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

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This report was prepared as an account of work sponsored
by the United States Government.  Neither the United States
nor the United States 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.

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                                                            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.

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                                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.

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                                 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

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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

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                           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

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                           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

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                              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.

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                   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

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                               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.

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                                 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.

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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.

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0>
                          W'V  I   \           •'*«      I
                      	—-J    ? ""••""•             !
                              )    '•  *
                      G°ui"<
                                                Figure 1.   Air  Surveillance Network Stations

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Figure 2.  Permanent Gamma Rate Recorder Locations

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         ~ 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

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                             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

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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      \
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                          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.

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                                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

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                               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

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 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

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5 Film Badges
3 TLD and 5 Film Badges
 Figure 5.   Film Badge and Thermoluminescent Dosimeter (TLD)  Network
                                   15

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 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

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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

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                           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

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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)

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