FINAL REPORT OF OFF-SITE SURVEILLANCE
                     FOR THE
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                       by the
    South-western Radiological Health Laboratory
            U. S. Public Health Service
   Department of Health, Education, and Welfare
                Las Vegas, Nevada
                  February 3, 1965
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 information,  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 damages
resulting from the use of  any information,  apparatus, method,  or pro-
cess disclosed in this report.

As  used in the above, "person  acting on behalf  of the  Commission"
includes 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,  dissemin-
ates,  or provides access to, any information pursuant to his employ-
ment  or contract with the Commission, or  his  employment with such
contractor.
  01

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                                                  SWRHL-l6r
  FINAL, REPORT OF OFF-SITE SURVEILLANCE
                     FOR THE
              NRX-A2 EXPERIMENT
                       by the
    Southwestern Radiological Health Laboratory
            U. S. Public Health Service
   Department of Health, Education, and Welfare
                Las Vegas, Nevada
           Copy No.  1

           0. R.  Placak
           SWRHL
           Las Vegas, Nevada
                 February 3,  1965
This surveillance performed under a Memorandum of
           Understanding (No. SF 54 373)
                      for the
       U. S. ATOMIC ENERGY COMMISSION

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                            ABSTRACT







The Public Health Service provided off-site surveillance in support of



the NRX-A2 reactor tests conducted on September 24 and October 15,



1964.  This  support  consisted of tracking the effluent,  monitoring



radiation dosage to the off-site  population,  and collecting environ-



mental samples (air, milk,  water and vegetation).  Analyses of these



data  indicate  that no  hazard •was created to the off-site  population



from the NRX-A2 tests.

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                      TABLE OF CONTENTS





ABSTRACT                                                         i



TABLE OF CONTENTS                                             ii



LIST OF FIGURES                                                 iii



LIST OF TABLES                                                  iii



INTRODUCTION                                                    1



Section 1.  NRX-A2 EPIV, September 24, 1964



           I. ,  OPERATIONAL PROCEDURES                        2



                A.  External Measurements                          2



                B.  Environmental Measurements                    4



           II.  RESULTS                                            9



                A.  Ground Monitoring Data                          9



                B.  Dose Rate Recorder Data                       10



                C.  Film Badge Data                               10



                D.  Air Sample Data                                11



                E.  Milk Sample Data                               12



                F.  Water Sample Data                             12



          III.  CONCLUSIONS                                      14



Section 2.  NRX-A2 EPV, October  15,  1964



           I.  OPERATIONAL PROCEDURES                       15



           II.  RESULTS



                A.  Ground Monitoring Data                         16



                B.  Dose Rate Recorder Data                       16



                C.  Film Badge Data                               16



                D.  Air Sample Data                                16



                E.  Milk Sample Data                               17



                F.  Water Sample Data                             17



                G.  Vegetation Sample Data                         19



          III.  CONCLUSIONS                                      20





                                ii

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                        LIST OF FIGURES


Figure 1.  Location of air samplers and dose  rate recorders for
           NRX-A2 EPIV.                                           3

Figure 2.  Location of air samplers and dose  rate recorders for
           NRX-A2 EPV.                                            5

Figure 3.  Environmental sampling locations for EPIV and EPV.     18
                        LIST OF TABLES


Table 1.  Dose rate measurements off the test range complex on
          September 24,  1964.                                       9

Table 2.  Meteorological Data for EPIV.                            10

Table 3.  Analysis of air samples collected following the NRX-A2
          EPIV Experiment.                                        11

Table 4.  Analyses of milk and vegetation samples collected
          following NRX-A2 EPIV.                                  13

TableS.  Meteorological Data for EPV.                             17
                                111

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                         INTRODUCTION

As' a part of the  ROVER Program, testing and disassembling of a
series of reactors designated NRX-A is being carried on under the
Nuclear  Engine for Rocket  Vehicle  Application (NERVA) Project at
the Nuclear Rocket Development Station.  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 NRX-A2
experiments conducted at Test Cell A onSeptember 24 and October 15,
1964.  Each test will be  covered in a separate section of this report.

