EPft-520/S-77-0
                 RADIOLOGICAL SURVEY OF
              PU6ET SOUND NAVAL SHIPYARD
                BREMERTON,  WASHINGTON,
                      AND ENVIRONS
     KINTAL PROTECTION AGENCY
Office of Radial ion Programs

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                                      EPA-52Q/5-77-001
RADIOLOGICAL SURVEY OP PUGET SOUND NAVAL SHIPYARD




       BR1M1RTON, WASHINGTON, AND ENVIRONS










                   R. S. Callis




                   S. T. Windham




                   C. R. Phillips




     Eastern Environmental Radiation Facility




                  P. O. Box 3009




           Montgomery, Alabama  36109
                  February 1977

      U. S. ENVIRONMENTAL PROTECTION AGENCY



           Office of Radiation Programs



               Waterside Mall East



               401 M Street, S.W.



              Washington, DC  20460

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                        FOREWORD
     The Office  of  Radiation  Programs  carries  out  a
national program designed to evaluate the exposure of man
to ionizing and nonionizing radiation, and to promote the
development  of  controls necessary to protect the public
health and safety and assure environmental quality.

     Technical  reports  allow  comprehensive  and  rapid
publishing   of   the  results  of  Office  of  Radiation
Programs' intramural and contract projects.  The  reports
are  distributed  to  State and local radiological health
offices, Office of Radiation Programs' technical and  ad-
visory  committees,  universities, laboratories, schools,
the press, and other interested groups  and  individuals.
These reports are also included in the collections of the
Library   of   Congress   and   the   National  Technical
Information Service.

     I encourage readers of these reports to  inform  the
Office  of Radiation Programs of any omissions or errors.
Your additional comments or requests for  further  infor-
mation are also solicited.
                                 W. D. Rowe, Pli.D.
                          Deputy Assistant Administrator
                              for Radiation Programs

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                      PREFACE
     The Eastern Environmental Radiation Facility  (EERF)
participates in the identification of solutions to prob-
lem areas as defined by the Office of Radiation Programs.
The Facility provides analytical capability for evalua-
tion and assessment of radiation sources through environ-
mental studies and surveillance and analysis.  The EERF
provides technical assistance to the State and local
health departments in their radiological health programs
and provides special analytical support for Environmental
Protection Agency Regional Offices and other federal
government agencies as requested.

     This study is one of several EERF projects designed
to assess environmental radiation contributipns from the
operation of nuclear-powered vessels,
                          Charles R. Porter
                                Director
                Eastern Environmental Radiation Facility

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                     CONTENTS

                                                  Page

FOREWORD	    i

PREFACE	   ii

LIST OF TABLES AND FIGURES	  iii

INTRODUCTION	    1

Characteristics of the Puget Sound Naval Shipyard
  and the Environs	    1

Survey and Analytical Methods	    2

Results and Discussion	    6

Conclusions	,	   16

References	   17


                      TABLES

1.  Results of aquatic life sample gamma analyses    7
2.  Results of air sample analyses	'	    9
3.  Results of vegetation sample analyses	    9
4.  Results of silt sample analyses	*...   10
5.  Results of core sample analyses	   13
6.  Exposure measurements observed over land.....   14
7.  Exposure measurements observed over water....   15


                     FIGURES

1.  Sampling locations in the area	    3
2.  Sampling locations in the harbor	    4
3.  Locations of probe counts taken	    4
4.  Silt sampling locations	   11
5.  Core sampling locations	   11
6.  Locations of external gamma radiation
      measurements	   13

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 Introduction

      The  Eastern Environmental Radiation Facility (EERF)
 of the  U.  S.  Environmental  Protection Agency (EPA),  in
 cooperation with the  U.  S.  Naval  Ship Systems Command
 (NAVSHIPS)  has  conducted radiological surveillance pro-
 grams in  a number of  ports  which  serve nuclear-powered
 vessels.   These studies  were  begun in 1963  and have  been
 conducted at ports on the East, West, and Gulf Coasts of
 the Continental United States and in Pearl  Harbor, Hawaii.
 These studies were undertaken to  determine  if nuclear-
 powered vessel  operations,  including berthing, repair, and
 servicing,  had  resulted  in  environmental radioactivity
 levels  which could contribute a detectable  radiation expo-
 sure to the public.   The survey of the harbor at Bremerton,
 Washington, in  October 1974,  was  the latest in this  series.

