beta radioactivity and all
charcoal cartridges are analyzed by gamma spectrometry with a 4- by 4-inch NaI(T
crystal and multi-channel analyzer. The concentrations of individual
3 3
radioisotopes are reported in pCi/m and /zCi-sec/m , extrapolated to the end
of collection. For gross beta and radioiodine radioactivity collected
3 3
from 300 m of air the Minimum Detectable Activity (MDA) is 0.1 pCi/m
for counting times of 2 minutes and 10 minutes, respectively.
Vegetation Samples
Following cloud passage, samples of natural vegetation are collected along
highways and at populated locations to augment or substantiate other evi-
dence of the radioactive deposition pattern. Samples are counted for gross
gamma radioactivity and are qualitatively analyzed by gamma spectrometry to
determine whether samples are positive or negative for test-related radio-
activity.
Samples of cow feed are collected at all milk sampling locations and are
analyzed by gamma spectrometry. The concentrations of individual radio-
isotopes identified in the samples are reported in pCi/kg if greater than
the MDA of 50 pCi/kg for a 10-minute count and sample weight of 1 kg.
16
-------
_Milk Samples
One-gallon milk samples are collected from dairy farms and family milk
cows located within the cloud path. Samples of 3.5 liters are analyzed
131
by gamma spectrometry techniques. The lower limit of detection of I and
133
I is about 20 pCi/1 for a 20-minute counting time. Samples containing
test-related radioactivity are also analyzed by radiochemistry techniques
89 90
for Sr and Sr, which have MDA's of 5 pCi/1 and 2 pCi/1, respectively.
Water Samples
One-gallon water samples are collected from stock tanks and potable water
sources at milk sampling locations within the effluent trajectory. All
samples are analyzed by gamma spectrometry. Those samples containing test-
89
related radioactivity are also analyzed by radiochemistry methods for Sr
90
and Sr. The minimum detectable concentrations are the same as those for
milk.
17
-------
APPENDIX B
Calculations of Thyroid Dose Equivalent
The dose equivalent rate to the thyroid may be described by the equation
d(DE)/dt = KEA exp - (Xefft) where
d(DE)dt = dose equivalent rate per unit time at time t
K = dimensional constant
E = effective energy of beta and gamma radiation,
MeV per disintegration
A = concentration of radioiodine in thyroid at time to,
eff = effective decay constant, I/unit time
t = time after deposition in thyroid
This assumes that the radioiodine is uniformly distributed throughout
the thyroid and that the size of the thyroid is large compared to the
range of the beta particles in tissue.
The total dose equivalent is estimated by integrating the above equation
from time zero to infinity assuming D = 0 at time zero.
DE = KEAjexp - (Xefft) dt
DE = (-l/Xeff) KEA exp - (Xefft) | o
DE = 0 + KEA/X _-
eff
Dose Equivalent from Inhalation of Radioiodines
The actual values for the parameters in the dose equation for I are
as follows:
18
-------
1. K = 1 rad x erg x 3.7xlQ4 dis x 8.64xlQ4 sec x QF
100 erg/g 6.24xl05 MeV uCi-sec day
where QF = Quality Factor of 1 rem/rad
K = 51.2 rem-g.dls
MeV-AiCi-day
2. E = 0.23 MeV
3. A. = C.Bf, where
m
C. = Time- integrated concentration of radioactivity,
/iCi'sec/m3
B = breathing rate of standard man, 2.32 x 10 m /sec*
*
f = fraction of inhaled radioiodine reaching the thyroid, 0.23
m = Thyroid weight of standard man, 20 g
(2.32 x 10"4 m3/sec) (0.23)^
20
1 31
4. X = 0.693/ (effective half-life for I)
Xeff = (°-693)/7.6 days*
"Recommendations of the International Commission on Radiological
Protection Report of Committee II on Permissible Dose for Internal
Radiation." ICRP-2 Pergamon Press, New York, London, Paris,,
Los Angeles, 1959.
19
-------
Substituting these parameters, the dose equation becomes
DE = (51.2)(0.23)(2.32 x Ip"4)(0.23)(7.6)C.