Under a Memorandum of Understanding with the Atomic Energy
Commission,  the  U. S.  Public  Health Service conducts  a  program
of radiological 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 Devel-
opment Station (NRDS) and the Tonopah Test Range (TTR) and for
simplicity will be called the test range complex throughout this
report.

Since Public Health Service monitors  must begin tracking and moni-
toring an effluent  cloud  close to its  point of origin, measurements
are also made  within the test range complex, but  are used  only as a
guide to  trajectory determination or for  purposes of checking instru-
mentation and methodology.   They did  not serve  as parameters in
determining dose to people  or contamination of  property  in  the
off-site area during the NRX-A2 tests  and are  not a subject of this
report.
                                 1

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          Section 1.  NRX-A2 EPIV, September 24, 1964
                I.  OPERATIONAL PROCEDURES

On September 24,  the reactor was tested under the conditions  known
as Experimental Plan IV (EPIV)  and  was operated  at  design  power
from 1055 to 1105 PDT.   The reactor  was tested in an upright posi-
tion so that  the hydrogen coolant exhausted upward along with escap-
ing fission products.
A.  External Measurements
    Ground Monitoring
    Thirteen  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) gamma and beta-gamma detection 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 pro-
    vides for a range  of  0 to 5 mr/hr in six scales.   The Radector
    has a range of 0 to 50, 000 mr/hr on two  scales. This instrument
    employs an air  ionization chamber.  These  instruments are
    accurate to +_ 20%,  and readings can be  taken to two significant
    figures.
    Remote Dose Rate Recorders
    Eberline RM-11 dose rate recorders were placed at sixteen  sta-
    tions around the  test range complex.  These recorders utilize  a
    Geiger  tube  detector to document radiation levels at specific lo-
    cations.   The instrument has a 0. 01 to 100 mr/hr  range and the
                                2

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Figure 1.  Location of air samplers and dose rate recorders for NRX-A2 EPIV.



                                     3

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    gamma dose rate is recorded on a 30-hour strip chart.   The

    RM-11  is accurate  to +_ 20% as calibrated with a Co    source.
    The  locations of dose rate recorders are presented in Figure 1.
    Aerial Cloud Tracking
    An Air Force U-3A aircraft, manned by two Public Health Service

    monitors equipped with portable instruments identical to those of
    the ground  monitors, tracked the reactor  effluent to position

    ground monitors.  Two Public Health Service C-45  aircraft con-
    taining  sampling equipment were  also used as aids  in cloud
    tracking.  However,  their primary purpose  was cloud sampling
    in order to determine cloud size and  inventory.  The results of

    their  sampling are reported separately.


    Film  Badges

    The PHS maintains 65 film badge stations off the test range  com-

    plex and assigns  badges to 166 off-site  residents.  The badge

    used is  made up of Dupont Type  555 film.   This film is accurate
    to +_50% in the 20 to  lOOmr range and +_10% in the 100 to 2000 mr

    range.

B.  Environmental Measurements

    Air Samples
    On the test day the  PHS  maintained General Metal  Works  high
    volume  air samplers containing glass  fiber prefilters at 36
    off-site locations as  shown in  Figures 1 and 2. Thirteen of the

    air samplers were  equipped with  MSA* charcoal cartridges  in

    addition to  the prefilters.  All  air sample prefilters  collected

    following the NRX reactor runs were returned to the Southwestern
    Radiological Health  Laboratory (SWRHL)  in Las Vegas to be

    counted for  gross beta activity  with  a thin  window, large area
    *Mine Safety Appliance Company
                                4

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Figure 2.   Location of air samplers and dose rate recorders for NRX-A2 EPV.



                                      5

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proportional probe connected to a high speed sealer.  The sys-


tem has an efficiency  of  approximately 30% for 1. 5 Mev betas



and has a background of 575 +_ 20 counts per minute.




