ML20082R325

1994 Radiological Environ Monitoring Rept

ML20082R325
Person / Time
Site:	Oyster Creek
Issue date:	12/31/1994
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-95-2150, NUDOCS 9505020051
Download: ML20082R325 (165)

Text

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Route 9 Suuth Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

C321-95-2150 April 27,1995 i

U.S. Nuclear Regulatory Commission Att: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Radiological Erwironmental Monitoring (REMP) Report Enclosed is a copy of the Oyster Creek REMP report for 1994. This submittal is made in acconlance with Technical Specification 6.9.1.e.

If you should have any questions or require further information, please contact Brenda DeMerchant, OC Licen3ing Engineer at (609) 971-4642.

Very truly yours, John J. Barton Vice President & Director Oyster Creek JJB/BDEM:je ec: Administrator, Region i Senior NRC Resident Inspector Oyster Creek NRC Project Manager Chief, Bureau of Nuclear Engineering 9505020051 941231 i PDR ADOCK 05000219 / '

R PDR /t I GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation 0/

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OYSTER CREEK NUCLEAR GENERATING STATION.

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

Construction began in December 1963. The station began commercial operation on December 23,1969, and at that time was the largest nuclear facility in the United States solely financed by a private company. -

The Reactor Building, Turbine Building and Ventilation Stack are the most prominent structures at the site. The Reactor Building stands approxi-mately 150 feet high with 42 feet extending below grade. The Reactor Building serves as a secondary containment and houses the primary containment (dryweII), the reactor vessel and its auxiliary systems which comprise the Nuclear Steam Supply System. The drywell, which houses the reactor vessel, is constructed of high-density reinforced concrete with an inner steelliner measuring 120 feet high and 70 feet in diameter.

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

The 652-ton reactor contains 560 fuel assemblies, each with 62 fuel rods that are 12 feet long, and 137 control rods. The reactor operates at a nominalpressure of 1,020 pounds per square inch and an average temperature of 540 degrees Fahrenheit.

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

Steam is supplied to the high pressure turbine from the reactor. After being used to drive the turbines and generator, the steam is condensed in the main condensers and returned to the reactor vesselin the form of water through the con-densate and feedwaterpumps.

The main condensers consist of three horizontal, single pass, divided water boxes containing 44,000 tubes having a totallength of about 1,875,000 feet. Cooling water is provided from Bamegat Bay, through the South Branch of the Forked River and passes through the condensers and discharges into Oyster Creek for retum to Barnegat Bay. The water is pumped by four 1,000-horsepowerpumps, each of which moves about 115,000 gallons per minute through the 6 foot diameterpipes that feed the condensers.

The ventilation stack is 368 feet high with 26 feet extend-ing below grade. The stack provides ventilation for the Reactor Building, Turbine Building and Radwaste Facilities.

Oyster Creek is owned by Jersey Central Power & Light (JCP&L) Company and oper-atedby GPUNuclear (GPUN) l Corporation. JCP&L and GPUN are units of the GPU System.

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1994 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT PREPARED BY OYSTER CREEK ENVIRONMENTAL ArrAIas GPU NUCLEAR CORPORATION

TABLE OF CONTENTS PAGE TABLE OF CONTENTS i LIST OF TABLES iii LIST OF FIGURES V

SUMMARY

AND CONCLUSIONS 1 INTRODUCTION 4 Characteristics of Radiation 4 Sources of Radiation 6 Nuclear Reactor Operations 10 Sources of Liquid and Airborne Effluents 13 DESCRIPTION OF THE OYSTER CREEK NUCLEAR GENERATING STATION SITE 16 General Information 16 Climatalogical Summary 17 EFFLUENTS 21 Historical Background 21 Effluent Release Limits 22 Effluent Control Program 25 Effluent Data 27 RADIOLOGICAL ENVIRONMENTAL MONITORING 31 Environmental Exposure Pathways to Humans from Airborne and Liquid Effluents 32 Sampling 33 Analysis 34 Quality Assurance Program 38 1 DIRECT RADIATION MONITORING 77 Sample Collection and Analysis 77 Results 79 ATMOSPHERIC MONITORING B4 Sampie col 1ection and Analysis 84 Results 85 AQUATIC MONITORING 89 l'

Sample Collection and Analysis 89 ResultS 90 i

TABLE OF CONTENTS (Continued)

PAGE TERRESTRIAL MONITORING 95 Sample Collection and Analysis 96 Results 96 GROUNDWATER MONITORING 98 Sample Collection and Analysis 98 Results 99 RADIOLOGICAL IMPACT OF OCNGS OPERATIONS 101 Determination of Radiation Doses to the Public 101 Results of Dose Calculations 105 REFERENCES 109 APPENDIX A: 1994 REMP Sampling Locations and 113 Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions APPENDIX B: 1994 Lower Limits of Detection (LLD)

Exceptions 125 APPENDIX C: Changes Effected in the 1994 REMP 127 APPENDIX D: 1994 Quality Assurance Results 129 APPENDIX E: 1994 EPA Cross-Check Results 134 APPENDIX F: 1994 Annual Dairy Census 138 APPENDIX G: Dose Calculation Methodology 140 APPENDIX H: 1994 Groundwater Monitoring Results 146 APPENDIX I: 1994 REMP Sampie Col 1ection and Analysis Methods 149 APPENDIX J: 1994 TLD Quarterly Data 152 l

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LIST OF TABLES TABLE TITLE PAGE 1 Sources and Doses of Radiation 7 2 Radionuclide Composition of OCNGS Effluents for 1994 28 3 Radiological Environmental Monitoring Program Summary, Oyster Creek Nuclear Generating Station - January 1994 through December 1994 42 4 TLD Exposure Periods During 1994 78 5 Species of Fish Caught as Part of the OCNGS REMP in 1994 94 6 Calculated Maximum Hypothetical Doses to an Individual from Liquid and Airborne Effluent Releases from OCNGS for 1994 107 7 Calculated Maximum Total Radiation Doses to the Population from Liquid and Airborne Effluent Releases from the OCNGS for 1994 108 A-1 Radiological Environmental Monitoring Program Sampling Locations 114 A-2 Synopsis of the Operational Radiological Environmental Monitoring Program - 1994 123 A-3 Sampling and Analysis Exceptions - 1994 124 B-1 1994 Lower Limits of Detection (LLD) Exceptions 126 C-1 Changes Effected in the 1994 REMP 128 D-1 1994 QA Sample Program - Number of Duplicate l Analyses Performed 131 l D-2 1994 OA Sample Program - Split Samples 132 D-3 Resolution of 1994 OCNGS REMP 5plit Samp1e Analytical Non-Agreements 133 E-1 US EPA Cross-Check Program 1994 135 l

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LIST OF TABLES (Continued)

TABLE TITLE PAGE G-1 Summary of Maximum Hypothetical Individual and Population Doses from Liquid and Airborne Effluent Releases from the OCNGS for 1994 145 H-1 OCNGS - 1994 Groundwater Results 147 I-1 Summary of Sample Collection and Analysis Methods 1994 150 J-1 1994 Quarterly Environmental TLD Report -

Teledyne Isotopes 153 J-2 1994 Quarterly Environmental TLD Report -

Panasonic 154 i

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LIST OF FIGURES  !

FIGURE TITLE PAGE 1 Oyster Creek Nuclear Generating Station Simplified Schematic. 11 2 Monthly Precipitation at the Oyster Creek '

Nuclear Generating Station During 1994 -

Compared with Historical (1946-1981) .

Atlantic City National Weather Service

. Average Precipitation Data 19 3 Location of Radiological Environmental Monitoring Program (RENP)' Stations  ;

Within One Mile of the Site 35  ;

4 Location of Radiological Environmental i Monitoring Program (REMP) Stations i Greater than One Mile and Within i Two Miles ~of the Site 36 j 5 Location of Radiological Environmental Monitoring Program (REMP) Stations Greater than Two Miles From the Site 37 6 Mean Panasonic TLD Gamma Dose-1989 through 1994-Indicator and Background Mean 80 7 Mean Panasonic TLD Gamma Dose for 1994 Based on Distance from OCNGS 81 l

l 8 Mean Teledyne and Panasonic TLD Gamma Dose

) for 1994 - Mean Dose in Affected Compass Sector 82 l 9 Weekly Mean Air Particulate Gross Beta l Concentrations for 1994 - :ndicator and Background Mean 86 l 10 Monthly Mean Air Particulate Gross Beta Concentrations - 1984 through 1994 87 11 Mean Cobalt-60 c.oncentration in Aquatic l l Sediment - 19&e through 1994 92 l

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l LIST OF FIGURES (Continued)

FIGURE TITLE PAGE 12 Mean Cobalt-60 Concentration in Clams -

1983 through 1994 93 '

13 Exposure Pathways for Radionuclides l Potentially Released from the OCNGS 103 H-1 Locations of On-Site Wells 148 i

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SUMMARY

ANT CONQLUSIONS The radiological environmental monitoring performed during 1994 by the GPU Nuclear Environmental Affairs Department at the Oyster Creek Nuclear Generating Station (OCNGS) is discussed in this report. The operation of a nuclear power plant results in the release of small amounts of radioactive materials to the environment. A radiological environmental monitoring program (REMP) has been established to monitor radiation and radioactive materials in the environment around the OCNGS. The program evaluates the relationship between

amounts of radioactive material released in effluents to the 4

environment and ~ resultant radiation doses to individuals.

Summaries and interpretations of the data were published semiannually from 1969-1985 and annually since 1986 (Ref. 18 through 25). Additional information concerning releases of 1

radioactive materials to the environment is contained in the Semi-Annual and Annual Effluent Reports submitted to the United States Nuclear Regulatory Commission (USNRC). }

During 1994, as in previous years, the radioactive effluents associated with the OCNGS were a small fraction of the applicable federal regulatory limits and did not have significant or measurable effects on the quality of the environment. Calculated maximum hypothetical radiation doses

, to the public attributable to 1994 operations at the OCNGS ranged from 0.00011 percent to a maximum of only 0.58 percent of the applicable regulatory limits. Furthermore, they were significantly less than doses received from other man-made sources and natural background sources of radiation.

Radioactive materials considered in this report are normally present in the environment, either naturally or as a result of non-OCNGS activities such as prior atmospheric nuclear weapons testing, medical industry activities, and the Chernobyl 1

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l accident. Consequently, measurements made in the vicinity of the site (i.e. taken at indicator stations) were compared to l background measurements to determine any impact of OCNGS  :

operations. Samples of air, precipitation, well water,  ;

surface water, clams, sediment, fish, crabs, vegetables, and 1 soil were collected. Samples were analyzed for radioactivity including tritium (H-3), gross beta, and gamma-emitting  ;

radionuclides. External penetrating radiation dose measurements also were zade using thermoluminescent dosimeters (TLDs) in the vicinity of the OCNGS.

l The results of environmental measurements were used to assess l

l the environmental impact of OCNGS operations, to demonstrate

[ compliance with the Technical Specifications (Ref. 1), the l Offsite Dose Calculation Manual Specifications (Ref. 2),

applicable federal regulations, and to verify the adequacy of containment and radioactive effluent control systems. The data collected by the REMP provided a historical record of the levels of radionuclides and radiation attributable to natural causes, worldwide fallout from prior nuclear weapons tests, and OCNGS operations.

Radiological impacts in terms of radiation dose as a result of OCNGS operations were calculated and also are discussed. The results provided in this report are summarized in the following highl.f.ghts:

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o During 1994, 1745 samples were taken from the aquatic, atmospheric, and terrestrial environments around OCNGS.

A total of 2152 analyses were performed on these samples.

Three hundred seventeen (317) direct radiation dose i measurements using TLDs also were made. Fifty-four (54) groundwater samples, including local domestic water supplies, were collected and one hundred thirty-four (134) analyses were performed on these samples.

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o In addition to natural radioactivity, trace levels of i cesium-137 (Cs-137) were detected in various media and were attributed to fallout from prior nuclear weapons testing and the Chernobyl nuclear accident.

o Cobalt-60 (Co-60) was detected in sediment samples as a result of OCNGS operations. Although Co-60 had been detected in clams from the Barnegat Bay system in prior study years, this nuclide did not appear in clam samples collected during 1994 and has not been detected since 1987.

o Cobalt-60 (Co-60), attributable to OCNGS effluents, was detected in one non-potable water sample from a shallow (17 ft.) monitoring well located within the OCNGS protected area. This was ascribed to a minute quantity of Co-60 bound to fine sediments entering this well through a cracked well casing. The casing was repaired and a subsequent sample showed no Co-60 activit'y.

o The predominant radionuclide released in OCNGS effluents was xenon-135 in gases. No liquid releases were made from the OCNGS in 1994. Estimated radiation doses to the public, attribut sle to 1994 effluents, ranged from l 0.00011 percent to a maximum of only 0.58 percent of l applicable regulatory limits.

o During 1994, the maximum whole body dose potentially received by an individual from airborne effluents was I

estimated to be about 0.0044 millirems. The whole body dose to the surrounding population from airborne effluents was calculated to be 0.35 person-rem. This is approximately 2.83 million times lower than the dose that l the total population in the OCNGS area receives from 1

natural background sources.

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INTRODUCTION Characteristics of Radiation Instability within the nucleus of radioactive atoms results in the release of energy in the form of radiation. Radiation is classified according to its nature -

particulate and electromagnetic. Particulate radiation consists of energetic subatomic particles such as electrons (beta particles),

protons, neutrons, and alpha particles. Because of its

limited ability to penetrate the human body, particulate radiation in the environment contributes primarily to internal radiation exposure resulting from inhalation and ingestion of r.dioactivity.

Electromagnetic radiation in the form of x-rays and gamma rays has characteristics similar to visible light but is more energetic and, hence, more penetrating. Although x-rays and gamma rays are penetrating and can pass through varying thicknesses of materials, once they are absorbed they produce energetic electrons which release their energy in a manner that is identical to beta particles. The principal concern for gamma radiation from radionuclides in the environment is 4

their contribution to external radiation exposure.

The rate with which atoms undergo disintegration (radioactive decay) varies among radioactive elements, but is uniquely constant for each specific radionuclide. The term " half-life" defines the time it takes for half of any amount of an element to decay and can vary from a fraction of a second for some radionuclides to millions of years for others. In fact, the natural background radiation to which all mankind has been exposed is largely due to the radionuclides of uranium (U),

thorium (Th), and potassium (K). These radioactive elements i

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l l were formed.with the creation of the universe and, owing to their long half-lives,. will continue to be present. for  ;

millions of years to come. For example,-potassium-40 (K-40) has a half-life of 1.3 billion years and. exists naturally l within our bodies. As a result, approximately 4000' atoms of  ;

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potassium emit radiation internally'within each of us every i second of our life.

In assessing the impact of radioactivity.on the environment, ,

it is important to know the quantity of radioactivity released  !

and the resultant radiation doses. The common unit of radioactivity is the curie (Ci). It represents the radioactivity in one gram (g) of natural radium (Ra) which is also equal to a decay rate of 37 billion rcdiation emissions; every second. Because of the ' extremely small amounts of radioactive material in the environment, it is more convenient i to use fractions of a curie. Subunits like picocurie'(pci),

(one trillionth of a curie), are frequently used to express j

the radioactivity present in environmental and biological ]

samples. ,

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! l l The biological effects of a specific dose of. radiation are the l same whether the radiation source is external or internal to l f the body. The important factor is how much radiation energy or dose was deposited. The unit of radiation dose is.the Roentgen Equivalent Man (rem), which also incorporates the

l. variable effectiveness of different forms of radiation to l produce biological change. For ' environmental radiation q

! exposures, it is convenient to use the smaller unit of I i millirem (mrem) to express dose (1000 mrem equals 1 rem).

When radiation exposure occurs over periods of time, it is l appropriate to refer to the dose rate. Dose rates, therefore, l

define the total dose for a fixed interval of time, and for environmental exposures, are usually measured with reference i to one year of time (mrem per year).

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t Sources of Radiation i

Life on earth has evolved 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, sorae people receive more than others. Radiation exposure from natural background has three components (i.e., cosmic, terrestrial, and . internal) . and varies with altitude and geographic location, as well as with

, living habits.

For example, cosmic radiation originating from deep interstellar space and the sun increases with altitude, since there is le'ss air which acts as a shield. Similarly, terrestrial radiation resulting from the presence of naturally occurring radionuclides in the soil varies and may be significantly higher in some areas of the country than in j others. Even the use of particular building materials 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, drinking water contains trace amounts of uranium and radium, and milk contains radioactive potassium. Table 1 summarizes the common sources of radiation and their average annual doses.

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TABLE 1 (Ref. 4) l Sources and Doses Of Radiation

• l Natural (82%) Maneede (18%)

I Radiation Dose Radiation Dose l Source (mRemlvearl Source (mRemlyear)

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

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

Tcrrestrial 28 (8%) Consumer products 10 (3%)

Internal 40 (11 %) Other < 1 (< 1%)

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

& nuclear fuel cycle)

APPROXIMATE TOTAL 300 APPRDXIMATE TOTAL 60 l

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

The average person in the United States receives about 300 mrem /yr (0.3 rem /yr) from natural background radiation sources. This estimate was revised from about 100 to 300 mrem because of the inclusion of radon gas which has always been present but has not been previously included in the calculations. In some regions of the country, the amount of natural radiation is significantly higher. Residents of Colorado, for example, receive an additional 60 mrem /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 additional 1 mrem /yr from cosmic radiation. In l several regions of the world, high concentrations of uranium ,

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( and radium deposits result in doses of several thousand 1 mPem/yr to their residents (Ref. 4).

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Recently, public attention has focused on radon (Rn), a l naturally occurring radioactive gas produced from uranium and l radium decay. These elements are widely distributed in trace j- amounts in the earth's crust. Unusually high concentrations .;

i have been found in certain parts of eastern Pennsylvania and northern 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 f are needed to determine the full extent of the problem j nationwide. Radon is the largest component of ~ natural j background radiation and may be responsible for a substantial 1

number of lung cancer deaths annually. The National Council on Radiation Protection and Measurements (NCRP) estimates that the average individual in the United States receives an annual

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dose of about 2,400 mrem to the lung from natural radon gas

(Ref. 4). This lung dose is considered to be equivalent to a l l whole body dose of 200 millirems. The NCRP has recommended.

j actions to control indoor radon sources and reduce exposures, a

When radioactive substances are inhaled or swallowed, they are

distributed within the body in a nonuniform fashion. For

example, radioactive iodine selectively concentrates in the j

thyroid gland, radioactive cesium is distributed throughout the body water and muscles, and radioactive strontium l concentrates in the bones. The total dose to organs by a '

{ given radionuclide also is influenced by the quantity and the

duration of time that the radionuclide remains in the body, 1 including its physical, biological, and chemical j characteristics. Depending on their rate of. radioactive decay

{ and biological elimination from the body, some radionuclides j stay in the body for very short times while others remain for j years.

1 j In addition to natural radiation, we are exposed to radiation j from a number of man-made sources. The single largest of 1

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f these sources comes from diagnostic medical- x-rays, and nuclear medicine procedures. Some 180 million Americans receive medical x-rays each year. The annual dose to an individual from such radiation avera ges about 53 millirems.

1 Much smaller doses come from nuclear weapons fallout and consumer products such as televisions, smoke detectors, and fertilizers. Production of commercial nuclear power and its I associated fuel. cycle contributes less than 1 mrem to the annual dose of about 300 mrem for the average individual living in the United States.

i i Fallout commonly refers to the radioactive debris that settles to the surface of the earth following the detonation of j nuclear weapons. It is dispersed throughout the environment i either by dry deposition or washed down to the earth's surf ace

by precipitation. There are approximately 200 radionuclides l produced in the nuclear weapon detonation process; a number of

these are detected in fallout. The radionuclides found in fallout which produce most of the fallout radiation exposures to humans are iodine-131 (I-131), strontium-89 (Sr-89),

cesium-137 (Cs-137), and strontium-90 (Sr-90) . There has been no atmospheric nuclear weapon testing since 1980 and many of the radionuclides, still present in our environment, have decayed significantly. Consequently, doses to the public from fallout have been decreasing. '

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As a result of the nuclear accident at Chernobyl, USSR, on April 26, 1986, radioactive material was dispersed throughout

, the environment and detected in various media such as air, 1

milk, and soil. Cesium-134, cesium-137, iodine-131, and other radionuclides were detected in the weeks following the Chernobyl accident.

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Nuclear Reactor Operations Common to the commercial production of electricity is the consumption of fuel which produces heat to make steam which turns the turbine-generator which generates electricity.

Unlike the burning 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 of uranium 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 with heat, radiation and free neutrons. The free neutrons travel through the reactor and are similarly absorbed by the uranium, permitting the fission process to continue. As this process continues, more fission products, radiation, heat, and neutrons are produced and a sustained reaction occurs. The heat produced is transferred -

via reactor coolant water - from the fuel to produce steam which drives a turbine-generator to produce electricity. The l fission products are mostly radioactive; that is, they are l unstable atoms which emit radiation as they decay to stable atoms. Neutrons which are not absorbed by the uranium fuel l may be absorbed by stable atoms in the materials which make up the components and struct9res of the reactor. In such cases, stable atoms often become radioactive. This process is called activation 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 contained within sealed 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 for use in the turbine. After the energy is extracted 10

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1 from the steam in the turbine, it is cooled and condensed back l 1

into water in the main condensers. This condensate is then l pumped back into the reactor vessel.

l Several hundred radionuclides of some 40 different elements  !

are created during the process of generating electricity.

Because of reactor engineering designs, the short half-lives of many radionuclides, and their chemical and physical properties, nearly all radioactivity is contained.

The OCNGS reactor has six independent barriers that confine radioactive materials produced by the reactor fuel as it heats

) the water. Under normal operating conditions, essentially all radioactivity is contained within the 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 operating temperatures may not be contained in the fuel.

The second barrier consists of zirconium (Zr) alloy tubes (termed " fuel cladding") that resist corrosion and degradation due to high temperatures. The fuel pellets are contained within these tubes. There is a small gap between the fuel and the cladding, in which the noble gases and other volatile radionuclides colle'ct and are contained.

The primary coolant water is the third barrier. Many of the d

fission products, including radioactive iodine, strontium and cesium are soluble and are retained in water in an ionic (electrically charged) form. These materials can be removed 1 in the reactor coolant purification system. However, krypton (Kr) and xenon (Xe) do not readily dissolve in the coolant, l

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particularly at high temperatures. Krypton and xenon collect as a gas above the condensate when the steam is condensed.

The fourth barrier consists of the reactor pressure vessel, turbine, condenser, 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, provides containment for radioactivity in the primary coolant.

The drywell provides the fifth barrier. It is a steel-lined vessel surrounded by concrete walls approximately 4 1/2 to 7 1/4 feet thick that enclose the reactor pressure vessel and recirculating 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 maintained at a negative pressure.

l Sources of Licuid and Airborne Effluents l Although the previously described barriers contain radioactivity with high efficiency, small amounts of l radioactive fission products are nevertheless able to diffuse or migrate through minor flaws in the fuel cladding and into the reactor coolant. Trace quantities of reactor system component and structural surfaces which have been activated, also get into the reactor coolant water. Many of the soluble fission and activation products such as iodines, strontiums, cobalts, and cesiums are removed by demineralizers in the purification system of the reactor coolant. The physical and 13

J chemical properties of noble gas fission products in the primary coolant prevent their removal by the demineralizers.

Because the reactor system has many valves and fittings, an d

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

Reactor off-gas, consisting primarily of hydrogen and radioactive non-condensable gases, is withdrawn from the reactor primary system by steam jet air ejectors. These air ejectors drive the process stream through a 60 minute holdup pipe at approximately 110 cubic feet per minute and then into the Augmented Off-Gas (AOG) System. The holdup pipe allows i radionuclides with short half-lives to decay. The 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 of f-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 4

stack, it is diluted by building ventilation, which averages approximately 200,000 cubic feet per minute, is monitored and sampled, and then is discharged out the top of the 368-foot stack.

The liquid waste processing system receives water contaminated with radioactivity and processes it by filtration, d

14

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

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I  :

a.

2 I

demineralization, and distillation. Purified radwaste water  !

l

, is recycled to the plant. Occasionally, it has been necessary

to discharge this purified water, under-the guidelines of i applicable permits, to the environment. Contaminants removed i during the purification process are stored in the radwaste

] building and are eventually disposed of via the radioactive i j 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 }i j has a' flow rate of 460,000 to'960,000 gallons per minute. i a i k

i i i i l4  !

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E. _ _ . -- -

_. . , __l

l DESCRIPTION OF THE OCNGS SITE General Information The Oyster Creek . Nuclear Generating Station is located in Lacey Township of Ocean County, New Jersey, about 60 miles J

south of Newark, 9 miles south of Toms River and 35 miles l north of Atlantic City. It lies approximately 2 miles inland from Barnegat Bay. The site, covering 1416 acres, is situated partly in Lacey Township and, to a lesser extent, in Ocean Township. The Garden State Parkway bounds the site on the west. Overland 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. The station is about 1/4 mile west of the highway and 1-1/4 miles east of the Parkway. The site property extends about 3-1/2 miles inland from the bay; the maximum width in the

! north-south direction is almost 1 mile. The site location is part of the New Jersey shore area with its relatively flat topography and extensive freshwater and saltwater marshlands.

The south branch of Forked River runs across the northern side of the site, and Oyster Creek partly borders the southern side.

It is estimated that approximately 3.3 million people reside within a 50 mile radius of the station (Ref. 3). The nearest population center is Ocean Township (population 5416) which lies less than two miles south-southeast of the site. Two miles to the north, 22,141 people reside in Lacey Township.

Dover Township, situated 9.5 miles to the north, is the nearest major population center with a population of 76,371.

The region adjacent to Barnegat Bay is one of the State's most rapidly developing areas. In addition to the resident population, a sizeable seasonal influx of people occurs during the summer. This influx occurs almost exclusively along the waterfront.

16

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

i 4

Climatolocical Summarv i

i. Meteorological data for 1994 were obtained from an on-site weather station. Data were routinely - quality assured and j categorized for 'further analyses, including historical I comparisons to both onsite and offsite sources.

Wind direction frequencies were climatologically normal for the year. The highest wind frequencies occurred'in the east-l southeast, east,- east-northeast and northeast sectors. 'The 4

! latter wind direction represents the_ normal late spring i - .

! through early autumn pattern of maritime tropical air i

i originating in the Gulf of Mexico. This air mass is described  :

I by above average humidity and temperatures. The other wind directions are characteristic of a normal climatological j weather pattern of westerly flow of air synonymous with these latitudes. ,

} This is especially true during the late autumn l through early spring seasons. These westerly' air masses are J l

characterized by low humidity and normal to below normal temperatures. Seasonal winds were evident, including the sea {

breeze circulation (Ref. 3) during the late spring through early autumn season.