(20)(0.693) X
/ *3 *5
DE(rems) = 3.45 x 10 (rems-m /MCi-sec)C. (/iCi-sec/m )
* 3*
or
3 3
D(mrem) = 0.35(mreiE'm /juCi-sec)C. (/iCi-sec/m )
For the DE to a child's thyroid the above equation must be multiplied
by a factor of 3 to account for differences in thyroid weight and
3
breathing rates (m /day) between an adult and a child (3 = 20 g/2g
x 6 m3/20 m3).
For other radioiodines the DE equation changes according to differences
in effective half-life and effective decay energies. The DE equations
T^ 1 ^5
for I and I are as follows:
i -t-t 3
I, DE(mrem) = (0.093 mrem-m ^
/LtCi-sec
l -1C o
3I, DE(mrem) = .(0-029 'larea.in )C±
yCi.sec
20
-------
In addition to differences in effective half-life and effective beta
132
particle energies, the DE equation for I is effected by the rapid
132
decay of I in the blood stream before it gets to the thyroid and by
•I O r\ -I o f\ ju •JL--JU
the decay rate of Te, the precursor of I ' . With these effects
132
incorporated, the DE equation for I becomes
-2 3
DE(mrem) = (5.1 x 10 mrem-m //uCi-sec)C.
132
where C. is the time-integrated concentration of Te.
* "Protection of the Public in the Event of Radiation Accidents."
Proceedings of a seminar sponsored by FAO/UN, 1 AEA, and World
Health Organization on 18 November, 1963 at Geneva, Switzerland,
1965. P. 210.
** LeGrand, J. and Dousset, M. "Evolution DuDebit D'Equivalent De
Dose Deliveree A La Glande Thyroide Agres Inhalation Instantanee
De Tellure 132 (French)." Health Physics Vol. 12, No. 10 October,
1966. p. 1407.
21
-------
APPENDIX C
XE Prime EP-VC - Printouts of Sampling Results
22
-------
APPENDIX C XE PRIME EPVC MILK RESULTS
LOCATION
NYALA NEV SHARPts RANCH
COLLECTED 06/13/69
NYALA NEV SHARPtS RANCH
COLLECTED 06/13/69
LAB-NO.«, 1311 1331 137CS 89SR
USE CODE PCI/L PCI/L PCI/L PCI/L
067448 LT(10) LT(10) LT(10) LT(5)
067497 LT(IOO) LTUOO) LTUOO) LT<5)
NOTE—UNLESS OTHERWISE NOTEDt RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K IS IN GRAMS PER UNIT OF SIZE.
LT
-------
APPENDIX C XE PRIME EP VC WATER RESULTS
LOCATION
NYALA NEV SHARPiS RANCH
COLLECTED 06/12/69
GAMMA
NEGLIGIBLE
NYALA NEV SHARP*S RANCH
COLLECTED 06/13/69
GAMMA
NEGLIGIBLE
SPECTRUM
SPECTRUM
DIABLO NEV 5 MI NW ON HWY 25
COLLECTED 06/12/69
DIABLO NEV 6 MI E Op"NYALA RD
K COLLECTED 06/12/69
LAB-NO.& ALPHA
USE CODE PCI/L
067449 LT(2)
067496 5
BETA
PCI/L
067450 82 760
067451 67 606
NOTE—UNLESS OTHERWISE NOTED* RESULTS ARE
IN PICO-CURIES PER UNIT or SIZE*
EXCEPT K JS IN GRAMS PER UNIT OF SIZE,
LT(X)=LESS THAN X* ND«NOT DETECTED* NA«NO ANALYSIS
1311
PCI/L
ND
ND
132TE 1331 3H
PCI/L PCI/L PCI/L
ND
ND
ND
ND
NA
NA
3.8E02 2.0E03 3.4E03 2.2E03
3.3E02 1.6E03 2.1E03 1.8E03
-------
APPENDIX C XE PRIME EP VC COW FEED RESULTS
LOCATION
NYALA NEY SHARPS RANCH
COLLECTED 06/12/69
N-FFP
NYALA NEV SHARPS RANCH
COLLECTED 06/13/69
GAMMA
NEGLiGIBLE
LAB-NO.& GROSSGA
USE CODE CPM/KG
067429 9.6E02
067498
SPECTRUM
Ui
NOTE^-UNLESS OTHERWISE NOTEDt RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K IS IN GRAMS PER UNIT OF' SIZE.
