ML20138B001

Radiological Environ Monitoring Rept

ML20138B001
Person / Time
Site:	Oyster Creek
Issue date:	12/31/1996
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-97-2125, NUDOCS 9704290031
Download: ML20138B001 (154)

Text

- -e j GPU Nuclear, Inc.

( U.S. Route M South NUCLEAR Post Oti ce Box 388 Forked over, NJ 08731-0388 Te1609-971-4000 April 23, 1997 6730-97-2125 U. S. Nuclear Regulatory Commission Attention: Docunient Coritrol Desk Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Oyster Creek Radiological Environmental Monitoring (REMP) Report - 1996 Enclosed is a copy of the Oyster Creek REMP Report for 1996. This sub sittal is made in accordance with Technical Specification 6.9.1.e. ,

ifyou should have any questions or require further information, please contact Brenda DeMerchant, OC Regulatory Affairs Engineer, at 609-971-4642.

Very truly yours, Michael B. Roche Vice President and Director Oyster Creek MBR/BDE/gl /

g. $6 Enclosure [C{'(- 3 J' cc: Administrator, Region 1 l NRC Project Manager I NRC Sr. Resident Inspector 9704290031 961231 PDR ADOCK 05000219 PDR R

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1 OYSTER CREEK NUCLEAR GENERATWG STATION

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OYSTER CREEK NUCLEAR GENERATING STA' TION l

Forked River, New Jersey The 650 MWplant is a single-unit, five-loop General l

l Electric Boiling Water Reactor (BWR). The site, about 800 acres, is in Lacey and Ocean

Townships of Ocean County. Located approximately nine m,?es south of Toms River, it is

, about 50 miles east of Philadelphia, and 60 miles south of Newark.

Construction began in December 1963. The station began

commercial operation on December 23,1969, and at that time was the largest nuclear i facility in the United States solely financed by a private company.

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The Reactor Building, Turbine Building and Ventilation Stack are the most prominent structures at the site. The Reactor Building stands approxi- l<

j mately 150 feet high with 42 feet extending below grade. The Reactor Building serves as a i secondary containment and houses the primary containment (dryweII), the reactor vessel

and its aux lllary systems which comprise the Nuclear Steam Supply System. The drywell, l which houses the reactor vessel, is constructed of high-density reinforced concrete with an i inner steelliner measuring 120 feet high and 70 feet in diameter.

l The reactor vesselis 63 feet high and 18 feet in diameter.

i The 652-ton reactor contains 560 fuel assemblies, each with 62 fuel rods that are 12 feet j

long, and 137 control rods. The reactor operates at a nominalpressure of 1,020 pounds per square inch and an average temperature of 540 degrees Fahrenheit.

l 1 The Turbine Building houses the turbine-generator, control g room, main condensers, power conversion equipment and auxiliary systems. The turbine- g generator consists of one high-pressure turbine, three low-pressure turbines, a generator i and an exciter. The turbines and generator tum at 1,800 revolutions per minute to generate g i

three-phase, 60-cycle electricity at 24,000 volts. The electricity generated is provided to the E, '

grid by two transformers which boost the voltage to 230,000 volts.

i Steam is supplied to the high pressure turbine from the

! reactor. After being used to drive the turbines and generator, the steam is condensed in the main condensers and returned to the reactor vesselin the form of water through the con-densate and feedwater pumps.

i The main condensers consist of three horizontal, single pass, divided water boxes containing 44,000 tubes having a totallength of about 1,875,000

. feet. Cooling wateris provided from Barnegat Bay, through the South Branch of the Forked l

{ River and passes through the condensers and discharges into Oyster Creek for retum to a i

Bamegat Bay. The water is pumped by four 1,000-horsepowerpumps, each of which moves about 115,000 gallons per minute through the 6 foot-diameterpipes that feed the condensers.

The ventilation stack is 368 feet high with 26 feet extend-l

! ing below grade. The stack provides ventilation for the Reactor Building, Turbine Building and Radwaste Facilities. l Oyster Creek is owned by Jersey Central Power & Light i

(JCP&L) Company and oper-ated by GPUNuclear(GPUN) l i Corporation. JCP&L and GPUN are units of the GPU System.

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1996 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT PREPARED BY OYSTER CREEK ENVIRONMENTAL AFFAIRS GPU NUCLEAR, INC.

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TABLE OF CONTENTS PAGE

TABLE OF CONTENTS i j

i LIST OF TABLES iv i

LIST OF FIGURES si

SUMMARY

AND CONCLUSIONS 1 INTRODUCTION 3 i C'naracteristics ofRadiation 3 l Sources ofRadiation 4

! Nuclear Reactor Operations 7 j Sources ofLiquid and Airborne Effluents 9 i DESCRIPTION OF THE OCNGS SITE 11 l

! GeneralInformation 11 Climatological Summary 11 EFFLUENTS 17 1

j Historical Background 17

Effluent Reler.se Limits 17

. Effluent ControlProgram 20 4

Effluent Data 21 i

I RADIOLOGICAL ENVIRONMENTAL MONITORING 25

i j Environmental Exposure Pathways to Humans from i Airbome and Liquid Efiluents 25 l Sampling 26 1 1

Analysis 27 Quality Assurance Program 31 {

.l DIRECT RADIATION MONITORING 69

. i j Sample Collection and Analysis '69 Results 70 l i 1 I i i 1 l l I i t

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TABLE OF CONTENTS (Continued)

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ATMOSPHERIC MONITORING 75 Sample Collection and Analysis 75 Results 75 AQUATIC MONITORING 80 i Sample Collection and Analysis 80 I Results 81 TERRESTRIAL MONITORING 88 Sample Collection and Analysis 88 Results 88 l

GROUNDWATER MONITORING 90 Sample Collection and Analysis 90 Results 91 RADIOLOGICAL IMPACT OF OCNGS OPERATIONS 92 Determination of Radiation Doses to the Public 92 Results ofDose Calculations 95 REFERENCES 98

. APPENDIX A: 1996 REMP Sampling Locations and 101 Descriptions, Synopsis ofREMP, and Sampling and Analysis Exceptions APPENDIX B: 1996 Lower Limits ofDetection (LLD)

Exceptions 112 )

l APPENDIX C: Changes to the 1996 REMP 114 APPENDIX D: 1996 Quality Assurance Results 116 APPENDIX E: 1996 Emironmental Radioactivity Interlaboratory Comparison Results 121 APPENDIX F: 1996 Annual Dairy Census 128 I

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{ TABLE OF CONTENTS (Continued) c i

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l APPENDIX G: Dose Calculation Methodology 130 1 i , l

APPENDIX H: 1996 Groundwater Monitoring Results 135 i

3-APPENDIXI: 1996 REMP Sample Collection and .

Analysis Methods 139 t 4 APPENDIX J: 1996 TLD Quanerly Data 142 i >

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4 LIST OF TABLES TABLE TITLE PAGE 1 Sources and Doses ofRadiation 5 2 Radionuclide Composition ofOCNGS Efiluents for 1996

• 22 3 Radiological Emironmental Monitoring Program Sununary, Oyster Creek Nuclear Generating Station- January 1996 through December 1996 33 4 TLD Exposure Periods During 1996 70 i 5 Cesium-137 Concentration in Aquatic Sediment -

1994,1995, and 1996 83 6 Species offish Caught as Part

, of the OCNGS REMP in 1996 87 7 Calculated Maximum Hypothetical Doses to an Individual from Liquid and Airborne Effluent Releases from OCNGS for 1996 96 8 Calculated Maximum Total Radiation Doses to the Population from Liquid and Airbome Effluent Releases from the OCNGS for 1996 97 l

A-1 Radiological Envi onmental Monitoring I Program Sampling Locations 102 j i

A-2 Synopsis of the Operational Radiological Emironmental Monitoring Program'- 1996 110 j i

A-3 Sampling and Analysis Exceptions - 1996 111 ;

B-1 1996 Lower Limits ofDetection (LLD) Exceptions 113 l

C-1 Changes to the 1996 REMP 115 D-1 1996 QA Sample Program - Number of Duplicate Analyses Performed 118 iv

LIST OF TABLE _S (Continued)

TABLE TITLE PAGE D-2 1996 QA Sample Program - Split Samples 119 D-3 Resolution of 1996 OCNGS REMP Split Sample Analytical Non-Agreements 120 E-1 1996 Environmental Radioactivity Inter-laboratory Comparison 122 )

(USEPA Cross-Check) Program Results E-2 1996 Analytics, Inc. Cross-Check Program Results 124 E-3 1996 Environmental Radioactivity Inter-laboratory Comparison 126 l

G-1 Sununary ofMaximum Hypothetical Individual and Population Doses from Liquid and Airbome J Efiluent Releases from the OCNGS for 1996 134 H-1 OCNGS - 1996 Groundwater Results 136 I-1 Radiological Environmental Monitoring Program Summary of Sample Collection and Analysis Methods-1996 140 J-l 1996 Quarterly Environmental TLD Report -

Teledyne Brown Engineering TLDs 143 J-2 1996 Quarterly Erwironmental TLD Report -

Panasonic TLDs 144 v

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e LIST OF FIGURES FIGURE TITLE PAGE 1 Oyster Creek Nuclear Generating Station Simplified Schematic 8 2 Wind Direction Frequency ofOccurrence-1996 Oyster Creek Nuclear Generation Station 13 3 Monthly Mean Ambient Air Temperature-Oyster Creek  !

Nuclear Generating Station - During 1996 Compared with Historical (1946-1981) Atlantic i City National Weather Service Average Temperature Data 14 4 Monthly Precipitation at the Oyster Creek Nuclear Generating Station During 1996 Compred with Historical (1946-1981) ,

Atlantic City National Weather Service i Average Precipitation Data 16 ,

5 Location of Radiological Environmental Monitoring Program (REMP) Stations Within One Mile of the Site 28 6 Location of Radiological Environmental '

Monitoring Program (REMP) Stations Greater than One Mile and Within Two Miles ofthe Site 29 7 Locatior, of Radiological Environmental Monitoring Program (REMP) Stations Greater than Two Miles From the Site 30 8 Mean Panasonic TLD Gamma Dose-1989 through 1996 7I 9 Mean Panasonic TLD Gamma Dose for 1996 Based on Distance from OCNGS 72 10 Mean Teledyne and Panasonic TLD Gamma Dose for 1996 -Mean Dose in Affected Compass Sector 74 vi

LIST OF FIGURES FIGURE TITLE PAGE 11 Mea s~ urement and Moving Range Chart - Quality Control Indicator Stations Compared to Background Limits - Air Particulate Gross Beta-1996 77 12 Bi-Weekly Mean Air Particulate Gross Beta Concentrations for 1996 78 13 Monthly Mean Air Particulate Gross Beta Concentrations - 1984 through 1996 79 14 Mean Cesium-137 Concentration in Aquatic Sedimera - 1984 throagh 1996 82 15 Mean Cobalt-60 Concentration in Aquatic Sediment - l 1984 tirough 1996 85 16 Mean Cobalt-60 Concentration in Clams-1983 through 1996 86

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17 Exposure Pathways for Radionuclides

Potentially Released from the OCNGS 94 H-1 Locations of On-Site Wells 138 1

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SUMMARY

AND CONCLUSIONS -

He radiological emironmental monitoring performed during 1996 by the GPU Nuclear Emironmental Affairs Department at the Oyster Creek Nuclear Generating Station (OCNGS) is discussed in this report. He operation of a nuclear power plant results in the release of small amounts of radioactive materials to the environment. A radiological emironmental monitoring program (REMP) has been established to monitor radiation and radioactive materials in the emironment around the OCNGS. He program evaluates the relationship between amounts of radioactive material released in emuents to the environment and resultant radiation doses to individuals. Summaries and interpretations of the data were published semiannually from 1969-1985 and annually since 1986 (Ref. 20 through 29). Additional information concerning releases of radioactive materials to the emironment is contained in the Semi-Annual and Annual Emuent Release Reports submitted to the United States Nuclear Regulatory Commission (USNRC).

During 1996, as in previous years, the radioactive emuents associated with the OCNGS were a small fraction of the applicable federal regulatory limits and did not have significaat effects on the quality of the emironment. Calculated maximum hypothetical radiation doses to the public attributable to 1996 operations at the OCNGS ranged from 0.000022 percent to a maximum of only 0.89 percent of the applicable regulatory limits. Furthennore, they were significantly less than doses received from other man-made sources and natural background sources of radiation.

Radioactive materials considered in this report are nonnally present in the emironment, either naturally or as a result of non-OCNGS aethities such as prict atnnpheric nuclear weapons testing, medical industry activities, and the 1986 Chemobyl accident. Consequently, . measurements made in the sicinity of the site were comparai to background measurements to determine any impact of OCNGS operations.

Samples of air, well water, surface water, clams, sediment, fish, crabs, and vegetables were collected.

Samples were analyzed for radioactivity including tritium (H-3), gross beta, and gamma-emitting radionuclides. Extemal penetrating radiation dose measurements also were made using thermoluminescent dosimeters (TLDs) in the vicinity of the OCNGS.

The results of these radiological measurements were used to assess the emironmental impact of OCNGS opemtions, to demonstrate compliance with the Technical Specifications (Ref.1), the Offsite Dose Calculation Manual Specifications (Ref. 2), applicable federal regulations, and to verify the adequacy of containment and mdioactive emuent control systems. He data collectal by the REMP also proside a 1

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historical record of the levels of radionuclides and radiation attributable to natural causes, worldwide fallout from prior nuclear weapons tests and the Chemobyl accident, as well as OCNGS operations.

l Radiological impacts in temis of radiation dose as a result of OCNGS operations were calculated and j

also are discussed. He results provided in this repon are summanzed in the following highlights: l o During 1996, 1181 samples were taken from the aquatic, atmospheric, and terrestrial emironments around the OCNGS. A total of 1245 analyses were perfonned on these samples.

Arce hundred twenty-four (324) direct radiation dose measure nents using TLDs also were i 1

made. Twenty-seven (27) groundwater samples, taken primarily from local municipal water i supplies and on-site wells, were collected and thirty-five (35) analyses were performed on those samples.

o Minute levels of cobalt-60 (Co-60) were detected in aquatic sediment samples and trace levels of cesium-137 (Cs-137) were detected in sediment and fish samples as a result of past OCNGS operations. As a result of the temsnation of routine liquid radioactive discharges in 1989 and the natural radioactive decay process, the concentrations of cobalt 60 and cesium-137 in I environmental media continue to decline to barely detectable levels.

o ne amount of radioactivity released in emuents from the OCNGS during 1996 was the l

smallest in the history of Station operation. The predominant radionuclide in gaseous efduents l

was xenon-135 (Xc-135) and in liquid emuents was tritium (H-3). Estimated radiation doses to the public, attdbuiable to 1996 cmuent3, magal num 0.000022 percent to a maximum of only 0.89 percent of applicable regulatory limits.

o During 1996, the maximum total body dose potentially received by an individual from liquid and airbome emuents was estimated to be about 0.0181 millirems. The total body dose to the surrounding population from liquid and airbome emuents was calculated to be 2.3 person-rem.

This is approximately 430,000 times lower than the dose that the total population in the OCNGS area receives from natural background sources.

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{l INTRODUCTION Characteristics of Radiation Instability within the nucleus of radioactive atoms results in the release ofenergy in the form of radiation.

Radiation is classified according to its nature - particulate and electromagnetic. Particulate radiation consists of energetic subatomic particles such a electrons (beta particles), protons, neutrons, and alpha particles. Because of its limited ability to penetmte the human body, particulate radiation in the i

emironment contributes primarily to intemal radiation exposure resulting from inhalation and ingestion ofradioacthity.

Electromagnetic radiation in the form of x-rays and gamma rays has characte.istics similar to visible light but is more energetic and, hence, more penetratmg Although x-rays and gamma rays are penetrating and can pass through varying thicknesses of materials, once they are absorbed they produce

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4 energetic electrons which release their energy in a manner that is identical to beta particles. He principal i

4 concem for gamma radiation from radionuclides in the emironment is their contribution to extemal radiation exposure.

1 The rate with which atoms undergo disintegration (radioactive decay) varies among radioactive elements,

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s but is uniquely constant for each specific radionuclide. The term " half-life" defines the time it takes for half of any amount of an element to decay and can vary from a fraction of a smond for some  !

radionuclides to millions of yws for others. In fact, the natural background radiation to which all mankind has been exposed is largely due to the radionuclides of uranium (U), thorium (Th), and potassium (K). These radioactive elements were formed with the creation of the universe and, owing to their long half-lives, will continue to be present for millions of years to come. For example, potassium-40 (K-40) has a half-life of 1.3 billion years and exists naturally within our bodies. As a result, approx,imately 4000 atoms of potassium emit radiation intemally within each of us every second

ofourlife.

In assessing the impact of radioactivity on the emironment, it is important to know the quantity of radioactivity released and the resultant radiation doses. The common unit of radioacthity is the curie (Ci). It represents the radioactivity in one gram (g) ofnatural radium (Ra) which is also equal to a decay rate of 37 billion radiation emissions every second. Because the level of radioactive material in the emironment is extremely small, it is more convenient to work with portions or fractions of a curie.

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1 Subunits like picoeurie (pCi), (one trillionth of a curie), are frequently used to express the radioactisity present in emironmental and biological samples.

l The biological effects of a specific dose of radiation are the same whether the radiation source is extemal l

, or intemal to the body, The important factor is how much radiation energy or dose was deposited. The  !

unit of radiation dose is the R[x:ntgen Equivalent Man (rem), which also incorporates the variable effectiveness of different fonns of radiation to produce biological change. For emironmental radiation l exposures, it is convenient to use the smaller unit of millirern (mrem) to express dose (1000 mrem equals I rem). When radiation exposure occurs over periods of time, it is appropriate to refer to the dose ,

l rate. Dose rates, therefore, define the total dose for a fixed intenal of time, and for emironmental j exposures, are usually measured with reference to one year of time (mrem per year). I i

Sources of Radiation

Life on carth has evolved amid the constant exposure to natural radiation. In fact, the single major source of radiation to which the general population is egosed comes from natural sources. Although everyone on the planet is eposed to natural radiation. some people receive more than others. Radiation egosure from natural background has th'ree components (i.e., cosmic, terrestnal, and intemal) and 5

varies with altitude and geographic location, as well as with lising habits.

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For example, cosmic radiauon ongmatmg from deep interstellar space and the sun mercases with altitude, because there is less air to act as a shield. Sia.ilr!y, t uM radiation resultiig Gun the presence of naturally occurring radionuclides in the soil varies and may be significantly higher in some areas of the country than in others. Even the use of particular building nutenals for houses, cooking with gas, and home insulation afTect exposure to natural radiation.

The presence of radioactivity in the human body results from the inhalation and ingestion of air, food.

and water containing naturally occurring radionuclides. For example, danking water contains trace amounts of uranium and radium, and milk contains radioactive potassium. Table I summanzes the common sources of radiation and their astrage annual doses.

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Sources and Doses of Radiation

• Natural (82%) Man-made (18%)

4 Radiation Dose Radiation Dose i Source (mrem /vear) Source (mrem /vear)

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Radon 200 (55 %) Medical X-ray 39 (11 %)

Cosmic rays 27 (8%) Nuclear Medicine 14 (4%)

• Terrestrial 28 (8%) Consumer products 10 (3%)

Internal 40 (11 %) Other <1 (<1%)

(Releases from nat. gas, j phosphate mining, buming of coal, weapons fallout,

& nuclear fuel cycle) a

! Approximate Total 295 Approximate Total 64 1

• Percentage contribution of the total dose is shown in parentheses.

4 i ne average person in the United States receives about 300 mrem />T (0.3 rem />T) from natural 1

l background radiation sources. This estimate was recently ruimi fmm (appmximately) 100 to 300 .

mrem because of the inclusion of radon gas which has always been present but has not been previously included in the calculations. In some regions of the country, the amount of natural radiation is significantly higher. Residents of Colorado, for example, receive an additional 60 mrem />T due to the

increase in cosmic and teirestrial radiation levels. In fact, for every 100 feet above sea level, a person will receive an additional 1 mrem /yr from cosmic radiation. In several regions of the world, high concentrations of uranium and radium deposits result in doses of several thousand mrem />T to their residents (Ref. 4).

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Recently, public attention has focused on radon (Rn), a naturally occurring radioactive gas produced

} from uranium and radium decay. These elements are widely distributed in trace amounts in the carth's j cmst. Unusually high concentrations have been found in certain parts of eastem Pennsylvania and

) northem New Jersey. Radon levels in some homes in these areas are hundreds of times greater than 1

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I levels found elsewhere in the United States. liowever, additional surveys are needed to determine the full extent of the problem nationwide. Radon is the largest component of natural background radiation and may be responsible for a substantial number of hmg cancer deaths annually. He National Council on Radiation Protection and Measurements (NCRP) estimates that the average individual'in the United States receives an annual dose of about 2,400 mrem to the lung from natural radon gas (Ref. 4). His I 4 lung dose is considered to be equivalent to a whole body dose of 200 millitems. The NCRP has I recommended actions to control indoor radon sources and reduce exposures.

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When radioactive substances are inhaled or swallowul, they are distributed within the body in a non-i uniform fashion. For example, radioactive iodine selectively concentrates in the thyroid gland, radioactive cesium is distributed throughout the body water and muscles, and radioactive strontium concentrates in the bones. He total dose to organs by a given radionue'_ide also is influenced by the I quantity and the duration of time that the radionuclide remams in the body, including its physical, j biological, and chemical characteristics. Dependmg on their rate of mdioactive decay and biological elimination from the body, some radionuclides stay in the body for very short times while others remam for years. l In asidition to natural radiation, we are exposed to radiation from a number of man-made sources. He smgle largest of these sources comes from diagnostic medical x-rays and nuclear medical procedures. i Some 180 million Americans receive medical x-rays cach year. He annual dose to an indisidual from j i

such radiation averages about 53 milhrems. Much smaller doses come from nuclear weapons fallout  ;

and ccm:umer preducts such as teknisions, smoke detectors, and fertilizers. Production of commercial nuclear power and its associated fuel cycle contributes less than 1 mRen to the annual dose of about 300 mrem for the average individual living in the United States.

Fallout commonly refers te the radioactive debris that settles to the surface of the earth following the detonation of nuclear weapons. It is dispersed throughout the emironment either by dry deposition or washed down to the earth's surface by precipitation. Here are approximately 200 radionuclides produced in the nuclear weapon detonation process; a number of these are detected in fallout. He radionuclides found in fallout which produce most of the fallout radiation exposures to humans are iodine-131 (1-131), strontium-89 (Sr-89), strontium-90 (Sr-90), and cesium-137 (Cs-137). Ecre has been no atmospheric nuclear weapon testing since 1980 and many of the radionuclides, still present in our emironment, hav: dqxi significantly. Consequently, doses to the public from fallout have been decreasing.

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i As a result of the nuclear accident at Chemobyl, USSR, on April 26,1986, radioactive material was

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i dispersed throughout the global environment and detected in various malia such as air, milk, and soil.

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Cesium-134, cesium-137, iodine-131, and other radionuclides released from Chernobyl were detected at I the OCNGS in significant amounts following the accident. Dese radionuclides continue to decay I l toward a stable state in the environment.

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i Nuclear Reactor Operations 5

l Common to the commercial production of electricity is the consumption of fuel which produces heat to

! make steam which tums the turbine-generator which generates electricity. Unlike the buming of coal, oil,

! or gas in fossil-fuel powered plants to generate heat, the fuel of most nuclear reactors is comprised of the I

clement uranium in the form of uranium oxide. He fuel produces power by the process called fission. )

1 In fission, the uranium atom absorbs a neutron (an atomic particle found in nature and also produced by i the fissioning of uranium in the reactor) and splits to produce smaller atoms termed fission products, along with heat, radiation, and free neutrons. He free neutrons travel through the reactor and are I

similarly absorbed by the uranium, permitting the fission process to continue. As this process continues, i l

imre fission products, radiation, heat, and neutrons are produced and a sustamed reaction occurs. He heat produced is transferred via reactor coolant (water) from the fuel to produce steam which drives a turbine-generator to produce electricity. He fission products are mostly radioactive; that is, they are unstable atoms which emit radiation as they decay to stable atoms Neutrons which are not absorbed by the uranium fuel may be absorbal by stable atoms in the materials which make up the components and structures of the reactor. In such cases, stable atoms often become radioactive. His process is called activation and the radioactive atoms which n:sult are called activation products.

He OCNGS reactor is a Boiling Water Reactor (BWR). He nuclear fuel is designed to be contamed within scaled fuel rods arranged in arrays called bundles which are located within a massive steel reactor vessel. As depicted in Figure 1, cooling water boils within the reactor vessel producing steam which drives the turbine. After the energy is extracted from the steam in the turbine, it is cooled and j

condensed back into water in the main condensers. His condensate is then pumped back into the reactor vessel and the cycle repeats Several hundred radionuclides of some 40 different elements are created in a nuclear reactor during the process of generating electricity. Because of reactor engineering designs, the short half-lives of many radionuclides, and their chemical and physical properties, nearly all radioactisity is contained.

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Oyster Creek Nuclear Generating Station m .n% StrnpHHed Schematic 4

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He OCNGS reactor has six independent baniers that confme radioactive materials produced in the reactor as it heats the water. Under normal operating conditions, essentially all radioactisity is contained within the first two baniers.

He ceramic uranium fuel pellets proside the first barrier. Most of the fission products are either trapped or chemically bound in the fuel where they remam However, a few fission products which are volatile or gaseous at normal operating temperatures may not be contained in the fuel.

He second banier consists of zirconium (Zr) alloy tubes (termed " fuel cladding") that resist corrosion and degradation due to high temperatures. He fuel pellets are contained within these tubes. Here is a small gap between the fuel and the cladding, in which the noble gases and other volatile mdionuclides collect and are contained.

He prunary coolant water is the third barrier. Many of the fission products, including radioactive iodine, strontium, and cesium are soluble and are retamed in water in an ionic (electrically charged) fonn.

Rese materials can be removed in the reactor coolant purification system. However, krypton (Kr) and xenon (Xe) do not readily dissolve in the coolant, particularly at high temperatures. Knpton and xenon collect as a gas above the condensate when the steam is condensed.

He fourth barrier consists of the reactor pressure vessel, turbine, condenser, and associated piping of the coolant system. He reactor pressure vessel is a 63-foot high tank with steel walls approximately eight inches thick. It encases the reactor core. He remainder of the coolant system, including the turbine and condenser and associated piping, provides containment for radioactisity in the primary coolant.

He drywell provides the fifth banier, it is a steel-lined vessel surrounded by concrete walls approximately 41/2 to 71/4 feet thick that enclose the reactor pressure vessel and recirculating pumps and piping.

He reactor building provides the sixth banier. It is a reinforced concrete and steel superstructure with walls approximately 5 feet thick that enclose the drywell and other plant components. He Reactor Building is always maintained at a negative pressure to prevent out-leakage.

Sources of Liauid and Airbome Efiluents Although the previously described barriers contain mdioactivity with high efliciency, small amounts of radioactive fission products are nevertheless able to diffuse or migrate through minor flaws in the fuel l 9

l

claddmg and into the reactor coolant. Trace quantities of reactor system component and structural surfaces which have been activated also get into the reactor coolant water. Many of the soluble fission and activation products such as iodines, strontiums, cobalts, and cesiums are removed by demineralizers in the purification system of the reactor coolant. The physical and chemical propenies of noble gas fission products in the primary coolant prevent their removal by the demmeralizers.

Because the reactor system has many valves and fittings, an absolute seal cannot be achieved. Minute dramage of radioactive liquids from valves, piping, and/or equipment associated with the coolant system may occur in the Reactor and/or Turbine Buildings. Noble gases, produced during the fission process, are collected as gaseous waste which is processed in :he multistage systems in the OCNGS Augmented Off-Gas Building, while the remaining radioactive liquids are collected in floor and equipment drains and sumps and are pumped to and processed in the OCNGS Radwaste Facility.

Reactor off-gas, consisting primarily of hydrogen and radioactive nons:ondensable gases, is withdrawn from the reactor primary system by steam jet air ejectors. Rese air ejectors drive the process stream through a 60 minute holdup pipe at approximately 110 cubic feet per minute and then into the Augmented Off-Gas (AOG) System. He holdup pipe allows radionuclides with short half-lives to decay. He Augmented OffGas System is a gaseous processing system which protides hydrogen conversion to water via a catalytic recombiner, removes the water (vapor) from the process stream, holds up the process stream to allow further decay of short-lived nuclides, and filters the off-gas using charcoal beds and High Efliciency Particulate (HEPA) filters prior to discharge to the base of the stack. Once the process stream enters the stack, it is diluted by building ventilation, which averages approximately 200,000 cubic feet per minute, is monitored and sampled, and then is discharged out the top of the 368-foot stack.

He liquid waste processing system receives water contanunated with radioactivity and processes it by filtration, demineralization, and distillation. Purified radwaste water is routinely recycled to the plant.

Occasionally, it may be necessary to discharge this purified water, under the guidelines of applicable permits, to the emironment. Contammants removed during the purification process are stored in the mdunste building and are eventually disposed of via the radioactive solids disposal systems. Before purificxi water is discharged to the emironment, it is firbt sampled, analyzed, assigned a release rate, and then released to the discharge canal which has a flow rate of 460,000 to 960,000 gallons per minute.