Gross  beta concentrations were  computed at  the time  of count


for the purpose of screening samples and delineating  the effluent



trajectory.  These samples were then stored for  five  days to


allow  natural activity to decay.   They were recounted at this


time and again seven days later.  Activity levels were then re-


computed to end of collection from these two later counts.  Sev-


eral air  samples exhibiting levels of activity  significantly above


natural background were recounted frequently to obtain a decay


curve.  The curve  obtained was then analyzed for best  fit to the


general equation y=ax .  Based on an analysis of decay  curves,


a T  '    relationship was  found to exist with a mean error of


_+ 5%.  This relationship was then used  to extrapolate  the activity


to the  end of the collection period.




All charcoal cartridges were analyzed for gamma isotopes  by


placing each cartridge directly on a 4" x 4" sodium iodide crys-


tal coupled to a 400-channel pulse height  analyzer set to view


energies from  0 to 2 Mev.  Assuming no break in the prefilter,


the activity on  the cartridge  should represent the gaseous fission


products such as isotopes  of iodine. Overall  detection efficiency


for this  geometry  is about 18% at 0. 53 Mev (I   ).  The mini-


mum detectable activity for I   ,1    ,1    , and I     is taken

                                                          131
to be 200 picocuries with an associated error of + 50% for I    ,



I   ,1   , and +_ 100% for I   . The time of count is 10 minutes.


Error  estimates are such  that values  less than 1 picocurie per


cubic meter (pc/M ) are generally not reported.  Since it is not


possible to define  duration of effluent passage at all locations.

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the reported values given as  pc/M  assume an average concen-
tration over each entire sampling period.
Milk and Water Samples
After each  release of activity from NRDS,  milk samples are
collected  from dairies  (processing plants),  producing dairy
farms,  and farms producing  milk for their  own consumption.
Milk samples were collected,  relative to this event, from the
locations  shown in Figure 2.   Each sample  w a s counted  for
50 minutes.   No  attempt  was  made to recount  samples  giving
low positive values.  The lower limit of detection  for  gamma
emitters  in milk samples is taken to be  20  picocuries  per
liter (pc/1)  at the time of  count, and all results below that value
are reported as <20 pc/1.  The  error associated  with reported
values is _+ 20  pc/1.  All  reported  values are extrapolated to
collection time.
All liquid samples are counted  in 3. 5 liter inverted well alumi-
num beakers which are placed on top of a 4" x4" crystal coupled
to a 400-channel gamma pulse  height analyzer.  Overall detec-
tion efficiency for the 0. 364 Mev photo-peak of I    is 6.4%.  A
matrix  technique  is employed  in computation to compensate for
the interference due to the presence of other  isotopes.  The in-
put to  this  matrix i s  variable, allowing for the  simultaneous
determination of any eight nuclides  for which  detection efficien-
cies  and interference  factors have  been obtained.  Actual com-
putation is performed by an IBM 1620 computer.

Vegetation Samples
Vegetation samples were obtained at  most milk sampling loca-
tions. An attempt was made to  make the  samples representative
of the cow's feed; however,  the samples  were taken primarily
                            7

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as early indicators of where  milk might  be  contaminated  and



were not intended to yield a cow intake-excretion formula.  For



this reason the vegetation samples are reported simply as fresh



fission products present or not present.

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                          II RESULTS


Experimental Plan IV re suited in low levels of radioactivity being de-

tected off the test range complex.  Radiation monitors  were posi-
tioned in an area southwest of the test area according to information

furnished by aerial monitors and the  U. S. Weather Bureau.  (See

Table  2).