1 The annual average tempsrature for the year was 53.2 degrees Fahrenheit. The normal average annual temperature for the j year is 53 degrees. During the 1993 calendar year, the annual average temperature was 53.1 degrees. During'1994, however, there were some differences from the past year. For example, below normal temperatures were experienced during the month of January. In fact, the average monthly temperature in January was 10 degrees lower than in January 1993. There were at least 7-10 storms in which some form of mixed precipitation fell (rain / snow / sleet) in the area. By February and for the remainder of the spring, temperatures in 1994 were higher than in 1993. The summer was described by below- normal temperatures except during June, where temperatures were 17

4 1

i I slightiv higher. The cooler trend persisted through early 1

autumn. The year finished out approximately 5 degrees above l normal for both November and December. During 1994 i temperatures ranged from a high of 95 degrees in June to a low

, of -3. 8 degrees in .Tanuary.

Precipitation totals varied greatly from month to month (Figure 2). The annual total amount of precipitation was 43.18 inches. This was approximately 1.68 inches higher than j the Atlantic City National Weather Service historical average (1946-1981) of 41.50 inches. Monthly totals ranged from 7.22 j inches in August to 0.68 incnes in October. Three months in-j which rainfall totals exceeded the monthly Atlantic City i

historical average by a large margin were March, July and i

1 August. During 1994, there were seven rainfall events in j which more than 1 inch of liquid equivalent precipitation

, fell. A strong, northeast storm occurred on March 28 in which I over 2.00 inches of rain fell in the area. This' storm also J

brought high winds, tides and beach erosion. During the other  !

j months, p';ecipitation was largely the result of three

$ activities. One source of precipitation was . f rom large

! extratropical storms, including the storm which occurred in

! March. Another source of above normal precipitation occurred

during the passage of warm fronts, especially during the j spring and summer. Much of the precipitation during the summer months of July and August were associated with a i

stationary weather front that remained over the region for I over two weeks. During these situations, small storms tend to form and travel along this front. The third type of precipitation event was from convective activity due to i thunderstorms and rain showers. This situation is predominant

in the spring and summer months and occurs over short distances and time frames. Convection of any type can produce

cloudbursts and associated flash flooding. There were no hurricanes or major snowfall events during the calendar year.

1 18 4

i

MONTIILY PRECIPITATION OYSTER CREEK NUCLEAR GENERATING STATION ,

i DURING 1994 COP.1 PARED WITII IIISTORICAL (1946-1981)

ATLANTIC CITY NATIONAL WEATilER SERVICE AVERAGE PRECIPITATION DATA ,

RAINFALL IN INCIIES to l

O OYSTER CREEK NGS E ATLANTIC CITY HISTORICAL I 7.22 7.12 m i 6

4.98 393 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC

For additional site specific meteorological data, refer to the OCNGS Annual Radioactive Effluent Release Report for 1994 (Ref. 26).

l l

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l 20 l

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f EFFLUENTS l

i '

} Historical Backaround Almost from the outset of the discovery of x-rays in 1895 by j

Wilhelm' Roentgen, the potential hazard.of ionizing radiation .

was recognized and efforts-were made to establish radiation '

{

J protection . standards. The International Commission on 1

j Radiological Protection (ICRP) and the National Council on

)

Radiation Protection and Measurements'(NCRP) were established  !

j' in 1928 and 1929, respectively. These organizations have the j l longest continuous experience in . the review 'of radiation l health effects and with making recommendations on guidelines  ;

j for radiolog! 11 protection and radiation exposure limits. In.

l 1955, the United Nations created a Scientific Committee on the l Ef fects of AtoLiic Radiation (UNSCEAR) to summarize reports [

received on radiation levels and the effects on man and his j environment. The National Academy of Sciences (NAS) formed a i I

committee in 1956 to review the biological effects of atomic I f radiation (BEAR). A series of reports have been issued by-  !

l this and succeeding NAS committees on the biological effects j of ionizing radiation (BEIR), the most recent during 1990 ,

l f

(known as BEIR V). The Federal Radiation Council (FRC) was f formed in 1959 to provide a federal policy on human radiation 9

j exposures. These federal policies are approved by the .',

! President of the United States.

i l i  !

These committees and commissions of nationally and~  !

{ internationally recognized scientific experts- have -been  !

dedicated to the understanding cf the health effects of  ;

i radiation by investigating all sources of relevant knowledge and scientific data and by providing guidance for radiological

protection. Their members are selected - from universities, ,

scientific- research centers and other national- and

} international research organizations. The committee reports contain scientific data obtained from physical, biological, ,

I  :

21 l

. - - - . . , - = . - - - . - - - - - - . - -- - - . . - . .

i i

i j and epidemiological studies on radiation health effects and serve as scientific references for information presented in

this report.

, Since its inception, the USNRC has depended upon the j

4 recommendations of the ICRP, the NCRP, and the FRC

(incorporated in the United States Environmental Protection Agency (USEPA) in. 1970) for basic radiation protection

!. standards and guidance in establishing regulations for the ,

j nuclear industry (Ref. 6 through 9).

4 Effluent Release Limits 4

^

) As part of routine plant operations, limited quantities of

j. radioactivity are released to . the environment in airborne j effluents. Liquid effluents may- also be released. An l effluent control program is implemented to ensure j radioactivity released to the environmar.t is minimal and does  !

j not exceed release limits. Radioactive effluent releases at j oyster Creek are under the regulatory jurisdiction of the USNRC. Regulations through the years have changed and reflect

{ operating experience and advances in reactor technology.  !

j Federal regulations as defined by Title 10 of the Code of ,

l Federal Regulations, Part 20 (10 CFR 20) establish limits on  :

l the concentrations of radioactive effluents released to the  ;

j environment. Federal effluent limits are set at low levels to

} protect the health and safety of the public. GPU Nuclear

] conducts operations in a manner that holds radioactive l l effluents to small percentages of the federal limits.

1. A recommendation of the ICRP, NCRP, and FRC is that radiation exposures should be maintained at levels which are "as low as ,

t

] reasonably achievable" (ALARA) and commnsurate with the '

4 societal benefit derived from the activities resulting in such  !

j exposures. For this reason, dose limit guidelines were  !

established by the USNRC for releases of radioactive effluents a

22 i

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l j from nuclear power plants. These guidelines were then used as the basis for the development of the Offsite Dose Calculation Manual (ODCM) and Technical Specifications. In keeping with l

t the ALARA principle, the OCNGS operates in a manner that l results in radioactive releases that are a small fraction of these limits. One example of this, is that no routine radioactive liquid releases have been made from the OCNGS since 1989, resulting in no dose to the public attributable to liquid effluents.

Applicable OCNGS Offsite Dose Calculation Manual Limits are as follows:

ODCM Specification 4.6.1.1.3.A Radioactivity Concentration in Licuid Effluent l The concentration of radioactive material, other than noble gases, in liquid effluent in the discharge canal at the U.S. Route 9 bridge shall not- exceed the concentrations specified in 10CFR Part 20, Appendix B, Table II, Column 2.

ODCM Specification 4.6.1.1.3.B Badioactivity Concentration in Licuid Effluent j The concentration of noble gases dissolved or entrained in liquid effluent in the discharge canal at the U.S.

Route 9 bridge shall not exceed 2.0 E-4 uCi/ml.

l l

ODCM Specification 4.6.1.1.4.A Limit on Dose Due to Licuid Effluent The dose to a MEMBER OF THE PUBLIC due to radioactive material in liquid effluent in the UNRESTRICTED AREA shall not exceed:

23

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1.5 mrem to the Total Body during any calendar quarter 5.0 mrem to any body organ during any calenday quarter i

3.0 mrem to the Total Body during any calendar year

or 10.0 mrem to any body organ during any calendar year  ;

ODCM Specification 4.6.1.1.5.A Dose Rate Due to Gaseous Effluent t

J The dose equivalent rate in the UNRESTRICTED AREA due to radioactive noble gas in gaseous effluent shall not exceed 500 mrem / year to.the total body or 3000 mrem / year to the skin.

f l -

ODCM Specification 4.6.1.1.5.B 4

Dose Rate Due to Gaseous Effluent 1

i The dose equivalent rate in the UNRESTRICTED AREA due to tritium (H-3), I-131, I-133, ar.:1 to radioactive material

{

in particulate form having half-lives of 8 days or more in gaseous effluents shall not exceed 1500 mrem / year to any body organ when the dose rate due to H-3, Sr-89, Sr-

90, and alpha-emitting radionuclides is averaged over no l more than 3 months and the dose rate due to other 1

radionuclides is averaged no more than 31 days.

ODCM Specification 4.6.1.1.6.C Air Dose Due to Noble Gas in Gaseous Effluent The air dose in the UNRESTRICTED AREA due to noble gas t

released in gaseous effluent shall not exceed:

24 e

1 5 mrad / calendar quarter due to gamma radiation-  !

10 mrad / calendar quarter'due to beta radiation i

10 mrad / calendar year due to gamma radiation f 20 mrad / calendar year due.to beta radiation j i

ODCM Specification 4.6.1.1.7.A '

Dose Due to Radiciodine ' and Particulates in Gaseous [

Ef fl'uent The dose to a MEMBER OF THE PUBLIC from I-131, I-133, and from radiciodines in particulate' form having half-lives l of 8 days or more in gaseous effluent, 'n i 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 Specification 4.6.1.1.8.A Annual Total Dose Due to Radioactive Effluent l The annual dose to a MEMBER OF THE PUBLIC due to radioactive l

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

Effluent Control Procram 1

Effluent control includes plant components such as the ventilation system and filters,, off gas holdup components, l demineralizers, and an evaporator system. In addition to l

minimizing the release of radioactivity, the effluent control program includes all' aspects of effluent and environmental 25

l j

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)

}' monitoring. This includes the operation and data analysis j associated with a complex radiation monitoring system, 2

J environmental sampling and monitoring, and a-comprehensive j quality assurance (QA) program. Over the years, the program .

) has evolved in response to changing regulatory requirements j and plant conditions. For ex' ample, additional instruments and l samplers have been installed to ensure that measurements of i effluents remain onscale in the event of. any accidental release of radioactivity.

}

i

{ Effluent Instrumentation: Liquid and ' airborne effluent

)

l s

measuring instrumentation is designed to monitor the presence '

and the amount of radioactivity in effluents. Many of these instruments provide continuous surveillance of radioactivity j releases. Calibrations of effluent instruments are performed -

j using reference standards certified .by the United- States

)

National Institute of Standards and Technology (NIST).

j Instrument alarm setpoints are pre-set to ensure that effluent l release limits will not be exceeded. If radiation monitor alarm setpoints are reached, releases are immediately  !

j terminated. Where continuous surveillance is not practicable l or possible, contingencies are specified in the Offsite Dose '

f Calculation Manual and/or the Technical Specifications.

i  :

Effluent Samnlina and Analysis: In addition to continuous

}

1 radiation monitoring instruments, samples of effluents- are .

j taken and subjected to laboratory analysis to identify the specific radionuclide' quantities being released. A sample must be representative of the ef fluent from which.it is taken.

l Sampling _and analysis provide a sensitive and precise method 4

of determining effluent composition. Samples are analyzed j using state-of-the-art laboratory counting equipment. {

Radiation instrument readings and sample results are compared  ;

to ensure correct correlation.

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l Effluent Data As part of routine plant operations, limited 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 of liquid and gas processing systems, and proper functioning of plant equipment. The largest variations occur in the airborne effluents of fission and activation gases which are proportional to the integrity of the fuel cladding l

and the operation of the OCNGS augmented off gas system. In general, effluents have been decreasing with time due to improved fuel integrity and increased efficiency of processing l systems.

l

With respect to activity released during 1994, the predominant radionuclide was Xe-135 in gases. No liquid releases were made from the OCNGS in 1994. The amount of rad.ioactivity released is summarized and reported annually to the USNRC.

Estimated radiation doses to the public, attributable to these effluents, were a small fraction of the spplicable regulatory limits (Tables 6 and 7). A summary of :he OCNGS liquid and airborne effluents for 1994 is provided in Table 2.

Radioactive constituents of these effluents are discussed in the following sections.

Noble Gases: The predominant radionuclides released in airborne effluents are the noble gases krypton (Kr) and xenon  !

(Xe). Small amounts of noble gases can also be released in liquid effluents. The total amounts of krypton and xe'on released into the atmosphere in 1994 were 135 curies and 190 curies, respectively. These noble gases were readily dispersed into the atmosphere when released and because of their short half-lives, quickly decayed into stable forms. No liquid releases were made from the OCNGS in 1994. l 27 l

TABLE 2 RADIONUCLIDE COMPOSITION OF OCNGS EFFLUENTS FOR 1994 i

Radionuclide Half-Life Liquid Eftluents (Ci)* Airborne Ettluents (Ci)

H-3 1.23E+01 Years No Releases 3.54E+01

! Ar-41 1.83E+00 Hours No Releases 2.24E-03 l Cr-51 2.78E+01 Days No Releases 9.36E-04 l

Mn-54 3.12E+02 Days No Releases 1.32E-04 Co-58 7.14E+01 Days No Releases 8.38E-05 Co-60 5.26E+00 Years No Releases 2.94E-04 l

l Zn-65 2.45E+02 Days No Releases 2.07E-05 Kr-85m 4.50E+00 Hours No Releases 2.61E+01 Kr-87 7.60E+01 Minutes No Releases 7.05E+01 Kr-88 2.80E+00 Hours No Releases 3.85E+01 l

j Sr-89 5.05E+01 Days No Releases 1.97E-03 Sr-90 2.88E+01 Days No Releases 2.11E-05 I-131 8.05E+00 Days No Releases 1.02E-02 l I-133 2.09E+01 Hours No Releases 4.85E-02 Xe-133 5.20E+00 Days No Releases 3.71E-01 Xe-135m 1.56E+01 Minutes No Releases 2.35E+01 l

Xe-135 9.10E+00 Hours No Releases 1.60E+02 Xe-138 1.75E+01 Minutes No Releases 5.86E+00 Cs-137 3.02E+01 Years No Releases 7.94E-06 Ba-140 1.28E+01 Days No Releases 1.90E-03 Alpha No Releases 2.75E-06 NOTE: All effluents are expressed in scientific notation. No other nuclides were detected.

• NO LIQUID RELEASES WERE MADE FROM THE OCNGS IN 1994 28 i

l

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4 i

j Iodines and Particulates: The discharge of iodines and. ,

j particulates to the environment is minimized by factors such ,

, as their high chemical reactivity, solubility in' water, and j the high removal efficiency of airborne and liquid processing _ f j systems.

6 i .

j Of the gaseous radiciodines, iodine-131 is of particular  :

} interest because of its relatively long half-life of- 8. 05 days. Particulates of relative concern are the-radiocesiums I l (Cs-134 and Cs-137), radiostrontiums (Sr-89 and'Sr-90), and  !

activation products, manganese-54 (Mn-54) and cobalt-60 j (Co-60). The total amount of iodines and particulates l released from the station in 1994 was approximately 0.064 l curies in airborne effluents. No liquid releases were made.

i from the OCNGS in 1994.

I i

) Tritium: Tritium is typically the predominant'radionuclide.

l released in liquid effluents and also is released in airborne j effluents. Tritium is a radioactive isotope.of hydrogen. It j is produced in the reactor coolant as a result of neutron 4

interaction with the naturally-occurring deuterium (also a hydrogen isotope) present in water. No liquid releases were made from the OCNGS in 1994. The total amount'of tritium released in airborne effluents in 1994 was 3'5.4' curies. To

} put this number in perspective, the world inventory of natural l cosmic ray-produced tritium is 70 million curies, which corresponds to a production rate of 4 million curies per year j (Ref. 10). Tritium contributions to the environment from nuclear power production are sufficiently small that they have j no measurable effect on the existing global environmental concentrations.  !

Transuranics: Transuranics are produced by neutron capture in -

. the fuel, and typically emit alpha and beta particles as.they l

} decay. Important transuranic isotopes produced in reactors are uranium-239 (U-239), plutonium-238 (Pu-238), plutonium-239

.j 29 i

_ _ _ , _ . _ _ ~ _ , , , ,

l t

i l

l (Pu-239), plutonium-240 (Pu-240), plutonium-241 (Pu-241),

l americium-241 (Am-241), plutonium-243 (Pu-243), plus other l isotopes of americium and curium. They have half-lives 1

ranging from hundreds of days to millions of years. Greater i

than 99% of all transuranics are retained within the fuel.

These nuclides are insoluble and non-volatile and are not readily transported to the environment. Gaseous and liquid processing systems remove greater than 90% of transuranics l

( that may be found in the reactor coolant. Because retention and removal efficiencies are so high, transuranics are not routinely monitored.

l Carbon-14: Production of carbon-14 (C-14) in reactors is small. It is produced in the reactor coolant as a result of neutron interactions with oxygen (0) and nitrogen (N).

Estimates for all nuclear power production worldwide show that 235,000 curies were released from 1970 through 1990 (Ref.11) .

Carbon-14 also is produced naturally by the interactions of cosmic radiation with oxygen ena nitrogen in the upper atmosphere. The worldwide inventory of natural C-14 is estimated at 241 million curies (Ref.11) . Since the inventory of natural carbon-14 is so large, releases from nuclear power plants do not result in a measurable change in the background concentration of carbon-14. Consequently, carbon-14 is not routinely monitored in plant effluents.

30

i l

RADIOLOGICAL ENVIRONMENTAL MONITORING I

( GPUN conducts a comprehensive radiological environmental j monitoring program (REMP) at the OCNGS to monitor radiation and radioactive materials in the environment. The information obtained from the REMP is then used to determine the effect of OCNGS operations, if any, on the environment and the public.

The USNRC has established regulatory guides which contain acceptable monitoring practices (Ref.12) . The OCNGS REMP was designed on the basis of these regulatory guides along with the USNRC Radiological Assessment Branch Technical Position on Environmental Monitoring (Ref. 13). For the OCNGS REMP, all of these guidelines have been met and in most cases have been exceeded.

The important objectives of the REMP are:

l i o to assess dose impacts to the public from OCNGS operations o to verify in-plant controls for the containment of radioactive materials o to determine buildup of long-lived radionuclides in the environment and changes in background radiation levels o to provide reassurance to the public that the program is capable of adequately assessing impacts and identifying noteworthy changes in the radiological status of the environment.

o to fulfill the requirements of the OCNGS Offsite Dose Calculation Manual (ODCM) and Technical Specifications.

31

l Environmental Exoosure Pathways to Humans from Airborne and Liould Effluents I

1 As previously discussed in the " Effluents" section, small l I

amounts of radioactive materials are released to the environment 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, drinking, eating, and direct exposure.

These routes of exposure are referred to as environmental exposure pathways. Figure 13, on page 103, illustrates the important exposure routes.

As can be seen from this figure, these exposure pathways are both numerous and varied. While some pathways are relatively simple, such as inhalation of airborne radioactive materials, others may be complex. For example, radioactive airborne particulates may deposit onto forage which when eaten by cows may be transferred into milk, which is subsequently consumed by man. This route of exposure is known as the air-grass-cow-milk-human pathway.

4 Although radionuclides can reach humans by a number of pathways, some are more important tnan 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 receiving the j greatest fraction of the dose is known as the critical organ.

This information was used to develop the Oyster Creek REMP.

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32 I 1

l

Sampling l

l The OCNGS radiological environmental monitoring program

! consists of two phases --

the preoperational and the j operational., Data gathered in the preoperational phase are I

)

used as a basis for evaluating radiation levels and

] radioactivity in the vicinity of'the plant after the plant i

becomes operational. The operational phase began in 1969 when i the OCNGS reactor achieved initial criticality.

r a >

The program consists of taking radiation measurements and l collecting samples from the environment, analyzing them fo2 >

j radioactivity content, and interpreting the results. Emphasis ,

l is on the critical exposure pathways to humans with samples

! taken from the aquatic, atmospheric, and terrestrial j environments. These samples include air, precipitation, well water, surface water, clams, sediment, fish, crabs, veg tables, and soil. Thermoluminescent dosimeters (TLDs) are I placed in the environment to measure gamma radiation levels.  ;

f The Offsite Dose Calculation Manual Specifications, .

along s

with recommendations from the scientific staff of GPUN, specify the sample types to be collected and analyses to be

1rformed.

I 4

u

Sampling locations were established by considering a

i meteorology, population distribution, hydrology, and land use  !

l characteristics of the local area. The sampling locations are l divided into two classes, indicator and background. Indicator l locations are those which are expected to show effects from OCNGS operations, if any exist. These locations were j primarily selected on the basis of where the highest predicted environmental concentrations would occur. While the indicator locations are typically within a few miles of the plant, the j background stations are generally at distances greater than 10 g miles from the OCNGS. Therefore, background samples are i collected at locations which are expected to be unaffected by

{ station operations. They provide a basis for evaluating 33 i

i l

l r fluctuations at indicator locations relative to natural background radioactivity and fallout from prior nuclear weapon tests. Figures 3, 4, and 5 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.

Analysis j In addition to specifying the media to be collected and the minimum number of sampling locations, the Offsite Dose Calculation Manual (ODCM) Specifications include the frequency of sample collection and the types and frequency of analyses to be performed. Also listed are analytical sensitivities (detection limits) and 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 analyzed per the requirements of the ODCM and Technical Specifications. Sample analyses which did not meet the requiied analytical sensitivities are presented in Appendix B. Changes in sample collection and analysis are described in Appendix C.

The analytical results are routinely reviewed by GPUN scientists to assure that established sensitivities have been achieved and that the proper analyses have been performed.

All analytical results are subjected to an automated review process which ensures that ODCM-required lower limits of detection are met and that reporting levels are not exceeded.

Investigations are conducted when action levels or reporting levels are reached or when anomalous values are discovered.

The action levels were established by GPUN and are typically 10 percent of the reporting levels specified in the ODCM and 34

Figure 3 I

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Forked River

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l I 348.75 11.2 I

326.25 .

33 303.75 g 56.25 ,

1 5 "

1 Mile 5

65 l

281.25 53

/64

~

l 1

- 78.75 63 55 DOCNGS 62 RG 1

258.75 "

56 35 1g 57 -

101.25 58 59 # 66 j 33 2

236.25 123.75 146.25 191.25 168.75

-- M^

W ~

', Waretown Oyster Creek Nuclear Genemting Station (DCNGS) laation of Radiological Environmental Monitoring Program (REMP) Stations within 1 mile of the site 35

i Figure 4 i

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Forked River i

348.75 11.2

( 326.25 7

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30.ug 77 i

56.25 j 1s

- 6 i e 1 23mes

)* --

7-281.25 69 19 70' i siiw -

i - _ L 1

\

"": /

3 I

i 25s.75 Y

-%. J2. =-

101.25

\

i i i 'l I (

1

' \

07 l 236.25 Ril 25 123,75 m x 70

-} 7g][

1 Waretow 22 i 146.15 l

Barnegat Bay

\

191.25 168.75 k

4 i

i

Oyster Creek Nuclear Generating Station (OCNGS)

Location of Radiological Environmental Monitoring Program (REMP)

Stations greater than 1 rnile and within 2 miles of the site

~,

' i 36 1

1

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

I

! Figure 5 l 11.25 j 348.75 l

! A 1

326.25 i

Lakewood 33.75 C 36 14 303.75 Toms River '

91 10 15 {

I3 ~

56.25

. 9 8

5 ,

I 90 78.75 68 ,

3 A N -

30 Miles 20 Miles 10 Miles 7 89 - 101.25 gg i 16 8' 4 88 81 87 123.75 11 146.25 168.75 4

17 0 F Atlantic Ocean H

236.25 h

- e 213.75 191.25 Oyster Creek Nuclear Generating Station (OCNGS)

Location of Radiological Environmental Monitoring Program (REMP)

Stations Greater than 2 miles from the Site 37

l t

Technical Specifications. These levels are purposely set low j so that corrective action can be initiated before a reporting level is reached.

Table 3, on page 42, provides a summary of radionuclide 4

concentrations detected in the primary environmental samples for 1994. The data are summarized in a format that closely l resembles the suggested format presented in the USNRC Branch Technical Position (Ref. 13). Quality Control (QC) sample

results were used to verify the primary sample result or the first result in the case of a duplicate analysis. To eliminate a bias in the results, the QC results were excluded from Table 3 and the main text of this report.

Measurement of low radionuclide concentrations in environmental media requires special analysis techniques.

Analytical laboratories use state-of-the-art laboratory equipment designed to detect beta and gamma radiation. This equipment must meet the required analytical sensitivities.

, Examples of the specialized laboratory equipment used are

germanium detectors with multichannel analyzers for 4 determining specific gamma emitting radionuclides, liquid i

scintillation detectors for detecting tritium, low level proportional counters for detecting gross beta radioactivity, and coincidence counters for low level I-131 detection.

Computer hardware and software used in conjunction with the counting equipment perform calculations and provide data

management. Analysis methods are described in Appendix I.

4 Ouality Assurance Procram A quality assurance (QA) program is conducted in accordance 4

with guidelines provided in Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs" (Ref.16) and 4

l 38 i

i l

as required by the ODCM and Technical Specifications. The QC 4

program is documented by GPUN written policies, procedures, and records. These documents encompass all aspects of the j REMP including sample collection, equipment calibration, laboratory analysis and data review. I

, l The QA program is designed to identify possible deficiencies so that immediate corrective action can be taken if warranted.

It also provides a measure of confidence in the results of the monitoring program in order to assure the regulatory agencies and the public that the results are valid. The quality assurance program for the measurement of radioactivity in environmental samples is implemented by: ,

o auditing all REMP-related activities including analytical laboratories 1

o requiring analytical laboratories to participate in the USEPA Cross-Check Program o requiring analytical laboratories to split samples for separate analysis (recounts are performed when samples are not able to be split)  ;

o splitting samples, having the samples analyzed by  ;

independent laboratories, and then comparing the results for agreement '

o reviewing QC results of the analytical laboratories including spike and blank sample results and duplicate analysis results.

I The quality assurance program and the results of the USEPA Cross-Check Program are outlined in Appendices D and E, r'espectively.

