ML20247B483

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1997 Radiological Environmental Monitoring Rept
ML20247B483
Person / Time
Site: Oyster Creek
Issue date: 12/31/1997
From: Roche M
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1940-98-20233, NUDOCS 9805080052
Download: ML20247B483 (182)


Text

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l GPU Nuc! var,Inc.

( U.S. Route #9 South NUCLEAR Post Office Box 388 Forked River, NJ 087310388 '

Tel 609 971-4000 April 30, 1998 1940-98-20233 l

l U. S. Nuclear Regulatory Commission j Attention: Document Control Desk Washington, D C 20555

Dear Sir:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Oyster Creek Radiological Environmental Monitoring (REMP) Report - 1997 Enclosed is a copy of the Oyster Creek REMP Report for 1997. This submittal is made in accordance with Technical Specification 6.9.1.e.

If you should have any questions or require further information, please contact Brenda DeMerchant, OC Regulatory Affairs Engineer, at 609-971-4642. j Very truly yours,

% Lafe b Michael B. Roche /

Vice President and Director Oyster Creek f l MBR/BDE/gl Enclosure

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cc: Administrator, Region I NRC Project Manager h

NRC Sr. Resident Inspector 9905080052 971231

[DR ADOCK 05000219 PDR l

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I ll OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey The 650 MWplant is a single-unit, five-loop General Electric Boiling Water Reactor (BWR). The site, about 800 acres, is in Lacey and Ocean g Townships of Ocean County. Located approximately nine miles south of Toms River, it is E about 50 miles east of Philadelphia, and 60 miles south of Newark.

Construction began in December 1963. The station began g) ;

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

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

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

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

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

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

The Turbine Building houses the turbine-generator, control l

room, main condensers, power conversion equipment and auxiliary systems. The turbine-generator consists of one high-pressure turbine, three low-pressure turbines, a generator l' and an exciter. The turbines and generator turn at 1,800 revolutions per minute to generate three-phase, 60-cycle electricity at 24,000 voks. The ciectricity generated is provided to the grid by two transformers which boost the voltage to 230,000 volts.

Steam is supplied to the high pressure turbine from the

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

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

feet. Cooling water is provided from Bamegat Bay, through the South Branch of the Forked g \

River and passes through the condensers and discharges into Oyster Creek for retum to E' Barnegat Bay. The water is pumped by four 1,000-horsepowerpumps, each of which

( moves about 115,000 gallons per minute through the 6-foot-diameter pipes that feed the g condensors. E The ventilation stack is 368 feet high with 26 feet extend-ing below grade. The stack provides ventilation for the Reactor Building, Turbine Building g; and Radwaste Facilities. E Oyster Creek is owned by Jersey Central Power & Light (JCP&L) Company and oper- l M

atedbyGPUNuclear(GPUN) E Corporation. JCP&L and GPUN are units of the GPU System. ll\'

I

e 1997 Radiological Environmental Monitoring Report l Prepared By ,

Oyster Creek Environmental ANairs GPU Nuclear, Inc.

4 TABLE OF CONTENTS l

PAGE TABLE OF CONTENTS i

. LIST OF TABLES , iv LIST OF FIGURES ti

SUMMARY

AND CONCLUSIONS 1 INTRODUCTION 3 Characteristics of Radiation 3 Sources of Radiation 4 Nuclear Reactor Operations 7 Sources of Liquid and Airborne Emuents 9 DESCRIPTION OFTHE OYSTER CREEK NUCLEAR GENERATING STATION SITE 11 GeneralInformation 11 i ChmatologicalSummary 11 EFFLUENTS 18 HistoricalBackground 18 Emuent Release Limits 18 Emuent Control Program 21 Emuent Data 22 RADIOLOGICAL ENVIRONMENTAL MONITORING 26 Environmental Exposure Pathways to Humans from Airborne and Liquid Emuents 26 Sampling 27 Analysis . . 28 Quality Assurance Program 32 DIRECT RADIATION MONITORLNG 50 Sample Collection and Analysis 50 Results 51 1

TABLE OF CONTENTS (Continued)

PAGE l

ATMOSPHERIC MONITORING 55 Sample Collection and Analysis 55 Results 55 AQUATIC MONITORING 60 Sample Collection and Analysis 60 Results 61 TERRESTRIAL MONITORING 69 Sample Collection and Analysis 70 Results 70 GROUNDWATER MONITORING 71 Sample Collection and Analysis 71 Results 72 RADIOLOGICAL IMPACT OF OCNGS OPERATIONS 73 Deternunstion of Radiation Doses to the Public 73 Results of Dose Calculations 76 REFERENCES 80 APPENDIX A: 1997 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions 83 , .

APPENDIX B: 1997 Lower Limits of Detection (LLD)

Exceptions 93 APPENDLX C: Changes to the 1997 REMP 95 APPENDLX D: Radionuclides Concentrations in 1997 Environmental Samples 102 ii

TABLE OF CONTENTS (Continued)

PAGE l

APPENDIX E: 1997 Quality Assurance Results 141 APPENDLX F: 1997 Environmental Radioactivity Interlaboratory Comparison Results 146 APPENDIX G: 1997 Ann:2al Dairy Census 157 APPENDIX H: Dose Calculation Methodology 159 APPENDIXI: 1997 Groundwater Monitoring Results 164 APPENDIX J: 1997 REMP Sample Collection and

' Analysis Methods , 168 APPENDIX K: 1997 TLD Quarterly Data 172 iii

LIST OF TABLES TABLE TITLE PAGE l

l 1 Sources and Doses of Radiation 5 2 Radionuclides Composition of OCNGS Effluents for 1997 23 3 Radiological Environmental Monitoring Progrrm Summary, Oyster Creek Nuclear Generating Station-January 1997 through December 1997, Condensed Summary 34 4 TLD Exposure Periods During 1997 51 5 Cesium-137 Concentration in Aquatic Sediment, 1994- 1997 (pCi/kg-dry) 62 6 Cobah-60 Concentration in Aquatic Sedunent, 1994 - 1997(pCi/kg-dry) 65 7 Species of Fish Caught as Part of the OCNGS REMPin 1997 68 8 Calculated Maximum Hypothetical Doses to an Individual from Liquid and Airborne Efiluent Releases from the OCNGS for 1997 78 9 Calculated Maximum Total Radiation Doses to the Population from Liquid and Airborne Effluent Releases from the OCNGS for 1997 79 A-1 Radiological Environmental Monitoring Program Sampliag Locations 84 A-2 Synopsis of the Operational Radiological Environmental Monitoring Program for the Oyster Creek Nuclear Generating Station - 1997 90 A-3 1997 Sampling and Analysis Exceptions 91 B-1 1997 Lower Limits of Detection (LLD) Exceptions 94 iv

\

LIST OF TABLES (Contmued)

TABLE TITLE PAGE.

C-1 Changes to the REMP During 1997  %

! D-1 Radiological Environmental Monitoring Program Summary Oyster Creek Nuclear Generating Station January,1997 through December,1997 103

E-1 1997 QA Sample Program - Number of Duplicate Analyses Perfonned 143 l

p E-2 1997 QA Sample Program - Split Samples 144 E-3 Agreement /Non-Agnement of Split Sample Analytical Results 145 F-1 1997 USEiA Cross-Check Program Results 147 F-2 1997 DOE EML Cross-Check Program Results 149 F-3 1997 ANALYTICS Environmental Cross-Check Program Results 153 F-4 1997 ANALYTICS/rBE Environmental Cross-Check Program Results 155 G-1 Annual Dairy Census - 1997 159 l

H-1 Summary of Maximum Hypothetical Individual and Population Doses l From Liquid and Airborne Effluent Relem= From the OCNGS for 1997 163 I-1 OCNGS Groundwater Results from the On-Site Spill Monitoring WellNetwork 165 l

J-1 Radiological Environmental Monitoring Program Sumnary of Sample Cah*a= and Analysis Methods - 1997 169 l K-1 1997 TLD Quarterly Data - Panasonic TLD's 173 i

K-2 1997 TLD Quarterly, Data- Teledyne Brown Engineering TLD's 174 y

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l LIST OF FIGURES FIGURE TITLE PAGE 1 Oyster Creek Nuclear Generating Station .

Senphfied S+= -t 8 2 Oyster Creek Nuclear Generating Station Wind Direction Fr%g of Occurnace- 1997 Wind Ihrection "From" Each Compass Sector-Values in' Percent of Hourly Occurrewe 13 3 Oyster Creek Nuclear Generating Station Monthly Mean Ambient Air Temperatum- 1997 Compand with Historical (1946-1981) Atlantic City National Westiwr Service Average Temperatum Data 15 4 Oyster Creek Nuclear Generating Station Monthly Precipitation - 1997 Compared with Historical (1946-1981) Atlantic City National Weather Service Average Precipitation Data 16 5 Location of Radiological Environmental Monitoring Program (REMP) Stations Within One Mile of the Site 29 6 Location of Radiological Environmental Monitoring Program (REMP) Stations

. Greater than One Mile and Within Two Miles of the Site 30 7 Location of Radiological Environmental Monitoring Program (REMP) Stations Greater than Two Miles From the Site 31 8 Mean Panasonic TLD Gamma Dose-1989 through 1997 ~ 52 9 Mean Panasonic TLD Gamma Dose for 1997 Pased on Distance from OCNGS 53 vi i

i LIST OF FIGURES (Continued)'

FIGURE TITLE PAGE l

l l 10 Air Particulate Gross Beta- 1997 Moving Range l Quahty Control Chart -Indicator Station Resuks -

Compared to Background Limits 57 11 Bi-Weekly Mean Air Particulate Gross Beta l Concentrations-1997 58 12 ' Monthly Mean Air Particulate Gross Beta l

Concentrations- 1984 through 1997 59 13 Mean Cesium-137 Concentration in Aquatic Sedunent- 1984 through 1997 63 l

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l 14 Mean Cobalt-60 Concentrationin '

l Aquatic Sedunent-1983 through 1997 . 66 l- 15 Mean Cobak-60 Concentration in Clams -

1983 through 1997 67 16 Exposure Pathways for Radionuclides l Potentially Palan=<i frorn the OCNGS 75 i

I-1 Locations of On-Site Wells 167 l

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SUMMARY

AND CONCLUSIONS .

. 'Ihe radiological envin  : 1 morutormg jorv.wd dunng 1997 by the GPU Nuclear Enthum 1 Affairs Dwirwit at the Oyster Creek Nuclear Cer=&ug Station (OCNGS) is 4=!s-A in this report The q--sen of a nuclear power pla i results in the release of small amounts of radioactive matenals to the environment. A radiowgical envkr- <- : l monitonng program 4

l (REMP) has been established to 'monstor radation and radioactive matenals in the environment around the OCNGS. 'Ihe pragmm evaluates the relatianchip between amounts of radioactive matenal released in efflumts to the environment and resultant radiation doses to indivaul< Summanes and interpretations of the data were published semiaan=1ly from 1 % 9-1985 and annually since 1986 (Ref. 20 through 30). AA&tinaal mfu ...& ion cm-% releases of r=Aanc+ive matenals to the emironment is matained in the Semi-Annual and Annual EfHuent Release' Reports subnutted to the United States Nuclear Regulatory Comnusss (USNRC).

Dunng 1997, as in previous years, the radioactiw efBuents ==~iat~I with the OCNGS were a small fraction of the applicable federal regulatney limits and did not haw significant effects on the quality of the emhumw4. c.icnt t~i maximum hypothetical radat on doses to the public attributable to 1997 operanons at the OCNGS ranged from 0.0000011 percent to a maximum of only 0.21 perant of the applicable regulatory limits. Fuiti-u. ore, they were siehaly less than doses received fmm other man-made sources and natural background sources of radiation.

Radioactive matenals cs kkM in this report are normally present in the envhu--% ' esther naturally or as a result of non-OCNGS activities such as prior Mo.cc,pisic nuclear weapons testing, medical industry activities, and the 1986 Chemobyl accident. Cna==ntly, measurements made in the vicaruty of the site were compared to background measurements to i; udes any impact of OCNGS go kes. Samples of air, well water, surface water, clams, sediment, fish, crabs, vegetables, and brmdleaf vegetaban were m!! aced Samples were analyzed for radioactivity including tritium (H-3), gross beta, and gamma-enuttmg r=& annelida < Extemalpenetrating radation dose measurements also were made using thennolummescent dosimeters (TLDs) in the sicanty of the OCNGS.

The results of these radiological measurements were used to assess the environmental impact of OCNGS operations, to dernonstrate compliance with the Technical Specifications (Ref.1), the Offsite Dose Calculation Manual Specifications (Ref. 2), applicable federal regulations, and to 1

i verify the adequacy of containment and radioactive effluent control systems. The data collected by the REMP also provide a historical record of the levels <.f radionuclides and rasation attributable l to natural causes, worldwide fallout from prior nuclear weapons tests and the Chemobyl accident, as I

wellas OCNGS operations.

