ML20206D741
| ML20206D741 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1998 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1940-99-20226, NUDOCS 9905040226 | |
| Download: ML20206D741 (147) | |
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{ GPU Nuclear,Inc.
( U.S. Route #9 South NUCLEAR Post Office Box 388 Forked River, NJ 087310388 l
l Tel 609-9714000 4 April 30,1999 1940-99-20226 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D C 20555
Dear Sir:
l Subject- Oyster Creek Nuclear Generating Station 1 Docket No. 50-219 :-
Oyster Creek Radiological Environmental Monitoring (REMP) Report - 1998 L i
I Enclosed is a copy of the Oyster Creek REMP Report for 1998. This submittal is made in l accordance with Technical Specification 6.9.1.e.
Ifyou should have any questions or require further information, please contact Brenda DeMerchant, OC Regulatory Affairs Engineer, at 609-971-4642.
Very truly yours, b
Nkichael B. Roche Vice President and Director Oyster Creek i
MBR/BDE/gl ' /.
Enclosure cc: Administrator, Region I f
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NRC Project Manager NRC Sr. Resident Inspector /{@
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OYSTER CREEK NUCLEAR GENERATING STATION Forkeci River, New Jersey he 650 MW plant is a single-unit, bines, a generator and an exciter. The turbines five-loop General Electric Boiling and generator turn at 1,800 revolutions per T Townships of Ocean County. Lo-Water Reactor (BWR). The site, about 800 acres, is in Lacey and Ocean minute to generate three-phase,60-cycle elec-tricity at 24,000 volts. The electricity generated is provided to the grid by two transformers cated approximately nine miles south of Toms which boost the voltage to 230,000 volts.
River, it is about 50 miles east of Philadelphta, Steam is supplied to the high-pressure tur-and 60 miles south of Newark. bine from the reactor. After being used to drive Construction began in December 1%3. the turbines and generator, the steam is (on-The station began commercial operation on densed in the main condensers and returned to December 23,1969, and at that time was the the reactor vessel in the form of water through largest nuclear facility in the United States the condensate and feedwater pumps.
solely financed by a private company. The main condensers consist of three hori-The Reactor Building, Turbine Building and zontal, single pass, divided water hoses con-Ventilation Stack are the most prominent struc- talning 44,000 tubes having a total length of tures at the site. The Reactor Building stands about 1,875,000 feet. Cooling water is pro-approximately 150 feet high with 42 feet ex- vided from Barnegat Bay, through the South tending below grade. The Reactor Building Branch of the Forked River and passes through serves as a secondary containment and houses the condensers and discharges into Oyster the primary containment (drywell), the reactor Creek for return to Barnegat Bay. The water is vessel and its auxillary systems which comprise pumped by four 1,000-horsepower pumps, the Nuclear Steam Supply System. The drywell, each of which moves abut 115,000 gallons per which houses the reactor vessel, is constructed minute through the 6-foot-diameter pipes that of high-density reinforced concrete with an in- feed the condensers.
ner steel liner measuring 120 feet high and The ventilation stack is 368 feet high with 70 feet in diameter. 26 feet extending below grade. The stack pro- g The reactor vessel is 63 feet high and 18 vides ventilation for the Reactor Building, E feet in diameter. The 652-ton reactor contains Turbine Building and Radwaste facilities.
560 fuel assemblies, each with 62 fuel rods that Oyster Creek is owned by jersey Central are 12 feet long, and 137 control rods. The Power & Light (JCP&L) Company and operated reactor operates at a nominal pressure of by GPU Nuclear (GPUN) Corporation. JCP&L I,020 pounds per square inch and an average and GPUN are units of the GPU System.
temperature of 540 degrees Fahrenheit.
The Turbine Building houses the turbine- g generator, control room main condensers, g power conversion equipment and auxiliary sys- _
tems. The turbine-generator consists of one high-pressure turbine, three low-pressure tur- A GPU COMPANY l
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OYSTER CREEK NHCLEAR GENERATING STATION Forked River, New Jersey l he 650 MW plant is a single-unit, blnes, a generator and an exciter. The turbines five-loop General Electric Bolling and generator turn at 1,800 revolutions per T Townships of Ocean County. Water Reactor (BWR). The site, about 800 acres,is in Lacey and Ocean minute tc generate three-phase,60-cycle elec-tricity at 24,000 volts. The electricity generated is provided to the grid by two transformers cated approximately ,dne miles south of Toms which boost the voltage to 230,000 volts. River, it is about 50 m'ies east of Philadelphia, Steam is supplied to the high-pressure tur-and 60 miles south o' Newark, bine from the reactor. After being used to drive g Construction began in December 1%3. the turbines and generator, the steam is con- 3 Re station began commercial operation on densed in the main condensers and returned to December 23,1%9, and at that time was the the reactor vessel in the form of water through largest nuclear facility in the United States the condensate and feedwater pumps. solely financed by a private company. The main condensers consist of three hori-The Reactor Building, Turbine Building and zontal, single pass, divided water hoses con-Ventilation Stack are the most prominent struc- talning 44,000 tubes having a total length of tures at the site. Re Reactor Building stands about 1,875,000 feet. Cooling water is pro-approximately 150 feet high with 42 feet ex- vided from Barnegat Bay, through the South tending below grade. The Reactor Building Branch of the Forked River and passes through serves as a secondary containment and houses the condensers and discharges into Oyster the primary containment (drywell), the reactor Creek for return to Barnegat Bay. Re water is vessel and its auxiliary systems which comprise pumped by four 1,000-horsepower pumps. I the Nuclear Steam Supply System. The drywell, each of which moves abut 115,000 gallons per j which houses the reactor vessel, is constructed minute through the 6-foot-diameter pipes that j of high-density reinforced concrete with an in- feed the condensers, ner steel liner measuring 120 feet high and he ventilation stack is 368 feet high with 70 feet in diameter. 26 feet extending below grade. Re stack pro-The reactor vessel is 63 feet high and 18 vides ventilation for the Reactor Building, feet in diameter. The 652-ton reactor contains Turbine Building and Radwaste facilities. i 560 fuel assemblies, each with 62 fuel rods that Oyster Creek is owned by Jersey Central Power & Light (JCP&L) Company and operated b are 12 feet long, and 137 control rods. The 3 reactor operates at a nominal pressure of by GPU Nuclear (GPUN) Corporation. JCP&L 1,020 pounds per square inch and an average and GPUN are units of the GPU System. temperature of 540 degrees Fahrenheit. The Turbine Building houses the turbine- E E generator, control room main condensers, g b g power conversion equipment and auxillary sys- E tems. The turbine-generator consists of one high-pressure turbine, three low-pressure tur- A GPU COMPANY s-A
sf , I I . I I I I 1998 RADIOIDCICAL ENv!RoNuortAL MomToRINc REPORT PRUARED By OYSTER CREEx E.muoNuzNTAL AFFAIRS GPU NLt1 EAR CORIORATION e L ~
I . I TABLE OF CONTENTS PAGE TABLE OF CONTENTS i LIST OF TABLES 111 I LIST OF FIGURES ' y
SUMMARY
AND CONCLUSIONS 1 INTRODUCTION 3 Characteristics ofRadiation 3 'l Sources of Radiation 4 g NuclearRector Operations 7 Sources of Liquid and Airborne Emments 9 I. DESCRIPTION OF THE OYSTER CREEK NUCLEAR GENERATING STATION SITE 11 GeneralInfonnation 11 Climatological Summary 11 EFFLUENTS 18 I Historical Background Emuent Release Ilmits Effluent ContalProgram 18 18 21 Emuent Data 22 RADIOIAGICAL ENVIRONMENTAL MONITORING 26 Environmental Exposure Pathways to Humans from Airbome and Liquid Emuents 26 Sampling 27 Analysis 28 Quality Assurance Program 31 DIRECT RADIATION MONITORING 33 Sample Collection and Analysis 33 .I Results 34 ATMOSPHERIC MONITORING 38 Sample Collection and Analysis 38 Results 38 AQUATIC MONITORING 43 Sample Collection and Analysis 43 Results 44 I I f
E I i TABLE OF CONTENTS (Continued) l PAGE ! TERRESTRIALMONITORING 52 l I Sample Collection and Analysis Results 52 53 GROUNDWATER MONITORING 54 Sample Collection and Analysis 54 Results 55 RADIOLOGICAI. IMPACT OF OCNGS OPERATIONS 57 Detennination of Radiation Doses to the Public 57 Results ofDose Calculations I 60 REFERENCES 64 APPENDIX A: I 1998 REMP SamplingImcations and Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions 67 APPENDIX B: I APPEND 1X C: 1998 Lower 1Jmits of Detection (LID) Exceptions Changes to the 1998 REMP 74 76 APPENDIX D: Radionuclide Concentrations in 1998 EnvironmentalSamples 78 APPENDIX E: 1998 Quality Assurance Results 105 APPENDIX F: 1998 EnvironmentalRadioactivity Interlaboratory Comparison Results 111 APPENDIX G: 1998 AnnualDairy Census 122 APPENDIX H: Dose Calculation Methodology 124 APPENDIXI: 1998 Groundwater Monitoring Iasults 129 I APPENDIX J: 1998 REMP Sample Collection 'nd Analysis Methods 132 APPENDIX K: 1998 TID Quarterly Data 136 I I I ' 11
e
.- LIST OF TABMS TABM TITLE PAGE l
- 1. Sources and Doses ofRadiation 5 {
2 Radicoucude Composition of OCNGS Emments for 1998 23
)
3 TLD Exposure Pededs During 1998 34 4 Cesium-137 Concentration in Aquatic Sediment, 1994 - 1998 (pCl/Kg<lry) 46 5 Cobalt 68 Comcastration in Aquatic Sediment, 1994 - 1998 (pCi/Kg-dry) 50 6 Species of Fish Caught as Part of the OCNGS REMPin 1998 51 7 Tritium Resuks from Oasite Groundwater
?'- " 4 Network (1989 through 1998) 56 l
8 Calculated Maximum R7; :^" "=" Doses to an ;
' Individual from Uguid and Airborne Efnutet :
Releases from OCNGS for 1998 ' 62 9 Calculated Maximum Total Radiation Doses to the Population from IJquid and Airborne Emment Releases from the OCNGS for1998 63 l A 1 P "-7
- EnviromanistalMonitoring Prograan Sampung Locations 68 A-2 Synopsis of the OperationalRadiological Environmental MonWoring Program - 1998 72 A 3 1998 Sampling and Analysis Exceptions 73 C-1 Changes to the REMP Dudag 1998 77 D-1 RadionuclideConcentrationsin1998 EnvirenasentalSan ples 78 l
E-1 1998 QA Sample Pngram Number of Duplicate Analyses Perfonned 15 E-2 1998 QA Sample Program - Split Samples 108 E-3 Interlsboratory Comparison Results 109 F-1 1998 USF.PA Cross Check Program Results 112 l l 1-l iii
LIST OF TABLES (Continued) TABLE TITLE PAGE F-2 1998 DOE EML Cross Check Program Results 114 F-3 1998 ANALYTICS Environmental Cross Check Program Results 118 i F-4 1998 ANALYTICS Cross Check Program Results 120 H-1 Summary of Maximum Hypothetical IndMdual and Population Doses From Uquid and Airborne Emuent Releases Fmen the OCNGS for 1998 128 I-1 Radionuclide Concentrations in Samples imm the On-Site Gmundwater Monitoring . Network 130 J-1 Summary of Sample Collection and Analysis Methods - 1998 133 K-1 1998 TIE Quarterty Data - Panasonic TLD's 137 K-2 1998 TID Quarterly Data - Teledyne Bmwn Engineering TID's 139 f I. $V l
IJST OF FIGURES FIGURE TITLE PAGE 1 Oyster Cnek Nuclear Generating Station
"' , """ s Schematic 8
2 Oyster CreekNuclear Generating Station Wind Direction Frequency of Occurnace- 1998 Wind Direction "Frona" Each Compass Sector-Values la Percent ofHourly Occurnace 13 3 Oyster Cnek Nuclear Generating Station Monthly Mean Ambient Air Temperature-1998 Compared witit Historical (1946-1981) Atlantic ' CityNationalWeather Serdce Average Temperature Data 15 4 Oyster Creek Nudeer Generating Station Monthly Precipitation - 1998 Compared with Historical (1946-1981) Atlantic City Nttional WeatherService Average Precipitation Data 16
- 5. I.mcations of Radiological Environmental Monitodag Program (REMP) Stations Within Two Miles of the OCNGS 29
. , _~ o,- E.ero.m .,
Monitoring Program (REMP) Stations Greater than Two Miles Fman the OCNGS 30 7 Mean Pa==-ic TLD Comana Dese-1989 through 1998 35 8 Mean Pa=-Ic TLD Ga=== Dose for 1998 Based on Distance from OCNGS 36 9 Air Particulate Gross Beta - 1998 Moving Range Quality Control Chart -Indicator Station Results Compared to Background Units 39 10 Bi-Weekly Mean Air Particulate Gross Beta Concentrations - 1998 41 11 Monthly Mean Air Particulate Gross Beta Concestrations - 1984 th.ough 1998 42 f I I
LIST OF FIGURES (Continued) FIGURE TITLE PAGE 12 Mean Cesiuni-137 Concentration in Aquatic Sedunent-1984 through 1998 45 13 Mean Cobalt 40 Concentration in Aquatic Sedunent- 1983 through 1998 48 14 Mean Cobalt 40 Concentration in Clams - 1983 through 1998 49 15 Exposure Pathways for Radionuclides PotentiallyReleased from the OCNGS 59 I-I Locations of On-Site Wells 131 I l l l l l l 1 VA
I
SUMMARY
AND CONCLUSIONS The radiological environmental morutoring performed dunng 1998 by the GPU Nuclear Environmental Affans Department at the Oyster Creek Nuclear Generatmg Station (OCNGS) is discussed in this report. He operation of a nuclear power plant results in the release of small amounts of radioactive materials to the emironment. A radiological emironmental monitoring program (REMP) has been established to monitor radiation and radioactive matenals in the emironment around the OCNGS. He program evaluates the relationship between amounts of radioactive material released in efBuents to the emironment and resultant radiation doses to indisiduals. Summaries and interpretations of the data were published senuannually from 1969-1985 and annually since 1986 (Ref. 20 through 31). Additional information conceming releases of radioactive materials to the j emironment is contamed in the Semi-Annual and Annual Effluent Release Reports subnutted to the United States Nuclear Regulatory Commission (USNRC). During 1998, as in previous years, the radioactive efBuents associated with the OCNGS were a small fraction of the applicable federal regulatory limits and did not have significant effects on the quahty of the emironment. The calculated maximum hypothetical radiation dose to the public attributable to 1998 operations at the OCNGS was only 0.15 percent of the applicable regulatory limit and significantly less than doses received from other man-made sources and natural background sources of radiation. Radioactive matenals considered in this report are normally present in the emironment, either naturally or as a result of non-OCNGS activities such as prior atmospheric nuclear weapons testing, medical industry activities, and the 1986 Chemobyl accident. Consequently, measurements made in f the vicinity of the site were compared to background measurements to determine any impact of OCNGS operations. Samples of air, well water, stuface water, clams, sediment, fish, crabs, and f vegetables were collected. Samples wue analyzed for radioactivity including tritium (H-3), gross beta, and gamma-enuttmg radionuclides. External penetratmg radiation dose measurements also were ( made using thermoluminescent amim+rs (TLDs) in the vicinity of the OCNGS. The results of these radiological measurements were used to assess the environmental impact of OCNGS operations, to demonstrate compliance with the Technical Specifications (Ref.1), the Offsite Dose Calculation Manual Specifications (Ref. 2), applicWe federal regulations, and to verify the adequacy of contairunent and radioactive effluent control systems. The data collected 1
by the REMP also provide a historical record of the levels of radionuclides and radiabon attributable to natural causes, worldwide fallout from prior nuclear weapons tests and the Chemobyl -ddet as wellas OCNGS operations Radiological unpacts in terms of rali. nee dose as a result of OCNGS operations were almlat~i and also are dia===~i The results provided in this report are summanzed in the following highhghts
. Dunng 1998, 638 samples were taken from the aquanc, atrresphene, and kusial envuunments around the OCNGS. A total of 893 analyses were performed on these samples.