39

I l

l The TLD readers are calibrated monthly against standard TLDs l to within five percent of the standard TLD values. Also, each i group of TLD's processed by a reader contains control TLDs i 1 ,

j 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 of TLDs to assure the reader i is functioning properly.

l l

l Other cross-checks, calibrations and certifications are in place to assure the accuracy of the TLD program: )

j o Semiannually, randomly selected TLDs are sent to an

, independent laboratory where they are irradiated to set doses not known to GPUN. The GPUN dosimetry l laboratory processes the TLDs and the results are  !

compared against established limits. 1 l

o Every two years, each TLD is checked for response l within 10 percent of a known value. I i

1 o Every two years, GPUN's dosimetry program is examined and recertified by the NIST National Voluntary Laboratory Accreditation Program (NVLAP) .

o Ten environmental TLD stations have quality control badges (Teledyne Brown Engineering) which are j processed by an independent laboratory. The i results are compared against GPU Nuclear TLD results.

The environmental dosimeters were tested and qualified to the American National Standard Institute's (ANSI) Publication N545-1975 and the USNRC Regulatory Guide 4.13 (Ref. 14 and 15).

40

e V

In addition to the GPU Nuclear REMP, the Nuclear Regulatory

Commission (NRC) and the New Jersey Department of

'l

Environmental Protection (NJDEP) also maintain surveillance i programs in the OCNGS area. These programs provide l

independent assessments of radioactive releases. and the radiological impact on the surrounding environment. The results from these programs have correlated closely with those from the GPU Nuclear program.

2 1

I i

)

i j

i i

i 1

l ,

j i

l 1

1 I

1 Y

41

1ABLE3 .

l T RA"lIOLOGICAtiENVIRONMENTSIIMONITORING PROGRAM S'UMM$RC J..

s'

" ' 'LYSTE$CREEKNUCLEADGENERATING STATION $ 3 ' + ~ N

' i J NUiRI.1994 THROtIGCif ECEMiER[1994)

THE FOLLOWING PAGES ARE A

SUMMARY

OF REMP DATA FOR THE SCHEDULED COLLECTION PERIOD JANUARY.1994 THROUGH DECEMBER,1994. DATA" ARE SUMMARIZED ON AN ANNUAL BASIS, WHERE: ,

SAMPLE TYPE -> Media being anal37ed.

ANALYSIS -> T pe 3 of analysis being performed on the particular media.

1. OF ANALYSES PERFORMED -> The total number of analyses perfonned for a particular sample 13pe.

Ll_D -> The mean lower limit ofdetection. Please note that this value is based on emples whose results showed no detectable activity.

INDICATOR STATIONS > The mean, minimum and maximum based on detectable activities of all indicator stations.

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

Station -> The station designation with the highest annual menn.

BACKGROUND STATIONS -> The mean, minimmn and maximum based on detectable activities of all background stations.

(N/f0T)-> The fraction ofdetectable activities /fotal munber of analges perfonned.

BACKGROUND STATIONS AT OCNGS STAT 10N(S): A,C,II,14 31,94 18 36 SAMPLE TYPE (S): AIR PARTICULATE SEDIMENT WELL WATER VEGETABLES AIR IODINE CLAMS SOIL PRECIPITAT10N SURFACE WATER FISit*

• BLUE CRAll'*

An asterisk (*) indicates no data.

• • Station 94 only.

42

m. m ._ __ _ ..m_. . ._ ._. _ . . . .

l .

. .. . . . . . . D TABLE J.; . . .. , . . ._

l . RADIOIA)CICAL FJWIRONMENTAL MONITORIMO PROGRAM ::

l 4YSTER CREEK NUCLEAR GENERATINC STATION :

l .'JANLIARY.19M THROUCH DECEMBER 1994 3 ~

J' ANNUAL

SUMMARY

- 8 AMPLE : '- ANAIJ5tS -- c NUCLIDE f #OF y -

LLD;: - INDICATOR STATIONS . HIGHEST ANNUAL MEAN y , BACKGROUND STATIONS TYPE i ANAL.'s L MIN X fMEAM7 1 MAX? 1(N/ TUT)! MINj  :

. MEAN $ ? MAX ? f(M/ +- TOT) 7 MIN'- - MEAN 4 iMAX ' - (N/ TOT)

..: gypy l

l AIR PARTICULATE Oross Beta 673 NollD 4.20E-03 1.55E-02 3 80E-02 (465/465) 6.80E-03 1.62E-02 3. ROE-02 (52/52) 3.30E-03 1.62E42 3.40E-02 (208.208)

(pCi m3) Reported Stathw# 4 AIR PARTICULATE Gamma Sean Ba-140 179 1.46E-02 <LLD < LID <!JD (0/123) <LLD <11D < tlD (0/14) (11D <llD (LID (0/56)

(pCi'm3)

AIR PARTICULATE Oanuna Scan Be.7 179 No 11D 6.40E-02 1.09E-01 1.70E-01 (123/123) 7.80E-02 1.16E-01 1.40E-01 (13/13) 6.50E-02 1.05 E-01 1.60E-01 (56/56)

(pCi/m3) Reported Station # 71 AIR PARTICt' LATE Gamma Scan Co-58 179 2.14E-03 <llD <llD < LID (O'l23) <llD <IID (LLD (0/14) <LLD < tJD <t1D (0/56)

(pCim3)

AIR PARTKTIATE Gamma Sean Co40 179 2.4RE43 < 11D (LID <llD (0/I23) <t1D < LID <llD (0/14) <llD < 11D <LLD (0/56)

(pCim3)

AIR PARTKTLATE Gansna Sean Cs-134 179 1.79E 03 (LLD <llD <LLD (0;l23) <LLD <lll) <11D (0/I4) <LLD < t1D <11D (0. 56)

(pCi m3)

AIR PARTICt'IATE Gamma Scan Cs-137 179 I.91 E-03 < llD <LLD < tJD (0 123) < tJD <tJD + 1J D (0 14) s tJ.D < LID <llD (0. 56)

(PCi m3) 43

<>. . _ . , . . . . . . : STABLE 33 .. .,

s RADIORDGICAL ENVIRONMFJtTAL MONITORING FROGRAM

' OYqrrERCREEKNt'CLEA IGENEstATINGFrATIONT'

[fJANTIARY'3 19N THROUGH DECEMBER.19M f ' "

-i NNUAL5UMMARY?

A 9 AMPLE OANALYsIS 3- N1CLIDE : 7# OF:3_. cIl3c ..

IMDBCA1DR STATIONS y) , .. -:: HIGHEST ANNUAL MEAN 2 n F RACEOROUND STATIONS o

• aTYPEj < ' " ,:l MtM :: MEAN jMAK$- (WrUT) i MIN L 2 MEAN j . ( MAKi (NrtDT) s MIN $ G MEAN 9 : MAX j (N/f0T)

< ? ANAL J 3e ' ^

<hM 2

' ~

c PERFr4 t AIR PARTICUIATE Gamma Scan Fe 59 179 5.15E-03 <IJD <UD <11D (0/123) < LLD <1lD <UD (0/14) <tlD <tLD <tlD (0/56)

(pCi m3)

AIR PARTICUIATE Gamme Scan I-131 179 6.55E-03 < t1D <tlD <uD (0/123) <t1D <UD <UD (0/14) <!1D < tlD <1lD (0/56)

(pChn3)

AIR PARTICUIATE Gamma Scan K-40 179 3.32E-02 <11D <11D <uD (0/123) < LID <11D <llD (0/14) <11D < LID <1lD (0/56)

(pCi'm3)

AIR PARTICt'IATE Gamma Scan La-140 179 6.97E-03 <llD <tlD < t1D (Oct23) <tlD <UD <11D (0/14) <11D < llD < 11D (0/56)

(pCi m3)

AIR PARTICULATE Camma Scan hin-54 179 2.02E-03 < tlD <llD <1lD (Ocl23) < !1D <UD (414) < t1D (LID <ILD (0/56)

(PCi'm3)

AIR PARTICULATE unmma Sean Nb-95 179 2. ROE-03 < LID < tlD < tlD (0/123) < t1D <11D <UD (0/14) < t3D <llD < tlD (S$6)

(pCi m3)

AIR PARTICt'IATE Gamma Scan Ra-226 179 3.31E-02 <tl.D < tlD < t3D (0:123) <UD <llD < LID (4'14) <llD ILD < llD (0 56)

(pCi m3) 44

. . . . . . . . . . . ... ? TABLE 3 y .

.m._ , , . . . . _ _ . _ ,

2. RADIGIDCICAL ENVIRON klENTAL MONITORINC PROGRAM X

. OYSTER CREER NUCLEAR GENERATING STATION F:

$ JANUARY;1994 THROUCH DECEMBFJt.19N @

" ? ANNttALgUMMARYe #

0 SAMPLE y ANAIAailS .:: q NUCilDE :- . ( # OF , 3LLD .:: . ... . p INDECATOR STATIOh.9 -

...3 HICHEST ANNUAL MEANp.,. .. ...;.. _j BACKCROUNDSTATIONS.-

TYPE- fANAlf.i i MIN U MEAN l

AtAKj (M/fGT) (MINj 5 MEAN.); 1 MAKS 7(N/FOT)NMIN '. 4MEAN/ '. MAX

~j (N/ TOT) -

- PERF.R *' W' ~~ ' '

AIR PARTICULATE Gansna Scan 1h-232 179 8.26E43 <LLD <t1D <11D (0/123) <11D <llD <UD (0/14) <UD <LLD <UD (0!$6)

(rCi m3)

AIR PARTICULATE Gamma Scan Zn-65 179 4.85E-03 <t1D <llD <tlD (0/123) <LLD <UD <LLD (a'I4) <UD <LLD < LID (0/56)

(pCi/m3)

AIR PARTICULATE Gamma Scan Zr-95 179 3.84E-03 < LIE <LLD <tLD (0/123) <t1D <LLD <!1D (0/14) (LID < tlB <t1D (0/56)

(pCi/m3)

AIR IODINE laline-131 675 1.57E-02 <t1D < TID < t1D (0'467) <t1D <11D <llD (0/52) <!1D <LLD <llD (0/208)

(rCi'm3)

PRECIPITATION Tmium 22 1.64E+02 <11D <!lD <t1D (0/12) <UD < LIE <ILD (0/4) <llD <tLD < LID (01 0)

(pCiL)

PRECIPITATION Gamma Scan Ha-140 22 9.73E @ <tlD <llD <UD (O'I 2) <llD <LLD <LLD (0'4) <t1D <LLD <llD (0/10)

(pci L)

PRECIPITATION Gamma Scan De-7 22 2.75E,01 1.50E+01 3.17E+01 4.30E+01 (10/12) 2.70E+0! 3.47E+01 4.30E+01 (3/4) 1.40E+01 2.72E+01 3.80E+01 (6/10)

(pci L) StationJ 72 PRFCIPITATION Gamma Scan Co-58 22 2.14E+00 < TID <WD < t1D (Gel 2) < t1D <LLD <UD (0/4) < llD <WD <WD (0.10)

(rCi !-)

45

, . < _. .m. m._ . ... ,.. _m.- .. ._ _ _ . . . _ _ _

.. - . .1.p TABLE 3:n. . ' . ., .

s .. RADIORDGICAL ElWIRONMENTALMONTTORING PROGRAM, M k OYSTER CERN NUCLEAR GENERATING STATION $jy

,' #JANUARYol9MTftaOUGH DECEMBERJ1994.? @3 ^

.f '? ANNUAL NJMMARY$ '~ M " *

uSAMPLE J  ?

ANALYSIS : e NUCLIDE;a y #OFw e- LIDy r INDICA 1DR STATIONS m; x., , IIIGIIEST ANNUAL MEAN z , RACE 1tOUND STATION $ e ATYPE$N.,^ ~ ~ ~ '~

~

[ANAlfjj , , $$ !MINW MEAN/ $MAKI((N' REFT / {[$.Mll@ MEAN[ '[ 84AKI OtfrOT) -$MINr MEAN k { MAKf (N/FOT) wE c , . , ~ <

a- .

PRECIPITATION Genuna Scan Co-60 22 2.40E+00 <tLD (LID < LID (0/12) < Lib <UD <WD (0/4) <LtB (LID (LID (0/10)

(pCil)

PRECIPITATION Gamma Scan Cs-134 22 1.90E+00 <LLD < TID <llD (012) <LLD < 1lD <11D (0/4) < LID <llD <11D (0/10)

(pCit)

PRECIPITATION Gansna Scan Os-137 22 2.19E+00 <LLD <UD < LID (0/12) <11D <UD < LID (0/4) <UD <11D <tLD (0/10)

(pCi L)

PRCCIPITATION Gamma Scan Fe-59 22 4.68E+00 <11D <UD <LLD (0/12) <UD <1lD < LID (0/4) <LLD (UD <UD (0/10)

(pCil)

PRECIPITATION Gamma Scan I-131 22 3.50E+00 (UD <1lD <llD (Oct2) (11D < LID < tlD (0/4) (UD < LID <UD (0 10)

(pCi L)

PRECIPITATION Gamma Scan K-40 22 2.S? E+01 4.00E+0! 4.00E+01 4.00E+01 (1/12) 4.00E+01 4.00E+0! 4.00E+01 (II4) <LLD <UD <1lD (0/10)

(pCi L) Stasiand 72 PRECIPITATION Gamma Scan La-140 22 3.94E+00 < tlD <1lD <UD (0/12) < LID <1lD <UD (0/4) <11D <LLD <11D (0/10)

(I('i l)

PRECIPITATION Gamme Scan Mn-54 22 2.13E+00 <UD <LLD <!lD (0/12) <11D <LLD (UD (0/4) <LLD <LLD <1lD (0/10)

(PCit)

PRECIPITATION Gamma Scan Nb-95 22 2.40E+00 <1lD (UD <11D (0 12) <1lD (UD <11D (O'4) <llD < llD <UD (G'IO)

(pCi. L) 46

TAllI1J IULillOli)CICAL ENVikONSIENTAL Af0NITORING PROCRA%f

^

OYSTE2 C F.EK NUCLEA %ENERATING hTATION JANUAR%1994 TIIRoI*CII DECE31BER,1994 ANNI?AL SU%I%I CT SA%IPI.F. ANAIASIs NIT 111)E #OF I .I.D l\ plCAT OR STA~I IONN IllG?'ENT ANNI'AI,51EAN IIALId;Rol' Nip NT A I IONN TYPE AN tt. %IIN %1EAN %LW (N40T) %IIN All3N alAX SIIN (NGOT) AIEAN %I W (NflOT) l PFRF. Nestlan #

PRI Cll11 AllON ti.inwna Scan Ra-226 22 5.14L 01 - l_1 I) - 1.1 D 1.lD (O12) <LLD < l.ll) < 11D (0 4) ' Lt.D <11D < LID (o 10)

(pC-: 1.)

PRECIPITATION Gamma Scan Th-232 22 RR6E+00 (11D <11D < 110 (0, I2) < 11D < llD <11D (0 4) <LLD <1JE < LID (0.'10)

(rCiL)

PRECIPITATION Gamma Scan Za65 22 4.59E+00 <t1D <11D <11D (0/12) <11D <11D <11D (0/4) <11D <llD <11D (WIO)

(rCil)

PRECIPTTATION Oamma Scan Zr-95 22 3.75E+00 <11D 41D <11D (0/12) <11D <11D <11D (0/4) <llD <11D <11D (0/10)

(; Cit)

SURFACE WATER Tntium 102 1.6"'E +02 <llD <11D <1lD (073) <llD <11D <11D (0/13) 1.90E+02 1.95E+02 2 00E+(12 (2/24)

(pCil)

SU~ FACE WATER Oamma Scan Ba-140 102 8 86E+00 <11D <11D cllD (&73) <11D (11D <1lD (0/13) <llD <llD <11D (&74)

(ICit)

SURFACE WATER Ganrna Scan Be 7 102 1.56E+01 <llD <llD 11D (0/78) <11D < TID <11D (&'13) <11D <llD <11D (W24)

(pCil)

SURFACE WATER Ganwne Scsa Co-38 102 8.86E+00 <llD <11D <11D (0GR) < TID <11D <11D (0/13) <llD <UD <llD (W24)

(gG t)

St'RFACE WATER Gamma Scan Co40 102 2.03 E+00 <11D <llD <11D (W73) <11D <11D (11D (Orl3) <LI D <llE <11D (424)

(rCiL) 47

. . ._. . _ . - ..m . . - .. ._ _ __ _- . _ .. .. _ _ __ _ _ . . . . __.

TABLE 3;t .. .,

t RADIORDCICAL ENYlRONMENTAL MO*UTORING PROGRAM /

'. Oil! ITER CREEK NUCLEAR GENERATING FFATION 3 i JANt!AR%19N THROUCH Dl!CEMBER 19N i ' ' '

'I ANNUAL

SUMMARY

5 SAMPLE ;  ;: ANALYST $ ; :;

-. NUCLIDEp .j # OF..g y Lib :, .

j INDSCATOR STATION 8;:- . _ . . s HIGHEST ANNUAL MEAN :s . _ _ , , . . .;. BACIsCROUND STATIONS -

JTYPEq i') ANA1. l:- f MINj MEAN k MAKi ((NITUT)j i MIN -~ S MEAN7 s MAKy [:((N/ TOT)( (MIN $ MEAN ; - MAX .. : (N/ TUT)

" PERF.

W' ' "

SURFACE WATLR Gamma Scan Cs-I34 102 I.73E+00 <11D < tlD <l.1D (0/78) <LLD (11D <llD (Df; <l.1D <IAD <llD (0/24)

(pCil)

St*RFACE WATER Gamma Scan Cs-137 102 1.90E+00 < tJD < llD <llD (0.78) <LLD <llD <11D (0!!3) < LID < TID <llD (024)

(pCil) f.URFACE WATER Gamma Scan Fe-59 102 4.2SE+00 < TID <llD <11D (0/78) < tlD <LLD <llD (0/13) <llD <llD <llD (0.14)

(gCi L)

SURFACE WATER Gamma Scan I-131 102 2 60E+0! <tLD <llD <11D (078) <t1D <llD <11D (0/13) <LLD <tJD <llD (0.14)

(pCUL)

SURFACE WATER Gamma Scan K-40 102 2.00E +01 2.20E+01 2.16E+02 3.00E+02 (73/78) 2.10E+02 2.53 E+02 2.80E+02 (13/13) I.90E+02 2.78E+02 3 40E+02 (2424)

(gCi L) Station-8 25 St'RFACE WATER Gamma Scan 12-140 102 3.41E+00 <1lD <llD <11D (0/78) <LLD (LLD <llD (0:13) <t1D <ILD <Lil) (O'24)

(rCiL)

St'RFACE WATER Gamma Scan Mn54 102 I85E+00 <llD <LtD < LID (0.78) <llD <llD <t1D (O'13) <llD < TID < IID (0.14)

(ICil.)

SURFACE WATER Genna Scan Nb-93 102 2.14E+00 <11D <llD <11D (0,78) <LLD <llD <llD (0/13) <t1D <11D <LLD (014)

(pCit)

Sl'RFACE WATER Gamma Scan Ra-226 102 4 60E+01 410E+01 4.35E401 4 60E+01 (2 78) 4 60E+01 4 60E+01 4 60E+01 (III3) 6.20E+01 6.30E+01 6.40E+01 (2 24)

(pCs I ) Station-# 93 48

s. , . .  ? TABLE 3;'

A RADIOBJOCICAL ENYHtONMENTAL MONITORINC PROGRAM ip

/ OYSTER CREEK MUCLEAQ CENERATINC FTATIONj _

kJANUAR%19N THROl!CH DECEMBER.19N li

'3ANNUAL

SUMMARY

b ~ '

i: SAMFIEJ  ? ANALYSIS-n n NUCLIDE? ' # OF 0 LLD 1. INDICATOR STATIONS - .. eincliEST ANNUAL MEANj 2 BACKGROUND STATIONS j .

.? TYPED HANAO - MIN 3 MEAM % MAK2]

(4/ TUT) LMIN.h SMEdMt![ "c MAKf (Mrt0T) 1 MIN.$ .: MEAN :/ MAX j '(N/f0T)

parRF. : Steelema SUMFACE WATER Gamma Scan lh-232 102 7.47E +00 < t1D <11D <113 (0/78) (11D <t1D <11D (4 13) (LLD < t1D (LID (0/24)

(pCil)

SURFACE WATG Gansna scan Zn45 102 4.17E+00 <LLD < t1D (11D (0/78) < LID <LLD <1lD (0/13) < t1D <11D <1lD (0.24)

(pCiL)

SURFACE WATER Gansna Scan 7s-95 102 3.37E +00 < LID <11D (llD (078) < t1D <LLD <11D (0/13) <llD (11D <llD (0/24)

(pCi L) wet 1 WATER Tritium 54 1.67E+02 1.60E+02 1.70E+02 1.80E+02 (2/41) 1.60E+02 1.70E+02 1.80E+02 (2/13) 1.40E+02 2 00E+02 2.70E + 02 (3.'13)

(pCil) Statim i wet 1 WATER Genuns Scan Ba-140 54 889E+00 <11D < t1D < t1D (0/41) <!1D < LID (llD (0/13) < LID < IlD <11D (0,83)

(rCi L)

WE11 WATER Gamma Scan Be-7 54 1.61E+01 <11D <llD <llD (014 1) <llD < tlD <t1D (0/13) < LID < LID <tLD (S'13)

(pCit)

WE11 WATER Gansna Scan Co-58 54 a.93E+00 <11D <llD < LID (0/41) <11D < LID <llD (0/13) <t1D < LID < tlD (0/13)

(gCi L)

WE11 WATER Gamme Scan Co40 54 2.15E+00 < t1D <llD < LID (0/41) < LIB < TID < t1D (0/13) <t1D <11D <LLD (S'13)

(pCil)

WEl1 WATER Ganuna sean Cs-134 54 182E*00 (11D (11D <llD (0/41) < llD <llD < LID (0 13) <llD < l.1D < tJD (O'13)

(PCi 1 )

49

- m _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ . . . _ - . _ - - _ _ - ___ ____ ._ _-__ -_-__ _ _ _ _ _ _ _ - - -t - _ _ - _ _ _ _ _ - _ - _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ . _ _ _

1

-- TA4 LE 3 -

RADIOIDGICAL ENVIRONMENTAL MONITORINO PROCRAM /

'! OYSTE3 CREEK NUCLEA2 CENERATING STATION ,

J JANtJA%Y.1994 TilROUCII DECEMBER,1994 .-

' G ANNitAL51TMM4RV'

- SAMI'II ANAI A NIN N111IDE if UF LIE 1.NI)lCATOR STA'lIOM - IIIGIIEST ANN 1!Al.MFAN - HACM;Rol!N D NTA IIONS TYPE AN tl.  : MIN . MEA.N .. -3IAN . (N/ TOT) MIN MEAN MAN' (N/ TOT) MIN " MEAN- MAN (N/ TOT)

I'l Rr. ~ Staem # -

WELL WXIl.R Uamma Sean Cs-137 54 2 00E + 00 < l.11) < LID < il D (04I) <ll.D 'll D dil) (o I3) (llD < LID < IJD (o i3)

(PCi 1.)

WEll. WATER Gamma Scan Fe-59 54 4.3I E400 <llD <llD <1lD (0/41) ellD < LIE <LLD (0/13) 41D <LLD < LID (0/13)

(pCit)

WEll. WATER Osa me Scan 1-131 54 1.78E41 (IlD <llD (IlD (0/4t) <llD <llD <llD (0/13) <LLD <llD <!lD (0/13)

(pCil) 1 WEll. WATER Osama Scan K-40 54 2.61E+01 2.SOE+01 2.30E+01 2.50E+01 (1/41) 2.50E+01 2.30E+01 2.30E+01 (1/2) 3.10E+01 3.10E+01 3.10E+01 (1/13)

(pCi/L) Stahon-8 19 WEll. WATER Gamma scan La-140 54 3.33E+00 ellD <llD cllD (0/41) <llD < TID <11D (0/13) <llD <llD <1lD (0/13)

(pCil)

TIEll. WATER GenenaScan h 54 54 1.91E+00 <llD <llD <llD (0/41) <llD <llD <llD (0/13) <llD < LID <llD (0/I3)

(pcit)

WELLWATER OaxanaScan W95 54 2.27E+00 <llD < TID <llD (0/41) <llD <11D 41D (0/13) <llD <1lD <llD (0/13)

(pCil)

WELL WATER Osmane scan Ra-226 S4 4.98E+01 <llD <llD <llD (0/41) <llD 41D < TID (0/13) 3.90E+0! 3.90E+01 3.90E+01 (1/13)

(pCi/L)

WEll. WATER Osama scan  % -232 $4 7.83E+00 2.40E+01 2.40E+01 2.40E+01 (1/41) 2.40E+0i 2.40E+01 2.40E+01 (!!!3) <llD <1lD <llD (0/13)

(pCit) W 21 50 t

w. , .

, TABLE 3t L RADIORDCICAL ENVIItONMENTAL MONITORING PROCRAM A

! OYl!rTER CREEKNUCLEAR GENERATING 5 TAT 10N i

>JANUAR%19N TffROUGH DECEMBER 19H j "

s ANNilAL5UMMARY:

y SAMPLE 1 ~ . ANARASIS : 9 NUCLIDE ( - # OF x:. : LID & .

.. , .INDICATORSTATIOMs 3

.  :: HICHEST ANNUAL MEAN r . . . , , BACKCROUND STATIONS :

3 TYPE? L ANAID. - 3 MtM i :MEAMJ -l MAX!? M(N/IUT) i: MIN} 4 MEAN .:; $ MAX <J :(N/ TOT)5 iMIN; j MEAN :.: y MAX L : (N/ TUT)

' PFRF. - thsten.#

WELL WATER Osmma Scan Zn 63 54 4.20E+00 < llD <lD (UD (0/41) <UD <llD (LLD (0/13) <LLD <LLD < tLD (0/13)

(g<il)

WEI L WATER Gamma Scan Zr-95 54 3.56E+00 < t1D < tlD <llD (0 41) (LLD < LID <UD (0.'l3) < LID <LLD <llD (0/13)

(rCil.)

CA111LtGE Gamma Scan Ba-140 9 4.33E+01 (LID < t1D <llD (0 6) < LID < llD <LLD (03) <LLD <11D < LID (O'3)

(rCikgWET))

CABBAGE Gamma Scan Be-7 9 9.43 E+01 160E+02 1.60E+02 1.60E+02 (l'6) 1.60E+02 I.60E402 I.60E+02 (1/3) 2.60E+02 2.60E+02 2 60E+02 (10)

(pcik g(WET)) Station-# 35 CAf1BAGE Gamma Scan Co-58 9 1.07E+0! < 11D <11D < TID (O'6) <UD <11D <t3D (0 3) < t1D <llD LU) (0 3)

(pCilg(%TT))

CAHRAGE Gamma Scan Co 60 9 1.23 E+01 < LID <LLD <11D (0!6) <ILD (UD <11D (0/3) <LLD <11D < t1D (03) ,

(PCikgWET))

CARBAGE Gamma Scan Cs-134 9 9.22E+00 <1lD (LLD <UD (0 6) <llD < t1D <UD (03) <LLD < tlD <lll) (0/3)

(pCikgWET))

CAI1BAGE Gamma Scan Cs-137 9 1.10E+01 < t1D <tlD < LID (0!6) < LID < t1D <LLD (0/3) <11D < LID <LLD (00)

(pCikgWET))

calli 1 AGE Gamma Scan Fe-59 9 2.62E+01 cijD < 11D < LID (0 6) <llD <t1D <11D (0 3) <LLD <llD < llD (0 3)

(pcin gWET))

i 51

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

~m _ _ _ _ ._ ._ ...._.m._ _m ___ ,-____m . _ . .. _ _ _ . .__ . _ _ . . .__ _. . . _ _ .