Radiological impacts in terms of ra&ation dose as a result of OCNGS opidiens were calcnhted and also are &scussed. 'Ibe results provided in this report are stui eizsiin the following highhghts:

o During 1997, 631 samples were taken from the aquatic, 2.+i*de, and terrestnal environments around the OCNGS. A total of 698 anahses were performed on these saraples.

l Two hundred twenty three (223) direct ra&ation dose measurements using TLDs also were

made. Forty-two (42) groundwater samples, taken primarily from local municipal water supplies and on-site wells, were collected and eighty-four (84) analyses were perfonned on those samples

o . Minute levels of cesium-137 (Cs-137) detected in aquatic se& ment samples were attributable in part to past effluents from the OCNGS. This is the first annual reportmg penod dunng which cobalt-60 (Co-60) was not detected in any emiron nental me&a. This is a result of the l nunmuzation ofliquid radioactive effluents and the natural radioactive decay process.

o. The amount of radioactivity released in efBuents from the OCNGS durmg 1997 was the third smallest in the lustory of Station operation. 'Ihe prrA-.... r radionuclides in gaseous and liquid effluents was tritium (H-3). Estimated ra&ation doses to the public, attributable to l 1997 effluents, ranged from 0.0000011 percent to 4 maximum of only 0.21 percent of applicable regulatorylimits.

o Dunng 1997, the maximum total body dose potentially received by an indivisial from liquid and airbome effluents was conservatively estim*dt o be about 0.027 nulhrems The total l

l body dose to the surrounang population from liquid and aubome efBuents was conservatively calculated to be 0.05 person-rem. This is approxunately 20 nulhon times lower than .the dose that the total population in the OCNGS area receives from natural backgmund sources l

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1 l INTRODUCTION Charactenstics of R=Aiatinn i

Instability within the nucleus of radioactive atoms results in the release of energy in the form of radiation.

Radiation is classified according to its nature - particulate and electromagnetic. Particulate radiation I

consists of energetic subatomic particles such as electrons (beta particles), protons, neutrons, and alpha

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particles. Because of its imuted ability to penetrate the human body, particulate radiation in the l 1

environment contributes primarily to intemal radiation exposure resulting from inhalation and ingestion of l radioactivity.

t l 1 l Electromagnetic radiation in the form of x-rays and gamma rays has characteristics similar to visible light i but is more energetic and, hence, more per.Asug. Although x-rays and gamma rays are penetrating and )

can pass through varying thicknesses of matenals, once they are absorbed they produce energetic l

electrons which release their energy in a manner that is identical to beta reticles. He principal concem for gamma radiation from radionuclides in the emironment is their cmtribution to external radiation exposure he rate with which atoms undergo disintegration (radioactive decay) varies among radioactive elements, but is uniquely constant for each specific radionuclides. 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 second for some radionuclides to nulhons of years for others. In fact, the natural background radiation to which all l mankmd has been exposed is largely due to the radionuclides of uranium (U), thorium (%), and potassium (K). Dese radioactive elements were fonned with the creation of the uniserse and, owing to i their long half-lives, will continue to be present for millions of years to come. For exampic, potassium-40 (K-40) has a half-life of 1.3 billion years and exists naturally within our bodies. As a' result, approximately 4000 atoms of potassium emit radiation internally within each of us every.second of our life.

In assessing the impact of radioactivity on the myrronment, it is important to know the quantity of radioactivity released and the resukant radiation doses. The common unit of radioactidty is the curie (Ci). It represents the radioactivity in one gram (g) of natural radium (Ra) which is also equal to a decay rate of 37 billion radiation emissions every second Because the level of radioactive matenal in the environment is extremely small, it is rmre comenient to work with portions or fractions of a curie.

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Subunits like picocune (pCi), (one tnihonth of a curie), are frequently used to express tle radioactivity l ' present in envuu.m.m I and biological samples.

W biological effects of a specific dose of radiatinn are the same whether the radiatiari source is extemal ,

l or internal to the body. The ioyvitud factor is how much radiation energy or dose was depacited h j unit of radiaton dose is the Roentgen Equivalent' Man (rem), which also incorporates the vanable I l

effectiveness of different forms of radianno to produce biological change For envig --- d radiation .

exposures, < is convement to use the smaller unit of mdhrem (mrem) to express dose (1000 mrem equals 1 rem). When radiation exposure occurs over penods of time, it is approprote to refer to the dose rate.

Dose rates, therefore, define the total dose for a fixed interval of time, and for envi,uou 1 exposures, are usually measured with reference to one year of time (mrem per year).

Sources of Radiation Life on earth has evolved amid the constant exposure to natural radiation. In fact, the single major source of radiation to which the general populatim is exposed cons fmm natural smrces Althmgh everyone on the planet is exposed to natural radiation, some people receive more than others Radiation exposure from natural background has three components (i.e., cosmic, terrestnal, and intemal) and varies with altitude ar.d geographic location, as well as with lising habits.

For example, cosmic radiation originating from deep interstellar space and the sun increases with altitude, becaw there is less air to act as a stueld Simdarly, terrestnal radiation resultmg from the presence of naturally occurnng radionuclides in the soil varies and may be signi6cantly higher in some areas of the country than in others Even the use of particular building matenals for houses, cookmg with gas, and home insulation affect exposure to natural radiation The presence of radioactivity in the human body results from the inhalation and ingestion of air, food, and water contauung naturally occurring radionuclides. For example, drinking water contains trace amounts of uranium and radium, and milk contains radioactive potassium. Table I summanzes the conunon sources of radiation and their average annual dose 4

TABLE 1 (Adapted from Ref. 4)

Sources and Doses of Radiation

  • Natural (82%) Man-made (18%)

Radiation Dose Radiation Dose Source (mrem /vear) Source .Jmrem/ gar).

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, phosphate nunmg, burning of coal, weapons fallout,

& nuclear fuel cycle) 9 Approximate Total 295 Approximate Total 64

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

The average person in the' United States receives about 300 mrem /yr (0.3 rem /yr) from rntural background radiation sources. This estimate was recently revised from (approximately) 100 to 300 mrem because of the inclusion of mdon gas which has always been present but has not been previously included in the calculations. In some regxns of the country, the amount of natural radiation is sigmficantly higher.

Residents of Colorado, for example, receive an aMMnn2160 mrem /yr due to the increase in cosmic and i-bial radiation levels. hi fact, for every 100 feet above sea level, a person will receive.an aMMan21 1 mrem /yr from cosmic radiation. In several regions of the world, high coi-Lations of uranium and radium deposits result in doses ofseveral thousand mrem /yr to their residents (Ref. 4).

Recently, public attention has focused on radon (Rn), a naturally occurnng radioactive gas pro.luced from uranium and radium decay. 'Ihese elements are widely distributed in trace amounts in the earth's crust. 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 levels found elsewhere in the United States. However, additional survep are needed to detemune the full extent of the problem nationwide. Radon is the largst component of natural background radiation and may be {

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responsible for a substantial number oflung cancer death < annually. 'Ibe National Council on Radiatim Protection and Measumnents (NCRP) estunates 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). ' Ibis lung dose is considered to be equivalent to a whole body dose of 200 mdhrems & NCRP has remmmended actions to catrol indoor radon sources and mduce exposures

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When radioactive substanas are inhaled or swallowed, they are distributed within the body in a non-umform fashion For example, radioactive iodme selectively concentrates in the thyroid gland, radioactive oesium is distributed throughout the body water and muscles, and radioactive strontium concentrates in i

the bones. The' total dose to organs by a given radionuclides also is influenced by the quantity and the duration of time that the radionuclides remams in the body, incl =iing its physical, biological, and chemical charactenstics Depending on their rate of radioactive decay and biological elinunation from the body, some radionuclides stay in the body for very short times while others remam for years.

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l l In addition to natural radiation, we are exposed to radiation from a number of man-made sources 'Ihe i

single largest of these sources comes from diaganctic medical x-rays and nuclear medical procedures i Some 180 million Americans receive medical x-rays each year. The annual dose to an indisidual from such radiation averages about 53 mdhrems Much smaller doses come from nuclear weapons fallout and I consumer products such as televisions, smoke detectors, and fertihzers, Production of commercial nuclear power and its associated fuel cycle contributes less than 1 mrem to the annual dose of about 300 l

mrem for the average indmdual lising in the United States.

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Fallout commonly refers to the radioactive debris that settles to the surface of the earth following the detonation of nuclear weapons it is dispersed throughout the environment either by dry deposition or washed down to the earth's surface by precipitation There are approximately 200 radionuclides produced in the nuclear weapon dannatina process, a number of these are detected in fallout. 'Ibe radionuclides found in fallout which produce most of the fallout radiation exposures to humans are todme-131 (I-131), strontium-89 (Sr-89), strontium-90 (Sr-90), and cesium-137 (Cs-137). There has been no atmospheric nuclear weapon testing since 1980 and many of the radionuclides, still present in our environment, have decayed significantly. Cc%+;1y, doses to the public from fallout have been decreasing.

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As a result of the nuclear accident at Chemobyl, USSR, on April 26,1986, radioactive material was disperW throughout the global environment and detected in vanous media such as air, milk, and soil.

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Cesium-134, cesium-137, sodme-131, and other radionuclides released from Chernobyl were detected at 1

the OCNGS in significant amounts following the accident. These radionuclides contmue to decay toward .

1 l a stable statein the emironment. I Nuclear Reactor Operations

, Common to the commercial production of electricity is the m-m 56cn of fuel which produces heat to l

l make steam which turns the turbine-generator which generates electncity. Unlike the burung of coal, oil, or gas in fossil fuel powered plants to generate heat, the fuel of most nuclear reactors is wuydsed of the l

element uraruum in the form of uranium oxide.' The fuel produces power by the process called fission. In i

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

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absorbed by the uranium, pundidug the fission process to contmue. As this process contmues, more fission products, radiation, heat, and neutrons are produced and a m=tained reaction occurs The heat )

l produced is tr-s,fr.ud via reactor coolant (water) from the fuel to produce steam which drives a tuttine-generator to produce electricity. The fission products are mostly radioactive; that is, they are i

unstable atoms which emit radiation as they decay to stable atoms. Neutrons which are not absorbed by l the uranium fuel may be absorbed by stable atoms in the matariah which make up the enmpnnenta and structures of the reactor. In such cases, stable atoms often become radioactive. This process is called

. activation and the radioactive atoms which result are called activa' tion products.

The OCNGS reactor is a Boiling Water Reactor (BWR). The nuclear fuel is designed to be contamed witlun sealed fuel rods arranged in anays called bundles which are located within a massive steel reactor vessel. As depicted in Figure 1, enoling 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 enndenced back into water in the main a- h*rs. This condensate is then pumped back into the reactor vessel and the cy,cle repeats Several hundred radionuclides of some 40 different elements are created in a nuclear reactor dunng the process of gesw.6ug electricity. Because of reactor engmeenng designs, the short half-lives of many radionuclides, and their chenucal and physical properties, nearly all radioactivity is enntained 7

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The OCNGS reactor has six ind: pendent barriers that confine radioactive matenals produced in the t

reactor as it heats the water. Under normal operating conditions, eaantially all radioactivity is contamed within the firsttwo barriers.

he ceramic uranium fuel pellets provide the first banier. 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 o%g tcmpu.hucs may not be contamed in the fuel. -

The second bamer consists of arconium (Zr) alloy tubes (termed " fuel claddmg") that resist corrosion and degradation due to high temperatu:es. The fuel pellets are contained within these tubes. There is a l small gap between the fuel and the claMmg. in which the noble gases and other volatile radionuclides l

collect and are contamed.

The primary 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 (dectrically charged) form. These matenals 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 Krypton and xenon collect j as a gas above the cmhm when the steam is enndemed The fourth barrier consists of the tractor pressure wssel, turbino, condenser, and associated piping of the coolant system. He reactor pressure vessel is a 63-foot high tank with eteel walls approximately eight mches thick. It encases the reactor core. He remamder of the coolant system, including the turbine and condenser and associated piping, provides contamment for radioactivity in the primary coolant.

The drywell provides the fifth bamer. It is a steel-lined vessel, surrounded by concrete walls approximately 41/2 to 71/4 feet thick, that encloses the reactor pressure vessel and recircularmg pumps

. and piping.

%e reactor building provides the sixth barrier. It is a reinforced concrete and steel superstructure with walls approxinutely 5 feet thick that enclose the dryvell and other plant components. The Reactor Buddmg is always maintained at a negative pressure to prevent out-leakage.

Sources of Liauid and Airbome Effluents Ahhnngh the previously described bamers contain radioactivity with high efficiency, small amounts of radioactive fission products are nevertheless able to diffuse or migrate through minor flaws in the fuel 9

1

1 l

claMmg and into the reactor coolant. Trace an=atu f reactor o system component and structural j surfaces which have been activated also get into the reactor coolant water. Many of the soluble fission and activation products such as iodmes, strontiums, cobalts, and cesiums are removed by denunerahzers in the purification system of the reactor coolant De physical and chenucal properties of noble gas fission products in the primary coolant prevent their removal by the denunerahzers f Because the reactor system has many valves arAl fittings, an absolute seal cannot be actueved Minute dramage of radioactive hquids from valves, piping, and/or equipment sE- =W with the coolant system may

[ occur m the Reactor and/or. Turbine Bmidings Noble _ gases, produced dunng the fission process, are i

collected as gaseous waste which is processed in the multistage systcms in the OCNGS AugmentaA Off-Gas

!' BnMmg. while the renummg radioactive hquids arr milac'ad in floor and equipment drams and sumps and are purr ped to and processed in the OCNGS Radwuste Facility.