TLDs were also unhzed to provide 170 direct radiation dose measurements Fortv groundwater samples, taken primarily from local municipal water supplies and on-site wells, were m16+d and eighty analyses were perfuni ed on those samples. Minute levels of cessm-137 (Cs-137) detected in aquatic aMiment samples were attributable in part to past efBuents from the OCNGS. This is the second consecutive annual repuiung penod dunng which cobalt-60 (Co-60) was not detectM in any enviim ;.1 media. This is a result of the minmuzation ofliquid radioactive efBuents and the natural radioactive decay Process The amount of radioactivity released in efBuents from the OCNGS dunng 1998 was the fifth smallest in the history of Station operation The pra- unt radionuclide in gaseous and liquid efBuents was tritium (H-3). The maximum radiation dose to the public, attributable to 1998 efBuents, was only 0.15 percent of applicable regulatory limit. i e Dunng 1998, the maximum total body dose potentially received by an indivxiual from liquid and airbome efBuents was conservatively W.="i to be 0.017 milhrems The total body I
- dose to the surrourxhng population from liquid and anbome efBuents was conservatively
~1=l*~i to be 0.1 person-rem. This is approwr idy 12.3 mdban times lower than the dose that the total population in the OCNGS area receives from natmal background sources
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I INTRODUCTION Characteristics of Radiati90 Instability within the nucleus of radioactive atoms results in the release of energy in the form of radiation. Radiation is classiSed according to its nature - particulate and electromagnetic. Particulate radiatinri consists of energetic subatomic particles such as electrons (beta particles), protons, neutrons, and alpha particles. Because of its imuted ability to penetrate the human body, particulate radiation in the environment contributes primardy to intemal radiation exposure resulting timiinhalation and ingestion of radioactisity. Electromagnetic radiation in the fonn ofx-rays and gamma rays has characteristics simdar to visible light but is more energetic and, hence, more penetrating. Although x-rays and gamma rays are peraating and can pass through varying thicknesses of matenals, once they are absorbed, they produce energetic electrons which release their energy in a manner that is identical to beta particles. The principal concem for gamma radiation from radionuclides in the environment is their contribution to external radiation I "Ihe rate at which atoms undergo disintegmtion (radioactive decay) varies among radioactive elements, but is uniquely constant for each specific radionuclide. 'Ihe 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 millions of years for oilers. In fact, the natural background radiation to which all manki:xi has been exposed is largely due to the radionuclides of uranium (U), thorium (Th), and potassium (K). "Ihese radioactive elements were formed with the creation of the universe and, owing to their long half-lives, will contmue to be present for millions ofyears to come. For example, potassium-40 (K-40) has a half-life of 1.3 billion years and exists naturally within our bodies. As a resuh, appmximately 4000 atoms of potassium emit radiation intemaL'y within each of us every second of our life. In assessing the unpact of radioactivity on the environment, it is important to know the quantity of radioactivity released and tle resultant radiation doses. The common unit of radioactisity is the curie I (Ci). It represents the radioactivity in one gram (g) of natural radium (Ra) which is also alud to a decay rate of 37 billion radiation emissions every second Because the level of tadioactive mated in the environment is extremely small, it is more convenient to work with portions or fractions of a c trie. I ' '
I I Subunits such as picoeurie (pCi), (one trillionth of a curie), are frequently used to express the radioactivity present in emirnnmental and biological samples. Le biological effects of a specific dose of radiation are the same whether the radiation source is extemal or intemal to the body. The important factor is how much radiation energy or dose was deposited. He unit of radiation dose is the Roentgen Equisalent Man (rem), which also incorporates the sariable effectiveness of different fonns of radiation to produce biological change. For emironmental radiation exposures, it is convenient to use the smaller unit of nulhrem (mrem) to express dose (1000 mrem equals I rem). When radiation exposure occurs over periods of time, it is appropriate to refer to the dose rate. Dose rates, therefore, define the total dose for a fixed intenst of time, and for emironmental exposures, l are usually measun:d with reference to one year of time (mrem per year). I Sources of Radiation Life on earth has evohed amid the constant exposure to natural radiation. In fact, the single major source of radiation to which the general population is exposed comes from natural sources. Although everyone on the planet is exposed to natural radiation, some people receive more than otins. Rnantion exposure from natural background has three wyc mts (i.e., cosmic, terrestnal, and internal) and varies with 1 altitude and geographic location, as well as with lising habits. 1 I For example, cosmic radiation originating from deep interstellar space and the sun increases with altitude, because there is less air to act as a shield. Sinularly, terrestnal radiation resulting from the presence of l naturally occurnng radionuclides in the soil varies and may be significantly higher in some areas of the country than in others Even the use of particular building matenals for houses, cooking 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 containing naturally occurring radionuclides. For example, drmkmg water contains trace amounts of uranium and radium, and milk contains radioactive potassium. Table I summanzes the common sources of radiarion and their average annual dose. I I 4
I I TABLE 1 (Adapted from Ref. 4) Sources and Doses of Radiation
- Natural (82%) Man-made (18%)
Radiation Dose Radiation Dose I Source (mrem /vear) Source (mrem /vear) I Radon Cosmic rays Terrestrial 200 (55 %) 27 (8%) 28 (8%) Medical X-ray Nuclear Medicine Consumer products 39 (11 %) 14 (4%) 10 (3%) Internal 40 (11 %) Other <1 (<1%) I (Releases from nat. gas, phosphate muung, burning I ofcoal, weapons fallout,
& nuclear fuel cycle)
Approximate Total 295 Approximate Total 64 - I l
- Percentage contribution of the total dose is shown in parentheses.
He average person in the United States receives about 300 mrem /yr (0.3 rem /yr) from natural backgroutxi radation sources. His estunate was recently revised from (approxunately) 100 to 300 mran because of the inclusion of radon gas which has always been present but has not been previously included in the calculations. In some regions of the country, the amount ofnatural radation is signi6cantly higher. Residents of Colorado, for example, receive an nMMnani 60 mrem /yr due to the increase in cosmic and terrestrial radiation levels. In fact, for every 100 feet above sea level, a person will receive an nMManni 1 mrem /yr from cosmic radiation. In several regions of the world, high concentrations of uranium and radium deposits result in doses of several thousand mrem /yr to their residents (Ref. 4). Recently, public attention has focused on radon (Rn), a naturally occumng radioactive gas produced l from uranium and radium decay. %ese elements are widely distributed in trace amounts in the earth's crust. Unusually high concentrations have been found in certam 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 surveys are needed to determine the full extent of the problem nationwide. Radon is the largest component of natural background radiation and may be 5
responsible for a substantial number oflung cancer deaths annually. He National Council on Radmtion Protection and Measurements (NCRP) eeime that the average individual in the United States receives an annual dose of about 2,400 mrem to the lung from natural radon gas (Ref. 4). His lung dose is considered to be equivalent to a whole body dose of 200 nulhrems he NCRP has twm >eded actions to control indoor radon sources and reduce exposures. When radioactive substances are inhaled or swallowed, they are distributed within the body in a non-uniform fashion. For example, radioactive iodine selectively concentrates in the thyroid gland, mAi-tive asium is distributed throughout the body water and muscles, and radioactive strontium concentrates in the bones. The total dose to organs by a given radionuclide also is influenced by the quantity and the duration oftime that the radionuclide remams in the body, including its physical, biological, and chemical charactenstics. Dependmg on their rate of radioactive decay and biological elinunation from the body, some radionuclides stay in the body for very short times while others remain for years. In addition to natural radiation, we are exposed to radiation from a number of man-made sources ne single largest of these sources comes from d%=no.ic medical x-rays and nuclear medical procedures Some 180 million Americans receive medical x-rays each year, ne annual dose to an indisidual from such radiation averages about 53 mdhrems Much smaller doses come from nuclear weapons fallout and 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 mrem for the average inelividual living in the United States. 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 emironment either by dry deposition or washed dawn to the earth's surface by precipitation. Here are approximately 200 radionuclides produced in the nuclear weapon detonation process; a number of these are detected in fallout. He radionuclides found in fallout which produce most of the fallout radiation exposures to humans are iodine-131 (I-131), strontium-89 (Sr-89), strontium-90 (Sr-90), and cesium-137 (Cs-137). Here has been no atmospheric nuclear weapon testing since 1980 and many of the radionuclides, still present in our emironment, have decayed significantly. Consequently, doses to the public from fallout have been decreasing. As a result of the nuclear accident at Chemobyl, USSR, on April 26,1986, radioactive matenal was dispersed throughout the global emironment and detected in various media such as air, milk, and soil. 6
1 i Cesium-134, cesium-137, iodine-131, and other rviionuclides released from Chemobyl were detected at the OCNGS in significant amounts following the accident. These radionuclides continue to decay toward a stable statein the emironment. Nuclear Reactor Operations Common to the commercial production of electricity is the consumption of fuel which produces heat to make steam which tums the tmbine-generator which generates electricity. Unlike the bunung of coal, oil, or gas in fossil fuel powered plants to generate heat, the fuel of most nuclear reactors is comprised of the element uranium in the form ofuranium oxide. The fuel produces power by the process called fission. In 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 I with heat, radiation, and free neutrons 'Ihe free neutrons travel through the reactor and are sinulady absorbed by the uranium, pemuttmg the fission process to contmue. As this process contmues, more I fission products, radiation, heat, and neutrons are produced and a sustained reaction occurs 'Ihe heat produced is transferred via reactor coolant (water) from the fuel to pmduce steam which drives a I turbtre-generator to produce electricity. 'Ibe Sssion products are mostly Mimerive; that is, they are unstable atoms which emit radiation as they decay to stable atoms. Neutrons which are not absorbed by the uraruum fuel may be absorbed by stable atoms in the matenals which make up the components and I structures of the reactor. In such cases, stable atoms often become radioactive. This process is called actnanon and the radioactive atoms which result are called activation products. The OCNGS reactor is a Boiling Water Reactor (BWR). The nuclear fuel is designed to be contamed within scaled fuel rods arranged in arrays called bundles which are located within a massive steel reactor vessel. As depicted in Figure 1, cooling water boils within the reactor vessel producing steam which drives the turbine. After the energy is extracted from the steam in the turbine, it is cooled and enndenW l back into water in the main condensers This enndenota is then pumped back into the reactor vessel and the cycle repeats l Several hundred radionuclides of some 40 different elements are created in a nuclear reactor durmg the process of generatmg electricity. Because of reactor enginwinig designs, the short half-lives of many radionuclides, and their chemical and physical propeities, nearly all radioactivity is enntnineA l 7
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____ ~ -- The OCNGS reactor has six independent barriers that confine radioactive matenals produced in the reactor as it heats the water. Under normal operating conditions, essentially all radioactisity is contamed withinthe first two barriers. The ceramic uranium fuel pellets provide the first barrier. Most of the fission products are either trapped or chemically bound in the fuel where they remain. However, a few fission products which are volatile or gaseous at normal operatmg towatures may not be enntained in the fuel. The second bariier consists of zirconium (Zr) alloy tubes (termed " fuel chddmg") that resist corrosion and degradation due to high temperatures The fuel pellets are contamed within these tubes. There is a small gap between the finel and the claddmg, in which the noble gases and other volatile radionuclides collect and are cantained I 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 (electrically charged) form. These I matenals can be removed in the reactor coolant purification system. However, krymton (Kr) and xenon (Xe) do not readily dissolve in the coolant, particularly at high tawaime. Krypton and xenon collect as a gas above the enndenote when the steam is condensed I The fourth barrier consists of the reactor pressure vessel, turbine, enndenw, and associated piping of the coolant system. The reactor pressure vessel is a 63-foot high tank with steel walls approximately eight inches thick. It encases the reactor core. The remainder of the coolant system, including the turbine and condenser and associated piping, prosides contamment for radioactisity in the primary coolant. The Drywell provides the fifth barrier. It is a steel-lined vessel, surrounded by concrete walls approxanately 41/2 to 71/4 feet thick, that encloses the reactor pressure vessel and recircularmg pumps and piping. The Reactor Building provides the sixth barrier. It is a reinforced concrete and steel superstructure with walls approximately 5 feet thick that enclose the drywell and other plant components The Reactor Building is always maintamed at a negative pressure to prevent out-leakage. Sources of Liauid and Airborne Effluents Although the previously described barriers contain radioactisity with high efficiency, small amounts of radioactive fission products are nevertheless able to diffuse or migrate through minor flaws in the fuel 9