. . . ;. ... . . TABLE 3 : - ... , . .

s

? RADIOIDCICAL ENVIRONMENTAL MONITORING PROGRAM g

'? OYSTER CREEK NtCIIAR GENERAftNG STATION :

ifJANUARVs19N THRotL'It DECEMRER.19Nj

" : ' ANNUAL 5tiMMARY1 SAMPLE i i ANALYSISgg NUCLIDE; . ] # OFn . - LLD -y ..

INDICATOR STATIONS c. .. .

. HIGHEST ANNUAL MEAN x . .. ._ . j BACKGROUND STATIONS -

'TYPEi '

> ANAll .: E bitM .L -[ MEAM f MAX T l(N/ TOT), , MINI ; MEANi : MAKf i (NGOT)( ) MIN ; ?MEAN f (MAX 1 . (N/ TOT)

' ' ' ~

PERF.' Iteestan #

CAllBAGE banuna scan 1-131 9 1.46E+0i < TID < LID (LLD (0/6) <llD <LLD <LLD (0/3) <LLD <LLD < tlD (00)

(KilgWET))

CADBAGE Gansna Sean K-40 9 No1.1) 2.40E401 2. ROE +03 3.20E403 (6/6) 2.60E+03 2.90E+03 3.10E+03 (3'3) 2.00E+03 2.37E+03 3.00E+03 (3!3)

(pCagWET)) Reported Station # 35 CAllflAGE Gamma Scan 12-140 9 169E+01 (IlD <llD < llD (O'6) < TID <LLD (LID (G3) <LLD <t1D <llD (0/3)

(pCi kg(WET))

CABBAGE Gamma Scan Mn-54 9 1.07E+01 <LLD <LLD <LLD (0/6) <llD <LLD <LLD (0/3) <LLD (LLD <1lD (0/3)

(pCng(WET))

CAltllAGE Gamma Scan Nb-95 9 1.17E*01 <llD < LID < tlD (0/6) < t1D < TID <LLD (0 3) < TID <LLD <LLD (0/3)

(pCiigWET))

CAllflAGE Gamma Scan Ra-226 9 2.02E+02 < TID < LID <1lD (04) <LLD <tLD <tlD (0<3) <LLD <LLD <t1D (0.3)

(pCilgWET))

CABilAGE Gamma Scan Th-232 9 4.25E+01 ' LID < t3D < TID (0.6) < t1D < TID <tlD (43) < LID < t1D <11D (03)

(PCitgWET))

CABBAGE Gamma Scan Zn-65 9 2.72E+01 < TID < TID < TID (O'6) < t1D < LID < TID (00) cilD < Lil) < t1D (0/3)

(pCag(WET))

CAllBAGE Gamma Scan Zr-95 9 1.88E+01 <11D < t3D <1lD (0 6) <LLD <t1D <11D (0<3) <ilD < LID (ILD (03)

(pCiig(WET))

52

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

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

(

1 TABLE 3s ,

1 RADIOLOGICAL ENVIRONM ENTAL MONITORINC PilOGRAM i

? OYSTER CREEK MUCLEAR' GENERATING NTATIONI QANUAR%29M TIIROUCH DECEMBER.19M f

" -> ANNUALSUMMARV) ' ~'

- SAMPLE r  ? ANALY5t$ . i NUCLIDE.... #OF. 11D - INDICATOR STATIONS . HIGHEST ANNUAL MEAN 9 BACKCROUND5TATIONS -

i { T)PF.f ANAL-  ? MIN '- MEAN MAK ;l .:(N/IUT) L MIN b } MEAN.? ?MAXf f(N/ TOT)li : MINE l.MEAN! iMAX9 . (N/ TOT) ppppy s r- -

collard Gamma Scan Ba-140 20 4 90E+0I <LLD <llD <LLD (0/I4) <LLD <uD <UE (0/7) <llD <UE <UD (0/6)

(pCikg(WET))

collard Gamma Scan De-7 20 9.46E+01 7.60E+01 I.47E+02 2.80E+02 (6/I4) 7.60E+01 1.78E+02 2.80E+02 (2/7) 1.40E+02 I.40E+02 1.40E+02 (1/6)

(pCitg(WET)) Station-# 66 collard Gamma Scan Co-53 20 1.12E+01 <LLD < LID <LLD (0.14) < 11D < l .I.D <LLD (0.7) < LID <llD <UD (0/6)

(rCikg(WET))

COLIARD Ommma Scan Co-60 20 1.33E+01 <uD (UD < LID (0/14) <LLD <llD <LLD (03) <LLD < LID <11D (0/6)

(pCilg(WET))

COIJARD Osmma Sean Cs-I34 20 9.65E+00 <llD <LLD

• 1J D (o 14) <UD <tlD <llD (0,7) <LLD < LID <LLD (0.'6)

(pCikg(WET))

COLLARD Gamma Scan Ca-137 20 1.07E+01 <llD <llD <11D (0/14) <llD < TID <llD (07) < t1D <UD <11D (0J6)

(pcikg(WET))

CotJARD Gamma Scan Fe-59 20 2.79E+01 <UD <llD (LLD (0/14) < LID < LID <tlD (0/7) <llD < t1D <llD (0/6)

(pCikg(WET))

collard Gamma scan I-131 20 1.65E+0i < TID <tlD <llD (O'14) <llD < LID <t1D (07) <11D <LLD <t1D (O'6)

(pCikg(WET))

COLIARD Gamma Scan K-40 20 NollD 2.30E +03 3 4t E+03 4.00E+03 (14'l4) 3.30E+03 3.59E+03 4.00E+03 (7/7) 3.00E*03 3 80E+03 4 80E203 (6'6)

(rCi1mWET)) Rcpwted Stathm W 66 53

.:;..... Y #5 ..

4

3. ,g.,

RADIORDCaCALEMYIItta Olr2L McNITORINC PhDORAMi:~

• x

% OYWTER CREEK NLM GENERATEMU NTATION}, ^

!?Q[:JANUARYg19M TitROUGH DECEMBER.19M ? -:;g

^

' ? ANNUAL 5UMMARF "

p SAMPLE p ci ANALYSIS;; :. NICtJDE ;.: 1IlDy . gINDICATORSTAff0NS '

_.... EHONEST ANNUAL MEAN .. . .,SACECItOUNDSTATIONS .

- 4TYPEl ^[y4OFgANAQ^ '

s  !! MIN ll MEAN dMAK} (IWTUT) 1 MIN ( 5 MEANY '$MAKh (N/ TUT) f;MINf! /MEANL 3 MAXJi j (N/ TOT)

> e

. pggy;; ie e .

<& g,,,,,,4 . , s collard Genune Scan La-140 20 1.79E+01 (11D <t1D <LLD (0/14) <llD (LLD (11D (OG) <1lD <LLD <t1D (or'6)

(pCiig(WET))

COLLARD Gamma Scan hin-54 20 1.06E+01 <llD <11D <llD (0/14) < t1D <11D < LID (07) (LLD <LLD < LID (O'6)

(pCiig(WET)) - ,

collard Gamma Scan Nb-95 20 1.31 E+01 <11D < t1D <llD (0,14) <llD < TID <LLD (67) *LLD <11D (LID (0/6)

(pCing(WET))

collard Genuna Scan Ra-226 20 1.94E+02 <11D <tlD (IlD (0/14) < LID <LLD <LLD (0/7) <llD <LLD < t1D (&6)

(pCiig(WET))

COLLARD Gamma Scan Th-232 20 415E+01 5.80E+0! 5.80E+0i 5.80E+01 (1r14) 5.80E+01 5.80E+01 5.80E+01 (1/7) < TID <llD <t1D (O '6)

(pCilg(WET)) Station-# 66 collard Gamma Scan Zn-65 20 2.97E+01 <11D . <LLD <11D (0!!4) (11D < TID <UE (0,7) <LLD <11D <tlD (0 6)

(rCilg(WET))

COLIARD Gamme Scan Zr-95 20 1.84E+01 (LID <llD (IlD (0/14) (LID (ILD <LLD (47) <11D <1lD <llD (G6)

(pCilg(WET))

Soft Gamma Scan lla-140 6 7.33E +01 <11D <llD < LID (0/4) <LLD < LID <LLD (0/2) < tlD <LLD <11D (07)

(pCilg(DRY))

SOIL Gamma Scan fle-7 6 1.03E+02 1.60E+02 2.00E+02 2.60E+02 (3 4) 1.60E+02 2.10E+02 2.60E+02 (27) < TID <llD < t1D (01)

(PCita(DRY)) Stathm 4 66 I

$4

l.-____ :i TABIE 3 >:

? RADIOLOGICAL ENVIRONMENTAL MONITORING FROGRAM }

[ OYtTTER CREEK NCCLEAR CENERATING NTATION 0 IJANUARYfl9N THROUGH~'DECEMRER 19N 2 ' ' " <

^ .. ANNUALNtfMMARYC p SAMPLE s 1. ANALYSIS :: .;. NUCLIDE V ..'. # OF v -

1LLD?. - INDICATOR STATIONS r . .. .. : HICIfEST ANNUAL MEANT.. ..

. ,1 BACECROUNDSTATIONS3

~

.TYPEi

^

J ANAL. !  ? MINT :: MEAN!( iMAK;I [(N/f0T)lj [ MIN & :- MEAN ) ?.MAK((NfrOT)} EMIN{l '; MEAN j-. MAX ^ : (N/ TOT)

PERF.

Seaslam #

SOIL Garruna scan Co-58 6 I.32E+0I < t1D (LLD (11 0 (0/4) (LLD (LLD <LLD (0/2) < LID < LtD <LLD (0,7)

(pCi.lgDRY))

SOIL Gamma Scan Co-60 6 1.65E+0I <LLD <t1D <llD (G'4) <llD <LLD <UD (0,2) <LLD <UD <LLD (02)

(pCag(DRY))

Soll Gamma Scan Cs-I34 6 1.27E+01 <llD <11D (UD (0/4) <LLD < LID <llD (02) <11D < LtD < t1D (0/2)

(pCikgDRY))

SOIL Gamma Scan Cs-137 6 NollD 9.90E+01 132E+02 1.60E+02 (4/4) 1.40E+02 1.50E+02 I.60E+02 ('2/2) 9.20E+01 1.26E+02 160E+02 (2'2)

(pCagDRY)) Reported Station-# 35 E Gamma Scan Fe.59 6 3.05E+01 <llD (LLD <UD (a 4) <WD < LID <11D (0/2) <Lt.D (UD < LID (S2)

(pCitgtD* H)

SO!L Gamma Scan 1-131 6 2.53E+01 <llD <UD <ILD (0/4) <11D < LID <t1D (0/2) <11D <UD < LID (0/2)

(pCi k gDRY))

SOIL Gamma Scan K-40 6 NollD 1.90E+03 235E+03 2. ROE +03 (4'4) 2.80E+03 2. ROE +03 2.80E+03 (2.2) 5.10E+03 7.IOE+03 910E+03 (22)

(pCikgDRY)) Reported Station-# 66 SOIL Gamma Scan Isl40 6 2.67E+0i <LLD <1lD <11D (0/4) <llD <UD <llD (0/2) (11D <11D <LLD (42)

(pCilgDRY))

SotL Gamma Scan Mn-54 6 IJ8E+0i <UD < tlD (UD (0 4) (UD <UD < LID (02) < LID IlD < U.D (0 2)

(pCi kmDRY))

55

? TABLE 3 A ... .. . . . .

.. l l

. RADIOLOCK.'AL ENVIRONMENTAL MONITORINO PROCRAM ?

, OYSTER CREEKNUCLEAR GENERATING STATION 4 s JANUARYs1994 THROUCH DECEMBElt.19N j ^ ~ ,

7ANNUALSUMMW Y-

.< 8 AMPLE;

ANALYSIS s : NUCLJDE u

. # OFj pLLD3 .. s INDICATOR 8TATIONSy  :. HIGIIEST ANNUAL MEAN >- , BACKGROUNDSTATIONS -

2 TYPE' . ANAki-:

- MIN y MEAN  : MAK t r. (.N/IUT) ( -: MIN y -j MEAM2 LMAX: (N/ TOT) i: MIN;;: fMEAN+

MAX: (N/ TOT)

_. p 501L Gamma Scan Nb95 6 1.9IE+01 <LLD <LLD < I.1D (0/4) <LLD <LJD <Lt.D (0/2) <I ID <LLD < l.1D (0/2)

(gCilg(DRY))

Soll Gamma Scan Ra-226 6 NollD 7.50E+ 02 8 55E402 9.50E+02 (4/4) 8.50E+02 8.60E+02 8.70E+02 (21) 2.10E+03 2.45 E+03 2.80E+03 (23)

(pCitgDRY)) Regwwted Station-# 35 SOIL Gamma Scan n 232 6 No LID 2.20E+02 3.43 E *02 430E+02 (4/4) 430E+02 430E+02 430E+02 (2'2) 8.10E+02 9.00E+02 9.90E+02 (2/2)

(g<i kg(DRY)) Reported Stati(m-# 66 SOIL Gamma Scan Zn45 6 2.90E+01 (LLD <LLD <LLD (0/4) <ll D <LLD <1lD (O'2) <LLD <tlD <llD (0/2)

(pCag(DRY))

SOI'. Gamma Scan Zr-95 6 2.73E+0i <tLD < t1D < LID (0/4) <LLD < t1D <LLD (0/2) (LID < LID < tlD (0/2)

(rCilg(DRY))

AQUATIC SEDl%IENT Gamma Scan Be-140 32 8.19E+01 (LLD <LI.D < LID (0.~24) <LLD <t1D < LID (0/4) (11D <LLD (LLD (GB)

(pCa kg(DRY))

AQUATIC SEDINfENT Ganuna Scan Be-7 32 1.26E+02 1.00E+02 238E+02 5.20E+02 (1824) 1.70E+02 3.55E+02 4.70E+02 (4!4) 1.40E+02 230E+02 3.00E+02 (6/8)

(pCikg(DRY)) Station-# 33 AQUATIC SEDl%IENT Gamma Scan Co.58 32 136E+01 <LLD <ILD (IID (0/24) <LLD <tLD (11D (0/4) <t1D <LLD <t1D (0 3)

(pCilg(DRY))

AQUATIC SEDi\fENT Gamma Scan Co40 32 1.60E+01 2.20E+01 3.14E+01 4.40E+ M (7/R 2. M *01 3 60E+01 4.40E+0! (3 4) < LID <IJ D

• LID (0 8) u SAMPLE ' q ANALYSIS; K N UCLIDEg j#0F(j, g LED; .,.. . ., INDICATOR STATIONS 7 g....,1NIG0fEST ANNUALMEANt v gg4f BACKCROUNDSTATIOfts  %-t  !

yTYPES,' n$ ' '

y ) MINI MEAN " .g:. . MAK ; (MrIUT) M #

, ~

?. ANAL,, b *

, . , $ MIftf-j.[m.

> ym. EAN VMAK% (N/EUF), ,<

, [ MEN f MEAN [MAXj (MrTUF)

AQUAUC ,

SEDIllENT Gamma Scan Cs-134 32 1.20E+01 <t1D <11D <llD (014) <11D <11D <llD (O'4) (UD <1lD <11D (01)-  !

(pCikgDRY)) i i

AQUATIC  !

SEDlilENT Gamma Scan Cs-137 32 2.03 E+01 2.10E+01 7.26E+0i 1.60E42 (17/24) 1.40E+02 1.48E+02 1.60E+02 ( 414 ) 220E+0! 4.46E+0! 6.70E+01 (8.1)  !

(pCilg(DRY)) Station # ~ 33  ;

AQUATIC SI Dli1ENT Gamma Scan Fe-39 32 3.50E+01 < t1D <11D <11D (0. 24) < TID < llD <11D (0/4) (11D < t1D <11D ' (0 8)

(pCikgDRY))

AQUATIC SEDIMENT Gamma Scan 1-131 32 3.58E+01 <11D <11D (11D (0/24) <11D <1lD <11D (0/4; <11D <1lD <llD (0/8)

(pCiltg(DRY))  ;

i AQUATIC SEDIitENT Gamma Scan K-40 32 NollD 1.40E+03 6.85E+03 1.50E+04 (24'24) 1.40E+04 1.48E+04 1.50E+04 (4'4) 1.20E+04 1.48E+04 1.70E+04 (11)  :

(pciig(DRY)) Rey =wied Station-# 33 AQUATIC SEDiilENT Gamma scan 1+140 32 2.58E+01 <llD <llD <UD (0/24) (I1D <UD <11D (0 4) <UD < t1D <1lD (0 8) -

(pCing(DRY))

l AQUATIC SFDtifENT Gamma Scan Mn-54 32 1.46E+01 <11D . <11D <llD (014) <11D < 11D <llD (0/4) (UD <1lD <11D (01) ,

(pcing(DRY))

• AQUATIC '

SEDIitENT Genune Scan Nb-95 32 1.98E+01 <UD <UD <llD (0/24) <11D <11D (11D (0/4) <11D <llD <11D (0,1)

(pCikgDRY))

AQUATIC SEDillENT Gamma Sean Ra-226 32 NollD 4.40E+ 02 1.02E+03 1.70E+03 (24 24) 1.20E+03 1.4SE+03 1.70E+03 (4 4) 8.20E+02 I.30E+03 1.70E+03 (11)

(pCi Lg DRY)) Repawied S:seian # 33 57

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

! TABLE 3- ,

7 RADIOLOGICAL ENVIRONMENTAL MONITORING FROGRAM (

l- OYSTER CREER NUCLEAR GENERATING STATION!

lJANUARYd19N THROLL11 DECEMBER;19N ; <

" % ANNUALSUMM4RY' l

e SAMPIE  :~ ANALYSIS : :- NUCLIDE 1 # OF. .' .. LLD y' s INDICATOR STATIONS; <  ; HIGHEST ANNUAL MEAN;- < BACECROUNDSTATIONS m jTYPE2 s 1 ANAL!  ? MIN / (MEAN) ):.MAy. i(NTOT)j. $MINSQMEAN[ 3 MAL (NGOT) jMI!Q iMEANj '. MAX ' (N/ TOT) 1 -

i  :: PERFJ: ( - Sesseen.#

AQU itC SEDialENT Gamma Scan Th-232 32 No11D 2.20E+02 4.06E+02 6.00E+02 (24/24) 5.50E+02 5.83E+02 &00E+02 (4/4) 4 00E+02 5.98E402 7.10E+02 (11)

(pCikgf DRY)) Reported Station-# 33 AQUATIC SEDl%IENT Gamma Scan Zn-65 32 3.49E+01 < tlD < TID < t1D (0,24) < t1D <t1D <LLD (a4) < TID < tlD < LID (at)

(fCikg(DRY))

AQUATIC SEDl% LENT Gamma Scan Zr-95 32 2.69E *01 < tlD < t1D < LID (0 24) < t1D < tlD < t1D (0/4) < LID < t1D <LLD (01)

(pCi kg(DRY))

BLUE CRAB Gamma Scan Da-140 18 4.28E+01 < TID <t1D < LLD (0/12) <!ID <LLD < t1D (0/6) <tlD <LLD <LLD (0/6)

(pCikg(WET))

BirECRAB Gamme Scan De-7 18 7.83E+01 <tJD <11D <ll.D (0/12) 11D <LLD <llD (0 6) < tLD <t1D < t1D (0/6)

(pcikg(WET))

BLUE CRAB Gamma Scan Co-58 18 105E+01 <llD <ilD (LLD (0/12) < llD < LID <llD (O'6) <tlD < t1D < t1D (0 6)

(pCikg(WET))

IILt'E CRAB Gamma Scan Co40 18 1.28E+01 < LLD < LID < LID (0/12) < tJD < TID <llD (0 6) < LID < t1D <llD (0'6)

(pCikg(WET))

BLUE CRAD Gamma Scan Co134 18 9.50E+01 < TID <t1D <LLD (0/12) < t1D < TID < TID (0/6) < TID <tlD <LLD (0:6)

(pCikg(WET))

BirE CRAB Gamma Sean Cs-137 18 1.IIE+01 < t1D < t1D <t1D (0 12) < tlD < llD <llD (0 6) 'llD < tJD < t1D (0 6)

(fCi kg(WET))

58

. . . . . . . .. . .. : TABLE 3 2.. . . . . . . . . .

L RADIOIDGICAL ENYlRONMENTAL MONITORINC PROGRAM 4 3 OYSTER CREEK NUCLEAR GENERATING FTATION 1 2 JANUARn19N THROUCH DF4T.MBER.1994 /

"2 ANNUAL

SUMMARY

/ EO'

.<. SAMPLE . :c ANALYST $ -: s NUCLIDE J f #OF.( .: LID / . _g INDICATOR STATIONS 1...... ..

. . .): HIGHEST ANNUAL MEAN k . .. . t BACECROUNDSTATIONS:

0TYPEi j ANAIJ.

g MIN.1 MEAN f MAK5 }(N_/F_OT)) (MIN [ 4 MEAM;; -it MARC 2 (N./T. O..T) 9. [ MINf; 4 MEAN ? : MAXs l (N/ TOT) s .

BLUE CRAB Ganwna Scan Fe-59 18 2.65E+01 <llD < TID < LLD (0/12) <t1D cl.1D <1lD (0/6) (LLD <t1D < LID (0/6)

(pCitgWET))

DI AT CRAB Gamma Scan 1-131 18 1.42E+01 <t1D <11D < t1D (0/12) <UD LLD <LLD . (O '6) <LLD <!J n < tJD $6)

(pCilg(WET))

Hl.t E CRAB Gamma Scan K-40 18 No llD 2.10E+03 2.70E+03 3.60E+03 (12'I2) 2.10E+03 2.75E+03 3 60E+03 (66) 2.00E+03 2.23E+03 2.60E +0) (6/6)

(pCi kgWET)) Reported StatiorWP 93 B11T CRAD Gamma Scan La-140 18 1.66E+01 <tlD (LLD < t1D (0/12) (LLD < LID <ILD (0/6) <t1D < Ul) <LLD (0/6)

(pClitg(WET))

BLUE CRAB Gamma Scan Mn 54 18 1.07E+0i < t1D < tlD <11D (0/12) <t1D <llD <t1D (0/6) <llD < t1D < t1D (O'6)

(pCilgWET))

DIITCRAD Gamma Scan Nb-95 18 1.17E+0i < TID <llD < LID (0/12) <tlD <UD <llD (O'6) <11D (LLD <LLD (O'6)

(pCikgWET))

Illt'E CRAB Gamma Sean Ra-226 18 1.95E+02 2.00E+02 2.00E+02 2.00E+02 (l!!2) 2.00E+02 2.00E +02 2.00E+02 (l'6) <llE (Lt.D <11D (0/6)

(pCi LgWET)) StationJ 93 DLUE CRAD Gamma Scan "Ih-232 18 4.17E+01 <t1D <LLD cllD (0/12) < TID < LID <11D (0/6) <LLD <llD (LID (0%)

(pCilg(WET))

HLUE CRAB Gamma Sean Zn45 18 2.75E +01 <LLD < t1D < tJD (0 12) <llD < LID <WE (0 6) <llD < LID < llD (G6)

(pcit (WET))

59

_ __ _ ..- _ _.__._.m . . _ . . . _. . _ _ - . . . . . . _ _ . _ . . . ._ _ .. . .

+ TAIBLE3 r x ~ .,

-- RADIOLOGICAL ENVIRONMENTAL MONTTORINC PItOCRAM i:

i OYNTER CREEK NOTLEAOGENERATING FTATION) ij JANUAR%19N THROUCH DECEMBER,19M f

'EANNtlALSUMMAltN ' ~'

1 SAMPIX v + ANALYSIS [ i NUC1JDEg ; 8 OFj .: LLD i

t. . c INDICATORSTATIOMsn .. . , .. c HIGHEST ANNUAL MEAN 4 ..