      This survey differed somewhat from previous ones.
 Meetings  were held with  both  NAVSHIPS and Puget Sound Naval
 Shipyard  (PSNS)  for the  purpose of providing EPA personnel
 with information on past and  present shipyard radiological
 operations and  procedures.  All requested information was
 freely  provided verbally and/or written.  The information
 requested was for the purpose of  determining sample  loca-
 tions,  procedures and types,  as well as nuclides and ap-
 proximate activities  to  be  expected.  Based on the infor-
 mation  received and that derived  from previous studies,
•EPA independently designed  the study to meet the above
 objectives.

 Characteristics of the Puget  Sound Naval Shipyard and the
   Environs

      PSNS is located  on  Sinclair  Inlet,  an  embayment off
 central Puget Sound,  approximately 24 kilometers west of
 Seattle,  Washington.   The shipyard is located adjacent to
 the City  of Bremerton, Washington.

      The  Inlet  is approximately 4.8 kilometers long  and
 1.2 kilometers  wide.   Inlet water depths at mean low tide
 range from approximately 6  meters at the southwest end to
 approximately 27 meters  at  the northeast end near Port
 Orchard.   Overhaul and repair of  nuclear powered vessels
 at this shipyard was  begun  in 1967.   The silt and core
 samples collected during the  survey and data from United
 States  National Oceanic  and Atmospheric Administration

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maps indicate that the bottom of Sinclair Inlet is mostly
mud with rocks at some locations.  Due to the relatively
wide, shallow nature of Sinclair Inlet, tidal flushing is
very limited.  .Gorst Creek flows into the southwest end
of the inlet but the flow rate is small and does not sig-
nificantly affect mixing and tidal action.  It is esti-
mated that a complete exchange of inlet water occurs
every 6 to 12 months (1).

     Communication with local authorities indicated com-
mercial fishing is rarely done in the inlet area.  How-
ever, salmon rearing facilities are located nearby.
Sport fishing and shellfishing are popular in the vicin-
ity.

     The shoreline in the Sinclair Inlet, Port Orchard,
Rich Passage, and other adjacent areas appeared to be
utilized primarily for residential, recreational, and
industrial-commercial applications.  There was no indi-
cation of large scale agricultural operations.

Survey and Analytical Methods

     The sampling locations covered a large area with
concentrated sampling in close proximity of the PSNS.
These locations are shown in figures 1 and 2.

     An underwater scintillation probe containing a 10
centimeter by 10 centimeter Nal(Tl) detector was used
in conjunction with a 400-channel pulse height analyzer
in an attempt to delineate areas of radioactivity.

     Twenty-minute counts were taken and a background
spectrum from location 1 (Liberty Bay) subtracted from
each spectrum.  Locations of probe counts taken in the
vicinity of the shipyard are indicated in figure 3.

     The underwater scintillation probe has proved use-
ful in previous surveys  (2) to quantitatively delineate
general areas of radioactivity.  The levels of activity
encountered in this survey were below the detection
limits for the underwater probe.  Dredge samples were
taken at locations where radioactivity seemed most
probable based on the location of various operations
within the shipyard.