10

.f i 1 i DESCRIPTION OF THE OCNGS SITE c

General Infgrmation l

l Re Oyster Creek Nuclear Generating Station is located in Lacey Township of Ocean County, New  !

1 Jersey, about 60 miles south of Newark,9 miles south of Toms River, and 35 miles north of Atlantic i City. It lies approximately 2 miles inland from Bamegat Bay. The site, covering 1416 acres, is situated j a

partly in Lacey Township and, to a lesser extent, in Ocean Township. He Garden State Parimny bounds the site on the west. Access is provided by U. S. Route 9, passing through the site and

, separating a 661-acre castem portion from the balance of the property west of the higimny. He station is about 1/4 mile west of the higimny and 1-1/4 miles east of the Parkway. The site property extends

l about 3-1/2 miles inland from the bay; the maximum width in the north-south direction is almost I mile.

The site location is part of the New Jersey shore area with its relatively flat topography and extensive fresimater and saltwater marshlands. The south branch of Forked River runs across the northern side of the site and Oyster Crak partly borders the southem side.

I l

l It is estimated that approximately 3.3 million people reside within a 50 mile radius of the OCNGS (Ref.

3). The nearest population center is Ocean Township which lies less than two miles south-southeast of a the site. Based on 1994 population estimates,5908 people reside in Ocean Township. Two miles to the I north of the OCNGS, 23,897 people reside in Lacey Township (estimated 1994 population). Dover  ;

Township, situated 9.5 miles to the north, is the nearest major population center with a population of 81,550 (estimated 1994 population). The region adjacent to Barnegat Bay is one of the State's most  !

rapidly developing areas. In addition to the resident population, a sizable seasonal influx of people occurs during the sununer. This influx occurs almost exclusively along the waterfront.

1 Gimatological Summag

]

Meteorological data during 1996 were obtained from an on-site weather station. These data are subject to extensive quality assurance techniques and categorized for further analyses, including historical comparisons to both on-site and off-site sources as well as statistical processes to monitor instrument performance.

Climatological highlights during the year included variability from nonnal precipitation, a cooler than nomial summer, and the century's worst snowfall event. He region is usually marked by contrasting weather pattems.

I1

During the summer months, winds are predominantly from the south and southwest directions. His

~

ushers in warm and humid weather conditions. Precipitation resulting from these conditions is generally of short duration but high intensity (showers and/or thundershowers). During the autumn, winter, and early spring, winds are generally from the west and northwest. Air masses during this time originate from the upper midwestem United States and Canada They are characteriztxi by generally cold and dry conditions.

Wind direction frequencies were normal during the year. The four highest frequency of occurrence sectors for the year, as measured at the 33-foot level, were winds from the west-northwest, west, northwest, and west-southwest (Fig. 2). Rese wind directions reflect nonnal climatological conditions I

, found at this latitude and area of the country. Seasonal winds were evident as well, including the sea breeze circulation (Ref. 3) during the late spring through early autumn season. Resulting winds during a ,

sea breeze are from the south and southeast. His resulted in a marked maximum of wind frequency i from the south during 1996 showing the presence of this thennally-induced wind created due to the  !

differential heating between the land and the ocean.

l The annual average tempemture for the year was 51.74 degrees Fahrenheit, slightly cooler than last year's average temperature of 53.04 degrees. The historical average annual tempemture is 53 degrees.

Eight of the twelve months were characterized by below normal temperatures. He largest difference occurred during the months of March and November (Fig. 3). Higher than normal temperatures j occurred during the month of December. He average monthly temperature during this month was over four degrees in excess of the normal temperature of 36 degrees. One reason for the lack of cold air  !

during December and the beginning of 1997 was due to the abnormal position of the polar jet stream.

This " ocean of air" helps bring cold air south during the winter. With the jet stream further north, this j l

allowed warmer air masses originating from the Pacific Ocean to entrain the region. For the second straight summer, temperatures were slightly below nonnal. During the summer, a semi-permanent l feature known as a sub-tropical high pressure system usually settles over the southem half of the United States. This area produces southwest flow and ushers in warm, humid conditions. This system was rarely in existence over the mid-Atlantic region during 1996. Although there were periods of high humidity over the region, temperatures remamed near or slightly below normal with pronounced cloud cover.

12

WIND DIRECTION FREQUENCY OF OCCURRENCE - 1996 OYSTER CREEK NUCLEAR GENERATING STATION WIND DIRECTION "FROM" EACH COMPASS SECTOR VALUES IN PERCENT OF HOURLY OCCURRENCE SSW ssW s 1o%

sW 6% 8% -

SW 9% w3w NNW 11 % NNW 6% NW 6% NW 9% 9%

33-FOOT WIND DIRECTION 380-FOOT WIND DIRECTION NOTE: TIIE FOUR (4) IIIGIIEST FREQUENCY OF OCCURRENCE SECTORS ARE IIIGIILIGHTED

i MONTHLY MEAN AMBIENT AIR TEMPERATURE OYSTER CREEK NUCLEAR GENERATING STATION DURING 1996 COMPARED WITH HISTORICAL (1946-1981) l ATLANTIC CITY NATIONAL WEATHER SERVICE AVERAGE TEMPERATURE DATA

IN DEGREES FAHRENHEIT I

les 80 - ------------------------ --------------- ---------------------------------------------------------------

= -

Oyster Cre6k l + Atlantic Cit!y 3

! O  !

64 - ------------------------ ----------- ----- ---- ---- ----- ---------------------- c-I E  !

i g- - ....----.-- ..-- __------ ----- --.. ---. .... --.- -.-- ---- -- .-

2. -

Jan Feb Mar Apr May Jan Jet Aug Sep Oct Nov Dec  !

i  !

i t

i I

t

1 l

Precipitation pattems were the most interesting feature of the year. The annual total precipitation amount was 52.92 inches. His is over eleven inches more than the Atlantic City National Weather l Service historical average (1946 - 1981) of 41.50 inches. Above normal precipitation totals were the case during April, June, July, September, October and December (Fig. 4). The summer precipitation was a result of increased cloud cover due the lack of the sub-tropical high pressure system described  !

carlier. This dome of warm, humid, and generally clear air reduces the amount of precipitation to air W

mass thunderstorms of short duration but higli intensity. There was an increase in extra tropical storms over the east coast during the summer including tropical systems such as Bertha in June, Fausto in l

September, and Josephine in October. Over 25 inches of snow fell during an intense winter storm that ,

i developed from January 6 through January 8. Blizzard conditions occurred which included heasy i snowfall, winds in excess of 20 miles per hour, and temperatures hovering around 20 degrees. However, the monthly precipitation total for January was slightly below normal. In fact, less than nonnal precipiiation was experienced during the January-March period. Due to the below normal temperatures for the first quarter, snowfall amounts were much above normal. Generally, the region will see l approximately 10 inches of snow. During 1996, the area received almost 40 inches. In summary, precipitation events in the region were a result oflarge extrats - 41 stomis, especially during the fall, winter, and early spring as well as the aforementioned tropical systems during the summer and early fall.

Also, precipitation during the spring and fall was attributable to the passage of warm fronts. A third j source of precipitation was from convective activity due to summer heat and humidity build up.

l However, a more frequent summer cloud cover reduced this source of violent weather (hail, lightning, tomado activity) during 1996.

For additional site specific meteorological data, refer to the OCNGS Annual Radioactive Efiluent Release Report for 1996 (Ref. 30) .

I i

15

MONTHLY PRECIPITATION OYSTER CREEK NUCLEAR GENERATING STATION D.URING 1996 COMPARED WITH HISTORICAL (1946-1981)

ATLANTIC CITfY NATIONAL WEATHER SERVICE AVERAGE PRECIPITATION DATA RAINFALL IN INCHES 10.00 8.08 8.00 - ------------------------------------------------------------------------------------------- ----

N Oyster Creek NGS 6.M 6.54 O Atlantic City NWS 6.06 6.00 - ------------------------------------------ ------ -------------- - . . . 5J2 . . . . . . . . . . . . . . ....

g C

E $

4.51 4.6 .

4.1 4.00 - --~~-- - --- - '-- '---~~' '--------'U ---

3.5 -

"z .f^f 3.5 - - - - - - - - - - - - - - - - -3.5 7 3.3

- - - - - - - - 3] - - - -

_ 3.2 3.05 18 19 2.59 27 _

---j - --- -- - -- - --- - --- - - - - - - -

- - i . 58- --- - -

2.00 -.-I-0.73 3

~1 0.M . .' . . . . . . . .

Z sc 2  % > Z 4 C A g > U A E s 4 g R R S n o @ E

EFFLUENTS Historical Backaround Almost from the outsct of the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazard of iomzing radiation was recogmzed and efforts were made to establish radiation protection standards. The International Commission on Radiological Protection (ICRP) and the National Council on Radiation Protection and Measurements (NCRP) were established in 1928 and 1929, respectively, R ese organizations have the longest continuous experience in the review of radiation health effects and with making recommendations on guidelines for radiological protection and radiation exposure limits. In 1955, the United Nations created a Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) to summarize reports received on radiation levels and the effects on man and his environment. He Nationi Academy of Sciences (NAS) fonned a committee in 1956 to review the biological effects of atomic radiation (BEAR). A series of reports have been issued by this and succeeding NAS committees on the biological effects of ionizmg radiation (BEIR), the most recent during 1990 (known as BEIR V).

Rese committees and commissions of nationally and intemationally recognized scientific experts have been dedicated to the understanding of the health effects of radiation by investigating all sources of relevant knowledge and scientific data and by providing guidance for radiological protection. Heir members are selected from ur.iversities, scientific iesearch centers, and other national and intemational research orgaruzations. He committee reports contain scientific data obtained from physical, biological, and epidemiological studies on radiation health effects and serve as scieWic references for information presented ir.this report.

Since its inception, the USNRC has depended upon the recommendations of the ICRP, the NCRP, and the Federal Radiation Council (FRC) (incorporated in the United States Environmental Protection Agency (USiiPA) m 1970) for basic radiation protection standards and guidance in establishing regulations for the nuclear industry (Ref. 6 through 9).

Efiluent Release Limits As part of routine plant operations, limitcd quantities of radioactivity are released to the emironment in liquid and airbome effluents. An effluent control program is implemented by GPU Nuclear to ensure radioactivity released to the emironment is muumal and does not exceed release limits. He Federal 17

i govemment establishes limits on radioactive materials released to the emirorunent. These limits are set  ;

at low levels to protect the health and safety of the public and are specified in the OCNGS Technical Specifications and Offsite Dose Calculation Manual (ODCM) (Ref. I and 2). GPU Nuclear conducts operations in a manner that holds radioactive emuents to small percentages of the federal limits.

A recommendation of the ICRP, NCRP, and FRC is that radiation exposures rhould be maintained at levels which are "as low as reasonably achievable" (ALARA) and commensurate with the societal 3

benefit derived from the activitics resulting in such exposures. For this reason, dose limit guidelines were

, established by the USNRC for releases of radioactive effluents from nuclear power plants. These guidelines were then used as the basis for the development of the Offsite Dose Calculation Manual

' (ODCM) and Technical Specifications. In keeping with the ALARA principle, the OCNGS operates in a manner that results in radioactive releases that are a small fraction of these limits.

. Applicable OCNGS Offsite Dose Calculation Manual limits are as follows:

- ODCM Specification 4.6.1.1.3.A Radioactivity Concentration in Liquid Emuent i

The concentration of radioactive nuterial, other than noble gases, in liquid emuent in the discharge canal at tiv: U.S. Route 9 bridge shall not exceed the concentrations specified in

~

10CFR Part 20, Appendix B, Table II, Cohunn 2.

4

- ODCM Specification 4.6.1.1.3.B Radioactivity Concentration in Liquid Emuent

. He concentration of noble gases dissolved or entrained in liquid emuent in the discharge carul at the U.S. Route 9 bridge shall not exceed 2.0 E-4 uCi/ml.

- ODCM Specification 4.6.1.1.4.A Limit on Dose Due to Liquid Emuent l l

Re dose to a MEMBER OF TIIE PUB 11C due to radioactive mateiial in liquid efIluent in the UNRESTRICTED AREA shall not execca. j i

l l

1 18 1 I

u

1.5 mrem to the Total Body during any calendar quaner 1 5.0 mrem to any body organ during any calendar quaner  !

I 3.0 mrem to the Total Body during any calendar year  !

or I 10.0 mrem to any body organ during any calendar year. i

- ODCM Specification 4.6.1.1.5.A Dose Rate Due to Gaseous Emuent 1he dose equivalent rate in the UNRESTRICTED AREA due to radioactive noble gas in gaseous emuent shall not exceed 500 mrem / year to the total body or 3000 mrem / year to the skin.

- ODCM Specification 4.6.1.1.5.B Dose Rate Due to Gaseous Emuent 1he dose equivalent rate in the UNRESTRICTED AREA due to tritium (H-3),1-131, I-133,  ;

and to radioactive material in particulate fonn iming half-lives of 8 days or more in gaseous emuents shall not exceed 1500 mrem / year to any body organ when the dose rate due to H-3, Sr-89, Sr-90, and alpha-emitting rad 3nuclides is averaged over no more than 3 months and the i

dose rate due to other radionuclides is averaged over no more than 31 days. 1

- ODCM Specification 4.6.1.1.6.A Air Dose Due to Noble Gas in Gascous Emuent The air dose in the UNRESTRICTED AREA due to noble gas released in gaseous emuent shall not exceed:

5 mrad / calendar quaner due to gamma radiation 10 mrad / calendar quarter due to beta radiation 10 mrad / calendar year due to gamma radiation 20 mrad / calendar year due to bett radiation 19

- ODCM Specification 4.6.1.1.7.A Dose Due to Radiciodine and Particulates in Gascous Effluent The dose to a MEMBER OF Tile PUBLIC from I-131,1-133, and from radiciodines in particulate fonn having half-lives of 8 days or more in gaseous emuent, in the UNRESTRICTED AREA shall not exceed 7.5 mrem to any body organ per calendar quarter 4

or 15 mrem to any body organ per calendar year.

d

- ODCM Specification 4.6.1.1.8.A Annual Total Dose Due to Radioactive Emuent J

The annual dose to a MEMBER OF Ti1E PUBLIC due to radioactive material in efIluent from

, the OCNGS in the UNRESTRICTED AREA shall not exceed 75 mrem to his/her thyroid or 25 mrem to his/her total body or to any other organ.

2 Emuent Control Progr;un Efiluent control includes plant components such as the ventilation system and filters, off-gas holdup components, demineralizers, and an evaporator system. In addition to ndnimizing the release of radioactivity, the efIluent control program includes all aspects of emuent and emironmental monitoring.

This includes the operation of a complex radiation monitoring system, collection and analysis of efiluent samples, emironmental sampling and monitoring, and a comprehensive quality assurance program.

Over the years, the program has evolved in response to changing regulatory requirements and plant conditions. For example, additional instnunents and samplers have been installed to ensure that measurements ofeffluents remain onscale in the event of any accidental release of radioactivity.

Efiluent Instmmentation: Liquid and airbome efIluent measuring instrumentation is designed to monitor the presence and the amount of radioactivity in effluents. Many of these instnunents proside continuous j surveillance of radioactivity releases. Calibrations of effluent instruments are performed using reference l

t standards certified.by the Natiod lastitute of Standards and Technology (NIST). Instmment alarm setpoints are pre-set to ensure that effluent release limits will not be exceeded If radiation monitor alarm I setpoints are reached, releases are inunediately terminated. Where continuous suneillance is not  ;

l 20

)

1 J

l l

l practicable or possible, contingencies are specified in the Offsite Dase Calculation Manual and/or the Technical Specifications.

Emuent Sampline and Analysis: In addition to continuous radiation monitoring instmments, samples of i 1

cmuents are taken and subjected to laboratory analysis to identify the specific radionuclide quantities l

being released. A sample must be representative of the emuent from which it is taken. Sampling and analysis provide a sensitive and precise method of determining emuent composition. Samples are analyzed using state-of-the-art laboratory counting equipment. Radiation instmment readings and l sample results are compared to ensure correct correlation.

Emuent Data 1

As part of routine plant operations, limited quantitics of radioactivity are released to the erwironment in emuents. The amounts of radioactivity released vary and are dependent upon operating conditions, power levels, fuel conditions, emciency ofliquid and gas processing systems, and proper functioning of plant equipment. The largest variations occur in the airbome emuents of fission and activation gases, which are proportional to the integrity of the fuel cladding and the operation of the OCNGS Augmented

. OffGas system. In genera', effluents have been decreasing with time due to improved fuel integrity and i increased efficiency of processing systems.

The amount of radioactivity released in emuents from the OCNGS during 1996 was the smallest in the history of Station operation and only one liquid release occurred during the year. In September, 148,600 gallons of slightly radioactive water was inadvertently released from the OCNGS to the environment.

His release occurred during a scheduled plant refueling outage with the reactor in cold shutdown for approximately two weeks. Tritium (11-3) was the predominant radionuclide in the liquid release while Xc-135 was the predominant nuclide in gaseous releases (Table 2). Estimated doses to the public, attributable to these emuents, were a small fraction of the applicable regulatory limits (Tables 6 and 7).

Summaries of OCNGS emuents can be found in Table 2 and in the Annual Emuent Release Report that is submitted to the USNRC (Ref. 30). Radioactive constituents of these emuents are discussed in the following sections:

Noble Gases: The predonunant radioactive materials released in OCNGS airbome emuents are the noble gases krypton (Kr) and xenon (Xe). Small amounts of noble gases can also be released in liquid 21

~

TABLE 2 RADIONUCLIDE COMPOSITION OF OCNGS EFFLUENTS FOR 1996 Radionuclide l Half-Life l Liquid Effluents (Ci) Airborne Effluents (Ci)

H-3 l 1.23E 1 Years l 6.14E 0 1.52E I Cr-51 l 2.78E 1 Days l < LLD 3.74E-4 Mn-54 l 3.12E 2 Days l 5.91 E-4 1.01E-4 i Co-58 l 7.14E I Days l 4.07E-4 2.09E-5 Co-60 l 5.26E O Years l 1.63E-3 3.07E-4 Kr-85m l 4.50E O Hours l < LLD 4.94E 0 Kr-87 l 7.60E 1 Minutesl < LLD 1.81E 1 Kr-88 l 2.80E O Hours l < LLD 1.19E 1 Sr89 l 5.05E I Days l < LLD 1.16E-3 Sr-90 l 2.88E I Days l < LLD 1.30E-5 I-131 l 8.05E 0 Days l < LLD 2.18E-3 1-133 l 2.09E 1 Hours l < LLD 6.26E-3 Xe-133 l 5.20E 0 Days l < LLD 4.38E O Xe-135 l 9.10E O Hours l < LLD 2.44E 1 Cs-137 l 3.02E 1 Years l 1.35E-4 5.78E-5 Ba-140 1.28E I Days < LLD 4.96E-4 Alpha _

< LLD 3.79E-6 NOTE: All effluents are expressed in scientific notation. No other nuclides were detected.

NOTE: < LLD = less than lower limit of detection.

22

i emuents. He total amounts of krypton and xenon released into the atmosphere in 1996 were 34.9 curies and 28.8 curies, respectively. Noble gases are inert, wl$ich means they do not react chemically or biologically. Xenon-135 with a half-life of 9.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> was the most abundant noble gas released. These l

noble gases were readily dispersed into the atmosphere when released and because of their short half-lives, quickly decayed into stable, nonradioactive forms. No noble gas activity was released in liquid emuents during 1996.

lodines and Particulates: He discharge ofiodines and particulates to the emironment is muunuzed by factors such as their high chemical reactivity, solubility in water, and the high removal emciency of airbome and liquid processing systems.

Of the gaseous radioiodines, iodine-131 is of particular interest because ofits relatively long half-life of 8.05 days. Particulates of relative concem are the radiocesiums (Cs-134 and Cs-137), radiostrontmms 1

(Sr-89 and Sr-90), and activation products, manganese-54 (Mn-54) and cobalt-60 (Co-60). The total l amount ofiodines and paiticulates released from the OCNGS in 1996 was 0.011 curies in airbome j l

emuents and 0.00276 curies in liquid emuents. j Tritium: Tritium is typically the predominant radionuclide released in liquid emuents and is also released in airbome emuents. Tritium is a radioactive isotope of hydrogen. It is produced in the reactor coolant as a result of neutron interaction with the naturally-occurring deuterium (also a hydrogen isotope) present in water. One liquid release was made from the OCNGS during 1996 in which 6.14 curies of tritium was released. The total amount of tritium released in airbome emuents uns 15.2 curies. To put these amounts of H-3 into perspective, the world inventory of natural cosmic ray-produced tritium is 70 million curies, which corresponds to a production-rate of 4 million curies per year (Ref.10). Tritium contributions to the emironment from nuclear power production are too small to have any measurable effect on the existing global emironmental concentrations.

Transuranics: Transuranics are produced by neutron capture in the fuel, and typically emit alpha and beta particles as they decay. Important transuranic isotopes produced in reactors are uranium-239 (U-239), plutonium-238 (Pu-238), plutonium-239 (Pu-239), plutonium-240 (Pu-240), plutonium-241 (Pu-241), americium-241 (Am-241), plutonium-243 (Pu-243), plus other isotopes of americium and curium. They have half-lives mngmg from hundreds of days to millions of years. Greater than 99% of all transuranics are retained within the nuclear fuel.

23

i i

4

'Ihese nuclides are insoluble and non-volatile and are not readily transported from in-plant pathways to the environment. Gaseous and liquid processing systems remove greater than 90% of transuranics that may be found in the reactor coolant. Because retention and removal efficiencies are so high, transuranics are not routinely morutored.

Carbon-14: Production of carbon 14 (C-14) in reactors is small. It is produced in the reactor coolant as

! a result of neutron interactions with oxygen (0) and nitrogen (N). Estimates for all nuclear power production worldwide show that 235,000 curies were released from 1970 through 1990 (Ref. I1).

t Carbon-14 also is produced naturally by the interactions of cosmic radiation with oxygen and nitrogen in l the upper atmosphere. The worldwide inventory of natural C-14 is estimated at 241 million curies j (Ref. I1). Since the inventory of natural carbon-14 is so large, releases from nuclear power plants do not result in a measurable change in the background concentration of carbon-14. Consequently, carbon-14 is not routinely monitored in plant effluents.

0 0 24

. -, .c ., ,. , . , , -. ._ . . . _ , . , - . . . . - . _ - . _ . . -

RADIOLOGICAL ENVIRONMENTAL MONITORING GPUN conducts a comprehensive radiological emironmental monitoring program (REMP) at OCNGS to monitor radiation and radioactive materials in the emironment. The infonnation obtained from the REMP is then used to detennine the effect of OCNGS operations, if any, on the emironment and the public.

He USNRC has established regulatory guides which contain acceptable monitoring practices (Ref.12).

De OCNGS REMP was designed on the basis of these regulatory guides along with the USNRC Radiological Assessment Branch Technical Position on Emironmental Monitoring (Ref.13). Regarding the OCNGS REMP, all of these guidelines have been met and in most cases have been exceeded.

He objectives of the REMP are:

o to assess dose impacts to the public from OCNGS operations o to verify in-plant controls for the containment of mdioactive materials o to detennine buildup of long-lived mdionuclides in the emironment and changes in background radiation levels o to provide reassurance to the public that the program is capable of adequately assessing impacts and identifying noteworthy changes in the radiological status of the emironment o to fulfill the aquirements of the OCNGS Offsite Dose Calculation Manual (ODCM) and Technical Specifications Emironmental Exposure Pathways to Humans from Airbome and Liquid Efiluents As previously discussed in the "Efiluents" section, small amounts of radioactive materials are released to i the emironment as a result of operating a nuclear generating station. Once released, these materials move through the emironment in a variety of ways and may eventually reach humans sia breathing, dankmg, eating, and direct exposure. Dese routes of exposure are referred to as emironmental exposure pathways. Figure 17 illustrates the important exposure routes.

25

i While some pathways are relatively simple, such as inhalation of airbome radioactive materials, others may be complex. For example, radioactive airbome particulates may deposit onto forage, which when eaten by cows, may be transferred into milk, which is subsequently consumed by man. His route of exposure is known as the air-grass-cow-milk-hunun pathway. l l

Although radionuclides can reach humans by a number of pathways, some are more important than others. The critical pathway for a given radionuclide is the one that produces the greatest dose to a population or to a specific segment of the population. His segment of the population is known as the critical group and may be defined by age, diet, or other cultural factors. The dose may be delivered to the whole body or confined to a specific organ; the organ receiving the greatest fraction of the dose is

known as the critical organ. His information was used to devriop the OCNGS REMP.

Sampling The OCNGS radiological environmental monitoring program consists of two phases - the preoperational and the operational. Data gathered in the preoperational phase are used as a basis for

, evaluating mdiation levels and radioactivity in the vicinity of the plant after the plant becomes operational. He operational phase began in 1969 when the OCNGS attained initial criticality.

The program consists of taking radiation measurements and collecting samples from the emironment, analyzing them for radioactive content, and interpreting the results. Emphasis is on the critical exposure pathways to humans with samples taken from the aquatic, atmospheric, and terrestrial emironments.

Rese samples include air, well water, surface water, clams, sediment, fish, crabs, and vegetables.

Thermoluminescent dosimeters (TLDs) are placed in the emironment to measure gamma radiation

. levels. He Offsite Dose Calculation Manual (ODCM) Specifications, along with recommendations from GPUN scientists, specify the sample types to be collected and analyses to be performed.

Sampling locations were established by considering meteorology, population distribution, hydrology, and land use characteristics of the local area. He sampling locations are divided into two classes, indicator and background. Indicator locations are those which are expected to show effects from OCNGS

. opemtions, if any exist. Rese locations were primarily selected on the basis of where the highest predicted emironmental concentrations would occur. While the indicator locations are typically within a

, few miles of the plant, the background stutions are generally at distances greater than 10 miles from the OCNGS. Herefore, background samples are collected at locations which are expected to be unaffected 26

by station operations. They provide a basis for evaluating fluctwions at indicator locations relative to natural background radioactivity and fallout from prior nuclear wet pon tests. Figures 5, 6, and 7 show l the current sampling locations around the OCNGS. Table A-1 in rppendix A describes the sampling locations by distance and azimuth (compass direction) from the OCNGS, along with ty1xis) of samples collected at each sampling location.

Analysis j l

I l In addition to specifying the minimum media to be collected and the minimum number of sampling locations, the Offsite Dose Calculation Manual (ODCM) Specifications include the frequency of sample collection and the types and frequency of analyses to be performed. Also specified am analytical sensitivities (detection limits) and reporting levels. Table A-2 in Appendix A provides a synopsis of the I sample types, number of sampling locations, collection frequencies, number of samples collected, types and frequencies of analyses, and number of samples analyzed. Table A-3 in Appendix A lists sampics which were not collected or analyzed per the requirements of the ODCM Specifications. Sample analyses which did not meet the required analytical sensitivities are presented in Appendix B. Changes in sample collection and analysis are described in Appendix C.

The analytical results are routinely resiewed by GPUN scientists to assure that established sensitisities have been achieved and that the proper analyses have been perfonned. All ana!>tical results are subjected to an automated review process which ensures that ODCM-required lower limits of detection are met and that reporting levels are not exceeded. Investigations are conducted when action levels or reporting levels are reached or when anomalous values are discovered. He action levels were established by GPUN and are typically 10 percent of the reporting levels specified in the ODCM Specifications. These levels are purposely set low so that corrective action can be initiated before a reporting levelis reached.

Table 3 provides a summary of radionuclide concentrations detected in the primary emironmental samples for 1996. He data are smnmarized in a format that closely resembles the suggested format presented in the USNRC Branch Technical Position (Ref.13). Quality Assurance (QA) sample results on split and/cr duplicate samples were used to verify the primary sample results.

27

i Fi re 5 i

i l

I I

i i

i i

i l

l t

l l

l i

i I

i i

4 1

4 i Oyster Creek Nuclear Generating Station (OCNGS)

} Locations of Radiological Environmental Monitoring Program (REMP) l Stations within 1 mile of the site 28 l

l

~

r -

l t "

l -

.C

[

(- -

J Oyster Creek Nuclear Generating Station (OCNGS)

Locations of Radiological Environmental Monitoring Program (REMP)

Stations greater than i mile and within 2 miles of the site 29

l f

i I

i l Figure 7 i

\

i j

i 1

l l

I t

i a

Oyster Creek Nuclear Generating Station (OCNGS)

} Locations of Radiological Environmental Monitoring Program (REMP) j Stations greater than 2 miles from the site 4

30 f

i 1

t -. . - , . . . - . - . , - . , - - . . . . . - , - - , . , , _ = - . . , -., , . - . - - .

1 4

Measurement of low radionuclide concentrations in emironmental media reqmres special analysis

, techruques. Analytical laboratories use state-of-the-art laboratory equipment designed to detect beta and

. gamma raAation. This equipment must mcet the required analytical sensitivities. Examples of the specialized laboratory equipment used are germanium detectors with multichannel analyzers for _

determuung specific gamma enutting radionuclides, liquid scintillation detectors for detecting tritium, low level proportional counters for detecting gross beta radsoactivity, and coincidence counters for low level 4

1-131 detection. Computer hardware and software used in conjunction with the counting equipment

< perform calculations and provide data management. Analysis methods are described in Appendix 1.