I~ claddmg and into the reactor coolant. Tmce quantities of reactor system component and structural surfaces which have been activated also get into the reactor coolant water. Many of the soluble fission and activation products such as iodmes, strontiums, cobalts, and cesiums are removed by denuneralizers in the purification system of the reactor coolant. He physical and chemical properties of noble gas fission products in the primary coolant prevent their removal by the demmerahzers I Because the reactor system has many valves and fittmgs, an absolute seal cannot be achieved. Minute dramage ofradioactive liquids from valves, piping, and/or equipment associated with the coolant system may occur in the Reactor and/or Turbine Buildirgs. Noble gases, produced durmg the fission process, are collected as gaseous waste which is processed in the multistage systems in the OCNGS Augmented Off-Gas Building, while the remauung radioactive liquids are collected in floor and equipment drams and sumps and are pumped to and processed in the OCNGS Radwaste Facthty. Reactor off-gas, consisting primarily of hydrogen and radioactive non-condemble gases, is withdrawn from the reactor primary system by steam jet air ejectors. These air ejectors drive the process stream through a 60 minate holdup pipe at approxunately 110 cubic feet per minute and then into the Augmented Off-Gas (AOG) System. He holdup pipe allows radionuclides with short half-lives to decay. He Augmented Off-Gas System is a gaseous processing system which provides hydrogen conversion to water via a catalytic recombiner, removes the water (vapor) from the process stream, holds up the process stream to allow further decay of short-lived nuclides, and filters the off-gas using charcoal beds and High Efficiency Particulate (HEPA) filters prior to discharge to the base of the stack. Once the process stream enters the stack, it is diluted by building ventilation, which averages approximately 200,000 cubic feet per minute, is morutored and sampled, and then is discharged out the top ofthe 368-foot stack. I he liquid waste processing system receives water contamimtad with radioactivity and processes it by filtration, demmerahzation, and distillation. Purified radwaste water is routinely recycled to the plant. Occasionally, it may be necessary to discharge this purified water, under the guidehnes of applicable permits, to the envirorrnent. Cud rants removed dunng the purification process are stored in the radwaste building and are eventually disposed ofvia the radioactive solids disposal systems Before purified water is discharged to the environment, it is first sampled, analyzed, assigned a release rate, and then released to the discharge canal which has a flow rate of460,000 to 980,000 gallons per minute. I E
! 10
I DESCRIPTION OF THE OYSTER CREEK NUCLEAR GENERATING STATION SIIE g GeneralInfonnata The Oyster Creek Nuclear Generating Station is located in Imey Township of Ocean County, New ' I. Jersey, about 60 miles south of Newark,9 miles south of Toms River, and 35 miles north of Atlantic I City. It lies approxunately 2 miles inland from Bamegat Bay. & site, covenng 1416 acres, is situated ! I partly in Izey Township and, to a lesser extent, in Ocean Township. The Garden State Parkwa'y I bounds the site on the west. Access is provided by U. S. Route 9, passing through the site and separating a 661-acre eastern portion from the balance of the property west of the highway. Tne station is about 1/4 l I mile west of the highway and 1-1/4 miles east of the Parkway. The site property extends about 3-1/2 miles inhnd from the bay; the maximum width in the north-south direction is almost 1 mile. The site I location is part of the New Jersey shore area with its relatively flat topography and extensive freshwater and saltwater marshlands & South Branch of Forked River runs across the northern side of the site and Oyster Creek partly borders the southem side. j lt is estimated that approximately 3.3 million people reside within a 50 mile radius of the OCNGS ; (Ref. 3) The nearest population center is Ocean Township which lies less than two miles south-southeast of the site. Based on 1994 population estimates,5908 people reside in Ocean Township. 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 (estimated 1994 population). The region adjacent to Bamegat Bay is one of the State's most rapidly developing areas. In addition to the resident population, a sizable seasonal influx of people occurs during the summer. This influx occurs almost exclusively along the waterfront. I Climatolostical Summary J Meteorological data were obtained during 1998 from an on-site weather station. These data are subject
- to extensive 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 monitor instrument performance.
I , I e 11
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'Ibe climate of New Jersey and a great deal of the country was greatly influenced by the El Nino /
Southern Oscillation (ENSO), a major warmmg of the ocean waters across the eastern and central tropical Pacific Ocean. The effects of the ENSO were felt from January through June. They include abnormal patterns of rainfall and cloudiness, especially over the tropics. North America typically I receives its strongest ENSO influence daring winter and early spring. The persistence of abnormally warm waters off the west coast have increased the occurrence of extra-tropical storms that have I buffeted the west coast with prolonged storms and increased mudslides. In addition, the persistence of the sub-tropicaljet stream has brought milder temperatures across the entire continental United States I during the winter, when the ENSO is strongest. "La Nina", described as a period of cold and dry conditions will sometimes follow its counterpart. It is not as common as the ENSO and did not appear I in the latter half of 1998. I Climatological highlights during the year included a third consecutive above normal temperature and precipitation pattern during the fall and winter, along with a fourth consecutive cooler than nonnal I summer. Tropical storm / hurricane activity in the Atlantic Ocean increased to 9 storms including Hurricane Bonnie which struck the North Carolina coast in August. Most of the storm's effects passed
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I south of the re;is During the summer months, winds were predommantly from the south and southwest directions. This I. ushers in warm and humid weather conditions. Precipitation resulting from these conditions is generally of short duration but high intensity (showers and/or thundershowers). During the autumn, winter and early spring, winds are generally from the west and northwest. Air masses during this time originate from the upper mid-west United States and Canada They are typically characterized by generally cold and dry conditions. Wind direction frequencies were normal during the year. The four highest frequency of occurrence sectors for the year, as measured at the 33-foot level, were winds from the northwest, west-northwest, west, and west-southwest (Fig. 2 ). Seasonal winds were evident as well, including the sea breeze circulation, (Ref. 3 ) during the late spring through early autumn season. Resulting winds during a sea breeze are from the south and southeast. The number of occurrences of this thermally-induced wind, created due to the differential heating between the land and the ocean, was reduced due to the strong west-southwesterly flow during the summer months. I g n 1 _ _ - - - _ - - _ _ _ _ .
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I I The annual average temperature for the year was 54.93 degrees Fahrenheit, warmer than last year's average temperature of 52.56 degrees. The historical average annual temperature is 53 degrees. Seven of twelve months were characterized by below normal temperatures, al hoagh differences from the historical average were small. The largest differences occurred during the months of June and October (Fig. 3 ). The winter months of January, February and December experienced above normal temperatures for the third consecutive year. The lack of a sustained polarjet stream in the continental United States was the reason for the warmer temperatures. In addition, the ENSO and the sub-polarjet stream bringing warmer air masses originating over the Pacific Ocean were the dominating features, especially during the months of January and February. Normal continental polar air masses only I 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 l I settles over the southern half of the United States. This area produces southwest flow and ushers in warm, humid conditions. This feature was not strong during 1998 and although there were periods of high humidity over the region, temperatures remamed near or slightly below normal with pronounced 'I cloud cover. For the third consecutive year, the area experienced above normal precipitation. The annual total precipitation amount was 54.24 inches, slightly higher than last years total of 50.93 inches. Th: 1998 total is over tulve inches more than the Atlantic City National Weather Service historical average (1946 -1981) of 41.50 inches. During the first six months, precipitation was greater than the monthly historical value. The greatest differences occurred in January, February, March, May and June (Fig 4). A total of 9.95 inches fell in May, highlighted by a 5-day rainfall total of 6.70 inches from May 8 through May 12, the result of several slow moving low pressure systems over the northeast United States. The abser ce of the semi-permanent sub-tropical high pressure belt over the southeast allowed an influx of moisture from the southwest. This moisture was enbncut by the ENSO over the eastern Pacific. This moisture also caused enhncM development of extra-tropical storms during the first half of the year. Typically, the ENSO will produce enhanced rainfall over the southern 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, there was an increase in tropical storm / hurricane activity due to the i I g a
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return of nonnal easterly flow in the tropics. Hurricane Bonnie passed east of the region on August 28, 1998 and produced high surf and gale force winds. Precipitation from Bonnie remained well off the coast. Typically, the main portion of winds and rain occur to the east and north of the hurricane's center. The moderate temperatures during the winter and late spring resulted in only a trace of snow for the months of January through April. A snowfall event of 5 inches occurred on December 23,1998. Generally the region will see approximately 10 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 associated with strong heating (thunderstorms, tomadoes, etc.) during 1998. The bulk of the year's precipitation occurred during the first halfinfluenced by an active ENSO period. For additional site-specific meteorological data, refer to the OCNGS EfDuent and Off-Site Dose Report for 1998 (Ref. 32) l 17
EFFLUENTS Historical Background Almost from the outset of the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazard of ionmng radiation was rengni7ed and efforts were made to establish radiation protection standards. %e Intemational Comnussion on Radiological Protection (ICRP) and the National Couned on Radiation Protection and Measurements (NCRP) wem established in 1928 and 1929, respectisely. Dese organizations have the longest continuous expenence in the resiew of radiation health effects and with makmg recommendations on guidelines for radiological protection and radiation exposure limits. In 1955, the United Nations created a Scientific Comnuttee on the Effects of Atomic Radiation (UNSCEAR) to summSze reports received on radiation levels and the effects on man and his emironment. De National Academy of Sciences (NAS) fonned a comnuttee in 1956 to raiew the biological effects of atomic radiation (BEAR). A series of reports have been issued by this and sum,4ng NAS comnuttees on the biological effects ofionmng radiation (BEIR), the most ircent during 1990 (known as BEIR V). These comnuttees and commissions of nationally and intemationally rengni7ed scientific experts have been Mu-*d o thet understandmg of the health effects of radiation by imestigating all sources of relemnt knowledge and scientific data and by providing guidance for radiological protection. Heir members are selected from universities, scientific research centers, and other national and intemational research orgaruzations. He committee reports contain scientific data obtamed from physical, biological, and epidemiological studies on radiation health effects and serse as scientific references for information presented in this report. Since its inception, the USNRC has depended upon the recommendations of the ICRP, the NCRP, and the Federal Ra&ation Couned (FRC) (incorporated in the United States Emironmental Protection Agency (USEPA) in 1970) for basic radiation protection standards and guidance in establishing regulations for the nuclear industry (Ref. 6 through 9). Effluent Release Limits As part of routme plant operations, hnuted quantities of radioactivity are released to the emironment in liquid and airbome effluents. An efBuent control program is implemented by GPU Nuclear to ensure
+
18
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I radioactivity released to the emirwuiwit is muumal and does not exceed release limits. The Federal govemment establishes limits on radioactive materials released to the emironment. These limits are set at
-low levels to protect the health and safety of the public and are speedied in the OCNGS Technical Specifications and Offsite Dose Calculation Manual (ODCM) (Ref. I and 2). GPU Nuclear conducts operations in a manner that holds radioactive efBuents to small percentages of the federal limits.
