3 3 }■> 4 0 {i i c 2 ■ o f Radiation Programsi.. EPA-520/5-77-001 RADIOLOGICAL SURVEY OF PUGET SOUND NAVAL SHIPYARD BREMERTON, 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 20460FOREWORD T 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 Programs1 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 ProgramsPREFACE 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 contributions from the operation of nuclear-powered ves Director Eastern Environmental Radiation Facility iiCONTENTS 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 iiiIntroduction 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-powe'red 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 Administrationmaps 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 2Figure 1. Sampling locations in the area 3 Figure 3. Locations of probe counts taken 4i 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 kr.ypton-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: 51. 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 6Table 1 Results of aquatic life sample gamma analyses Specific Gamma Activity Sample Type Location pCi/g Wet Weight Sea cucumber West of Pier (Site 5)' 6 1 3 7Cs “°K 0.01 ± 56% 0.60 ± 40% Starfish West of Pier 6 2 1 “Bi 1.3 ± 46% ■ (Site 5) “°K 1.7 ± 30% Mussels West of Pier 6 21 “Bi 1.2 ± 53% '(Site 5) “°K 0.4 ± 50% Crabs West End of Dry 2 3 2Th 0.05 ± 76% Dock 1 (Site 13) “°K 2.1 ± 4% 21 “Bi 0.02 ± 42% Clams 200 m West of 137Cs 0.01 ± 63% PSNS at shoreline “°K 1.0 ± 33% 2 1 “Bi 0.02 ± 73% Rock Cod Under Pier 6 137Cs 0.02 ± 51% (Site 9) 2 2 6Ra 0.04 ± 62% “°K 3.1 ± 19% 7minimum 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 AEG 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 8Table 2 Results of air sample analyses Location Radionuclide On Pier 6 8 5Kr West of Radiological Support Building Radiological Support SH Building Radiological Support 3H Building Activity (pCi/1) 17.4 ± 10% 0.4 ± 50% 0.3 ± 66% Radiological Offices Building Radiological Support Building NDA - No detectable activity. NDA NDA' Table 3 Results of vegetation sample analyses Sample Type Location Moss West of Pier 6 Site 5 Kelp Dry Dock 1 Site 6 Radionuclide 3 5Zr~Nb 2 3 2Th 6 °Co “°K 21 “Bi “°K Specific Gamma Activity (pCi/gm) 0.14 ± 25% 0.05 ± 54 0.02 ± 65 1.00 + 23% 0.72 ± 36% 10.50 ± 14% dP o\o 9Table 4 Results of silt sample analyses (Only samples with cobalt-60 activity are shown) i Location Cobalt, Cesium Potassium Activity pCi/gm Dry Weight l & Site 07 (West side of Pier 6) 6 °Co 0.04 ± 41% 137Cs 0.31 i 9% **°K 8.8 6% Site 08 (East side of Pier 6) soCo 0.04 ± 44% 137Cs 0.28 ± 9% **°K 7.6 ± 6% Site 12 (Between Pier 6 & 7) 6 °Co 0.02 ± 60% 1 3 7Cs 0.27 ± 9% I*°K 8.4 ± 6% Site 14 (Dyes Inlet) 60Co 0.02 ± 87% 1 3 7Cs 0.28 ± 11% “°K 10.1 ± 6% Site 18 (Between Pier 5 & 6) 60Co 0.02 i 62% 13 7Cs 0.23 ± 9% “°K 8.1 ± 5% Site 19 (Between Pier 5 & 6) eoCo 0.03 ± 57% 137Cs 0.25 ± 9% **°K 10.3 ± 5 Site 22 (End of dry dock 6) 60Co 0.07 + 30% 1 3 7CS 0.15 ± 18% “°K 5.3 ± 9% Site 32 (750 m Southeast of Pier 6) 60Co 0.04 ± 74% 13 7Cs 0.26 ± 15% uoK 11.8 ± 9% Site ' 34 (200 m South of Pier 6) 60CO 0.09 ± 50% 137Cs 0.2 ± 17% ** °K 9.8 ± 9% 10 Figure 4 J Silt sampling locations Figure 5. Core sampling locations 11 Icobalt-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 (pR/hr). At the western end of the shipyard, location G1 on figure 6, the gamma radiation level was 8.5 pR/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. 12Table 5 Results of core sample analysis (Only samples with detectable cobalt-60 are sh’own) Location Site 22 End of dry dock 6 Depth Below Sediment Water Interface (cm) Activity pCi/gnf Dry Weight 2.5 Site 22 End of dry dock 6 5.0 60Co 0.07 ± 68% 137Cs 0.44 ± 17% 1*°K 1.85 ± 23% 60Co 0.62 ± 16 137Cs 0.09 ± 64 l*°K 7.58 ± 25 cP ©P oP \ Figure 6. Locations of external gamma radiation measurements 13Table 6 Exposure measurements observed over land PIC Data Location pR/hr Location pR/hr Location pR/hr G01 8.5 G12 6.9 G23 7.3 G02 6.3 G13 6.7 G24 7.1 G03 5.7 G14 .6.7 G25 5.9 G04 5.9 G15 6.5 G26 5.3 G05 5.9 G16 6.9 G06 6.5 G17 6.7 G07 6.9 G18 6.5 G08 6.7 G19 6.7 G09 6.9 G20 6.9 GIO 6.5 G21 6.7 - Gil 6.9 G22 6.7 14Table 7 Exposure measurements observed over water PIC Data Location pR/hr Location pR/hr Location pR/hr E01 4.5 E16 4.7 E31 4.5 E02 4.5 E17 4.7 . E32 4.5 E03 • 4.3 E18 4.7 E33 4.5 E0'4 4.7 E19 4.9 E34 4.7 E05 4.5 E20 9.9 E35 4.5 E06 5.1 E21 18.3 E36 4.5 E07 4.7 E22 10.4 E37 4.3 E08 4.5 E23 9.5 E38 4.5 E09 ‘ 4.5 E24 4.9 E39 4.7 E10 4.3 E25 4.5 E40 4.5 Ell 1 4.5 E26 4.7 E41 4.5 E12 4.5 E27 6.3 E42 4.3 E13 4.7 • E28 7.3 E43 4.3 E14 4.9 E29 5.5 E44 4.7 E15 4.5 E30 4.7 15Conclusions 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. ♦ 16i i i i i 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 Ionization Chambers for Measurement of Environmental Radiation Exposure Rates," HASL-260 (1972). 5. Navy Environmental Impact Statement for the TRIDENT Support Site, Hood Canal. i f 17 r•j;ii:i■) s'.'.- .=•; e:.vpsttal protection agency EASTERN ENVIRONPLAA ’L RADIATION FACILITY' P. T. Bex 2009 Montgomery, Alabama 30109 r m OFFICIAL BUSINESS Penalty for Private Use $300 AN EQUAL OPPORTUNITY EMPLOYER POSTAGE AND FEES PAID U. S, ENVIRONMENTAL PROTECTION A EPA-335 return this sheet to at* ve edd-eos. if y.;.j do \0f wish to recede has otahred O or if chv;e o f ado f e s s ; s ot-t ed □ 11 ed y: a; e charge, includir,;; ZiPcTSee