A.  Ground Monitor Data
    Gamma dose rates above background were detected in the vicin-
    ity of Lathrop Wells, on Highway 95, and at  Dansby's Ranch
    located 10 miles southwest of Lathrop Wells. (See Table 1 below).
    Lathrop Wells has a population of about fifty people.  Monitoring

    at these places on the day following the test produced only back-
    ground readings.  Monitors  were  also called  upon to check the
    off-site area during the night  following the  test when activity was

    detected on the NRDS.  Readings above background were found
    off the test range complex  for five  miles  along Highway 95

    starting nine miles  northwest of Lathrop  Wells. The maximum

    reading of 0. 12 mr/hr was found 9. 8 miles NW of Lathrop Wells

    at approximately  0100 hours on September 25.

Table  1.  Dose rates occurring off the  test range complex on
          September 24,  1964.
Location
(See Fig. 1)
Lathrop Wells
Dansby's Ranch
Hwy 95(4.5 mi NW
of Lathrop Wells)
Time of Peak
Dose Rate
(PDT)
1234
1320
1220
Time of dose rates
greater than
background
1215-1500
1250-1450
1240-1330
Net Peak
Dose Rate
(mr/hr)
0.43
0. 07
0. 23

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Table 2.   Meteorological Data for EPIV
Upper Air Data:  Jackass Flats, Nevada, 1100PDT, September 24, 1964
Height
Wind
                     Pressure   Temperature  Dew Point   Relative
(Ft. MSL)
SFC
4000
5000
6000
7000
8000
9000
10000
11000
12000
13000
14000
(Deg/Kts)
070/18
060/22
060/13
080/11
040/04
030/04
090/08
090/08
098/11
080/12
073/18
070/19
(mb)
895
883
854
824
794
768
738
712
687
662
638
614
,o .
28. 6
25. 0
22. 7
20. 0
17. 3
15. 3
12.9
10. 7
8. 0
5. 5
3.6
1. 7
<°C)
0.6
- 3.4
- 2. 7
- 3.6
- 4. 0
- 4. 2
- 4.6
- 5.6
- 7.6
- 9. 1
-12. 6
-18.8
Humidit-
15
15
18
20
23
26
29
31
32
34
29
20
B.  Dose Rate Recorder Data
    The recorder at  Lathrop Wells indicated radioactivity associ-
    ated with effluent from the NRX-A2 test on September 24.  This
    instrument recorded a net peak dose rate of 0.18  mr/hr at
    1230 hours PDT.  The time interval in which  the dose rate ex-
    ceeded  background was 1210 to 1340 hours and the estimated
    external dose during cloud passage was  0. 08 mr.

C.  Film Badge Data
    Due to  the low dose rates encountered at points south and west
    of the test range  complex, no off-site film badges were collected
    immediately following the NRX-A2 test. Badges collected  since
    that time,  however; have had no exposure  which could be attri-
    buted to the EPIV test.
                                10

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D.  Air Sample Data
    Several samples taken following the test contained fresh fission

    products.  The results of  analysis of the prefilters and charcoal

    cartridges are presented in Table 3.

Table 3.   Analysis of air  samples containing  fresh  fission products
          collected following the NRX-A2 EPIV  Experiment reported
          in  c/M-^ at end of collection.
             ON        OFF    Vol-   Prefilter
Location  Time-Date Time-Date ume    Gross
             PDT       PDT     (M3)   Beta
	Activity
  Gamma Pulse
Height Analysis

jlSl  133   135
Lathrop   0715, 9-24 1455, 9-24  261     450
 Wells
          1500,9-24 0715,9-25  553     2.3


Dansby    1050, 9-24 1550, 9-24  183     420
 Ranch

Death     0940,9-24 1500,9-24  211     2.5
 Valley Jet.
          1500,9-24 0625,9-25  642     2.2


Stovepipe  1045, 9-24 1500, 9-24  181      <1
 Wells
          1510,9-24 1030,9-25  804     1.5


Furnace   1100,9-24 1500,9-24  146     3.6
 Creek
          1510, 9-24 0955, 9-25  750      19
                                                P
                                                C
                                                P
                                                C
                                                P
                                                C
  13
  <1