A recommendation of the ICRP, NCRP, and FRC is that radiation exposures should be maintained at levels which are "as low as reasonably achievable" (ALARA) and commensurate with the societal benefit derived from the activities resulting in such exposures For this reason, dose limit guidelines were established by the USNRC for releases of radioactive efBuents from nuclear power plants. 'Ihese 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. Applicable OCNGS Offsite Dose Calculation Manual limits are as follows:
- ODCM Specification 4.6.1.1.3.A Radioactivity Concentration in Liouid Effluent i
The concentration of radioactive matenal, other than noble gases, in liquid effluent in the discharge canal at the U.S. Route 9 bridge shall not exceed 10 times the liquid efHuent concentrations spectfied in 10CFR PaJt 20.1001-20.2401, Appendix B, Table II, Column 2.
- ODCM SpeciScation 4.6.1.1.3.B Radioactivity Concentration in Liauid EfBuent The concentration of noble gases dissolved or entrained in liquid efBuent in the discharge canal at the U.S. Route 9 bridge shall not exceed 2.0 F-4 uCi/ml. - ODCM Specification 4.6.1.1.4.A Limit en Dose Due to Liauid EfBuent The dose to a MEMBER OF THE PUBLIC due to radioactive material in liquid effluent in the UNRESTRICTED AREA shallnot exceed:
1.5 mrem to the Total Body dunng any calendar quarter i 19
I 5.0 mrem to any body organ dunng any calendar quarter 3.0 mrem to the Total Body dunng any calendar year or I 10.0 mrem to any body organ dunng any calendar year.
- ODCM Specification 4.6.1.1.5.A Dose Rate Due to Gaseous Effluent I Le dose equivalent rate in the UNRESTRICTED AREA due to radioactive noble gas in gaseous efBuent shall not exceed 500 mren6 ear to the total body or 3000 mrem / year to the skin. - ODCM Specification 4.6.1.1.5.B I 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 fonn having half-lives of 8 days or more in gaseous efBuents shall not exceed 1500 mren4 tar to any body organ when tle dose rate due to H-3, Sr-89, Sr-90, and alpha-enutting 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 he air dose in the UNRESTRICTED AREA due to noble gas released in gaseous effluent shall not exceed:
5 mrad / calendar quarter due to gamma radiation 10 mrad / calendar quarter due to beta radiation L 10 mrad / calendar year due to gamma radiation 20 mrad / calendar 3 car due to beta radiation [ r 20
p lI iI ODCM Specification 4.6.1.1.7.A LI Dose Due to Radiciodine and Partientata in Gaseous Emuent ~ The dose to' a MEMBER OF THE PUBLIC from I-131, I-133, and from radimiins in particulate. form having half-lives of 8 days or more in gaseous eBuent, in the UNRESTRICTED AREA shall not exceed 7.5 mrem to any body organ per calendar quarter or 15 mrem to any body organ per calendar year.
- ODCM Speci6ca% 4.6.1.1.8.A Annual Total Dose Due to Radioactive EfHuent 4
The annual dose to a MEMBER OF THE PUBLIC due to radioactive matenal in eBuent from 'I the OCNGS in the UNRESTRICTED AREA shall not exceed 75 mrem to his/her thyroid or 25 mrem to ins /her total body or to any other organ. Etlluent Control Program I EfBuent control includes plant components such as de ventilation system and filters, off-gas holdup components, demmerahzers, and an evaporator system. In addition to muumtzing the release of radioactivity, the efBuent control program includes all aspects of efBuent and ensimuindal trestvilug. This includes the operation of a complex radiation momtorire system, collection and analysis of efBuent samples, envimmodal sampling and momtoning, and a comprehensive quality assurance program. Over l 1 the years, the program has evolved in imes to changing regulatory requirements, industry events and I plant conditions. For example, additional instmments and samplers have been installed to ensure that
. measurements of efBuents remam onscale in the event of any accidental release of radioactivity.
EBuent Instmmentation: Liquid and airbome efHuent measurmg mstrumentation is designed to morutor the presence and the amount of radioactivity in eBuents. Many of these instruments provide contmuous survedlance of radioactivity releases Calibrations of efHuent instmments are performed using reference l standards certified by the National Institute of Standards and Technology (NIST). Instrument alarm l setpoints are pre-set to ensure that efHuent release limits will not be exceeded. If radiation momtor alann setpoints are reached releases are i m +My terminated. l I-iI " '
Where continuous survedlance is not practicable or possible, contingencies are specified in the Offsite Dose C*nkion Manual and/or the Technical Specifications. Effluent Samolina and Analysis: In addition to continuous radiation monitoring instruments, samples of
- effluents are taken and subjected to laboratory analysis to identify the specific radionuclide quantities being released. A sample must be representative of the esuent from which it is taken. Sampling and analysis provide a sensitive and precise method of detauunwg effluent composition. Samples are analyzed using state-of-the-art laboratory counting equipment. Radiation instrument readmgs and sample results are wuped to ensure correct correlation.
Effluent Data As part of routine plant operations, Imuted quantities of radioactivity are released to the environment in effluents. The amounts of radioactivity released vary and are dependent upon operating conditions, power levels, fuel conditions, efficiency ofliquid and gas processing systems, and proper functinning of plant equipment. The largest variations occur in the airbome eBuents of fission and activation gases, which are proportional to the integnty of the fuel claddmg and the operation of the OCNGS Augmented Off Gas system. In general, effluents have been decreasmg with time due to improved fuel integnty and mereased efficiency ofprocessing systems The amount of radioactivity released in effluents from the OCNGS during 1998 was the fifth smallest in the history of Station operation. The predominant radionuclide in gaseous and liquid efHuents was tritium (Table 2). Estimated doses to the public, attributable to these efHuents, were a small fraction of the applicable regulatory limits (Tables 8 and 9). Summaries of OCNGS eBuents can be found in Tat >le 2 and in the Annual Effluent and Offsite Dose Report that is subnutted to the USNRC (Ref. 32). Radioactive constituents of these eBuents are discussed in the following sections: l Noble Gases %e predonunant radioactive materials released in OCNGS airborne eBuents are typically the noble gases krypton (Kr) and xenon (Xe). Small anxxmts of noble gases can also be released in liquid I emuents. The total amounts of krypton and xenon released into the atmosphere in 1998 were 0.00323 curies I and 8.29 curies, respectively, which is the lowest total in the history of the OCNGS. Noble gases are inert. which means they do not react ch_ica]Iy or biologically. Xenon-135 with a half-life of 9.1 hours was the most abundant noble gas released. Rese noble gases were readily dispersed into the atmosphere when released and because of their short half-lives, quickly decayed into stable, nonradioactise forms. No noble gas
I TABLE 2 RADIONUCLIDE COMPOSITION OF OCNGS EFFLUENTS FOR 1998 I Radionuclide Half-Life Liquid Effluents (Ci) Airborne Efiluents (Ci) H-3 1.23E 1 Years 1.10E 2 3.07E2 Na-24 1.50E 1 Hours <LLD 1.69E-6 i i Cr-51 2.78E 1 Days <LLD 8.04E-5 Mn-54 3.12E 2 Days <LLD 9.31E-5 l Co-58 7.13E 1 Days <LLD 3.38E-5 Co-60 5.26E 0 Years <LLD 3.82E-4 Kr-85m 4.50E 0 Hours <LLD 3.23E-3 Sr-89 5.05E I Days <LLD 5.02E-4 , Sr-90 2.88E 1 Years <LLD 9.29E No-95 3.50E 1 Days <LLD 2.1IE-6 Tc-99m 6.00E 0 Hours <LLD 1.44E-6 I-131 8.05E 0 Days <LLD 1.56E-3 I-132 2.26E 0 Hours <LLD 1.50E-4 I-133 2.09E 1 Hours <LLD 7.55E-3 1-134 5.20E 0 Minutes <LLD 8.46E-7 I-135 6.68E 0 Hours <LLD 1.32E-6 .I Xe-135 9.10E 0 Hours <LLD 8.29E0 I Cs-137 3.02E 1 Years <LLD 6.51E-6 Ba-140 1.28E I Days <LLD 1.21E-3 Gross Alpha - - 4.91E-6 NOTE: All effluents art expressed in scientific notation. No other nuclides were detected. NOTE: < LLD = less than lower limit of detection. I I
activity was released in liquid eSuents durmg 1998. Iodioetand Partim1*=: h discharge ofio6es and particulates to the environment is nunmuzed by factors such as their high chemical reactivity, solubility in water, and the high removal efficiency of aubome and liquid processing systems Of the gaseous r=dinindie, iodine-131 is of particular interest because ofits relatively long half-life of 8.05 days. Particulates of relative concem are the radiocesiums (Cs-134 and Cs-137), radiostrontiums (Sr-89 and Sr-90), and activation products, n=ngana -54 (Mn-54) and cobalt-60 (Co40). h total amount ofiodmes and particulates released from the OCNGS in 1998 was 0.0116 cunes in airbome esuents. No iodines or particulates were released in liquid efBuents. Tntium Tritium (H-3) is typically the predaminant radionuclide released in liquid esuents and is also released in anbome esuents. Tritium is a radioactive isotope of h>xirogen It is produced in the reactor fuel and components and in reactor coolant as a result of neutron interaction with the naturally-occumng deuterium (also a hydrogen isotope) present in water. Liquid effluents from the OCNGS in 1998 resulted in 0.011 cunes of tritium being released. Tritium released in autome efBuents accounted for 307 curies of radioactivity. As in 1997, the amount of gaseous tritium released dunng 1998 was higher than the annual amounts released prior to 1997, most likely as a result of control rod blade leakage However, to put these amounts of H-3 into p+tive, the world inventory of natural cosmic ray-produced tritium is appindu=icly 70 million curies, which corresponds to a production rate of 4 million curies per year (Ref.10). Tritium contributions to the emironment from OCNGS effluents are too small to have any measurable effect on the existing concentrations in the offsite emironment. Transuranics: Transuranics are produced by neutron capture in the fuel, and typically emit alpha and beta particles as they decay. Important transuranic isotopes produced in reactors are uranium-239 (U-239), plutonium-238 (Pu-238), plutonium-239 (Pu-239), plutonium-240 (Pu-240), plutonium-241 (Pu-241), americium-741 (1m-241), plutonium-243 (Pu-243), plus other isotopes of amencium and curium. They have haF-hv.s rangmg from hundreds of days to millions ofyears. Greater than 99% of all transuranics are reta%h%in the nuclear fuel. 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 transuranics that may be found in the reactor coolant. Because retention and remosal efficiencies are so high, isotopic E 24 L.
o analyses for transuranics are not routmely perfonned. However, most transuranics are alpha emitters and are monitored by perfornung routine gross alpha analyses. Carbon-14: Production of carbon-14 (C-14) in reactors is small. It is produced in tle reactor coolant as a result of neutron interactions with oxygen (O) and rutrogen (N). Eeimata for all nuclear power production worldwide show that 235,000 curies were released from 1970 through 1990 (Ref.11). Cartx;n-14 also is produced naturally by the interactions of cosmic radiation with oxygen and strogen in the upper atmosphere. The worldwide inventory of natural C-14 is edimataA at 241 million curies (Ref. I1). Since the inventory ofnatural carbon-14 is so large, releases from nuclear power plants do not result in a measurable change in the background concentration of carbon-14. Consequently, carbon-14 is not routinely monitored in plant effluents. e 25
1 I l RADIOLOGICAL ENVIRONMENTAL MONITORING l GPUN conducts a comprehensive radiological emiremental morutoring program (REMP) to morutor i radiation and radioactive materials in the emironment around the OCNGS. The information obtamed from the REMP is then used to determine the effect of OCNGS operations, if any, on the environment and the public. I The USNRC has established regulatory guides which contain acceptable momtoring practices (Ref.12). I The OCNGS REMP was designed on the basis of these regulatory guides along with the USNRC Radiological Assessment Branch Technical Position on Emironmental Monitoring (Ref.13). The I OCNGS REMP meets or exceeds all of these guidelines. The objectives ofthe REMP are: l l e to assess dose impacts to the public from OCNGS operations l I e to verify in-plant controls for the contamment of radioactive matenals e to morutor any buildup oflong-lived radionuclides in the environment and changes in background radiationlevels e to provide reassmance to the public that the program is capable of adequately assessing unpacts and identifying noteworthy changes in the radiological status of the environment a to fulfill the requirements of the OCNGS Offsite Dose Calenhtion Manual (ODCM) and Technical Specifications
. Environmental Exposure Pathways to Humans from Airborne and Liauid Efiluents As previously discussed in the " Effluents" section, small amounts of radioactive matenals are released to the emironment as a result of operating a nuclear generating station. Once released, these materials move through the environment in a variety of ways and may eventually reach humans via breathing, dankmg, eatmg, and direct exposure These routes of exposure are referred to as envie-imel exposure oathways. Figure 15 illustrates the important exposure routes.