Reactor off-gas, consisting primarily of hydrogen and rachoactive non-conanable gases, is withdrawn from' the reactor primary system by steamjet air ejectors. Lese air ejectors drive the process stream through a 60 l' minute holdup pipe at approximately 110 cubic feet per minute and then into the Angmantad Off-Gas (AOG) l' t

System. He holdup pipe allows r=iinaarlib with short half-lives to decay. He Augmented Off-Gas j System is a gaseous processing system which provides bydrogen 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 Efficiency Particulate (HEPA) filters prior to discharge to the base of the stack. Once the process stream enters the stack, it is diluted by buikhng ventilation, which averages approximately 200,000 cubic feet per minute, is morutored and sampled, and then is discharged out the top ofthe 368-foot stack, r

Le liquid waste processing system receives water cantamiaa'ad with radioactivity and processes it by filtration, deminerali= tina _, and dietillatinn- Purified radwaste water is routmely recycled to the plant.

Occasionally, it may be necessary to discharge this punfied water, under the guidali- of applicable permits, to the enviwo-st. C-sa== removed during the' purification process are stored in the radwaste buddung and are eventually disposed of via the radioactive solids disposal systems Before punfied water is discharged to the envirormwd, it is first 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 nunute l

10 L

l 4

i DESCRIPTION OF THE OYSTER CREEK NUCLEAR l

GENERATING STATION SITE i

l l GeneralInfo4matum

'Ibe Oyster Creek Nuclear Ccm .ug Station is located in lacey Township of Ocean County, New .

Jersey, 'about 60 miles south of Newark, 9 miles south of Toms River, and 35 miles north of Atlantic City. It lies approxunately 2 miles inland from Bamegat Bay. The site, covenng 1416 acres, is situated partly in Lacey Township and, to a lesser extent, in Ocean Township. The Garden State Parkway bounds the site on the west. Access is provided by U. S. Route 9, passing through the site and% dug a 661-acre eastern portion from the balance of the property west ofthe highway. Ibe station is about 1/4 l mile west of the highway and 1-1/4' miles east of the PaAway. The site property extends abcut 3-1/2 l

miles inland from the bay; the maxunum width in the north-south direction is almost 1 mile. The site j location is part of the New Jersey shore area with its relatively flat tqxgraphy and extensive freshwater l and sahwater marshlands The South Branch of Forked River runs across the northem side of the site and Oyster Creek partly borders the southem side.  !

It is estimated that approxunately 3.3 million people reside withs a 50 mile radius of the OCNGS l (Ref. 3). The nearest population center is Ocean Township which lies less than two miles south- l l

southeast of the site. Based on 1994 population estunates,5903 people reside in Ocean Township. j I

Two miles to the north of the OCNGS,23,897 people reside in lacey Township (estunated 1994 population). Dover Township, situated 9.5 miles to the north, is the nearest major population center with a population of 81,550 (actimatai 1994 population). The region adjacent to Barnegat Bay is l one of the State's most rapidly developing areas. In addition to the resident population, a sizable seasonal influx of people occurs during the. summer. This influx occurs almost exclusively along )

the waterfront.

Climatolomcal Summary Meteorological data were obtamed during 1997 from an on-site weather station. These data are subject to emive quality assurance techniques and categorized for further analysis, including historical comparisons with both on-site and off-site sources as well as statistical processes to I monitor instrument performance. -

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' The climate of New Jersey and a great deal of the country was greatly influenced by the El Nino

' Southern Oscillation (ENSO) phenomenon, a major warnung of the ocean waters across the castem and central tropical Pacific Ocean ne effects of the ENSO were initially experienced in March I and continued throughout the year. They include abnormal pattems of rainfall and cloudiness, especially over the tropics. North America typically receives its strongest ENSO influence during l l winter and early spring. The persistence of abnormally warm waters off the west coast have l l

l mereased the occurrence of extra-tropical storms that have buffeted the west coast with prolonged I storms and increased mudslides. In addition, the persistence of the sub-tropical jet stream has brought milder temperatures across the entire continental United States during the winter, when the ENSO is strongest. The ENSO is expected to have a significant influence on our climate through mid-1998. ' Beyond that point, prognostication of the ENSO is difEcult.

l Climatological highlights during the year included a second consecutive above normal temperature and precipitation pattern during the fall and winter, along with a second consecutive cooler summer.

Tropical storm activity in the Atlantic Ocean was lirrited to one storm, mainly curtailed due to the l

l influence of the ENSO in that abnormally' strong' upper-level westerly winds extended from the eastern North Pacific to the southwestern Sahel area of Africa, a breedmg ground of the Atlartic hurricane, i

During the summer months, winds were predonunantly from the south and southwest directions.

l This ushers in warm and humid weather conditions. Precipitation resulting from these cenditions 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 origmate from the upper midhest United States and Canada They are generally characterized by 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 northwest, west .

northwest, west, and west-southwest (Fig. 2). Seasonal winds were esident as well, including the sea biceze circulation (Ref. 3) during the late spring through early autumn season. Resulting winds during a sea breeze are from the south and southeast. The number af occurrences of this thermally-induced wind, created due to the differential heating between the'laad 'and the ocean, was reduced for the second straight year due to the strong west-southwesterly flow during the summer months, a direct result of the ENSO.

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, The annual average air temperature for 1997 was 52.56 degrees Fahrenheit, warmer tlum last year's average temperature of 51.74 degrees The historical average annual temperature is 53 degrees.

However,1997 was far from a normal year with regard to temperature. Eight of the twelve months were charactenzed by below normal temperatures. The largest difference occurred during the months of May, June, and August (Fig. 3). He winter months of January, February, and December experienced above normal temperatures for the second straight year. He lack of a sustained polar jet stream in the continental United States was the reason for the warmer temperatures. In addition, the ENSO and the sub-polar jet stream, bringing warmer air masses .

4' originating over the Pacific Ocean, were the dnminating features, especially during the months of November and December. Normal continental polar air masses only. penetrated as far south as Canada and retreated north. During the summer months, temperatures were below normal. A semi-permanent feature known as the sub-tropical high-pressure system usually settles over the southern j half of the United States. His area produces southwest flow and ushers in warm, hum'd i conditions. This feature was not strong during 1997 and although there were periods of high humidity over the region,' temperatures remained near or slightly below normal with pronounced cloud cover. -

l For the second straight year, the area experienced above normal precipitation (Fig. 4). The annual total precipitation amount was 50.93 inches, compared to 52.92 inches during 1996. The 1997 total is more than eleven inches greater than the Atlantic City National Weather Service historical average (1946 -1981) of 41.50 inches. As previously discussed, the lack of the semi-permanent sub-tropical high pressure belt over the southeast allowed an influx of moisture from the southwest.

j This moisture was enhanced by the ENSO over the eastern Pacific. This moisture also caused enhanced development of extra-tropical . storms, even during the summer months. In fact, the area experienced one of the largest storm events in late August when the area received over 3.50 inches l

of rain. Typically, the ENSO will produce enhanced ramfall over the southem tier of the United States and along the southeast coast. Summer precipitation was also a result of showers and thunderstorms that develop in warm, humid air. These events are generally of short duration but high intensity. As described earlier, the lack of easterly winds in tiie tropics inhibited the development of tropical storms. Tropical stcrm Danny affected the area on July 25 with nummal rainfall and wind. He moderate temperatures reduced snowfall amounts for the year to

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approxanately 4 inches (January and Febmary); Generally, the region will see approximately 10 l

inches of snow. In summary, precipitation events in the region were a result oflarge extra-tropical storms, especially during the fall, winter and early spring along with warm frontal passages. A

, more frequent summer cloud cover reduced the frequency of violent weather conditions associated l with strong heatmg (lightning, hail, tornado activity) during 1997. For additional site-specific meteorological data, refer to the OCNGS Annual Radioactive Effluent Release Report' for 1997 (Ref. 31),

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EFFLUE @i Historical Background Almost from the outset of the discovery of x-rays in 1895 by Wilhelm Retgen. the potential hazard of ionmng radiation was r=ghi and efforts were nude to establish radiation protection standards. 'Ibe Intemational Comnussion on Radiological Protection (ICRP) and the Natioral Council on Radiation Protection and Measurements (NCRP) were established in 1928 and 1929, respectively. These organuations have the longest contmuous experience in the review of radiation health effects and with makmg re- . adations on gniddie for radiological protection and radiation exposure limits. In 1955, the United Nations created a Scientific ~ Committee on the Effects. of Atomic Radmdon (UNSCEAR) to summanze reports received on radiation levels and 'the effects on man and his envimmuent. 'Ihe National Academy of Sciences (NAS) formed a w- .h in 1956 to review the biological effects of atomic radiation (BEAR). A series of reports have been issued by this and succeeding NAS unmJdces on the biological effects ofionmng radiation (BEIR), the most recent dunng 1990(known as BEIR V).

'Ihese comnuttees and commissions of nationally and intemationally regni=1 scientific experts have been d~iicat~i to the undmtanding of the health effects of radiation by investigating all sources of relevant knowledge and scientific data and by providing guidance for radiological protection. Their members are selected from universities, scientific research centers, and other national and international research organ >7ations The comnuttee reports contain scientific data obtamed from physical, biological, and epidemiological studies on radiation health effects and serve as scientific Jauas for information presentedin this report. ._

Since its inception, the USNRC has depended upon the rw-42 e4ations of the ICRP, the NCRP, and the Federal Radiation Council (FRC) (incorporated in the Uruted States Environmental Protection Agerx:y (USEPA) in 1970) for basic radiation protection standards and guidance in establishing regulations for the nuclear industry (Ref. 6 through 9).

EfDuent Release Limits As part of routine plant operations, knuted quantities of radioactivity are released to the emironment in liquid and airbome efHuents. An efHuent control program is implemented by GPU Nuclear te ensure radioactivity releasco to the envisums,t is muumal and does not exceed release limits. The Federal 18

l govemment establishes limits on radioactive materials released to the emironment. These limits are set at low levels to protect the heejth and safety of the.public and are specified in the' OCNGS Technical Speci6 cations and Offsite Dose C@leion Manual (ODCM) (Ref. I and 2). GPU Nuclear conducts operations in a manner that holds radioactive effluents to small percentages of the federal limits.

A ixa-srxiation of the ICRP, NCRP, and FRC is that radiation exposures should be maintamed at levels which are "as low as reasonably achievable" (ALARA) and commensurate with the societal benefit derived from the activities resultmg in such exposures For this reason, dose limit Pliaac were established by the USNRC for releases of radioactive efBuents from nuclear power plants. These guidelines were then used as the basis for the development of the 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.

Applict.bk OCNGS Offsite Dose Calculation Manual limits are as follows:

- ODCM Specification 4.6.1.1.3.A .

Radioactivity Coruun.Gon in Liauid MIuent

'Ihe concentration of radioactive matenal, other thab noble gases, in liquid effluent in the discharge canal at the U.S. Route 9 bridge shat! not exceed- 10 times the liquid efBuent concentrations =peci6al in 10CFR Part 20.1001-20.2401, Appendix B, Table II, Column 2.

- ODCM Specification 4.6.1.1.3.B Radioactivity Concentration in Liauid EfBue_nJ

'Ihe concentration ofnoble gases dissohed or entramed in liquid effluent in the discharge canal 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 Liouid EfBuent The dose to a MEMBER OF THE PUBLIC due to radioactive material in liquid effluent in the UNRESTRICTED AREA shallnotexceed:

1.5 mrem to the Total Body during any calendar quarter 19

.._____m... _ _ _ _ _ _ _ _

5.0 mrem to any body organ dunng any calendar quarter 3.0 mrem to the Total Body dunng any calendar year ,

or 10.0 mrem to any body organ dunng any calendar year.

- ODCM Specification 4.6.1.1.5.A Dose Rate Due to Gaseous EfBuent The dose equivalent' rate in the UNRESTRICTED AREA due to radioactive noble gas in gaseous efBuent 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 Effluent The dose equivalent rate in the UNRESTRICTED AREA due to tritium (H-3), I-131, I-133, and to radioactive matenal in particulate form having half-lives of 8 days or more in gaseous efBuents 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 radionuclides is averaged over no more than 3 months and the dose rate due to other radionuclides is averaged over no more than 31 days.

- ODCM Specification 4.6.1.1.6.A Air Dose Due to Noble Gas in Gaseous Effluent The air dose in the UNRESTRICTED AREA duc to noble gas released in gaseous efHuent shall not exceed:

5 mrad / calendar quarter due to gamma radiation 10 mrad / calendar cuarter due to beta radiation 10 mrad / calendar year due to gamma radiation 20 mrad / calendar year due to beta radiation 20

l.

ODCM Si xdradion 4.6.1.1.7.A Dose Due to F=Aiaiadina and Particulate in Gaseous Effluent

'Ihe dose to a MEMBER OF THE PUBLIC from I-131; I-133, and from rasoactive matenal in particulate form having half-lives of 8 days or more in gaseous efBuent, in the UNRESTRICTED AREA shall not exmed 7.5 mrem to any body organ per calendar quarter or 15 mrem to any body organ per calendar year.

- ODCM Snaci&=+ ion 4.6.1.1.8.A Annual Total Dose Due to Radioactive Emuent

'Ihe annual dose to a MEMBER OF 'IEE PUBLIC due to radioactive matenal in esuent frcm the OCNGS in the UNRESTRICTED AREA shall not exceed 75 mrem to hidher th>Toid or 25 mrem to his/her total body or to any other organ ,

EfBuent Control Program EfBuent control includes plant a- r r-..:- such as the verwi1=*ina system and filters, off-gas holdup components, denunerahzers, and an evaporator system. In addition to d' dAg the release of ra&oactivity, the efBuent control program ir.cludes all ' aspects of efBuent and ensam-.: 1 monitoring.