F SACECROUND STATIONS e tTYPF.? J' ANAL 2.?

s.. MIN.1 i.MEAM::. . MAKi.1. (N/tU..T) { 2 MIN 3 -j MEAN . ,: ! MAK ^ y,

... . (N/TO,T). ? MIN:f S M. EAN..;. : MAX 3 i(MtT. O...T)

BLUE CRAB Gamma Scan Zr-95 18 1.8tE+01 < LID <tlD <LLD (0/12) (LLD <llD <tlD (0<6) <llD <t1D <LLD (06)

(pCikg(WET))

BLLTFISit Gamma Scan Ba-140 12 5.08E+01 < tlD <llD < tlD (0/11) < LID <tlD <LLD (0/I) < tlD (LLD <ILD (0/I)

(pCikg(WET))

IILITFisil Gamma Scan lle-7 12 9.23E+01 < llD <llD <t1D (0/II) < LID < t1D <LLD (Oil) <LLD <llD e llD (0/1)

(rCi kg(WET))

BLUEFistl Gamma Scan Co-38 12 1.18E+01 <tlD <LLD <LLD (Os t i) <llD <LLD < TID (0/l) <tLD < LID <LLD (0 8)

(pCikg(WET))

It!1TFisil Gamma scan Co.60 12 1.35E+01 < llD < LID < LID (0/11) < LID <LLD <t1D (O'l) <llD <LLD (LLD (O't )

(pCikg(WET))

I3LtTFISII Gamma Scan Cs-134 12 1.08E+01 < LID <LLD <LLD (0/11) (LLD < ILD <LLD (0/I) < TID <LLD (LLD (G'l)

(pCikg(WET))

BilTFISil Gamma Scan Cs-137 12 2.02E+01 1.20E+0! 1.40E+0! 2.00E+01 (6/11) 1.20E+01 1.40E+01 2.00E+01 (6/10) <LLD (LLD < TID (0< l)

(pCilg(WLT)) Station # 93 BLLTFISit Gamma Scan Fe-59 12 2.93E+01 <LLD <llD < t1D (0/11) < LID <t1D < TID (0/l) (LID <LLD <llD (G I)

(pCikg(WET))

BLtTFISil Gamma Scan 1-131 12 1.86E+0! <llD < t1D < tlD (O'll) < llD < t1D < t3D (Gel) <llD < 1lD < llD (0. I)

(pCiig(WET))

60

STABLE 3e i ILADIGIDCICAl) ENVIRONMENTAL MON 110 RING PROCRAM 5 5 OYSTE3 CREEK N UCLEA3 GENERATING STATION i

/JANUARL 19N TIIItOUCH DECEMBFA 19N k '

• ANNUAL SUMMA *Y -

! .SA%IPI.E ANAL YNIN N UCLil)E #OF LLD 13DICATOR NTATIONS ,- IIICIIENT AANUAL MEAN BACAGROUNIP NTAIIONS TYI'E ANA1.  ; MIN 3tEAN . MAX (NfrOT) ~ MIN: ' %IEAN - SIAX ' '(NfrOT)' ' >IIN . ' > LEAN '- SIAN .(N/IOT)

PFRF. Station # 1 11L0111511 Uanuna Scan k-40 12 NollD 3.00E 4 03 3.72 E+03 5. RUE +03 (11/11) 550E+03 3. ROE 403 S.80E+03 (!!I) 3.60E+03 3 60E403 3.60E*03 (Ill)

(pCi kg(WET)) Reported Station 8 33 BLUEFIsil Gamme Scan La-140 12 1.78E+01 <LLD <LLD <LLD (0/II) (IlD <1lD <LLD (0/I) <11D <LLD <llD (0/I)

(pci-MWET))

BLUEFISH Osm ma Scan Mn54 12 1.16E+01 (LLD <llD <llD (0/11) <llD <11D <LLD (0/1) <LLD <11D <llD (0/l)

(PCi4 WET))

BLUEFISH Genune Scan Nb95 12 1.26E+01 <llD < LID <11D (0/II) < LID < LID <llD (0/l) <llD <llD <1JD (0/l)

(pCdg(WET))

BLUEFISH Osama Scan Ra-226 12 2.32E+02 <llD <1lD < LID (0/11) <L1D <11D <11D (0/l) <llD <llD <11D (0/l)

(pChia(WET))

BLUEFISH Oenune Scan 3 -232 12 4.67E+01 <L1D <11D <11D (0/11) < LID <llD <11D (0/I) <11D <1lD < LID (0/I)

(pCiig[ WET))

BLUEFISH Omnuma Scan Zn45 12 2.06E+01 <LLD (IlD <llD (0/11) <1lD <1LD <11D (Orl) <LLD <llR <11D (0/I)

(pCag(WET))

BLUEFISH Genuna Scan Zr-95 12 2.00E+01 <11D (11D <11D (0/1I) <llD <11D <llD (0/I) <11D <1lD <11D (0/1)

(pCAg(WET))

SUMMER Be-140 6 * * * * *

• F1DUNDER Onnens Scan 4.67E+0 B (*F) (*F) <11D <llD <llD (0/6)

(pCih1 WET))

61 ,

_ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ ___ _ _ _ __. -. . - ~-. - - _ _- _. . .-- _- . _ ~ _ - . _ __..__m ._ _ _ __

TABLE 3

RADiotDGICAL ENVIRONMENTAL MONITORING PROGRAM i}

l OYSTER CREEK Nt1 CLEAR GENERATING !!rFATION [f fJANt!AR$19N TilROUCH DECEMRER.1994 {::

? ANNt!AL StNMARC ~ ' ' W

-:: SAMPLE . s ANALYNES .. t NUCLIDE: ' MW -- 'LLD-

. nINDICATOR STATIONS 5  ; HICHEST ANNUAL MEAN.s -J BACEGROUND STATM)N$

- ANAIJ j MIN..' s MEAN -j fMAKi (NrtTFT) iMIK) MEAN )] 2 MAKP . (NTFOT)3 iMINj iMEAN )

1 TYPE:. x  ; MAX ? ::(N/ TOT)

- PERF. ' hhW -

SUhthlER FIDUNDER Gamma Scan De-7 6 7.67E+01 * * *

(*!*) * * *

(*!*) <t1D < t1D <LLD (0/6)

(rCi kgWET))

SUhlitER FIDUNDER Gamma Scan Co-38 6 1.02E+01 (*/*) (*/*) <llD <LLD <LLD (Oc6)

(prikg(WET))

SUhtNfER FIDUNDER Gamma Scan Co40 6 1.18E+01 (*/*) * *

(*!*) <11D (LLD <llD (O'6)

(pCikWWET))

St %I%f ER FIDUNDER Gamma Scan Os-134 6 9.50E +00 * *

(*!*) *

(*/*) <llD < t1D < tlD (0 6)

(pcikg(WET))  !

St%fNfER Flot'NDER Gamma Sean Cs-137 6 1.10E+01 (*/*) *

(*!*) *LLD <lll) <LLD (O'6)

(rCikg(WET))

SUhlitFR FtIWNDER Gamma Scan Fe-59 6 2.32E+01 * * *

(*/*) * * * (*,*) <tJJ) <llD < LID (0 6)

(rCils(WET))

t SI'NI%IER Fint'NDFR Gamma Scan I-131 6 1.52E+0i * *

(* *) * * *

(* *) <!J D a llD < tJD (0 6)

(PCik af WFT))

62

k NADIOLO";ICAL ENVIRONMENTAL MONTTORING FROGRAIN TOYSTER CREEK NUCLEAR GENERATING NTATION t

, f JANUAR$ 19M TIIROUGH DECEMBER 219Mjl ' '

• ANNilAL

SUMMARY

" ^ -

, t SAMPLE y _-: ANALYSIS . .'i.. NUCtJDE;: :. W OF t . " LID O

. ;;tNDICATORSTATIONS3 . ~ HIGHEST ANNUAL MEAM d .

J SACEOROUND 5TAllONS x 0 TYPE:7 ' 5 ANAL 2} ' T MINJ MEAN ' ;;MAKj (M/ TUT) I[ MIN? 4.MEANl- ' MAXJ f.'(N/ TOT)) [ MIN] hMEAM L IMAX; .. (M/TUI) 1 PERF/

• Itteelen # 0 SUhthlER F1DUNDER Gamma Scan K-40 6 NoIJD * * *

(*/*) * * *

(*/*) 3.00E +03 3.33E+03 4.00E+03 (6'6)

(pCilg(WET)) Reputal SUAIMER FIDUNDER Gamma Scan 14-140 6 1.60E+0! * * *

(*/*) * * *

(*/*) < LID < LID < LID (0/6)

(pCilgWET))

St?ltMER FIDUNDER Gamma Scan Mn 54 6 9.83E+00 * * * * * *

(*/*) (*/*) <LLD <LLD < LID (0/6)

(pCilgWET))

SirklitER FIntNDER Gamma Scan Nb-95 6 1.13 E+0! * * *

(*/*) * * *

(*/*) <llD < llD <llD (0 6)

(go tgWET))

St atifER FIJWNDER Gamma Scan Ra-226 6 1.76E+02 * * * * *

(*/*) *

(*/*) < LID < LID <LLD (O'6)

(pCilgWET))

St%f%IER T15WNDER Gamma Scan Th-232 6 4 00E* 01 (*s ')

(*/*) (LLD <LLD <LLD (0/6)

(pCikgWET))

St3 filer FifWNDER (pCi kg(WFT))

Gamma Scan Zn45 6 2.67E + 01 * * *

(*. *) * * *

(") < IJ D < IJD < t.ID (0 6) 63

!  :; TABLE 3 - >

[ RADICIDCICAL ENVIRONhlENTAL RIONITORING PROGRAM ?

-! CYgrrER CREEK N UCLFX1 GENERATING STATION i ,

sco lANUAR%19N TifROL!Cll DECEMBFJt.19N ~)

ANNITAL 951mf% FAT SA%ll*l.E ANAIA NIS N1'CI.llW, ,#OF 11D l.NillCATOR NTAllONN lilGIIESI ANN!!Al, %IEAN - HAL AGROUNI) N4AllONN

. TYPE ' AN Al. AllN %IEAN NIAN (N401') SilN %IIMN ' ' 3IAX (NGOT) SilN - 'AIEAN SIAN ' (N401-) +

PF Rl". Station 4 St'5111t R

• <UD FLOUNDER Gamnn Scan Zr-95 6 1.75E+0! * *

(*!*) * * *

(*i') <LLD (LLD (O'6) ;

(pCikg(WET)) l 9.00E+0! * * * * *

• SEA BASS Omnune Scan Be-140 2 (*/*) (*F) cLLD <11D <11D (0/2)

(pCikg(WET))

SEABASS OsnuneScan Be-7 2 1.50E+02 * * *

(*F) * * * <11D <UD

(*F) <llD (0/2)

(pChig(WET))

SEA BASS Genuna Scan Co 58 2 1.85E+01 (*F) (*F) <11D <LLD < LID (0/2)

(PCiig(WET))

SEA BASS h Scan Co40 2 2.50E+01 (*F) * * *

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

(pCiVn1ET))

• *

• I SEA BASS Genuna Scan Co.134 2 1.70E+01 (*F) * * *

(*F) <uD <uD <11D (0/2)

(pCikg(WET))

SEA BASS Omnuun Scan Ca-137 2 2.30E+01 (*/*) *

(*F) (LLD (UD <UD (Gr2) -

(pCih[ WET))

64

[

. . . . . . . . . .. .? TABLE 3 . . . . . . . . . . .. ...._.S..

? RADIOLOGICAL ENVIRONMENTAL MONITORINO FitOGRAM 7:

E OYFTER CREEK NUCLEACCENERATING STATION'

? JANUARY,19N TItROUCl! DECEMBER.19N 5 '

0~ ANNUAL SUMMAOY:

l iSAMPLE2 , ANALYSIS - 1NUCLIDE 7 (4 OF. 7 ;g LLD.g ,,

_11NDICATORSTATION$g , . . .s HIGHEST ANNUAL MEAN.qs . 9 BACKGROUND STATIONS .:. *

^

iTYPE9 3ANA10 ~ .i MIN i , MEAN iMA%F (N/IUT) ? MIN 0 n MEAMM if MAKy (N/FOT) 1 MINl iMEAN(. ? MAX:.: ? (N/ TOT)

~ *~~'

i PERF.E > ' 9teston-#

• * * * * * <llD <LLD <11D SEA BASS Gamma Scan Fe-$9 2 4.30E+01 (*F) (*!*) (0/2)

(pCikg(WET))

SEA BASS Gamma Scan I-131 2 3.00E+01 (*F) (*F) <llD <llD <llD (a2)

(pCikg(WET))

SEA BASS Gamma Scan K-40 2 NollD *

(*F) (*F) 3.30E+03 3.30E+03 3.30E+03 (2/2)

(pCilg(WET)) Reported SEA BASS Gamma Scan 12-140 2 3.00E+01 (*/*) (*F) <llD < llD <LLD (0.7)

(pCitg(WET))

SEA BASS Gamma Scan Mn-54 2 1.70E401 (*F) (*F) <LLD <LLD <Lt.D (0.7)

(pCitg(WET))

SEA DASS Gamma Scan Nb-93 2 2.50E+01 (*?) (*F) <LLD <LLD <11D (a?)

(pCiLg(WET))

SEA HASS Gamma Scan Ra-226 2 4 00E+02 * * *

(*. * )

• * * (*;*) = 11D < LID < LID (0:2)

(Wila(WFT))

65

_ . _ . _ _ . _ _ _ _ _ - _ _ _ - - - _ _ _ - -_ - _-____--a - _ - - . _ _ _ _ - _ - _ _ _ _ . - - _ - - -

^ c . .. , ? .. pTABLE 3 a . - , <

j RADIOIDCICAL ENVIRONMENTAL MONTTOItIMO PROGRAM y OYSTER CREEK NUCLEAR GENERATING FTATION 0

/JANUARYy1995 THROtM2R DECEMBER.1994j

1ANNt%, 1,5UMMARYS c

SAMPLEy  ;( ANALYSIS 6 NUCLIDEp ;#OF.A ,;L1D e

' . . .. . ? INDICATOR staff 0NS .

& HMHEST ANNUAL MEAN 0 ~- . J ACKOltOljND B STATIONS-'v.. -

iTYPEI ^

?.MINh MEAM ^ W 't [MAXj (N/fUT) ,"J ^MINjl iMEAN MIMAC (N/ TOT) { MIN [,[MEAN/ ;MAXt I(N/ TUT)

.t ANAL.]

E PERF.:. he SEA BASS Gamma Scan D-232 2 9.00E+01 * * *

(*/*) * * *

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

(pCilg(WET))

SEA BASS Gamma Scan Zn45 2 3.00E+01 (*/*) * * *

(*/*) (UD <1lD <11D (0/2)

(pCiig(WET))

Gamma Scan * * * * *

• SEA DASS Zr-95 2 3.50E+01 (*/*) (*/*) <11D <LLD <1lD (0/2)

(;Cilg(WET))

CIAMS Gamma Scan 14 140 63 4.60E+01 <11D <11D <11D (0/39) <11D <llD < LID (0/13) ellD <11D <11D (0'24)

(Ifikg(WET))

CLAMS Gamma Scan De-7 63 8.48E+01 <1lD <llD (11D (0/39) <llD <!lD <11D (0/13) (UD <1lD <llD (0.'24)

(pCiigWET))

CIAMS Gamma Scan Co-58 63 1.04E+01 < 11D < LID <1lD (0 39) <11D <1lD <11D (0/13) <llD <11D (11D (0/24)

(pCikgWET))

CIAMS Gamma Scan Co40 63 1.33E+01 <1lD <11D <1lD (0/39) <1ID <11D <11D (0/13) <11D <llD < 11D (0/24)

(pcikg(WET))

01_uls Gamnw Scan Cs-134 63 9.56E+00 < 1lD < llD silD (0 39) <llD <1lD < 11D (O'13) <llD < l.lD <1lD (0 24)

(PCs Lg(WET))

66

4 ...,...............Y. . , . ... ,. . . , b

! RADIOLOCICAL ENVIRONMENTAL MONITORING PROGRAM 5

'i% OYSTER CREEK NUCLEAR GENERATING STATION i

' f JAN11ARY219N THROUGH DECEM BERs 19N @

? ANNUAL

SUMMARY

g -

r

.! SAMPLE : s -: ANALYSIS - ! NUCLIDE #OF1 l LIE;:  ; INDICATOR STATIONS L . .. . . '; HIGHEST ANNilAL MEAN t.. . . . .; BACKCROUND STATIONS v

'a TYPEi 2ANAth MIN i MEAN y MAX J !. (N/FOT)f f: MIN .L lMEAN) [ MAKs- [(M/r0T)) [. 341N1 i MEAN 0- tMAK> (1/ ROT)

Pirppj pm CIAAIS Gamma Scan On-137 63 1.07E+0! <llD <llE < LlD (0/39) <LLD <!JD <ll.D (0/13) <l.1D <11D <!JD (0/24)

(pCikg(WET))

CLuis Gamma Scan l'e-59 63 2.41 E+01 <uD (llD <LLD (0d9) <llD <LLD (LLD (0!!3) (LLD <UR <LLD (0/24)

(pCikg(WET))

CIANIS Gamma Sean 1-131 63 1.57E+01 < LID <llD <llD (0/39) <11D <UR <LLD (0/13) < LID <LLD <LLD (0/24)

(pCi kg(WET))

CIAAIS Gamma Scan K-40 63 No 11D 630E+02 1.29E+03 1.80E+03 (39/39) 8.30E+02 136E403 1.80E+03 (13/I3) 1.20E+03 1.44E+03 1.90E+03 (24'24)

(pCikg(WET)) Rerortal Stahon-# 24 CisutS Gamma Scan l # 140 63 1.81E+01 < t1D < t1D <LLD (0/39) <LLD <11D <11D (0/13) <11D <1lD <t1D (024)

(pcilg(WET))

Clauls Ganune Scan kin-54 63 1.05E+01 <t1D <LLD <LLD (0/39) <11D <llD <LLD (0/13) <UD < LID <LLD (0/24)

(pcikg(WET))

CIAhls Gamma Scan Nb-95 63 1.32E+01 <L1D <LLD <11D (0/39) <11D <t1D < LID (0/I3) <LLD < 11D <llD (0/24)

(pcikg(WET))

CIAhlS Gamma Scan Ra-226 63 2.IOE+02 7.00E+02 7.00E+02 7.00E+02 (1/39) 7.00E+02 7.00E+02 7.00E+02 (1/13) 1.90E402 1.90E+02 1.90E+02 (1/24)

(pcilg(WET)) Stauen-# 23 CLutS Gamma scan Th-232 63 4.56E* 01 (LID <LLD <ljD (O'39) <llD <llD <UD (0/13) <1lD <llD <LLD (024)

(rCi1gWET))

67

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:.  :'  ? V V l 7  ? $  ?  ?  ? E  ?  ?  ?

%. ::n hs: W  ; y W W W W W W

':W-

+ J ~

4 y g g n y y y y

... .y ,

m m m m m m m m m e

• 1 h

~

y  ? A E b b E

- 3 4 4 4 4 3 4 ba ,

x ni & a a a a 3 3 a 3

.l l l l l l l l l

[3 . m . . . . . .

~

air9 a Sa jax 9 ga l:, [a 8a ja [a 9 se ni axq a . 95 se

<g> a ex atm Eg og g g og - og g

TABLE 3: ~

? RADIOLOGICAL ENVIRONMENYA13 MONITORINC FROGRAM ;

J OYSTER CREEK NUC1 EAR GENERATING STATION i; .

F JANUARYa19N THROUGH DECEMBElt.19M s-eANNUE N Vt "~

l

- '. SAMPLE : r ANALYSIS e r NUCLIDE<  :

NOF4 .LLD= .. INDICATORSTATIONS e . , . ;: HICHEST ANNUAL MEAN :::  : BACECROUND STATIONS 1 l TYPE.- -ANAIJ l MIN / ) MEAN.'?t MAK[ L(MrrOT)h hMINi i.MEAN? ? MAK?; ;(NflUT)T b MIN 1.- !MEANi J MAX i 5 (N/ TOT) w

_ yyy :

ST RIPED BASS Gamma Scan Ba-140 11 4.27E+01 (LLD <llD <llD (0/11) <llD <LLD < LID (0/11) * * *

(*/*)

(pCilg(WET))

< LID < llD <11D * *

• STRIPED BASS Gamma Scan Be-7 11 7 27E+ 01 <llD <1lD <1lD (0/11) (0/11) (*?)

(pCilg(WET))

STRIPED BASS Gamma Sean Co-58 11 1.04 E+01 (LID < llD <llD (0/11) (IID <LLD <11D (0/11) * * *

(*r)

(pCikg(WET))

STRIPED BASS Gamma Scan C060 11 1.lRE+01 < ILD <llD <1lD (0/11) <11D < LID (11D (0/11) * * *

(*/*)

(pCiig(WET))

STRIPED BASS Gamma Scan Cs-134 11 8.55E+00 41D <11D <llD (0/l1) <1lD < 11D <LLD (Wil) * * *

(*s)

(pcing(WET))

51DIPED BASS Gamma Scan Cs-137 11 1.21E+01 1.10E+01 130E+01 1.70E+01 (4/11) 1.10E+01 1.30E+0! l.70E+01 (411) * * *

(*r}

(pCikg(WET)) Station # 93 STRIPED BASS Gamma Scan Fe-59 11 2.64 E+01 <llD <11D <11D (0 11) <1lD <1lD <1lD (0/11) * * *

(*/*)

(g<ilg(WET))

STRIPED BASS Gamma Scan 1-131 11 1.47E+01 <11D <11D <11D (0/11) <LLD <llD <11D (0/II) * * *

(*F)

(pCilg(WET))

STRIPED ilASS Gamma Scan K-40 Il No llD 3.00E+03 3.4 t E + 03 3.90E+03 (11/11) 3.00E+03 3.4 t E+ 03 3.90E+03 (11/11) * * *

(*M)

(pCi n g(WET)) Reponed Sia:M 93 70

MADIGl.OCICAL ENVIRONMENTAL MONITORINC PROCRAM g

, OYSTE3 CRI'EK NtTI.EAO GENERATING STATION i

%>;; ~ SJANilARYs 19N TIIROUCil DerrEMBER.1994 i arw. va.2 ~

SANNt!AL SUMM4RY SAMPl.E ANAIMIN- N L'CI.lDE # OF - 1.1 D -  : IN DICATOR STATIONS IllGilr.aT/ONt%I,MFAN - .. ssACKGROUND STAllONS c TYPE ANAL. ^ MIN MEAN MAX (NR OT) MIN  : MEAN - SLG '- 0 l Tis s I " AllN i MEMN -' SIAX ' (NROT)

PFRF. Staem# ,

S I RIPt D ilASS UanunaScan 14-140 11 1.4 E + 01 a ll.D < LI D < tlD (0:11) <LLD (LLD silD (0 11)

( *; * )

(pCikg(% ET))

STRIPED RASS Ganwna Scan hin-54 11 9.9 t E+00 <tLD < llD <LLD (0/II) <llD (LLD <llD (0/11) * * *

(*!*)

(pCikg(WET))

UitIPED BASS Osame Scan Nb-95 11 1.lBE+01 <1lD (11D <llD (0/11) <llD <llD <llD (0/11) * * *

(*r)

(pCag[ WET))

511tlPED BASS OmnumaScan Ra-226 11 1.77E+02 (IlD <1lD <11D (0/11) <11D <IlD <!lD (0/II) * * * (*p)

(pC'W)

STRIPED BASS Genuma Scan Th-232 11 4.27E+0! <!1D <IlD <11D (0/11) (LID <1lD <llD (0/11) * * *

(*r} i (pCiMWET))

STRIPED BASS Genens Scan Zn45 11 2.71E+01 <11D <llD <!lD (0/II) < LID <UD <1lD (0/11) * * *

(*r}

(PCag(WET)) i f

STRIPED BASS OmnumaScan Zr 95 11 1.67E+0i < LID <11D <1lD (0/11) <llR < LID <11D (0/11) * * *

(*r)

(PCa s(WET))

WIhTER FIDUNDER Omnunm Soma Ba-140 2 4.50E+0! <11D <1lD <llD (0/2) < LID < LID <1lD (0/2) * * *

(*r)

(pCiMWET))

WINTER FLOUNDER OmneneScan Bo 7 2 S.00E+01 <llD <1lD <llD (0/2) (IJD <11D <1lD (0/2) * * *

(*r)

(pCas(HTTD 71

i .

. .z . . . . . .. f: TABLE 3 i:. . . . .

1 RADIOLOGICAL ENVIRONMENTAL MONTTORINO PROGRAM i

L OYSTER CREEK NUC114R GENERATING BTATION J i f JANUARYg19N THROUCH DFCEMBER,19Mi

~ ci ANNtfAL

SUMMARY

s

- SAMPLE;

. 7. ANALYSISj 2 NUCLIDEo 1p OF-/-..  ; LIE :( ,. s INDICATOR STATIONS.:: . . . .. , -; HIGHEST ANNUAL MEAN e -- SACKCROUND STATf0MS *

{ {: TYPE)

{-ANA1.) " : MIN [ MEAN ): MAKg ](MITOT)? ! MIN.? {MEANlj : MAK:7 [(N/ TOT)l JMIN[ :L MEAND 1 MAX ! : (N/ TOT) .

PFRU - W ~

WINTER FtDUNDER Gamma Scan Co-58 2 1.05E+0i <llD <11D <llD (00) (11D <llD <1lD (0/2) (*F)

(;CilgWET))

WNTER 11DUNDER Gamma Scan Co40 2 1.20E+01 < t1D < LID < llD (02) <11D < t1D <11D (0/2) * * *

(*/*)

(pCitgWET))

WINTTR Flot% DER Gamma Scan Cs-134 2 9.00E+00 <llD < l.lD (11D (01) ellD <llD < t1D (0 2) * * *

(*r)

(g<ikgWET))

<t1D <llD <t1D <t1D <tlD <11D * * * (*p)

WINTER FIDUNDER Gamma Scan Cs-137 2 1.05E+01 (0/2) (0 2)

(pCilg(%TT))

WINTER FIDL'NDER Gamma Scan Fe-59 2 2.50E+01 <llD < LID < t1D (0/2) < TID < t1D < t1D (0/2) * * *

(*r)

(pCi kgWET))

WINTER FIDUNDER Gamma scan 1-131 2 1.45E+01 < LID < LID <11D (0.7) <llD <llD <llD (O'2)

• * * (*;*)

(pCilgWET))

WINTER FIDUNDER Gamma Scan K-40 2 No11D 3.40E+03 3.45E+03 3.50E+03 (2/2) 3.40E+03 3.45E+03 3.50E*03 (20) * * *

(*i+)

(pCikgWET)) Repwted . Station.# 93 WINTER FLOUNDER Gamma Scan l # 140 2 1.55E+01 <11D <!lD <11D (0/2) <11D <llD <11D (00) * * *

(+/*)

(pCilgWET))

WINTER l10UNDER Gamma Scan Mn-54 2 l.05E401 <llD <l.lD < LID (0/2) < LID <llD < LID (07) * * * (*p) yCika(WET))

72

lib . . . Mi ., . . . , e, . . ... . STABLE 3 3 .. jrg- 7. ,.

if.! RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM !

% OYttrER CREEK NUCLEAR GENERATING STATION E

[JANUARYd9N THROUGH DECEMBER.19N $ -

rs

h% 5UMMMY1- ' '

l e

I sSAMPLEs tAMALYSIS j icNUCLIDEN j #OFg itIlD3 .. 7 INDICATOR STATION 8 i x . . f. MicHEST ANNUAL MEANj ,,,_s. g BACKCROIMDSTATIONS s jMINf ]MAnp (N/FOT) IMINj $MEAN[ .3MAKi f/(N/NT)[^:.: ;f MIN [ [MEAN[ 5 MAXI ((N. TUT)

T TYPE d . .p.se .. . m.. SANAle MEAM y 4 ' -

~ ^-

s fpgggy ,

g,,gg,,4 -

WINTER ILOUNDER Ganvas Scan Nt>.95 2 1.30E+01 < td (LIE < LID (0/2) (UD (11D <llD (0/2) * * *

(*/*)

(FCitgWET))

WINTER FIDUNDER Gansna Scan Ra-226 2 2.00E+02 <LLD <LLD <llD (G'2) <llD <llD <UD (02) * * *

(*!*)  ;

(pCilgWET))  !

i WINTER Fl(WNDER Gamma Scan ,, Th-232 2 4.50E+01 <llD <UD (LLD (0/2) <llD <UD <LLD (07) * * *

(+/*)

(pcingWET))

WINTER FLOUNDER Osmma Scan Zn-65 2 3.00E+01 <UD <UE <UD (0/2) <LLD <tLD <LLD (0/2) * * *

(*/*)

(pClig(WET))

WINTER FIAR.fNDER Gamma Scan Zr-95 2 l.75E+01 <llD < LID < llD (0.7) < LID <LLD <LLD (0/2) * * * -

(*/*)

(pCikg(WET))

BID %TISil Gamma scan Ba-140 1 100E+01 <LLD <UD <tLD (Oil) (11D <llD <LLD (0/1) * * *

(*!*)

(pCi kg(WET))

BID %TISil Gamma Scan Ik.7 I 8.00E+01 <LLD <LLD <llD (0!I) <llD (UD (UD (0/l) * * *

(*/*)

(pCilg(WET))

BIDWFISIl Gamma Scan Co-58 I I.10E+01 <LLD <11D < LID (0/l) <llD <UD <LLD (0/1) * * *

(+/*)

(pCikg(WED)

BI D W FISil Gamma Scan Co40 1 130E+01 <UD <llD (UD (O'I) <UD <LLD <llD (O'I) * * *

(*!*)

(rCita(WET))

73

., . . . . . . . . .. .f.... . -. . . .+; TABLE 3 y .