 ND

  12
57
42
55
45
 84
 37

ND
 82
ND
                                                C  ND  ND   ND
                                                P
                                                C  ND   <1   ND
                                                P
                                                C  ND  ND   ND
                                                P  0.5  2.4   3.5
                                                C   <1  4. 9   ND
                                                P
                                                C  ND  ND   ND
                                                P  0.5  2.4   3.5
                                                C   <1  3. 9   ND
P=prefilter    C = charcoal cartridge    ND=not detectable

    Air samples  taken on September 24  atScotty's  Castle,  Beatty

    and Springdale showed no fresh fission products when analyzed.
                                11

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E.  Milk Sample Data


    Milk samples obtained on the test day and the two following days

                                              133
    at Dansby's Ranch indicated low  levels of I    .  Iodine-131 was


    not present in detectable quantities. Dansby's  Ranch is 22 miles


    southwest of  Test Cell A.  Six other milk samples  collected did


    not contain fresh  fission products in  detectable quantities.


    (See Table 4).  The cesium values  reported are within the range


    of  the  cesium  levels  generally  found in the particular  areas


    sampled.



F.  Water Sample Data


    Water samples collected on the day of the test at Dansby's Ranch


    and the  day after the  test at the  Watson and Selbach Ranches


    near L/athrop Wells, Lathrop Wells Gas Station,  Furnace Creek


    and Stovepipe Wells did not  show detectable levels  of radio-


    activity.
                                12

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       Table 4.  Analyses  of milk  and  vegetation samples collected following NRX-A2 EPIV
COLLECTION DATA
LOCATION
(Azimuth and Distance
from Test Cel 1 A)
Dansby Ranch
Lathrop Wei 1 s
225° 22 mi .

Hunter's Ranch
Olancha, California
248° 100 mi.
Lone Pine Dai ry
Lone Pine, California
261° 98 mi.
M&R Cattle Company
Canti 1 , Cal i forni a
221° 140 mi .
Hills Dai ry
Barstow, California
200° 140 mi .
DATE
COLrf&TED
9-24
9-25
9-26
9-27
9-26


9-26


9-27

9-27


Milk Radioassay Data
ACTIVITY (pc/l)
,13. ,133 Cs137
<20 200 20
<20 70 30
<20 20 20
<20 <20 25
<20 <20 65


<20 <20 40


<20 <20 40

<20 <20 20


Vegetat ion
Samples
Taken
P
P
P
— — —
ND


ND


ND

ND


OJ
      ND=fresh  fission  products  not  present  in  vegetation.
       P=presence of  fresh  fission products  in  vegetation  samples.
     	=vegetation samples not  taken.

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                        Ill CONCLUSIONS






The NRX-A2 test of September 24,  1964, yielded low levels of radio-



activity to the off-site area.  The effluent was encountered in a small



area of the  Armagosa Desert between Death Valley Junction, Stove-



pipe Wells,  and the NRDS.  Fresh fission products were detected as



far away as Stovepipe Wells (45 miles) and Furnace Creek (40 miles)



in the form  of radioiodines on air filters. In both cases the concen-



trations were less than five picocuries per cubic meter  of air.   The



maximum levels  of radioactivity  detected off the test range complex



were found at Lathrop Wells,  Nevada.   These  levels of 0.43 mr/hr



net gamma and 450 pc/M3 of gross beta activity were not considered



health hazards to the population.






Environmental samples  collected following  the  test did not show de-



tectable amounts of radioactivity more than thirty miles  from NRDS.



Only one milk cow was in the effluent path -within 80 miles of the test



area.  This cow was located at  Dansby's Ranch which  is 22 miles



south-west of Test Cell A and eight miles south-west of Lathrop Wells,



Nevada.   Although the  milk from this cow was not  used for human



consumption at the time of the  test, samples were taken for several



days following NRX-A2 EPIV.  This milk contained no I    in detect-



able  quantities and the  peak I    concentration was  200 pc/1 -which
occurred on the day of the test. Since this milk sample -was  collected



only two to three hours  after  cloud



milk -was evidently due to inhalation.
only two to three hours  after  cloud  passage, the I    found in the
                                14

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            Section 2.  NRX-A2 EPV, October 15,  1964





                I.  OPERATIONAL PROCEDURES





The reactor was tested under the conditions known as Experimental



Plan V (EPV) on October 15, 1964 at 1210 hours PDT.  The test was



approximately a twenty minute  run at less than 20 per cent of design



power.  The reactor  was in an upright position so that the fission



products exhausted upward.