This includes the operation of a complex ra&ation monituag system, collection and analysis of efBuent samples, emironmental sampling and morutoring, and a cargdssive quahty assurance program Over the years, the program has evolved in response to d-.girg regulatory requmments and plant maditinas For example, additional instruments and samplers have been installed to ensure that measurements of effluents remam onscale in the event of any accidental release of ra&oactisity.

. Effluent Instnment=*ian: Liquid and aubome efBuent measuring instrumentation is designed to morutor the presence and the amount of radioactivity in efBuents. Many of these instnanents proside continuous surwdlance of radioactivity releases. Calibrations of efBuent instrurnents are performed using reference j standards certified by the National Instinite of Standards and Technology (NIST). Instrument alarm setpoints are pre-set to ensure that effluent release limits will not be exceeded If ra&ation morutor alarm setpoints are reached, releases are L-:--Jwly temunated.

l 21

Where continuous survedlance is not practicable or possible, contingencies are specified in the Offsite Dose C*n1* ion Manual and/or the Technical Specifications.

Emuent Sampline and Anahsis: In addition to continuous radiation monitoring instruments, samples of efHuents are taken and subjected to laboratory analysis to identify the specific radionuclides quantities being released. A sample must be repn:sentative of the efHuent from which it is taken. Sampling and analysis provide a sensitive and precise method of deternunmg efBuent composition. Samples are analyzed using statemf-the-art laboratory counting equipment. Radiation instrument readmgs and sample results are compared to ensure. correct correlation.

Effluent Data As part of routine plant operations, Imuted quantities of radioactivity are released to the emironment in efHuents. He amounts of radioactivity released vary and are dependent upon operating conditions, power levels, fuel conditions, efficiency ofliquid and gas processing systems, and proper functioning of plant equipment. He largest variations occur in the airborne effluents of fission and activetion gases, which are proportional to the integrity of the fuel claddmg and the operation of the OCNGS Augmented Off Gas system. In general, efBuents have been decreasing with time due to improved fuel integnty and increased efficiency ofprocessing systems.

The amount of radioactivity eleased in efHuents from the OCNGS during 1997 was the third smallest in the history of Station operation. He predonunant radionuclides in gaseous and liquid efHuents was tntuim (Table 2). Estunated doses to the public, attributable to these efHuents, were a small fraction of the app!icable regulatory limits (Tables 8 and 9). Summaries of OCNGS effluents can be found in Table 2 and in the Annual EfHuent Release Report that is submitted to the USNRC (Ref. 31). Radioactive constituents of these efBuents are discussed in the following sections:

Noble Gases he predommant radioactive materials released in OCNGS airbome efHuents are typically the noble gases krypton (Kr) and xenon (Xe). Small amounts ofnoble gases can also be released in liquid effluents. He total amounts of krypton and xenon released into the atmosphere in 1997 were 0.91 curies and 20.9 curies, respectively. Noble gases are inert, which 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. Rese noble pases were readily dispersed into the atmosphere wien released and because of their short 22

\

TABLE 2 l

RADIONUCLIDES COMPOSITION OF OCNGS EFFLUENTS FOR 1997 l

Rad' . alide .l Half-Life Liquid Effluents (Ci) Airborne Efiluents (Ci)

H-3 l 1.23E 1 Years 1.05E-2 1.35E 2 Cr-51 l 2.78E 1 Days < LLD 1.42E-5 Mn-54 l 3.12E 2 Days < LLD 1.14E-5 Co-60 l 5.26E 0 Years < LLD 2.92E-5 Kr-85m l 4.5GE 0 Hours < LLD 4.50E-2 Kr-87 l 7.60E 1 Minutes < LLD 5.77E-1 Kr-88 l 2.80E 0 Hours < LLD 2.88E-1 l Sr-89 l 5.05E 1 Days < LLD 8.64E-4

. Sr-90 l 2.88E 1 Years < LLD 1.70E-5 1-131 l 8.05E 0 Days < LLD 2.72E-3 1-133 l 2.09E 1 Hours < LLD 1.27E-2 Xe-133 l 5.20E O Days < LLD 1.29E-1 Xe-135 l 9.10E O Hours < LLD 2.08E 1 Cs-137 l 3.02E 1 Years < LLD 3.47E-5 j Ba-140 1.28E 1 Days < LLD 8.63E-4 Alpha _

< LLD 5.31E-6 i

NOTE: All effluents are expressed in scientific notation. No other nuclides were detected.

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

23

half-lives, quickly decayed into stable, nonmdioactive forms. No noble gas actisity was released in liquid effluents during 1997.

I lodmes and Particulate: The dscharge ofiodiner and particulate to the emironment is nunimued by 1

factors such as their high chemical reactivity, solubility in water, and the higl. ccmoval efficiency of airbome and liquid processing systems Of the gaseous radioiodmes, iodine-131 is of particular interest because ofits relatively long half-life of 8.05 days. Particulate of relative concem are the radiocesiums (Cs-134 and Cs-137), radiostrontium (Sr-89 and Sr-90), and activation products, manganese-54 (Mn-54) and cobalt-60 (Co40). The total amount ofiodmes and particulate released from the OCNGS in 1997 was 0.0172 curies in airborne effluents. No iodines or particulate were released in liquid effluents.

Tritium: Tritium (H-3) is typically the predommant radionuclides released in liquid effluents and is also released in airbome effluents. Tritium is a radioactive isotope of hydrogen. It is produced in the reactor fuel and components and in reactor coolant as a result of neutron interaction with the naturally-occurring deu. xium (also a hydrogen isotope) present in water. Liquid releases from tir OCNGS during 1997 resulted in 0.0105 curies of tritium being released. Tritium released in airbome effluents accounted for 135 cmies including 17 curies of tritium from the OCNGS Isolation Condensers. The amount of gaseous tritium released in 1997 was approximately an order of magnitude greater tlun the amounts released in previous years, most likely as a result of control rod blade leakage. However, to put these amounts of H-3 into perspective, the world inventory of natural cosmic ray-produced tritium is approximately 70 million curies, which corresponds to a production rate of 4 million curies per year (Ref.10). Tritium contnbutions to the environment from OCNGS effluents are too small to have any measurable effect on the existmg concentrations in the oEsite emironment.

Tmnsuranics: Transuranic are produced by neuura 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), plutoruum-241 (Pu-241), americium-241 (Am-241), plutonium-243 (Pu-243), plus other isotopes of americium and curium. They have half-lives rangmg from hundreds of days to millions of years. Greater than 99% of all transuranic are artamed within the nuclear fuel.

24

I These nuclides are insoluble and non-volatile and'are not readily transported from in-plant pathways to the emironment. Gaseous and liquid processing systems remove greater than 90% of transuranic that may be found in the reactor coolant. Because retention and removal efficiencies are so high, isotopic j analyses for transuranic are not routinely performed. Howner, most transuranic are alpha emitters and are monitored by performing routine gross alpha analyses.

Carbon-14: Production of carbon-14 (C-14)in reactors is small. It is produced in the reactor coolant as a result of neutron interacdons with oxygen (0) and nitrogen (N). Eoimes for all nuclear power production worldwide show that 235,000 curies were released from 1970 through 1990 (Ref. I1).

Carbon-14 also is produced natumlly by the interactions of cosmic radiation with oxygen and nitrogen in the upper atmosphere. The worldwide inventory of natural C-14 is esumated at 241 million curies (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 rout %1y monitored in plant effluents.

I I

I I

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25

RADIOLOGICAL ENVIRONMENTAL MONITORING GPUN conducts a wmrJasive radiological envkuma momtoring program (REMP) to momtor radiation and radioactive matenals in the environment around the OCNGS. h information obtamed l from & REMP is then used to &moww the effect of OCNGS operations,-if any, on the environment and the public. ,

h USNRC has established regulatory guides which contam acceptable momtonng practices (Ref.12).

'Ihe OCNGS REMP was designed on the basis of these regulatoiy gui&s 'along with the USNRC Radiological Assessment Branch Technical Position on Enthuma Manitnring (Ref.13). The OCNGS REMP meets or exceeds all of these gnidalinac .

'Ihe objectives ofthe REMP are:

o to assess dose impacts to the public fran OCNGS operations o to verify in-plant controls for the contamment of radioactive matenals o to mostor any buildup oflong-lived radionuclides in the craironment and changes in background radiationlevels o

to provide reassurance to the public that the program is capable of %taly assessing impacts and identifying notewathy changes in the radiological status of the emironment o to fulfill the requirements of the OCNGS Offsite Dose calenUon Manual (ODCM) andTechnical Specifications

]Faviu-

1 Exnosure Pathways to Humans from Airborne and Liouid EfHuents As presiously discussed in the "EfBuents" section, small amounts cf radioactive matenals are released to the environment as a result ofoperatmg a nuclear generating station. 'Once relM these matenals move through the environment in a vanety of ways and may eventually reach humans via breathing, dnnking, eatmg, and direct exposure 'Ibese routes of wc are referred to as enviv_-..  : 1 exposure pathways. Figure 16 illustrates the important exposure routes.

26

\

(

Whde some pathways are relatively simple, such as ink i-+= of airborne' radioactive matenals, others may be complex. For example, ra&oactive airbome particulate may deposit onto forage, wiuch when eaten by cows, may be t- rm.mi into milk, which is suhe~-ntly u.smusi by man. This route of exposure is known as the air grass <:ow-milk-human pathway.

Although r=dinn-1we can reach humans by a number of pathways, some are more important than others The critical pathway for a given ra&onuclide is the one that produces the greatest dose to a pnpal dna or to a speedic segment of the population This segment of the pnp"I= don is known as tie entical 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. This infmii dion was used to develop the OCNGS REMP l

l l Samphna lhe OCNGS radiological emism ion.1 momtorirg program consists of two phases - the preoperational and the operatonal Data gathered in the preoperational phase were used as a basis for evaluating radiatinn levels and radioactivity in the sicinity of the plant after the plant became operational The j operational phase began in 1%9 when the OCNGS attamed initial criticality, i

I The program consists of taking radiation measurements and call ~*ing samples from the envirsome, '

analyzing them for rascactive content, and intopimag the results Emphasis is on the critical exposure pathways to humans with samples taken from the aquatic, atmospheric, and im>&ial ernironments These samples include air, well water, surface water, clams, =ediment. fish, crabs, vegetables and brnadleaf vegetation. Thermolummescent dosimeters (TLDs) are placed in the emironment to measure i gamma ra&ation levels. The ODCM Specifications, along with r+- u Mnne from GPUN scientists, l

! specify the sample types to be collected and analyses to be performed.

S hmpling locations werc +bmi by considenng meteorology, pmdwinn distribution, hydrology, and land use charactenstics of the local area. The sampling locations are divided into two classes, indicator and braly mnid. Indicator locations are those which are expected to show effects from OCNGS operations, if any exist. These locations were primarily selected on the basis of where the highest predicted emin==i=>ial concentrations would occur. While the indicator locations are typically within a few miles of the plant, the background stations are generally at dict =am greater than l'0 miles from the OCNGS. Therefore, background samples are collected at locations which are expected to be un=&**d 27

1 by station operatons They pnwide a basis for evaluatmg fluctuations at indicator lacatinas relative to natural background radioactivity and fallout from prior nuclear weapon tests. Figures 5,6, and 7 show the currcnt sampling lacatinac around the OCNGS. Table A-1 in Appendix A describes the $n= ling j lacarian_c by distance and azimuth (compass direction) from the OCNGS, along with type (s) of samples collected at each sampling location.

Anahsis In addrtion to specifying the nununum media to be enI!-tM and the nummum number of sampling lacatinnc. the ODCM Speci6 cations include the frequency of sample collection and the types and frequency of analyses to be pufwe. Also =pecineA are analytical sensitivities (detection limits) and reporting le.c. Table A-2 in Appendix A provides a synopsis of the sample types, number of sampling locations, collection frequencies, number of samples enHactaA types and frannencies of analyses, and number of samples analyzed. Table A-3 in Appendix A lists samples which were not collected or analyzed in accordance with the requi-,mb of the ODCM Specincatinne. Sample analyses which did not meet the required analytical sensitivities are presented in Appendix B. Changes in sample collection and analysis are described in Appendtx C.

l The analytical results are routmely reviewed by GPUN scientists to assure that established sensitivities l

have been achieved and that the proper analyses have been performed. All analytical results are subjected to an automated review process which ensures that ODCM-reqmred lower limits of detection are met and that reporting levels are not exceeded Investigations are ennAwaA when action levels or reporting levels l are reached or when anomalous values are discovered The 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 level is reached.