I g w
I I Whde some pathways are relatively simple, such as inhalation of airborne radioactive matenals, others may be complex. For example, radioactive airbome paiticulates may deposit onto forage, which when eaten by cows, may be trie.fmod into milk, which is suWquently consumed by man. ' Ibis route of exposure is known as the air-grass-cmv-milk-human pathway. Although radionuchdes can reach humans by a number of pathways, some are more important than others, The critical pathway for a given radionuclide is the one that produces the greatest dose to a population or to a specific segment of the population. This segment of the population is known as the critical group and may be defined by age, diet, or other cultural factors The dose may be delivered to the whole body or confined to a specific organ; the organ receising the greatest fraction of the dose is known as the critical organ. This infommtion was used to develop the OCNGS REMP Sampline The OCNGS radiological environmental morutonng program consists of two phases - the preoperational and the operational. Data gathered in the preoperational phase were used as a basis for evaluatmg radiation levels and radioactivity in the vicinity of tle plant after the plant became operational The operational phase began in 1%9 when the OCNGS attamed initial criticality. The program consists of takmg radiation measurements and collectmg samples frrm the enviraguent, analyzing them for radioactive content, and intershug the results Emphasis is on the critical exposure pathways to humans with samples taken from the aquatic, atmospheric, and terrestnal emironments
'Ihese samples include air, well water, surface water, clams, sediment, fish, crabs, and vegetables.
Thermolummescent dosimeters (TLDs) are placed in the emironment to measure gamma radiation levels.
'Ihe ODCM Spmwatkas, along with rw i- w Mns from GPUN scientists, specify the sample types to be collected and analyses to be performed Sampling locations were established by considenng meteorology, population distribution, hydrology, and land use charactenstics of the local area. 'Ihe sampling locations are divided into two classes, indicator and background. Indicator locations are those which are expected to show effects from OCNGS operations, if any exist. These locations were primanly selected on the basis of where the highest predicted envi>w--nal concentrations wouki occur. Whde the indicator locations are typically within a few miles of the plant, the background stations are generally at dictanm greater than 10 miles from the OCNGS. Therefore, background samples are m!!MM at locations which are expected to be unawetM 27
fl I by station operations. They provide a basis for evaluating fluctuations at indicator locations relative to natural background mdioactivity and fallout from prior nuclear weapon tests. Figures 5 and 6 show the current sampling locations around the OCNGS. Table A-1 in Appendix A describes the sampling locations by distance and azimuth (compass direction) from the OCNGS, along with type (s) of samples collected at each sampling location. { Analvsis I In addition to specifying the muumum media to be collected and the muumum number of sampling I locations, the ODCM Specifications stipulate the frequency of sample collection and the types and frequency of analyses to be performed. Also specified are analytical sensitisities (detection limits) and j I reporting levels. Table A-2 in Appendix A provides a synopsis of the sample types, number of sampling locations, collection frequencies, number of samples collected, types and frequencies of analyses, and number of samples analyzed. Table A-3 in Appendix A lists samples which were not collected or I analyzed in accordance with the requirements of the ODCM Specifications. Sample analyses which did i I not meet the required analytical sensitivities are preseM in Appendix B. Changes in sample collection and analysis are described in Appendix C. i
)
l The analytical results are routinely revie,ed by GPUN scientists to assure that established sensitivities have been achieved and that the prom analyse:: have been performed. All analytical results are subjected to an automated rt view process nich ensures that ODCM-required lower limits of detection are met and that renorting les els are not excreded. Investigations are conducted when reporting levels are reached or when anomalous es aa dkcovered. Analytical REMP sample results are presented in Appendix D in this report. Table D-1 in Appendix D provides a tabular reporting of all analytical results for samples collected in 1998. Table D-1 i summanzes the data in a format that closely resembles the suggested format presennxi in the USNRC Branch Technical Position (Ref.13). Quality Assurance (QA) sampic results for split and/or duplicate samples were used to verify the primary sample results 'Ihe QA program is described below. I I _ I I
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Oyster Cresk Nuclear Generating Station (OCNGS) Locadoms ofRameloglea1 Empiromsmoment Manhedag Programa (RIMF) Stadoes greader than 2 udies team the OCNCS 30
Measurement of low radxxtuclide concentrations in emironmental media requires special analysis techmques. Analyticallaboratories use state-of-the-art laboratory equipment designed to detect beta and gamma radiation. This equipment must meet the required analytical sensitisities. Examples of the speciatived laboratory equipnet used are germanium detectors with multichannel analyzers for identifying specific gamma enutting radionuclides, liquid scintillation detectors for Macring tritium, low levelproportional counters for datenggross beta radioactivity, and coincidence counters for lowlevel I-131 detection. Computer hardware and software used in conjunction with the countmg equipment perform calenlatinn_< and provide data management Analysis methods are described in Appendix J. Ouahty Assurance Program A Quahty Assurance (QA) program is conducted in accordance with guidelines provided in Regulatory Guide 4.15, " Quality Assurance for Radiological Monrwsg Programs" (Ref.16) and as required by the
, ODCM Specifications (Ref. 2) and Technical Specifications (Ref.1). The QA program is documented by GPUN written policies, procedures, and trxords. These documents encompass all aspects of the W REMP including sample collection, equipment calibration, laboratory analysis, and data review.
The QA program is designed to identify possible deficiencies so that immedmte corrective action can be taken ifwarranted. It also provides a measure of confidence in the results of the momtoring program in order to assure the regulatory agencies and the public that the results are ulid. The Quality Assurance program for the measurement ofradioactivity in environmental samples is implemented by: e auditing all REMP-mlated activities including analytical laboratories I e requinng analytical laboratories to participate in an NRC approved Emironmental Radioactivity Intercompanson Program e requinng analytical laboratories to split samples for separate analysis (recounts are performed when samples are not able to be split) e splitting samples, having the samples analyzed by mdependent laboratories, and then companng the results for agreement e reviewing QA results of the analytical laboratories including spike and blank sample resuhs and duplicate analysis results 31
The Quahty Assurance program and the results of the Environmental Radioactisity Intercompanson Program are outlined in Appendices E and F, respectively. The TLD readers are calibrated monthly agamst standard TLDs to within five percent of the standard ILD values. Also, each group of TLDs processed by a reader contains control TLD: that are used to correct for minor variations in the reader. The accuracy and variability of the results for the control TLDs are examined for each group ofTLDs to assure the reader is functinning properly. Other cross-checks, calibrations, and certifications are in place to assure the accuracy of the TLD program Senuannually, randomly selected TLDs are sent to an mdependent laboratory where they are irruimted to set doses not known to GPUN. The GPUN dosimetry laboratory processes the TLDs and the results are compared agamst established limits Every two years, each TLD is checked for response within 10 percent of a known value Every two years, the GPUN dosimetry program is emued and recertified by the NIST National Voluntary Laboratory Accreditation Program (NVLAP) Four OCNGS REMP TLD stations have collocated quahty assurance badges which are processed by an independent laboratory (Teledyne Brown E ghadug). The results are compared agamst GPU Nuclear Panasonic TLD results I The emironmental dosimeters were tested and quahfied to the specifications in the American National Standard Institute's (ANSI) Publication N545-1975 and USNRC Regulatory Guide 4.13 (Ref.14 I and 15). Il l l \ b 32 m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
DIRECT RADIATION MONITORING Dose rates from ewemal radiation sources were measured at a number oflocations in the vicinity of the OCNGS using thermolumirmd dosimeters (TLDs). Naturally occurnng sources, including radiation of cosmic origin and natural radioactive matenals in the air and ground, as well as fallout from prior nuclear weapon testing, resulted in a certain amount of penetratmg radiation being recorded at all morutoring lomtions. Indicator 1LDs were placed systematically, with at least one station i:: ~ch cf 16 meteorological 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 five mile radius of the OCNGS, located in areas where the potential for deposition of radioactivity was determmed to be high, in areas of public interest, and population centers. Background locations were located greater than twenty miles distant from the OCNGS and generally in an upwind direction. Samole Cdlection and Anahsis A state-of-the-art thermolummescent dosimeter is used. Thermoluminescence is a process in which ionizing radiation, upon interacting with the sensitive material 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 material. These TLD traps are so stable that they do not decay appreciably over the course of years. This pro 5 ides an excellent method of integrating the exposure received over a period of time. The energy stored in the TLDs as a result of interactions with radiation is removed and measured by a controlled heating process in a calibrated readmg system. As the TLD is heated, the phosphor releases the stored energy as light. The amount oflight given off is directly proportional to the radiation dose the TLD received. The readmg process ' zeros' the TLD and prepares it for reuse. The TLDs in use for environmental nnutoring 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 were exposed quarterly at 44 morntoring locations rangmg from less than 0.2 miles to 25 miles from the OCNGS. Two Panasonic Model 814 TLDs were exposed at each location. One of these locations was designated as a quality control station where two additional Model 814 badges were collocated Four Teledyne Brown Engmeering TLDs were also exposed at designated quahty contml stations. Panasonic Model 814 TLDs provide 4 irepm+nt detectors per badge and 8 detectors per station. 33 l
I i The scheduled exposure periods for 1998 were: Table 3 TLD EXPOSURE PERIODS I ' DURING 1998 Start Date Collection Date I 19 Jan 98 13 Apr 98 13 Jul 98 13 Apr 98 13 Jul 98 12 Oct 98 l I 12 Oct 98 11 Jan 99 l All TLD dose rate data presented in this report have been normahzed to elimmate differences caused by slightly differing exposure periods. All results were normahzed to a standard quarter (91.3 days). TLD dose I rate data are presented in Tables K-1 and K-2 in Apperxhx K. Results The mean background dose exceeded the trean indicator dose danng 1998 suggesting that the OCNGS had little if any affect on off-site exposure The mean dose rate from indicator stations using Panasonic TLDs was 10.0 mrem / standard quarter with a range from 6.9 to 17.5 mrem / standard quarter (Table K-1). De mean background dose was 10.8 mrem /standra quarter with doses rangmg from 9.2 to 12.4 mrem / standard quarter. Mean doses at background stations have historically exceeded mean doses at indicator stations, most probably due to differences in local geology. nese results are consistent with the results of measurements from previous years (Fig. 7). I Dose rates were slightly higher at some locations within 0.4 miles of tle OCNGS when compared to background doses (Table K-1 and Fig 8). However, these slightly higher doses were recorded at stations that I were all located in the Owner Controlled Area where public access is restricted or completely denied. In contrast, doses recordcd at stations located at approximately the same distance from the OCNGS where the public has unrestricted access (US Route 9) were less than those recorded at the background stations. S=h11y, the mean dose recorded at locations along US Route 9 (Stations 61, 62, 63, 64, 65, and 66) was 9.3 mrem / standard quarter compared to a mean dose of 10.0 mrem / standard quarter recorded at the background stations. In addition, the maxmium dose recorded at these indicator stations was 11.0 mrem / standard quarter while the highest recorded background dose was 12.4 mrem / standard quarter. These
, mhs suggest that OCNGS prahbuted Many to N 34
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I I Regarding Teledyne Brown Engireing TLD data, the dose rate measured at indicator stations averaged 9.2 mrem / standard quarter and ranged from 7.9 to 10.0 mrem / standard quarter (Table K-2). 'Ihe dose at background TLD stations averaged 10.3 mrem / standard quarter and ranged from 9.5 to 10.9 mrem / standard quarter. The mean dose rate from the background stations was higher than the mean dose rate from the indicator stations, again suggestmg that OCNGS operation contributed little if any to off-site exposure. I I I I I I I I I I I I 'I lI I
i I 1 l ATMOSPHERIC MONITORING A potential exposure pathway to man is the inhalation and ingestion of ai2 borne radioactive materials. Air was sampled by a network of seven continuously operating air samplers and then analyzed for radioactisity content. I_ Indicator air sampling stations are located in prevaihng downwind duections, local population areas, and areas of public and special interest. All indicator stations are located within 6.1 miles of the OCNGS. A background air sampling station is located 25 miles northwest of the OCNGS in Cookstown, NJ. ! I Samole Collection and Anahsis i I Mechanical air samplers are used to contmuously draw a recorded volume of air first through a glass 6ber I (particulate) filter and then through a charcoal cartridge. A dry gas meter, which is temperature compensated, is used in line with the filters to record the volume of air sampled. Internal vacuums are also measured in order to pressure correct the indimted volume. All air samplers are maintamed and calibrated by the OCNGS -I Instrument and Control Department. The particulate filters were collected eve 2y two weeks and analyzed for gross beta radioactivity. The filters were then combined quarterly by individual stations and analyzed for gamma-enutting radionuclides. I Charcoal cartridges, used to collect gaseous radiciodmes, contam activated charcoal. Charcoal cartridges were collected weekly and analyzed for iodme-131 (I-131) actisity. Results .I The results ofthe atmospheric morutoring dunng 1998 demonstrated that, as in previous yeast, the radioactive airborne efEuents associated with the OCNGS did not hae any measurable effects on the enth-st. During 1998,183 gross beta analyses were performed on air particulate filters (Table D-1). The background mean gross beta activity (0.0151 pCi/m') was slightly higher than the indicator mean (0.0142 pCi/m') and all gross beta analysis results were within two standard desiations of the historical mean. A quahty control check j ofindicator station results shows that all but one of the 157 observations were within statistical control limits (Fig. 9). ,I 38
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AOUATIC MONITORING Brackish water from Barnegat Bay is drawn in through the South Branch of Forked River, pumped into the OCNGS cooling systems, and then discharged to Bamegat Bay via Oyster Creek. Normally, no radioactive matenal is introduced to this non-contact cooling water. On occasion, radioactive liquids may be released to the chscharge canal in accordance with the limits established in the OCNGS Offsite Dose CAhtion Manual (ODCM) Specifications, Technical Specifications, and 10CFR20. Highly purified water, contauung traces of radioactivity, may be chscharged into the OCNGS discharge canal, which routinely has a muumum flow rate of slightly under one-half million gallons per minute. Liquid efBuents during 1998 resulted in the release of 0.011 curies of tritium. Fish, clams, and crabs are harvested from the bay on a recreational and, to a limited extent, commercial basis. The ingestion pathway is addressed because of fish, clam, and crab consumption by man. Samples of surface water, sedunent, 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 morutor any environmental
' impact that may be associated with liquid efBuents 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. Sechment and clam samples were also collected senuannually. Grab samples of surface water and sediment were collected from three indicator stations and one background station. Grab samples ofclams were collected from two indicator stations and one background station. An indicator station (Station 33) is located in the OCNGS discharge canal where surface water and sedunent are collected, but no clams are available for collection. Two additinnal 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 /Litde Fu Harbor. Fish samples were collected sermannually (when available) from two indicator stations and one background station. One crab sample was collected annually from an indicator station. Indicator stations for fish and crabs are located in the OCNGS discharge canal and the background station for fish is located in Great Bay /Litde Egg Harbor. Crab pots were used to catch blue crab. Traps, as well as the hook and line technique,were used to catch fish.