LT(X)=LESS THAN X, ND*NOT DETECTED* NA»NO ANALYSIS
N-FFP= No Fresh Fission Products
-------
APPENDIX C XE PRIME EP VC NATURAL VEGETATION RESULTS
NJ
LOCATION
COYOTE SUMMIT NEV
COLLECTED 66/12/69
N-FFP
COYOTE SUMMIT NEV 5 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 10 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 15 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 20 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 25 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 30 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
LAB-NO.S- GROSSGA
USE CODE CPM/KG
067428 2.7E03
067437 1.9E03
067430 3.3E03
067438 4.1E03
067443 5.7E04
067431 2.9E03
067447 3.1E03
NOTE—UNLESS OTHERWISE NOTED* RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K JS IN GRAMS PER UNIT OF SIZE.
LT
-------
APPENDIX C XE PRIME EP VC NATURAL VEGETATION RESULTS
K)
LOCATION
COYOTE SUMMIT NEV 35 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 40 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 45 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 50 MI W COYOTE SMT
COLLECTED o&/12/69
N-FFP
COYOTE. SUMMIT NEV 55 MI w COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 60 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 65 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
LAB-NO.& GROSSGA
USE CODE CPM/KG
067432 1.4E03
067439 3.2E03
067435 1.4E03
067444 2.5E03
067445 1.8E03
067433 1.2E03
067436 U6E03
NOTE—UNLESS OTHERWISE NOTED* RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K JS IN GRAMS PER UNIT OF SIZE,
LT(X)sLESS THAN X* ND=NOT DETECTED* NA*=NO ANALYSIS
N-FFP = .No Fresh Fission Products
-------
APPENDIX C XE PRIME EP VC NATURAL VEGETATION RESULTS
LOCATION
COYOTE SUMMIT NEV 70 MI vT COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 75 MI W COYOTE SMT
COLLECTED 06/12/69
LAB-NO.8, 6ROSS6A
USE CODE CPM/KG
067440 2.0E03
067434 4.6E03
NJ
00
COYOTE SUMMIT NEV 80 Ml W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOTE SUMMIT NEV 85 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
COYOJE SUMMIT NEV 90 MI W COYOTE SMT
COLLECTED 06/12/69
N-FFP
067446 5.0E03
067441 1.3E04
067442 1.5E03
NOTE—UNLESS OTHERWISE NOTED? RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K IS IN GRAMS PER UNIT OF SIZE.
LT(X)*LESS THAN X, ND*NOT OETECTEDt NA«NO ANALYSIS
N-FFP = No Fresh Fission Products
-------
APPENDIX D
XE Prime EP-IXA - Printouts of Sampling Results
29
-------
APPENDIX D XE PPIME EP IXA AIR SAMPLING RESULTS
LOCATION
COYOTE SUMMIT NEV KOYNE MILL
969 ON-TIME OR/28/69 1854 CC
OFF-TIME 08/28/69 2054 SIZE
COYOTE SUMMIT NEV KOYNE MILL
969 ON-TIME 08/28/69 1854 PF
OFF-TIME 08/28/69 2054 SIZE
COYOTE SUMMIT NEV
973 ON-TIME 08/28/69 1850 CC
OFF-TIME 08/28/69 2045 SIZE
COYOTE SUMMIT NEV
973 ON-TIME 08/28/69 1850 PF
OFF-TIME 08/28/69 2045 SIZE
CURRANT NEV
004 ON-TIME 08/28/69 0630 CC
OFF-TIME 08/29/69 0630 SIZE
GAMMA
NEGLIGIBLE
SPECTRUM
CURRANT NEV
004 ON-TIME 08/28/69 0630 PF
OFF-TIME 08/29/69 0630 SIZE
BLUE EAGLE RANCH NEV
027 ON-TIME 08/28/69 0655 PF
OFF-TIME 08/30/69 0620 SIZE
LAB-NO.& 1311
USE CODE PCI/M3
072048
29. M3
072047
29. M3
072041
85. M3
072039
85. M3
072223
377 M3
072158
377 M3
072288
338 M3
ND
NO
132TE 1331
PCI/M3 PCI/M3
1351
91SR
PCI/M3 PCI/M3
8.2EOO ND
1.8E01 4.3E01 ND
5.4E01 1.5E02 2.6E02 5.2E02 1.2E02
ND
LT(.l) ND
ND
ND
ND
0.4EOO 1.1EOO ND
1.3EOO 2.9EOO ND
ND
ND
NOTE—UNLESS OTHERWISE NOTED* RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K IS IN GRAMS PER UNIT OF SIZE.
