SWRHL-19r
FINAL REPORT OF OFF-SITE SURVEILLANCE
FOR THE
PHOEBUS 1-A EXPERIMENT
by the
Southwestern Radiological Health Laboratory
U. S. Public Health Service
Department of Health, Education, and Welfare
January 17, 1966
This surveillance performed under a Memorandum of
Understanding (No. SF 54 373)
for the
U. S. ATOMIC ENERGY COMMISSION
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LEGAL NOTICE
This report was prepared as an account of Government-sponsored
work. Neither the United States, nor the Atomic Energy Commission,
nor any person acting on behalf of the Commission:
A. Makes any warranty or representation, expressed or implied,
with respect to the accuracy, completeness, or usefulness of the
information contained in this report, or that the use of any infor-
mation, apparatus, method, or process disclosed in this report
may not infringe privately owned rights; or
B. Assumes any liabilities with respect to the use of, or for dam-
ages resulting from the use of any information, apparatus, method,
or process disclosed in this report.
As used in the above, "person acting on behalf of the Commission" in-
cludes any employee or contractor of the Commission, or employee of
such contractor, to the extent that such employee or contractor of the
Commission, or employee of such contractor prepares, disseminates,
or provides access to, any information pursuant to his employment or
contract with the Commission, or his employment with such contractor.
Copy No. 5
Delbert S. Earth
Bioenvironmental Research Proj
SWRHL
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SWRHL-19r
FINAL REPORT OF OFF-SITE SURVEILLANCE
FOR THE
PHOEBUS 1-A EXPERIMENT
by the
Southwestern Radiological Health Laboratory
U. S. Public Health Service
Department of Health, Education, and Welfare
Las Vegas, Nevada
January 17, 1966
This surveillance performed under a Memorandum of
Understanding (No. SF 54 373)
for the
U. S. ATOMIC ENERGY COMMISSION
-------
ABSTRACT
The Southwestern Radiological Health Laboratory provided off-site
radiation surveillance in support of the Phoebus 1-A Experiment
of June 25, 1965. This support consisted of tracking the effluent,
monitoring radiation dosage to the off-site population and collecting
environmental samples in downwind areas. Although off-site con-
tamination occurred as a result of the Phoebus test, the data col-
lected indicate that radioactivity levels did not exceed the safety
criteria established by the Atomic Energy Commission for the off-
site population.
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TABLE OF CONTENTS
ABSTRACT i
TABLE OF CONTENTS ii
LIST OF TABLES AND FIGURES iii
INTRODUCTION 1
I. OPERATIONAL PROCEDURES 3
A. EXTERNAL MEASUREMENTS 3
1. Ground Monitoring 3
2. Dose Rate Recorders 3
3. Aerial Cloud Tracking 4
4. Film Badges 4
B. ENVIRONMENTAL MEASUREMENTS 4
Milk and Water Samples 8
Vegetation 9
II. RESULTS 10
A. GROUND MONITORING 10
B. DOSE RATE RECORDERS 10
C. FILM BADGES 12
D. AIR SAMPLES 12
E. WATER SAMPLES 12
F. MILK SAMPLES 14
G. VEGETATION SAMPLES 17
m' CONCLUSIONS 18
DISTRIBUTION
11
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LIST OF TABLES
Table 1. Threshold detectability at time of count of several
radionuclides in air samples(90% confidence level). 8
Table 2. Meteorological data. 11
Table 3. Analyses of air samples collected following
Phoebus 1-A, EP4. 13
Table 4. Potable water samples collected following
Phoebus 1-A, EP4. 14
Table 5. Analysis of milk samples collected following
Phoebus 1-A, EP4. 15
LIST OF FIGURES
Figure 1. Reactor in testing position. 2
Figure 2. Air surveillance network stations in Nevada. 5
Figure 3. Special air sampling and dose rate recorder
locations following Phoebus 1-A, EP4. 6
Figure 4. Milk and water sampling locations following
Phoebus 1-A, EP4. 16
111
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INTRODUCTION
As a part of the ROVER Program, testing and disassembling of a
series of reactors designated Phoebus is being conducted by
Los Alamos Scientific Laboratory at the Nuclear Rocket Devel-
opment Station (NRDS). The subject of this report is the off-site
surveillance provided by the Public Health Service (PHS) for the
Atomic Energy Commission (AEC) in support of the Phoebus 1-A
Experiment.