Ouality Assurance Procram i l

i .

2 A Quality Assurance (QA) program is conducted in accordance with guidelines prosided in Regulatory l Guide 4.15, "Quahty Assurance for Radiological Monitoring Programs" (Ref.16) and as required by the ODCM Speci6 cations (Ref. 2) and Technical Specifications (Ref.1). The QA program is documented i

by GPUN written policies, procedures, and records These documents encompass all agects of the ]

REMP including sample collection, equipment calibration, laboratory analysis, and data resiew. I l The QA program is designed to identify possible deficiencies so that imnuhate corrective action can be

. taken if karranted. It also provides a measure of confidence in the results of the monitoring program in 1

order to assure the regulatory agencies and the public that the results are valid. The Quahty Assurance program for the measurement of radioactivity in emironmental samples is implemented by:

o auditing all REMP-related activities including analytical laboratories o requinng analytical laboratories to participate in an NRC approved Emironmental Radioactivity Intercompanson Program o requiring analytical laboratories to split samples for separate analysis (recounts are performed when samples are not able to be split) o splitting samples, havirig the samples analyzed by independent laboratories, and then comparing the results for agreement o reviewing QA results of the analytical laboratories including spike and blank sample results and duplicate analysis results 31

2 i

De Quality Assurance program and the results of the Environmental Radioactisity Intercomparison  !

1 ,

Program are outlined in Appendices D and E, respectively.  !

he TLD readers are calibrated monthly agamst standard TLDs to within five percent of the standard  !

j TLD values. Also, each group of TLDs processed by a reader contains control TLDs tint are used to ,

1 l correct for minor variations in the reader, he accuracy and variability of the results for the control i TLDs are exanuned for each group ofTLDs to assure the reader is functioning properly. l t

Other cross checks, calibrations, and certifications are in place to assure the accuracy of the TLD l  !

Program

. l o Semiannually, randomly selected TLDs are sent to an independent labor < tory where j

they are irraAated to set doses not known to GPUN. The GPUN dosimetry laboratory l~

j processes the TLDs and the results are compared agamst established limits r

1

o Every two years, each TLD is checked for meus within 10 percent of a known value'  ;

i o Every two years, the GPUN dosunetry program is 'ess.M and imJe by the i NIST National Voluntary Laboratory Accreditation Program (NVLAP) -

l' i .

)

l o Ten OCNGS REMP TLD stations have collocated quality assurance badges which are processed by an invk=vimt laboratory (Teledyne Brown Engmeering). He results

! are compared against GPU Nuclear Panasonic TLD results

(

i ne environmental dosimeters were tested and qualified to the Amencan National Standard Institute's j (ANSI) Publication N545-1975 and the USNRC Regulatory Guide 4.13 (Ref.14 and 15). In addition i to the OCNGS REMP, the Nuclear Regulatory Comnussion (NRC) and the New Jersey Department of t-1 Emironmental Protection (NJDEP) also mamtam suneillaro: programs in the OCNGS area. Rese programs provide independent assessments of rachoactive releases and the radiological impact on the surroundmg emironment. He results from these programs have been consistent with the results from

the OCNGS REMP. j i

4 4

i i

32 i

- ~

TABLE 3.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROCRAM

SUMMARY

NUCLEAsr OYSTER CREEK NUCLEAR GENERATING STATION J ANUARY,1996 THROUGH DECEMBER,1996 THE FOLLOWING PAGES ARE A

SUMMARY

OF REMP DATA FOR THE SCHEDULED COLLECTION PERIODJANUARY,1996 THROUGH DECEMBER,1996. DATA

• ARE SUMMARIZED ON AN ANNUAL BASIS,WHEREt DLSCJITION OF TERMS l

. 1 SAMPLE TYPE -> Media being analyred I ANALYSIS -> Type of analysis being performed on the particular media.

• OF ANALYSES PERFORMED -> The itwal number of analyses performed for a particular sample type.

1 LLD -> The mean lower limit of detection. Please note that this value is based on samples m hose results showed no detectable activity. I INDICATOR STATIONS -> The mean, minimum and maximum based on detectable activities of all indicator stations.

IIIGilEST ANNUAL MEAN -> The mean, minimum and maximum based on detectable activities of the station with the highest annual mean.

STATION -> The station designation with the highest annual mean.

B ACKGROUND STATIONS -> The mean, minimum and maximum based on detectable activities of all background stations.

t NflTYD -> The fraction of detettable activities / Total number of analyses performed.

BACKGROUND STATIONS AT OCNGS STATION (S): A. C. II,14 31.94 1 36 SAMPLE TYPE (S): AIR PARllCULATE SEDIMENT WELL WATER VEGETABLFS AIR IODINE CLAMS SURFACE WATER FISII" BLUE CRAB" I An asterisk (') indicates em data.

" Station 94 only.

33

TAttE3 -

RADIGIDGICAL DIVERONMENTAL MONITUltfMO PROGRAM -

OYST7A CREEK NUCIEAR CENEIRAT1NG STATION NUCLEAR  : JANUARY.1996 THROLM;N DECCEMBER,1996

. ANNUALlttm4 MARY SAMPt1 ANALYSIS NUC1JDE #(W- RJD INIMCATUR STA110NS RIGOHutT ANNUAL MNb BACKGROUND STATIONS TIfPE AN Al. ' MIN MEAN ~ MAX (N/ TOT) - MIN MEAN MAX' (NrfY)T) MIN MEAN MAX (NrtUT)

FFRF. W AIR PARTICULATE Gnus Beta 349 Noll.D 6.80E4)3 1.43E4)2 2.50E-02 (241/241) 9 60E413 1.51E4)2 2.50E-02 (27/27) 1.46E-02 1.71 E4)2 2.35E4)2 (IOR/IOR)

(pCVml) Regtuted StaraM 72 AIR PART1CULATE Gamme Scan Ag-11(kn 52 5.12E-01 <LLD (LLD <LLD (W36) (LLD <LLD <LLD ifW4) <LLD <t ID <LLD (Wl6)

(ITVml)

AIR PAR 11CULA"E Garr.ma Scan Ba-140 52 3.99E-03 <LLD (LLD <LLD (0/36) <LLD (LLD <LLD (0/4) <Lil) <LLD <LLD (W16)

(pCVml)

AIR PARllCULATE Ganana Scan Be-7 52 No ul) 4 30E-02 6.52E-02 8.30E-02 (36/36) 6.10E-02 7.23E4)2 8.30E4)2 (4/4) 4.10E42 6 45E4)2 R.40E4)2 (16/16)

(rfum3) Regwwted StatuM 20 AIR PARTICULATE Gamma Scan Co-58 52 6.37E4M <LLD <LLD <LLD (0/36) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (0/16)

(pCVm3)

AIR PARTICULATE Gamma Scan Co-60 52 7.33E4M <LLD <LLD <LLD (W36) <LLD <LLD <LLD (9/4, <LLD <LLD < LID (0/16)

IgTUm3)

AIR PARTICULATE Ganuna Scan Cs-134 52 5.69E4M <LLD <LLD <LLD (0/36) <LLD <LLD <LLD (0/4) (LLD <LLD <LLD (0/16)

(pCvmin 34

TABtE.3

. RAD 50tDGICAL ENVIRONMENTAL MONTTORfMG FROGRAC h NUCLEAR > ; OYSTFJt CREFJL NtCLEAR GENERA 11NG STATNM

, f JANUARY,19% THROUGH DECDfBER,19%

ANNUAL 8UMMARY RNDICATURSTATIONS - MIGMFET ANNUAI.MFAN BACKGINM.TMD STAT 10NS

' SAMPIE ANALYSIS ' NUClJDE : 40F- RlD .

. MIN MEAM: i. MAX .i (N/ TOT) ' MIN ; .MEAM MAX -~

(N/lUT)- MIN MEAN MAX (N/f0T)

TYPE AMAI. '

Statiuse-#

PERF.

AIR

<LLD <LLD (W36) <LLD <LLD <LLD (0/4n <LLD <LLD <LLD (0/16)

PARTlCULATE Gamma Scan Cs-137 52 5.90E 04 <LLD (pCum3)

AIR <LLD

<LLD <LLD (0/16) (LLD <LLD <LLD (0/41 (LLD <LLD (Wl6)

PART1CULATE Gamma Scan hi9 52 1.41E4)3 <LLD (pCahn3)

AIR

<LLD <LLD <LLD <LLD <LLD (W4) <ll.D <LLD <LLD (0/16)

PART1CULATE Gamma Scan 1-131 52 1.6t E-03 <LLD (0/36)

(gumi)

AIR (1/36) 5 00E4)3 5.90E4)3 5.90E4)3 (1/4) 1.40E4)2 1.*)E-02 L40E-02 (1/16)

PARTICULATE Gamma Scan K 40 52 1.03E-02 5.90E-03 59)E4)3 5.90E-03 Statm# I (pCVm3)

AIR

<LLD <LLD <LLD <LLD <LLD (0/4) <LLD <LLD <LLD (0/16)

PART1Cl u 1E Gamma Scan La-140 52 1.95E4)3 <LLD (0/36)

(gi/m3)

AIR <LLD (0/16)

<LLD <LLD <LLD (0/36) <LLD <LLD <LLD (0/4) <LLD <LLD PART1CULATE Gamma Scan Mn-54 52 6ME414 (pCVmi)

AIR

<LLD (LLD <LLD <LLD (0/4) <LLD (Lt.D <LLD (0/16)

PARTICULATE Gamma Scan Nb-95 52 8.23E-04 <LLD <LLD (0/36) s p'i/mli 35

. TABt2 3 .

RADIO 00GICAL ENVIRONMENTAL N, PROGRAM ?

OYMR CREEK NUCLFAR GENERATING STATION NUCLEAR . JAMUARY.1996 TIEROUCII DECEBEBER,19N

= - AMMUAL

SUMMARY

SAMPt.E ANALYSIS NUCLIDE S OF -_ IJD ENDDCATUR STA110MS NIGHFST AMMUAL MFAN - BACK(M?ND STATIONS 1YPE ANAL MIM . .MEAN MAXI (MftD T) . MIN MEAM MAX (Nf1T)T) MIM - MFAN MAX (MrIU T)

PFRF. !Pa.tM ,

AIR PARTICULATE Gamma scan Ra-226 52 9 80E-03 1.00E4)2 1.fDE-02 1.00E-02 (1/36) 1.(UE412 1.00E42 1.00E42 (1/4) 1.IOE-02 1.10E4)2 1.10E412 (1/16)

(pCvm3) Statan# 66 AIR PARTICULATE Gamma Scan Sh-125 52 1.37E4)3 <LLD <LLD <LLD (0/36) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (Wl61 (rC hn3)

AIR PARTICULATE Gamma Scan Th-232 52 2.38E-03 <LLD <LLD <LLD (0/36) <LLD <LLD <LLD (0/4) <LLD <LLD <LLD (W16e (pCunt1)

AIR PARTICULATE Gamma scan U-235 52 2.22E-03 <LLD (LLD <LLD (0/16) <LLD <LLD <LLD (W4) (LLD <LLD <LLD (W16)

(rfum3)

AIR PARllCtfLATE Gamma Scan Zn-65 52 1.47E4)3 <LLD (LI D <Lt.D (0/36) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (Wl6)

(pCumb AIR PARTICULATE Gamma Scan Zr-95 52 1.0RE4)3 <LLD <LLD <LLD (0/36) <LLD <LLD <LLD (W4) <LLD <LLD <tLD (Wl6) q<Vml)

AIR IODINE Inhne-131 6R5 1.81E412 (LLD (LLD <LLD (W473) <LLD <LLD <LLD (0/53) <LLD <LLD <t1D (W212)

(rCvml) 36

TAMES.

RADODEAMMCAL ENVlW0lWEENTAL MONITURNIG FROGRAM ,

GN NUCLEAR oviii CREEK NUCERAR GODERATING STA) UN

JANUARY.199611tROUGN BRCllMBER,1995,'

ANNUAL MmtMARY 54MPtA : ANALY515 NUCIJDE #OF tJE - IMDOCATUR STA1101W NIGINQTT AM18UAL MEAN BACKGROUND WATMMits 1TPE ' ANAt. ' MIN ~ MEAN MAX (Nff0T) ' MfM. h aEAN - MAX ,M) . ' MfM MEAN' MAX (N/ TOT)

PEur.

w SURFACE WARR Gamma Scan Ag-I lom 48 1.96E+00 <LLD (LLD <LLD (W32) <LLD <LLD (LLD (W4) <LLD <LLD <LLD (WI6) f(CL/L)

SURFACE WATER Gamma Scan Ba-140 48 9.79E+00 <LLD <LLD <LLD (W32) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (0/16)

(pCUL)

SURFACE WATER Gamma Scan Be-7 4A I.64E+01 <LLD <LLD <LLD (0/32) (LLD <LLD <LLD (W4) <LLD <LLD <LLD (0/16)

(pCi/L)

StOFACE WATER Gamma Scan cms 8 48 2.13E+00 <LLD <LLD <tLD (W32) <tLD <LLD <LLD (W4) <LLD <LLD <LLD (0/16)

(pCil)

StCFACE WATER Gamma Scan Co 60 48 2.34E+00 <LLD <llD <LLD (0/32) (11D <1lD <LLD (W4) <LLD <LLD (LLD (W16)

(pCi/L)

SURFACE WATER Gamma Scan Cs-134 48 1.83E+00 <LLD <LLD <LLD (0/32) <LLD <LLD <LLD (0/4) <LLD <1lD <LLD (0/16)

(;CdL)

SURFACE WARR Gamma Scan Cs-137 48 2.17E+00 <LLD <LLD <LLD (0/32) <LLD <LLD <LLD (0/4) (LLD <t1D <LLD (0/16)

I igCi/L)

SURFACE WATER Gamma Scan Fe-59 48 4.69E+00 (LLD <LLD <LLD (0/32) <LLD <llD (LLD (0/4) (LLD <llD <LLD (W16)

(pCi/L)

SURFACE WATER GammaSem I-131 4R 3.49E+M <LLD <LLD <LLD (0/32) <LLD <LLD <LLD (0/4) <LLD <LLD <LLD (0/16)

{pCi/L) 37

-TAgtA 3 -:

. RADIOEDGKAL ENVIROfWIENTAL MONt1DRING FROGRAM .

hN OY1mER CRERK NUCLEAR GitNBRATING STAT 10M NUCLEAR J ANUARY.19n 75 trot >GN DRCD0BER,194 ..

ANNUAL RUMMARY '

SAMPIA ANALYSE - MUC1JDir, eor. 3J3 3NDICATOR NTAT10NS ' NIGHICNT ANNUAL MEAN BACKGROUND STAT 10fG TYPE. ANAL. ' MIN MFAN . MAX: (N/ TOT) MBN MEAN

^

MAX . (N/IO T) MIN. MEAN MAX (N/f0T)

PERF. hinn4 SURFACE WATER G ... Scan K-40 48 NoILD I.00E+02 2. lRE+02 2.90E+02 (32/32) 2.10E+02 2.58E+02 2.90E+02 (4/4) 9.30E+01 2.53E+02 3. lOE+02 (16/16)

(pCi!L) Reputed Statum # 24 StRI%G WATER Gamma Scan La-140 48 3.76E+00 <LLD <LLD <11D (0/32) <LLD <LLD <t1D (W4) <LLD <t1D <LLD (0/16)

(gCiq )

StOFACE WATER Gamma Scan Mn-54 48 2.04E+00 <t1D <LLD (LLD (0/32) (LLD <llD . <LLD (0/4) <LLD <LLD <Lt D to/16)

(pCi/L)

SURFACE WA1ER Ganuna Scan Nb-95 48 2.31 E+00 <LLD <LLD <t1D (W32) <LLD <LLD <LLD <LLD <t.LD (0/4) <LLD (0/16)

(PCi/L)

StCFACE WATER Gamma Scan Ra-226 48 4 87E+01 <11D <LLD <LLD (0/32) <LLD < LID <LLD (W4) 5.10E+01 5.10E+01 510E+01 (1/16)

'(pCi/L)

SURFACE WATER Gamma Scan Slwl25 48 5.27E+00 <t1D <LLD <LLD (0/32) < LID <t1D <LLD (0/4) <t1D <LLD <llD (0/16) f PC i/L)

SURFACE WATER Gamma Scan 1h-232 4M R.31E+00 <LLD <LLD <t1D (Of32) <LLD <t1D <LLD ((V4) <LLD <LLD <11D (0/16)

(pCi/L)

SURFACE WATER Gamma Scan U-235 4M 1.29E+0i <t1D <t1D <LLD (0/32) <LLD <LLD <LLD (0/4) <LLD <t1D <t1D (Orl6) 5 (PCi/L)

SURFACE WATER Ganunn Scan Zn-65 48 4.7 t E+00 <11D <LLD <LLD (0/32) (LLD <t1D <LLD <LLD <t1D <LLD (Of4) (0/16)

(ice /l.)

38

7

TAgtAS : g;

, RAB00lDGKALENVWDlWIENTALnenlEITORNEGFROGRAM -

OTNTFR CRFJIK NUCIEAR GEN 1! RATING STAT 10M -

NUCLEAR ,- JANUARY.1986 THROUGN DECEMBER,1996 :

AMMUALIIUMMARY SA95'1E- ANALY35 : . NUCLIDE - #OF IJE INDOCATUR STATMPMS : INGHFST ANNUAL MEAN . BACKGROUNDSTA110N!t .

TYPE ANAL MIN ' MEAN' l MAX- (MffTW) MIN MFAN, MAX (Nff0T) MfM . . MFAN MAX (Nff0T)

Pl!EF, 9entined StA2 FACE W ATER Gamma Scan Zr-95 48 3.5ME+4 K) (LLD <LLD <Lt.D (W32) . <LLD <LLD <t1D (W45 <LLD <LLD (LLD ((V16)

(pCL'L)

WELL W ARR Tntium 12 1.70E+02 <LLD <LLD <LLD (M) (LLD <LLD <LLD (W41 <LLD <Lil) <t1D (W4)

(pCi/L)

% ELL WATER Ganuna Scan Ag-llOrn 12 1.75E+00 <LLD <LLD <LLD (M) <LLD <LLD <LLD CV4) <LLD < t LD <LLD (W4)

(pCi/L)

WEI1 WATER Gamma Scan Ba-140 12 8.75E+00 <LLD <LLD <LLD (M) (LLD <LLD <LLD (W4) <LLD <LLD <LLD (W4)

(PCi/L)

CELLWARR Gamma Scan Be-7 12 1.6RE+01 <11D <LLD <11D (M) <tLD <LLD <LLD (W4) <LLD <LLD (LLD (W4)

(pCi/L)

WELL WATi~R Gamma Scan Co-58 12 2. ORE +00 <LLD <11D (11D (M) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (W4)

(pri/LI WELI WATER Gamma Scan Co-M) 12 2.27E+00 <LLD <11D <LLD (M) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (W4)

(gdVL)

WELL WATER Gamma Scan Cs-134 12 i R9E+00 <11D <LLD <LLD (M) <11D <LLD <LLD (W4) (LLD <LLD <LLD CV4)

(pCi/1J WELL WATER Gamma Scan Cs-137 12 2.03E+3) <LLD <LLD <LLD (M) <LLD <llD <LLD (W4) <LLD <LLD <LLD (W4)

(pCi/L) 39

~ - ~. . . .. -

TABER 3 .

' . RAINOEJDGICAL ENVIEUNIStNTAL MONtTORING FROCRAM b ,

OTNTER CREM NUCIIAR GENERAT1MC STOY10N T JANUARY.1995 THROUGN tt.CDeBER,1995 ~

W CLEAR AMMUAL

SUMMARY

INDICATURSTAT10MS NH; HEST ANNUAL MEAM RACKGROUND STAT 10 Pts -

NAMPRE ANALYNIR MUCIJOE  : # 0F. 11D MEAN MAX .(MfrY)T)' . MIN .MEAN MAX (MrtOD TYPE  : AMAl. MIN : MEAM MAX (Mf1UD ' MIM -

Sestleed PERF.

<LLD (M) <LLD <!1D < LID (W4) <LLD <LLD <LLD (W4)

Wl-LL W ATER Ganuna Scan it-59 12 4.33E+uO <LLD <LLD (pCVL)

<LLD (M) <LLD <llD <LtD (W4) <LLD <LLD <LLD (W4)

WE11 WATER Gamma Scan I-131 12 2.97E+00 <llD <LLD (gtrul.)

<LLD <LLD <LLD <LLD (44) <LLD <LLD < LID (W4)

WT11WATTR Gamma Scan K40 12 2.74E+00 <LLD <LLD (M) trTUL)

<LLD (M) <LLD <llD <llD (W4) <LLD <LLD <LLD (W4)

%T1L WATER Gamma Scan La-140 12 3.58E+00 <LLD <LLD (pCUL)

<LLD <LLD (LLD (LLD (W4) <llD <LLD < LID (W4)

DELL WATER Gamma Scan Mn-54 12 1.99E+00 <LLD <LLD (WR)

(PCt/L)

<LLD (M) (LLD <LLD <LLD (W4) <LLD < LID < LID (fV4)

WELL WATER Gamma Scan Nh95 12 2.33 E+(W) <LLD <t1D (PCUL)

<LLD <LLD <LLD <llD (0/4) <llD <LLD <LLD ((V4)

WELL WATT.R Gamma Scan Ra-226 12 4 67E+01 (LLD <LLD (M)

(ICi/L)

(LLD <11D <LLD (W4) <llD <LLD <LLD (W4)

WELLWATER Ganuna Scan SM25 12 5 00E+00 <llD <LLD <:LLD (M)

(ICUL)

<LLD (0/4) <LLD <tLD < LID (W4)

WELL WATER Gamma Scan 1h-232 12 7.75E+00 <'LD <llD <LLD (M) <LLD <t1D (pCUL) 40

TARES .

RADIOLDGICAL ENVHKMWEENTAL MONITORNOG PROGRAC i OYtT12 CREEK MUCREAR GENE! RATING STA11DN -

NUCLEAR JANUARY,1996 TWROLER DRCEMBER.1996 ANNUAL

SUMMARY

MMPIE ANALYSIS . NUC1JDF. HW LID INDICATUR STAT 1f DNS ' , NH',OHIST ANNUAL Mi(AM - BACKUROUNDSTATIONS 1YPE ANAL. . MIN : , MEAN -MAX ~ (MrTOT) . MIN MEAN - MAX -(Nff0T) MfM- MFAN MAX (NfroT)

PFJtF. Semelem4 W ELL WATLR Gamma Scan U-235 12 1.28E+01 <LLD <LLD <LLD (M) (LLD <L11) <LLD (W4) <LLD <LLD <LLD (W4)

(PC vl)

WELL WATER Gamma Scan Zn45 12 4.25EMW) <LLD <LLD <LLD (WR) <11D <LLD <LLD (W4) <LLD <t1D <LLD (W4)

(pCi/L)

WELL WATER Gamma Scan Zr-95 12 3.58EMX) <LLD <LLD <LLD (M) <LLD (LLD <LLD (W4) <LLD <LLD <LLD (W4)

(pri/L)

CABBAGE Gamma Scan Ag-ll0m 4 7.50EMN) <LLD <LLD <llD - (0/4) <LLD (LLD <LLD (W2) * * *

(*/*)

(pCa r(WED)

CABBAGE Gamme Scan Ba-140 4 3.75E401 <LLD <11D <11D (0/4) <LLD <LLD <LLD (Of2) * * *

(*/*)

(pCdg(WET))

CABBAGE Gamma Scan Be-7 4 8110E+01 1.20E+02 1.20EM)2 1.20E+02 (1/4) 1.20E+02 1.20E+02 1.20EM)2 (1/2) * * *

(*/*)

(pCd g(WET)) Starmw# 35 CABBAGE Gamma Scan C+5R 4 8.50E+00 <Lil) <LLD <LLD (W4) <t1D <LLD <LLD (W2) * * *

(*/*)

(pCAg(WET))

CABBAGE <LLD

• Gamma Scan Co-N) 4 9.75 E+00 (LLD <llD (0/4) <LLD <LLD <LLD (W2) * *

(*/*)

(pCdg(WET))

CABBAGE 4 <LLD <LLD

• Gamma Scan Cs.134 8.25E+00 <t1D <LLD (0/4) <LLD <LLD (Of2) * *

( */* )

y-Tdg(WET))

41

- . _ _ . .- ~ . . - - - . . .

• TARRAS - a RABODEDGICAL ENTIRONMENTAL MONFTOEtING FROGRAM OTSTER CREEK NUCIXAR GENERA 11NG STATEDM NUCLEAR ' '

' JANUARY.19MT11 ROUGH DECEMBER,19M i

~ ANNUALNUMMARY SNDOLATUR STA110NS INGHEST ANNUAL MEAN BACKGIt(R,91D STATMW6 5AMPRE ANALYSIE. NUCL3DE SOF LID ,

MEAN MAXl (MrtUT) MEN MEAN MAX (N/ TOT)' MfM MEAN MAX (MITUT) 1YPE ,

.AAAI.-

MIN :

PERF. Sestkin A ,

(LLD <LLD <LLD (W4) <LLD <ll D <LLD (W2) ( *P )

CABBAGE Gamma Scan Cs-137 4 K.75E+4 K)

(PCaApWT.T))

Gamma Scan R 59 4 1.RRE401 <LLD <LLD <!J D (W4) <RD <LLD <LLD (W2) * (*/*)

CABBAGE spCiAgt%Tm) 1-131 4 1.18E+01 <LLD <LLD <LLD (W4) <LLD <LLD <LLD (N2) * *

(*P)

CABBAGE Gamma Scan frCiArt%TD)

Gamm= Scan K4) 4 NoLLD 2 50E+03 3.25E+03 410E+03 (4/4) 2.80E+03 3.45E+03 410E+03 (2/2) * * *

(*r)

CABBAGE Reputed Statu M 35 (pCiag(WE'I))

Gamme Scan 12-140 4 1. ORE +0! <LLD <tLD < LIE (0/4) <llD <LLD <LLD (0/2) * *

(*P)

CABBAGE (pCiag(WIT))

Gamma Scan Mn-54 4 8.75E+00 <LLD <LLD <LLD (N4) <LLD <LLD <LLD (W2)

(*P)

CABBAGE (gCi/kg(%T.T))

4 9.75E+00 <LLD <LLD <LLD (W4) <LLD <LLD <LLD (0/2) (*/* )

CABBAGE Gamma Scan Nt>-95 (pCAg(WET))

CABRAGE Gamme Scan Ra.226 4 1.7AE+02 <LLD <LLD <LLD (W4) <LLD <LLD <LLD (W2) * * *

(*r) tr ri!krtWET))

Sb-125 4 2.00E+01 <LLD <LLD <ll D (W4) <LLD <LLD <tLD (0r2)

(*F)

CABBAGE Gamma Scan (Fri/kg(WETM 42

- TAatX,3 +

. RADOGEDGICAL WITIBtWWENTAL MUNFTOWNG F910 GRAM .

OYN11!M CME!K NUCsman ogNgl MAT 98G STAT 10N NUCLEAAt l G ' J ANUARY,19MTHROUGN BRCItMDI!tR,1995

~

'E  : ANNUALStm8 MART ANALY3I5 - NUCIJDE .SUF eld INplCA1YDR STATIONS NIGNEST ANNUAL MEAN ' BACKGROUNDSTATM)MS SAMPLE 1TPE . ANAt. MEN - MEAN: !. MAX (Nf1DT) . MIN MEAN -MAX. (N/1Y)T) MIN MEAN- MAX. ('tr!UT)

PERF, enne4 CABBAGE Gamma Scan Ih-232 4 3.75E401 <LLD (LLD <LLD (W4) <LLD (LLD <LLD (W2) ( */* )

QCdg(WET))

CABBAGE Gamma Scan U-235 4 4.75 E+01 <LLD <LLD <LLD (W4) (LLD <LLD <LLD (W2) * * *

(*/*)

4Cag(WLT))

CABBAGE Gamma Scan Zn45 4 2.25E+01 <LLD <LLD <LLD (W4) <LLD <LLD <LLD ('W2)

(*/*)

(pCag(WET))

CABBAGE Gamma Scan Zr-95 4 1.50E+01 <LLD <ll D <LLD (W4) <LLD <LLD <LLD (W2) * *

(*/*)

(pCWg(WED)

Gamma Scan Ag-ll0m 9 1.17E+0i <LLD <LLD <LLD (W5) <LLD <LLD <LLD (W4) <LLD <LLD (LLD (W4)

COLLARD (pCdg(WET)) ,

Gamma Scan B a-140 9 4R9E+0! <LLD <LLD <llD (W5) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (W4)

COLLARD (PCWg(WET))

2.70E+02 2,70E+02 2.70E+02 (1/l) 9.10E+0! 1.IOE+02 1.30E,02 (2/4)

COLLARD Gamma Scan Be-7 9 1.15E+02 2.10E+02 2.37E+02 2.70E+02 (3/5)

QTWg(WET)) Stataw# 66 Gamma Scan Co-58 9 1.33E+01 <LLD <tl.D <1ID (W5) <LLD (LLD <LLD (W4) <LLD <LLD <LLD (W4)

COLLARD (pCAg(WED)

Garnma Scan CMO 9 1.63E+01 <LLD < LID <LLD (W5) <LLD <LLD <LLD (W4) <LLD <LLD (LID (W4)

COLLARD (pCag(WETM 43

- _ . _ ~ .