LT(X)=LESS THAN X, ND=NOT DETECTED* NA=NO ANALYSIS
PF = Par t i_cnl <-* t<^ Fi 1 t:«^r-
ND
8.4EOO 2.7E01 6.7E01 6.7E01 2.6E01
ND
ND
-------
APPENDIX D XE PRIME EP IXA AIR SAMPLING RESULTS
LOCATION
DIABLO NEV
006 ON-TIME 08/28/69 0625 CC
OFF-TIME Ofl/29/69 0625 SIZE
DIABLO NEV
006 ON-TIME Ofl/28/69 0625 PF
OFF-TIME OR/29/69 0625 SIZE
ELY NEV
007 ON-TIME 08/28/69 1140 PF
OFF-TIME Ofl/29/69 1025 SIZE
LUND NEV
016 ON-TIME Ofl/2fl/69 0758 CC
OFF-TIME Ofl/29/69 0814 SIZE
GAMMA
NEGLIGIBLE
SPECTRUM
LUND NEV
016 ON-TIME 08/28/69 0758 PF
OFF-TIME 08/29/69 0814 SIZE
LUND NEV
016 ON-TIME 08/29/69 0814 CC
OFF-TIME 08/30/69 0625 SIZE
GAMMA
NEGLIGIBLE
SPECTRUM
LAB-NO. S. 1311
USE CODE PCI/M3
072065 ND
344 M3
072068 ND
344 M3
072159
299 M3
072242 ND
359 M3
072161
359 M3
072240 ND
339 M3
132TE
PCI/M3
ND
ND
ND
ND
NOTE—UNLESS OTHERWISE NOTED, RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZEf
EXCEPT K IS IN GRAMS PER UNIT OF SIZE.
LT(X)=LESS THAN X, ND=NOT DETECTED* NA=NO ANALYSIS
PF = Particulate Filter
1331
PCI/M3
0.9EOO 2.5EOO ND
ND
0.9EOO 2.1EOO ND
ND
1351
PCI/M3
0.3EOO ND
l.OEOO ND
ND
ND
ND
ND
91SR
PCI/M3
ND
ND
ND
ND
ND
ND
CC = Charcoal Cartridge
-------
APPENDIX 0 XE PRIME EP IXA AIR SAMPLING RESULTS
U)
l-O
LOCATION
LUND NEV
016 ON-TIME 08/29/69 0814
OFF-TIME OB/30/69 0625
NYALA NEV
048 ON-TIME OR/28/69 0700
OFF-TIME 08/29/69 0700
NYALA NEV
048 ON-TIME 08/28/69 0700
OFF-TIME 00/29/69 0700
QUEEN CITY SUMMIT NEV
981 ON-TIME 00/28/69 1925
OFF-TIME 08/28/69 2050
QUEEN CITY SUMMIT NEV
981 ON-TIME 08/28/69 1923
OFF-TIME 08/28/69 2050
SUNNYSIDE NEV
033 ON-TIME Ofl/28/69 1700
OFF-TIME 08/29/69 1930
GAMMA
NEGLIGIBLE
SUNNYSIOE NEV
033 ON-TIME 08/28/69 1700
OFF-TIME 08/29/69 1930
NOTE—UNLESS OTHERWISE NOTED, RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K IS IN GRAMS PER UNIT OF SIZE.