Analytical REMP sample results are presented in two tables in this report. Table 3 provides a enndenced summary of radionuclides concentrations detected in the primary envimoi-41 samples for 1997. This table provides a enadanced summary of only ODCM reqmred sample results and positive analytical results Table D-1 in Appendix D provides a tabular reporting of all analytical resuhs for samples collected in 1997. Both of these tables summanze the data in a format that closely resembles the l suggested format presented in the USNRC Branch Technical Position (Ref.13). Quality Assurance (QA) sample.results for split and/or duplicate samples weie used to serify the primary sample resuhs 1 The QA programis described below. 1 i

1 28 I I

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Fi re 5 l Oyster Creek Nuclear Generating Station (OCNGS)

Locations of Radielegical Envinumental Monitoring Pagram (REMP)

Stations within 1 mile of the site 29

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Oyster Creek Nuclear Generating Station (OCNGS) 14 cations ofRadiologicalEminumentalMonitoring Pngram(REMP)

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l

Measurement of low radionuclides concentrations in environmental media requires special analysis 1

technimia= Analytical laboratories use stateof-the-art laboratory equipment designed to detect beta and l gamma radiation. This equipment must meet the required analytical sensitivities. Examples of the piimi laboratory equipment used are germanium detectors with multichannel analyzers for.

identifying specific gamma enuttmg radionuclides, liquid scintillation detectors for Maning tritium, low i

level proportional counterr, for detecting gross beta radioactivity, and coincidence counters for low level

) .

I-131 Ma*= Computer hardware and software used in conjunction with the countmg equipment perform calculations and provide data iri uasmet. Analysis methods are described in Appendix J.

I

Ouahty Assurance Procram A Quahty Assurance (QA) program is c* tad in accordanz with miMines provided in Regulatory

. j Guide 4.15, " Quality Assurance for Radiodcal Monitoring Programs" (Ref.16) and as required by the l ODCM Specifications (Ref. 2) and Technic Specifications (Ref.1). The QA program is documented l

by GPUN written policies, procedures, and records. These hments enenmnass all aspects of the -

REMP including sample collection, equipment calibration, laboratory analysis, and data resiew.

The QA program is designed to identify possible deficiencies so that immediata corrective action can be taken if warrantal it also provides a measure of ennMence in the resuhs of the momtoring program in order to assure the regulatory agencies and the public that the results are salid. The Quahty Assurance program for the measurement of radioactivity in emironmental samples is implemented by-o auditing all REMP-related actisities including analytical laboratories o requinng analytical laboratories to participate in an NRC approved Emironmental Radioactivity Interwmparison Program o requinng analytical laboratories to split samples for separate analysis (recounts are l

performed when samples are not able to be split) I

~

o splittmg samples, having the samples analyzed by mdepenuent laboratories, and then comparing the resuhs for agreement o reviewing QA results of the analytical laboratories including spike and blank sample results and duplicate analysis results 32

The Quahty Assurance progen and the resuhs of the En6.- maal Rachoactisity hsig- . pdm Program are authned in Appendias E and F, respectively. .

L l The TLD readers are calibrated monthly against standard TLDs to within five percast of the standard TLD values Also, each group of1LDs processed by a reader contams control TLDs that are used to l correct for minor variations in the reader The accuracy and variability of the results for the control

' TLDs are exanuned for each group ofTLDs to assure the reader is functmaina properly.

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

Progen.

o Semiana'=Hy, i.udoirdy selected TLDs are sent to an mdependent laboratory where they are irradiattvi to set doses not known to GPUN. The GPUN dosimetry laboratory processes the TLDs and the results are o uparsi agamet actablielwi lirnits l

l o Every two years, each TLD is checked for response within 10 percent of a known value o Every two years, the GPUN dosunetry program is exrma and decertified by the NIST National Voluntary IAoratory Am utidion Program (NVLAP) l o Four OCNGS R.EMP TLD stations have collocated quahty assurance badges which are processed by an i% laboratory (Teledyne Brown Fp-+.ug). The results are unupersi against GP.U Nuclear Panasonic TLD resuhs t

The emironmental dosimeters were tested and quahfied to the specifications in the American National Standard Insatute's (ANSI) Publication N545-1975 and USNRC Regulatory Guide 4.13 (Ref.14 and 15). In addition to the OCNGS REMP, the Nuclear Regulatory Comnussion (NRC), and the New Jersey l

Department of Environmental Protecbon (NJDEP) also mamtam smveillance programs in the OCNGS area. These programs provide i% assessinents of rachoactive releases and the radiological impact on the surroundmg emironment. The resuhs from these programs have been consistent with the results from the OCNGS REMP.

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DIRECT RADIATION MONITORING Dose rates from extemal radiation sources were measured at a number oflocations in the sicinity of the OCNGS using thermo;uminescent dosimeters (TLDs). Naturally occurnng sources, including radiation of cosmic origin and natural radioactive materials in the air and ground, as well as fallout fmm prior nuclear weapon testmg, resulted in a certam amount of penetratmg radiation being recorded at all morutoring locations. Indicator TLDs were placcd system *imlly, with at least one station in each of 16 cardmal compass sectors (in a ring), typically within 0.25 miles of the OCNGS, or as close as reasonable highway access would pemut TLDs were also placed in each of the 16 sectors within a fhe mile radius of the OCNGS, located in areas where the potential for deposition of radioactive matenal was determmed b

to be high, in areas ofpublic interest, and population centers. Background locations were located greater than ten miles distant from the OCNGS and generally in an upwind direction.

S_a mple Collection and Anahsis A state-of-the-art thennoluw--w dosimeter is usa!. Hermolummescence is a process in which iomzmg radiation, upon interactmg with the sensitive matenal of the TLD (the phosphor or ' element')

causes some of the energy deposited in the phosphor to be stored in stable ' traps' in the TLD matenal Rese TLD traps are so stable that they do not decay appreciably over the course of years. His prosides an excellent method ofirnepalug the exposure received oser a period of time. The energy stored in the TLDs as a resuh ofinteractions with radiation is removed and measured by a controlled heatmg process in a calibrated readmg system. As the TLD is heated, the phosphor releases the stored energy as light.

The amount oflight given offis directly proportional to the radation dose the TLD received. He readmg process ' zeros' the TLD and prepares it for reuse.

He TLDs in use for environmental momtoring at the OCNGS are capable of accurately measuring exposures between 1 mrem (well below normal emironmental levels for the quarterly monitoring periods) and 1000 rem.

TLDs from 44 monitoring locations were exposed quarterly, from locations ranging from approumately 0.2 miles to 31.1 miles from the OCNGS, dunng 1997. Two Panasonic Model 814 TLDs were exposed at each location. One of these locations was designated as a quahty control station wlere two additional Model 814 badges were collocated As an additional quahty control measure, Teledyne Brown Fngimmng TLDs were also exposed at six stations. Panasonic Model 814 TLDs preside 4 independent detectors per badge and 8 detectors per station.

50

W =cheaded exposure penods for 1997 were:

Table 4 TLD EXPOSURE PERIODS DURING 1997 Start Date Collection Date 11 Nov 96 - 03 Feb 97 03 Feb 97 28 Apr 91 28 Apr 97 ' 28 Jul 97 28 Jul 97 27 Oct 97 27 Oct 97 19 Jan 98 All TLD dose rate data prme=*ed in this report have been run Li to elmunate dhTous.es caned by slightly ddfenng exposure penods All resnits were normahzed to a standard quarter (91.3 days). TLD dose rate data are preeenred in Tables K-1 and K-2 in Appeixhx K.

Results Ibe mean background dose ~W het mean irii.-W dose dunng 1997 suggestmg that the OCNGS had little if any effect on ofioite exposure The mean dose rate frorn irii. a# stations using Panasonic TLDs was 12.83 mrem / standard quarter with a range from 10.12 to 21.28 mrem / standard quarter (Table l K-1). The mean backgrourxl dose was 12.94 mrem / standard quarter with doses rangmg from 12.16 to 13.70 mrem / standard quarter. These results are consistent with the results of measurements from previous years (Fig. 8).

TaAr=*ar dose rates were higher than background dose rates at a few stations located withm several hundred feet of the OCNGS Turbme Bmiding close enough to be affected by direct radiation (Table K-1 u and Fig. 9). However, these higher doses were recorded at stations that were all located in the Owner Controlled Area, where public access is restricted or ci-. ;1-riy demed. In contrast, doses recorded at stations located at appivo.dy the same d>=tance from the OCNGS, where the public has unrestricted access (US Route 9), were less than those recorded at the background statmn< h mean dose recorded

- at stations akmg US Route 9, appiv=. uh 0.2 - 0.5 miles from the OCNGS.(Stations 61, 62, 63, 64, 65, and 66),' was 12.03 mrem / standard quarter cwupseed to a mean background dose of 12.94 mrem / standard quaner in =Mh. the maximum dose recorded at these indicator stanons was 13.14 mrem /arandard quarter while the highest recx>rded background dose was 13.70 mrem / standard quarter.  !

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These results suggest that OCNGS operatxxx contributed little ifany to off-site exposum Regarding Teledyne Brown Ergireog 'ILD data, the d'ose rate measured at indicator stations averagal 12.8 mrem / standard quarter and ranged frorn 10.1 to 15.4 mrem / standard quarter (Table K-2). The dose

! at background TLD stations averaged 13.1 mrem / standard quarter and ranged from 10.7 to 14.5.

mrem / standard quarter. The mean oose rate from the background stations wm higher than the mean dose I rate from the indicator stations, again 9png that OCNGS operation contributed little if any to off-site exposure.

i l

1 54

ATMOSPHERIC MONTFORING' A potential exposure pathway to man is the inhalation and ingestion of airborne radioactive matenals. Air was samplal by a network of seven contmuously operating air samplers and then analy2ed for radioactivity content.

Indicator air sampling stations are located in premiling downwind directions, local population areas, and

~

areas of public and specral interest. All indicator stations are located within 6.5 miles of the OCNGS. A background air sampling station is located 25 miles northwest of the OCNGS in Cookstown, NL Sample Collection and Analvsis 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 tempera *.::e u nys4 is used in line with the filters to record the volume of air sampled. Intemal vacuums are also measured in order to pressure correct the indicated volume. All air samplers are maintained and calibrated by the OCNGS Instmment and Control Department.

He particulate filters were collected every two weeks and analyzed for gross beta radioactivity. He filters were then combined quarterly by indisidual station locations and analyzed for gamma-enuttmg radionuclides.

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

Results ne results of the atmospheric monitoring dunng 1997 demonstrated that, as in presious years, the radioactive airbome effluents associated with the OCNGS did not have any measurable effects on the environment.

Dunng 1997,181 gross beta analyses were performed on air particulate filters (Tables 3 aM D-1). One l filter was lost prior to analysis (Apperxhx A-3). He background mean gross beta actisity (0.0154 pCi/m') was slightly higher than the indicator mean (0.0152 pCi/m') and all gross beta analysis results were within two standard deviations of the historical mean. A quahty control check ofindicator station 55

results showed that 175 of the 181 observations fell within established statistical controi Smits (Fig.10).

Six observations fell outside the 3-sigma limits, probably due to the effects of precipitation on the dust loadmg of the particulate filters. For example, with less ramfall, there is greater potential for an increased dust loawng on the particulate filters, which in tum could result in slightly higher gross beta concentrations. Conyctsely, larger amounts of ramfall at a particular sampling location could result in reduced dust Imang and lower gross beta emcentrations. He highest emcentration outside the control limits was from Station 72. His particulate filter was collected on October 6,1997 and had a gross beta result of 0.019 +/- 0.002 pCi/m' His result is within the historical mnge and only slightly higher (0.009 pCi/m') than the requued sensitivity for this analysis. A gamma isotopic analysis performed on this station's composite filters showed that only naturally occumng Be-7 was detected Companson of the 1997 bi-weekly mean air particulate gross beta concentrations from indicator and background stations shows that indicator and background concentrations were essentially' identical j (Fig.11). %ese results are consistent with the results ofgross beta analyses of air samples from previous years (Fig.12). De air particulate gross beta analysis results indicate that effluent matnining gross beta radioactivity from OCNGS operation did not have any measurable impact on the local emironment.

Gamma isotopic analyses were performed on 28 air particulate filter composites (Tables 3 and D-1). He only radionuclides identified was naturally occurring beryllium-7, which was seen in simdar concentrations at both indicator and background stations. Because Be-7 is a naturally occurnng nuclide, it can not be attributed to effluents from the OCNGS.

Air charcoal cartridges (362) were analyzed for iodine-131 (I-131) and no radiciodine was detected in any of the samples (Tables 3 and D-1). Two samples were lost due to air sampler malfunction (Appendix A-3).

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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 coolinn 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. 'Ihe 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 Chhdon Manual (ODCM) Specifications, Technical Specifications, and 10CFR20. Highly purified water, contauung trace levels of radioactivity, may be discharged into the OCNGS discharge canal, which routinely has a minimum flow mte of slightly under one-half million gallons per minute. Non-soutme radioactive liquid releases were made from the OCNGS dunng 1997 in which a total of 51,900 gallons of water containing approxunately 0.0105 curies.of actisity (tritium) was used to flush the on-site Fire Protection System and then released to the emironment Samples of surface water, sediment, fish, blue crab, and hard clams were routmely collected from locations in the OCNGS Discharge Canal, Bamegat Bay, and Great Bay /Little Egg Harbor in order to nxnitor any environmental impact that may be associated with liquid effluents from the OCNGS.

Samole Collection and Anahsis Surface water samples from two stations were collected monthly while an additional two stations were sampled on a senuannual basis. Sedunent and clam samples were also collected senuannually. Grab samples of surface water and # ment were collected from three indicator stations and one background station. Grab samples of clams were collected from two indicator and one background station. One indicator station for surface water and sediment is located in the OCNGS Discharge Canal - Oyster Creek; no clams are available for collection at this station. Two addinnnM indicator stations for surface water, sediment, and clams are located in Bamegat Bay in close proxmuty to the mouth of Oyster Creek. One background station is located approxunately 22 miles south of the OCNGS in Great Bay /Little Egg Harbor.