~q,"  : pj , c, ; ; .r-, .;fABBA3 . 6 . __ , a RADODEDGOLAL ENVnt0MMENTAL MONTNMt3NG FROGRAQ n

N(# CLEAR orma CREnx nucasAm esNumATues sTAn0N iid . JANUAKY,1986 T53000W BBCBSER. 9985 -

, 4

, AIWEUALM8 MART '

. BARS'IE : .. AMALTW . .NUCIJDE [HW; .LLD  : g f!WICAftmSTAT90N5 L,4 . . NIGHRST AMMUAL MEAN t

SACKGROUNDSTADONS TYPE t ANAL; . , MIN; . DEAN - -: MAX * (MrM7T) . DEN: MEAN MAX . IMrfDT) ' MIN 'MEAN MAXL (WTOT)

' FERF. t W

COLLARD Gamma Scan Cs-134 9 1.18E+0i <LLD (LLD <11D <11D (0/5) (LLD (LLD (0/4) <LLD <LLD <llD (W4)

(pCAg(%TT))

COLLARD Gamma Scan Cs-137 9 1.2RE401 <!1D <t1D <LLD <LLD (W5) <LLD <llD (W4) (LLD <LLD- <LLD (0/4)

Iffdg(%TT))

COLLARD Gamma Scan Fe-59 9 3 00E+01 <LLD <LLD <LLD <LLD (0/5) <t1D <LLD (W4) <LLD (LLD <LLD (0/4) yCiAgtWET))

Coll.ARD Gamma Scan I-131 9 1.52E+0I <LLD <LLD <ILD (0/5) <LLD <LLD (LLD (W4) <t1D <LLD <LLD (0/4)

(PCiag(WET))

COLLARD Gamma Scan K-40 9 No LLD 2.60E+03 4.06E+03 4.70E+03 (5/5) 4.70E+03 4.70E+03 4.70E+03 (I/1) 1.90E+03 4.15E+03 5.30E+03 (4/4)

@CAg(WET)) Reputed Station-# 66 COLLARD Gamma Scan La.140 9 I.77E+01 <1LD <LLD <LLD (0/5) <11D <tLD <lJD (W4) <LLD <LLD (LLD (0/4)

(gCiAgt%TT))

COLLARD Ganwna Scan Mn-54 9 1.34E+01 (llD < LID <LLD (IV5) (LLD <llD <LLD (0/4) <llD <LLD (11D (fv4)

(pCiAg(WET))

COLLARD Gamme Scan W 95 9 1.43E+0! <llD <LLD <LLD <11D <t1D <LLD (0/5) (0/4) <LLD <LLD <11D (0/4)

(pCi/kpWET))

COLLARD Gamma Scan Ra-226 9 2.33E+02 <LLD <LLD < LID <LLD <LLD <LLD (0/5) (W4) < LID <LLD <LLD (0/4)

(pCiApWET))

4-$

TAME 3 -

RADODEDGICAL ENVIR0lGENTAL MOMff0RENG PROGRAC1 OYNTY3t CREEK NUCIAAR GENF2ATING STATION NUCLEAR JANUARY,1996 TWROUGH DECDfRER,1996 ANNUAL

SUMMARY

NIGftRNT ANNUAL MEAN BACKGROLTND STA110NS SAlW11 ANALYSEE .- NUCLIDF, - # OF .-

IJR - INDICATUR STATM7NS -

MEAN MAX- (N/fUT) ' MIN MFAN MAX' (MftY)T)' MIN MEAN MAX (NTIOT)

TYPE ANAL' _ MfM :

Somelam-4 PERF.

<LLD <LLD <LLD <LLD <LLD (W4) <LLD <t.LD <LLD (W4)

COLLARD Gamma Scan Sh-125 9 2.78E44)I < LL.D ((W5)

(pCAg(WET))

<LLD <LLD <LLD <LLD <LLD (0/4) <LLD <LLD <LLD (W4)

COLLARD Gamma Scan Th-232 9 5.33E+0L <LLD (W5)

(pCiAg(WET))

<LLD <LLD <LLD (Of5) <LLD (LLD <LLD (W4) <LLD <f1D <LLD (W4 COLLARD Ganana Scan U-235 9 6.22E+01 (FWg(WET))

<LLD (LLD (0/5) <LLD (LLD <LLD (W4) <llD <t1D <LLD (W4)

COLLARD Gamma Scan Zn-65 9 3.44E+01 <LLD (pCAg(WET))

<LLD <LLD <LLD (0/5) <LLD <LLD <LLD (0/4) <LLD (LLD <LLD (W4)

COLLARD Gamma Scan Zr 95 9 2.18E+0i (pCAgtWET))

<LLD (LLD <LLD (Of6) (LLD <LLD <LLD (0/3) (LLD <LLD <LLD (W2)

BLt!E CR AB Gamma Scan Ag-llOrn 8 1.43E+01 (pCi/kgt WET))

<LLD <11D <LLD (OM) <LLD <LLD <LLD (Of3) ellD <LLD (LLD ((V2)

BI ITE CR AB Gamma Scan Ba-140 8 LOSEM2 ,

(pCiAg(WET))

s

<LLD (LLD <LLD (LLD <LLD (W3) <LLD <LLD <LLD (0/2)

BLUE CRAB Gamma Scan Be-7 8 1.41E+02 <LLD (OM)

(pCA g(WET))

<LLD (11D (LLD <LLD (Wil <LLD <LLD <LLD (Gr2p BLUE CRAB Gamma Scan CmSR R I.59E+01 <LLD <LLD (Of6)

(pCAgtWETM 45

y , ,--x -  % _ ~ - -

TAatE 3 RABIGEDGICAL ENVtWDfmRNTAL MONt1DRIf8G PROGRAli OTitTFJt CREllK NUCEEAR GENERATING STAT 10'E '

NUCLEAR = JANUARY.199611tEKWGM DECEnesEst.190s .

ANfUtlAl,fttmtMARY 5ABWlE ANALYWEE NUClJDE 8OF LID IMDOCATOR STA110M5 NIGOIE15T ANNUAL MFAN RACKGROUND STAT 90NN TYPE ANAL ' ~ MIN MEAN , MAX (NffUT) MIN -MEAN MAX (MffDT) . MfM MEAN MAX (MflVT)

PF.RF. 9tathed BLUE CRAB Gamma Scan OW) R 1.98E+0! (11D <LLD <LLD (OM) <LLD <LLD <LLD (0/3) <LLD (LLD (LLD (Of2)

(gGtg(WET))

BLtT CR AB Gamma Scan Cs-134 8 1.43E+01 <LLD <LLD <LLD (OM) < LID <LLD <11D (0/3) <tLD (LID < LIE (0/2)

(rCdgtWET))

CLtTCRAB Gamma Scan Cs-137 8 1.56E+01 <LLD sLLD <LLD (OM) <11D <llD < LIE (Of1) (LLD <llD <LLD (Of2)

(rcd g(WET))

ELUE CRAB Gamma Scan IV-59 8 4.38E+01 <llD (LLD <tLD (M) <LLD <tLD <LLD (0/3) (LLD <LLD <t1D (0/2) I (pCdg(%TT))

BLUE CRAB Gamme Scan 1-131 R 5 63E+01 <llD <LLD <llD (0M) <LLD <LLD <LLD (Of3) <Li.D <LLD <LLD (W2) frCag(WEDF BLUE CRAB Gamma Scan K-$1 R No LLD 1.70E+03 2'5E+03 2e0E+03 (6M) 2.00E+03 2.27E+03 2.reE+03 (3/3) 2.40E+03 2.45E+03 2.50E+01 (2/2)

(rCdg(WET)) Repited Staram-# 93 BLUE CRAB Gamma Scan La-140 R 3.93E+01 (LLD <t1D (LLD (OM) <llD (LLD <LLD (Of3) <t1D (LLD <LLD (0/2) trCag(WET))

BLUE CRAB Gamma Scan mms 4 N 1.f0E+01 (LLD <llD (LID (M) <LLD < LIE <LLD (0/3) <tLD <LLD <tLD (Of2)

(gCdg(WET))

BLUE CRAB Ganana Scan NN95 R 2.04E+01 <llD <llD <LLD (M) <11D <LLD <llD (Of3) <11D <LLD <LLD (0/2)

(gCdgt%TTH 46

TAet23 :

RAWODEDGICAL ENVlWDNMENTAL MONTWOOtBMG PROGRAR UTTTER CWHK NUCl2AR GEMMATWIG STATION NUCLEAR J ANUARY.1996 THROUGW DECEDOBER.1995 AMMUAI,14UMMARY ANALYSIB MUCLHW, #UF ' INDUCATUR STA1WWES HIGHEST AMMUAL MEAN BACKGWtRrND STATWWIS SADel.E Lib .

AMAI. ' MfM MEAN  : MAX 04tTOT) MfN MEAN MAX (N/10T) MIN MEAM MAX P4tTOT)

TYPE PFJtr.- 9tmelem-#

Ra-226 8 2.96E+02 <LLD <LLD <LLD (0%) <LLD < LID <LLD UV1) (LLD <LLD (LLD HV2)

BLUE CRAB Gamma Scan (rCag(WLT))

8 4.00E+01 <LLD <1lE <LLD (M) <tLD <LLD (LLD (Orl) <I1D <LLD <LLD (W2)

ELUE CRAB Gamma Scan Sh-125 (pCap WET))

8 8.33E+01 9.80E+01 9 ROE +01 9 mE+01 (1m) 9.80E+01 9 ME+Cl 9 80E4Cl (1/3) 3.90E+01 3.90E+Cl 3.4DE +01 (1/2)

BLUE CRAB Gamma Scan Th-232 Statum # 93 (pCdpWET))

7.25E+01 <LLD <LLD <LLD (GM) (LLD <LLD <LLD (Gr3) <LLD <LLD <LLD (0/2)

ELUE CRAB Gamma Scan U-235 R 5

(pCWgtWET))

Gamma Scan Zn45 8 4 IIE+01 <11D < LIE <LLD (GM) <llD <LLD <LLD (Of3) < LIE <LLD <LLD (0/2)

BLUE CRAD IgGig(%TT))

BLUE CR AB Gamma Scan Zr 95 8 3.05E+01 (LLD <LLD <LLD (QM) <t1D <LLD (LLD (Of3) (Li.D <llD (LLD (0/2)

(pCd tt%TT))

BLUEFISil Gamma Scan Ag-II0m 3 1.00E+01 <LLD <LLD <llD (Of3) <llD <11D (LLD (Of3)

(*F)

(gCng(Wi T))

BLUEFISit Gamme Scan Ba-140 3 I E E402 <LLD <LLD < LIE (Of3) <LLD <llD <LLD (Of3) (*/*)

(gCAgtWi T))

L 9.30E+01 (LLD <LLD <LLD (Ort) <11D <LLD . <I1D (Orl) *

(*P)

BLUlllSet Gamma Scan Be-7 3 frCAg(WETn 47

c ?AttE 3 RADODEAGICAL ENVIEIOMBENTAL MONMUESf4G PItOGRADE OY9TER CREEK MUCIAAR GP9ERATINC STA110M . , .,; ' '

NUCLEAR 349gUARY.1996TWROUGH DECEMBER,1996 -

. ANNUAllRmttd 8OF RAD . IKiTUR STATION 5 - MIGHEINT ANNUAL MEAN : BACKGENRTMD STATMWtS c SAMPIE . - ANALYSEE NUC1JDE TYPE ANAI. I MIN ' MFAN iMAX: (N/TTN) MIN - MEAN MAX; (MfrOT) . MIM MEAN MAX (Nff0T)

PERF, %etne>4 Gamma Scan Co-58 3 130E+01 (11D <LLD <LLD (0/3) <lLD <11D <LLD (W3)

(*P)

ELUEFiSH (gGAg(WTih 1.33E+01 <LLD <LLD <LLD (0/3) <tLD <LLD <t1D (0/3) * (*F )

Bl_UEFISH Gamma Scan Co-Ni 3

(;Cdg(WET))

Cs.134 3 9.67E+00 <LLD (LLD <LLD (0/3) <LLD <LLD <LLD (0/3) (*/* )

BLUEF15H Gamma Scan (gGA g(%Y1'))

• *

• ci ,

Gamma Scan Cs-137 3 130E+01 1.20E+01 1.20E+01 1.20E+01 (1/3) 1.20E+0i 1.20E+01 1.20E+01 (1/3)

ELUEFISH Statund 93 (pCAg(WTT))

Gamma Scan Fe-59 3 3 33E+01 <LLD <LLD (LLD (Of3) <LLD <LLD <LLD (0/3) *

(*F)

BLUEFISH (PCWgtWET))

Gamma Scan 1-131 3 8.23E+01 <11D <t1D <llD (Of3) (LLD <LLD <t1D (0/3) * * *

(*r)

ELUEFISH (Fag (WET)) ,

No11D 3.80E+03 413E+03 4.70E+03 (3/3) 3. ROE +03 4.13E+03 4.70E+03 (3/3) * * (*/*)

BLUEFISH Gamme Sca,n K40 3 Repiuted Statum # 93 (pCdg(%TT'))

La-140 3 3.93E+0i <LLD <llD <LLD (9/3) <LLD <LLD <LLD (0/3) * (*P)

BLUEFISH Gamma Scan (rCag(%ET))

1.10E+01 <t1D <LLD <t1D (Or3) <LLD <LLD <LLD (Of3)

(*/*)

BLUEF1SH Gamma Scan Mn-54 3 4CAg(WED) 48

- ,  : , TAMA S .

RAB00tDMCAL EMYWEGMBENTAL MONFmIENG PROGRAM OTW11R CREEK NUCIEAR GNTING STATION - i NUCLEAN <

. J ANUARY.1996 THROUGH IECEMBER.1995 ANNUAL

SUMMARY

BAMPIE . ANALYSIS . NUC1JDE . S OF; llE . INDICATUR STA110'f% ,

NIGWR5T ANNUAL MEAN u - BACKGROL9805TATMWe5 TYPE ~ AMAI. MIN - MEAN MAX '(N/fDT) MfM 'MEAN MAX (N/mT) ' MIN MAX

_MEAM (VIUT)

PERF, - 9amehm-8 ELUEFISif Gamma Scan F495 3 1.53E+01 (LLD <LLD <LLD (0/3) <LLD <LLD <1JE (0/3) * * *

(*/* )

(gCd g(WET))

ELUIJ1Sil Gamma Scan Ra-226 3 1.90E+02 2.30E+02 2.30E+02 2.30E+02 O/3) 2.30E+(.2 2,30E+02 2.30E+02 (1/3) * * *

( */* )

(g(Mgt WE"Il) Starmw# 93 ELUEn5ft Gamma Scan SM 25 3 2.33E+0! <LLD <LLD <LLD (0/3) <LLD <11D <LLD (0/3) * * *

(*/*)

(pCWg(WETM BLUEFISif Gamma Scan Th-232 3 4.33E+01 <LLD < LIE <LLD (Of3) <tLD (LLD <LLD (0/3) * * *

(*/*)

(pCng(WET))

ELUEFISil Comma Scan U-235 3 5 00E+01 <LLD <LLD (LLD (0/3) <11D < LIE <LLD (0/3) * * *

(*/*)

(pCW g(WET))

ELUEF1511 Gamma Scan Zn45 3 3.00E+0! <LLD <11D <LLD (0/3) <LLD <LLD <LLD (Of3) * * *

(*/*)

(pCWg(WET))

hLUI:nSil Gamma Scan Zr-95 3 2.23E+01 <LLD <LLD <llD (0/3) <LLD < LID (LLD (0/3) * * *

(*/*)

(gCAg(WET))

CLAMS Gamma Scan Ag-Il0m 20 1.03E+01 <LLD <llD <11D (0/12) < LID <LLD (LLD (0/4) <1lD <t1D <11D (M)

(pCWg(WET))

CLAMS Gamma Scan Ba-140 20 5.70E+01 <1lD <LLD <11D (0f12) <11D <LLD <LLD (0/4) <11D < LID <LLD (M) frCWg(WET))

49

TAttA 3 3 ,

RAasORDGICAL ENVIEDNMENTAL MONtTUEWfeG FROGRAM .

OYSTER CM MUCIRAR MMEIRATWNI STATION NUCLEAR . JANUARY,1986TERotMNIDRCEMBE!'R f996 1:

AMapt",*UMMAmy SAMPLE ANALYSTS NL N # OF- LIE . IMDOCATUR STA11DN5  : NNNIENT AMMlJAL MEAM BACRGROUND 5 TAT 10NN 1YFE AMAI.  : MIN - MEAM MAX' (Mff0T) DEN MFAN MAX MIM .

~ (N/ TOT) MEAM MAX (MITOO PERF. Stashm-#

CLAMS mnuna Scan Be-7 20 9.75E+01 <LLD (LLD <LLD (Wl2) <LLD (LLD (LLD OV4 D <LLD <LLD <LLD (M) 4Cdg(WET))

CLAMS Gamma Scan Cn-58 20 1.22E+01 <LLD < Lib <11D (W12) <LLD < LID <llD (W4) <LLD <LLD <LLD (M) -

QCdg(WET))

CIAMS Gamma Scan Co-e0 20 1.52E+01 (LLD <LLD <LLD (W12) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (M)

(pCdg(WET))

CLAMS Gamma Scan Cs-134 20 1.10E+01 <LLD (LID <LLD (W12) <LLD <LLD <LLD (W4) <llD < LID <t1D (Mt (gCAg(WET))

CIAMS Gamma Scan Cs-137 20 1.19E+0! <LLD <11D <11D (W12) <LLD <11D <LLD (W4) <llD <LLD <LLD (M)

(pCAg(WET))

CLAMS Gamma Scan IV-59 20 2.f4E+01 <LLD <LLD <LLD (W12) <LLD < LID <LLD (W4) <11D <LLD <LLD (M)

(pCWgtWET))

CLAMS Gamma Scan I-131 20 2,01 E+01 (11D < LID <llD (W12) <11D (LLD <LLD <11D <LLD (W4) <llD (M)

(pCWg(WET)) '

CIAMS Gamma Scan K-40 20 No11D 8. ROE +02 1.2tE+03 IE)E+03 (12/12) 1.30E+03 1.33E+03 1.40E+01 1.10E+03 1.34E+03 1.m F+01 (4/4) (Mt)

(pCWr(WET)) Repiuted Statam s 24 CIAMS Gamma Scan 12-140 20 2.32E+0! <LLD <11D <11D (W12) <LLD <11D <LLD (W4) <LLD <LLD <LLD (M) qCMg(WET))

50

4 TAstK3 - 5 RADODEJDGICAL ENVIWtMWWENTAL MIIMITORING FROGRAM .

'~~~

OY5m CREER NUCREAR GENERATING STA110N NUCLEAN ' JANtJARY 1946THWOUGM DEC1!MBER.1996 AMMUAL

SUMMARY

~

NTUR STATTDPM NNiMEST ANNUAL MFAN ' BACKGROUND 5TATM)MS 5AMPl1 ANALYSI!E NUCIJDK SOF. LLD MAX (MftDT) MfN MEAN MAX (N/IT)T) MIN MFAN MAX (N/RTT)

TYPE ANAI. . - MIM . 'MEAM.

PFRF.

' Sentina-#

<LLD (WI2) (LLD <LLD <LLD (W4) <LLD <LLD <LLD (M)

CLAMS Gamma Scan Mn-54 20 1.24E+01 (LLD <ll.D QCWg(WET))

<LLD <LLD (W12) <LLD <t1D <LLD (0/4) <LLD <LLD <LLD (M)

CIAMS Gamma Scan Nb-95 20 l3RE+01 <LLD (pCAg(WET))

<LLD <LLD (W12) <LLD <LLD <LLD (W4) <LLD <LLD <LLD (M)

CLAMS Gamma Scan Ra-226 20 2.4I E+02 <LLD QCAg(WET))

<LLD <LLD (Orl2) <LLD <LLD <t1D (W4) <LLD <LLD <LLD (M)

CLAMS Gamma Scan $15125 20 2.89E+01 <LLD QCag(WET)) .

<LLD (LLD <LLD (0/12) <LLD <LLD <t1D (W4) <tLD <LLD <LLD (Mt CLAMS Gamma Scan "Ih-232 20 4.85E+01 (ICag(%Ti'))

<LLD <LLD (0/12) <LLD <t1D <t1D (W4) (LLD <LLD <LLD (M)

CLAMS Gamma Scan U-235 20 615E+01 (LLD (pCWg(WET))

i

< LID < LID <LLD <11D <LLD (Ord) <LLD <LLD <LLD (M)

CIAMS Gamma Scan Zn-65 20 2.81E+01 <L1D (0/12)

(pCa rtWET))

<LLD ' <t1D (LLD (0/12) <LLD <LLD <LLD (0/4) <LLD <LLD <t1D (M)

CLAMS Gamma Scan Zr-95 20 2.09E+01 L (pCWF(WET))

<LLD <11D ' <llD (0/4) <11D <LLD <LLD (Of3) <LLD <LLD <LLD (0/I)

STRIPED BASS Gamma Scan Ag-110m 5 1.70E+01 vpCdgt WITil 51

_-_______=_________-_ . _ _ _ _ .- _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ - _ _ . _ _ _ . ____ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ ._. _ _ _ _ _ _ _ _ _ _

i ,  :: >

TARIA 3 ty ,

RADIGISUICALENVIROMBENTALMONff0ERNGFROGRAM s

\. UTSTER NNUCIEAR GENERATW9G STA110M NUCLEAN P .

f JANUARY,NB5TWROUGW DECEMBER,1986 U ggggggg,may ' c; 1 ,

IMIOCAftR $tA1 MIME  : WIGHEST ANNUAL MEAN BACMGROUND STA110N5

- NAMP1E. . ANALYSUB. NtCJRE S OF . IJE ANAL' MIN 'MEAN-

' MAX! (N/TUULLMIN; MEAN MAX :(Nff0T) MIN MEAN MAX (NrtDT)

TYPE; '

PERF. E 9eseismJ 2.14E+02 <LLD (LLD (LLD (W4) <LLD <LLD <tLD- (0/3) (LLD (LLD (LLD (WI)

STRIPED BASS Gamma Scan BaI40 5 (pCWg(%T'T))

(LLD <LLD <LLD 10/4) (LLD <LLD <tLD (0/1) (LLD <LLD <LLD (WI)

STRIPED B ASS Gamma Scan Be-7 5 1.60E+02 (Fag (%TT))

<LLD <LLD <LLD (0/4) <LLD <tLD <LLD (Of3) (LLD <LLD <LLD (0/I)

STRIPED BASS Gamma Scan Co-58 5 2D4E+01 (gtriQg(WET))

<LLD <LLD (0/4) <LLD <LLD <LLD (0/3) <LLD <LLD <LLD (Orl)

STRIPED BASS Gamme Scan Co4) 5 1.RRE+01 <LLD (gCag(WET))

<LLD <LLD <LLD (0/4) <LLD <LLD <LLD (W3) <LLD <LLD <LLD (WI)

STRIPED B ASS Gamma Scan Cs-134 5 1.6AE+01 (pCWg(WET))

<LLD <LLD (0/4) <LLD <LLD <LLD (0/3) <LLD <LLD <LLD (Ort)

STRIPED BASS Gamme Scan Cs-137 5 2.45E+01 <LLD (pCWr(WET))

<LLD <LLD (0/4) <LLD <LLD <!.1D (0/3) <LLD <LLD <LLD (Off)

STRIPED BASS Gamma Scan Fe-59 5 6.00E+01 <LLD (gCWg(WET))

<LLD <LLD <LLD <LLD <LLD (0/3) <LLD <LLD <LLD (0/11 STRIPED BASS Gamma Scan 1-131 5 1.44E+02 (LLD (0/4)

(ICWg(%TT))

NollD 2.90E+03 3.75E+03 4.40E+03 (4/4) 3.60E+03 4 03E+03 4.40E+03 (3/3) 4.00E+03 4.00E+03 4.00E+03 (1/1)

STRIPED BASS Gamen Scan K4) 5 Repwred Staivn # 93 (gCWr(WET))

52

TAWl2 3 ,

RASEGIDGOCAL ENTIMONMENTAL MONFfDRM9G PROGRAM '-

h NUCLEAR UT!INR CMIK NUCIEAR GENMATW9G STATION

JANUARY.1995TIIRGIMM DRCEMWER,1996 AMMUAL

SUMMARY

ANALYtB MUCIJIE # OF- IJD NTTR STA110N5 MIGNENT AMMUAL MEAN BACKGROUPEDSTAM SAMPt1

ANAL.  : MIN - -MEAN. -MAX (4f1DT) : MIN MEAM MAX IMftOT) MIM MEAM MAX (WIUT)

TYPE PFRF. 9asetnod Gamma Scan 12-140 5 9.00E+01 <LLD <LLD <LLD (W4) <LLD <LLD <tLD (W3) <tLD <LLD (LLD (WI)

STRIPED B ASS (pCag(WET))

Mn-54 5 1.86E+01 <tLD < LID <LLD (W4) <LLD <LLD <LLD (Wh <LLD <LLD <LLD (WI)

STRIPED BASS Gamma Scan

<r ca twET))

r Gamma Scan Nh-95 5 2.64E+01 (LLD <LLD <LLD (W4) <LLD <LLD <LLD (W3) <llD <LLD <LLD (WI)

STRIPED B ASS (pCAg(WET))

Gamma Scan Ra-226 5 3.46E+02 <LLD <LLD <LLD - (W4) <LLD <LLD <LLD (W3) <LLD <LLD <LLD (WI)

S1RIPED BASS (gCWg(WET))

Gamme Scan Sb-125 5 4.12E+01 <LLD < LID <LLD (W4) <LLD <llD <LLD (W3) <LLD <LLD <LLD ((VI)

STRIPED BASS (pCWg(WET))

STRIPED B ASS Gamma Scan 'th-232 5 7.40E+01 <LLD <LLD <LLD (W4) (LLD <LLD <LLD (W3) <LLD (LLD <LLD (fe t) tgC Ag(WET))

STRIPED RASS - Gamma Scan U-235 5 8.00E+01 <LLD <LLD <llD (W4) <LLD <LLD <LLD (0/3) <LLD (LLD <11D (WI)

(pCWg(WET))

Zn45 5 4 9RE+01 <LLD <LLD <11D (W4) <t1D < LID (LLD (W3) <LLD <LLD <tLD (WI)

STRIPED R ASS Gamma scan 4Cdg(WED) 53

.. - . -- . .. - - .- . . .__ _ ~ .

TAME 3

. RADIOEDGICAL ENVPJIDNBENTAL MONffDRING 190 GRAM OYM11R CREEK NUCLEAR gel 45tATWOG STA110N NUCLEAR JANUARY.1986 THROUG11 DOK1BEWER.1996 AMMUALltUMMARY 5AMPIE ANALYSIS MUtiJDK #OF- IJD IMDOCA1UR STATIONS - HMMIMT ANNUAL MEAN BAChGROL91D STATM)MS TYPE : ANAL. MIN - _ MEAM MAX ~ (N/ TOT) _ l MEN MEAM MAX (M/IT)T) MtM MEAM MAX . (M/ TUT 1 PERF, %stine-#

STRIPED RASS Gamma stan Zr-95 5 3 6kE+0i <11D (LLD (LLD ((V4) (LLD (LLD <LLD (GO) <llD <LLD <LLD (Orl)

(gCag(WET))

SUMMER  ;

FLOUNDER Gamma Scan Ag-I I0m 2 1.R5E+01 * * *

(*/*) * * *

(*F) <LLD <LLD <LLD (0i7) frCag(WET))

SUMMER FLOUNDER Gamme Scan Be.140 2 9.50E+01 * * *

(*F) * * *

(*/*) <LLD < Lib <LLD ((O (pCa r(%TT))

SUMMER FLotrNDER Gamma Scan Be-7 2 1.fi)E+02 * * *

(*/*) * * *

('/*) <LLD <LLD <LLD (Of2) l (pCWg(MTD)

SUMMER FLOUNba Gamma Scan Co-5R 2 1.85E+01 * * *

(*/*) * * *

(*/* ) <LLD (f LD <LLD ((V2)

(gCWg(W ET))

SUMMER FLOUNDER Gamme Scan Co-N) 2 2.85E+01 * * *

(*!*) * * *

(*F) (LLD <LLD <LLD (0/2)

(pCdgNET))  ;

SUMMER FLOUNDER Gamme Scan Os .