LT(X)=LES<; THAN X. ND=NOT DETECTED, NA=NO ANALYSIS
PF = Particulate Filter
814
625
700
700
700
700
925
050
923
050
PF
SIZE
CC
SIZE
PF
SIZE
CC
SIZE
PF
SIZE
700 CC
930 SIZE
SPECTRUM
700
930
PF
SIZE
LAB-NO. &- 1311 132TE 1331 1351
USE CODE PCI/M3 PCI/M3 PCI/M3 PCI/M3
072177 0.2EOO 0.4EOO ND ND
339 M3
072074 0.7EOO ND 0.6EOO ND
308 M3
072075 l.OEOO 3.0EOO 4.9EOO ND
308 M3
072052 3.5EOO ND 5.3EOO ND
35. M3
072051 5.1E01 1.7E02 3.1E02 5.5E02
35. M3
072236 ND ND ND ND
400 M3
072167 0.1EOO 0.4EOO ND ND
400 M3
91SR
ND
ND
ND
ND
1.9E02
ND
ND
-------
APPENDIX D XE PRIME EP IXA NATURAL VEGETATION RESULTS
OJ
U)
LOCATION
COYOTE SUMMIT NEV
COLLECTED 08/2fl/69
NO-FFP
COYOTE SUMMIT NEV KOYNE MILL
COLLECTED 08/28/69
NO-FFP
HANCOCK SUMMIT NEV
COLLECTED 08/28/69
NO-FFP
HANCOCK SUMMIT NEV 11 MI W
COLLECTED 08/28/69
NO-FFP
QUEEN CITY SUMMIT NEV
COLLECTED 08/28/69
NO-FFP
LAB-NO.i GROSSGA
USE CODE CPM/KG
072046 1.6E03
072055 2.2E03
072045 2.3E03
072057 1.-9E03
072056 1.8E04
NOTE—UNLESS OTHERWISE NOTED, RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE,
EXCEPT K IS IN GRAMS PER UNfT OF SIZE.
LT(X)=LESS THAN X, ND=NOT DETECTED, NA=NO ANALYSIS
N-FFP = No Fresh Fission Products
-------
APPENDIX D XE PRIME EP IXA MILK RESULTS
LOCATION
DUCKWATER NEV HALSTEAD RANCH
COLLECTED 08/30/69
DUCKWATER NEV HALSTEAD RANCH
COLLECTED 09/03/69
LUND NEV MCKENZIE DAIRY
COLLECTED 08/30/69
LUND NEV MCKENZIE DAIRY
COLLECTED 09/01/69
NYALA NEV SHARP«S RANCH
w COLLECTED 08/29/69
NYALA ~NEV SHARP «s RANCH
COLLECTED 08/30/69
NYALA NEV SHARP»S RANCH
COLLECTED 08/31/69
NYALA NEV SHARP*S RANCH
COLLECTED 09/01/69
SHOSHONE NEV VAUGHN RHODES RANCH
COLLECTED 08/30/69
SHOSHONE NEV VAUGHN RHODES RANCH
COLLECTED 08/31/69
LAB-NO.!,
USE CODE
072090
072244
072091
072248
1311 1331
PCI/L PCI/L
LT(10) ND
LT(10) ND
LT(10) ND
LT(10) ND
072076 LT(IO) LT(10)
072089 LT(10) ND
072245 LT(10) ND
072249 LTUO) ND
072092 LTUO) ND
072247 LT(10) ND
NOTE--UNLESS pTHERWISE NOTED. RESULTS ARE
IN PiCO^CURlES PER UNIT OF SIZE.
EXCEPT K IS IN GRAMS PER UNIT OF SIZE.