Fish samph were collected senuannually from two indicator stations and one background station.

One crab sample was collected during 1997 from an indicator station. Indicator stations for fish and l

1 crabs are located in the OCNGS discharge canal and the background station for fish is located in l l

l 60

Great Bay /Lrttle Egg Harbor. Crab pots were used to catch blue crabs. Traps, as well as the book and line technique, were used to catch fish.

Sediment, clams, fish, and crab samples were analyzed for gamma enutting nuclides and surface water was analyzed for tritium as well as gamma-enutting nuchdes Results Operation of the OCNGS had no detectahle effect upon the local surface water which was sampled 28 times at four differat W=ti== dunng 1997. One gamma-enutting nuclide, potassium-40 (K-40),

was detected in all 28 samples (Tables 3 and D-1). Potassium-40 is naturally oewog and commonly found in salt water at or above the observed concentrates No other radionuclides were detectedin surface water samples.

Five gamma-emitting nuclides were detected in the 8 sediment samples collected during 1997 (Tables 3 and D 1). Four of these radionuclides, beryllium-7'(Be-7), potassium-40, radium-226 (Ra-226), and thorium-232 (Th-232), are naturally occurring and were MMM at both background and indicator stations. Cesium-137 (Cs-137), which is a fission product, was also MMM 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 past years. The results of the sedunent sampling program indicate that the presence of cesium-137 in the =adimente of the OCNGS discharge canal and nearby portions of Barnegat Bay may be attributable in part to past liquid discharges from the facility.

A review of sedunent sample analysis results for the 1994-1997 period shows that cesium-137 was detected in 85 percent of background and only 62 percent ofindicator samples (Table 5).

However, cesium-137 concentrations detected at the two indicator stations (Stations 33 and 93),

which are closest to the OCNGS liquid discharge point, show concentrations higher than that found at background stations (Figure 13). During the four year period, the mean concentration of cesium-137 at background stations was 32 pCi/kg-dry, while the mean concentration at indicator Stations 33 and 93 was % pCi/kg-dry. In addition, the highest concentration of Cs-1 137 at an indicator station was 240 pCi/kg-dry, which was detected at Station 33 during March 1996. The highest concentration at background stations during the same four year period was 67 PCi/kg-dry.

61

l i

l l Table 5 l

Cesium-137 Concentration in Aquatic Sedunent .

l 1994 - 1997 (PCi/kg-dry) '

i Station Station Station Station Station Station Station Station

, Date 23 ~24- 25 31 32 33 93 94 t

Jan 94 26 22 <LLD 40 54 140 110 67 i

Apr 94 - <LLD 21 <LLD 49 45 150 67 ,

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1 1

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Aug 95- <LLD <LLD 9 13 32 60. 91 15 Oct 95 47 31 <LLD <LLD <LLD 51 120 27 Mar % <LLD <LLO <LLD 37 20 240 110 26 Jun % 32 21 11 23 <LLD 56 71 22 Aug % 16 <LLD <LLD 17 <LLD <LLD 100 24 Sep % <LLD <LLD 15 39 23 33 100 17 May 97 45 < LLD z :3, e ,, . ;

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- Stations 23,24,25,32, 33, and 93 are indicator stations

- Stations 31 and 94 are background stations

-LLD-Lower Limit ofDetection 62

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It is important to note that even the highest concentration of Cs-137 observed in sedanents (240 pCi/kg-dry) was only slightly above the Lower Limit of Detection spect6ed by the Nuclear Regulatory Commissim (180 pCi/kg-dry) and only 12 percent of the ODCM Reporting Level for Cs-137 in fish and broad leafvegetation (2,000 pCi/kg-wet).

Over the years, there has been a dramati c reduction in liquid discharges from the OCNGS and there have been no routme discharges of radioactist liquid wastes since 1989. As a result of this reduction in liquid efHuents, as well as the ongoing natural radioactive decay process, the level of Cs-137 in

. M. A contmues to decrease (Fig.13).

Cobalt-60 was not detected in either indicator or background station sedunent samples dunng 1997 (Tables 3 and D-1). The presence of cobalt-60 in sedunent samples in previous years has been attributed to past OCNGS liquid releases (Ref.19). Dunng the years 1994 through 1997, cobalt-60 was detected in 54 percent of sediment samples collected from indicator stations 33 and 93 (Table 6).

Both stations are located in the OCNGS discharge canal. Dunng the same time period, no Co-60 was detected at either of the background stations, Stanons 31 and 94, nor was it detected at any other

~ indicator station (Table 6). As documented in previous reports, OCNGS-related cobalt-60 activity had been found in sedanent and clams from Barnegat Bay since the mid 1970's. The amount of radioactivity in liquid effluents has been significantly reduced since that time and this decrease in the rate of input of cobalt-60 to the environment. combined with radioactive decay of the existing inventony, has resulted in a gradual dechne in the cobalt-60 concatration in sediment and clams (Figs.

14 and 15). The last detectable concentration of this radionuclides in clams was found during the third quarter of1987 (Fig.15).

No radionuclides attributable to efBuents from the OCNGS were found in samples of clams, fish and crabs collected during 1997 (Tables 3 and D-1).

i 64

~

i l

l l

l Table 6 l

l Cobalt-60 Concentration in Aquatic Seduneet l

l 1994-1997 l

l (PCi/kg-day) i 1

+l

, Statim Statim Station Station Station Station Station' Statim Date 23 24 25 31 32 33 93 94 Jan 94 <LLD <LLD <tLD <LLD <LLD 26 37 <LLD l 1 1 Apr 94 <LLD <LLD <LLD- <LLD <LLD 38 26 <LLD 1 Jul94 <LLD <LLD <LLD <LLD <LLD <LLD 22 <LLD l l

Nov 94 <LLD <LLD <LLD <LLD <LLD 44 27 <LLD l Mar 95 <LLD <LLD <LLD <LLD <LLD <LLD 18 <LLD May 95 <LLD <LLD <LLD <LLD <LLD 41 <LLD . <LLD Aug 95 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

! Oct 95 <LLD <LLD <LLD <LLD <LLD 14 20 <LLD Mar 96 <LLD <LLD <LLD <LLD <LLD 180 <LLD <LLD

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- Stations 23,24,25, 32,33, and 93 are indicator stations

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l 65 t

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Six clam samples were collected from tlace different locations dunng 1997. Gamma isotopic analyses indimtad that the only gamma-enuttmg nuclide present was potassium-40, which is naturally .

! occurnng and commonly found in salt. water (Fables 3 and D-1).

i Eleven fish samples, yielding seven species, were collected from 3 sampling locations dunng 1997.

J The species and number of samples collected air listed in Table 7.

TABLE 7 SPECIES OF FISH CAUGHT AS PART OF THE OCNGS REMP IN 1997 Fish Number of Samples striped bass 3 bluefish 2 tautog- 2 blowfish 1 l sea bass 1 l winter flounder 1 American eel Naturally occurring potassium-40 was the only radionuclides detected in fish samples collected during 1997 (Tables 3 and D-1).

One blue crab sample was collected from the OCNGS discharge canal dunng 1997. A gamma i isotopic analysis was performed on this sample and naturally occumng potassium-40 was the only l

radionuclides identified (Tables 3 and D-1). The close association of this species with sediments could make it susceptible to cesium-137 and cobalt-60 uptake. However, no detectable Cs-137 or Co-60 activity has been observed in blue crab samples since routine collection began in 1985.

l I

l l 68 ,

l L__________-_______________-_ ,

l l

l TERRESTRIAL MONITORING Radionuclides released to the atmosphere may be deposited on vegetation and may be incorporated into milk, vegetation, vegetables, and other food products. To assess the impact of dose to humans from this ingestion pathway, samples of green leafy vegetables and broadleaf l

vegetation were collected and analyzed during 1997.

He contra aion of radionuclides from OCNGS effluents to this ingestion pathway was assessed by comparing the results of samples collected at indicator stations in prevalent downwind locations, primarily to the southeast of the site, with background samples collected from distant and generally upwind directions. Indicator samples are collected at the two locations with the highest D/Q (deposition factor). These locations were identified using site-specific meteorological data. His technique is utilized in lieu of performmg any garden census, because it ensures that representative measurements of radioactivity in the highest potential exposure l pathways are obtained as required by Technical Specification 6.8.4.b.

In addition, a dairy census was conducted to determme the locations of commercial dairy operations and milk producing animals in each of the 16 meteorological sectors out to a distance l of five miles from the OCNGS. He census showed that there were no commercial dairy operations and no dairy ammals producing milk for human consumption within a 5 mile radius i of the plant (Appendix G).

l A vegetable garden was maintained near the site boundary of the OCNGS in the east-southeast l

! sector, which is one of the two sectors with the highest potential for radioactive deposition in accordance with the Offsite Dose Calculation Manual (Ref. 2). - This indicator garden was greater than 50 square meters (500 square feet) in size and produced green leafy vegetables.

l Broadleaf vegetation was collected in the southeast sector, which is the second sector in which the highest potential for radioactive deposition is predicted to occur. A commercial farm located approximately 24 miles northwest of the site was used as a background station.

b 69 1

i l t I C______.__ . _ _ _ . .__ _ ._

3 Samole Collection and Analy1is Vegetables, specifically cabbage and collards, and broadleaf vegetatien, specifically tree leaves, were collected on a monthly basis begmmng in July and endmg in November 1997. A gamma I

isotopic analysis was performed on each sample.

Results The results'of the terrestnal monitoring during 1997 demonstrated that the radioactive effluents associated with the OCNGS did not have any measurable effects on vegetation.

A gamma isotopic analysis was performed on eight collard samples, nine cabbage samples, and four bmadleaf vegetation samples (Tables 3 and D-1). Naturally occurring potassium-40 (K-

40) was detected in all of the samples collected from both indicator and background stations.

Beryllium-7 (Be-7), which is also naturally occurring, was identified in 5 of 5 collard samples and detected in 1 of 4 cabbage samples collected from the indicator garden. Beryllium-7 was also detected in 4 of 4 broadleaf vegetation samples collected from the indicator station.

Another naturally occurring nuclide, thorium-232 (Th-232) was detected in 3 of 4 broadleaf vegetation indicator samples. No other radionuclides were detected in vegetable or broadleaf vegetation samples. Of the radionuclides detected, all are naturally occurring, and none are associated with OCNGS operation.

70

GROUNDWATER MONITORING The Oyster Creek Nuclear Generating Station is located on the Atlantic Coastal Plain Physiographic Province. His 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 sedunen+s meet.

t At least five distinct bodies of fresh groundwater or aquifers exist in the vicinity of the OCNGS.

From the surface downward,they are:

1. Unconfined, Recent and Upper Cape May Formation
2. Confined, Lower Cape May Formation
3. Confined, Cohansey Sand
4. Confined, Upper Zone in the Kirkwood Formation
5. Confined, Lower Zone in the Kirkwood Formation -

The unconfined Recent and Cape May Formations are replenished directly by local precipitation.

The recharge to the confined aquifers occurs prunarily from direct rainfall penetration on the outcrop areas, which are generally to the west of the site at higher elevations.

Samole Collection and Analgis -

As part of the routine REMP, three groundwater wells were sampled on a quarterly basis. Grab samples were obtamed from two local Municipal Utility Authority wells and an on-site dnnkmg 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. He third sampling location is the 400' deep on-site well that supplies dnnkmg water to the OCNGS. Each sample was subjected to a tritium and gamma 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 and September of 1997. This network 71

is comprised of fifteen wells which are located in the Cape May, Cohansey and Kirkwood x Aquifers.. Grab ecmple methodology was used and the samples were also analyzed for tritium and gamma emitting nuclides.

?

Results

' The results of the groundwater monitoring during 1997 demonstrated that, as in previous years, the radioactive effluents associated with the OCNGS did not have any measurable effects on offsite groundwater quality.

Twelve routine REMP well water samples were collected during 1997. No radioactivity w3s detected in any of these samples (Tables 3 and D-1).

The results of the analyst of 30 samples collected from the onsite spill monitoring well network were simdar to results seen in past years (Table I-1). Only the naturally occurring radionuclides tritium, potassium-40, radium-226, and thorium-232 were WaA A tritium concentration of 170 pCi/ liter was detected at two well locations, Stations 3 and 7 in September 1997. These concentrations are historically typical for local groundw3ter samples.

Considering the very large environmental inventory of tritium due to cosmic ray interactions, it is highly unlikely that the tritium in the OCNGS' effluents could have a measurable effect on existing environmental concentrations. The maximum tritium level detected was 170 +/- 90 pCi/ liter, which is more than 11 times lower than the ODCM specified lower limit of detection (2000 pCi/ liter). In addition, this level is only 0.85 percent of the EPA drmkmg water limit of 20,000 pCi/ liter.

72

4 I

RADIOLOGICAL IMPACT OF OCNGS OPERATIONS An assessment of potential radiological impact indicated that radiation doses to the public from 1997 operations at the OCNGS were well below all applicable regulatory limits and were 1

i 'significantly less than doses received from common sources of radiation. He 1997 total body dose, potentially received by a hypothetical mammum exposed individual, from OCNGS liquid and airborne effluents, was conservatively calculated to be 2.7E-2 millirem total or only 1.1E-1 percent of the regulatory limit. He 1997 total body dose to the surroundmg population from OCNGS liquid and airborne effluents was calculated to be 5.0E-2 person-rem This is approximately 20 million times lower than the doses to the total population within a 50-mile radius of the OCNGS resulting from natural background sources.