• 2 1.85E+01 * * *

(*/*) * * *

(*/*) <LLD <LLD <LLD (Or2)

(pCag(%TT))

SUMMER I

FLOUNDER Gamma Scan Cs-137 2 2.45 E+01 * * *

(*F) * * *

(*/*) <LLD <LLD <LLD (Of2)

(pCa r(WET))

F 54

. TAMR S ,

RAIIOGEDGtCALNALN FROGRA"O [

GN NUCLEAN ofiirnic-noci,A.-Ti G.TAiion JANUARY.1986 TWB00GN DRCEMBER.1996

. AMMUALittmfMARY

- SAMPli ANALM MLM'IJDE # 0F. IJD IMWOLAffR STAliO8M NIGOp3T ANNUAL MEAN BACKGROUND 5TATM M 1TPE AMAL. MIN MEAM ! MAX (MrttW) MIN MFAM MAX (MffDT) MIM MFAN MAX .(M/ TOT)

FWEF. ' W SUMMER FLOUNDER Gamma Scan Fe-59 2 6.00E+01 * * *

(*/*) * * *

(*/*) (LLD dLD <LtD (Of2)

(JCng(M)

SUMMER ROUNDER Gamma Scan I-131 2 3 00E+01 * * *

(*/*) * * *

(*/*) <11D (LLD <LLD (0/2)

(gCag(WET))

SUMMER

• *

• 3.70E+03 4.15E+03 4 60E+03 (2/2)

ROUNDER Gamma Scan K40 2 No LLD * * *

(*/*) (*/*)

(gCag1 WET)) Reputed SUMMER FLOUNDER Ganwne Scan 12-140 2 4 00E+0i * * *

(*/*) * * *

(*P) <LLD <LLD <!.1D (Of2)

(gd'Ag(WET))

t SUMMER Mn-54 2 2.35E+01 * '* *

(*/*) * * *

(*F) <LLD <LLD <LLD (0/2)

ROUNDER Gamma Scan .

(rrag(WET))

SUMMER ,

FLOUNDER Gamma Scan Nh 95 2 2.50E+01 * * *

(*/*) * * *

(*/*) (LLD <LLD cLLD (Of2)

(gCWg(WTT))

SUMMER ,

FLOUNDER Gamma Scan Ra-226 2 3.50E+02 * * *

(*/*) * * *

(*F) <LtD <t1D <LLD (0/2)

(ICdst%TD)

SUMMER Fl.OUNDER Gamma Scan Sh-125 2 4.50E+01 * * *

(*/*) * * *

(*/*) <LLD <t1D <LLD (af2)

(gCWg(WIT))

55

TASTE 3 -

RABODIAMMCAL ENYNIGNRENTAL MUNITDOWNG PROGRAM UNTIMt CREEK NUCIAAR GENIstATING STA110M NUCLEAN ,

JANUART.1996 TMER BFCDIRER,1996 -

- ANNUALIIUMMAR1i SAMPtE,_ ANALY1 BIS NUCLIDE # (W . IJD INDICA 1DR STAT 90b($ - NIGNENT ANNUAL MEAN BACKGROUND STATIONS 1TPE- ANA1. h@fM  :

.MEAN' .MAXt (N/ TUT) - MIN MEAN MAX (MITOT). MIN MEAN MAX (M/ TOT)

PERF. ' Somekm-#

SUMMER FLOUNDEP, Gamma Scan D-232 2 9.00E+01 * * *

(*F) * * *

(*/*) <LLD (LLD <LLD (tV2)

(pCa rtWET))

SUMMER IT_OUNDER Gamma Scan U-235 2 9mE+01 * * * , (*F) * * *

(*/*) <LLD <LLD <LLD ((V2)

(pCag(WETH SUMMER FLOUNDER Gamma Scan Zn45 2 6 00E+0i * * *

(*/*) * * *

(*F) (LLD cLLD <LLD (W2)

(pCdgt WI'T))

SUMMFR FLOUNDER Gamma Scan Zr-95 2 3.50E+01 * * *

(*/*) * * *

(*F) <LLD <11D <LLD ((V2)

(gCdg(WET))

TAtTTDG Gamma Scan Ag-IIOm I 1. foe +01 <LLD <LLD <LLD (Ofl) <LLD <t1D <LLD '((Yl) *

(*/*)

(pCdgtWET))

TQUTOG Gamma Scan Ba-140 1 5.00E+C2 <11D <LLD <LLD (Off) <LLD <LLD <t1D (0/1) *

(*/*)

(ICiA rt%1'I'))

TAUTOG Gamma Scan Be-7 I 2.00E+02 <11D (LIE (LIE (0/l) <LLD <LLD <LLD (0/1) (*/*)

(gGMgtWET))

TAITIDG Ganens Scan Co-58 1 3.00E+01 <LLD <LLD <11D ((VI) (LLD <LLD <t1D (Ofl) (*/* )

(pCdg(WET))

56 i

I m ---- 1-- - , .. - - - - - - - - _ - - - - , - - _ . _ - - - - - - _ - - - - - - - - . - - - - - - .--. _ _ - - _ - _ _ _ _ _ _ -- _ - _ - - - - _ . - - - - -

,;.TAMA 3 -  : i:

RADOutDG0 CAL ENVENU'UbEDITAL MONrf0MNG FPOGRAM ' 1 UTS17A CREI!K NUCIEAR GRNERATING STA110M NUCLEAR  : JANUARY,1996TWstOUGst tsCI!MBER,1995

! ANNUALIIUMMARY 11D . fMBECATOR STA110NE ' RIGMF3T ANNUAL MEAN BACKGIOUND STAT 10PIS MMPIE. - . ANALM5 . NUCUDE # 0F -

ANAL- MIN - MEAN T MAX (M/ TUT) MfM MEAM MAX (IJIT)T) MIN MEAN MAX (W TO T)

TYPE PERF. 9tnelem4 I 2 mE+01 (LLD <LLD <LLD (0/l) (LLD <LLD <LLD (WI) (*/* )

TAtTIDG Gamma Scan Co-N) 4CiQg(WET))

Gamma Scan Cs-134 1.70E+01 <RD <LLD <t1D (0/1) <LLD <LLD <LLD (0/1)

(*/*)

TAtTTOG 1 (g<'WgtWET))

Cs-137 2.00E+01 <LLD <LLD <LLD (0/1) <LLD <LLD <LLD (WI) (*/* )

TAtTTOG Gamma Scan 1

((TWg(Wi'T))

Gamma Scan Fe-59 7.OnE+01 <llD <LLD <LLD (0/1) <LLD <LLD <LLD (0/1) *

(*/*)

TAtTTOG 1 4CWg(WET))

Gamme Scan 1-131 5.00E+02 <LLD <LLD <LLD (Ort) <LLD <LLD <LLD (Of1)

(*/*)

TALTIDG 1 I (gCWg(WIT))

K 40 No LID 4.70E+03 4.70E+03 4.70E+03 (1/1) 4.70E+03 4.70E+03 4.70E+03 (1/1) (*/* )

TAtTIDG Ga:wne Scan 1 Reputed Stathm4 93 (rCWgtWET))

TAtTTOG Gamma Scan La-140 1 1f0E+02 <LLD <LLD <LLD (Orl) < Lib (LLD <LLD (Orl) (*/*)

(rCWr(WET))

Gamma Scan Mn-54 2.00E+01 <1lD ' <LLD <LLD (Orl) <RD <LLD <LLD (Oro *

(*/*)

TALTIDG 1 QCWg(WFT))  ;

i 57 i

.u

TAGLAS _

RADOntDGICAL IENVNIONbMINTAL MUNITURNOG FROGRA OYtTTEL CREFK NUCUEAR GENERATING STAT 10M NL8 CLEAR . JANUART,1996 TWRGUGH DECEMBElt,1996 ANNUALIIUMMARY

1. NDICATTR STA110NS IBGINET ANNUAL MRAN BACKGROUND STATIONS 5AMPRE ANALYSIS . NUCLIDE #OF LID MEAN- MAX (N/f0T) : MIN - ~MEAN. MAX (MrtOT) MIN MEAN . MAX- (NftOT) 1YPE - ANAL. . MIN ~

PFM. - %eened NN95 3.(W)E+01 (LLD <LLD. <1LD (WI) <LLD <LLD (LLD (WI) * * *

(*r)

TALTTDG Gamma Scan 1 (fag (WET))

Gamma 5can Ra-226 3 00E402 <11D <LLD <tLD (WI) < LID <LLD (LLD (WI) * * *

(*r)

TAtTTOG 1 affAg(WET))

4.0DE+01 <LLD <LLD <LLD (W1) <LLD <LLD <LLD (W1)

• * * (*F)

TAtTroG Gamma Scan Sh125 1 (pCWpWET))

Gamme Scan Th-232 8.00E+01 <LLD <LLD <LLD (WI) <11D <LLD <LLD (WI) * * *

(*r)

TAUTOG 1 (pCAgCET))

Gamma Scan U-235 I I.00E+02 <LLD <LLD (LLD (WI) <ll D <llD (LLD (WI) * * *

(*r)

, TAtTTDG QCWg(WED)~

• * * (*P)

Zn-65 5 00E+01 (LLD <LLD <LLD (WI) <LLD <LI.D <LLD (WI)

TAtTTOG Gamma Scan 1 (pCat(WETh 5.00E+01 <LLD <LLD <LLD (WI) <LLD <LLD <11D (WI) * *

(*P)

TAtTTDG Gamma Scan Zr-95 1 (gCdg(WET))

1.10E+01 <t1D <LLD <LLD (WI) <LLD <llD <LLD (WI) * *

(*Pl WEAKilSH Genuna Scan Ag-110m i (pCWFtWET))

<LLD <LLD <LLD (WI) < LID < TID <LLD (WI) * * (*/*)

WEAKilSil Gamma Scan Ba-140 1 3.nnE+02 apCa pWET))

58

TABIES-RA3500AGICALENTIBONMENTALBenNTtoeINGFROGRAM :

hNNUCLEAR UTIITER CREt1 NUCIEAR GENERATING STA110N J ANUARY,1855 THROLWR DECneWER,1996 .

l' ANNUALIIUMMARY

N9GHEllT ANNUAL MRAM BACKGROUNDSTATIONS ;

SAMPIE - ANALYSIll MUC1JDE 80F llD INDICATOR STATWIN5 iMBC :MEAM iMAX (MITUT) ' MIM ' MEAM MAX (MfiY)T). MIN MFAN MAX (Mff0T)

TYPE. 1

' AMAI.

StaHue #

PERF.

It0E+02 (LLD <LLD <LLD (WI) <LLD <LLD <LLD (0/1) * * (*/*)

WEAKRSH Gansna Scan Be-7 I 4Cdg(WET))

1.#)E+01 <LLD <LLD <LLD . (0/1) <LLD (LLD <LLD (M ) * * *

(*/*)

WEAKRSH Gansna Scan Co-58 1 t pCdgNET))

<LLD <LLD <LLD (0/1) <llD <LLD <LLD (O'l) (*/* )

WEAKRSH Gamma Scan Co N) I 1.30E+01 (rCA g(WET))

Cs-134 I 8 00E+00 <tLD <LLD <11D (M) <LLD <llE <llD (Orl) (*f)

WEAKRSH Gamma Scan QCdgNET))

i Nol.LD 1.70E+01 1.70E+01 1.70E+0i (In) 1.70E+01 1.70E+01 1.70E+01 (1/1)

(*/*)

WEAKRSH Gamma Scan Cs-137 Reprwied Statmuv# 93 (pCAg(WET))

I $00E+0i <LLD <LLD < LIE (M) (LLD <llD <LLD (M) * *

(*/*)

WEAKRSH Gamma Scan Fe-59 (pCdgtWET))

<LLD <LLD <LLD (Orl) <l.1D <llD <LLD (0/1) * * * (*/*)

WEAKRSH Gamma Scan 1-131 1 3.00E+02 4CdgtWET))

4.00E+03 4 00E+03 4 00E+03 (1/1) ( */* )

UEAKRSH Gamma Scan K-40 I NollD 4.00E+03 4.00E+03 4 00E+03 (!!!)

Reprwied Statm# 93 (gCdg(WET))

( */* )

La-140 9.00E+01 <LLD <LLD <LLD (M) <LLD < LID <LLD (M)

WEAKRSH Gamma Scan 1 yCdgtWET))

59

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. - TARA 3 :E RADOORAGICAL NAL MONMORING FROGRAM OTST13t CREEK NUCIAAR GENERATING STATION NUCLEAR f JANUARY.1995 TBROUGH DUICWMBElt,1995 -

ANNUALitUM90 ART EAMf"IE . .ANALYM NUCL5DF 80F. RJD INDICATUR STAT 10N5 IRGIRutT AMNUAL MIMM BACKhm STATTONS TYPE- AMAt. : < MIM ' ;MEAN MAX (WTTN) MIN MEAN MAX (NftT)T) MfM MEAN MAX (MftVIT)

PERF. 9tasino4 WINTER ROUNDER Gamma Scan Ag-110m i 1.N)E+01 <LLD <tLD <LLD (WI) <LLD < LID <LLD (0/1) * *

(*/*)

FWg(WET))

WINTER

<LLD <LLD * *  ?

FLOUNDER Gamma Scan Ba-140 I 2.0[)E+02 <LLD <LLD <LLD (Of1) <LLD (0/1) (*/*)

KWg(WET))

UINTER ROUNDER Gamma Scan Be-7 I 1.80E+02 <LLD <LLD <LLD (Orl) <LLD <LLD <LLD (Ort) * * *

(*r)

Wag (WLT))

CINTER ROUNDER Gamme Scan Co-58 1 2 mE+01 <ll.D < LIE <llD (Orl) <LLD <LLD <LLD (Off) * * *

(*r)

Kag(WET)) ,

WIN 1ER Flot?NDER Gamma Scan Co4iG I 2.00E+ )1 <11D <LLD <LLD (Orl) (LLD (LLD <LLD (Orl) * * *

(*r)

(rCngt%TT))

WINTER FLOUNDER Gamma Scan Cs-134 I 1.90E+01 <LLD <LLD <LLD (Ofi) <LLD <LLD <l.1D (WI) (*/*)

Fag (WED)

WINTER ROUNDER Gamma Scan Cs-137 1 1.W)E+01 <t1D <LLD <LLD (Orl) <LLD <LLD <LLD (Orl) (*/*) ,

Fdg(WET))

61

s TANJC3 "l"IRABEDEDGICALENTIBGlWEENTALMGMfRNINIGFROGRAM .

OTSTER CENRK NUCLEAR MTWIG STATION -

NUCLEAR  ; JANUARY,1996 THROUGII RECDGBER,19W

' ANNUALfttmEMARY

- SAMPIE -  : ANALYST 5- NUCLIDEC . # OF, LLD -- IN99CA1DR STA110N5 , . ' WIGERST ANNUAL MEAN  : BAGGROUND STATIONS TYPE ANA* e - MIN ~ MEAN - ; MAX (Vf0T) MfM MEAN MAX (M7 TDT) MIN MEAN MAX. (NTIUU FERF. 9tmelumJ WINTER FLOUNDER Gamma Scan Fe-59 I 5 00E+01 (LLD <llD <LLD (M) <LLD <LLD <LLD (M) (*/* )

(gCWr(WET))

DIVTER FLOUNDER Gamma Scan I-131 I 1.20E+02 <LLD <LLD <11D (M) <LLD <LLD <LLD (WI) (*/*)

(gGOg(WET))

WINTER FLOUNDER Gamme Scan KJO 1 NollD 3 50E+03 3.50E+03 3.50E+03 (Ill) 330E+03 3.50E+03 3.50E+03 (1/l) (*/*)

(pCWg(WET)) Reputal Stathm4 93 WINTER FLOUNDER Gamma Scan La-140 I 1.10E+02 <LLD <LLD <LLD (M) <LLD <LLD <LLD (M) * * *

(*/* )

trCAg(WET))

WINTER FLOUNDER Gamma Scan Mn-54 1 2 00E+01 <llD <11D <LLD (M) <11D <LLD <LLD (M) (*/*)

(pct /kg(WED) witnER FLOUNDER Gamme Scan NN95 1 3.00E+0i (LLD <LLD <LLD (M) <LLD <L11) <llD (M) (*/*)

(gCvh g(WET))

WINER FLOUNDER Gamma Scan R a-226 1 3 00E+02 <LLD <LLD <LLD (M) <LLD (Lil) (LLD (M) (*/*)

rgCa rtwTT))

62

a. , q; TAMRS3 nt ,

,. n: RAWOGEANNCAL ENWNSENTAL N PROGRAM (MitTER CRMK NUCIEAR N1 WIG STATION , , ,

NUCLEAA :U .j;_ , j JANUARY,1986 THRotM;W DOCEMBER 1995  !$!I i!"

~ , '1j :gygpgggggggggy ANAL M , NUCUDE : 4 OF _ - ! Lib IMMCA1DR STA110NS  ;! NIGHENT ANNUAL DEAN , BACKGROUND STA110N5

, SAkWIE - pi, ,

MAX TYPE-  : ' ANAL :  ? ' MIN l !MEAN: { MAX (N/fDT) : DEN' MEAM MAX .- (MffDT) MtM ;. .MEAN OWTUT1 9tseined FF2F.

WINTER FLOUNDER Gamma Scan Sb-125 1 5 00E+01 <LLD <LLD <LLD (0/1) <LLD <LLD <LLD (Ort) * * *

(*r)

(tCdg6 VET))

WINTER

• FLOUNDER Gamma Scan 1h-232 I R.00E+01 <tLD <LLD <LLD (M) <LLD <LLD <LLD (M) (*F )

(gCagsWET))

WINTER

• FLOUNDER Gamma Scan U-235 1 9.00E+01 <LLD <LLD <LLD ((VI) <LLD <LLD <LLD (fVI) * *

(*/*)

(ifdg(WIm)

WINTER *

• Gamma Scan Zn45 6 00E+01 <LLD <LLD <LLD ((VI) <LLD <LLD <LLD (oft) *

(*/*)

FLOUNDER 1 (rCi4 gtWET))

WINTER *

(*/*)

FLOUNDER Gamma Scan Zr-95 I 400E+01 <LLD <LLD <LLD (Ort) (LLD <LLD <LLD (Orl)

(pCag(WET))

WillTE PERCH Gamma Scan Ag-II0m 1 2.00E+01 <LLD <LLD <LLD (Orl) <tLD <LLD <LLD (0/1) * * *

(*r)

($dgtWET))

WHITE PERCil Gamma Scan Ba-140 I 2.00E+02 (LLD <LLD <LLD (Orl) <LLD <LLD <LLD (Orl) *

(*/*)

(ICag(WET))

63

, 4 ;p TAMK3 ,

- , RA350tDINC45,NALNPROGRAM OYmIR CM NLN GENI!RATW8G STAT 90N -

NUCLEAN JANtJARY. EME TEBOUGM DEICERSElt. NM ,

l ANNE.%LIIUMMARY

' NIGIHutT ANNUALMRAN -  ; RACKGRotiND STATM)M5 SAMPIE ANALYM NUGJUE SOF IJD :u , INDICA 1TR STAT 10NE MIN MEAN MAX (N/ TOT) MIN .MEAN MAX 01/1U11 TYPE ANAI. ' MfN ! - MEAN. : MAX' tWITFT) etar. saaeh e

<LLD <LLD (WI) (LLD <LLD <LLD (0/1) * (*/* )

WilllE PERCH Gamma scan Be-7 1 2.00E+02 <llD i trCW3(%TI'))

<LLD <LLD (0/1) <LLD <LLD <LLD (0/I) (*/* )

WHITE PERCH Gamma Scan Co-SR 1 2 00E+01 <LLD (pCWgtWET))

<LLD <LLD <11D (0/1) <LLD <LLD <LLD (0/1) * * (*P)

WillTE PERGI Gamma Scan Co-N) 3 3 00E+01 (pCWgtWET))

<LLD <LLD (0/1) <LLD < LIE <LLD (0/1) (*/* )

WlHTE PERC11 Gamma Scan Cs-134 1 2.00E401 <LLD (pCWg(WET))

<1lD <LLD (I.LD (0/1) <ll.D < LIE <LLD (0/1) * *

(*/*)

WHITE PEROI Gamma Scan Cs-137 1 2.00E+01 (gCWgtWET)) '

7.00E+01 <LIS < LIE <llD (0/1) <LLD <LLD <LLD (Off) * * (*/*)

WHITE PERCH Gamma Scan Fe-59 I (pCWgt%TT))

<LLD <LLD < LID (0/1) -1LD < LID <1lD (Orl) * *

(*/*)

WillTE PERCH Gamma Scan I-13 I 1 1.40E+02 (Kn g(WET))

3.90E+03 3.90E+03 3.90E+03 (1/1) 3.90E+03 3.90E+03 3 90E+03 (1/1) (*/* )

OHITE PERCH Gamma Scan K-40 1 NollD r Regwned Starnw# 93 (pCWg(WET))

(LLD <llD <LLD (0/1) <LLD <llD <11D (3/1) * * (*/*)

DHTTE PERCl{ Ganune Scan 12-140 I 1.10E+02 (Fa g(WET))

6%

TAetA 3. .

- RADIOEDGSCAL StTERDMhWETAL MONTTURMcG PROGRAM OT1tTER C8EMX NtICLEAR GEDeutATING STAT 90M~

NUCLEAR  : JANtJARY. W THROUGH DECEMEElt,1995 -

- AMMUALIIUMMARY

- NM;OHtST AMMUAL MEAN BAGGROUND STATMN45

- SAMPLE . ANALYSE NUClJDE #OF LLD ENDECATUR STAT 181N5 -

MEAM MAX (MrtUT) MfM MEAM MAX (NrtDT)- - *EIN . MEAM - MAX - (MrfUU TYPE AMAL -  : MIM

• Etnelmed PERf'.

<LLD (WI) <LLD <11D <LLD (WI) * (*/* )

U11HT PER GI Gamma Scan Mn-54 1 2.(W)E+0i <LLD <LLD (pCAg(WET))

4 00E+0! <l)LD <LLD <LLD (M) <LLD <LLD <LLD (W1)

(*r)

WIM PERG1 Ganwne Scan Nh95 1 (gCdrtWET))

5.00E+02 <LLD <LLD (LLD (W1) <LLD <LLD <LLD (W1) * * *

(*r)

OfflTE PERCll Gamma Scan Ra-226 1 (pCA F(WET))

6.00E+01 < LID <LLD <LLD (Of1) <Lt.D <llD <LLD (WI) * * *

(*r)

WIITTE PERCll Gamma Scan Sh-125 1 (pCdg(WET))

Th-232 I 9.00E+01 < LID <11D <LLD (WI) <LLD <l.1D <llD (WI) * * *

(*r)

WlilTE PERCll Gamme Scan (gCAg(WET))

U-235 1.20E+02 <LLD <LLD <LLD (WI) <llD <11D <LLD (WI) * * *

(*r)

WHITE PERCH Gamma scan 1 (pCdg(WED)

Zn45 6.00E+01 <LLD <LLD <LLD (0/1) <LLD <LLD <LLD (aft) * * *

(*r)

W111TE PERCH Gamma Scan 1 (pCAg6 VET))

7s-95 5.00E+01 (LLD <tLD <LLD (WI) <LLD (11D <LLD (WI) * * *

(*r)

WlI11E PERCH Gamma Scan 1 qCWg(WED) 65

. TARE. 3 RAB00tDWICALNAL MONTTOMRG FROGRAM ON CREEK RU man GENERATWOG STA110M '

NUCLEAR i - JANUARY.1996TEBOUGM DBCEMBER.9995 ANNt1ALil10960ARY INDICA 1YIR ftAT90M5 WIGMFJIT ANNUAL MEAM BACKGROUND STATMMIS SAMPLE ANALYW5 .NUCLIDE : # 0F. LLD MEAM : BSAX . (MMOT) : DO MEAM MAX (Mf!T)T) . MIN . MEAM- MAX- (M/70T)

TYPE ' ANAL : MIM -

a; emes.g FERF. _

AQUAT1C <LLD <LLD (WR) 1.33E401 <LLD <LLD <LLD (0/24) <t1D <LLD <LLD (W4) (LID SEDIMENT Gamma Scan Ag-IIOm 32 (pCAg(DRY))

i M)UATIC <LLD <LLD <LLD (WR) 32 R cAE+01 <LLD <LLD <LLD (W24) <LLD <LLD <LLD (W4)

SEDIMENT Gamma Scan Ba.140 (rO/kg(DRY))

AQUATIC I WE+02 2.23E+02 2.uoE+02 (7/R)

Be-7 32 1.26E+02 8.10E+01 2.13E+02 6.00E+02 (9/24) 6.00E+02 6 00E+02 tk00E+02 (1/4)

SEDIMENT Gamma Scan StatmM 24 (PCs/kgtDRY))

AQUAT1C (LLD <t1D (W8) 1.43E+01 <LLD <LLD <11D (0/24) <LLD <LLD <LLD (W4) <LLD SEDIMENT Gamma scan Co-58 32 (pChag(DRY))

AQUAVC <LLD < LIE <LLD CMd) 32 1.60E+01 1.50E+01 7.f0E+01 1. ROE +02 (3/24) 1.50E+01 9.75E+01 IEE+02 (2/4) (Oni) i SI'DIMENT Gamma Scan StamM 33 spr:A g(DRY))

1 AQUATIC <LLD <LLD <LLD (0/8) 32 1.29E+01 <LLD <l.LD <LLD (0/24) (LLD <LLD (LLD (W4)

SrDIMENT Gamma Scan Cs 134 (KMFDRY))

AQUAUC 1.70E+01 2.56E401 3.90F.+01 (R/3) 32 2.10E+01 1.10E+01 6 06E+01 2.*E+02 (14/24) 3.30E+0! 1.10E+02 2.*E +02 (3/4)

SI:DIMENT Gamma Scan Cs-137 StatmM 33 (KMgtDRY))

66

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RANDIAMMCALWlVWONIGNTAE,IWONfTOMMG PROGRAQ OTSTEIR CEEEK NUCIm NTWIG STATWOM NUCLEAR ,

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,, AN1494LIIUIntARY -

sal @tE . ANALY9M ' MUCtJDir, ;#0F 11D .

RMpfCATUR STATTOME MIGlltiltT ANNUAL MEAM 3 BACE6M 57A110M5 TYPE 'AMAl. .  ! MON - ..MEAM  : MAX ' (M/IUT) . MfM MEAM . MAX ' . pertDT) . MEM MEAM' MAX. (M/ TUT 1 PERF. %mehed AQUATIC .

SEDIMENT Gamma Scan Fe-59 32 ' 3.4RE+01 <LLD <LLD <LLD (W24) <t1D <LLD <llD (WS) <llD < LIE <ilD (M)

(pCAgt DRY))

AQUATIC SEDIMENT Gamma Scan 1 131 32 3.77E+01 <LLD <LLD <LLD (W24) <LLD <LLD <LLD (W4) (LLD <LLD <LLD (M)

(pCdrt DRY))

AQUATIC SEDIMFNT Gamme Scan K-40 32 NoLLD 3.60E+02 4.14E+03 1.10E+St (24/24) 5.40E+03 6.50E+03 7.90E+03 (4/4) 5.00E+03 1.18E+34 I.80E+04 (R/8)

(pCiAg(DRY)) r Reputed Statam4 23 AQUATIC SEDIMENT Gamme Scan 12-140 32 '2.98E+01 <LLD <llD <llD (0/24) <LLD <LLD <LLD (W4) <L1D <LLD <LLD (M)

(pCi/kg(DRY))

4

/.QUATIC SEDIMENT Gamma Scan Mn-54 32 1.50E+01 <llD ' < LIE <LLD (W24) <tLD < LIE <LLD '(W4) <llD <t1D <LLD (M)

(gCdg(DR Y))

AQUATIC SEDIMENT Gemma Scan NN95 32 1.98E+01 < LIE <LLD <LLD (W24) <LLD < LIE <LLD (W4) <LLD < LIE <LLD (M)

(gCdg(DRY))

AQUAT1C SEDIMENT Gamma Scan Ra-226 32 'NoLLD 3.90E+02 1.06E+03 2.00E+03 (24/24) 1.20E+03 1.53E+03 2.00E+03 (4/4) 4.70E+02 1.36E+03 2.40E+01 (A/8)

(gCAg(DRY)) ' Reputed Statand 93 67 c, - _ _ _ _ _ _ _ _ _ _ _ - -

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l 20----------------------------------------------------------------------------------------------------------

18 - -----------------------------------------------------------------------~~--------------

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i

i

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)

A companson of dose per affected compass sector demonstrates that the highest dose was not measured

)

in the sector most likely to be affected by effluents from the OCNGS (Fig.10). Using Panasonic TLD .

r b results, the data indicate that the south-southwest sector had the highest dose during 1996. Based upon on-site meteorology for 1996, the highest air dispersion (X/Q) factors were in the east-southeast sector L (Fig. 2) and the highest dose due to OCNGS effluents should have been recorded in that sector. -

1 l However, the highest dose was recorded in the south-southwest sector, which is 90 degrees opposite.

! from the east-southeast sector. In addition, the lowest mean dose of the sixteen sectors surrounding the i t

OCNGS was recorded in the east-southeast sector, which is further evidence that the OCNGS had little

! if any effect on off-site expost:re. -

i i

. These results also indicate good correlation between the dose as recorded by the two independent TLD J

' networks at the ten collocated stations (Figure 10).