LT(X)sLESS THAN X. NDsNOT DETECTED. NA«NO ANALYSIS
137CS K 89SR 90SR
PCI/L GM/L PCI/L PCI/L
LT(10) 1.6EOO NA NA
LT(10) 1.6EOO NA NA
LT(10) 1.6EOO NA NA
1.0E01 1.6EOO NA NA
2.0E01 1.6EOO LT(5) 5
UOE01 1.7EOO NA NA
2.0E01 1.6EOO NA NA
1.0E01 1.3EOO NA NA
1.0E01 1.4EOO NA NA
1.0E01 1.6EOO NA NA
-------
APPENDIX 0 XE PRIME EP IXA MILK RESULTS
LOCATION
SHOSHONE NEV VAUGHN RHODES RANCH
COLLECTED 09/01/69
LAB-NO,& 1311 1331
USE CODE PCI/L PCI/L
072246 LTUO) ND
137CS
PCI/L
K
GM/L
89SR
PCI/L
1.0E01 1.3EOO NA
90SR
PCI/L
NA
NOTE—UNLESS OTHERWISE NOTEDt RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K IS IN GRAMS PER UNIT OF SIZE.
LT(X)«LESS THAN X» ND=NOT DETECTEDt NA«NO ANALYSIS
OJ
Ul
-------
APPENDIX 0 XE PRIME EP IXA WATER RESULTS
LOCATION
PUCKWAIER NEV HALSTEAD RANCH
COLLECTED 08/30/69
GAMMA SPECTRUM
NEGLIGIBLE
LUND NEV MCKENZIE DAIRY
COLLECTED 08/30/69
GAMMA SPECTRUM
NEGLIGIBLE
NYALA NEV SHARP15 RANCH
COLLECTED 08/29/69
GAMMA SPECTRUM
£ NEGLIGIBLE
NYALA NEV SHARP»S RANCH
COLLECTED oe/30/69
GAMMA SPECTRUM
NEGLIGIBLE
SHOSHONE NEV VAUGHN RHODES RANCH
COLLECTED 08/30/69
GAMMA SPECTRUM
NEGLIGIBLE
LAB-NO.* ALPHA
USE CODE PCI/L
078094 NA
BETA
PCI/L
NA
072095 NA
NA
072077 LT(2)
072096 NA
NA
072093 NA
NA
NOTE—UNLESS OTHERWISE NOTEDt RESULTS ARE
IN PICO_-CURIES PER UNIT OF SIZEt
EXCEPT K JS IN GRAMS PER UNIT OF SIZE.
LT
-------
APPENDIX0XE PPIME EP IXA COW FEED RESULTS
OJ
LOCATION
NYALA NEV SHARPtS RANCH <
COLLECTED oa/29/69
NERA
NYALA NEV SHARP»S RANCH
COLLECTED 08/30/69
NERA
NYALA NEV SHARP'S RANCH
COLLECTED 09/03/69
NERA
LUND NEV MCKENZIE DAIRY
COLLECTED 08/30/69
NERA
LUND NEV MCKENZIE DAIRY
COLLECTED 09/03/69
.NERA
DUCKWATER NEV HALSTEAD RANCH
COLLECTED 08/30/69
NERA
DUCKWATER NEV HALSTEAD RANCH
COLLECTED 09/03/69
NERA
LAB-NO.& 95ZR
USE CODE PCI/KG
072078 ND
072098 1.2E03
072251 1.1E03
072099 1.1E03
072253 3.0E02
072097 4.9E02
072252 4.6E02
NOTE—UNLESS OTHERWISE NOTEDf RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZE*
EXCEPT K JS IN GRAMS PER UNIT OF SIZE.
LT(X)sLESS THAN X* ND*NOT DETECTED* NA=NO ANALYSIS
NERA = No Event-Related Activity
-------
APPENDIX D XE PRIME EP IXA COW FEED RESULTS
LOCATION LAB-NO.*. 95ZR
USE CODE PCI/KG
SHOSHONE NEV VAUGHN RHODES RANCH 072100 5.5E02
COLLECTED 08/30/69
NERA
SHpSHpNE NEV VAUGHN RHODES RANCH 072350 6.9E02
COLLECTED 09/02/69
NERA
NOTE—UNLESS OTHERWISE NOTEDt RESULTS ARE
IN PICO-CURIES PER UNIT OF SIZEt
EXCEPT K IS IN GRAMS PER UNIT OF SIZE.