Deternunation of F=Aation 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 radionuclides concentrations in the environment which may contribute to an internal dose of radiation. Thermoluminescent desimeters (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 deternune intend doses.

During wrmal plant operations the quantities of radionuclides released are typically too small to be measured once released to the offsite environment. 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 Effluent Emironmental Dosimetry System) and EFFECTS (Radioactive Effluent Filing, Evaluation and Comparison with Technical Specifications). Rese programs are based upon the OCNGS Offsite Dose Calculation Manual (ODCM). These models incorporate

. 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.

He type and amount of radioactivity released from the OCdGS is calculated using measurements from effluent radiation monitoring instruments and effluent sample analysis.

73

Once released, the dispersion of radionuclides in the environment is readily actimat~1 by

~

computer marialina Airbome releases are diluted and carried away from the site by atmospheric diffusion which continuously acts to disperse radioactivity. Variables which affect atmospheric dispersion include wind speed and direction, arma=pharic 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 Barnegat Bay estuary and Atlantic' Ocean ne pathways to human exposure are also included in the model. These pathways are depicted in Figure 16. The exposure pathways considered for the discharge of the station's liquid effluent are fish and shellfish consumption and shoreline exposure. He exposure pathways considered .

for airborne effluents include plume exposure, inhalation, vegetable consumption (during 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, meat ammals, and crop yields.

When detemunmg the dose to humans, it is necessary to consider all pathways and all exposed tissues (sumnung the dose from each) to provide the total dose for each organ as well as the total body from a given radionuclides in the environment. Dose calculations involve determuung the energy absorbed per unit mass in the various tissues. Thus, for radionuclides taken into the body, the metabolism of the radionuclides 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 grcups (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 individual

. is assumed to be affected by the combined maxunum environmental concentrations wherever they occur. For liquid releases at 'he OCNGS, the maxunum 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 74

FIGURE 16 EXPOSURE PATHWAYS FOR RADIONUCLIDES POTENTIALLY RELEASED FROM THE OCNGS l

l Gaseous Effluents l

Oyster Creek Station g w I 8- 5 o f" 3 $ $

L.iquid / $ g a Effluents pFF""g] fJ s' s' [

Raamd O h Direct y irradiation r

. +

/ \ > <

Consumption v

. O n e> n immersion . 66 (Boating / Swimming)

  • Shoreline Irradiation (Beach / Fishing)

Ingestion Seafood Consumption

~

J PREDOMINANT RADIONUCLIDES

%?,ist.1 " "'-

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![bk!*bh$'fdh!.

75

43 pounds of fish and shellfish. For airbome releases, the maumum hypothetical indisidual would live at the location of highest radionuclides concentration for inhalation and direct plume exposure while eating 1,389 pounds of vegetables per year. 'Diis location is 522 meters to the southeast based on historical meteorological air dispersion analysis (Ref. 2). The usage factors and other assumptions 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 effluents and the entire population using the Bamegat Bay estuary and Atlantic Ocean for liquid effluents.

Appendix H contains a more detailed discussion of the dose calculation methodology.

Results of Dose Calculations 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 human body (not including radon), averages about 100 mrem /yr. The natural background radiaticn from cosmic and ter*:strial 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 millirems 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 contnbute a vety 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. I8).

Results of the dose calculations are sununarized in Tables 8 and 9. Table 8 compares the calculated maximum dose to an individual of the public with the OCNGS ODCM Specifications, Technical Specifications,10CFR20.1301, and 10CFR50 Appendix I dose limits.

Table 9 presents the maximum total body radiation doses to the population within 50 miles of 76

the plant from airbome releases, and to the entire population using Bamegat Bay and the a Atlantic Ocean, for liquid releases.

These conservative calculations of the doses to members of the public from the OCNGS ranged from 0.0000011 percent to a maxunum of only 0.21 percent of the applicable regulatory limits.

l They are also considerably lower than the doses from natural background and fallout from prior nuclear weapon tests.

a, m

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\

l 77

TABLE 8 CALCUL'ATED MAX,IMUM HYPOTHETICAL DOSES TO AN INDIVIDUAL p ' FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM TIIE OCNGS FOR 1997 EFFLUENT REGULATORY LIMITS PERCENT OF RELEASED , CALCULATED DOSE REGULATORY mrem /YFAR SOURCE mrem / YEAR LIMIT UQUID 3 - TOTAL BODY ODCM SPEC 4.6.1.1.4 1.1E-7 3.7E-6 LIQUID 10- ANY ORGAN ODCM SPEC 4.6.1.1.4 1.1E-7 1.1E-6 AIRBORNE 100 - TOTAL BCDY 10CFR20.1301 2.7E-2 2.7E-2 (NOBLE GAS)

AIRBORNE 3000 - SKIN ODCM SPEC 4.6.1.1.5 2.7E-2 9.0E-4 (NOBLE GAS)

AIRBORNE 15 - ANY ORGAN ODCM SPEL 4.6.1.1.7 3.lE-2 2.lE-1 (IODINE AND PARTICULARS)

TOTAL-UQUID 25 -TOTAL BODY ODCM SPEC 4.6.1.1.8 2.7E-2 1.1E-1 ANDAIRBORNE TOTAL -UQUID 75 -HIYROID ODCM SPEC 4.6.1.1.8 3.lE-2 4.lE-2 AND AIRBORNE TOTAL -UQUID 25 - ANY OTHER ODCM SPEC 4.6.1.1.8 2.7E-2 1.1E-1 AND AIRBORNE ORGAN f

78

)

r l

l TABLE 9 CALCULATED MAXIMUM TOTAL RADIATION DOSES TO THE  !

POPULATION FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM THE OCNGS FOR 1997 l

i l

l Calculated Population I Total Body Dose Person-rem / Year - I I

1 From Radionuclides in Liquid Releases 1.2E-5  ;

(Barnegat Bay and Atlantic Ocean Users) l l

From Radionuclides in Airbome Releases 5.0E-2 l (Within 50-Mile Radius of OCNGS) i l DOSE DUE TO NATURAL BACKGROUND RADIATION 1

Approximately 990,000 Person-rem Per Year i

I -

l i

I I

r 79 I

l l j 1

l-i

. REFERENCES (1) Jersey Central Power and Light Company. Oyster Creek Nuclear Generating Station Operating License and Technical Specifications, Appendix A, DPR-16, April 1969.

l (2) GPU N'uclear Corporation. Oyster Creek Offsite Dose Calculation Manual, Procedure 2000-ADM-4532.04. l 1

j (3) GPU Nuclear Corporation. Oyster Creek Nuclear Generating Station, Updated Final Safety Analysis Report.

l (4) National Council on Radiation Protection and Measurements, Report No. 93, Ionmng Radirtion Exposure of the Population of the United States,1987.

(5) CRC Handbook, Radioecology: Nuclear Energy and the Environment, F. Ward Whicker l and Vincent Schultz, Volume I,1982. l l

i j (6) National Council on Radiation Protection and Measurements, Report No. 22, Maximum Permissible Body Burdens and Maxunum Permissible Concentrations of Radionuclides l' in Air and Water for ' Occupational Exposure, (Published as National Bureau of l Standards Handbook 69, Issued June 1959, supersedmg Handbook 52). j l (7) Intemational Commission on Radiological Protection, Publication 2, Report of

( Committee II on Permissible Dose for Internal Radiation (1959), with 1962 Supplement Issued in ICRP Publication 6; Publication 9, Reccaroner4ations on Radiation Exposure,

~

(1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 9 concermng 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.

i 80 L_ _ _ . _ . . _- _ _ ._ _ _ _ _ _ . . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ ___

i.

(10) National Council on Radiation Protection and Measurements, Report No. 62, Tritium in the Environment, March 1979.

l (11) National Council on Radiation Protection and Measurements, Report No. 81, Carbon-14 i in the Environment, May 1985.

l (12) United States Nuclear Regulatory Commission. Regulatory Guide 4.1, Programs for i

Monitoring Radioactivity in The Environs of Nuclear Power Plants, Resision 1, April 1975.

l (13) United States Nucleai Regulatory Commission Branch Technical Position, An Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

l (14) America National Standards Institute, Inc., Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry, ANSI N545-1975.

l (15) United States Nuclear Regulatory Commission. Regulatory Guide 4.13, Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry:

Environmental Applications, Revision 1, July 1977.

(16) United States Nuclear Regulatory Commission. Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams a.s the Emironment, Revision 1, Febmary 1979.

(17) United States Nuclear Regulatory Commission. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision I, 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 .

Transport and Accumulation Patterns in Barnegat Bay, New Jersey and Adjacent Shelf Waters. Estuarine and Coastal Marine Science (1980) 10,119-142.

81

(20) GPU Nuclear Corporation.1986 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generatmg Station. May 1987.

(21) GPU Nuclear Corporation.1987 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station. Mry 1988.

l (22) GPU Nuclear Corporation.1988 Radiological Environmental Monitoring Repon for Oyster Creek Nuclear Generatmg Station. May 1989.

(23) GPU Nuclear Corporation.1989 Radiological Environmental Monitoring Repon for Oyster Creek Nuclear Generatmg Station. May 1990.

(24) GPU Nuclear Corporation.1990 Radiological Environmental Monitoring Repon 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) G,PU Nuclear Corporation.1992 Radiological Environmental Monitoring Repon for Oyster Creek Nuclear Generating Station. May 1993. -

(27) GPU Nuclear Corporation.1993 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1994.

(28) GPU Nuclear Corporation.1994 Radiological Environmental Monitoring Report for

- Oyster Creek Nuclear Generating Station. May 1995.

(29) GPU Nuclear Corporation.1995 Radiological Environmental Monitoring Repon for Oyster Creek Nuclear Generatmg Station. May 1996.

l l (30) GPU Nuclear, Inc.1996 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generatmg Station. May 1997.

(31) GPU Nuclear, Inc. Oyster Creek Nuclear Generating Station EfBuent and Offsite Dose Report. January 1,1997 through December 31,1997.

82

I I

APPENDIX A 1997 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Samp'dng and Analysis Exceptions I

83 l

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l TABLE A-2 SYNOPSIS OF THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR THE OYSTER CREEK NUCLEAR GENERATING STATION 1997 (1)

SAMPLE TYPE NUMBER OF COLLECTION NUMBER OF TYPE OF ANALYSIS NUMBER OF SAMPLING FREQUENCY ' SAMPLES ANALYSIS FREQUENCY SAMPLES LOCATIONS COLLECTED ANALYZED (2)

@ Particulate 7 Bi-weekly 182 Gross Beta Bi-weekly 181(3)

Gamma Quarterlycomposite 28 iIodine 7 Weekly 362 1-131 Weekly 362(3) yellWater 3 Quarterly 12 Gamma Quarterly '12 H-3 Quarterly 12 urface Water 4 2 locations-Monthly 28 Gamma Monthly 28

. 4 locations - Semi- ,

H-3 (2 Stations) 28 Annually Semiannually (4 Stations) lam 3 Semiannually 6 Gamma Semiannually 6 ediment 4 Semiannually 8 Gamma Semiannually 8 7egetables 2 Monthly (4) 17 Gamma Monthly (4) 17 lroadleaf 1 Monthly (4) 4 Gamma Monthly (4) 4 7egetation ssh 3 Semiannually 11 Gamma Semiannually 11 rab I Annually i Gamma Annually 1 LD-Ttledyne 4 Quarterly 22 Inunersion Dose Quarterly 22 usun Engincedng LD-Panasonic 44 Quarterly 201 Immersion Dose Quarterly 201

.JJ) This table does not include Quality Assurance (QA) samples.

8) The number of samples analyzed does not include duplicate analyses, recounts, or reanalyses.

?) See Ttble A-3.

Q) Collected during harvest season only.