! l 1

1

, l

. p 4

k j

l' 3

4 4

73

MEAN TELEDYNE AND PANASONIC TLD GAMMA DOSE FOR 1996 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MEAN DOSE IN AFFECTED COMPASS SECTOR DOSE IN MILLIREM PER STANDARD QUARTER C

NOTE: Teledyne TLD's are not located in all compass sectors 15 - ---------------------------- ------------ --------------------------------------------------------------------

3 '

e s g

o i i

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5- -- -- ---- -- ---- - -- -- ---- ---- -- ---- ---- -- --

i 0 i i i i i i i i i i i i i i i N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW AFFECTED COMPASS SECTOR t

, i

ATMOSPliERIC MONITORING A potential exposure pathway to man is the inhalation and ingestion of airborne radioactn e materials.

Air was sampled by a network of thirteen continuously operating air samplers and then analyzed for radioactivity content.

Indicator air sampling stations are located in prevailing downwind directions, local population areas, and areas of public and special interest. All indicator stations are located within 6.5 miles of the OCNGS.

Background air sampling stations are located greater than 17 miles from the site in Lakewood, Allenburst, Cookstown, and Hanunonton, NJ.

Samnle Collection and Analysis Mechanical air samplers are used to continuously draw a recorded volume of air first through a glass fiber (particulate) filter and then through a charcoal cartridge. A dry gas meter, which is temperature compensated, is used in line with the filters to record the volume of air sampled. Internal vacuums are also measured in order to pressure correct the indicated volume. All air samplers are maintained and calibrated by the OCNGS Instrument and Control Department.

He particulate filters were collected every two weeks and analyzed for gross beta radioactivity. He filters were then combined quarter!y by individual station locations and analyzed for gamma-emitting radionuclides.

Charcoal cartridges, used to collect gaseous radioiodines, contain activated charcoal. Charcoal cartridges were collected weekly and analyzed for iodine-131 (1-131) actisity. ,

Results The results of the atmospheric monitoring during 1996 demonstrated that, as in presious years,' the radioactive airborne effluents associated with the OCNGS did not have any measurable effects on the emironment.

During 1996,349 gross beta analyses were perfomied on air particulate filters (Table 3). Two samples were lost due to air sampler malfunction (Appendix A-3). He background mean gross beta actisity (0.0171 pCi/m') was slightly higher than the indicator mean (0.0143 pCi/m') and all gross beta analysis results were within two standard deviations of the historical mean. A quality control check ofindicator r station results shows that all of the 214 observations were within statistical limits (Fig.11).

75

Comparison of the 1996 bi-weekly mean air particulate gross beta concentrations from indicator and background stations shows that indicator and background concentrations were essentially identical (Fig.12). In all but two of the comparisons, the mean background concentration exceeded the mean indicator concentration. 'These results are consistent with the results of gross beta analyses of air samples from previous years (Fig.13). These air particulate gross beta analysis results indicate that effluent containing gross beta radioactivity from OCNGS operation did not have any measurable impact on the local ensimunent.

Gamma isotopic analyses were perfonned on 52 air particulate filter composites (Table 3). The only radionuclides identified were naturally occurring beryllium-7, potassium-40, and radium-226, which -

were seen in similar concentmtions at both indicator and background stations. Because tlwy are naturally occurring nuclides, their occurrence cannot be attributed to efiluents from the OCNGS.

Air charcoal cartridges (670) were analyzed for iodine-131 (I-131) and no radiciodine was detected in any of the samples (Table 3). Six samples were lost due to air sampler malfunction (Appendix A-3).

76

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AOUATIC MONITORING Brackish water from Bamegat Bay is drawn in through the south branch of Forked River, pumped into the OCNGS cooling systems, and then discharged to Bamegat Bay via Oyster Creek. Fish, clams, and crabs are harvested from the bay on a recreational and, to a limited extent, commercial basis. The ingestion pathway is addressed because of fish, clam, and crab consumption by man.

On occasion, a radioactive liquid release is discharged in accordance with the limits established in the OCNGS Offsite Dose Calculation Manual (ODCM) Specifications, Technical Specifications, and 10CFR20. Highly purified water, containing traces of radioactivity, may be discharged into Oyster Creek which routinely has a minimum flow rate of slightly under one-half million gallons per minute.

1here was one radioactive liquid release, an inadsertent release of 148,600 gallons of water containing approximately 6.14 curies of activity, from the OCNGS during 1996. Samples of surface water, sediment, fish, blue crab, and hard clams were routinely collected from the OCNGS intake and discharge canals, as well as Bamegat Bay, Manahawkin Bay, and Great Bay /Little Egg liarbor in order to monitor any emironmental impact that may be associated with liquid effluents from the OCNGS.

Sample Collection and Analysis Surface water samples from two stations were collected monthly while an additional six stations were sampled on a quarterly basis. Sediment and clam samples were collected quarterly. Grab samples of surface water and saliment were collected from six indicator stations and two background stations.

Grab samples ofclams were collected from three indicator and two background stations. Three indicator stations for surface water and sediment are located in the OCNGS discharge canal - Oyster Creek; no clams are available for collection at these stations. Three additional indicator stations are located in Barnegat Bay in close proximity to the mouth of Oyster Cra:k. One background station is located in Manahawkin Bay, approximately 11 miles south of the OCNGS. A second background station is located approximately 22 miles south of the OCNGS Great Bay /Little Egg Iktrbor.

Blue crab and fish samples were collected quarterly (when amilable) from two indicator stations and one background station. Both indicator stations are located in the OCNGS discharge canal and the background station is located in Great Bay /Little Egg flarbor. Crab pots were used to catch blue crab.

Traps, as well as the hook and line technique, were used to catch fish.

Surface water, sediment, clam, fish, and crab samples were analyzed for gamma-emitting nuclides.

I 80

&su_Its Operation of the OCNGS had no detectable effect upon the local surface water which was sampled 48 times at eight different locations during 1996. Two gamma-emitting nuclides, potassium-40 (K-40) and radium-226 (Ra-226), were detected in 48 and 1 of the samples, respectively (Table 3). Both of these  ;

radionuclides are naturally occurring and commonly found in salt water at or above the obsen'ed concentrations. No other radionuclides were detected in surface water samples.

1 Six gamma-emitting nuclides were detected in the 32 sedanent samp'es collected during 1996 (Table 3). i Four of these radionuclides, beryllium-7 (Be-7), potassium-40, radium-226, and thorium-232 (Th-232), )

are naturally occurring and were detected at both background and indicator stations. Cesium-137 (Cs-137), which is a fission product, was also detected in both background and indicator samples.

Cesium-137 was widely distributed and detected in considerable abundance as a result of fallout following atmospheric weapons tests and the 1986 Chernobyl accident. Cesium-137 was also released in small quantities from the OCNGS in liquid effluents in 1996 (Table 2) as well as in past 3rars. The results of the sedunent sampling program indicate that the presence of cesium-137 in the sediments of the OCNGS discharge canal and nearby portions of Bamegat Bay may be attributable in part to past liquid discharges from the facility, A review of sediment sample analysis results for the previous three years (1994,1995, and 1996) shows cesium-137 was detexted in 83 percent of background and only 63 percent of indicator samples (Table 5). However, cesium-137 concentrations detected at the two indicator stations (Stations 33 a:xi 93), which are closest to the OCNGS liquid discharge point, show concentrations higher than that found at background stations (Figure 14). During the presious three years, the mean concentration of cesium-137 at background stations was 32 pCi/kg4y, while the -

average concentration at indicator Stations 33 and 93 was 101 pCi/kg-dry. In addition, over this three year period, the highest concentration of Cs-137 at an indicator station was 240 pCi/kg-dn, which was detected at Station 33 during March 1996. The highest concentration at background stations during the same period was 67 pCi/kg-dry.

It is important to note that even the highest concentration of Cs-137 observed in sediments (240 pCi/Kg-dry) was only slightly above the Lower Limit of Detection specified by the Nuclear Regtdatory i Conunission (180 pCi/Kg-dry) and only 12 percent of their Reporting inel for Cs-137 in fish and broad  !

leaf vegetation (2,000 pCi/kg-wet).

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Station Station Station Stanon Station Station Station Station Date 23 24 25 31 32 33 93 94 Jan 94 26 22 <LLD 40 54 140 110 67 f

Apr 94 <LLD 21 <LLD 49 45 150 67 48 Jul94 <LLD <LLD <LLD 24 29 160 70 46

, Nov 94 24 37 <LLD 22 44 140 95 61 Mar 95 <LLD <LLD <LLD <LLD 72 46 94 <LLD f

May 95 56 <LLD <LLD <LLD <LLD 130 100 32 Aug 95 <LLD <LLD 9 60 ,

f 13 32 91 15 Oct 95 47 31 <LLD <LLD <LLD 51 120 27 Mar 96 <LLD <LLD -<LLD 37 20 240 110 26 Jun 96 32 21 11 23 <LLD 56 71 22 Aug 96 16 <LLD <LLD 17 <LLD <LLD 100 24 Sep 96 <LLD <LLD 15 39 23 33 100 17 se' dgi, g Y^; deIfNN Ngg;jf[ p;ss$ /- #

Maximum 56 37 15 49 72 240 120 67 Average 34 26 12 29 40 110 94 35

, Minimum 16 21 9 13 20 33 67 15

- Stations 23, 24, 25, 32, 33, & 93 are indicator stations

- Station 31 & 94 are background stations 83:

i Over the years, there has been a dramatic reduction in liquid discharges from the OCNGS and there have been no routine discharges of radioactive liquids since 1989. As a result of this reduction in liquid efiluents, as well as the ongoing natural radioactive decay process, the levels of Cs-137 in sediments continues to decrease (Fig.14).

Cobalt-60 was detected in thirteen percent of the aquatic sediment indicator station samples and none of the background station samples (Table 3). The presence of this radionuclide in Damegat Bay sediments

is ofinterest because it can be attributed to past OCNGS liquid releases (Ref.19). As documented in previous reports, OCNGS-related cobalt-60 activity has been found in sediment or clams from Bamegat Bay since the mid-1970's. He volume ofliquid effluents has been significantly reducal since that time i and this decrease in the rate ofinput of cobalt-60 to the environment, combined with radioactive decay of the existing inventory, has resulted in a gradual decline in the cobalt-60 concentration in sediment and clams (Figs.15 and 16). He last detectable concentration of this radionuclide in clams was found during the third quarter of 1987 (Fig.16).

4 Twenty clam samples were collected from five different locations during 1996. Gamma isotopic analyses indicated that the only gamma-emitting nuclide present was potassium-40, which is naturally occurring and commonly found in salt water (Table 3).

1 Eight blue crab samples were collected from three locations during 1996. A gamma isotopic analysis was performed on each sample and naturally occurring potassium-40 and thorium-232 were the only

, radionuclides identified (Table 3). The close association of this species with Bamegat Bay sediments could make it susceptible to cesium-137 and cobalt-60 uptake. liowever, no detectable Cs-137 or Co-60 activity has been observed in blue crab samples since routine collection began in 1985.

Fourteen fish samples, yielding seven species, were collected from 3 sampling locations during 1996.

The species and number of samples collected are listed in Table 6.

4 84

MEAN COBALT-60 CONCENTRATION IN AQUATIC SEDIMENT - 1984 THROUGH 1996 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS IN PICOCURIES PER KILOGRAM (DRY)

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TABLE 6 SPECIES OF FISil CAUGIIT AS PART OF Tile OCNGS REMP IN 1996 Fish Number of Samples striped bass 5 bluefish 3 summer flounder 2 tautog 1 weakfish I white perch I winter flounder 1 Potassium-40 was detected in all fish samples and radium-226 was detected in one of 14 fish samples collected in 1996 (Table 3). Both of these nuclides are naturally occurring and not attributable to OCNGS operation. Detectable quantities of cesium-137 were observed in one of three bluefish samples and in one weakfish sample collected from indicator station 93 (Table 3).

As discussed above, cesium-137 is a fission product that is attributable to various sources such as -

atmospheric weapons testing, the Chernobyl nuclear accident, and OCNGS effluents. During the past six years, Cs-137 activity was detected in 19 of 162 indicator fish samples and in 0 of 43 background fish samples. These results suggest that cesium-137 released in past OCNGS effluents may be responsible in part for the trace levels of cesium detected in fish samples. These detected levels are very low with the maximum concentration observed in fish (170 pCi/kg-wet - (Table 3))

being only 13 percent above the regulatoiy required Lower Limit of Detection of 150 pCi/kg-wet for aquatic biota (Ref. 2). In addition,170 pCi/kg-wet is only 8.5 percent of the Reporting Level of 2,000 pCi/kg-wet specified by the Nuclear Regulatory Commission (Ref. 2). Similar low levels of this radionuclide are found in fish throughout the world as a result of fallout (Ref.18).

The potential radiation doses associated with the trace amounts of Co-60 and Cs-137 in sediments and Cs-137 in fish are included in the calculation of the doses due to liquid effluents from the OCNGS (Appendix G). These doses are a small fraction of the regulatory limits and significantly less than the doses recieved from other man-made sources and natural background sources of radiation.

87

TERRESTRIAL MONITORING Radionuclides released to the atmosphere may be deposited on soil and vegetation and may be incorporated into milk, vegetables, and other food products. To assess the impact of dose to humans from this ingestion pathway, food product samples such as green leafy vegetables were collected and analyzed during 1996.

The contribution of radionuclides from OCNGS effluents to this ingestion pathway was assessed by comparing the results of food product samples collected in prevalent dowmvind locations, primarily to the southeast of the site, with background samples collected from distant and generally upwind directions.

In addition, a dairy census was conducted to determine the locations of commercial dairy operations and milk producing animals in each of the 16 meteorological sectors out to a distance of l

five miles from the OCNGS. The census showed that there were no commercial dairy operations and no dainj animals producing milk for human consumption within a 5 mile radius of the plant (Appendix F).

Two gardens were maintained near the site boundary of the OCNGS in the two sectors with the highest potential for radioactive deposition in accordance with the Offsite Dose Calculation Manual (Ref 2). Both of these indicator gardens are greater than 50 square meters (500 square feet) in size and produce green leafy vegetables. A commercial farm located approximately 24 miles northwest of the site was used as a background station.

Sample Collection and Analysis Broadleaf vegetables, specifically cabbage and collards, were collected on a monthly basis beginning in July and ending in November 1996. A gamma isotopic analysis was performed on each sample.

Results The results of the terrestrial monitoring during 1996 demonstrated that the radioactive efiluents associated with the OCNGS did not have any measurable effects on vegetation.

A gamma isotopic analysis was performed on nine collard samples and four cabbage samples (Table 3). Naturally occurring potassium-40 (K-40) was determ in all of the samples collected f

I 88

from both indicator and background stations. Another naturally occurring nuclide, beryllium-7 (Be-7), was identified in 3 of 5 collard samples collected from indicator stations and in 2 of 4 collard samples collected from the background station. Beryllium-7 was also detected in 1 of 4  ;

cabbage samples collected from indicator stations. No other radionuclides were detected in vegetable samples. Of the radionuclides detected, all are naturally occurring, and none are associated with OCNGS operation.

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0 89

GROUNDWATER MONITORING The Oyster Creek Nuclear Generating Station is located on the Atlantic Coastal Plain Physiographic Province. This Province extends southeastward from the Fall Zone, a topographic break that marks the boundary between the Atlantic Coastal Plain and the more rugged topography of the Piedmont Province. The Fall Zone is also where the crystalline and sedimentary rocks of the Piedmont and the unconsolidated Coastal Plain sediments meet.

At least five distinct bodies of fresh groundwater or aquifers exist in the vicinity of the OCNGS.

From the surface downward, they are:

1. Unconfmed, Recent and Upper Cape May Formation

2. Confmed, Lower Cape May Formation

, 3. Confmed, Cohansey Sand

4. Confmed, Upper Zone in the Kirkwood Formation

5. Confmed, Lower Zone in the Kirkwood Formation The unconfmed Recent and Cape May Formations are replenished directly by local precipitation.

The recharge to the confmed aquifers occurs primarily from direct rainfall penetration on the outcrop areas, which are generally to the west of the site at higher elevations.

Sample Collection and Analysis As part of the routine REMP, three groundwater wells were sampled on a quarterly basis. Grab samples were obtained from two local Municipal Utility Authority wells and an on-site drinking water well. The Lacey Municipal Utility Authority combines water from three wells which are drilled to depths of 239',248', and 267'. This sampling location is 2.2 miles north-northeast of the OCNGS. A second sampling location is the Ocean Township Municipal Utility Authority well which is approximately 360' deep and located 1.6 miles from the OCNGS in a south-southwest direction. The third sampling location is the 400' deep on-site well that supplies drinking water to the OCNGS. Each sample was subjected to a tritium and ganuna isotopic analysis.

In addition, a well network installed around the OCNGS in 1983 to serve as an early detection and monitoring system for spills, was sampled in March 1996. This network is comprised of fifteen wells which are located in the Cape May, Cohansey, and Kirkwood Aquifers. Grab sample methodology was used and the samples were also analyzed for tritium and gamma emitting nuclides.

90

Results The results of the groundwater monitoring during 1996 demonstrated that, as in previous years, the radioactive effluents associated with the OCNGS did not have any measurable effects on offsite groundwater quality. l l

Twelve routine REMP well water samples were collected during 1996. No radioactivity was detected in any of these samples (Table 3).

The results of the analyses of 15 samples from the onsite spill monitoring well network were similar to results seen in past years (Table H). Only the naturally occurring radionuclides tritium, potassium-40, and thorium-232 were detected. A tritium concentration of 850 pCi/ liter was detected at Well #9 (WW-9). This concentration was approximately four times higher than

expected based upon the previous four years of data. This well was immediately resampled and the H-3 result was found to be 180 +/- 100 pCi/ liter. The original result (850 pCi/ liter) was most l probably caused by a sampling anomaly and not representative of the actual concentration of tritium in this well.

The maximum tritium level of 180 +/- 100 pCi/ liter was at the lower detection limit and is 0.9 percent of the EPA drinking water limit of 20,000 pCi/ liter. Considering the very large environmental inventory of tritium due to cosmic ray interactions and nuclear weapons testing, it is highly unlikely that the tritium in the OCNGS's effluents could have a measurable effect on existing environmental concentrations. These nuclides have been detected in the past in similar concentrations at both indicator and background stations and are not attributed to OCNGS effluents.

\-

91

RADIOLOGICAL IMPACT OF OCNGS OPERATIONS 4

An assessment of potential radiological impact indicated that radiation doses to the public from 1996 operations at the OCNGS were well below all applicable regulatory limits and were significantly less than doses received from common sources of radiation. The 1996 total body dose, potentially received by a hypothetical maximum exposed individual, from OCNGS liquid and airborne emuents, was conservatively calculated to be 1.8E-2 millirem total or only 7.2E-2 percent of the regulatory limit. The 1996 total body dose to the surrounding population from OCNGS liquid and airborne emuents was calculated to be 2.3 person-Rem. This is approximately 430,000 times lower than the doses to the total population within a 50-mile radius of the OCNGS resulting from natural background sources.

Determination of Radiation Doses to the Public To the extent possible, doses to the public are based on direct measurement of dose rates from external sources and measurements of radionuclide concentrations in the environment which may contribute to an internal dose of radiation. Thermoluminescent dosimeters (TLDs) positioned in the environment around the OCNGS provide measurements to determine external radiation doses to humans. Samples of air, water, food products, etc. are used to detennine internal doses.

During normal plant operations the quantities of radionuclide releases are typically too small to be measured once released to the offsite emironment. As a result, the potential offsite doses are calculated using a computerized model that predicts concentrations of radioactive materials in the emironment and subsequent radiation doses on the basis of radionuclides released to the environment. OCNGS doses were calculated using two advanced computer programs called SEEDS (Simplified Emuent Environmental Dosimetry . System) and EFFECTS (Radioactive Emuent Filing, Evaluation and Comparison with Technical Specifications). These programs are based upon the OCNGS Offsite Dose Calculation Manual (ODCM). These models iacorporate the guidelines and methodologies set forth by the USNRC in Regulatory Guide 1.109 (Ref.17). Due to the conservative assumptions that are used in the models, the calculated doses are considerably

(

higher than the actual doses to people.

The type and amount of radioactivity released from the OCNGS is calculated using measurements from emuent radiation monitoring instruments and eff.tuent sample analysis. Once released, the dispersion of radionuclides in the emironment is readily estimated by computer modeling.

Airborne releases are diluted and carried away from the site by atmospheric diffusion which 92

continuously acts to disperse radioactivity. Variables which affect atmospheric dispersion include I wind speed and direction, atmospheric stability, and terrain. A meteorological monitoring station northwest of the OCNGS permanently records and telemeters all necessary meteorological data.

Computer models are also used to predict the downstream dilution and travel times for liquid releases into the Bamegat Bay estuary and Atlantic Ocean.

The pathways to human exposure are also included in the model. These pathways are depicted in Figure 17. The exposure pathways considered for the discharge of the station's liquid effluent are fish and shellfish consumption and shoreline exposure. The exposure pathways considered for airbome effluents include plume exposure, inhalation, vegetable consumption (durir.g growing season), and land deposition.

SEEDS employs numerous data files which describe the area around the OCNGS in terms of demography and foodstuffs production. Data files include such information as the distance from the plant stack to the site boundary in each of the sixteen compass sectors, the population groupings, gardens of more than 500 square feet, meat animals, and crop yields.

When detennining the dose to humans, it is necessary to consider all pathways and all exposed tissues (surr_ ming the dose from each) to provide the total dose for each organ as well as the total body from a given radionuclide in the environment. Dose calculations involve determining the energy absorbed per unit mass in the various tissees. Thus, for radionuclides taken into the body, the metabolism of the radionuclide in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted, and half-life. SEEDS and EFFECTS also contain dose conversion factors for over 75 radionuclides for each of four age groups (adult, teen, child, and infant) and eight organs (total body, thyroid, liver, skin, kidney, lung, bone, and gastro-intestinal tract).

Doses are calculated for what is termed the " maximum hypothetical individual." This indisidual is assumed to be affected by the combined maximum environmental concentrations wherever they occur. For liquid releases at the OCNGS, the maximum hypothetical individual would be one who stands at the U.S. Route 9-discharge canal shoreline for 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year while eating 43 pounds of fish and shellfish. For airbome releases, the maxunum hypothetical individual would live at the location of highest radionuclide concentration for inhalation and direct phime exposure while eating

[ 1,389 pounds of vegetables per year. This location is 522 meters to the southeast based on historical meteorological air dispersion analysis (Ref. 3). The usage factors and other assumptions 93

FIGURE 17 EXPOSURE PATHWAYS FOR RADIONUCLIDES POTENTIALLY RELEASED FROM THE OCNGS Gaseous Effluents Oyster Creek Station m h 5 2 luents b &- D i rect y irradiation r

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used in the model result in a conservative overestimation of dose. Doses are calculated for the population within 50 miles of the OCNGS for airborne efiluents and the entire population using the Barnegat Bay estuary and Atlantic Ocean for liquid effluents. Appendix G contains a more detailed discussion of the dose calculation methodology.

Results of Dose Calculatioju Doses from natural background radiation provide a baseline for assessing the potential public health significance of radioactive effluents. The average person in the United States receives about 300 millirem (mrem) per year from natural background radiation sources. Natural background radiation from cosmic, terrestrial, and natural radionuclides in the humen body (not including radon), averages about 100 mrem /yr. The natural background radiation from cosmic and terrestrial sources varies with geographic location, ranging from a low of about 65 mrem /yr on the Atlantic and Gulf coastal plains to as much as 350 mrem /yr on the Colorado plateau (Ref. 5).

The National Council on Radiation Protection and Measurements (NCRP) now estimates that the average individual in the United States receives an annual dose of about 2,400 millirem.s to the lung from natural radon gas. This lung dose is considered to be equivalent to a whole body dose of 200 millirems (Ref. 4). Effluent releases from the OCNGS and other nuclear power plants contribute a very small percentage to the natural radioactivity which has always been present in the air, water, soil, and even in our bodies.

In general, the annual population doses from natural background radiation (excluding radon) are 1,000 to 1,000,000 times larger than the doses to the same population resulting from nuclear power plant operations (Ref.18).

Results of the dose calculations are summarized in Tables 7 and 8. Table 7 compares the calculated maximum dose to an individual of the public with the OCNGS ODCM Specifications, Technical Specifications, 40CFR190,10CFR20.1301, and 10CFR50 Appendix I dose limits.

Table 8 presents the maximum total body radiation doses to the population within 50 miles of the plant from airborne releases, and to the entire population using Barnegat Bay and the Atlantic Ocean, for liquid releases.

These conservative calculations of the doses to members of the public from the OCNGS ranged from 0.000022 percent to a maximum of only 0.89 percent of the applicable regulatory limits.

They are also considerably lower than the doses from natural background and fallout from prior i nuclear weapon tests.

l 95

TABLE 7 cal,CUL.ATED MAXIMUM HYPOTHETICAL DOSES TO AN INDIVIDUAL FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM THE OCNGS FOR 1996 EFFLUENT REGULATORY LIMITS PERCENT OF RELEASED CALCULATED DOSE REGULATORY mrem / YEAR SOURCE mrem / YEAR LIMIT UQUID 3 - TOTAL BODY ODCM SPEC 4.6.1.1.4 1.6E-2 5.3E-1 UQUID 10 - ANY ORGAN ODCM SPEC 4.6.1.1.4 8.9E-2 8.9E-1 AIRBORNE 100 - TOTAL BODY 10CFR20.1301 2.1E-3 11E-3 (NOBLE GAS)

AIRBORNE 3000 - SKIN ODCM SPEC 4.6.1.1.5 6.5E-4 2.2E-5 (NOBLE GAS)

AIRBORNE 15 - ANY ORGAN ODCM SPEC 4.6.1.1.7 1.1E-2 7.3E-2 (IODINE AND PARTICULATE)

TOTAL-LIQUID 25 -TOTAL BODY ODCM SPEC 4.6.1.1.8* - 1.8E-2 7.2E-2 AND AIRBORNE TOTAL-UQUID 75 -TIIYROID ODCM SPEC 4.6.1.1.8' l.1E-2 1.5E-2 AND AIRBORNE TOTAL- UQUID 25 - ANY OTIIER ODCM SPEC 4.6.1.1.8' 9.0E-2 3.6E-1 ANDAIRBORNE ORGAN

• 40 CFR 190 9

96

TABLE 8 CALCULATED MAXIMUM TOTAL RADIATION DOSES TO THE POPULATION FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM THE OCNGS FOR 1996

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Calculated Population Total Body Dose

{ Person-Rem / Year OCNGS From Radionuclides in Liquid Releases 2.3 (Barnegat Bay and Atlantic Ocean Users)

From Radionuclides in Airborne Releases 4.5E-2 (Within 50-Mile Radius of OCNGS) f f DOSE DUE TO N ATURAL BACKGROUND RADIATION Approximately 990,000 Person-Rem Per Year f

)

97

REFERENCES (1) Jersey Central Power and Light Company. Oyster Creek Nuclear Generating Station Operating License and Technical Specifications, Appendix A, DPR-16, April 1969.

(2) GPU Nuclear Corporation. Oyster Creek Offsite Dose Calculation Manual, October 19fi3.

(3) GPU Nuclear Corporation. Final Safety Analysis Report, Oyster Creek Nuclear Generating Station, Revision 9, June 1995.

(4) National Council on Radiation Protection and Measurements, Report No. 93, Ionizing Radiation Exposure of the Population of the United States,1987.

(5) CRC Handbook, Radioecology: Nuclear Energy and the Environment, F. Ward Whicker

{ and Vincent Schultz, Volume I,1982.

(6) National Council on Radiation Protection and Measurements, Report No. 22, Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure, (Published as National Bureau of Standards Handbook 69, Issued June 1959, superseding liandbook 52).

(7) Intemational Commission on Radiological Protection, P N ton 2, Report of Committee II on Permissible Dose for Internal Radiation (1959), with D62 Supplement Issued in ICRP Publication 6; Publication 9, Recommendations on Radiation Exposure, (1965);

ICRP Publication 7 (1965), amplifying specific recommendations of Publication 9 concerning environmental monitoring; and ICRP Publication 26 (1977).

(8) Federal Radiation Council Report No.1, Background Material for the Development of Radiation Protection Standards, May 13,1960.

(9) National Council on Radiation Protection and Measurements, Report No. 39, Basic Radiation Protection Criteria, January 1971.

(10) National Council on Radiation Protection and Measurements, Report No. 62, Tritium in the Environment, March 1979.

98

(11) National Council on Radiation Protection and Measurements, Report No. 81, Carbon-14 in the Environment, May 1985.

(12) United States Nuclear P.egulatory Commission. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in The Emirons of Nuclear Power Plants, Revision 1, April 1975.

(13) United States Nuclear Regulatory Commission Branch Technical Position, An Acceptable Radiological Emironmental Monitoring Program, Revision 1, November 1979.

(14) American National Standards Institute, Inc., Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry, ANSI N545-1975.

(15) United States Nuclear Regulatory Commission. Regulatory Guide 4.13, Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Emironmental Applications, Revision 1, July 1977.

(16) United States Nuclear Regulatory Commission. Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Nonnal Operations) - Emuent Streams and the Emironment, Revision 1, February 1979.