The Phoebus 1-A Experiment was conducted at Test Cell C on
June 25, 1965 under conditions identified as Experimental Plan 4.
The nominal operating power was 1100 megawatts. Other experi-
mental plans generated such low power that there was no detectable
off-site radioactivity. The reactor was tested in an upright
position so that the hydrogen coolant exhausted upward along with
escaping fission products. The test configuration is shown in
Figure 1.
Under a Memorandum of Understanding with the Atomic Energy Com-
mission, the U. S. Public Health Service conducts a program of radio-
logical monitoring and environmental sampling in the off-site area
surrounding the Nevada Test Site and the Nellis Air Force Range. The
overall complex of the Nevada Test Site (NTS) and the Nellis Air Force
Range (NAFR) includes the Nuclear Rocket Development Station and
the Tonopah Test Range (TTR) and for simplicity will be called the
test range complex throughout this report.
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Figure 1. Reactor in testing position.
2
(Photograph courtesy of
Los Alamos Scientific Laboratory)
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I. OPERATIONAL PROCEDURES
A. EXTERNAL MEASUREMENTS
1. Ground Monitoring
Ground monitors tracked the reactor effluent passage with
portable instruments. Each monitor was equipped with an
Eberline E-500B, a Precision Model 111 Standard
"Scintillator", and a Victoreen Radector Model No. AGB-
50B-SR.
The Eberline E-500B has a range of 0 to 200 milliroentgens
per hour (mR/hr) in four scales with an external halogen
filled GM tube and a 0 to 2000 mR/hr range from an internal
Anton 302 tube. The Precision Model 111 "Scintillator" is
used primarily for low level detection and provides for a
range of 0 to 5 mR/hr in six scales. The Radector has a
range of 0. 05 to 50, 000 mR/hr on two scales. This instru-
ment employs an inert gas ionization chamber. Errors
associated with these instruments are of the order of +_20%.
2. Dose Rate Recorders
Eberline RM-11 dose rate recorders are placed at twenty-one
stations around the test range complex. These recorders
utilize a Geiger tube detector to document radiation levels at
specific locations. The instrument has a 0. 01 to 100 mR/hr
range and the gamma dose rate is recorded on a 30-hour
strip chart. The RM-11 is accurate to j^20% as calibrated
with a l 37Cs source.
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3. Aerial Cloud Tracking
An Air Force U3-A aircraft, manned by two Public Health
Service monitors equipped with portable instruments iden-
tical to those of the ground monitors, tracked the reactor
effluent to position ground monitors. Public Health Service
cloud sampling aircraft were also used as aids in cloud
tracking. However, their primary purpose was cloud sam-
pling in order to determine cloud size and inventory. The
results of their sampling are reported separately by the SWRHL
Engineering Development Program.
4. Film Badges
During June, the PHS maintained 86 film badge stations off
the test range complex and assigned badges to 168 off-site
residents. The badge used is made up of DuPont type
555 film. This film is accurate to j^50% in the 20 to
100 mR range and +_10% in the 100 to 2000 mR range. The
lower limit of detectability is 20 mR.
B. ENVIRONMENTAL MEASUREMENTS
Ninety-five air samplers were routinely operated in the western United
States at the time of these experiments. Thirty-two of these were
located in Nevada and are presented in Figure 2. Two supplementary
air sampling locations were established for the Phoebus 1-A Experi-
ment and are shown in Figure 3.
All samplers were equipped with Whatman 541 prefilters. A portion
of the routine samplers and both supplementary stations were
equipped with MSA charcoal cartridges. All air sample prefilters
and charcoal cartridges collected following the Phoebus 1-A test
were returned to the Southwestern Radiological Health Laboratory
in Las Vegas for analysis.