     The Radiological Support Building  (Building 839),
is located on the south end of Pier 6.  Equipment in

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                                BAINBRIDGE
                                ISLAND
  BREMERTON
  HARBOR
Figure 1.  Sampling  locations in the area

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Figure 2.  Sampling locations in the harbor
 Figure  3.  Locations of probe  counts  taken



                      4

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 the building  is  used  to process  and  seal  radioactive
 waste  into drums for  shipment  to a commercial waste dis-
 posal  site.   The areas adjacent  to the  Radiological Sup-
 port Building were  surveyed  in greater  detail because  of
 the possibility  of  radioactive waste discharges  in this
 area.

     A standard  Peterson dredge  was  used  to  sample ap-
 proximately the  top 10 centimeters of sediment.   The sam-
 ples were dried  at  110° C, ground to a  fine  powder,
 placed in a 400  cm3 "cottage cheese  container",  and
 counted on a  10  centimeter by  10 centimeter  Nal  (Tl) de-
 tector or a 40 cm3  Ge(Li) detector.

     Sediment core  samples were  collected by divers at
 several locations.  The purpose  of the  samples was to
 define the vertical distribution of  any radioactivity  in
 the bottom sediment.  These  samples  were  collected by
 pushing a 2.5-centimeter diameter by 61-centimeter tube
 into the sediment as  far as  possible and  then capping
 the ends of the  tube.  In the  laboratory  the cores were
 frozen and then  cut into 2.5-centimeter sections  and
 counted in the wet  state on  either of the gamma  detectors
 mentioned above.

     Vegetation  samples  (moss  and kelp),  were collected
•as available  in  the area of  the  shipyard.  They  were
 generally found  on  rocks and pier pilings.   These sam-
 ples were dried  at  110° C, ground to a  fine  powder, and
 analyzed for  gamma-emitting  radionuclides.

     Water samples  were collected and analyzed for gamma
 emitters and  tritium.

     Fish samples collected  at several  locations  were
 also analyzed for gamma-emitting radionuclides.   These
 samples were  cut  and  packed  and  counted in 400 cm3
 "cottage cheese  containers."

     Two air  samples  were collected  specifically  for the
 determination of  krypton-85  and  tritium.  Also air sam-
 ples were taken  to  determine the presence of any  gamma
 emitters.  The three  procedures  used for  this collection
 are as follows:

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1.   The sample for krypton-85 analysis was collected
adjacent to the Radiological Support Building by com-
pressing 1 m3 of air into a tank.  The analysis of
this sample was done by cryogenically removing the
krypton and counting by liquid scintillation (3).

2.   The samples collected for tritium determination
were also collected adjacent to the Radiological
Support Building.  A low volume vacuum pump and drierite
columns were used for the collection.  The analysis was
performed by equilibrating the drierite with water and
analyzing the water for> tritium.

3.   The samples collected for the analysis of gamma
emitters were collected at the Radiological Support
Building and the Radiological Offices Building  (Building
495).   Building 495 was chosen because of its close
proximity to the Radiological Support Building.  A High
Volume air sampler and MSA Dust Filters were used for
collection.

     External radiation exposure measurements were made
at several locations using a pressurized ionization
chamber (PIC) (4).  Particular interest was given to the
boundary of the PSNS since these areas are accessible to
the public.

Results and Discussion

     All samples were analyzed for gamma-emitting
isotopes with particular interest in cobalt-60.  Past
surveys have shown that cobalt-60 is the predominant
radioisotope resulting from nuclear operations.  In addi-
tion,  water samples were analyzed for tritium and air sam-
ples were analyzed for krypton-85.

     There is minimal commercial fishing in the area so
fish samples were difficult to obtain.  Rock cod and
several crustaceans were analyzed and showed no detect-
able amount of cobalt-60.  No radioactivity above mini-
mum detectable levels was found in any of the sea life
samples other than natural activity and a trace amount of
cesium-137  (0.02 ± 51%) attributed to fallout.  Data from
the aquatic life samples are shown in table 1.