(17) United States Nuclear Regulatory Commission. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Emuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, Revision 1, October 1977.

(18) NUREG/CR-4068, Summary of Historical Experience with Releases of Radioactive Materials from Commercial Nuclear Power Plants in the United States,1985.

(19) Olsen, C.R., et. al.,1980. Reactor-released Radionuclides and Fine-grained Sediment -

i Transport and Accumulation Pattems in Barnegat Bay, New Jersey and Adjacent Shelf Waters. Estuarine and Coastal Marine Science (1980) 10,119-142.

(20) GPU Nuclear Corporation. 1986 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1987.

e 99

1 (21) GPU Nuclear Corporation. 1987 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1988.

(22) GPU Nuclear Corporation. 1988 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1989.

(23) GPU Nuclear Corporation. 1989 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1990.

(24) GPU Nuclear Corporation. 1990 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1991.

(25) GPU Nuclear Corporation. 1991 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1992.

(26) GPU Nuclear Corporation. 1992 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Str. tion. May 1993.

(27) GPU Nuclear Corporation. 1993 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1994.

(28) GPU Nuclear Corporation. 1994 Radiological Emironmental Monitoring Report for

[ Oyster Creek Nuclear Generating Station. May 1995.

f (29) GPU Nuclear Corporation. 1995 Radiological Er.vironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1996.

(30) GPU Nuclear Corporation. 1996 Annual Radioactive Efiluent Release Report for Oyster Creek Nuclear Generating Station. March 1997.

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APPENblX A 1996 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions

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TACLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance (miles) Azimuth (derrees) Description '

AFT, AIO,TLD 1 0.2 228 SW of site, at Oyster Creek Fire Pond, Forked River, NJ  !

WWA 1 0.1 227 On site well at OCNGS Forked River, NJ APT, AIO, TLD 3 6.1 94 E of site, near Coast Guard Station, Island Beach State Park APT,AIO.TLD 4 4.7 215 SW of site, where Route 554 and the Garden State Parkway meet, Barnegat, NJ APT, AIO,TLD 5 5.2 355 N of site, Garden State Parkway Service Area, Forked River, NJ TLD 6 2.2 14 NNE of site Lane Place, behind St.

Pius Church, Forked River, NJ i

TLD 7 1.8 111 ESE of site, Bay Parkway, Sands Point Harbor, Waretown, NJ TLD 8 2.3 180 S of site, Route 9 at the Warctown Substation, Warctown, NJ TLD 9 2.0 230 SW of site, where Route 532 and the Garden State Parkway meet, Warctown, NJ AFT, AIO,TLD A 31.1 25 NNE of site, JCP&L office parking lot, next to substation, Allenhurst, NJ APT, AIO,TLD C 35.1 309 NW of site, JCP&L office rear parking lot Cookstown, NJ AFT, AIO.TLD H 35 248 WSW of site, Atlantic Electric office storage yard, Hammonton, NJ 102

TABLE A-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance (miles) Arimuth (derrees) Description I

TLD -10 10.2 21 NNE of site, Route 37 and Gilford Avenue.

Toms River, NJ TLD 11 83 156 SSE of site,80th and Ancher Streets at Water Tower, Harvey Cedars, NJ TLD 12 9.4 192 SSW of site, Atlantic Electric substation access road, Cedar Run, NJ TLD 13 83 345 NNW of site, Dover Road, next to last pole traveling west, South Toms River, NJ APT, AIO,TLD 14 18 I N of site, Larrabee Substation on Randolph Road, Lakewood, NJ TLD 15 19 309 NW of site, Route 539, last pole on moth side across from Bomare Site, New Egypt, NJ TLD 16 18 271 W of site, two poles south of the inti:rsection ofRoutes 563 and 72.

TLD 17 19 214 SW of site, Route 563,2 miles north at high voltage line, New Gretna, NJ AFT, AIO,TLD 20 0.7 93 E of site, on Finninger Farm on south side of access road, Forked River, NJ TLD 22 1.6 146 SE of site, at 27 Long John Siker Way, Skipper's Cove, Waretown, NJ SWA, CLAM, AQS 23 4.0 63 ENE of site, Barnegat Bay ofr Stouts Creek 400 yards SE of Flashing Light "1" 103

TAILE A-1 (continued) - -

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance (miles) Azineth (dersees) Description SWA, CLAM, AQS 24 2.0 104 ESE of site, Barnegat Bay,250 yards SE of Flashing Light "3" SWA, CLAM, AQS 25 1.8 127 SE of site, Barnegat Bay off Holiday Harbor, 200 yards SE oflagoon mouth SWA, CLAM, AQS 31 10.5 183 S of site, Manahawkin Bay 253 3rds SE of buoys C "23" and N "24" SWA. AQS 32 1.9 98 E of site, mouth ofOpter Creek discharge canal SWA, AQS, 33 0.7 104 ESE of site,1200 yards east of Route 9 FISH, CRAB Bridge in Oyster Creek Discharge Canal VEG 35 0.4 110 ESE of site, cast of Route 9 and north of the Discharge Canal, Forked River, NJ VEG 36 24 315 N'W of site, at "U-Pick" Farm, New Egypt, NJ WWA 37 2.2 19 NNE of Site, off Boox Road at Lacey MUA Pumping Station, Forked River, NJ WWA 38 1.6 193 SSW of Site, on Route 532, at Waretown MUA Pumping Station, Waretown, NJ TLD 51 0.4 358 N of site, on the access road to Forked River site, Fo: Led River, NJ TLD 52 0.4 340 NNW of site, on the acu:ss road to Forked River site, Forked River, NJ TLD 53 0.3 310 NW of site, at the GPU Energy Visitor's Center, Forked River, NJ 104

U - m W W W W W l

TABLE A-1 (continued) l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance (miles) Arimuth (decrees) Description ,

I TLD 54 0.3 294 WNW of site, on the access road to Forked l River site, Forked River, NJ TLD 55 1.5 273 W of site, next to Basin #1 on the Forkel River site, Forked River, NJ TLD 56 1.1 258 WSW of site, on the siren pole of the Building 12 parking lot, Forked River site, Forked River, NJ TLD 57 0.2 203 SSW of site, on Southern Area Stores access road, Forked River, NJ TLD 58 0.4 180 S of site, on Southern Area Stores access road, Forked River, NJ TLD 59 0.3 163 SSE of site, on Southern Area Stores access road, Waretown, NJ TLD 60 0.4 136 SE of site, on Southern Area Stores access road entrance, Waretown, NJ TLD 61 0.3 116 ESE of site, on Route 9 south of Oyster Creek Main Entrance, Forked River, NJ I TLD 62 0.2 99 E of site, on Route 9 at access road to Main Gate, Forked River, NJ TLD 63 0.2 70 ENE of site, on Route 9 at North Gate access road, Forked River, NJ TLD 64 0.3 .t3 NE of site, on Route 9 north of North Gate access road, Forked Riwr, NJ 105

TACLE A-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance (miles) Azimuth (derrees) Description TLD 65 0.4 22 NNE of site, on Route 9 at Intake Canal Bridge , Forked River, NJ AFT, AIO, 66 0.5 127 SE of site, east of Route 9 and south of the TLD,VEG Discharge Canal, Waretown, NJ TLD 67 1.0 161 SSE of site, on Route 9 at Waretown Plaza, Warctown, NJ TLD 69 1.3 70 ENE of site, at the intersection of Chesapeake Drive and Buena Vista Road, Forked River, NJ TLD 70 1.6 183 S of site, on Route 532,3/4 mile west of Route 9, in front of-Martin residence, Waretown, NJ '

APT, AIO,TLD 71 1.7 165 SSE of site, on Route 532 at the Waretown Municipal Building, Waretown, NJ APT,AIO,TLD 72 1.9 27 NNE of site, at Library, Forked River, NJ APT,AIO,TLD 73 1.8 111 ESE of site, on Bay Parkway, Sands Point Harbor, Waretown, NJ TLD 74 2.0 90 E ofsite, Orlando Drive and Penguin Court, Forked River, NJ TLD 75 2.0 69 ENE of site,1225 Beach Bhti. and Maui Drist, Forked River, NJ TLD 76 1.7 51- NE of site, on Lacey Road across from Captain's Inn Restaurant, Forked Riser, NJ 106

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TABLE A-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sampic Station Medium Code Distance (miles) Azimuth (derstes) Description TLD 77 1.5 26 NNE of site, NJ State Marina parking lot, Forked River, NJ TLD 78 1.8 2 N of site,1514 Arient Road, Forked Ristr, NJ TLD 79 2.9 162 SSE of site, Hightide Drive and Bonita Drist Warctown, NJ TLD 80 3.1 38 NE of site, Riviera Drive and Dewey Drist, 12noka Harbor, NJ TLD 81 4.6 192 SSW of site, east of Route 9 at Brook and School Streets. Barnegat, NJ TLD 82 4.4 38 NE of site, Bay Way and Clairmore Avenue, Lanoka Harbor, NJ TLD 83 5.8 29 NNE of site, Route 9 and llarbor inn Road, Berkeley, NJ TLD 84 4.8 339 NNW of site, on Lacey Road,1.3 miles west of the Garden State Parkway on siren pole, Forked River, NJ TLD 85 3.8 254 WSW of site, on Route 532,just before landfill, Warctown, NJ TLD 86 4.8 226 SW of site, on Route 554, I mile west of the Garden State Parkway, Barnegat, NJ TLD 87 7.2 143 SE of site, north of Seaview Drive on siren pole, Loveladies, NJ 107

u ---

TACLE A-1(continued)

RADIOLOGfCAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sampic Station i Medium Code Distance (miles) Azimuth (derreeQ Description TLD 88 6.6 127 SE of site, castern end of 3rd Street, Barnegat Light, NJ TLD 89 6.2 110 ESE of site, Job Francis residence, Island Beach State Park TLD 90 6.6 74 ENE of site, parking lot A-5, Island Beach State Park TLD 91 9.5 4 N of site, on Robins Parkway, near Lobster Shanty Restaurant Toms River, NJ TLD 92 9.2 48 NE of site, at Guard Shack / Toll Booth, Island Beach State Park SWA, AQS 93 0.25 150 SSE of site, Oyster Creek Discharge Canal, west of the confluence of freshwater Oyster Creek FISH, CRAB 93 0.1 to 0.3 128 to 250 SE to WSW of site, Oyster Creek Discharge Canal between pump discharge and

. Route 9 SWA, AQS, 94 21.8 201 SSW of site, in Great Bay, mouth of Jimmic::

CLAM, FISH Creek west of channel marker 1 CRAB 94 21.8 201 SSW of site, in Great Bay, adjacent to docks of Cape Horn Marina TLD Tl 0.2 228 SW of site, at Oyster Creek Fire Pond, Forked River NJ TLD RA 2.5 243 WSW of site, at Ocean County VoTech School on siren pole, Warctown, NJ 108

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TABLE A-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sampic Station Medium Cmic Distance (miles) Arimuth (derrees) Dewription TLD RC 1.1 15 NNE of site, at scunge pumping station across from Oyster Bay Restaurant, Forked Riser, NJ TLD RD 1.3 43 NE of site, at Twin Rivers scunge pumping station, Forked Ri er,NJ TLD RF 0.5 14 NNE of site, on access ioad to Forked River site, Forked River, NJ TLD RG 0.6 82 E of site, on Finninger Farm, ucst of dredge spoils basin, Forked River, NJ TLD RH 1.8 222 SW of site, at Ocean Community Cemetery off Route 532, 4 Waretown, NJ TLD RI 0.5 251 WSW of site, on access road to Southern Area Stores, near Building 17, Forked Riser, NJ TLD RJ 1.7 343 NNW of site, in Pheasant Run development, Sheflield Drive and Derby Court, Forked River, NJ SAMPLE MEDIUM IDENTIFICATION KEY APT = Air Particulate SWA =

Surface Water FISH = Fish AIO = AirIodine AQS =

Aquatic Sediment CRAB = Crab WWA = Well Water CLAM = Clams VEG = Vegetables TLD =

Thermoluminescent Dosimeter 109

TABLE A-2 SYNOPSIS OF TIIE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONDUCTED BY GPUN ENVIRONMENTAL AFFAIRS DEPARTMENT OYSTER CREEK NUCLE AR GENERATING STATION 1996 (1)

SAMPLE TYPE NUMBER OF COLLECTION NUMBER OF TYPE OF ANALYSIS NUMBER OF SAMPLING FREQUENCY SAMPLES ANALYSIS FREQUENCY SAMPLES LOCATIONS COLLECTED ANALYZED (2)

Air Particulate 13 Bi-weekly 349(3) Gross Beta Bi-weekly 349(3)

Gamma Quanerly composite 52 Air Iodine 13 Weekly 685(3) 1131 Weekly 685(3)

Well Water 3 Quarterly 12 Gamma Quarterly 12 11-3 Quarterly 12 Surface Water 8 2 locations-Montidy 48 Gamma Monthly 48 (2 Stations) 8 locations- Quarterly Quanerly (8 Stations)

Clam 5 Quarterly 20 Ganuna Quarterly 20 1 Sediment 8 Quarterly 32 Gamma Quarterly 32 Vegetables 3 Monthly (4) 13 Ganuna Monthl>(4) 13 Fish 3 Quarterly 14 Gamma Quarterly 14 Crab 3 Quanerly 8 Gamma Quarterly 8 TLD-Teledyne 10 Quarterly 40 Quarterly 40 Immersion Dose.

Brown Engineering TLD-Panasonic 71 Quarterly 284 Immersion Dose Quarterly 284 (1) This table does not include Quality Assurance (QA) samples.

(2) The number of samples analy cd does not include duplicate analyses, recounts, or reanalyses.

(3) See Table A-3.

(4) Collected during harvest season only.

110

TABLE A-3 1996 SAMPLING AND ANALYSIS EXCEPTIONS During 1996,1181 samples were collected from aquatic, atmospheric, and terrestrial environments around the OCNGS. This is far more than the minimum number of samples and analyses required by the Offsite Dose Calculation Manual (ODCM) Specifications. No sampling or analysis exception occurred in 1996 that resulted in a deviation from or violation of the requirements of the

, ODCM.

The air sampler at station 20 was vandalized during the period of July 1,1996 to July 10, 1996.

Because sample integrity could not be assured, no analysis was performed on the air particulate and air iodine filters. This is not an ODCM required sampling location.

The air sampler at Station 4 failed due to a loss of power on August 20, 1996 when lightning struck the line transformer that provides power to the station. The transformer was replaced on September 6,1996 and power subsequently restored on September 12,1996. No samples could be collected during this period. This is not an ODCM required sampling location.

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APPENDIX B 1996 Lower Limits of Detection (LLD) Exceptions 112 l

TABLE B-1 During 1996, there were no Lower Limit of Detection (LLD) violations on any analyzed REMP Sample

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a APPENDIX C .

Changes To The 1996 REMP F

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TABLE C-1 Changes to the 1996 REMP May 1996 - Panasonic TLDs at Station 54 were moved during the May 22,1996 changcout to a location approximately 100 feet closer to the stack. This was done to allow easier access during changeouts. The station description as given for Station 54 in Appendix A-1 remains unchanged. Siting requirements as defined in the ODCM (Ref. 2) were not compromised as a result of this relocation.

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1 APPENDIX D 1996 Quality Assurance Results f

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The OCNGS REMP Quality Assurance (QA) Program is comprised of three phases. Phase I requires samples collected at designated stations be split and analyzed by separate (independent) laboratories. Analysis results from the quality assurance (QA) laboratory are compared to those from the primary laboratory as set forth in OC Environmental Affairs procedure 6530-ADM-4500.07. Agreement criteria are established in this procedure. If non-agreement of the data occurs, an investigation begins which may include recounting or reanalyzing the sample (s) in question. During 1996, there were no such initial non-agreements in interlaboratry split sample results.

Phase 11 requires laboratories analyzing REMP samples for the OCNGS to participate in a program invohing analysis and reporting of single-blind radiological samples, such as the USEPA Cross-Check Program. This serves as independent verification of each laboratory's ability to correctly perform analyses on various kinds of samples containing unknown quantities of specific radionuclides. The Phase 11 program was significantly expanded during 1996 by the inclusion of an interlaboratory comparison program in addition to the USEPA Cross-Check Program. The new interlaboratory comparison program involves analysis of single-blind radiological samples supplied for a variety of sample media to both the primary and secondary laboratories by an independent contractor (Analpics, Inc. of Atlanta, GA). Results of these interlaboratory comparison programs are presented in Appendix E.

Phase III reg'iires that the REMP analytical laboratories perform duplicate analyses on every twentieth sample. The number of duplicate analyses performed during 1996 is outlined in Table D-1. Results of the duplicate analyses were reviewed in accordance with procedure 6530-ADM-4500.07. No non-agreements occurred during 1996 regarding duplicate analyses of OCNGS REMP samples.

Table D-2 outlines the split sample portion (Phase I) of the QA program for the media collected during 1996. Of the 15 samples that were split, none resulted in an initial non-agreement (Table D-3).

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TABLE D-1 1996 OA SAMPLE PROGRAM NUMBER OF DUPLICATE ANALYSES PERFORMED ANALYSES SAMPLE GROSS GAMMA MEDIUM BETA H-3 I-131 ISOTOPIC AIR PARTICULATE 17 2 AIR IODINE 36 WELL WATER 1 1 SURFACE WATER 3 AQUATIC SEDIMENT 2*

CLAMS 2 FISH 0 CRABS 1 VEGETABLES 0

• 1 DUPLICATE ON QA SAMPLE 118

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TABLE D-2 1996 OA SAN 1PLE PROGRAM SPLIT SAMPLES NUMBER OF NUMBER OF SAMPLE REGULAR COLLECTION QA QA SAMPLE MEDIUM STATIONS FREQUENCY STATIONS COLLECTION

-FREQUENCY WELL WATER 3 QUARTERLY l QUARTERLY f SURFACE 2 MONTHLY MONTHLY WATER 6 QUARTERLY 1 QUARTERLY SEDIMENT 8 QUARTERLY l

( QUARTERLY CLAMS 5 QUARTERLY I SEMI-ANNUALLY (WHEN AVAILABLE)

VEGETABLES 3 MONTHLY I QUARTERLY (WHEN AVAILABLE) (WHEN AVAILABLE)

TLD 71 QUARTERLY 2 QUARTERLY f

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i TABLE D-3 During 1996, there were no initial non-agreements between OCNGS REMP split sample analytical results j l

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APPENDIX E 1996 Environmental Radioactivity Interlaboratory Comparison Results l

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I TABLE E-1 1996 Environmental Radioactidty Interlaboratory Comparison (USEPA Cross-Check) Program Results Tcledyne GPUN-ERL Brown Eng.

Collection EPA Results Results Results Date Media Nuclide (A) (B) (B) 01/23/96 Water Sr-89 73.0 8.7 75.33 1.53 73.67

• 3.21 St-90 5.0 8.7 8.33

• 0.58 5.00

• 0.00 01/26/96 Water Alpha 12.1 i 8.7 14.00

• 1.00 19.00

• 1.00 Beta 7.0 8.7 8.47

• 1.15 7.13 0.21 02/02/96 Water 1 131 67.0 + 12.1 70.00

• 1.00 71.67

• 3.06 03/08/96 Water H-3 22002.0

• 3816.9 22000.00

• 0.00 22000.00 0.00 04/16/96 Water Alpha 74.8

• 32.4 69.33

• 2.52 63.67

• 2.89 Beta 166.9 43.4 156.67

• 5.77 160.00 0.00 Co-60 31.0

• 8.7 31.33

• 2.08 31.67 1.15 St-89 43.0 8.7 45.00

• 1.00 41.33

• 2.31 Sr-90 16.0

• 8.7 16.67

• 1.15 15.33

• 0.58 Cs-134 46.0

• 8.7 42.00 1.73 42.33

• 1.53 Cs-137 50.0

• 8.7 51.67

• 1.53 52.33 1.53 06/07/96 Water Co-60 99.0 8.7 98.67

• 1.53 99.00

• 1.73 Zn-65 300.0 52.0 326.67 *. 5.77 309.33

• 2.08 Ba 133 745.0

• 130.1 770.00

• 0.00 711.00

• 71.42 Cs-134 79.0

• 8.7 75.33

• 0.58 69.67

• 1.53 (C)

Cs-137 197.0

• 17.3 206.67

• 5.77 202.00

• 2.65 07/12/96 Water Sr-89 25.0

• 8.7 30.33

• 1.53 22.67 1.53 Sr-90 12.0

• 8.7 10.33

• 0.58 12.33 * .l.15 07/19/96 Water Alpha 24.4

• 10.6 23.67

• 0.58 22.67

• 0.58 Beta 44.8

• 8.7 48.00

• 3.00 45.33

• 2.08 08/09/96 Water H-3 10879.0

• 1837.6 11000.00

• 0.00 9800.00

• 346.41 10/04/96 Water 1 131 27.0

• 10.4 32.00

• 3.00 26.33

• 2.31 10/15/96 Water Alpha 59.1

• 25.7 59.33

• 4.16 55.67

• 5.03 Beta 111,8

• 29.1 106.67

• 5.77 110.00 0.00 Co-60 15.0

• 8.7 15.33

• 0.58 14.67

• 1.53 Sr-89 10.0 i 8.7 18.00 3.61 9.00 6.00 St-90 25.0

• 8.7 16.00

• 1.00 26.00

• 1.00 (D)

Cs-134 20.0 8.7 19.33

• 0.58 19.67 1.15 ,

Cs-137 30.0

• 8.7 31.33

• 0.58 29.33

• 1.15 l

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TABLE E-1 (cont.)

1996 Environmental Radioactivity Interlaboratory Comparison I (USEPA Cross-Check) Program Results .

Teledyne GPUN-ERL Brown Eng-Collection EPA Results Results Results Date Media Nuclide (A) (B) (g) 10/25/96 Water Alpha 10.3

• 8.7 8.43

• 2.23 9.03 1 0.72 Beta 34.6

• 8.7 35.33 1.53 39.67 0.58 11/8/96 Water Co-60 44.0 8.7 45.67

• 0.58 44.67 0.58 Zn-65 35.0

• 8.7 37.67

• 2.08 38.67

• 0.58 -

Ba-133 64.0 10.4 66.00 0.00 '56.67

• 3.21 Cs-134 11.0

• 8.7 11.67

• 0.58 12.00 0.00 Cs-137 19.0

• 8.7 21.00 1.00 20.67

• 1.15 A. EPA Results - Expected Laboratory precision (control limit,

• 3 sigma, n = 3). Units are pCi/L.

B. Results - Average

• one standard deviation. Units are pCi/L.

C. The Teledyne Brown Engineering Cs-134 result is below the control limit. To verify the cause of the deviation, a Cs-134 standard has been purchased. If the Cs-134 efliciency is lower than the efficiency at 604 Kev and 795 Key, then rather than change those efficiencies (which may be needed for other isotopes of comparable energies), the Cs-134 branching intensity shall be adjusted.

D. The ERL Sr-90 result is below the control limit. Upon investigation it was found that the background count rate was 2.47 cpm. This was outside of the instrument background control limit and should not have been used. The sample holders are now being kept clean to prevent reoccurrence.

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- TACLE E-2 1996 Analytics,Inc. Cross-Check Program Results Collection ANALYTIC 5 Uncertaksey GPU Mfin Mas Date Niedia Nuclide Value (3 Sigen) (I Signum) Resalueles Yahme Ratio Raele Rana Agreessment Notes *

(A) (B) 3/12/96 ' Fiher Alpha 12 1 03 36.0 10 0.83 0.75 133 Yes ,

Beta 85 4 13 63 8 74 0.87 0.8 1.25 Yes [

1:1296 Fiher Ce-141 194 10 ,33 58.2 210 1.08 0.8 1.25 Yes ,

Cr-51 719 36 12.0 59.9 760 1.06 0.8 1.25 Yes Cs-134 128 6 2.0 64.0 120 0.94 08 1.25 Yes Cs-137 141 7 23 60.4 150 1.06 0.8 1.25 Yes i Co-58 106 5 1.7 63.6 110 1.04 0.8 1.25 Yes i Mn-54 70 3 1.0 70.0 75 1.07 0.8 1.25 Yes i 0.8 Yes I Fe-59 186 9 3.0 62.0 210 1.13 1.25 Zn-65 215 11 3.7 58.6 230 1.07 0.8 1.25 Yes Co.60 169 8 2.7 63.4 180 1.07 0.8 1.25 Yes 3/12.96 Cartndge 1-13I 92 5 1.7 55.2 91 0.99 0.8 1.25 Yes j 3/12.96 Filter Sr-90 36 2 0.7 54.0 26 0.72 0.8 1.25 No Yes "B" Agreement ( l result see Nde D) 1/12/96 MA Ce-141 234 12 4.0 58.5 170 0.73 0.8 1.25 No Out of Range (see nnte C)

Ce-141 234 12 4.0 58.5 240 1.03 0.8 1.25 Yes Corrected Results (see Note C) i Cr-51 858 43 143 59.9 790 0.92 0.8 1.25 Yes Cs-134 154 8 2.7 57.8 140 0 91 0.8 1.25 Yes Cs-137 170 9 3.0 56.7 170 1.00 0.8 1.25 Yes ,

Co-58 128 6 2.0 64.0 130 1.02 0.8 1.25 Yes Mn-54 84 4 13 63.0 84 1.00 0.8 1.25 Yes Fe-59 223 11 3.7 60.8 240 1.08 0.8 1.25 Yes Zn-65 260 13 43 60.0 290 1.12 0.8 1.25 Yes Co-60 204 10 33 61.2 200 0.98 0.8 1.25 Yes l'12/96 MA I-131 13 I 03 39 0 15 1.15 0.75 133 Yes (I result see Note D) l'12/96 Milk Sr-89 31 2 0.7 46.5 20 0.65 0.75 133 No Yes-B" Agreement St-90 16- 1 03 48.0 22 138 0.75 133 No Yes"B" Agreement 1.'12,96 Soil Ce-141 0.323 0.02 0.007 48.5 03 0.93 0.75 133 Yes Cr 51 1.182 0 06 0.020 59.1 1.175 0.99 0.8 1.25 Yes l Cs-134 0.212 0.01 0.003 63.6 0.175 0.83 0.8 1.25 Yes On-137 0332 0.02 0.007 49.8 0325 0.98 0.75 133 Yes Co-58 0.176 0.01 0.003 52.8 0.163 0.93 0.8 1.25 Yes Mn-54 0.116 0.01 0.003 , 34.8 0.119 1.03 0.75 133 Yes Fe-59 0307 0.02 0.007 46.1 0313 1 02 0.75 133 Yes ,

Zn-65 0358 0.02 0.007 53.7 0363 1.01 0.8 1.25 Yes Co.60 0.281 O_01 0 003 843 0.288 1.02 0.8 1.25 Yes 124

-. . --- . . . . . _ - . - . , . . . . . - . . . . . . - - - - .- - - - - . . - . . - ~ - --. - . , - . . . - - . . - - . - - ~ . .

I TACLE E-2 (cont.)

- 1996 Analytics, Inc. Cross-Check Prograni Results .

i Notes: *  ;

A. Units are pCi/L for Milk, pCi/g (dry) for Soit and total pCi for Filter and Cartridge.

B. Values are average of tluce or more determinations, unless otherwise indicated.

C. The value reported to Analytics was in error (Mean of(233.4+242.0+24.5 )instead of Mean of(233.4+242.0+2E)

D. Due to insufficient sampic only I analysis was performed. j I

To determine agreement or possible agreement:

1. Divide cach Analytics value by its associated one sigma uncertainty to obtain the resolution.  ;

2. Divide cach GPU value by the corresponding Analytics value to obtain the ratio.  :

3. The GPU measurement is in agreement if the value of the ratio falls within the limits shown in the following table for -l the corresponding resolution. l lt i

Agreement Agreement Resolution Agreement "A" Criteria "B" Criteria  ;

<3 no comparison no comparison no comparison 13-<4 0.4 - 2.5 0.3 - 3.0 . no comparison l 24-<8 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 <

l 2 8 - < 16 0.6 - 1.67 0.5 - 2.0 0.4 - 2.5 3 216 - < 51 0.75 - 1.33 0.6 - 1.67 0.5 - 2.0  :

2 51 < 200 0.80 - 1.25 0.75 - 1.33 . 0.6 - 1.67 l 4 2 200 0.85 -1.18 0.80 - 1.25 0.75 - 1.33 t "A" criteria are applied to the following analyses:  ;

i Gamma Spectrometry where the principal gamma energy used for identification is greater than 250 key, Tritium analyses ofliquid samples, and Low-level 1-131. ,

"B" criteria are applied to the following analyses:

Gamma Smim... dry where the principal gamma energy used for identification is less than 250 key, Sr-89 and

~

Sr-90 determinations, Gross Alpha and Gross Beta. .