The operational procedures followed on this experiment were simi-



lar to those used in support of the September 24 test.
                               15

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                          II.  RESULTS






On October  15,  1964  Experimental  Plan V  was conducted with low



levels of radioactivity being detected northeast of the test range  com-



plex.  A summary of weather conditions at 1230 on the test day is



presented in Table 5.





A.  Ground Monitor Data



    Due to  the  low dose  rates encountered by aerial monitors,  no



    ground  monitors were positioned off the test range complex.



    However,  ground monitors  located  on the test range complex



    downwind from the reactor encountered no readings above back-



    ground.





B.  Dose Rate Recorder Data



    RM-11  recorder charts collected following NRX-A2 EPV  indi-



    cated no dose rates above background.





C.  Film Badge Data



    Due to the low dose rates encountered, no film  badges  •were col-



    lected immediately following the NRX-A2 test.  Badges collected



    since that time, however;  have  had no exposures which could be



    attributed to the EPV  test.





D.  Air Sample Data



    Only one  off-site  air  sample contained detectable quantities of



    fresh fission products. The charcoal cartridge at Indian Springs



    showed 150 total picocuries of I   .  This sample was  started at



    1800 on the test day and the air sampler motor failed during the



    night. However; if the sampler  ran for only two hours, 150 total



    picocuries would b e   less than one  picocurie  per cubic meter





                                16

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    on the filter.  Although the effluent from EPV went to the north-

    east, it is believed that northerly drainage winds carried some

    radioactivity to the south during the night resulting in radioiodine

    being detected at Indian Springs.


Table 5.   Meteorological data  for EPV.
Upper air data at: Jackass Flats, Nevada, 1230 PDT, October 15, 1964

 Height     Wind    Pressure  Temperature  Dew  Point  Relative
(Ft. MSL) (Deg/Kts)      (mb)       ( C)          (°C)    Humidity
SFC
4000
5000
6000
7000
8000
9000
10000
11000
12000
13000
14000
Calm
250/02
220/02
180/02
140/01
180/02
180/04
170/05
180/08
180/12
170/16
180/16
892
880
850
821
791
752
735
711
686
659
634
611
28. 3
26. 8
23. 3
20.4
17. 5
14.6
12. 1
9. 1
6.4
3. 2
0. 8
- 1.9
- 1.8
- 2.0
- 2.4
- 3.4
- 4. 0
- 4. 8
- 5. 0
- 6. 0
- 6. 3
-7.3
- 6.3
-11. 0
14
15
18
20
23
26
30
34
40
46
51
50
E.  Milk Sample Data
    Milk samples were collected at Lund, Nevada on October 16 and

    at Alamo and Hiko on October 20. These samples did not contain
    detectable quantities of fresh fission products.

F.  Water Sample Data
    A water sample collected from a water trough at Goss Ranch on
    October 16

    the sample.
October 16 contained 75 pc/1 of I   .  No I    was detectable in
                                17

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                               r  V3C4 _. \c     If  !
                               \r^.^ \MfAO If
Figure 3.  Environmental sampling locations for EPIV and EPV.
                               18

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G.  Vegetation Sample Data
    In order to determine cloud trajectory, vegetation samples were
    collected at Goss Ranch, Hiko and Alamo, Nevada.  The samples
    from Goss Ranch and Hiko contained low levels of  fresh fission
    products.
                                19

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                        III.  CONCLUSIONS





The  NRX-A2  EPV experiment of  October 15,  1964,  yielded low



levels  of  radioactivity off  the  test range complex.  The effluent



was found in an area northeast of the test range complex between



Test Cell A and Hiko, Nevada.