{ , . . . . . . . . . . . . . ,

iRADIOEDCICAL ENVIRONMENTAL MONIToltfMC PaoGRAM3 M 3OYSTERCREEKMUCLEAltGENERATINGSTATIONh Gyi:

.EJANUARL1994 THROUGH DECEMBER;19N $ ' ' '~

'~ F ANNUAL

SUMMARY

?

^ j SAMPLE : FANAINSISg gNUCLIDEA g#OFg aLIEg

._ ,(INDICA 1DRSTATIONS:Si es.,..z IUCHEST AM.NUAL MEANp- -

3 SACECROUND STATIONb iTYPE?' ' [ANAll.i - .;

s $ M.IM.. i..

MEAN ?. MAKi[! - , (N/fUT)s

' $ MIN $, MEAN'[$.MAKE (N/FOT)

... $ MIN 5 "'SMEANY hMAXl:ld.y(N/TOf) p .

BIDWHSil Ganuna Scan Cs-134 1 1.00E+01 <11.D <llD < LID (0/l) <1lD <llD <1lD (0/I) * * *

(+/*)

(pCiigwET))

HIDWFISII Gansna Scan Cs-137 1 1.20E+01 (LLD < LIE <LLD (0/l) <LLD <11D <11D (0/l) * * *

(*i j (pCilgWET))

111DWFISil Ganwna Scan Fe-59 1 3.00E+01 <LLD (11D <l.LD (0/1) < LID < 11D <LLD (G 1)

(+/*)

(pCikgWET))

BIDWFISil Genuna Scan 1-131 1 1.50E*01 <LLD <!1D <1lD (0/1) (LID <LLD <LLD (0/l) * * *

(*r)

(pCi,1gWET))

BIDWFISil Gamma Scan K-40 1 No LtD 4.60E+03 4.60E+03 4.60E+03 (1/l) 4.60E+03 4 60E+03 4.60E+03 (l/l) * * *

(+/*)

(pcilgWET)) Reported StationJ 93 B1DWFISIl Gamma Scan 12-140 I 1.60E+01 <LLD <!JD <11D (0/l) <llD <LLD <LLD (0/I) * * *

(*r)

(pCitgWET))

111DWFISII Gamma Scan hin-54 1 9.00E+00 <llD <11D <llD (0/l) < LID <11D < LID (0/l) * * *

(*r)

(pCilgWET))

BIDWFISil Gamma Scan hb95 1 1.10E+0i <LLD <11D <1lD (0/I) <1lD <11D <11D (0/I) * * *

(*F)

(pCilgWET))

BID %TISil Gamma Scan Ra-226 1 2.00E+02 <llD < 1lD (11D (0/I) < LID <LLD <11D (G't )

(*/*)

(pcitarWETM 74

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

. . . . f:M TABLE 3;;.. %

RADIOIJOCICAL ENVIRONMENTAL MONHORING PROGRAM

+

4 OYSTER CREEK NUCLEAR GENERATING strATION s ^ .

/JANUAR% 19M TIIROUGR DRCEMBER,19M f ' *

?ANNt!ALSUMMARN M' tSAMPLE s s .v... A. NA. . LYSIS w NUCLIDE m #OF iLIE a w: . .:INp6CA1DRSTATIO%

~

rp y 893088E8T AN. NUA. L MEAM ; --- . ._, BACKCROUND S. TAT 1l0845 +

, - ~

. e y; g -- -

- ;- p ,

r - , , ,

litDWRSil Gamma Scan Th-232 1 5.00E+0I < LID (IlD (LIE (0/I) <llD (11D (LLD (0/I) * * *

(*F)

(pCite(WET))

HIDWHSII Ganune Scan Zn-65 3.00E+01 <llD < t1D <LLD- (0/l) <llD <11D (0/I) * *

(pCilg(WET))

1 .IID *

(*r)

DIDWHSII Genune Scan Zr 95 I I.80E+01 < LID < LID <11D (0,1) < TID < llD < LID (0/l) * * *

(*/*)

(pCitg(WET))

WEAKRSil Gemma Scan Ba-140 4 5.50E+01 <LLD (LLD <llD (0/4) (11D <t1D <1lD (0/4) * * *

(*/*)

(pCite(WET))

WEAKHSII Genune Scan Be-7 4 9.00E+0i <11D <UD <LLD (0/4) <llD <11D <UD (0/4) * * *

(*/*)

(pCitg(WET))

WEAKRSil Gamma Scan Co-58 4 I.13E+01 <LLD < lid < LID (0/4) < TID <LLD <llD (0/4) * * *

(*/*)

(pcilg(WET))

WEAKRSil Genune Scan Co.60 4 1.15E+01 (UD < t1D < LID (0/4) <llD < TID < LID (44) * * *

(+/*)

(pcilg(WET))

WEAKRSII Gamma Scan Cs134 4 1.05E+01 (LID <LLD <LLD (0/4) <llD <11D <11D (0/4) * * *

(*/*)

(pr 4 MWET))

WEAKRSil Gamme Scan Ca-137 4 1.67E+01 9.40E+00 9.40E+00 9.40E+00 (1/4) 9.40E+00 9.40E+00 9.40E+00 (t /4) * .

(*/*)

(pCikgWET)) StatimJ 93 75

_ __ _ . . _ .m .. _ _ ~_ . _ . . ..

% . . , ...r. . . . . . . . . _ , . . . _ , .

4 RADIOLOCICAL ENVIRONMENTAL MONITORING PROGRAM i '

^

" s%@YSTER CREEK NOCLEAR CENERATING FIATION f

$JANUARYa19N THROUCH DECEMBER,19N -s

' ': ANNUAL SUMMARVN s- SAMPLE ': ~ 7---AMALY$15 i c NUCLIDE; [ # OFe . gLLD& . ... -.

INDICATOR STATION $ 7 . . . . & HIGHEST ANNUAL MEAN. ; ....s..

. g SACKGROUND STATIONS t TYPE}

' ANAIAj (MIN J MEAM" i MAK f (!VfUI) % MIN.;i ( MEAM$E5 MAK? T(N/ TOT).} LMIN.$-?J)tEAN J 9 MAKf 5(MfroT) ' ' ' ' '

f PFRF.' " ge.sa # ,

< t1D * *

• WEAKFISit Gamma Sas Fe-59 4 2.70E+01 (LLD (I1D <LLD (0/4) (LLD <llD (0/4) (*/*)

j (pCilg(WET))

WE.EFISit Gansna Scan I-131 4 1.95E+01 < LID < LID <llD (0/4) <LLD <LLD < LID (0/4) * * *

(*/*)

(pCikg(WET))

WEAKFISII Gamma Scan K-40 4 No LID 3.10E + 03 3.45 E+03 3 60E+03 (4 4) 3.10E+03 3.45E+03 3 60E+03 (4e4)

• * * (*p)

(pCikg(WET)) Reported .e lion # 93 WEAKFISil Gamma Scan l # 140 4 1.78E+01 <LLD < t1D <LLD (0/4) <llD <LLD <LLD (0/4) * * *

(*/*)

(pCikg(WET),

WEAkFISit Gamma Scan Mn-54 4 1.00E+01 (LLD <llD <t1D (0/4) < LID <I1D <UD (0/4) * * *

(+/*)

(pCilg(WET))

WEAKFISII Gamma Scan Nb-95 4 1.25E+0i <LLD (LLD (LLD (0/4) < LID <11D <LLD (W4) * * *

(*/*)

(rCilg(WET))

WEAKFISil Gamma Scan Ra-226 4 2.38E +02 < LID <UD <llD (O'4) ellD <UD <tLD (0'4) * * *

(*/*)

(pcilg(WET))

WEAKFISil Gar ana Scan 1h-232 4 4.25E+01 <1lD <LLD <LLD (0/4) <LLD < LID <UD (0/4)

(*/*)

(pCilg(WET))

WEAKFISil Gamme Scan 7a45 4 2.95 E + 01 <LLD < t1D <llD (0/4) < LID < t1D <UD (0,4) * * *

(*?)

(pcikg(WET))

WEAKFisil Gamme Scan Zr-95 4 1.90E+01 (UD < t1D <11D (0/4) <LLD <llD (11D (0/4) * * *

(*?)

(rCita(WET))

76

4 i

j DIRECT RADIATION MONITORING Dose rates from external radiation sources were measured at a ,

number of locations in the vicinity of the OCNGS using i

thermoluminescent dosimeters (TLDs). Naturally occurring i

sources, including radiata . of cosmic origin and natural radioactive materials in the air and ground, as well as

) fallout from prior nuclear weapon testing, resulted in a ,

j certain amount of penetrating radiation being recorded at all

monitoring locations. Indicator TLDs were placed systematically with at least one station in each of 16 cardinal compass sectors (in a ring) at the site at a maximum I

distance of 1.5 miles. TLDs were also placed within a five I

mile radius of the OCNGS, in locations where the potential for deposition of radioactivity is known to be high, in areas of public interest, population centers, as well as in background locations which are typically greater than ten miles distant 4 l

from the OCNGS and generally in an upwind direction. '

l Samole Collection and Analysis 1

A state-of-the-art thermoluminescent dosimeter is used.

l Thermoluminescence is a process in which ionizing radiation, upon interacting with the sensitive material of the TLD (the l 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 I l decay appreciably over the course of years. This provides 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 reading system. As j

the TLD is heated, the phosphor releases the stored energy as light. The amount of light given off is directly proportional 3

to the radiation dose the TLb received. The reading process

! ' zeros' the TLD and prepares it for reuse.

4 77 4

,-., .n. -, -

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

During 1994, TLD's were collected every twelve weeks from locations ranging from less than 0.2 miles to 35.1 miles from the OCNGS. Four GPUN Panasonic TLD's were exposed at each of 71 monitoring locations. Two of the 71 monitoring locations were used as quality control (QC) stations, at which four additional GPUN Panasonic TLD's were exposed. In addition, Teledyne Browne Engineering TLD's were exposed at ten selected locations which have -been designated as quality control stations.

GPUN Panasonic TLD's provide sixteen independent detectors at each station. Teledyne Isotopes TLD's provide an additional four measurements.

TLD's were exposed for periods of 12 weeks. The scheduled exposure periods for 1994 were:

Table 4 TLD EXPOSURE PERIODS DURING 1994 Start Date Copection Date 17 JAN 94 11 APR 94 11 APR 94 04 JUL 94 04 JUL 94 26 SEP S4 26 SEP 94 19 DEC 94 All TLD dose rate data presented in this report have been normalized to eliminate differences caused by slightly differing exposure periods. All results are normalized to a standard quarter (91.3 days). TLD dose rate data are presented in Tables J-l and J-2 in Appendix J.

78

_ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ '

Results In 1994, the mean dose rate from indicator stations using i Panasonic TLDs was 10.52 mrem / standard quarter with a range i from 7.94 to 18.57 mrem / standard quarter (Table J-2). The )

mean background dose was 11.20 mrem / standard quarter with doses ranging from 9.37 to 13.79 mrem / standard quarter. The mean background dose exceeded the mean indicator. dose suggesting OCNGS had little if any affect on off-site

{

exposure. These results are consistent with the results of  !

measurements from previous years (Fig. 6). The standard deviation of-dose rates ranged from 0.28 to 4.36 mrem / standard '

quarter. Considering that the standard ' deviation of dose i rates was as high as 4.36 mrem / standard quarter, ' the data [

indicate that there is no relationship between dose rates and  !

! distance from the OCNGS-(Fig. 7)~. '

t l Regarding Teledyne Brown Engineering TLD data, the dose. rate measured at indicator stations averaged -10.1 mrem / standard quarter and ranged from 7.7 to 13.4 mrem / standard quarter (Table ' J-1) . The dose at background TLD stations averaged' 11.4 mrem / standard quarter and ranged from 9.0 to 15.3 -

mrem / standard quarter. The mean dose rate from the background l f stations was higher than the mean dose rate from the indicator l l stations again suggesting that OCNGS operation contributed (

l little if any to off-site exposure.

I A comparison of dose per affected compass sector demonstrates that the highest dose was not measured in the sector most.

likely to be affected by effluents from the OCNGS (Fig. 8).

l l 79

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

MEAN PANASONIC TLD GAMMA DOSE - 1989 T11ROUGII 1994 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DOSE IN MILLIREM PER STANDARD MONTil 10 8

t 6 -*-INDICATOR MEAN  ;

-o- BACKGROUND MEAN 3 g o i 4

^

a i%

2 .

i i

i 0 i

E I

=

Y-

= [

r a E

e D [

I e

dv I ke {.

E D e

v $

v v 4 E g

=

r "5

" I r

3 C

2

@ N N N 8 g 8 8 2 2 ~

2 2 h 3 8 8 8 b h & 2 h 2 2 h DATE

I I

l MEAN PANASONIC TLD GAMMA DOSE FOR 1994 IRASED ON DISTANCE FROM OCNGS l

OYSTER CREEK RADIGI,0GICAL ENVIRONMENTAL MONITORING PROGRAM DOSE IN MILLIREM PER STANDARD QUARTER 20 i

18 l

l 14 5 0 TO 2 MILES y g 02 TO 5 MILES E OVER 5 MILES l

l 10 8

4 2

0 " '-

Apr-94 Jul-94 Sep-94 Dec-94 MONTH OF COLLECTION

MEAN TELEDYNE AND PANASONIC TLD GAMMA DOSE FOR 1994 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MEAN DOSE IN AFFECTED COMPASS SECTOR DOSE IN MILLIREM PER STANDARD QUARTER 20 l NOTE: Teledy ne TLD's are not located in all cosepass sectors l l

E PANASONIC TLD 15 O TELEDYNE TLD l

e r;

i

~

\

l N NNE NE ENE E ESE SE SSE S SSW . SW WSW W WNW NW NNW ,

i AFFECTED COMPASS SECTOR ,

4

The data indicate that the south-southwest sector had the highest dose during 1994. Based upon on-site meteorology for 1994 however, the highest air dispersion (X/Q) factors were in the east-southeast sector; this is where the highest dose due to OCNGS effluents should occur. The south-southwest sector is approximately 90 degrees opposite the east-southeast sector, which is further evidence that the OCNGS had little if any effect on off-site exposure.

These results also indicate good correlation between the dose per sector as recorded by the two independent TLD networks (Figure 8).

l t

l l

l l i 83 I

1 I

l A_TMOSPHERIC MONITORING A potential exposure pathway to man is the inhalation and 1

i ingestion of airborne radioactive materials. Air was sampled by a network of thirteen continuously operating air samplers and then analyzed for radioactivity content. Airborne l

I radioactivity also was monitored by collecting and analyzing precipitation samples.

Indicator air sampling and precipitation stations are located in prevailing downwind directions, local population areas, and areas of public and special interest. All indicator stations l are located within 6.5 miles of the OCNGS. Background air sampling and precipitation stations are located greater than 17 miles from the site in Lakewood, Allenhurst, Cookstown, and Hammonton, NJ.

l Samole Collection and Analysis Mechanical air samplers are used to continuously draw a recorded volume of air through a glass fiber (particulate) filter and then through a charcoal cartridge. A dry gas meter, which is temperature compensated, is used inside the air sampler to record air volumes. Internal vacuums are also measured in order to pressure correct the indicated volume.

All air samplers are maintained and calibrated by GPU Nuclear instrument and control technicians.

The particulate filters were collected weekly and analyzed for gross beta radioactivity. The filters were then combined monthly by individual station locations and analyzed for gamma-emitting radionuclides.

84

i Charcoal cartridges, used to collect gaseous radiciodines, contain activated charcoal. Charcoal cartridges were ,

t collected weekly and analyzed for iodine-131 (I-131) activity. l Precipitation samples were collected monthly using .an eight-inch diameter funnel that drains into a collection container. A quarterly precipitation composite per station was then prepared. Six of the thirteen composite samples were analyzed for tritium and gamma-emitting radionuclides. The ;

remaining seven samples were stored pending the outcome of the six analyzed samples.

Results i

The results of the atmospheric monitoring during 1994 demonstrated that, as in previous years, the radioactive i

airborne effluents associated with the OCNGS did not have any I measurable effects on the environment.

l 1

During 1994, 673 gross beta analyses were performed on air i particulate filters (Table 3). Three analysis results were not included because two filters were found misaligned and a >

sampler malfunctioned once (Appendix A-3). The background mean gross beta activity (0.0162 pCi/m') was slightly higher than the indicator mean (0.0155 pCi/m') and all gross beta analysis results were within two standard deviations of the i historical mean.

I j comparison of the 1994 weekly mean air particulate gross beta concentrations for indicator and background stations ' shows

. that indicator and background concentrations were essentially identical (Figure 9). These results are consistent with the results of gross beta analyses of air. samples from previous years (Figure 10). The air particulate gross beta analysis  !

results clearly show that effluent containing gross beta  !

radioactivity from OCNGS operation did not have any measurable l -impact on the local environment.

! 85 f

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Gamma isotopic analyses were performed on 179 air particulate

filter composites (Table 3). Three additional composite j results were not included in Table 3 due to sampling anomalies 4

(Table A-3) The only radionuclide identified was naturally J

occurring beryllium-7, which was seen in similar concentrations at both indicator- and background stations.

1 Because it is a naturally occurring nuclide, the observed

-; beryllium-7 activity cannot be attributed to effluents from the OCNGS.

i

] Air charcoal cartridges (675) were analyzed for iodine-131

(I-131) and no radiciodine was detected in any of the samples

(Table 3). The results of one sample were not used due to a sampler malfunction (Appendix A-3).

l With regard to precipitation sampling, 22 gamma isotopic and 1

22 tritium analyses were performed in 1994 (Table 3). No tritium activity was detected in any precipitation sample.

Two naturally occurring radionuclides, bery111um-7, and l potassium-40 were detected. Low levels of each of these i radionuclides have been detected at both indicator and S

background stations in the past. Neither is associated with OCNGS operation.

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AOUATIC MONITORING I i i Brackish water from Barnegat Bay is drawn in through the south j- branch of Forked River, pumped into the OCNGS cooling systems, l and then discharged to Barnegat Bay via Oyster Creek. Fish, j

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 l

l consumption by man.

On occasion, a radioactive liquid release may be discharged in accordance with the limits established in the OCNGS Offsite Dose Calculation Manual (ODCM) Specifications, Technical i specifications, and 10CFR20. Highly purified water, containing traces of radioactivity, may be discharged into ' l j Oyster Creek which has a minimum flow rate of slightly under .

) one-half million gallons per minute. There were no

) radioactive liquid releases from the OCNGS during 1994 and there have been no routine radioactive liquid releases since 1

1989. Samples of surface water, sediment, fish, blue crab, t and hard clams were routinely collected from the OCNGS intake ,

{ and discharge canals, as well as Barnegat Bay, Manahawkin Bay, i

and Great Bay in order to monitor any environmental' impact l

2 that may be associated with past releases.

i Samole Collection and Analysig

( ,

J Surface water, sediment, and clam samples were collected every

)

four weeks. Grab samples of surface water and sediment were i collected from six indicator stations and two background

stations. Grab samples of clams were collected from three l indicator and two background stations. Three indicator stations for surface water and sediment are located.in the j OCNGS discharge canal - Oyster Creek. No clams are available  !

'_ for collection at these stations. Three additional indicator stations are located in Barnegat Bay in close proximity to the

, mouth of Oyster Creek. One background station is located in '

i l i 89 i l'

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l Manahawkin Bay, approximately 11 miles south of the OCNGS. A l

second background station is located approximately 22 miles south of the OCNGS in Great Bay.

Blue crab and fish samples were collected every four weeks l

(when available) from two indicator stations and one background station. Both indicator stations are located in the OCNGS discharge canal and the background station is located in Great Bay. Crab pots were used to catch blue crab.

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

All samples were analyzed for gamma-emitting nuclides; water samples were also subjected to tritium analyses.

l Results l Operation of the OCNGS had no detectable effect upon the local surface water which was sampled 102 times at eight different locations during 1994. Two gamma-emitting nuclides, potassium-40 (K-40), and radium-226 (Ra-226), were detected in 97 and 4 of the samples, respectively (Table 3). Tritium (H-

3) activity was detected in 2 samples (Table 3) at background stations only. Each of these radionuclides is naturally occurring and commonly found in salt water at or above the observed concentrations. No other radionuclides were detected in surface water samples.

Six gamma-emitting nuclides were detected in the 32 sediment composite samples collected during 1994 (Table 3). Four of these radionuclides, beryllium-7 (Be-7 ), potassium-40, radium-226, and thorium-232 (Th-232), are naturally occurring and l were detected at both background and indicator stations.

Cesium-137 (Cs-137), which is a fission product, was also detected in both background and indicator samples. As fallout, Cs-137 was widely distributed and detected in l

considerable abundance following atmospheric weapons tests and 90

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1 J

the Chernobyl accident. It was last released ' in trace quantities from the OCNGS in liquid effluents in 1991. The presence of this radionuclide in both background and indicator ,

{ samples ' suggests that the cesium-137 activity detected in Barnegat Bay sediments originated from the former sources and not OCNGS operation.

i j Cobalt-60 was detected in twenty-nine percent of the aquatic

sediment indicator station samples and none of the background l station samples (Table 3). The presence of this radionuclide j in Barnegat Bay' sediments is of interest because it can be 4

j attributed to past OCNGS liquid releases. As documented in >

{ previous reports, OCNGS related cobalt-60 activity has been  ;

) found in sediment and clams from'Barnegat Bay since at least l 3

j the mid-1970's. The volume of liquid effluents has been

}. significantly reduced since that time and this decrease in the +

j rate of input of cobalt-60 to the environment, combined with  !

i radioactive decay of the existing inventory, has resulted in a gradual decline in the cobalt-60 concentration in sediment f~

and clams (Figs. 11 and 12). The last detectable

[

concentration of this radionuclide was found in clams during the third quarter of 1987 (Fig. 12).

l Sixty-three clam samples were collected from five different

! locations during 1994. Gamma isotopic analyses indicated that j the only gamma-emitting nuclides present were potassium-40 and j j

e radium-226 which are naturally occurring and commonly found in

salt water (Table 3).

l Eighteen blue crab samples were collected from three locations j during 1994. A gamma isotopic analysis was performed on each sample of crab meat and naturally occurring potassium-40 and

radium-226 were the only radionuclides identified (Table 3).

{ The close association of this species with Barnegat Bay sediments could make it susceptible to cobalt-60 uptake.

However, no detectable Co-60 activity has been observed in l-

.L 91 I

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i blue crab samples since routine collection began in 1985.

l Forty-one fish samples, yielding eight species, were collected a

from 3 sampling locations during 1994. The species and number of samples collected are listed below:

i TABLE 5 SPECIES OF FISH CAUGHT AS PART OF THE OCNGS REMP IN 1994 Fish Number of Samples bluefish 12

. striped bass 11 summer flounder 6

weakfish 4

tautog _

3 i sea bass 2

winter flounder 2 d

blowfish 1 j Naturally occurring potassium-40 was detected in each of the 41 fish samples (Table 3). Detectable quantities of 4

l I

cesium-137 were observed in 6 of 11 bluefish samples, 4 of 11 l striped bass samples, and one of four weakfish samples collected from indicator station 93 (Table 3). As discussed above, Cs-137 is a ubiquitous fission fallout product and has been detected in considerable abundance following atmospheric 5

weapons tests and the Chernobyl nuclear accident. It was last discharged in small quantities from the OCNGS during 1991.

The maximum level of Cs-137 activity (20 pCi/kg (wet)) was i

only 13 percent of the lower limit of detection and 1.0 l percent of the reporting level specified by the OCNGS

Technical Specifications and Offsite Dose Calculation Manual Specifications. Similar low levels of this radionuclide are j found in fish throughout the world as a result of fallout (Ref. 16). l l

94 I

i

! TERRESTRIAL MONITORING 3

i Radionuclides released to the atmosphere may be deposited on soil and vegetation and may be incorporated into milk, vegetables, and/or other food products. To assess the impact j of dose to humans from the ingestion pathway, food product samples such as green leafy vegetables were collected and

, analyzed during 1994. Surface soil samples were also j collected and analyzed for the purpose of monitoring the i potential buildup of atmospherically deposited radionuclides.

4

] The contribution of radionuclides from the OCNGS operation was

assessed by comparing the results of samples collected ~in l prevalent downwind locations, primarily to the southeast of the site, with background samples collected from distant and j generally upwind directions.

1 i

j A dairy census was conducted to-determine the locations of j commercial dairy operations and milk producing animals in each l

} of the 16 meteorological sectors out to a distance of five miles from the OCNGS. The_ census showed that there were no

{ commercial dairy operations and no dairy animals producing j milk for human consumption within a 5 mile radius of the plant

! (Appendix F).

j The Environmental Affairs Staff at the OCNGS established and i

a maintained two gardens near the site boundary. in the two j sectors with the highest potential for radioactive deposition in lieu of performing an annual garden census. Both of these indicator gardens are greater than 50 square meters _in size j and produce green leafy vegetables. A commercial farm located

approximately 24 miles northwest of the site was used as a background station.

i a

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I Samole Collection and Analysis Broadleaf vegetables, specifically cabbage and collards, were collected on a monthly basis beginning in June and ending in December 1994. A gamma isotopic analysis was performed on each sample.

Surface soil samples from the gardens were collected during July and October. Each soil sample was subjected to a gamma isotopic analysis.

Results The results of the terrestrial monitoring during 1994 demonstrated that the radioactive effluents associated with the OCNGS did not have any measurable effects on vegetation or soil.