' 43
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, clam, fish, and crab samples were analyzed for gamma-etfutting nuclides and surface water was analyzed for tritium as well as gamma-enuttmg nuchdes Results l Operation of the OCNGS had no Meahle effect upon the local surface water which was sampled 40 times t
at four different locations during 1998. One gamma-enutting nuclide, potassium-40 (K-40) was MmM in 27 of 28 analysis perfonned (Table D-1). Tritium (H-3) activity was also detected in one sample (Table D-1). Both of these nuchdes are naturally h%g and minuenly found in salt water at or above the observed concentrations. No other radhh were MmM in surface water samples. L Five gamma-emitting nuclides were detected in the 8 sediment samples collected during 1998 (Table 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 not attributable to OCNGS effluents. Cesium-137
- (Cs-137), which is a fission product, was also detected in both background and indicator samples.
Cesium-137 was widely distributed and detected in considerable abundance as a result of fallout following atmospheric weapons tests and the 1986 Chernobyl accident. Cesium-137 was also released in small quantities from the OCNGS in liquid effluents in past years. The results of the sediment sampling program indicate that the presence of cesium-137 in the sedunents 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 #mant sample analysis results for the 1994 - 1998 period shows cesium-137 was detected in 82' percent of background and only 60 percent of indicator samples (Table 4). l 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 consistently higher than those found at background stations (Fig.12). During the previous five years, the mean concentration of cesium-137 at background stations was 32 pCi/kg dry, while the average concentration at indicator Stations 33 and 93 was 93 pCi/kg-dry, in addition, during this five year period, the highest concentration of Cs-137 at an indicator station was 240 pCi/kg-day, which was detected at Station 33 during March 1996. The highest concentration at a background station during the same five year period was 67 pCi/kg-dry. It is important to note that even the highest concentration of Cs-137 observed in sedinunts (240 pCi/Kg-dry) v.3s oc!y shghtly above the 180 pCi4 dry Lower Limit of Deari speci6ed by the Nuclear Regulatory [ 44' l
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I Table 4 Cesium-137 Concentration in Aquatic Sediment 1994 - 1998 (pCi/Kg-dry) , 1 Station Station Station Station Station Station Station Station Date 23 24 25 31 32 33 93 94 Jan 94 26 22 < LLD 40 54 140 110 67 Apr 94 < LLD 21 < LLD 49 45 150 67 48 Jul 94 < LLD < LLD < LLD 24 29 160 70 46 Nov 94 24 37 < LLD 22 44 140 95 61 Mar 95 < LLD < LLD < LLD < LLD 72 46 94 < LLD May 95 56 < LLD < LLD < LLD < LLD 130 100 32 Aug 95 < LLD < LLD 9 13 32 60 91 15 Oct 95 47 31 < LLD < LLD < LLD 51 120 27 Mar 96 < LLD < LLD < LLD 37 20 240 110 26 Jun 96 32 21 11 23 <LLD 56 71 22 Aug 96 16 < LLD < LLD 17 < LLD < LLD 100 24 l Sep 96 < LLD < LLD 15 39 23 33 100 17 May 97 45 < LLD #f g 64 20 Oct 97 < LLD < LLD su , 7
% 12 31 Jun 98 < LLD < LLD 34 45 Nov 98 < LLD < LLD ,
58 g2 < LLD Maximum 56 37 15 49 72 240 120 67 Average 35 26 12 29 40 92 94 34 Minimum 16 21 9 13 20 12 67 15 I
- Shaded areas indicate no data
- Stations 23,24,25,32,33, and 93 are indicator stations
- Stations 31 and 94 are background stations 46
I Commission (Ref.13) and only 12 percent of their Reporting level for Cs-137 in fish and broad leaf vegetation (2,000 pCi/kg-wet). Over the years, there has been a dramatic reduction in liquid discharges from the OCNGS and there have been no routme &scharges ofliquid mdioactive wastes since 1989. As a result of this reduction in liquid effluents, as well as the ongoing natural radioactive decay process, the level of Cs-137 in sediments contmucs to decrease (Fig.12). l Cubalt-60 was not detected in either indicator or background station se& ment samples during 1998 l (Table D-1; Fig.13). The presence of cobalt-60 in sediment samples in pre ious years has been attributed to past OCNGS liquid effluents (Ref 19). During the years 1994 through 1996, cobalt-60 was detected in 58 percent of seament samples collected from indicator stations 33 and 93, located in the OCNGS Discharge Canal (Table 5). Dunng the same time period, no Co-60 was detected at either of the background stations, Stations 31 and 94, nor was it detected at any other indicator station. As documented in previous reports, OCNGS-related cobalt-60 activity had been found in Wiment and clams from Bamegat Bay since the mid-1970's. 'Ihe amount of ra&oactivity in liquid effluents has been significantly reduced since that time and this decrease in the rate ofinput of cobalt-60 to the environment, combined with radioactive decay of the existmg inventory, has resulted in a gradual decline in the cobalt-60 concentration in se& ment and clams (Figs.13 and 14). The last detectable concentrations of this radionuclide in Wiment were found during tie third quarter of 1996 (Fig.13), and in clams, during the third quarter of 1987 (Fig.14). No radionuclides attributable to effluents from the OCNGS were found in samples of clams, crabs and fish collected during 1998 (Table D-1). I Six clam samples were collected from three different locations during 1998. Gamma isotopic analyses imiistal that the only gamma-emittmg nuclide present was potassium-40, which is naturally occurnng and commonly found in salt water (Table D-1). One blue crab sample was collected from the OCNGS discharge canal during 1998. A gamma isotopic analysis was performed on this sampic and naturally occumng potassium-40 and thorium-232 were the only radionuclides identified (Table D-1). The close association of this species with Wimente 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 routme collection began in 1985. 47
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Table 5 Cobalt-60 Concentration in Aquatic Sediment 1994 - 1998 (pCi/Kg-day)
Station Station Station Station Station Station Station Station Date 23 24 25 31 32 33 93 94 Jan 94 < LLD < LLD < LLD < LLD < LLD 26 37 < LLD Apr 94 < LLD <LLD < LLD < LLD <LLD 38 26 <LLD Jul94 < LLD < r.LD < LLD < LLD <LLD < LLD 22 < LLD Nov 94 < LLD < LLD < LLD < LLD < LLD 44 27 < LLD 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 Jun 96 < LLD < LLD <LLD < LLD <LLD 15 < LLD < LLD Aug 96 < LLD < LLD < LLD < LLD < LLD < LLD 33 < LLD Sep 96 < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD May 97 < LLD < LLD , g < LLD < LLD Oct 97 < LLD < LLD g < LLD < LLD Jun 98 < LLD < LLD <
< LLD < LLD Nov 98 < LLD < LLD < LLD < LLD Maximum < LLD < LLD < LLD < LLD < LLD 180 37 < LLD Average < LLD <LLD < LLD < LLD <LLD 51 26 < LLD Minimum < LLD < LLD < LLD < LLD < LLD 14 18 < LLD
- Shaded areas indicate no data
- Stations 23,24,25,32,33, and 93 are indicator stations
- Stations 3I and 94 are background stations
Eighteen fish samples, yielding nire species, were collected from 3 sampling locations dunng 1998l The species and number of samples collected are listed in Tabb 6.
TABLE 6 SPECIES OF FISH CAUGHT AS PART OF THE OCNGS REMP IN 1998 Fish Number of Samples bluefish 3 striped bass 3 white perch 3 winter flounder 3 tautog 2 blowfish I su bus I summer flounder 1 -
weakfish 1 Naturally occurring potassium-40 was the only radionuclide detected in fish samples collected during 1998 (Table D-1).
51 i .
IERRESTRIAL MONITORING Radionuclides released to the atmosphere may be deposited on soil and vegetation and may be incorporated into ndik, vegetation, vegetables, and other food products. To assess the impact of dose to humans from this ingestion pathway, samples of green leafy vegetables were collected and analyzed during 1998.
The contribution 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, I primarily to the southeast of the site, with backgroc : wples collected from distant and generally upwind directions. Indicator samples are collected at the two locations with the highest D/Q (deposition I factor). These locations were identified using site-specific meteorological data. This technique is utilized in lieu of performing any garden census, because it ensures that representative measurements of I radioactivity in the highest potential exposure pathways are obtained as required by Technical Specification 6.8.4.b.
In addition, a dairy census was conducted to determine the locations of commercial dairy operations and milk producing ammals in each of the 16 meteorological sectors out te a distance of five miles from the OCNGS. The census showed that there were no commercial dairy operations and no dairy animals producing milk for human consumption within a 5 mile radius of the plant (Appendix G).
I Two gardens were maintained near the site boundary of the OCNGS in the two sectors with the highest potential for radioactive deposition in accordance with the Offsite Dose Calculation Manual (Ref 2).
Both of these indicator gardens are greater than 50 square meters (500 square feet) in size and produced green leafy vegetables. A commercial farm located approximately 24 miles northwest of the site was used as a background station.
I Sample Collection and Analysis Broadleaf vegetables, specifically cabbage and collards, were collected on a monthly basis begmamg in l
August and ending in November 1998. A gamma isotopic analysis was performed on each sample.
52
Resju The results of the terrestrial monitoring during 1998 demonstrated that the radioactive efBuents associated with the OCNGS did not have any measurable effects on vegetation.
A gamma isotopic analysis was performed on twelve collard samples and six cabbage samples (Table D-1). Naturally occurring potassium-40 (K-40) was detected in all of the samples collected from both i indicator and background stations. Beryllium-7 (Be-7), which is also naturally occurring, was identified in 3 of 8 collard samples and detected in 2 of 4 cabbage samples collected from the indicator garden.
I No other radionuclides were detected in vegetable samples. Of the radionuclides detected, all are naturally occurring, and none are associated with OCNGS operation.
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GROUNDWATER MONITORING The Oyster Creek Nuclear Generating Station is located on the Atlantic Coasud Plain Physiographic Province. This Province extends southeastward from the Fall Zone, a topographic break that marks the boundary between the Atlantic Coastal Plain and the more rugged topography of the Piedmont Province.