     Air samples were collected and analyzed for tritium,
krypton-85, and other gamma emitters.  The tritium con-
centration in these samples was found to be less than the

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                         Table 1

      Results of aquatic life sample gamma  analyses
Sample Type


Sea cucumber


Starfish


Mussels


Crabs



Clams



Rock Cod
     Location
West of Pier 6
(Site 5)

West of Pier 6
(Site 5)

West of Pier 6
(Site 5)

West End of Dry
Dock 1  (Site 13)
200 m West of
PSNS at shoreline
Under Pier 6
(Site .9)
Specific Gamma Activity
   pCi/g Wet Weight
                       137
      Cs
   211*
                      2 1
      Bi
     'K
                         'Bi
   137Cs
    *°
   1 3 7
   226
    if 0
    0.01 ± 561
    0.60 ± 40%
    1.3
    1.7

    1.2
    0.4
± 46%
± 30%

± 53%
± 50%
          0.05 ± 76%
          2.1  ±  4%
          0.02 ± 42%
    0.01 ± 63%
K   1.0  ± 33%
Bi  0.02 ± 73%
Cs  0.02 ± 51%
Ra  0.04 ± 62%
K   3.1  ± 19%

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minimum detectable level (1 pCi/1).  The krypton-85
level was found to be 17.4 pCi/1 which is considered
to be within average background levels.  No samples
were taken elsewhere because this is the only area
where it was deemed that any possibility of elevated
levels of these nuclides existed.  The two filters
from the high-volume air sampler were analyzed for
gamma emitters and none were detected.  These results
are shown in table 2.

     Water samples were collected and analyzed for
gamma emitters and tritium.  No activity above minimum
detectable levels was observed in these samples.  The
minimum detectable level for tritium is 0.2 nCi/1.

     Samples of aquatic vegetation were collected in
the harbor area and analyzed for gamma-emitting radio-
isotopes.  Only atrace amount of cobalt-60  (0.02 ± 65%)
was found in one of the samples.  The only activity de-
tected in the other vegetation samples was natural ra-
dioactivity and fallout.  Results from analysis of
these samples are shown in table 3.

     Silt samples were taken at 34 locations and trace
quantities of cobalt-60 were found in 9  (table 4).
These results indicated that releases have taken place
in the past.  The levels determined are close to the
limit of detectability  (0.02 pCi/gm) indicating no sig-
nificant releases have taken place for several years.
The locations of the cobalt-60 activity in the shipyard
area were expected due to past releases.  However, the
activity found at site 14  (Dyes Inlet) was unexpected.
This activity was probably due to tidal action or pos-
sibly a release from another type of facility.  The
Navy Environmental Impact Statement for the TRIDENT
support site on the Hood Canal stated that low levels
of radioactivity from the AEC Reactors on the Columbia
River could be detected in the Hood Canal marine life
(5).  The silt sampling locations in the vicinity of
the shipyard are shown in figure 4.

     Core samples were collected at eight locations
(see figure 5) to determine the vertical distribution
of radioactivity in the sediment.  The predominant
activity found was from naturally occurring and typical
fallout radionuclides.  Only two samples collected at
the south end of dry dock 6 had detectable amounts of

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                        Table 2

             Results of air sample analyses
      Location

On Pier 6
West of Radiological
  Support Building

Radiological Support
  Building

Radiological Support
  Building

Radiological Offices
  Building

Radiological Support
  Building
NDA - No detectable activity.
                 Radionuclide
                     a s
                       Kr
                       !H
                       'H
 Activity
 (pCi/1)

17.4 ± 10%
 0.4 ± 50%


 0.3 ± 66%


    NDA


    NDA
Sample
Type

Moss
Kelp
                        Table 3

        Results of vegetation sample analyses
   Location

West of Pier 6
Site 5
Dry Dock 1
Site 6
Radionuclide

  35Zr-Nb

  60Co



  •»°K
  Specific
  Gamma
  Activity
  (pCi/gm)