Low levels of fresh fission products -were found on vegetation sam-



ples collected at Goss Ranch and Hiko  and  in  a water sample from



Goss Ranch but no radioactivity was found in milk sampled at Hiko,



Lund and Alamo.  It  is  concluded  that the  radioactivity  from  this



test did not  constitute a  hazard to the  off-site  population.
                               20

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                         DISTRIBUTION

 1-15    SWRHL, Las  Vegas,  Nevada
   16    G.  D.  Ferber, USWB,  MRPB (R-3. 3), Washington, D.  C.

   17    Phillip W.  Allen,  USWB, NVOO, Las Vegas, Nevada

   18    Harold Mueller,  USWB, NVOO, Las Vegas, Nevada

19-20    Col. E.  G.  Halligan,  DASA, NVOO,  Las Vegas, Nevada

   21    C.  S.  Maupin, REECo, Mercury,  Nevada
   22    V.  M. Milligan,  REECo, Mercury, Nevada
   23    Vincent Vespe,  ALOO,  Albuquerque, New Mexico
24-26    George T.  Anton, SNPO-N, Jackass Flats, Nevada
   27    B.  P.  Helgeson, SNPO-N, NRDS,  Jackass Flats, Nevada

   28    John C.  Gallimore, WANL, NRDS,  Jackass Flats,  Nevada
   29    Morton I. Goldman,  NUS,  Washington, D.  C.

   30    Elmer Hemmerle, Westinghouse Electric Corp. ,  Pittsburgh,  Pa.

   31    David  Smith,  Lewis Research Center, SNPO-C, Cleveland, Ohio

   32    John M. Wright, SNPO-N, Jackass Flats,  Nevada
   33    Hugo G. Simens, NERVA Test Opns. , Aerojet-Gen. Corp. ,
                 Jackass  Flats, Nevada

   34    Bernd Kahn, DRH, RATSEC,  Cincinnati, Ohio

   35    Raymond Moore, DRH, PHS,  Region VII,  Dallas, Texas

   36    James G. Terrill Jr. ,  DRH, PHS, Washington, D.  C.

37-39    Robert H.  Goeckermann, LRL, Livermore, California
   40    John W. Gofman,  LRL,  Livermore,  California
   41    Keith Boyer,  LASL,  Los Alamos,  New Mexico

   42    Charles I. Browne,  LASL, Los Alamos, New Mexico
   43    Alvin  C. Graves, LASL, Los Alamos, New Mexico
   44    Harry S. Jordan, LASL, Los Alamos, New Mexico
   45     L.  D. P. King, LASL, Los Alamos, New Mexico

   46    Herbert T. Knight, LASL, NRDS,  Jackass Flats,  Nevada

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DISTRIBUTION (cont1)

47     William E. Ogle, LASL, Los Alamos,  New Mexico
48     Fred Sanders, LASL, Mercury,  Nevada
49     Oren Stopinski, LASL, Los Alamos, New Mexico

50     James E.  Reeves, Manager^  NVOO, AEC, Las Vegas,  Nevada

51     Otto H. Roehlk,  OSD, NVOO, Las  Vegas, Nevada

52     Henry G. Vermillion, NVOO, AEC, Las  Vegas,  Nevada

53     Robert E.  Baker, AEC, Washington, D.  C.
54     Col. Ralph S. Decker,  SNPO, Washington, D. C.

55     Gordon M. Dunning,  DOS, AEC,  Washington, D. C.

56     Brig.  Gen. D. L. Crowson,  DMA,  AEC,  Washington, D.  C.

57     Mail & Records, NVOO, AEC, Las Vegas, Nevada

58     J. A.  Mohrbacher, Radiation Services, Pan American,  NRDS,
             Jackass Flats, Nevada

59-75  Author's copies

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