The Fall Zone is also where the crystalline and sedimentary rocks of the Piedmont and the unconsolidated Coastal Plain sediments meet.
- At least five distinct bodies of fresh groundwater or aquifers exist in the vicinity of the OCNGS. From the surface downward, they are:
- 1. Recent and Upper Cape May Formation
- 2. Lower Cape May Formation 3 Cohansey Sand
- 4. Upper Zone in the Kirkwood Formation
- 5. Lower Zone in the Kirkwood Formation The Recent and Cape May Formations are replenished directly by local precipitation. The recharge to the underlying aquifers occurs primarily from direct rainfall penetration on the outcrop areas, which are generally to the west of the site at higher elevations.
Samole Collecti?3 and Analysis As part of the routine REMP, three groundwater wells were sampled on a quarterly basis. Grab samples were obtained from two local Municipal Utility Authority wells and an on-site drmkmg water well. The Lacey Municipal Utility Authority combines water from three wells which are drilled to depths of 239',248', and 267'. This sampling location is 2.2 miles north-northeast of the OCNGS. A second sampling location is the Ocean Township Municipal Utility Authority well which is approximately 360' deep and located 1.6 miles from the OCNGS in a south-southwest direction. The third sampling location is the 400' deep on-site well that supplies drmkmg water to the OCNGS. Each sample was subjected to a tritium and gamma isotopic analysis.
54
l l In addition, a groundwater monitoring network' installed around the OCNGS in 1983 to serve as an early detection and monitoring system for spills, was sampled in March and October 1998. This
{ network is comprised of fifteen wells which are located in the Cape May, Cohansey, and Kirkwood Aquifers. Grab sample methodology was used and the samples were also analyzed for tritium and gamma emitting nuclides.
Results '
The results of the REMP groundwater rionitoring during 1998 demonstrated that, as in previous years, the radioactive effluents associated wi:h the OCNGS did not have any measurable effects on offsite dnnkmg water.
Twelve routine REMP well water samples were collected during 1998. No radioactivity was detected in any of these samples (Table D-1).
The results of the analyses of 28 samples collected from the onsite groundwater monitoring well network were similar to results seen in past years except for tritium concentrations (Table I-1).
Tritium, potassium-40, and thorium-232 were the only nuclides detected in these wells and each is naturally occurring. Tritium, however, is also produced as a byproduct in the OCNGS reactor and it was detected in these monitoring wells more frequently than in prior years (Table 7). Tritium was detected in 15 of the 28 samples collected in 1998. Tritium concentrations ranged from 150 to 840 pCi/ liter with an average concentration of 299 pCi/ liter. Prior to 1998, the highest frequency of occurrence was seven positive tritium results out of 25 samples in 1991. Only two positive tritium results,170 pCi/ liter in each, were observed during 1997, and only one positive result (180 pCi/ liter) was observed during 1996.
t 55
TABLE 7 l
FREQUENCY OF OCCURRENCE OF TRITIUM kL IN THE ONSITE GROUNDWATER MONITORING NETWORK (1989 through 1998) \
Year Number of Samples Number of Tritium Collected Results That Were Above the Lower Limit of Detection 1998 28 15 1997 30 2 1996 15 1 1995 30 3 1994 29 1 1993 30 1 1992 25 2 1991 25 7 1990 30 5 1989 28 2 The increase in the frequency of occurrence and concentration of tritium in the onsite groundwater monitoring wells can be attributed to the increase in the amount of tritium in airbome effluents from the OCNGS during 1997 and 1998. Increases in reactor coolant tritium concentrations, thought to be related to control rod blade leakage, have resulted in an increase in the amount of tritium released in gaseous effluents. Remedial efforts during the 17R outage in the autumn of 1998, including the replacement and shuffling of control rods, were implemented in order to reduce or eliminate this source oftritium.
The highest tritium concentration detected in onsite monitoring wells during 1998 (840 pCi/ liter) was only 42 percent of the analytical Lower Limit of Detection of 2,000 pCi/ liter specified by the Nuclear Regulatory Commission (Ref.13) and only 4.2 percent of the USEPA drinkmg water limit of 20,000 pCi/ liter. In addition, as discussed above, no tritium was detected in samples collected from offsite drmkmg water wells.
l 56 l
1
I RADIOLOGICAL IMPACT OF OCNGS OPERATIONS l
An assessment of potential radiological impact indicated that radiation doses to the public from 1998 operations at the OCNGS were well below all applicable regulatory limits and were significantly less than doses received from common sources of radiation. The 1998 total body dose, potentially received by a hypothetical maximum exposed individual, from OCNGS liquid and airborne effluents, was conservatively calculated to be 1.7E-2 millirem total or only 6.8E-2 percent of the regulatory limit. The 1098 total body dose to the surrounding population from OCtlGS liquid and airbome effluents was calculated to be 1.0E-1 person-rem. This is approximately 12.3 million times lower than the doses to the total population within a 50-mile radius of the OCNGS resulting from natural background seurces.
1 I Determmation of Radiation Doses to the Publiq To the extent possible, doses to the public are based on direct measurement of dose rates from l
external sources and measurements of radionuclide concentrations in the environment which may contribute to an internal dose of radiation. Thermoluminescent dosimeters (TLDs) positioned in the environment around the OCNGS provide measurements to determine external radiation doses i to humans. Samples of air, water, food products, etc. can be used to determine internal doses.
I During normal p' ant 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 environment and subsequent radiation doses on the basis of radionuclides released to the emironment. OCNGS doses were calculated using a computer program called SEEDS (Simplified Effluent Environmental Dosimetry System). This program is based upon the OCNGS Offsite Dose Calculation Manual (ODCM) and incorporates 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 SEEDS, the calculated doses are considerably higher than the actual doses to people.
The type and amount of radioactivity released from the OCNGS is calculated using measurements from effluent radiation monitoring instmments and effluent sample analysis.
Once released, the dispersion of radionuclides in the environment is readily estimated by 57
I l computer modeling. Airborne 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, atmospheric stability, and terrain. A meteorological monitoring station northwest of the OCNGS permanently records and telemeters all necessary !
meteorological data. A computer program is also used to predict the downstream dilution and travel times for liquid releases into the Bamegat Bay estuary and Atlantic Ocean.
The pathways to human exposure are also included in the model. These pathways are depicted l
in Figure 15. The exposure pathways considered for the discharge of the station's liquid effluent are fish and shellfish consumption and shoreline exposure. The exposure pathways considered j for airbome 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 j I. the plant stack to the site boundary in each of the sixteen compass sectors, the population ~ l groupings, meat ammals, and crop 3ields.
I When determining the dose to humans, it is necessary to consider all pathways and all exposed tissues (summmg the dose from each) to provide the total dose for each organ as well as the total body from a given radionuclide in the emironment. Dose calculations involve determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides tsken into the body, the metabolism of the radionuclide in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted, and half-life. SEEDS also contains dose conversion factors for over 75 radionuclides for each of four age groups (adult, teen, child, and infant) and eight organs (total body, th>Toid, liver, skin, kidney, lung, bone, and gastro-intestinal tract).
I Doses are calculated for what is termed the " maximum hypothetical indisidual". This individual is assumed to be affected by the combined maximum environmental concentrations wherever they occur. For liquid releases at the OCNGS, the maxunum hypothetical individual would be one who stands at the U.S. Route 9-discharge canal shoreline for 67 hours per year while eating I
' 58 I-
I I FIGURE 15 EXPOSURE PATHWAYS FOR RADIONUCLIDES POTENTIALLY RELEASED FROM THE OCNGS Gaseous Effluents I '
l Oyster Creek Station m 5 =I O 5 l $ l Ef luents I
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Ingestion I Seafood Consumption l
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l 43 pounds of fish and shellfish. For airborne releases, the maxunum hypothetical individual would live at the location of highest radionuclide concentration for inhalation and direct plume exposure while eating 1,389 pounds of vegetables per year. This location is 2,616 meters to the south-southwest based on meteorological air dispersion analysis. 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 airbome effluents and the entire population using the Barnegat 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 l I 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 includmg radon), averages about 100 mrem /yr. The natural background radiation from cosmic cad terrestnal 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 I, that the as crage 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 l
I body dose of 200 millirems (Ref. 4). Efiluent releases from the OCNGS and other nuclear
- power plants contribute a very small percentage to the natural radioactisity which has always been present in the air, water, soil, and even in our bodies.
In general, the annual population doses from natural background radiation (excluding radon) are 1,000 to 1,000,000 times larger than the doses to the same population resulting from nuclear power plant operations (Ref.18).
l Results of the dose calculations are summarized in Tables 8 and 9. Table 8 compares the calculated maxunum dose to an individual of the public with the OCNGS ODCM Specifications, Technical Specifications,10CFR20.1301, and 10CFR50 Appendix 1 dose limits.
Table 9 presents the maxunum total body radiation doses to the population within 50 miles of the i
! ' 60 i
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'l plant from airbome releases, and to the entire population using Barnegat Bay and the Atlantic Ocean, for liquid teleases.
These conservative calculations of the doses to members of the public from the OCNGS resulted l in a manmum dose of only 0.15 percent of the applicable regulatory lirrits. They are also >
considerably lower than the doses from natural background and fallout from prior nuclear weapon tests.
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TABLE 8 CALCULATED MAXIMUM HYPOTHETICAL DOSES TO AN INDIVIDUAL FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM THE OCNGS FOR 1998 5
W EFFLUENT REGULATORY LIMITS PERCENT OF RELEASED CALCULATED DOSE REGULATORY I mrem / YEAR SOURCE mrem / YEAR LIMIT UQUID 3 - TOTAL BODY ODCM SPEC 4.6.1.1.4 8.6E-8 2.9E-6 LIQUID 10 - ANY ORGAN ODCM SPEC 4.6.1.1.4 8.6E.8 8.6E-7 AIRBORNE 100 - TOTAL BODY 10CFR20.1301 4.3E-5 4.3E-5 (NOBLE GAS)
AIRBORNE 3000 - SKIN ODCM SPEC 4.6.1.1.5 6.6E-5 2.2E-6 I (NOBLE GAS)
AIRBORNE (IODINE AND 15 - ANY ORGAN ODCM SPEC 4.6.1.1.7 2.2E-2 1.5E-1 PARTICULATE)
TOTAI-UQUID 25 -TOTAL BODY ODCM SPEC 4.6.1.1.8 1.7E-2 6.8E-2 AND AIRBORNE TOTAL UQUID 75 - THYROID ODCM SPEC 4.6.1.1.8 2.2E-2 2.9E-2 AND AIRBORNE TOTAL UQUID 25 - ANY OTHER ODCM SPEC 4.6.1.1.8 6.6E-5 2.6E 4 AND AIRBORNE ORGAN E
62 a
I TABLE 9 CALCULATED MAXIMUM TOTAL RADIATION DOSES TO THE !
POPULATION FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM THE OCNGS FOR 1998 l I Calculated Population l
Total Body Dose Person-rem / Year l
From Radionuclides in Liquid Releases 1.0E-3 (Bamegat Bay and Atlantic Ocean Users) .
From Radionuclides in Airborne Releases 1.0E-1 (Within 50-Mile Radius of OCNGS) l I l l
DOSE DUE TO NATURAL BACKGROUND RADIATION l
Approxunately 1,230,000 Person-rem Per Year Based upon 1990 Census Data l
l l
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REFERENCES (1) Jersey Central Power and Light Company. Oyster Creek Nuclear Generating Station Operating License and Technical Specifications, Appendix A, DPR-16, April 1969.
(2) GPU Nuclear, Inc. Oyster Creek Offsite Dose Calculation Manual, Procedure 2000-I ADM-4532.04.
(3) GPU Nuclear, Inc. Oyster Creek Nuclear Generating Station, Updated Final Safety Analysis Report.
(4) National Council on Radiation Protection and Measurements, Report No. 93, Ionizing Radiation Exposure of the Population of the United States,1987.
(5) CRC Handbook, Radioecology: Nuclear Energy and the Environment, F. Ward Whicker I
and Vincent Schnitz, Volume I,1982.
(6) National Council on Radiation Protection and Measurements, Report No. 22, Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure, (Published as National Bureau of Standards Handkok 69, Issued Joe 1959, superseding Handbook 52).
(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, Recommendations on Radiation Exposure, (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 9 concerning environmental monitoring; and ICRP Publication 26 (1977).
1 (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 l Radiation Protection Criteria, January 1971.
I I 64
o 1
(10) National Council on Radiation Protection and Measurements, Report No. 62, Tritium in the Environment, March 1979.
(11) National Council on Radiation Protection and Measurements, Report No. 81, Carbon-14
]
in the Environment, May 1985.