4
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N E \V A D A
Q AIM SAMPLER WITH PREFILTER
• AIR MMPLCN WITH PREFM.TER AND
CMAHCOAL CARTNIOK
Figure 2.
Air surveillance network stations in Nevada.
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WARM SPGS.
TWIN SPGS
OfJODIABLO
N£LL/S AIR FORCE
RANGE
0 5 K) 20 30
D Air Sampler with Prefilter
B Air Sampler with PrefilMrB
Charcoal Cartridge
Temporary Air Sampler
RM II
Figure 3. Special air sampling and dose rate recorder locations
following Phoebus 1-A, EP4.
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Prefilters were counted for gross beta activity, and simultaneously
for gross alpha, with a Beckman "Wide Beta" proportional counting
system. This system has an efficiency of approximately 45% for
0. 54 Mev betas and a background of 6 +_ 1 counts per minute. Gross
beta concentrations were computed at the time of count for the
purpose of screening samples and delineating the effluent trajectory.
Samples which were believed to contain fresh fission products were
recounted several times within the first 48 hours. Based on these
counts, an individual decay constant was computed for each sample.
This constant was used to extrapolate the gross beta result to the
end of the collection period.
Prefilters which indicated activity levels greater than 10 pCi/m3
were analyzed for the biologically significant gamma emitting iso-
topes by placement directly upon a 4'x4" sodium iodide crystal. All
reported values are corrected for the decay to the end of the col-
lection period. Since it was not possible to define duration of effluent
passage at all locations, the reported values given as pCi/m3 assume
an average concentration over each entire sampling period. Results
are also reported in — 5— to indicate the potential gross beta
inhalation exposure at each location. This unit is obtained by
multiplying pCi/m3 by the sampling time in seconds.
All charcoal cartridges and some prefilters were analyzed for gam-
ma isotopes by placing each directly on a 4"x4" sodium iodide
crystal coupled to a 400-channel pulse height analyzer set to view
energies from 0 to 2 Mev. The activity on the cartridge should
represent primarily the gaseous radioiodines. Calculations were
performed by an IBM 1620, utilizing a matrix technique. This
method compensates for the mutual interference between isotopes
for a given spectrum by the simultaneous solution of n equations
7
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containing n unknowns, where n represents the number of isotopes
for which solution is sought. Due to time and memory limitations
on the 1620, a value for n = 8 is employed. The input to the com-
puter program is variable so that solution may be made for any
eight isotopes for which standard spectra are available. While this
method is preferable to others for which it is practical to use the
1620, it is impossible to calculate an error interval.
Threshold detectability of several radionuclides is presented in Table 1
and is the result of an examination of previous data collected under the following:
a. Count time in days after fissioning as indicated by
footnotes.
b. Prefilters collect unfractionated fission products
resulting in a complex sprectrum.
c. MSA charcoal collects gaseous fission products only
(primarily iodines).
d. An eight isotope matrix is employed for computation
and isotopes other than those examined are present in
amounts which are small relative to those eight.
e. Natural activity on air samples is approximately five
times system background.
Table 1. Threshold detectability at time of count of several radio-
nuclides in air samples (90% confidence level).
Sample Type
Whatman No. 541
(pCi)
MSA Charcoal
(pCi)
131I 132Te-I
500 1000
200
200 400
100
1 3 3 j 1 35j 14
500 1000
200
200 400
100 -
=°Ba-La
500
200
200
100
Length
of Count
10 min
1 0 min
1 0 min
10 min
Notes
1
2
1
2
1 - counted at less than 3 days after fissioning.
2 - counted at 3 days or more after fissioning.