4 e

90

TABLE A-3 ,

i 1997 SAMPLING AND A]i4 LYSIS EXCEPTIONS' -

j During 1997, 631 samples were collected from aquatic, atmospheric, and terrestrial

! environments around the OCNGS. This is far more than the muumum number of samples required by the Offsite Dose Calculation Manual (ODCM) Specifications. There were sampling l

and analysis exceptions tha' occurred in 1997 that resulted in minor deviations from the requirements of the ODCM, These deviations did not compromise GPUN's ability to assess the

impact of the OCNGS on public health or the environment because the scope of the monitoring t

program exceeds the ODCM requirements The ciresastances surrounding these events are described below.

l l

An air particulate sample collected from Station 72 on June 3,1997 was lost. This sample was L believed to be shipped along with six other air particulate filters and seven air iodine filters to the Environmental Radioactivity Laboratory, Harrisburg, Pa. for analysis. After receipt and processing of all filters by the lab, OCNGS was notified that the air particulate filter from Station 72 was never received, even though the envelope that the filter was enclosed in during the l

. sampling and shipping process was received. Further investigation revealed that the lab

technician responsible for processing this batch of samples could not remember whether this l
sampls was received or not. Although not definitively deternuned how the sample was lost, it is
believed that this filter was received by the lab and lost while in their possession. Station 72 is -

l b

! an ODCM required station. Air particulate gross beta results from six other air samples  !

collected during the same period were background. In addition, the gamma isotopic quarterly

- composite results from this station, as well as the six other stations, were background. Prior to l this event, approximately 4750 air particulate samples were received, processQ atxi analyzed by l

the Environmental Radioactivity Laboratory without ever losing a sample. The probability of l recurrence is considered extremely low.

l The air sampler at Station 72 failed due to a blown fuse on June 3,1997, after 4.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of operation. Only 17.5 cubic meters of air passed through the air iodine filter. Because of the low volume collected, no analysis was performed on this air iodine cartridge. Station 72 is an ODCM required sampling locatiors. Air samplers at five other indicator statious and one background station continued to operate during this period. Analysis results on the six air iodine L

91 l

samples from these stations were all less than the lower limit of detection. In addition, the quarterly air particulate fdter composite analysis performed on all filters for this period, which included the air particulate filter from Station 72, showed only background levels of  ;

radioactivity.

l The air sampler at Station 3 failed on October 6,1997 due to a blown fuse. The sampler ran for l only I hour after the filter change and drew only 4.9 cubic meters of air. The air iodine filter l-i l

mstalled in this station was therefore not analyzed. His is not an ODCM required sampling l location. The analytical re-dts fwm the other six operatmg stations during this period were background.

l

. On October 14,1997, air sa.nplers at Stations 72 and 73 were inadvertently not restarted after Instrument and Control Technicians finished performmg a calibration check. The samplers remamed off until the next filter change which occurred on October 21,1997. Both of these stations are required by the ODCM specifications. Air iodine samples, collected prior to sampler shutdown, were collected, analyzed, and all results were below the ODCM specified lower limits of detection. Two samplers at indicator stations not required by the ODCM continued to operate during this period. Analytical results from all operating stations during the six day period were ,

less than the lower limit of detection. A procedure change was implemented which will prevent recurrence of this event.

l ,

The air sampler at Station C failed on October 14,1997 due to pump failure. The sampler ran I

t for 20.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to failure. Station C is the ODCM required background station. His station was restarted by Instrument and Control Technicians on October 22,1997. The sample collected prior to sampler failure was analyzed and the result was less then the required lower limit of detection.

l 92 1

L-___ __

)

l i

l APPENDIX B 1997 Lower Limits of Detection (LLD) Exceptions 93

/

TABLE B-1 1997 LOWER LIMITS OF DETECTION (LLD) EXCEPTIONS During 1997, there were no' Lower Limit of Detection (LLD) violations on any analyzed REMP Sample t

94

t 1 l \

! i i

J l

l APPENDIX C Changes to the REMP During 1997 1

1 l

95

~* - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ , _ _ _ _

TABLE C-1 Channes to the REMP During 1997 '

A comprehensive self-assessment of the Radiological Environmental Monitoring Program (REMP) was .

j performed during 1996. The purpose of the self-sissessment was to evaluate the need to modify the REMP, which has been largely -h=ged since 1987, based upon the following factors:

1) The radioactive effluent history for the Oyster Creek Nuclear Generating Station (OCNGS)
2) The results of more than 28 years of radiological environmental monitoring associated with )

the OCNGS ,

3) The status of independent radiological environmental monitoring performed by regulatory agencies
4) Cost-benefit considerations The quantity of radioactive effluents released from the OCNGS has significantly declined'since the first l decade of plant operation. Gaseous effluents were reduced by approximately two orders of magnitude . j as a result of the addition of the Augmented Off-gas (AOG) Treatment System in 1980. As the reliability of that system improved, the quantity of gaseous effluents generally ~ continued to decline through the 1980's and 1990's. Routine liquid radioactive effluent releases were ternunated in 1989, .

1 resulting in another significant reduction in the quantity of radionuclides released to the environment  ;

As a result of these effluent minmuzation measures, the quantity of radioactive effluents. from the OCNGS has been reduced to a minute fraction of the regulatory limits. l l

GPU Nuclear's radioactive effluent reduction measures, in conjunction with the radioactive decay of previously released radionuclides, have led to a.significant decline in the levels of plant specific radionuclides observed in the environment. Historically, the only measurable impacts of OCNGS effluents on the emironment have been the accumulation of low levels of cobalt-60 in sedunents and clams, and low levels of cesium-137 in sediments and fish, from Barnegat Bay and contiguous streams.

Cobalt-60 was not detected in sedunent samples during 1997 and has not been detected in clams since 1987. 'Ibe maximuth levels of cesium-137 in sedunents are well below the Lower Limits of Detection (LLD's) specified by the USNRC. Concentrations of cesium-137 in fish are only slightly higher than the LLD's and similar to the levels of this radionuclides observed in fish throughout the world as a result offallout.

96

l h New' Jersey Bureau of . Nuclear Engineering (BNE) performs independent radiological environmental monitoring around the OCNGS, including the monitoring of surface water, sediment,  ;

, clams, vegetables, air and direct radiation monitoring utilizing TLDs. During the 1990's, the BNE also '

completed the mstallation of a network of continuous radiation monitors around the OCNGS. The )

network consists of 19 pressurized ionintion chambers in a ring around the OCNGS, typically located within one mile of the Station, with some monitors as far away as 2.7 miles. These monitors are f . extremely sensitive, capable of measuring gamma radiation in units of microroentgens per hour. The -

! continuous radiation readmgs are transmitted on a real-time basis to the BNE's offices in Trenton, New Jersey and to GPUN's Environmental Affairs Department at the OCNGS. Continuous air sampling devices are also installed at each of the BNE monitoring locations. These air samplers can be remotely j activated from the BNE offices. l The significant' reduction in the quantity of radioactive effluents released from the OCNGS and the associated reduction in the levels of plant specific radionuclides in the environment, combined with the increase in the amount of independent monitoring performed by the BNE, provided the basis for

! implementing a number of changes in the REMP during 1997. These changes have not compromised GPUN's ability to assess the impact of the OCNGS on public heal,th or the environment and in all j cases, the revised program meets or exceeds the requirements specified in the Offsite Dose Calculation l Manual (ODCM). The program changes are discussed in detail below:

l January,1997 The results of more than 28 years of continuous air monitoring have unequivocally demonstrated that radioactive effluents from'the OCNGS have no impact on air quality. These measurements included periods when the quantity of radioactive effluents was significantly greater than the amounts l released in recent years. Based upon these results, and the increase in the air monitoring capability of the BNE, six' air sampling stations were elimmated from the REMP. Air particulate and air iodine sampling Stations 1,4,5, A, H, and 14 were eliminated. The indicator stations (1,4 and 5) were located in low D/Q sectors and outside of population areas. Stations 14, A, and H were redundant background stations. The remaining program not only includes the ODCM required stations (Stations 66, 71, 72, 73, and 'C), but also two additional indicator air sampling stations (3 and 20).

97

t i

January,1997 . A tritium analysis was added to tlie surface water monitoring program Prior to this addition, only a gamma isotopic analysis was being performed on each j i

sample. The program change improves the ability to assess the environmental j

impact ofefBuents from the OCNGS.

February,1997 Four Panasonic model 801 TLDs were replaced with two Panasonic model 814 TLDs at each TLD station. Model 814 badges contain three calcium sulfate elements, whereas model 801 badges contain two calcium sulfate elements.

February,1997 Changes were made to the TLD monitoring locations. Three new quarterly stations were established and 25 quarterly stations were eliminated. Ten annual TLD stations were added to the program These stations, although not

~

part of routine REMP, were added to provide' additional direct radiation monitoring capability in the unlikely event of an unanticipated release from the OCNGS.

Quarterly stations 68,98, and 99 were established and collocated with TLDs

. from the NRC network. Station 68 was located in the western sector at a distance of 1.2 miles from the OCNGS. Station 98 was established in the WNW sector at a distance of 1.3 miles and Station 99 was located in the NW sector at a distance of 1.5 miles. Station 55 was relocated in the western sector, being moved from 1.5 miles to 0.3 miles from the OCNGS. In addition, Station 56 was relocated in the WSW sector, being moved from 1.1 miles to 0.3 miles from the OCNGS. Stations 4, 5, 7, 14, 15, 16, 17, 20, 60, 67, 69, 70,76,77, 80, 87, H, RA, RC, RD, RF, RG, RH, RI, and RJ were elimmated.

These stations were eliminat~1 because some were not located in high D/Q sectors, some were not located in a population area or in an area of public ,

interest, and some were located too closely to other stations. The ODCM requires 32 quarterly TLD monitoring stations around the OCNGS. The revised program includes 44 quarterly monitoring stations as well as 10 annual stations.

March,1997 As discussed above, the concentration of plant specific radionuclides in aquatic sedunent have dropped below the LLD's specified in the ODCM as a result of 98 L .. _ . . . _ _ ._ _ . _ . _ -_ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _______ _

l t

l l

L the temunation of routine liquid radioactive effluent releases in 1989. Based I l

upon these results, three redundant indicator stations for aiuatic l sediment and '

l surface water sampling (25, 32, and 93) were elimmated. None of these stations were required by.the ODCM. Indicator Stations 32 and 93 were elimmated because they were located within several hundred feet of Station 24 (mouth of Oyster Creek) and 33 (US Route 9 Bridge over the Discharge Canal) which provide sufficient monitoring of the Discharge Canal Indicator station 25 was located south of the mouth of Oyster Creek in Barnegat Bay. Adequate monitoring is provided by Station 33 and Station 24, which is located 200 yards southeast of the mouth of the OCNGS Discharge Canal.

Station 31 was established as a background station, but in fact was found to be within the influence of past liquid discharges (Ref 19). This station was therefore elimmated and Station 94, located approximately 22 miles south of Oyster Creek in Great Bay /Little Egg Harbor, serves as the background

' station. The revised program includes two additional stations not required by j the ODCM (Stations 23 and 24).

March,1997 The fregirency of sample collection for surface water at Stations 23 and 24 and all aquatic sediment collcaion was changed from quarterly to semiannually.

Surface water samples at Stations 33 and 94 will continue to be collected on a monthly basis. The revised program continues to exceed the requirements of the ODCM.

In order to improve our ebility to monitor any unanticipated liquid releases from the OCNGS, a surface water composite sampler was installed in the l Discharge Canal,just downstream of the Station's discharge points. Although t

presently not part of the routine REMP, weekly composite samples will proside a much more frequent indication of effluent water quality.

March,1997 As discussed above, plant specific radionuclides have not been detected in clams for approximately 11 years, and routine liquid radioactive effluent releases were terminated in 1989. Based upon these facts, two redundant clam sampling stations (25 and 31) were elinunated. Indicator Station 25 was l 99 w_____-_____-___-__-___-________ . _ - _ - _ _ _ _ . . _ .

l i 1

l 1

l located just south of the mouth of Oyster Creek in Barnegat Bay in close proximity to indicator Station 24. Station 24 is located in Barnegat Bay, just off the mouth of Oyster Creek, which is the best location for monitoring any accumulation of effluent related radionuclides. Station 31 was originally l established as a background station, but was found to be within the influence of i

i past liquid discharges (Ref 19). This station was therefore elimia*d and Station 94, approxunately 22 miles south of Oyster Creek, in Great Bay /Little Egg Harbor, serves as the background station. The revised clam collection program contmues to exceed the requirements of the ODCM.

March,1997 He frequency of collection of clams was changed from quarterly to l  ;

senuannually. He basis for this change is that no OCNGS related  ;

I radioactivity has been detected in clams since 1987 and routine liquid effluent

! releases were termmated in 1989. In' addition, the only plant specific radionuclides ever detected in clams is cobalt-60, wiiich has a half-life of 5.26 l l I

years. A semi-annual sampling frequency will be more than sufficient to )

l '

! monitor any accumulation of radionuclides in clams. The clam collection i program continues to exceed the ODCM requirements.

l March,1997 Crab sampling at one indicato station (93) and a background station (94) was elimmated. The crab collection cod analysis program began in 1985 and since j that time,150 samples were collected and analyzed. Here has never been any OCNGS related radioactivity detected in any of these samples. Based upon 1 this record, Stations 93 and 94 were elimmated and collection of crabs froin .

1 l Station 33, in the OCNGS Discharge Canal, was changed from quarterly (when available) to annually. He crab collection program continues to exceed the requirements of the ODCM which does not call for any crab sampling..

March,1997 Given that the maximum cesium-137 concentrations in fish are only slightly higher than the LLD's specified in the ODCM and that routine liquid effluent releases were termmated in 1989, the frequency of fish sampling was changed from quarterly to semiannually. The revised fish sampling program continues to exceed the requirements of the ODCM.

-100 9

_ _ _ _ _ _ _ _ _ _ _ _ . - _ - .__:_.________,__._-___..,__- _ . _ _ . _ .- . . - . . _ _ _ . . _ _ . _ _ _ _ . _ . . _ . _ - . _.________.__________m_____._____ _ -__

June,1997 The vegetable garden at Station 66 was eliminated and replaced with wild broadleaf vegetation sampling from the same location. Any deposition of radioactive effluents will continue to be measured at this station as required by f

the ODCM.

September,1997 TLD Station 53 was moved approxunately 100 feet closer to the OCNGS because the building to 0hich it was attached was demolished. The station l ' azimuth of 310 degrees remams the same.

l e

101

l l

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l APPENDIX D Radionuclides Concentrations in 1997 Environmental Samples J

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