A gamma isotopic analysis was performed on twenty collard samples and nine cabbage samples (Table 3). Naturally occurring potassium-40 (K-40) was detected in 100 percent of the samples collected from both indicator and background stations. Another naturally occurring nuclide, beryllium-7 (Be-7), was identified in 7 of 20 cabbage and collard samples collected at indicator stations and in 2 of 9 cabbage and collard samples collected at background stations. Thorium-232 (Th-232), which is also naturally occurring, was detected in 1 of 14 indicator samples. No other radionuclides were l detected in vegetable samples. None of the radionuclides j detected are associated with OCNGS operation. l l

96

Cesium-137 activity was detected in all indicator and background soil samples collected from the gardens in which vegetables were grown (Table 3). The mean concentration of Cs-137 at the background station was 126 pCi/kg (dry) while the mean concentration found at the indicator stations was 132 pCi/kg (dry). The occurrence of similar concentrations of Cs-137 in all samples from both indicator and background stations indicates that the minute amounts of this radionuclide detected in the soil were a result of previous weapons testing and the Chernobyl nuclear accident and not the result of deposition of effluents from the OCNGS. In addition to cesium-137, the naturally occurring radionuclides beryllium-7, potassium-40, radium-226, and thorium-232 were detected in soil samples (Table 3).

l 97

GROUNDWATER MONITORING The Oyster Creek Nuclear Generating Station is located on the Atlantic Coastal Plain Physiographic Province. This Province extends southeastward from the Fall Zone, a topographic break that marks the boundary between the Atlantic Coastal Plain and the more rugged topography of the Piedmont Province. The Fall Zone is also where the crystalline and sedimentary rocks of the Piedmont and the unconsolidated coastal plain sediments meet.

At least five distinct bodies of fresh groundwater or aquifers exist in the vicinity of the OCNGS. From the surface downward, they are:

1. Unconfined, Recent and Upper Cape May Formation

2. Confined, Lower Cape May Formation

3. Confined, Cohansey Sand

4. Confined, Upper Zone in the Kirkwood Formation

5. Confined, Lower Zone in the Kirkwood Formation The unconfined Recent and Cape May Formations are replenished directly by local precipitation. The recharge to the confined aquifers occurs primarily from direct rainfall penetration on the outcrop areas, which are generally to the west of the sito at higher elevations.

Samole collection and Analysis As part of the routine REMP, five offsite groundwater wells were sampled on a monthly basis. Grab samples were obtained from four local residences and one OCNGS well. The depths of the residential wells are unknown but most local domestic wells draw upon the Cohansey aquifer; the OONGS well is approximately 380 feet deep, in the Kirkwood formation. Each sample was subjected to a tritium and gamma isotopic analysis.

98

In addition, a well network was installed around the OCNGS in 1983 to serve as an early detection and monitoring system for spills, separate from routine REMP sampling. In March and October of 1994, fifteen of these wells located in the Cape May, Cohansey and Kirkwood aquifers, were sampled using grab sample methodology. The samples were analyzed for tritium and gamma emitting nuclides.

Results The results of the groundwater monitoring during 1994 demonstrated that, as in previous years, the radioactive effluents associated with the OCNGS did not have any measurable effects on offsite groundwater quality.

Fifty-four routine REMP well water samples were collected during 1994 (Table 3). Potassium-40 was detected in only one indicator sample and one background sample. Thorium-232 was also seen only once in 41 indicator samples and radium-226 was seen in one out of 13 background samples. None of these naturally occurring radionuclides can be attributed to effluents from the OCNGS. Another naturally occurring radionuclide, tritium, was detected in two of 41 indicator samples and t-hree of thirteen background samples. The mean concentration (170 pCi/ liter) detected at the indicator stations was lower than that detected at the background i station (200 pCi/ liter). To put these results into perspective, the EPA drinking water limit is 20,000 pCi/ liter. ,

Therefore, 170 and 200 pCi/ liter represent only 0.85 and 1.00 I percent of the limit.

The results of toe analyses of 29 samples from the onsite spill monitoring well network were similar to those from the offsite wells except for the results of a sample collected 1 from station OC-WW-12 in March 1994 (Appendix H). The naturally occurring radionuclides tritium, potassium-40, l 99 l

l i

and thorium-232 were detected in five of the 29 samples.

These three nuclides have been detected in the past in similar concentrations at both indicator and background stations and are not attributed to the OCNGS effluents.

Cobalt-60 is an OCNGS activation product that was detected in a minute concentration at OC-WW-12 in March 1994 (Table H-1).

This monitoring well is a shallow well (17 feet deep) of non-potable water and is located within the OCNGS protected area, i

This well is located approximately 60 feet west of the New

! Radwaste building and is just outside the Radiologically Controlled Area (RCA). perimeter. The Co-60 activity in this sample was traced to fine sediments suspended in the water which entered the well when the casing was accidently broken.

The casing was repaired upon discovery of the breakage. The

! concentration of Co-60 activity for this sample was 2.3 pCi/ liter (Table H-1) . This result is 15 percent of the lower limit of detection (15 pCi/ liter) and less than one percent of the reporting level (300 pCi/ liter)- specified for water j samples in the OCNGS Technical Specifications and Offsite Dose Calculation Manual Specifications. When a gamma isotopic reanalysis of this well water sample was performed after i filtering out the sediments, the results for all radionuclides were less than detectable activity. This well was sampled again in October 1994 and no cobalt-60 activity was detected.

)

100

l  !

RADIOLOGICAL IMPACT OF OCNGS OPERATIONS l An assessment of potential radiological impact indicated that radiation doses to the public from 1994 operations at OCNGS were well below all applicable regulatory limits and were significantly less than doses received from common sources of radiation. There was no dose attritsuted to liquid effluents because no liquid releases were made from the OCNGS in 1994.

The 1994 whole body dose, potentially received- by a j hypothetical maximum exposed individual, from OCNGS airborne effluents, was conservatively' calculated to be about 4.4E-3 millirem total or only 8.8E-4 percent of the OCNGS Offsite Dose Calculation Manual (ODCM) Specification limit. The 1994 whole body dose to the surrounding population from OCNGS airborne ef fluents was calculated to be 3.5E-1 person-rem.

This is approximately 2.83 million times lower than the doses to the total population within a 50-mile radius of the OCNGS

! resulting from natural background sources. '

Determination of Radiation Doses to the Public l

To the extent possible, doses to the public are based on direct measurement of dose rates from extetaal sources and measurements of radionuclide concentrations in the environment which may contribute to . an internal dose of radiation.

i Thermoluminescent dosimeters (TLDs) positioned in the j environment around the OCNGS provide measurements to determine external radiation doses to humans. Samples of air, water, food products, etc. are used to determine internal doses.

During normal plant operations the quantities of radionuclide releases are typically too small to be -measured once distributed in the offsite environment. As a result, the potential offsite doses are calculated using a computerized model that predicts concentrations of radioactive materials in l

l 101

. _ . . .-.r , - . _ .

1 i

i the environment and subsequent radiation doses on the basis of radionuclides released to the environment. GPUN calculates dose using two advanced computer programs called SEEDS I (Simplified Effluent Environmental Dosimetry System) and

EFFECTS (Radioactive Effluent Filing, Evaluation, and l Comparison with Technical Specifications) sof tware whose basis l is the site's Offsite Dose Calculation Manual (ODCM). These j models incorporate the guidelines and methodologies set'forth j by the USNRC in Regulatory Guide 1.109, (Ref. 27) . Due to the i

conservative assumptions that are used in the model, the calculated doses are considerably higher than the actual doses i to people.

l j The type and amount of radioactivity released from the OCNGS j is calculated using measurements from effluent radiation monitoring instruments and effluent sample analysis. Once l released, the dispersion of radionuclides in the environment is readily determined by computer modelling. Airborne j releases are diluted and carried away from the site by j: atmospheric diffusion which continuously acts to disperse

radioactivity. Variables which affect atmospheric dispersion 4 ,

{ include wind speed and direction, atmospheric stability, and I terrain. A meteorological monitoring station northwest of the i reactor site is linked to a computer terminal which permanently records all necessary meteorological data.

Computer models are also used to predict the downstream i

!, dilution and travel times for liquid releases into the j Barnegat Bay estuary and Atlantic Ocean. l t

! The pathways to human exposure also are included in the model.

.i These pathways are depicted in Figure 13. The exposure-j pathways considered for the discharge of the station's liquid effluent are fish and shellfish consumption and shoreline exposure. The exposure pathways considered for airborne effluents include plume exposure, inhalation, vegetable

! consumption (during growing season) and land deposition.

SEEDS and EFFECTS employ numerous data files which describe

) 102 4

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• o- - _ - _ _ . . _ _ _ _ . . _ . _ _ _ _ - _ _ _ . . - __.- __ __ _

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R 1 FIGURE 13 ' t EXPOSURE PATHWAYS FOR RADIONUCLIDES POTENTIALLY RELEASED FROM THE OCNGS

l-i Gaseous Effluents i,  !

! Oyster Creek Station _

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the area around the OCNGS in terms of demography and foodstuf fs production. Data files include such information as the distance from the plant stack to the site boundary in each compass sector (sixteen in all), the population groupings, l

gardens of more than 500 square feet, meat animals, and crop I yields.

When determining the dose to humans, it is necessary to consider all pathways and all exposed tissues (summing the dose from each) to provide the total dose for each organ as well as the whole body from a given radionuclide in the environment. Dose calculations involve determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides taken into the body, the metabolism of the radionuclide in the body must be known along with the physical characterictics of the nuclide such as energies, types of radiations emitted and half-life. SEEDS and EFFECTS also contain dose conversion factors for over 75 radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body, thyroid, liver, skin, kidney, lung, bone and gastro-intestinal tract).

Doses are calculated for what is termed the " maximum hypothetical individual." This individual is assumed to be  !

affected by the combined maximum environmental concentrations wherever they occur. For liquid releases, the maximum hypothetical individual would be one who stands at the U.S.

Route 9-discharge canal shoreline for 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year while eating 43 pounds of fish and shellfish. For airborne releases, the maximum 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 522 meters to the southeast based on historical meteorological / air dispersion analysis (Ref. 3). The usage factors and other assumptions used in the model result in a conservative overestimation 104

of. dose. Doses are-calculated for the population within 50 miles of the OCNGS for airborne effluents and the entire population using the Barnegat Bay estuary and' Atlantic Ocean for liquid effluents. Appendix G contains-a'more detailed discussion of the~ dose calculation methodology.

Results of Dose Calculations t'

i f Doses from natural background radiation provide a baseline for j assessing the potential public health significance of j radioactive effluents. The average person in the United j States receives about 300 millirem (mR) per year from natural

{ background radiation sources. Natural' background radiation from cosmic, terrestrial and natural .' radionuclides in the *

]

j human body (not including radon), averages about 100 mR/yr.

j- The natural background radiation from cosmic and terrestrial j sources varies with geographic location, ranging from a low of j about 65.mR/yr on the Atlantic and Gulf coastal plains to as much as 350 mR/yr on the Colorado plateau (Ref. 5). The

} National Council on Radiation Protection and Measurements (NCRP) now estimates that the average individual in the United j States receives an annual dose of about 2,400 millirems to the l lung from natural radon gas. This lung dose is considered to-j be equivalent to a whole body dose of 200 millirems (Ref. 4).

i Effluent releases from the OCNGS and other nuclear power {

l plants contribute only a very small percentage to the natural

] radioactivity which has always been present in the air, water, j soil and even in our bodies. In general, the annual j population doses from natural background radiation (excluding l radon) are 1,000 to 1,000,000 times larger than the-doses to l the same population resulting from nuclear power plant  !

operations (Ref. 17).

l Results of the dose calculations are summarized in Tables 6

{ and 7. Table 6 compares the calculated maximum dose to an 4

l 3

105 I

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4 individual of the public with the OCNGS ODCM Specification,  !

4 Technical Specification, 40CFR190, and 10CFR50 Appendix I dose j limits. Table 7 presents the maximum total body radiation l

doses to the population within 50 miles of the plant from

airborne releases, and to the entire population using Barnegat i Bay and the Atlantic Ocean, for liquid releases.

I l

These conservative calculations of the doses to members of the l public from the OCNGS ranged from 0.00011 percent to a maximum .

i of only 0.58 percent of time applicable regulatory limits.

They are also considerably lower than the doses from natural 1

background and fallout from prior nuclear weapon tests.

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

e 3

' TABLE 6 CALCULATED MAXIMUM HYPOTHETICAL DOSES TO AN INDIVIDUAL FROM LIOUID AND AIRBORNE EFFLUENT RELEASES FROM THE OCNGS FOR 1994 REGULATDRY LIMfTS PERCENT OF EFFLUENT CALCULATED DOSE . REGULATORY RELEASED mRemlVEAR SOURCE mRent' YEAR LIMIT -

LIQUID 3 TOTAL BODY DDCM SPEC 4.6.1.1.4 " "

LIQUID ' 10. ANY ORGAN " "

ODCM SPEC 4.6.1.1.4 AIR 8ORNE 500 - TOTAL BODY 00CM SPEC 4.6.1.1.5 4.4E.3 8.8E 4 til0BLE GAS)

AIRBORNE 3000 - SKIN ODCM SPEC 4.8.1.1.5 3.3E.3 1.1E-4 (NOBLE GAS)

AIRBORNE 15 ANY DRGAN ODCM SPEC 4.6.1.1.7 3.7E 2 2.5E 1 (l005d! AND PARTICULATE)

TOTAL. LIQUID 25 TOTAL BODY ODCM SPEC 4.8.1.1.8' 4.4E.3" 1.0E.2" AIO AIRBORNE TOTAL. LIQUID 75. THYR 010 00CM SPEC 4.6.1.1.8' 3.7E 2" 4.9E.2" AND AIRBORNE TOTAL.LlQUID 25 ANY OTHER ODCM SPEC 4.6.1.1.8' 3.3E 3" ~ 1.3E.2" AND AIRBORNE ORGAN 40 CFR 100 .

There were no liquid effluents raisesed dwing 1994.

107

e h

TABLE 7 3  !

CALCULATED MAXIMUM TOTAL RADIATION DOSES TO THE l POPULATION FROM LIOUID AND AIRBORNE EFFLUENT RELEASES I

FROM THE OCNGS FOR 1994 l i

'l 3

Calculated Population Total Body Dose i

Person-Rem / Year j OCNGS

• 1 j From Radionuclides in Liquid ReleaFes *

(Barnegat Bay and Atlantic Ocean Users) i a

From Radionuclides in Airborne Releases 3.5E-1 (Within 50-Mile Radius of OCNGS) l  !

DOSE DUE TO NATURAL BACKGROUND RADIATION

) Approximately 990,000 Person-Rem Per Year 1

I

• There were no liquid effluents released during 1994.

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

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l REFERENCES I

! i (1) Jersey Central Power and Light Company. " Oyster Creek j Nuclear Generating Station Operating- License and Technical Specifications," Appandix - A, DPR-16, April i 1969.

}

j i (2) GPU Nuclear Corporation. " Oyster Creek Offsite ' Dose I Calculation Manual," October 1983.

(3) GPU Nuclear Corporation. " Final Safety Analysis Report, j Oyster Creek Nuclear Generating Station," August 1993.

l l

j (4) National Council on Radiation Protection and {

j Measurements, Report No. 93, " Ionizing Radiation Exposure l j of the Population of the United States," 1987. "

4 s

1 w. '

j (5) CRC Handbook, "Radioecology: Nuclear Energy and the ~

{ Environment," F. Ward Whicker and Vincent Schultz, Volume i I, 1982.

}j . (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 j Exposure," (Published as National Bureau of Standards 2

Handbook 69, Issued June 1959, superseding Handbook 52). ,

I l j (7) International Commission on Radiological Protection, j Publication 2, " Report of Committee II on Permissible a

Dose for Internal Radiation (1959)," with 1962 Supplement Issued in ICRP Publication 6; Publication 9, i i " Recommendations on Radiation Exposure," (1965); ICRP  ;

j Publication 7 (1965), amplifying specific recommendations  !

j of Publication 9 concerning environmental monitoring; and -

j ICRP Publication 26 (1977).

l  !

109 3

r

l i-(8) Federal Radiation Council Report No. 1, " Background l Material for the Development of Radiation Protection

Standards," May 13, 1960.

(9) National Council on Radiation Protection and 3

i Measurements, Report No. 39, " Basic Radiation Protection )

Criteria," January 1971. I i

) (10) National Council on Radiation Protection and  !

l Measurements, Report No. 62, " Tritium in the Environment," March 1979. i I  :

{

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

i b

(12) United States Nuclear Regulatory Commission. Regulatory j Guide 4.1, " Programs for Monitoring Radioactivity in The

Environs of Nuclear Power Plants," Revision 1, April l

~

1975. i i

1 (13) United States Nuclear Regulatory Commission Branch

,i Technical Position, "An . Acceptable- Radiological l j Environmental Monitoring Program," Revision 1,-November j

} 1979. '

4 i

_ (14) American National Standards Institute, Inc., t

) " Performance, Testing, and Procedural Specifications for -

l Thermoluminescence Dosimetry," A'.4SI N545-1975.  ;

1 (15) United States Nuclear Regulatory Commission. Regulatory j Guide 4.13, " Performance, Testing and Procedural Specifications for . Thermoluminescence Dosimetry T j

Environmental Applications," Revision 1, July 1977. '

i l

I  :

I 110 I i'!-

e l

(16) United States Nuclear Regulatory Commission. Regulatory i Guide 4.15, " Quality Assurance for Radiological )

Monitoring Programs (Normal Operations) -

Effluent Streams and the Environment," Revision 1, February 1979.

(17) NUREG/CR-4068 " Summary of F- corical Experience with Releases of Radioactive MattOls from Commercial Nuclear i Power Plants'in the United ikat=3",.1985.

1 i

r

(18) GPU Nuclear Corporatior. "1986 Radiological

Environmental Monitoring VD yort #or Oyster Creek Nuclear ,

Generating Station." May 198'. I i (19) GPU Nuclear Corporation. "1987 Radiological  !

Environmental Monitoring Report Cor Cyster Creek Nuclear I

Generating Station." May 1988.

1 (20) GPU Nuclear Corporation. "1988 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1989.

j (21) GPU Nuclear Corporation. "1989 Radiological I

Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1990.

(22) GPU Nuclear Corporation. "1990 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1991. l

)

(23) GPU Nuclear Corporation. "1991 Radi? logical l

Environmental Monitoring Report for Oyster Creek Nuclear l Generating Station." May 1992.

111 l

h (24) GPU Nuclear. Corporation. "1992 Radiological Environmental Monitoring Report for Oyster Creek Nuclear .,

Generating Station" May 1993.

, (25) GPU Nuclear Corporation. "1993 Radiological Environmental Monitoring Report for Oyster Creek Nuclear ,

Generating Station" May l'i94.

(26) GPU Nuclear Corporation. "1994 Annual Radioactive Effluent Release Report for Oyster Creek Nuclear.  ;

Generating Station" March 1995. l (27) United States Nuclear Regulatory Commission. Regulatory l Guide 1.109, " Calculation of Annual Doses to Man from- l Routine Releases of Reactor Effluents for the purpose of [

Evaluating Compliance with 10 CFR Part 50, Appendix I," r Revision 1, October 1977.

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1 112 l_______1____________ . - _ _ _ _ .

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j APPENDIX A

. 1994 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling j and Analysis Exceptions s

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROca_aN CAMPLING LOCATIONS Sample Station Medium Code Distance Azimuth Description APT, AIO, RWA, 1 0.2 miles 228' SW of site, at Oyster Creek Fire TLD Pond, Forked River, NJ WWA 1 0.1 227 On site well at OCNGS Forked River, NJ

-APT, AIO, RNA, 3 6.1 94 E of site, near Coast Guard Station TLD Island Beach State Park APT, AIO RNA, 4 4.7 215 SW of site, where Route 554 and the TLD Garden State Parkway meet, Barnegat, NJ APT, AIO, RNA, 5 5.2 355 N of site, Garden State Parkway

[

s TLD Service Area, Forked River, NJ

.TLD 6 2.2 14 NME of site, Lane Place,-behind St.

Pius Church, Forked River, NJ TLD 7 1.8 111 ESE of site, Bay Parkway, Sands Point Narbor, Waretown, 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, RWA, A 31.1 25 NNE of site, JCP&L office parking TLD lot, next to substation, Allenhurst, NJ APT, AIO, RWA, C 35.1 309 NW of site,'JCP&L office rear TLD parking lot, Cookstown, NJ

_ _ _ _ _ _ _ - _ _ . - - - _ - _ - - _ _ = - _ _ _ - - - _ - _ _ - - - _ _ _ . _ - _ - _ _ _ _ - - _ . _ . . .-. , - _ - . . - . . . _ _ - -- _ -_-_ _-__-___-

. _ . . m._. . . . _- . . _ _ . . . _ . . . _ . _ . . - . _ . _ - - _ _ . . _ . . . . .

. .m_... . . . _ . . . . .- - -.

_ ..__....m___.___-_._.m ...._m _. . ~ . . . . . - - . . _ . . . . _ _ _ _ _ _ . _ . .

i TABLE A-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS 1

l Sample Station .

Medium Code Distance Azimuth Descrintion  !

APT, AIO, RWA, H 35 miles 248' WSW of site, Atlantic Electric office TLD storage yard, Hammonton, NJ ,

TLD 10 10.2 21 NNE of site, Route 37 and Gilford Avenue, ,

Toms River, NJ '

TLD 11 8.3 156 SSE of site, 80th and Anchor Streets at Water Tower, Harvey Cedars, NJ TLD 12 9.4 192 SSW of site, Atlantic Electric substation access road, Cedar Run, NJ H TLD 13 8.3 345 '

NNW of site, Dover Road, next to last pole y traveling west, South Toms River, NJ APT, AIO, RNA, 14 18 1 N of site, Larrabee Substation on TLD Randolph Road, Lakewood, NJ TLD 15 19 309 NW of site, Route 539, last pole on south side across from Bomarc Site, New Egypt, NJ TLD 16 18 271 W of site, two poles south of the intersection of Routes 563 and 72. ,

TLD 17 19 214 SW of site, Route 563, 2 miles north at high voltage line, New Gretna, NJ WWA 18 1.7 -42 NE of site, at marina, Lacey Road, Forked River, NJ ,

. . . _ _ . .__ _ - . . . _ . . _ . . _ _ . _ _ _ _ _ . _ . _ . _ _ - _ . . . . _ . . _ _ _ _ _ _ . _ _ . . _ _ _ . . . . _ _ .__ . . . . _ _ . m . ..m..

TABLE A-1 (continued) ,

NITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance Azimuth Descriotion WWA 19 1.6 miles 73* ENE of site, 1015 Inland Road, Forked River Beach, Forked River, NJ APT, AIO, RWA, 20 0.7 93 E of sita,_on Finninger Farm on south side TLD of access road, Pole BT17, Forked River, NJ WWA 21 1.0 115 ESE of site, at 215 Dock Avenue, Waretown, NJ TLD, WWA 22 1.6 146 SE of site, at 27 Long John Silver Way, Skipper's Cove, Pole IBT152 ON, Waretown, NJ H

" SWA, CLAM, AQS 23 4.0 63 ENE of site, Barnegat Bay off Stouts Creek a 400 yards SE of FL"1" SWA, CLAN, AQS 24 2.0 104 ESE of site, Barnegat Bay, 250 yards SE of FL"3" SWA, CLAM, AQS 25 1.8 127 SE of site, Barnegat Bay of f Holiday Harbor, 200 yards SE of lagoon mouth SWA, CLAM, AQS 31 10.5 183 S of site, Manahawkin Bay 25 yards SE of 4

C "23" and N "24" SWA, AQS 32 1.9 98 E of site, mouth of Oyster Creek discharge canal SWA, AQS, 33 0.7 104 ESE of site, 1200 yards east of Route 9 FISH, CRAB Bridge in Oyster Creek Discharge Canal VEG, SOIL 35 0.4 110 ESE of site, east of Route 9 and North of the

Discharge Canal, Forked River, NJ l

. _ _ . . .._..__m ... ._....._.__._....____.__.._____.m ...._...._._._.~._-.m_. _ . . . . _ . . _ _ . _ _ .

TABLE A-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LN*ATIONS I

t Sample Station

• Medium Code Distance Azimuth Description '

VEG, SOIL 36 24 miles 315' NW of site, at "U-Pick" Farm, New Egypt, NJ TLD 51 0.4 358 N of site, on the access road to Forked I

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 the JCP&L Visitor's Center, i Forked River, NJ H

" TLD 54 0.3 294 WNW d ofr.e, on the access road to Forked q Rivel 612.a, Forked River, NJ TLD 55 1.5 273 W of site, next to Basin 81 on the Forked River site, Forked River, NJ TLD 56 1.1 258 WSW of site, on the siren pole of the Building 12 parking lot, Forked River site, [

Forked River, NJ.

TLD 57 0.2 203 SSW of site, on Southern Area Stores access road, Pole BT 375, L, Forked River, NJ TLD 58 0.4 180 S of site, on Southern Area Stores-access i road, Pole JC-7-L, Forked River, NJ TLD 59 0.3 ' 163 SSE of site, on Southern Area Stores access road, Waretown, NJ TLD 60 0.4 136' SE of site, on Southern Area Stores access road entrance, waretown, NJ '

l t t

_ _ _ _ _ _ _ _ ____ _ _ . . . _ _ _ . _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ .m__ , , . _ . . . , . . . . . . . . _ . . . _ . . . _ . .m.- . . _ -,

. .. . . . .. _ - . ._ . _ - . . _ _ _ _ . . . ...- _ .= _ ..--.. - . _ .. _._ - .m . . . . _ _ _ . _ _ _ . . . _ . . - . _ _ _ _ _ _ _ . m. . . ._ .

l 1

TABLE A-1 (continued)

RADIOLOGICAL ENVIRONNENTAL MONITORING PROGRAM SAMPLING LOCATIONS '

Sample Station Nedium Code Distance Azimuth Description TLD 61 0.3 miles 116* ESE of site, on Route 9 south of Oyster Creek Nain Entrance, Pole BT1458, Forked River, NJ  ;

TLD 62 0.2 99 E of site, on Route 9 at access road to Nain Gate, Pole BT-61, Forked River, NJ [

TLD 63 0.2 70 ENE of site, on Route 9 at North Gate access road, Pole BT 14D63, Forked River, NJ TLD 64 0.3 48 NE of site, on Route 9 north of North Gate access road on Pole JC407X, Forked River, NJ

[ TLD 65 0.4 22 NNE of site, on Route 9 at Intake Canal ,

ao Bridge on Pole JC406L, Forked River, NJ .