Milk and Water Samples
After the release of activity from NRDS, milk samples were collected
from three dairy farms and several farms producing milk for their
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own consumption. Each milk sample is counted for 40 minutes
using a 400-channel analyzer viewing an energy range from 0 to
2 Mev. All liquid samples are counted, with no prior preparation,
in 3. 5 liter inverted well aluminum beakers which are placed over a
4"x4" sodium iodide crystal. The lower limit of detection for 1 31I
and l 33I in milk and water is 20 pCi/1 at time of count, and all re-
sults below that value are reported as non-detectable. The reported
values have, at time of count, a 2 sigma error estimate of +_ 15 pCi/1
or + 10%, whichever is greater.
Vegetation Samples
Vegetation samples were collected in the suspected effluent trajec-
tory to indicate deposition on the ground. They were also obtained
at most milk sampling locations, with an effort made to make the
sample representative of the cows' feed. These samples were
taken as early indicators of where milk might be contaminated and
were not intended to yield intake-excretion data. For this reason
the vegetation sample results are reported simply as fresh fission
products present or not present.
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II. RESULTS
Experimental Plan 4 was conducted in the approximate time inter-
val 1315 to 1326 hours PDT on June 25, 1965. A summary of
meteorological conditions on the test day is presented in Table 2.
Heavy rain showers in the area north of NRDS limited aerial
tracking of the effluent; however, initial on-site tracking of the
effluent indicated a 0 bearing. Off-site environmental monitoring
o o
indicated contamination in the sector of 10 to 50 .
A. GROUND MONITORING
A ground monitor assigned to Queen City Summit (65 miles, 15
from Test Cell C) detected cloud arrival at 1615 PDT and measured
a peak dose rate of 0. 065 milliroentgens per hour at 1631 hours.
Dose rates above background persisted at this location and are
believed to have been associated with heavy rain in the area.
Monitoring of Highway 25 north and south of Queen City Summit
on the evening of June 25 indicated that this location was on the
hot line. Queen City Summit is unpopulated.
B. DOSE RATE RECORDERS
Dose rate recorder data collected from Diablo on June 26 indicated
a cloud arrival time of 1630 PDT on June 25, 1965. A net peak dose
rate of 0. 05 mR/hr occurred at 1700 PDT. The dose rate thereafter
-1.15 ^
decayed as t . During previous reactor tests dose rates fol-
lowing cloud passage have dropped sharply; however, "rainout" of
fission products in the Diablo area was probably the cause of the
sustained dose rates greater than the normal background of 0. 025 mR/hr.
10
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Table 2.
Sky condition
Clouds
Visibility
METEOROLOGICAL, DATA
PHOEBUS 1-A, EP4
Full Power Test, June 25, 1965
Brkn. Brkn.
.6 Cumulonimbus, .3 Cirrus
Unrestricted
Upper air data at: Jackass Flats, Nevada, 1310 PDT, 6/25/65
Height
(Ft. MSL)
SFC 3615
4000
5000
6000
7000
8000
9000
10000
11000
12000
13000
14000
15000
Wind Pressure
(Deg/Kts) (mb)
040/08
070/07
140/07
190/10
190/12
190/13
200/13
200/13
200/13
210/13
210/13
210/13
220/13
881
870
839
808
780
750
724
700
673
648
622
599
577
Temperature Dew
( C) Point
<°C)
24.6
23.3
20. 3
17. 0
13. 7
10. 0
7.4
4.8
1.9
-0. 7
-2. 3
-4. 0
-5. 1
4.4
4. 3
3. 5
2.2
1.0
-0. 2
-0.8
-1.6
-3. 0
-4. 2
-5. 2
-6.3
-7. 1
Relative
Humidity
(%)
27
29
33
37
42
49
56
63
70
77
80
84
86
SFC = surface
11
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The recorder data indicated a return to the background level on
June 26. The exposure dose to Diablo due to cloud passage, as-
suming a one hour passage time, was calculated to be 0. 04 mR,
and the infinite dose due to deposition was estimated to be 1.2 mR.
Diablo was the only populated location that received a measurable
external dose. Recorder data collected from Alamo, Caliente,
Pioche and Lund did not indicate dose rates greater than
background.