Criteria are similar to those listed in USNRC Inspection Procedure 84750 with minor adjustments to account for activity concentrations with large uncertaintics. j i

125  ;

i i

TABLE E-3 1996 Environmental Radioactivity Interlaboratory Comparison Analytics, Inc. Cross-Check Program Results Tcledyne Brown Collection Media Nuclide ANALYTICS Engineering Date Value Value Ratio (A) (B) 3/12/96 Water 1-131 36

• 2 39 5 1.08 Cc-141 88 4 89 i 9 1.01 Cr-51 322

• 16 330 30 1.02 Cs-134 58 3 53

• 5 0.91 Cs-137 64

• 3 65 7 1.02 4

Co-58 48

• 2 49* 5 1.02 Mn-54 31 2 37 4 1.19 Fe-59 83

• 4 93

• 9 1.12 1 Zn-65 97 5 100 10 1.03 Co-60 76

• 4 81

• 8 1.07 3/12/96 Milk 1131 13

• 1 16

• 6 1.23 ,

Ce 141 234

• 12 240

• 20 1.03 I Cr-51 858

• 43 880* 90 1.03 Cs 134 154

• 8 150

• 20 0.97 Cs 137 170

• 9 180*20 1.06 Co-58 128

• 6 140

• 10 1.09 l

< Mn-54 84

• 4 93

• 9 1.11 Fe-59 223*11 250 30 1.12 I Zn-65 260

• 13 260

• 30 1.00 Co-60 204i10 220

• 20 1.08 3/12/96 Water Sr-89 24

• I 30 4 1.25 Sr 90 21

• 1 23

• 2 1.10-3/12/96 Milk Sr-89 31

• 2 30

• 4 0.97 Sr90 16 i 1 17 i 1 1.06 4

3/12/96 Water H-3 2982

• 149 2800 200 0.94 6/19/96 Filter Alpha 35

• 2 37

• 3 1.06 i

Beta 144 7 150

• 10 1.04 6/19/96 Filter Cc 141 400 20 500

• 50 1.25 Cr 51 1048

• 52 1200

• 100 1.15 I Cs-134 310

• 16 310 30 1.00 4 Cs-137 764

• 38 910

• 90 1.19 l

Co 58 173

• 9 210

• 20 1.21 Mn-54 559

• 28 690i70' l.23 Fe-59 144

• 7 190 A 20 1.32 j Zn-65 108

• 5 140

• 10 1.30 ,

Co-60 156

• 8 180 20 1.15 6/19/96 Filter Sr-90 74i4 71 3 0.96

} 6/19/96 Filter Sr-90 49

• 2 64

• 3 1.31 6/19/96 Filter Sr-90 63

• 3 66

• 4 1.05

)

126 i

1

TABLE E-3 (cont.)

1996 Environmental Radioactivity Interlaboratory Comparison Analytics, Inc. Cross-Check Program Results Notes:

A. Tcledyne Results -Results are one determination, counting error is two standard deviations.

Units are pCi/ liter for water and milk. For gamma results, if two standard deviations are less than 10%, than a 10% error is reported. Units are total pCi for air particulate filters.

B. Ratio of Teledyne Brown Engineering to Analytics results.

To detennine agreement or possible anreement:

1. Divide each Analytics value by its associated one sigma uncertainty to obtain the resolution.

2. Divide each value by the corresponding Analytics value to obtain the ratio.

3. The measurement is in agreement if the value of the ratio falls within the limits shown in the following table for the corresponding resolution.

Agreement Agreement Resolution Acreement "A" Criteria "B" Criteria

<3 no comp no comp no comp 23-<4 0.4 - 2.5 0.3 - 3.0 no comp 24-<8 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 2 8 - < 16 0.6 - 1.67 0.5 - 2.0 0.4 - 2.5 216 - < $ 1 0.75 - 1.33 0.6 - 1.67 0.5 - 2.0 2 51 - < 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.67 2 200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33 "A" criteria are applied to the following analyses:

Gamma Spectrometry where the principal gamma energy used for identification is greater than 250 key, Tritium analyses ofliquid samples and Low-level 1-131.

"B" criteria are applied to the following analyses:

Gamma Spectrometry where the principal gamma energy used for identification is less than 250 key, Sr-89 and Sr-90 determinations and Gross Alpha and Beta.

Criteria are similar to those listed in USNRC Inspection Procedure 84750 with minor adjustments to account for activity concentrations with large uncertainties.

Summary:

All Teledyne Brown Engineering and Analytics, Inc. results were determined in agreement according to applicable agreement criteria.

127 i l

k J

s M

< j i

i 4

P 1 F

i a

i APPENDIX F 1996 Annual Dairy Census 1

i 6

l t

1 i

l 128 l i

1

_ _ _ - . _ _ _ . _ _ . _ _ . _ _ . _ _ _ . . ~ . , . . _ . . . _ _ _ _ . . . _ . _ _ _ _ _ . _ . . . _ . . _ . _

i i

a .

s. -

l Annual Dairy Census - 1996 i

,i ' An annual dairy census was conducted to determine the number of commercial dairy operations

1. . ,

' and/or lactating dairy animals providing milk for human consumption located within a five mile  !,

. radius of the OCNGS. As a result of the study, no commercial dairy operations were identifud  ;

within the vicinity of the OCNGS.

Ocean County Agricultural Extension Senice Agent, Ms. Debra Fiola, was contacted regarding i

', the occurrence of daig animals within a five mile radius of the OCNGS. Ms. Fiola indicated that

! no commercial dairy operations were active in the study area. The closest known dairy animals  !

i .

j whose milk was being used for human consumption were goats owned by three families in the l Whiting area which is approximately 12 miles northwest of OCNGS.  ;

i 4

i j ,-

l

?

5 I l

J l

'b e

l 1

129 I

(

APPENDIX G Dose Calculation Methodology i

E

[

130 W

. .....__-.._m.

To the extent possible, radiological impacts were evaluated based on the direct measurement of dose rates or of radionuclide concentrations in the environment. However, the emuents associated with 1996 OCNGS routine operations were too small to be measured once dispersed in the offsite environment. As a result, the potential offsite doses could only be estimated using computerized models that predict concentrations of radioactive materials in the environment and subsequent radiation doses on the basis of radionuclides released to the erwironment. GPUN calculates doses using two advanced class "A" dispersion models called SEEDS (Simplified Emuent Environmental Dosimetry System) and EFFECTS (Radioactive Emuent Filing Evaluation and Comparison with Technical Specifications). These models incorporate the guidelines and methodology set forth in USNRC Regulatory Guide 1.109 (Ref.17). SEEDS uses real-time hourly meteorological information matched to the time of release to assess the dispersion of effluents in the discharge i

canal / estuary system and the atmosphere. Combining this assessment of dispersion and dilution with emuent data, postulated maximum hypothetical doses to the public from the OCNGS T

emuents are computed. The maximum individual dose is calculated as well as the dose to the total population within 50 miles of the OCNGS for gaseous emuents and the entire population downstream of the OCNGS around Barnegat Bay and the Atlantic Ocean for liquid emuents.

Values of environmental parameters and radionuclide concentration factors have been chosen to provide conservative results. As a result, the doses calculated using this model are conservative estimates (i.e., overestimates) of the actual exposures.

The dose summary table, Table G-1, presents the maximum hypothetical doses to an individual, as well as the population dose, resulting from effluents from OCNGS during the 1996 reporting period.

Individual Doses From Liquid Effluents As recommended in USNRC Regulatory Guide 1.109 (Ref.17), dose calculations resulting from OCNGS liquid emuents are performed on four age groups and eight organs. The pathways considered are consumption of fish, consumption of shellfish, and shoreline exposure. All pathways are considered to be primary recreational activities associated with Barnegat Bay and the Atlantic Ocean in the vicinity of the OCNGS. The " receptor" would be that individual who cats fish and shellfish that reside in the OCNGS discharge canal, and stands on the shoreline influenced 131 I

by the station discharge. Table G-1 presents the maximum total body dose and critical organ dose for the age group most afTected.

For the 1996 reporting period, the calculated maximum hypothetical total body dose received from liquid effluents would have been 1.6E-2 mrem. This represents 5.3E-1 percent of the OCNGS ODCM specification limit. Similarly, the maximum hypothetical organ dose from liquid effluents would have been 8.9E-2 mrem to the gastro-intestinal tract. This represents 8.9E-1 percent of the OCNGS ODCM annual dose limit.

Individual Doses From Gaseous Effluents There are seven major pathways considered in the dose calculation for gaseous efiluents. These are: (1) plume exposure, (2) inhalation, (3) consumption of cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing on contaminated ground.

The maximum plume exposure reported in lines 3 and 4 of Table G-1 generally occurs at, or near, the site boundary. These " air doses" are not to an individual but are considered to be the maximum dose at a location. The location is not necessarily a receptor.

With respect to airborne noble gas releases for the 1996 reporting period, the maximum plume exposure (air dose) would have been 9.2E-4 and 2.9E-4 mrad for OCNGS gamma and beta radiation, respectively. These doses are equal to only 9.2E-3 percent and 1.5E-3 percent of the OCNGS Offsite Dose Calculation Manual (ODCM) annual dose limits, respectively.

The calculated airborne dose to the closest individual in the maximally affected sector (SE) for total body dose and skin dose was at a distance of 522 meters using the default parameters specified in the ODCM. The data are presented in lines 5 and 6 of Table G-1. Maximum calculated plume exposures to an individual, regardless of age, from gaseous efiluents during the 1996 reporting period were 2.lE-3 mrem to the total body and 6.5E-4 mrem to the skin. These doses are equivalent to only 2.lE-3 percent and 2.2E-5 percent of the applicable annual dose limits, respectively.

132

The dose to the maximum exposed organ due to radioactive airborne iodine and particulates is presented in line 7, Table G-1. This does not include the total body plume exposure, which was separated out on line 5. The dose presented in this section reflects the maximum exposure to an organ for the appropriate age group. During 1996, gaseous iodines and particulates from OCNGS would have resulted in a maximum dose of 1.lE-2 mrem to any organ. This dose is only 7.3E-2 percent of the OCNGS ODCM specified annual dose limit.

Population Doses From Liauid and Gaseous Efiluents The population doses resulting from liquid and gaseous effluents are summed over all pathways and the affected population (Table G-1, lines 8-11). Liquid population dose is based upon the population located within the region from the OCNGS outfall extending out to the Atlantic Ocean.

The population dose due to gaseous effluents is based upon the 1980 population projections of the Final Safety Analysis Report (FSAR) (Ref. 3) and considers the population out to a distance of 50 miles around the OCNGS as well as the much larger total population which can be fed by food stuffs grown in the 50 mile radius. Population doses are summed over all distances and sectors to give an aggregate dose. Total OCNGS liquid and gaseous effluents resulted in a population dose of 2.3 person-rem total body for the 1996 reporting period. This is approximately 430,000 times lower than the doses to the same population resulting from natural background sources.

133

. TABLE G-1

SUMMARY

OF MAXIMUM IIYPOTIIETICAL INDIVIDUAL AND POPULATION DOSES FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM TIIE OCNGS FOR 1996 INDIVIDUAL DOSES' Percent Effluent ODCM Specification Limit Calculated Dose Age Dist. Sector of Reg.

Released Group (m) Limit LIQUID 3 mrem-Total Body 1.6E-2 mrem Teen Receptor 1* 5.3E-1 %

LIQUID 10 mrem-GI Tract 8.9E-2 mrem Adult Receptor l' 8.9E-1 %

AIRBORNE 10 mrad-Gamma 9.2E-4 mrad - $22 SE 9.2E-3 %

AIRBORNE 20 mrad-Beta 2.9E-4 mrad - $22 SE 1.5E-3 %

AIRBORNE 100 mrem-Total Body' 2.lE-3 mrem All 522 SE 2.lE-3 %

AIRBORNE 3000 mrem-Skin 6.5E-4 mrem All 522 SE 2.2E-5 %

AIRBORNE 15 mrem-Any Organ 1.1E-2 mrem Child 522 SE 7.3E-2 %

POPULATION DOSES 2 Calculated Effluent Dose Released (Person-Rem) l> QUID Total Body 2.3E O LIQUID Gastro-Intestinal 1.83E 1 GASEOUS Total Body 4.5E-2 GASEOUS Thyroid 7.2E-2 Receptor 1 is the Discharge Canal at the U.S. Route 9 bridge.

Individual doses for the calendar year were calculated using the EFFECTS software. These calculations utilize default meteorology referenced in the OCNGS Offsite Dose Calculation Manual.

2 Population doses were calculated using the SEEDS software.

This limit is from 10CFR20.1301. The ODCM limit is 500 mrem.

134

APPENDIX H 1996 Groundwater Monitoring Results 135

TABLE H-1 OCNGS GROUNDWATER RESULTS ON-SITE SPILL MONITORING WELL NETWORK March 1996 Results Analysis Performed: Tritium and Gamma Isotopic TRITIUM GAMMA ISOTOPIC

• STATION 11-3 K-40 Th-232 WW-1 <l70 pCi/ liter <17 pCi/ liter <5 pCi/ liter WW-2 <l70 pCi/ liter <30 pCi/ liter <10 pCi/ liter WW-3 <170 pCi/ liter 53+/-17 pCi/ liter <5 pCi/ liter WW-4 <170 pCi/hter <20 pCi/ liter <7 pCi/ liter WW-5 <170 pCi/ liter <20 pCi/ liter 11+/ 5 pCi/ liter WW-6 <l70 pCi/ liter <40 pCi/ liter <ll pCi/ liter WW-7 <180 pCi/ liter <50 pCi/ liter 15+/-10 pCi/ liter WW-9 180 100** pCi/ liter <18 pCi/ liter <5 pCi/ liter WW-10 <l80 pCi/ liter <20 pCi/ liter <6 pCi/ liter WW-12 <l80 pCi/ liter <l7 pCi/ liter <5 pCi/ liter WW-13 <l80 pCi/ liter <l8 pCi/ liter _ <5 pCi/ liter WW-14 <l80 pCi/ liter <40 pCi/ liter <l2 pCi/ liter WW-15 <l80 pCi/ liter <l7 pCi/ liter <4 pCi/ liter WW-16 <180 pCi/ liter <30 pCi/ liter <10 pCi/ liter WW-17 <l80 pCi/ liter <40 pCi/ liter <12 pCi/ liter

• No other gamma isotopic nuclides detected.

• • Resample Result l

136

TABLE 11-1 (continued)

OCNGS-GROUNDWATER RESULTS ON-SITE SPILL MONITORING WELL NETWORK TYPICAL ANALYTICAL SENSITIVITIES (LLD's)

H-3 180 pCiAiter Be-7 30 pCiAiter K-40 50 pCi/ liter Mn-54 3 pCiAiter Co-58 4 pCi/ liter Fe-59 8 pCiaiter Co-60 4 pCi/ liter Zn-65 8 pCi/ liter Nb-95 4 pCiMiter Zr-95 6 pCi/ liter Ag-110m 3 pCi/ liter Sb-125 8 pCiAiter I-131 7 pCiSiter Cs-134 3 pCi/ liter Cs-137 4 pCi/ liter Ba-140 19 pCi/ liter La-140 8 pCi/ liter Ra-226 80 pCiditer Th-232 11 pCiaiter U-235 20 pCi/ liter l 137

Fieure H-1 Locations df On-Site Wells Building Key 1 Turbine Generator 6 Warehouse 2 Reactor Bldg. 7 Rad Waste 3 Maintenance Bldg. 8 Guard House 4 Off-Gas Bldg. 9 Office Bldg.

5 Waste Storage 10 Engineering Bldg.

11 Parking Lot l SUBSTATION W-1 $ l__________,___ ___________________________________

f N DISCHARGE CANAL  ! INTAKE CANAL

^ f W-6 l

_______________________________ ___. i i O O e w-5 j l W-2 W.3 W-4 l 8 11 l ----I g g! l l W-7J l -

l l 1 3 -l I I I i 10 _._ l 9 l W-12 OO l l W-13 l 8 2 l~~ ~~~

'g$ $ W-15 g l 33 W-10 7

$9 -

l 11 \ l

\, 4 b h-16 W-14 6 l

'N'

____.-________________________ _l 11

$ W-17 138

APPENDIX I 1996 REMP Sample Collection and Analysis Methods 139

TABLE l-l RAD!OIDGICAL ENVIRONMENTAL MONTTORING PROGR AM

SUMMARY

OF SAMPLE COLLLCTION AND ANALYSIS METIIODS 1996 Collect 5m Procedure Approximate Sample Analwis Procedure I Analpis Sample Medium Sampling Methed Number Size Colleded ' Number Procedure ,W Gross Beta Air Particulate Two week composite of contmuous air sampling I f iter TMI Faironmental Imv background gas flow at Affm thrmgh fiher paper g (approxima*ely 1200 Affairs Departnw n proportional counting 6530-IMP 4522'05 weekly) 6510-IMP-4592 05 Gamma Spectrmcopy Air Quasterly composite of each station OCNGS 6 filters TMI Environmental Gamma Isotopic analpis Particulate Emironmental Affairs (approximately 7200 Affairs Department Department Procedure cubic rneters) Prardure 6530-1MP-4522 05 6510-IMP-4592.05 Gamma Spectroscopy Air Weekly composite ofcontinuous air sampling OCNGS I cartridge TMI Environmental Gamma Isotopic analpis lodme through charcoal filter Emironmental Affairs (approximately 600 Affairs Depadrnent Department Procedure cubic meters weekly) Procedure 6530-IMP-4522.05 6510-IMP-4591.04 l

Gamma Spedroscopy Surface Monthly grab sample at two stations and quarterly OCNGS 3.78 liters TMI Emironmental Gamma Isotopic analpas Water grab sample at an additional six stations Emironmental Affairs Affairs Department Department Pmeedure Procedure 6530-1MP-4522.06 6510-1MP-4592.06 Gamma Isntopic analpis 6510-OPS-4591.04 Tcledyne Brown Er*gineering PR(M42-5 Gamma Spectrmcopy Well Quarterly grab sample OCNGS 3.78 liters TMI Emironmental Gamma Isotopic analysis Water Emironmental Affairs AfTairs Department Department Procedure Prah 6530-IMP-4522.10 6510-IMP-4592.06 Gamma Isotopic analysis 6510-OPS-4591.04 Teledyne Bmun Engineermg PR(M42-5 Ganana Spectmscopy Clams Quarterly grah sample OCNGS 1kg TMI Emironmental Gamrna Isotopic analpis Fish Quarterly grab sample Emironmental Affairs (ifpossible) AITairs thyartment Crabs Quarterly grab sample Department Prmdure Procedure 6530-IMP-4522.14 6510-IMP-4592.03 Gamma ls<4oric analpis 6530-lMP-4522.16 6510-OPS-4591.04 Teledyne Drown Engineenng PR(M42-5 140

TAllLE I-l RADIGIDGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF SAMPLE COLIlXTION AND ANALYSIS MET 1tODS 1996 Collecti Procedure Approximate Sample Anahsis Procedure Analysis Sample Medium Sampling Method Number Size Collected ~ Number Prah Alstrad Gamma Spedrmenpv Sediment Quarterly grab sample OCNGS 3.78 liters 'I MI-EC Gamma Isotopic analysis .

Emironmental Affairs 6510-IMP-4592.04 Department Procedure 6510-OPS-4591.04 6530-IMP-4522 03 Gamma Isotopic analysis Teledsne Brown Engmeermg PRO-042-5 Gamma Spectrmmpy Vegetables Four week grab sample OCNGS 1 & g or nmre TMI-EC Gamma Isotopic analysis Emironmental Affairs (ifpnssible) 6510-lMP-4592 03 Department Procedure 65104)PS-4591.04 6630-IMP-4522.04 Gamma isMopic analysis Teledyne 13rmm Engineermg PRO 442-5 Tritium Well Water Quarterly grab sample OCNGS 3.78 liten TMI-EC Sample is filtered and Emironmental AfTairs 6510-lMP-4592 02 mixed mth scintillatica Department Procedure 6510-OPS-4591.05 fluid fiw scintillation 6530-lMP-4522.10 counting, Teledyne Brown Sample is filtered possibly Engineering distilled, and mixed with PRO 452-2 scintdlation fluid fiv PRO 452-35 scire.illation counting.

TLD (Panasonic) Immersion Dose Dosimeters exchanged quarterly OCNGS Four Badges TMI-Dosimetry nermoluminescent Emironmental Affairs 6610-OPS-4243,01 dosimetry Department Procedure 6530-1MP-4522 02 TLD (Teledyne 11rown Immersion Dose Dosimeters exchanged quarterly OCNGS One lhdge Teledyne 11rown 11cmoluminescent Engineermg) Emironmental AITairs Engineering dosunetry Department Procedure PRO-342-17 6530-IMP-4522 02 141

APPENDIX J 1996 TLD QUARTERLY DATA

I!l1ll1ili 1 l Ii \ l R

A E

L C w U k N N I I.

4 63 7 42 3 3 5 4 d 1 023 2 01 001 G e WS t e

t

9. 2 9 4 34 3 0. 2.9 Mde- 4 3 3 5 3 5 3 2I 2 1 1 I 1 I 1 1 1 I 1 R

MM 0 8

1 T v e

A N D. 5 5 5 6 5 7 4 32 7 M?

Ef I

V D

I dt 0 000 000 02 1 N

I D

GR NA NSe ED u

. NN Mn e 4 7 0. 8 3 2 21 2 R. 2 271621 I 3 4 2 WA e 1 1 1 1 1 1 1 1 I

"*OCt 4 e3 T R

. mR ED MN A

.."I"Y DR E T. T "ER 1

J

- "TA TQ f

t v

E"f l

t^P t

MD R A

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N dD. 3034 2 2 63 4 2 4 000 0I 0000 A2ER D N i

e T."* DA I T Mtm

_'TS LR le 0 1 3 2 2 4 4 91 7

""TPAl t Ud h I

e r 13 3 2 3 3 1 51 1 121 1 2 1 1 1 1 I CE NM E

MR NI m"l OL l i l

" VM i

N -

E! J Yt LR RA

• ET TG ve RN 9 1 5 8 2 8 3 6 5 2 AI M l N D.

I d 01 00000000 N a

@U NR R WS 8 6 9. R. 8 4 7 91 5 M %, 2 3 2 1l 2 4 1 1 I I 1 1

1 1 2 1 1 1 1 g

A E

L UCU PN G

\

M AC1 8 1 C4 m73 97 09 R 1 b

%w

,' jh OtEEK G TWIC BTdTION >

NUCLEAg Im QLIAR1ERLY Ef6NAl, TIS REPORT . PAMA90NIC TIPS -

, NUCLEAR RtWMfMG TAtt2

• Mit,tBEM PER STANDARD QUARTER amp 2-STANDARD DE%1AT1tWW

• Staunn - Mrst PWind 1996 Secased Pwled 1996 ; TWed PMind 1996 s

- Pueren Pweed 1995 ,

Reedna Sed. Dr' Readiu IInd. Dev Ramdene Std. Due Rement Shl. Dev A

• 13.05 0.35 11.86 1.09 11.43 1.58 10 09 I 48 C 12.09 0.38 11.37 0 81 11.35 0.42 9.35 1.41 11 12.12 0.72 10.54 0.63 10 44 0.76 8 91 1.78 1 14 19 0 98 12.89 1.22 14 21 0.99 10.56 0.79 3 11.41 0.57 10.26 1.04 10 71 1.72 9 47 1.40 4 I I.14 0.27 9.98 0.40 10 12 0.61 8 81 0.77 5 12.43 1.01 10 RR 0 60 11 32 0 30 9 82 0.47 6 11.19 0.50 10.43 1.11 10.76 0 54 8.96 I.18 7 10.91 0 44 9.73 0 96 9 82 0 69 8 68 0.51 8 1839 0.59 10.34 1.53 10.77 0.36 9.84 1.18 9 12.44 0 82 11.25 0.92 11.46 0 36 10 81 0 43

- RA I I .03 0.24 - 9.78 0.98 9.% 0.70 9.26 0.83 A RC 12.35 0.48 11.26 0.55 1139 0 84 10.21 0.58 d^ RD 11.27 0.64 10.29 0.69 1041 031 9.63 0.62 RF i1.47 0 80 10 66 1.33 11.49 0 42 1002 1.25 RG 10.96 0.48 9 65 1.13 9.45 0.81 8.25 0.71 RII 11.16 0.25 9.94 1.15 10.18 0.78 9.65 0.56 RI 12.47 0.50 10.67 0.77 12.46 1.16 10.89 0.32 RJ 11.41 0.35 10.55 0.95 10.24 0.55 9.84 0.62 Tl 14 09 0.81 14.07 133 14.02 0.82 10 37 1.09 10 11.76 1.05 Il .00 031 1039 0.49 9.05 1.11 Il 11.55 0.74 10.28 0 65 10 33 0 67 9.51 0.58 12 1233 1.12 11.12 1.08 11.35 1.07 10.23 1.41 13 10 64 0.38 9.82 1.68 034 10.10 835 0.58 i 14 13.86 0 88 12.60 0.86 12.71 131 12.64 1.92 15 11.93 0.64 . I I .04 039 10.89 1.10 9.58 1.07 16 10 95 0.77 9.51 0 60 9.77 0.40 8 88 1.29 17 13.22 4.88 1039 0.76 10.73 0.92 9 33 1.05 20 11.I4 0 44 10.22 1.22 10.04 I.02 8.67 0.95 22 10.67 0.68 9.70 0.52 9.74 0.71 9.49 1.25 51 14 34 0.48 13.72 1.47 14.00 1.13 1232 0.74 52 16.23 0.52 14 83 0.76 15.53 1.24 12.89 0.98 53 14.96 0 99 13.93 0.83 14.10 135 10.23 0.91 54 12.55 1.05 11.59 0.61 12.40 0.65 10 06 0 90

" 11 6% 0 67 10 60 0 97 11 23 0 64 1058 0 99

i TAM 2 J-2 (Osmalemed)

OYSTER CitRIK NUCLEAR GElWCRATING STATKPI -

NUCLEAR 194 QUAk11tRLY ENVIRONMENTAL 11D RITORT . PAMA90MIC 1175 - NUCLEAR RIfMMTNG TAttJ, . Mit.1AREld Prat STAMaskp QUARTER AMD 34TA98RARD DFVIAT90'IR Stuttne pirut Perted 19M Serend Ptvied 994  : Tidrd PWeed 194 . Fuusre Pwtud 194 Reeent Sed. Dev Readema !ted. Dev handina Sed. Ikw tendisa Sad. Dev 56 12.90 136 1834 1.13 11.55 1.40 11.21 0 71 57 16 65 0.10 13.85 0 00 17.29 2.53 11.47 1.42 58 1587 1.01 14 4) 1.42 17.07 0.90 10 61 0 95 59 15.11 0.73 13.96 1.03 15.28 0.80 11.44 0.54 60 11.61 0 82 10 25 0 93 11.59 031 10.4R 0 48 of 11.20 0.81 9.RR 0.77 10.83 0 61 9.73 0.58 62 1237 0.R8 10.29 0 84 11.41 1.11 10 09 0 54 63 11.77 0 65 10.50 1.01 11.65 0.05 1065 1.27 64 II35 0.98 9.90 0 24 10.RR 035 9 65 0 RR 65 11.53 0 84 1019 0 71 11.12 O R6 9.7R 0.52 66 11.07 1.06 9 89 0.76 10.53 1.01 R.R7 1.09

- 67 I I .RI 0.56 10.44 0 40 11.43 1.00 10.04 0.87 4 69 11.48 0.81 9.9R 1.26 10.32 0.43 9.58 0.61

• 70 I I .09 0 80 9 69 0.58 10.I6 0.60 9 67 0.82 71 11.52 0.85 1032 0 RI 1089 0 33 9.69 1.57 72 I1.69 0.8R 10.89 0.R4 I1.06 0.54 9.94 0.85 73 10.69 0.51 9.92 1.02 9.95 0 R3 R.65 1.86 74 11.44 0.64 16 61 0 81 10.27 0 85 9.71 0.51 75 13.01 0.76 11.65 0.98 11.43 0.77 1034 1.11 76 11.22 0.54 9.95 1.02 10.16 0.54 9.07 0.89 77 I2.76 0.64 Il .47 0.55 11.50 0.77 10.65 0.70 7R 11.11 0.73 10.55 1.01 10.13 0.51 9.11 1.07 79 10.74 0.54 9 RR I.19 9.67 0 RO 9.04 0 40 80 11.84 036 10 25 0.87 10.48 0.58 9.74 0.44 RI 12.02 0.26 10.63 1.10 10.98 0.27 10.19 0 66 82 12.0R 0.56 11.03 0.66 10.63 0.93 10.24 03R R1 12.53 0.R0 10.74 139 10.90 0 86 10 31 0.74 h4 12.79 0 59 11.44 0.4R 11.95 039 9.75 0.74 R5 11.29 0 49 10.05 0 67 10.23 0.75 9.91 0 64

[

R6 11.80 0.5R 10.70 1.16 11 05 0.70 9.57 0 91 l 87 13.52 0.91 12.20 0.77 12.35 0.88 11.25 0.94 R8 1031 0 47 935 0.7R 9.4R 0.61 R.57 0.75 89 11.25 0.91 9.57 IA) R.99 0 87 R.21 0 64 90 10.62 0.55 9 46 1.00 0 00 0.75 R.51 04I 91 11.73 1.07 10 57 0.56 10.41 0.29 9 33 0 R9 92 12.26 0.76 11.54 0 67 10 83 1.02 9 45 1.55