 0.14 ± 25%
 0.05 ± 54%
 0.02 ± 65%
 1.00 ± 23%
 0.72 ± 36%

10.50 ± 14%

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                        Table 4

            Results of silt sample analyses
    (Only samples with cobalt-60 activity are shown)
             Location

Site 07 (West side of Pier 6)



Site 08 (East side of Pier 6)



Site 12 (Between Pier 6 & 7)



Site 14 (Dyes Inlet)



Site 18 (Between Pier 5 & 6)



Site 19 (Between Pier 5 & 6)



Site 22 (End of dry dock 6)



Site 32 (750 m Southeast of Pier  6)



Site 34 (200 m South of Pier 6)
Cobalt, Cesium &
Potassium
Activity
pCi/gm
Dry Weight
 6 0
1 3 7
 It 0
 6 0
137
 it 0
Co  0.04  ±  41%
Cs  0.31  ±   9%
   K
Co
Cs
K
     8.8
        6%
0.04 ± 44%
0.28 ±  9%
7.6  ±  6%
 6 0
1 3 7
Co   0.02  ±  60%
Cs   0.27  ±   9%
   'K
     8.4
        6%
 6 0
137
 it 0
Co   0.02  ±  87%
Cs   0.28  ±  11%
K   10.1   ±   6%
 60Co  0.02 ± 62%
137Cs  0.23 ±  9%
 i* o
   K
     8.1   ±   5%
 6 0
1 3 7
Co   0.03  ±  57%
Cs   0.25  ±   9%
'K   10.3   ±   5
 60Co  0.07 ± 30%
137Cs  0.15 ± 18%
 *°K   5.3  ±  9%

 60Co  0.04 ± 74%
137Cs  0.26 ± 15%
 *°K  11.8  ±  9%
 6 0
137
 I* 0
 Co   0.09  ±  50%
 Cs   0.2   ±  17%
 K    9.8   ±   9%
                          10

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Figure 4.  Silt sampling locations
Figure 5.  Core sampling locations
                  11

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cobalt-60.  A comparison of the silt and core samples
is difficult because the levels observed were close to
the limits of detectability.   The analytical results
from the core samples are shown in table 5.

     Measurements of the external gamma radiation expo-
sure were made at several locations using a PIC  (figure
6).  A series of measurements was taken along the indus-
trial security fence on the north edge of PSNS.  A
series of measurements was also made over water along
an imaginary line approximating the shipyard boundary in
Sinclair Inlet running approximately 185 meters from the
ends of the piers.  These locations were chosen because
they represented the nearest sites that were accessible
to the general public.

     Along the industrial fence at the northern and
western perimeters of PSNS only one location had a gamma-
radiation level which was higher than the gamma background
for the area (see table 6).  Measurements indicated the
average background from cosmic and terrestrial radiation
for the area to be 6.6 ± 1.2 micro-roentgens per hour
(uR/hr).  At the western end of the shipyard, location Gl
on figure 6, the gamma radiation level was 8.5 yR/hr.  At
this location fill material had been used to stabilize the
shoreline against erosion, and this material was noted to
be a possible source of the elevated exposure.

     The series of PIC measurements taken on the inlet off
the ends of the piers  (E39 through E44) produced gamma-
radiation levels which were no different than background
levels over water in that area  (Table 7).

     Measurements El through E38 were made between and
adjacent to the piers and dry docks of the shipyard
(figure 6).  At locations E20 through E23 and locations
E27 and E28, elevated gamma radiations were evident.  The
source of these elevated readings appeared to be the
Radiological Support Building.
                          12

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                            Table 5

                Results of core sample analysis
       (Only samples with detectable cobalt-60 are shown)
         Location

    Site 22
    End of dry dock 6
    Site 22
    End of dry dock 6
Depth Below
Sediment Water
Interface (cm)
      2.5
      5.0
    Activity
    pCi/gm
    Dry Weight
 6 0