C. FILM BADGES
Due to the low dose rates encountered off the test range complex
following the Phoebus 1-A test, no film badges were collected
immediately following the experiment. Film badges collected since
the test date have not indicated exposures that could be attributed to
the Phoebus 1-A test.
D. AIR SAMPLES
Charcoal cartridges collected from four locations following
Phoebus 1-A contained isotopes of radioiodine. The analyses are
presented in Table 3. Cartridges collected from Twin Springs
Ranch, Warm Springs, Clark Station, Nyala, Currant, Sunnyside,
Caliente, and Warm Springs Ranch did not contain radioiodines.
Gross beta analysis of prefilters from these locations did not
indicate concentrations greater than normal background levels
(<2 pCi/m3), although strontium-91 was detected on several pre-
filters in concentrations of approximately 1 pCi/m3.
E. WATER SAMPLES
Water samples collected from several potable supplies following
the experiment contained * 31I. Iodine-133 was not detected in any
12
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Table 3. Analyses of air samples collected following Phoebus 1-A, EP4.
Location Air Date Date Gross Beta Activity
(See Figure 3) Volume Time Time Prefilter at End of
(m3) On Off Collection
t~/~: / — *\ /pv-i-secx
Queen City Summit
(unpopulated)
Diablo 541
Alamo 482
Hiko 499
AEC Standards for
Radiation Protection
XKv-A/iii , v rn3 '
6/25 6/26 , , . ,_ ,.,
1551 1145 1'6 1-15x10*
0700 0920 '46 4'36X1°4
6/25 6/26
0700 0730 ' ' X
6/25 6/26 5
0805 0810 ' '
Gamma Pulse Height Analysis
Activity (pCi/m3) at end of collection
lector 131T 132 T 133I 1 35 I
P
C
P
C
P
C
P
C
7. 7
.63
1. 1
.56
.6
.36
100
3.6
.87
2. 1
.21
1.4
. 24
8000
22
2. 1
2.5
1.8
1. 5
1. 0
1000
15
1. 3
ND
1. 2
ND
. 34
4000
-- = gamma pulse height analysis not performed.
ND= not detectable
P = prefilter
C = charcoal cartridge
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of the samples. The results of the analyses are presented in
Table 4. The contamination found in the water could possibly reflect
"rainout" and subsequent runoff into water supplies.
Table 4. Potable water samples collected following Phoebus 1-A, EP4
Location
(See Figure 4)
Caliente
Pioche
Twin Springs Ranch
Blue Jay Maint. Station
Warm Springs Ranch
Date Collected
June 28
July 7
Aug 4
June 28
July 7
July 7
July 28
July 7
July 28
June 28
Aug 4
Radioassay Data
pCi/1 131I
160
100
ND
50
ND
60
ND
160
ND
130
ND
F. MILK SAMPLES
Milk -was sampled at several locations following the Phoebus 1-A
test. The results of the analyses are presented in Table 5. Several
samples -were obtained prior to the effluent passage, as denoted by
an asterisk in the date column. The data indicate that radioiodine
contamination of the area northeast of the test range complex
existed prior to the Phoebus effluent passage. This contamination
is believed due to three prior events: (1) a Chinese mainland nuclear
detonation on May 14, 1965 which introduced low levels of J 31I into
milk supplies over much of the United States, (2) a test of the nuclear
rocket NRX-A3 which was conducted at NRDS on May 20, 1965, and
(3) an accidental release of fission products from the Diluted Waters
event conducted at NTS on June 16, 1965. The latter two events are
14
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Table 5. Analysis of milk samples collected following Phoebus 1-A, EP4.
Location
(See Figure 4)
Stewart's Dairy
Alamo
Schofield Dairy
Hiko
Blue Eagle Rn.
Currant
Manzonie Rn.