LT(X)=LESS THAN X. ND=NOT DETECTED* NA=NO ANALYSIS
NERA = No Event-Related Activity
00
-------
DISTRIBUTION
1 - 13 National Environmental Research Center, Las Vegas, Nevada
14 Mahlon E. Gates, Manager, AEC/NVOO, Las Vegas, Nevada
15 Robert H. Thalgott, AEC/NVOO, Las Vegas, Nevada
16 Henry G. Vermillion, AEC/NVOO, Las Vegas, Nevada
17 Donald W. Hendricks, AEC/NVOO, Las Vegas, Nevada
18 Robert R. Loux, AEC/NVOO, Las Vegas, Nevada
19 Mail & Records, AEC/NVOO, Las Vegas, Nevada
20 Technical Library, AEC/NVOO, Las Vegas, Nevada
21 Chief, NOB/DNA, AEC/NVOO, Las Vegas, Nevada
22 Harold F. Mueller, ARL/NOAA, AEC/NVOO, Las Vegas, Nevada
23 Howard G. Booth, ARL/NOAA, AEC/NVOO, Las Vegas, Nevada
24 M. Klein, SNSO, Washington, D.C.
25 George P. Dix, SNSO, Washington, D.C.
26 John P. Oewett, SNSO-N, Jackass Flats, Nevada
27 - 30 Peter Strom, SNSO-N, NRDS, Jackass Flats, Nevada
31 William C. King, LLL, Mercury, Nevada
32 James E. Carothers, LLL, Livermore, California
33 Ernest A. Bryant, LASL, Los Alamos, New Mexico
34 Harry S. Jordan, LASL, Los Alamos, New Mexico
35 Charles I. Browne, LASL, Los Alamos, New Mexico
36 L. E. Little, NRTO, NRDS, Jackass Flats, Nevada
37 W. S. Wilgus, NRTO, NRDS, Jackass Flats, Nevada
38 Eastern Environmental Radiation Laboratory, EPA, Montgomery, Ala.
39 Elmer Hemmerle, WANL, Pittsburgh, Pennsylvania
40 G. Gallimore, Pan Am. World Airways, Jackass Flats, Nevada
41 Martin B. Biles, DOS, USAEC, Washington, D.C.
42 J. Doyle, EG&G, Las Vegas, Nevada
43 Richard S. Davidson, Battelle Memorial Institute, Columbus, Ohio
44 Carter D. Broyles, Sandia Laboratories, Albuquerque, New Mexico
45 Maj. Gen. Frank A. Camm, DMA, USAEC, Washington, D.C.
46 Stanley M. Greenfield, Assistant Administrator for Research &
Monitoring, EPA, Washington, D.C.
47 William D. Rowe, Deputy Assistant Administrator for Radiation
Programs, EPA, Rockville, Maryland
-------
Distribution (continued)
48 Ernest D. Harward, Act. Dir. of Technology Assessment, Office
of Radiation Programs, EPA, Rockvilie, Maryland
49 - 50 Charles L. Weaver, Dir., Field Operations Div., Office of
Radiation Programs, EPA, Rockville, Maryland
51 Gordon Everett, Dir., Office of Technical Analysis, EPA,
Washington, D.C.
52 Library, EPA, Washington, D.C.
53 Kurt L. Feldmann, Managing Editor, Radiation Data & Reports,
Office of Radiation Programs, EPA, Rockville, Maryland
54 Regional Radiation Representative, EPA, Region IX, San Francisco,
California
55 Arden E. Bicker, REECo, Mercury, Nevada
56 John M. Ward, President, Desert Research Institute, University
of Nevada, Reno
57 - 58 Technical Information Center, USAEC, Oak Ridge, Tennessee (for
public availability)
------- |