1 3 7
 e o

137
 Co   0.07  ±  68%
 Cs   0.44  ±  17%
'K    1.85  ±  23%

 Co   0.62  ±  16%
 Cs   0.09  ±  64%
'K    7.58  ±  25%
Figure 6.  Locations of external gamma radiation measurements

                              13

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                Table 6



Exposure measurements observed over land



                PIC Data
Location
G01
G02
G03
G04
G05
G06
G07
G08
G09
G10
Gil
yR/hr
8.5
6.3
5.7
5.9
5.9
6.5
6.9
6.7
6.9
6.5
6.9
Location
G12
G13
G14
G15
G16
G17
G18
G19
G20
G21
G22
yR/hr Location
6.9 G23
6.7 G24
6.7 G25
6.5 G26
6.9
6.7
6.5
6.7
6.9
6.7
6.7
yR/hr
7.3
7.1
5.9
5.3







                  14

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                 Table 7



Exposure measurements observed over water



                 PIC Data
Location
E01
E02
E03
E04
EOS
E06
E07
E08
E09
BIO
Ell
E12
E13
E14
E15
yR/hr
4.5
4.5
4.3
4.7
4.5
5.1
4.7
4.5
4.5
4.3
4.5
4.5
4.7
4.9
4.5
Location
E16
E17
E18
E19
E20
E21
E22
E23
E24
E25
E26
E27
E28
E29
E30
yR/hr
4.7
4.7
4.7
4.9
9.9
18.3
10.4
9.5
4.9
4.5
4.7
6.3
7.3
5.5
4.7
Location
E31
E32
E33
E34
E35
E36
E37
E38
E39
E40
E41
E42
E43
E44

yR/hr
4.5
4.5
4.5
4.7
4.5
4.5
4.3
4.5
4.7
4.5
4.5
4.3
4.3
4.7

                  15

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Conclusions

     As a result of the survey of the Puget Sound Naval
Shipyard, the following conclusions can be drawn:

1.   The results of this study indicate the procedures
utilized by the Navy to control the release of radio-
active material into the Bremerton Harbor from PSNS are
apparently effective.

2.   Levels measured are close to the detection limit
for the most sensitive analytical equipment.  This indi-
cates that nuclear operations at the Puget Sound Naval
Shipyard are not contributing a significant radiation
exposure to the public.

3.   External exposure measurements in public areas in-
dicate no exposures above natural background resulting
from PSNS operations.

     The continuation of the current practices regarding
waste discharge and the Navy monitoring program should
assure continued absence of significant public exposure
for routine nuclear ship operations.
                          16

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                     REFERENCES


1.    Oil on Puget Sound, University of Washington Press,
     1972.

2.    WINDHAM, SAM T. and CHARLES R. PHILLIPS.  "Radio-
     logical Survey of New London Harbor, Thames River,
     Connecticut, and Environs."  Radiation Data and
     Reports, Vol. 14, No. 11, November 1973.

3.    CUMMINGS, S. L., R. L. SHEARIN, C. R. PORTER.  "A
     Rapid Method for Determining 85Kr in Environmental
     Air Samples."  International Atomic Energy, Vienna
     (1971).  IAEA-SM-148/11.

4.    DECAMPO, J. A., H. L. BECK, and P. D. RAFT.  "High
     Pressure Argon lonization Chambers for Measurement
     of Environmental Radiation Exposure Rates," HASL-260
     (1972).

5.    Navy Environmental Impact Statement for the TRIDENT
     Support Site, Hood Canal.
                         17

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UNITED STATES ENVIRONMENTAL PROTECTION AGENCY
  EASTERN ENVIRONMENTAL RADIATION FACILITY
                P, 0, Box 3009
          Montgomery, Alabama 36109
              OFFICIAL BUSINESS

       , Penalty for Private Use $300

        AN EQUAL. OPPORTUNITY EMPLOYER

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