Currant
Sharpe Ranch
Nyala
Young Ranch
Caliente
Horlacher Rn
Pioche
McKenzie Dairy
Lund
Date ' r
Collected TT
Hay
6/25/65* x
6/26
6/28
6/29
7/02
7/04
7/05
7/07
7/15
6/25/65*
6/26
6/28
7/02
7/07
6/28/65 x
7/01
7/03
7/04
7/05
7/07
7/18
6/19/65* x
6/28
6/29/65 x
7/07
6/28/65 x
7/06
6/28/65 x
7/07
6/28/65 x
* samples obtained before Phoebus
Pasture Radioiodine
or in feed
Gr. Chop
x ND
P
P
P
--
ND
ND
x ND
P
P
ND
ND
x P
P
—
P
--
P
ND
P
ND
x P
ND
x
--
ND
effluent passage
Analysis
ND
ND
20
20
20
50
ND
30
ND
30
40
50
60
ND
100
180
50
50
30
60
ND
50
20
ND
ND
ND
ND
ND
ND
ND
O
133J
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
40
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
ND
-- no sample collected
ND = not detectable
P = present
15
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LUND
A Me K«nzi«
Dairy
^Monzonie Rn
URRANT
BLUE
JAY STA.
A/Blue Eagle
Rn.
Sharp *.Rn.
NYALA
PIOCHE
Horlocher
Rn.
Schoncld Dairy
CALIENTE
Young Rn.
NELLIS AIR FORCE
ALAMO
Stewarts Dairy
OlWARM SPGS.
BRANCH
LATHROP
WELLST-
A MILK SAMPLE
LOCATIONS
A WATER SAMPLE
LOCATIONS
LAS VEGAS
Figure 4. Milk and water sampling locations following Phoebus 1-A EP4.
16
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reported in SWRHL-18r and the PHS interim report for the Diluted
Waters event, issued November 15, 1965. Some contamination,
however, must be attributed to the Phoebus effluent since I levels
increased and the presence of l 33I (Ti/2 = 20 hrs) and l 32Te-I
(Tj/2 = 77 hrs) was noted on feed samples..
G. VEGETATION SAMPLES
Positive evidence of effluent passage and deposition, as determined
by the presence of 91Sr on vegetation, was obtained at Diablo, Queen
City Summit, and Hiko. Many vegetation samples contained fission
products of intermediate age such as 140Ba-La and 95Zr-Nb. This
contamination may also be associated with the events discussed
above.
17
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III. CONCLUSIONS
The effluent from the Phoebus 1-A Experiment was detected off the
test range complex, but the levels represented small fractions of
the guides cited in the AEC Standards for Radiation Protection,
AEC Manual, Chapter 0524* .
The radiation dose standard for external whole body exposure to an
individual is 500 millirem per year. As discussed on page 12, the
only populated location to receive an external dose was Diablo,
where 0. 04 mR was due to cloud passage and 1. 2 mR was due to
deposition.
The iodine air concentrations as measured by charcoal cartridges
off the test range complex are presented in Table 3. Also presented
are the AEC standards for soluble iodine concentrations. The stand-
ards represent concentrations of radioactivity that should not be
exceeded on a continual basis. For the purpose of applying these
standards, radioactive concentrations in effluents may be averaged
over periods up to one year. Since the levels presented in Table 3
did not exist longer than 27 hours in any instance, it is evident that
the concentrations represented a small fraction of the protection
standards.
(1) U. S. Atomic Energy Commission Manual Chapter 0524,
Standards for Radiation Protection.
18
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The charcoal measured iodine concentrations presented in Table 3
may also be expressed in pCi-sec/m3. By applying the appropriate
conversion factors developed by R. S. Decker an estimate of the
potential thyroid dose may be calculated. The conversion factors
for l 31I and 1 33I are 3. 24xlO~? and 9. 21 x 10"8 millirad/pCi-sec/m3
respectively. The doses due to l 32I and l 3 5I inhalation are negli-
gible. The potential inhalation dose to any off-site location following
Phoebus 1-A was calculated to be less than 0. 1 mR. This may be
compared to the AEC standard for thyroid exposure to an individual
which is 1500 millirem per year.