I
' 1 (12) United States Nuclear Regulatory Commission. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in The Environs of Nuclear Power Plants, Revision 1, April 1975.
l I (13) United States Nuclear Regulatory Commission Branch Technical Position, An Acceptable Radiological Environmental Monitoring Program, Revision 1. November 1979.
l i
(14) American National Standards Institute, Inc., Performance, Testing, and Procedural l
Specifications for Thermoluminescence Dosimetry, ANSI N545-1975. !
I (15) United States Nuclear Regulatory Commission. Regulatory Guide 4.13, Performance, i
j Testing and Procedural Specifications for Thermoluminescence Dosimetry: ,
Environmental Applications, Revision 1, July 1977. i I (16) United States Nuclear Regulatory Commission. Regulatory Guide 4.15, Quality l
l Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent i Streams and the Environment, Revision 1, February 1979.
(17) United States Nuclear Regulatory Commission. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor EfHuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977.
(18) NUREG/CR-4068, Summary of Historical Experience with Releases of Radioactive Materials from Commercial Nuclear Power Plants in the United States,1985.
lm (19) Olsen, C.R., et. al.,1980. Reactor-released Radionuclides and Fine-grained Sediro.mt Transport and Accumulation Patterns in Bamegat Bay, New Jersey Ltd Adjacent Shelf Waters. Estuarine and Coastal Marine Science (1980) 10,119-142.
lI l
' 65 L
(20) GPU Nuclear Corporation.1986 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1987.
(21) GPU Nuclear Corporation.1987 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1988.
(22) GPU Nuclear Corporation.1988 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1989.
(23) GPU Nuclear Corporation.1989 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1990.
(24) GPU Nuclear Corporation.1990 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1991.
(25) GPU Nuclear Corporation.1991 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1992.
(26) GPU Nuclear Corporation.1992 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating 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 Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1995.
(29) GPU Nuclear Corporation.1995 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1996.
(30) GPU Nuclear, Inc.1996 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1997.
(31) GPU Nuclear, Inc.1997 Radiological Emironmental Monitoring Report for Oyster Creek Nuclear Generating Station. May 1998.
(32) GPU Nuclear, Inc. Oyster Creek Nuclear Generating Station Efiluent and Offsite Dose Report. January 1,1998 through December 31,1998. March 1999.
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I APPENDIX A I 1998 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling I and Analysis Exceptions I
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I I 67 e
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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Distance Azimuth Medium Qde {!pilg) i (derrees) Description TLD 1 0.3 227 SW of site, at OCNGS Fire Pond, Forked River, NJ WWA 1 0.1 208 On-site wells at OCNGS, Forked River, NJ 0.2 359 APT, AIO, TLD 3 6.1 94 E of site, near old Coast Guard Station, Island Beach State Park TLD 6 2.2 14 NNE of site, Lane Place, behind St. Pius Church, Forked River, NJ TLD 8 2.3 180 S of site, Route 9 at the Waretown Substation, Waretown, NJ TLD 9 2.0 230 SW of site, where Route 532 and the Garden State Parkway meet, Waretown, NJ APT, AIO, TLD C 25 309 NW of site, GPU Energy offie.: rear parking lot, Cookstown, NJ TLD 11 8.3 156 SSE of site, 80'" and Anchor Streets at Water Tower, Harvey Cedars, NJ TLD 14 21.7 1 N of site, Larrabee Substation on Randolph Road,Lakewood,NJ i AFT, AIO 20 0.7 93 E of site, on Finninger Farm on south side of access road, Forked River, NJ TLD lc2 1.6 146 SE of site, at 27 Long Silver Way, Skippers Cove, Waretown, NJ SWA, CLAM, AQS 23 4.0 63 ENE of site, Barnegat Bay off Stouts Creek, 400 yards SE of Flashing Light "1" SWA, CLAM, AQS 24 2.0 104 ESE of site, Barnegat Bay, 250 yards SE of Flashing Light "3" SWA, AQS, FISH, 33 0.4 to 0.5 112 to 130 E to SE of site, east of Route 9 Bridge in OCNGS CRAB Discharge Canal l
VEG 35 0.4 110 ESE of site, cast of Rcute 9 and north of the OCNGS Discharge Canal, Forked River, NJ VEG 36 24 315 NW of site, a' ' ".2" Farm, New Egypt, NJ 68
TABLE A-1(Cont.)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample ' Station Distance Azimuth Medsom Qds failg) (derrees) Description WWA 37 2.2 19 NNE of Site, offBoox Road at Lacey MUA Pumping Station, Forked River, NJ WWA , 38 1.6 193 SSW of Site, on Route 532, at Ocean Township MUA Pumping Station, Waretown, NJ TLD 51 0.4 358 N of site, on the access road to Forked River site, Forked River, NJ TLD 52 0.4 340 NNW of site, on the access road to Forked River site, Forked River, NJ TLD 53 0.3 310 NW of site, at sewage liA station on the access road to the Forked River site, Forked River, NJ TLD 54 0.3 294 WNW of site, on the access road to Forked River site, Forked River, NJ TLD 55 0.3 265 W of site, on Southern Area Stores security fence, west of OCNGS Switchyard, Forked River, NJ TLD $6 0.3 250 WSW of site, on utility pole cast of Southern Area Stores, west of the OCNGS Switchyard, Forked River, NJ TLD 57 0.2 203 SSW of site, on Southern Area Stores access road,
_ , Forked River, NJ TLD- 58 0.4 180 S of site, on Southern Area Stores access road, Forked River, NJ
[ TLD 59 0.3 163 SSE of site, on Southern Area Stores access road, Waretown, NJ TLD 61 0.3 116 ESE of site, on Route 9 south of OCNGS Main Entrance, Forked River, NJ l TLD 62 0.2 99 E of site, on Route 9 at access road to OCNGS Main Gate, Forked River, NJ TLD ,63 0.2 70 ENE of site, on Route 9 at access road to OCNGS North Gate, Forked River, NJ TLD 64 0.3 48 NE of site, on Route 9 north of OCNGS North Gate access road, Forked River, NJ TLD 65 0.4 22 NNE of site, on Route 9 at Intake Canal Bridge, Forked River, NJ 69 f
TABLE A-1(Cont.)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Distance Azimuth Medium Code (miles) (derrees) Description AFT, AIO, TLD, 66 0.5 127 SE of site, east of Route 9 and south of the Discharge I VEG TLD 68 1.2 271 Canal, Waretown, NJ W of site, on Garden State Parkway at mile j
marker 71.7 l
AFT, AIO, TLD 71 1.7 165 SSE of site, on Route 532 at the Waretown Municipal Building, Waretown, NJ APT, AIO, TLD 72 1.9 26 NNE of site, on Lacey Road at Knights oi Columbus Hall, Forked River, NJ AFT, AIO, TLD 73 1.8 111 ESE of site, on Bay Parkway, Sands Point Harbor, Waretown, NJ I TLD 74 2.0 90 E of site, Orlando Drive and Penguin Court, Forked River, NJ I TLD 75 2.0 69 ENE of site, Beach Blvd. and Maui Drive, Forked River, NJ TLD 78 1.8 2 N of site,1514 Arient Road, Forked River, NJ TLD 79 2.9 162 SSE of site, Hightide Drive and Bonita Drive, Waretown, NJ TLD 81 4.6 192 SSW of site, east of Route 9 at Brook and School Streets, Barnegat, NJ TLD 82 4.4 38 NE of site, Bay Way and Clairmore Avenue, Lanoka Harbor, NJ TLD 84 4.8 339 NNW of site, on Lacey Road,1.3 miles west of the Garden State Parkway on siren pole, Forked River, NJ TLD 85 3.8 254 WSW of site, on Route 532, just east of Wells Mills Park, Waretown, NJ TLD 86 4.8 226 SW of site, on Route 554,1 mile west of the Garden State Parkway, Barnegat, NJ I TLD 88 6.6 127 d
SE of site, eastern end of 3 Street, Barnegat Light, NJ I TLD 89 6.2 110' ESE of site, Job Francis residence, Island Beach State Park I TLD 90 6.6 74 ENE of site, parking lot A-5, Island Beach State Park 70
I TABLE A-1(Cont.)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Distance Azimuth Medium Code (miles) (derrees) DescriDtion TLD 92 9.2 48 NE of site, at Guard Shack / roll Booth, Island Beach State Park FISH 93 0.1 to 0.3 128 to 250 SE to WSW of site, OCNGS Discharge Canal between Pump Discharges and Route 9, Forked River, NJ SWA, AQS, CLAM, 94 21.8 201 SSW of site, in Great Bay /Little Egg Harbor FISH TLD 98 1.3 297 WNW of site, on Garden State Parkway at mile marker 72.3 TLD 99 1.5 318 NW of site, on Garden State Parkway at mile marker 72.8 I TLU Tl 0.3 227 SW of site, at OCNGS Fire Pond, Forked River, NJ I SAMPLE MEDIUM IDENTIFICATION KEY APT = AirParticulate SWA = Surface Water TLD = Thermoluminescent Dosimeter AIO = AirIodine AQS = Aquatic Sediment FISH = Fish WWA = Well Water CLAM = Clams CRAB = Crab VEG = Vegetables I
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I . 71
I l
TABLE A-2 SYNOPSIS OF THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR THE OYSTER CREEK NUCLEAR GENERATING STATION 1998 (1)
SAMPLE TYPE NUMBER OF COLLECTION NUMBER OF TYPE OF ANALYSIS NUMBER OF SAMPLING FREQUENCY SAMPLES ANALYSIS FREQUENCY SAMPLES LOCATIONS COLLECTED ANALYZED (2)
Air Particulate 7 Bi-weekly 183 Gross Beta Bi-weekly 183(3)
Gamma Quarterly composite 28 AirIodine 7 Weekly 364 I-l31 Weekly 364 Well Water 3 Quarterly 12 Gamma Quarterly 12 H-3 Quarterly 12 Surface Water 4 2 locations-Monthly 28 Gamma Monthly 28 4 locations - Semi- H-3 (2 Stations) 28 Annually .
Semiannually (4 Stations)
Clam 3 Semiannually 6 Gamma Semiannually 6 Sediment 4 Semiannually 8 Gamma Semiannually 8 Vegetables 2 Monthly (4) 18 Gamma Monthly (4) 18 Fish 3 Semiannually 18 Gamma Semiannually 18 Crab i Annually 1 Gamma Annually 1 TLD-Teledyne 4 Quarterly 16 Immersion Dose Quarterly 16 Brown Engineering TLD-Panasonic 44 Quarterly 170 Immersion Dose Quarterly 170 (1) This table does not include Quality Assurance (QA) samples.
(2) The number of samples analyzed does not include duplicate analyses, recounts, or reanalyses.
(3) See Table A-3.
(4) Collected during harvest season only.
' 72 l
[
TABLE A-3 1998 SAMPLING AND ANALYSIS EXCEPTIONS During 1998, 638 samples were collected from aquatic, atmospheric, and terrestrial environments around the OCNOS. This is far more than the muumum number of samples required by the Offsite Dose Calculation Manual (ODCM) Specifications. There were sampling and analysis exceptions that occurred in 1998 that resulted in minor desiations from the requirements of the ODCM. These deviations did not ccanpromise GPUN's ability to assess the impact of the OCNGS on public health or the environment because the scope of the monitoring program exceeds the ODCM requirements. The circumstances surrounding these events are described below.
On September 3,1998, Instrument and Control Technicians were calibrating the air sampler at Station 66. Because there was a higher than usual loading on the particulate filter, the technicians replaced the particulate filter. Because of this, two filters were used to collect the sample during the two week collection period, as opposed to a single filter being used. Both filters were analyzed separately and the activity detected on each filter was within the normal range.
During the year,170 out of a possible 176 Panasonic TLDs were collected and analyzed. Six TLD's, which were lost due to vandalism, are listed below:
STATION COLLECTION ODCM REQUIRED LOCATION DATE STATION 75 16 Apr 98 NO 6 22 Jul 98 YES 85 14 Oct 98 YES 6 14 Oct 98 YES 68 15 Oct 98 YES 51 13 Jan 99 YES
(
l 73
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I APPENDLX B 1998 Lower Limits of Detection (LLD) Exceptions I
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- 6. s i....
1998 LOWER LIMTFS OF DETECTION (LLD) EXCEPTIONS During 1998, there were no Lower Limit of Detection (LLD) violations on any analyzed REMP sample.
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I 75 m
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t I
'I I
I APPENDIX C Changes to the REMP During 1998 I
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I il "
l Table C-1 Channes to the REMP during 1998 January,1998 The background TLD station at Allenhurst, NJ (Station A) was elimmated and reestablished in Lakewood, NJ (Station 14). Station 14 is located 21.7 miles from OCNGS at an azimuth of I degree. The Lakewood station is in a more practical location in regard to the TLD replacement tour.
May,1998 A vegetable garden was reestablished at Station 66. The vegetable garden at this location had been eliminated in 1997 in lieu of collecting broadleaf vegetation from this location. This change allows for easier and quicker access to broadleaf vegetation.
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I t
77
i APPENDIX D Radionuclide Concentrations in 1998 Environmental Samples I
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