As seen in Table 4, water samples from five locations contained
1311. The values are all below 300 pCi/1 of l 31I, the AEC protec-
tion standard for continuous exposure. The contamination cannot
be positively identified with Phoebus effluent since J 3 3I was not
detected in the June 28 samples. In addition, air sampling and
ground monitoring data indicate that Warm Springs Ranch was not
in the effluent trajectory; therefore, it is probable that a fraction
of the 1 311 in water from that and other locations was due to one of
the three sources previously mentioned - the Chinese mainland
detonation, the NRX reactor run, and the Diluted Waters event.
Milk sampling following Phoebus 1-A indicated contamination due
to the effluent deposition. If one scales directly from data in
(3)
FRC Report No. 5 , Table 1, it can be calculated that a dose of
21 millirad could have been delivered to the thyroids of residents
at Blue Eagle Ranch. The dose prediction assumes the conditions
(2) "Radiological Prediction and Monitoring of Tests at the Nuclear
Rocket Development Station", P. Griffiths and P. Erickson,
Space Nuclear Propulsion Off ice--Nevada, November 1965.
(3) "Background Material for the Development of Radiation Protection
Standards" Report No. 5 of the Federal Radiation Council, July 1964.
19
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presented in FRC No. 5 and that the contamination was the result
of Phoebus deposition alone. As discussed in the milk results
section, the latter assumption is probably not precise. The
21 millirad value represents 1. 3% of the 1500 millirem standard.
20
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DISTRIBUTION
1 - 15 SWRHL, Las Vegas, Nevada
16 James E. Reeves, Manager, NVOO, AEC, Las Vegas, Nev.
17 R. H. Thalgott, NVOO, AEC, Las Vegas, Nevada
18 O. H. Roehlk, NVOO, AEC, Las Vegas, Nevada
19 H. G. Vermillion, NVOO, AEC, Las Vegas, Nevada
20 Col. E. G. Halligan, DASA, NVOO, AEC, Las Vegas, Nev.
21 Central Mail & Records, NVOO, AEC, Las Vegas, Nevada
22 Bryce L. Rich, LRL, Mercury, Nevada
23 - 25 R. H. Goeckermann, LRL, Livermore, California
26 H. T. Knight, LASL, Jackass Flats, Nevada
27 Keith Boyer, LASL, Los Alamos, New Mexico
28 W. E. Ogle, LASL, Los Alamos, New Mexico
29 H. S. Jordan, LASL, Los Alamos, New Mexico
30 Orin Stopinski, LASL, Los Alamos, New Mexico
31 James G. Terrill, Jr. , DRH, PHS, Washington, D. C.
32 Raymond Moore, DRH, PHS, Dallas, Texas
33 Vincent Vespe, ALOO, AEC', Albuquerque, N. Mex.
34 - 36 G. M. Dunning, AEC, Washington, D. C.
37 R. E. Baker, AEC, Washington, D. C.
38 J. S. Kelly, AEC, Washington, D. C.
39 Brig. Gen. D. L. Crowson, DMA, AEC, Washington, D. C.
40 P. W. Allen, ARFRO, ESSA, NVOO, Las Vegas, Nevada
41 H. Mueller, ARFRO, ESSA, NVOO, Las Vegas, Nevada
42 M. I. Goldman, NUS, Washington, D. C.
43 - 46 B. P. Helgeson, SNPO-N, Jackass Flats, Nevada
47 David Smith, SNPO-C, Cleveland, Ohio
48 R. S. Decker, SNPO, USAEC, Washington, D. C.
49 - 50 J. E. Faulkner, WANL, Pittsburg, Pennsylvania
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Distribution - continued
51 Perry Davidson, WANL, NRDS, Jackass Flats, Nevada
52 V. M. Milligan, REECo, Mercury, Nevada
53 N. E. Erickson, Aerojet General Corp., Jackass Flats, Nev.
54 H. G. Simens, Aerojet General Corp. , Jackass Flats, Nevada
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