APT, AIO, RWA, 66 0.5 127 SE of site, east of Route 9 and south of the TLD, VEG,' SOIL Discharge Canal, inside fence, Waretown, NJ TLD 67 1.0- 161 SSE of site, on Route 9 at Waretown Plaza, Waretown, NJ TLD 69 1.3 70 ENE of site, at the intersection of Chesapeake Drive and Buena Vista Road on Pole JC1347L, Forked River, NJ TLD 70 1.6 183 S of site, on Route 532,-3/4 mile west of Route 9, in front of Nartin residence, Waretown, NJ APT, AIO, RWA, 71 1. 7 . 165 SSE of site, on Route 532 at the Waretown

• TLD Nunicipal Building, Waretown, NJ F

APT, AIO, RWA, 72 1.9 27 NNE of site, at Library, TLD Forked River, NJ L

TABLE A-1 (continued) ,

RADIOIDGICAL ENVIRC anal MONITORING PROcnaM SAMPLING IDCATIONS l

[

Sample Station Medium Code Distance Azimuth Descrintion APT, AIO RNA, 73 -1. 8 miles lil' ESE of site, on Bay Parkway, Sands Point t TLD Harbor, Waretown, NJ TLD 74 2.0 90 E of site, Orlando Drive and Penguin Court, Pole JC6472L, Forked River, NJ TLD 75 2.0 '69 ENE of site,1225 Beach Blvd. and Maul Drive, Forked River, NJ l ,

TLD 76 1.7 51 NE of site, on Lacey Road across from

• Captain's Inn Restaurant, Forked River, NJ

[ TLD 77 1.5 26 NNE of site, NJ State Narina parking lot, w

Forked River, NJ  !

TLD 78 1.8 2 N of site,1514 Arient Road,' Forked River, NJ i TLD 79 2. 9_ 162 SSE of site, Hightide Drive and Bonita Drive Pole JC124 ON

• TLD 80 3.1 38 NE of site, Riviera Drive and Dewey Drive, Pole BT787, Lanoka Harbor, NJ '

TLD 81 4.6 192 SSW of site, east of Route 9 at Brook and  :

School Streets, Pole JC257BGT, Barnegat, NJ. i TLD 82 4.4 38 NE of site, Bay Way and Clairmore Avenue, Pole JC1273L, Lanoka Harbor, NJ TLD 83 5.8 29 NNE of site, Route 9 and Harbor Inn Road, ,

Pole BT666B, Berkeley, NJ  !

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. _,, __--,__-.4. - - - - -- - - . . - . . . - - - . . . . - - - . - . . . - - . - , - , - - - - ...,-.-=-.-.....s ~.--...-._-z- . . - - . - . . _ . - _ _ - ._ _ ___ = - _ _ _ - - _ _

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

m_.._ m --_.._..m.._. . _ . . . - . - _ _ _ . . . _ _ . _ . _ _ - _ . _ _ _ . . . . _ . _ . . -

1 TABLE A-1 (continued) l RADIOLOGICAL' ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS l

l Sample Station Medium Code Distance Azimuth Description TLD 84 4.8 miles 339' NNW of site, on Lacey Road,1.3 miles west of the Garden State Parkway on JCP&L siren pole, Forked River, NJ TLD 85 3.8 254 WSW of site, on Route 532 West, just prior +

to landfill, Pole BT354, 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 87 7.2 143 SE of site, north of Seaview Drive on siren pole, Loveladies, NJ

$ TLD 88 6.6 127 SE of site, eastern end of 3rd Street, Barnegat Light, NJ TLD 89 6.2 110 ESE of site, Job Francis residence, Island-Beach State Park 1 TLD 90 6.6 74 ENE of site, parking lot A-5, Pole JC181, Island Beach State Park TLD 91 9.5 4 N of site, on Robins Parkway, near Lobster Shanty Restaurant, Toms River, NJ TLD 92 9.2 48 NE of' site, at Guard Shack / Toll Booth, Island Beach State Park l SWA, AQS 93 0.25 150 SSE of site, Oyster Creek Discharge Canal, west of the confluence of freshwater Oyster Creek i t

r .

[

t c

TABLE A-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance Azimuth Description FISH, CRAB 93 0.1 to 0.3 128' to 250* SE to WSW of site, Oyster Creek miles Discharge Canal between pump discharge and Route 9 SWA, AQS, 94 21.8 201 SSW of site, in Great Bay, mouth of Jisunies CLAM, FISH Creek west of channel marker 1 CRAB 94 21.8 201 SSW of site, in Great Bay, adjacent to docks of Cape Horn Marina TLD T1 0.2 228 SW of site, at Oyster Creek Fire Pond, Forked River, NJ w

U TLD RA 2.5 243 WSW of site, at Ocean County voTech School on JCP&L siren pole, Waretown, NJ TLD RC 1.1 15 NNE of site, at sewage pumping station across from Oyster Bay Restaurant, Forked River, NJ '

TLD RD 1.3 43 NE cf site, at Twin Rivers sewage pumping station, Forked River, NJ

• TLD RF 0.5 14 NNE of site, on access road to Forked River-site, Forked River, NJ TLD RG 0.6 82 E of site, on Finninger Farm, west of dredge spoils basin, Forked River, NJ i

TLD RH 1.8 222 SW of site, at Ocean Community Cemetery off Route 532, Waretown, NJ i

_. ..-.m...______ . ._..__m_._._ . . _ . . _ . _ . . . _ . . -_....m.. ._..m. _ _ _ . = . - - . . _ _ _ , ~ _ . _ ~ . _ , . - . . _ . . _ . . - - .._...m.

TABLE A-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance Azimuth ' Description f

TLD RI 0.5 251 WSW of site, on access road to Southern Area Stores, near building 17 TLD RJ 1.7 343 NNW of site, in Pheasant Run development, Sheffield Drive and Derby Court, Forked River, NJ ,

SAMPLE MEDIUM IDENTIFICATION KEY H

APT = Air Particulate SWA = Surface Water SOIL = Soil U AIO = Air Iodine AQS = Aquatic Sediment FISH = Fish '

t RWA = Precipitation CLAM = Class CRAB = Crab WWA = Well Water VEG = Vegetables TLD = Thermoluminescent Dosimeter

1 l

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) TABLE A-2 SYNOPSIS OF THE OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONDUCTED BY GPUN ENVIRONMENTAL AFFAIRS OR i I

OYSTER CRWK NUCLEAR GENERATING STATION 1994 (1)

I S AMPLE TYPE NUMBER OF COLLECTION NUMBER OF TYPE OF ANALYSIS NUMBER OF SAMPLES SAMPLING FREQUENCY SAMPLES ANALYSIS FREQUENCY ANALYZED (2)

LOCATIONS COLLECTED 4

Air Particulate 13 weekly 675 Gross Beta weekly 673 (3)

Gamma 4-week composite 179 Air Iodine 13 weekly 675 I-131 weekly 675 Precipitation 13 4-wak 50 Gamma 12-week composite 22 (4) combined for a 12-week H-3 12-wmk composite 22 (4) composite 1 Well Water 5 4-week 54 Gamma 4-week 54

! H-3 4-wwk 54 I-131 4-week 26 (6)

Surface Water 8 4-week 102 Gamma 4-week 102 4

H-3 4-wwk 102 1-131 4-week 54 (6)

Clam 5 4-wmk 63 Osama 4-w uk 63 i

Saliment 8 4-wnk 32 Gamme 12-week composite 32 Vsgetables 3 4-week 29 Gamme 4-week 29 Soil (5) 3 12-week 6 Gamma 12-week 6 Fish 3 4-week 41 Gamma 4-week di Crab 3 4-week 18 Gamma 4-week 18 TLD-Teledyne Bmsn 10 12-week 37 Immersion Dose 12-week 37 Engineering TLD-Panasonie 71 12-week 281 Immersion Dose 12-week 281 l l (1) This table does not include Quality Control (QC) results.

(2) The number of samples analyzed does not include duplicats analyses, recounts, or reanalyses.

(3) See Table A-3.

l (4) Only compowtes from stations A, C, H,66,72, and 73 were analyzed.

! (53 Only collected u hen vegetables are collected.

I

! (6) Radioiodine analysis terminated in July. See Table C-1. l l

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! l 1 i j Table A - 3 1

i 1994 SAMPLING AND ANALYSIS EXCEPTIONS l

i} - During 1994, 1745 samples were collected from the aquatic, i i atmospheric, and terrestrial environments around the OCNGS. A l j total of 2,152 analyses were performed on these samples. This is i far more than the minimum number of samples and analyses required j by the Offsite Dose Calculation Manual (ODCM) Specifications. No i campling or analysis exception occurred in 1994 that resulted in a j dsviation from or violation of the requirements of the ODCM.

1 I An air particulate filter, collected on January 11, from station 5, j was misaligned during routine installation and only a partial i i cample was collected. The gross beta analysis result and the  !

j monthly composite gamma isotopic result from this station were not '

. uced. This air monitoring station is not required by the ODCM.

I <

j The air particulate / iodine sample collected on September 27, at l

! station 71, was lost due to a sampler malfunction (blown fuse) l l af ter 77.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of operation. The sampler was returned to service

within 5 working days. This sampler is in the location specified in ODCM specification 4.5.2.1.1 for an indicator station . -

ODCM i specification 4.5.1.2 allows for the loss of a sample if there is

a malfunction of the automatic sampling equipment. In addition, i the OCNGS REMP employs nine air particulate / iodine indicator stations where only four are required by the ODCM specifications.

) An air particulate filter, collected on November 28, from station j 5, was misaligned during routine installation and only a partial

cample was collected. The gross beta analysis result and the

! monthly composite gamma isotopic result from this station were not j used. This station is not required by the ODCM specifications.

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APPENDIX B l

1994 Lower Limits of Detection (LLD) Exceptions l I

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125

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TABLE B-1

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! DURING 1994, THERE WERE NO LOWER LIMIT OF DETECTION

! (LLD) VIOLATIONS ON ANY ANALYZED REMP SAMPLE 4  !

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i APPENDIX C Changes Effected in the 1994 REMP 1

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I j TABLE C-1 i CHANGES EFFECTED IN THE 1994 REMP l I

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July 1994

. The sample preservation technique of acidifying Surface Water and Well Water samples prior to analyses was eliminated. This procedural

requirement was dropped because of concerns of d

personal safety in handling the acid and also because there is no derived analytical benefit.

In turn, the need to perform a radiochemical

! iodine-131 analysis on surface water and well I water samples was eliminated. The I-131 result

! obtained from the gamma isotopic analysis, which

! meets the ODCM required sensitivity, was used in

! place of the radioiodine analysis result.

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e APPENDIX D 2

1994 Quality Assurance Results i

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l-l The OCNGS Environmental Affairs REMP Quality Assurance (QA) l Program consists of three phases. Phase I consists of l splitting samples collected at designated stations and having them analyzed by separate (independent) laboratories.

Analysis results from the quality control (QC) laboratory are ,

compared to those from the primary laboratory as set forth in OCNGS Environmental Affairs procedure 6530-ADM-4500.07.

Agreement criteria are established in this procedure. If non-agreement of the data occurs, an investigation begins ,

which may. include recounting or reanalyzing the sample (s) in question. .

Phase II requires that laboratories analyzing REMP samples for the OCNGS participate in the USEPA Cross-Check Program. ~This serves- as independent verification of each laboratory's ability to correctly perform analyses on various kinds of samples containing unknown quantities of specific l radionuclides. Results of this interlaboratory comparison. j program are presented in Appendix E.

{

Phase III requires that. the REMP analytical laboratories' l l perform duplicate analyses on every twentieth sample. The -

i number of duplicate analyses performed during 1994 is outlined l in Table D-1. 'Results cf the duplicate analyses were reviewed

_ in accordance with procedure 6530-ADM-4500.07. No l l non-agreements occurred during 1994 regarding duplicate l analyses of OCNGS REMP samples. i Table D-2 outlines the split sample portion (Phase I) of the <

QA program for the media collected during 1994. No non-agreements occurred between analyses in 1994. (See Table D-3).

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TABLE D-1

! 1994 OA SAMPLE PROGRAM l NUMBER OF DUPLICATE ANALYSES PERFORMED j l

ANALYSES 1 SAMPLEI [GRO5Sl . . ;g J:. '.[ . . . . .(GAMMA..,..

PEDll]H < Eg'fA i]L-y 'I-131' tISOTOPIC-3 j AIR PARTICULATE 35 11 3

J 1

AIR IODINb 36 i r

, RAIN WATER 1* 1*

l 2

WELL WATER 7 2 6 i

a SURFACE WATER 3 2 3 1  ;

, AQUATIC SEDIMENT 3  ;

CLAMS 4 FISH 2 ,

l CRABS 1 i

4 VEGETABLES 1

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SOIL 0

• 1 DUPLICATE ON QC SAMPLE-

! 131

t TABLE D-2 1994 OA SAMPLE PROGRAM SPLIT SAMPLES NUMBER OF NUMBER OF QA SAMPLE SAMPLE MEDH.IM REGULAR COLLECTION FREQUENCY QA COLLECTION FREQUENCY STATIONS STATIONS b

PRECIPITATION 13 MONTHLY 1 QUARTERLY COMPOSITE WHEN AVAILABLE WELL WATER S MONTHLY 1 QUARTERLY SURFACEW4Tkh 8 MONTHLY 1 QUARTERLY SEDIMENT 8 MONTHLY 1 QUARTERLY COMPOSITE CLAMS 5 MONTHLY 1 QUARTERLY WGETABLES 3 MONTHLY 1 QUARTERLY WHEN AVAILABLE WHEN AVAILABLE Soll 3 QUARTERLY 1 QUARTERLY  !

WHEN VEGETABLES AVAILABLE WHEN WGETABLES AVAILABLE I

TLD 71 QUARTERLY 2 QUARTERLY 132

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TABLE D i RESOLUTION OF 1994 OCNGS REMP SPLIT SAMPLE ANALYTICAL t NON-AGREEMENTS

! Aansmashv m e. I SAAAPLE M SAfdPLE DATE NUCUDE RE4NA',Yesa nEASON POn 800NNT.

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I DURING 1994, THERE WERE NO SPLIT SAMPLE ANALYTICAL NON-AGREEMENTS.

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APPENDIX E 1994 US EPA Cross-Check Results 8

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TABLE E-1 OYSTER CREEK NUCLEAR GENERATING STATION US EPA CROSS CHECK PROGRAM 1994 l DATE MEDIA NUCLIDE EPA RESULTS (A) ERL RESULTS (B)* Tl RESULTS (B)"  !

JAN 1994 WATER Sr-89 25.0 a 8.7 NO DATA (C) 24.00 e 1.00 Sr 90 15.0 e 8.7 NO DATA (C) 15.67 e 1.53 Gross Alpha 15.0 e 8.7 10.33 2 0.58 21.67 0.58 Gross Beta 62.0 z 17.3 24.33

• 4.73 (D) 72.33 s 3.79 g FEB 1994 WATER l-131 119.0

• 20.8 123.33

• 5.77 110.00 e 0.00 Ra-226 19.9 e 5.2 NO DATA (C) 21.00 e 1.00 Ra-228 14.7

• 6.4 NO DATA (C) 15.67 e 1.53 l U (Natural) 10.1

• 5.2 NO DATA (C) 9.73 a 0.12 MAR 1994 WATER H-3 4936.0 e 857.1 5000.00 e 100.00 4833.33 e 152.75 Pu-239 27.6

• 4.9 NO DATA (C) 25.33 0.58 APR 1994 WATER Co-60 20.0 e 8.7 20.33 e 2.08 23.67 e 3.21 Sr-89 20.0 2 8.7 NO DATA (C) 19.00 s 1.00 Sr-90 14.0 e 8.7 NO DATA (C) 13.00 3 0.00 Cs-134 34.0 e 8.7 32.00 e 1. 73 34.00 e 1.73 i Cs-137 29.0 e 8.7 30.00 e 1.00 34.00 e 2.65 Ra-226 20.0 a 5.2 NO DATA (C) 15.67 e 1.53 Ra-228 20.1 e 8.7 NO DATA (C) 15.33 3 0.58 U (Natural) 25.0 t 5.2 NO DATA (C) 22.33 3 0.58 Gross Alpha 86.0 e 38.2 78.33

• 3.79 78.00 e 3.00 Gross Beta 117.0 3 31.2 103.00 e 6.08 102.67

• 6.43 JUN 1994 WATER Co-60 50.0 2 8.7 50.33 e 1.53 43.00 e 2.00 Zn-65 134.0 a 22.6 140.00 s 0.00 13.33

• 0.58 (E)

Ru-106 252.0 e 43.4 200.00 10.00 (F) 201.33 s 9.29 (F)

Ba-133 98.0 17.3 89.67 s 1.53 85.00 e 3.00 cs 134 40.0 a 8.7 35.67 2 1.53 29.33

• 3.79 (G)

Cs-137 49.0 e 8.7 52.00 e 0.00 49.67 e 1.53 Ra-226 15.0 e 4.0 NO DATA (C) 15.33 3 0.58 Ra 228 15.4 6.8 NO DATA (C) 16.33 s 1.53 U (Naturat) 52.6 9.2 NO DATA (C) 54.33 e 1.15 l JUL 1994 WATER Sr-89 30.0

• 8.7 NO DATA (C) 26.00

• 1.73 Sr-90 20.0 e 8.7 NO DATA (C) 19.00

• 0.00 Gross Alpna 32.0 a 13.9 14.67 2 1.53 (H) 25.33 3 2.89 Gross Beta 10.0 2 8.7 15.00 s 0.00 16.00

• 0.00 l AUG 1994 WATER H-3 9951.0 e 1726.3 9966.67

• 57.80 9700.00 2 100.04 AUG 1994 AIR FILTER Sr-90 20.0 2 8.7 NO DATA (C) 18.00 2 0.00 Cs-137 15.0

• 8.7 15.67 a 1.15 17.00 e 1.73 Gross Alpha 35.0 e 15.6 38.67 0.58 31.33 s 2.08 Gross Beta $6.0 17.3 53.67 e 1.15 59.33 a 3.21 SEP 1994 WATER Ra-226 10.0

• 2.6 NODATA(d) 10.67 4 0.58 Ra 228 10.2 2 4.5 NO DATA (C) 9.70 a 0.52 U (Natural) 35.0 s 5.2 NO DATA (C) 38.67 e 0.58 SEP 1994 MILK K-40 1715.0 a 149.2 1800.00

• 100.00 1740.00 e 153.95 Sr-89 25.0 e 8.7 NO DATA (C) 24.33 e 2.52 Sr-90 15.0 e 8.7 NO DATA (C) 17.67 s 1.53 1 131 75.0 e 13.9 72.67

• 2.52 81.67

• 5.86 Cs-137 59.0 m 8.7 61.33 2 2.08 70.33 i 4.62 (1)

OCT 1994 WATER l-131 79.0 e 13.9 90.00

• 3.46 71.00 s 3.00 57.0

(

Gross Alpha m 24.3 48.33

• 3.06 47.00 a 3.00 Gross Beta 23.0 e 8.7 26.67 e 0.58 25.33 e 1.53 l

l 135 i

TABLE E S (continued)

OYSTER CREEK NUCLEAR GENERATING S7ATION j US EPA CROSS CHECK PROGRAM 1994 Oct 1994 WATER Co-60 40.0 e 8.7 37.33 s 0.58 41.00 1.00 Sr-89 25.0 s 8.7 NO DATA (C) 24.67

• 2.08 I Sr-90 15.0 e 8.7 No DATA (C) 14.33 e 1.15 Cs134 20.0 s 8.7 18.67 0.58 21.67 e 1.53 Cs137 39.0 8.7 40.00 3 1.73 41.67 e 2.31 Ra 226 9.9

• 2.6 NO DATA (C) 11.33 e 0.58 Ra-228 10.1

• 4.3 NO DATA (C) 9.33 3 0.58 U (Natural) 20.0 s 5.2 NO DATA (C) 18.00 e 0.00 l Gross Alpha 57.0 s 24.3 54.00 e 2.00 51.33 e 1.53 Gross Beta 142.0

• 36.4 126.67 s 5.77 120.00 s 0.00 l NOV 1994 WATER Co-60 59.0

• 8.7 56.67

• 2.52 52.00 2 0.00 2n-65 100.0

• 17.3 106.67 s 11.55 81.33 e 7.02 (J)  !

Ba-133 73.0

• 12.1 72.33 a 3.06 58.33 s 2.89 (J)

Cs-134 24.0 e 8.7 21.33 e 1.15 19.67 3 2.52 Cs 137 49.0 a 8.7 51.33 e 1.15 54.33 e 2.31

• GPUN ERL - The Environmental Radioactivity Laboratory located in Middletown, Pa.

• • Tl - Teledyne Isotopes Westwood laboratory located in Westwood, N.J. During 1994, the parent company of

, this Laboratory merged with another firm. It is now Teledyne Brown Engineering Westwood Laboratory.

A. EPA Results

• Expected Laboratory precision (s 3 sigma, n=3 control limit). Units are pCi/L for water and milk except K-40 (Nat.) is in mg/L. Units are total pCi for air particulate filters.

B. Results Average a one standard deviation. Units are pCl/L for water and milk except K-40 (Nat.) is in mg/L. Units are total pCi for air particulate filters.

C. No data available. Analysis not performed by laboratory.

D. When the sagte was received at the laboratory is was found to be frozen. This may have affected the samle matrix for the Cs 137. If the Group ! lons (Na, K, Cs, etc.) plated out onto the walls of the sample container this would result in the low activities. The Group III fons (Ac, Th, etc.) may not have been affected.

E. The average value of three analyses on the " Report of Analysis a was 133 pCi/ liter which is in good agreement with the EPA. The value reported to EPA (13.3 pcl/L) was in error by a factor of ten due to a typing error.

F. The EPA notified participants that the Radiation Quality Assurance Program has been experiencing problems with the Ruthenium-106 used in the Performance Evaluation Studies and in the Standards Distribution 4

Program. The tu-106 has been discontinued until further notice.

G. The first aliquot, prepared according to EPA dilution instructions was rounted on four detectors in the 1 liter Marinetti geometry with Cs-134 results (based on the 796 kev peak) in pcl of 32.0, 25.1, 31.7 and 30.8. The 31.7 result was not reported. Had that been reported instead of 25.1, the average would have been 31.5 and the normalized deviation would have been -2.94 instead of -3.70. A second aliquot was prepared and a single measurement was made with the result of 31.1 pCf/1. An undiluted aliquot was measured in a 150 mt geometry with the result of 33.5 pcl/1. That result is comparable with the Marinelli results. Thus, sample preparation (dilution, volune determination, maintaining correct pH, etc.), sample geometry, and detector efficiency do not seem to be the cause of the low results.

H. The ERL Alpha results reported to the EPA were incorrect. A sample size of 0.4L instead of 0.2L was used in the calculations. The corrected results of 32, 27 and 30 pcl/L are within the control timits and below the warning regions. Also the precision among the individual results is acceptable. t

1. The milk sagte was counted four times. The reported Cs 137 values were based on one aliquot of 1 liter volume and an aliquot of 0.865 liter counted two times. It is suspected that the 0.865 liter volume was incorrectly determined. If 1 liter (the usual volume for counting milk samples) is used in the calculation, then the average of three results equals 63.6 pCf/L which gives a normalized deviation to the known of 1.59. The fourth count (a 1 liter aliquot) had Cs-137 activity equal to 64.2 pCi/L which is in good agreement with the average of the other three. Teledyne will set up a log for recording aliquots used for EPA samples and record how the aliquot volume was determined.

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d TABLE E-V (continued)

OYSTER CREEK NUCLEAR GENERATING STATION US EPA CROSS-CHECK PROGRAM 1994 I

i J. The EPA requires that water samples be diluted before games analysis. That imposes a feature not i appropriate for the handling of envirofunental samples. As in the 6/10/94 water sample, it appears that the first aliquot may not have been accurately prepared. A second aliquot was prepared and counted three j times with results in pCl/L and normallred deviation of:

Co-60 60.6 +0.55 Zn-65 140.0 0.00 Cs-134 22.9 -0.38 s

Cs-137 58.5 +3.29 Ba-133 69.8 0.79 i

Four of the five are now in good agreement with the EPA results. The Cs 137 is high, but within the control limits when conpared to the grand average deviation of all laboratories of 2.89. The grand

everage was 51.9 pC1/L. For future samples of this type Telodyne grown will have two technicians each j prepare an oliquot and compare the counting results to check for preparation techni p differences.

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APPENDIX F 1994 Annual Dairy Census f

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l Annual Dairy Census - 1994 l

l l An annual dairy census was conducted to determine the number I of commercial dairy operations and/or lactating dairy animals  ;

providing milk for human consumption located within a five mile radius of the OCNGS. No commercial dairy operations were identified within the vicinity of OCNGS.

Ocean County Agricultural Extension Service Agent, Ms. Debra Fiola, was contacted regarding the occurrence of dairy animals within a five mile radius of the OCNGS. Ms. Fiola indicated

] that no commercial dairy operations were active in the study area. She also indicated that to the best of her knowledge, no local 4H Club members were raising dairy animals within the i study area. In a subsequent conversation with a representative of the Ocean County 4H Club, it was confirmed that no dairy animals existed within the study area.

Furthermore, the closest known dairy animals whose milk was being used for human consumption were goats owned by three families in the Whiting area (approximately 12 miles NW of OCNGS). Several f amilies who owned goats in Jackson Township, I further to the north were also identified.

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APPENDIX G  ;

Dose calculation Methodology r

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j To the extent possible, radiological impacts'were evaluated

j. based on the direct measurement of dose rates or . of.

radionuclide concentrations in the environment. However, the

radionuclide releases associated with 1994 OCNGS operations I were largely too small to be measured once dispersed'in the 1

i j offsite environment. As a result, the potential offsite doses l

were estimated by using computerized models that. predict' i e

concentrations of radioactive materials in the environment and subsequent radiation doses on the basis of radionuclides

]

released'to the environment. GPUN calculates dosessusing two l advanced class "A"' dispersion models called SEEDS,(Simplified -!

i Effluent Environmental Dosimetry System) and EFFECTS l J

(Radioactive Effluent Filing, Evaluation, and Comparison with Technical Specifications). These models incorporate the j . guidelines.and methodology set forth in USNRC Regulatory Guide 1.109 (Ref . 2 7 ) . SEEDS uses hourly meteorological information f

a matched to the time of releases to assess the dispersion of .

j effluents in the discharge canal / estuary system . and the j

i.

' atmosphere. Combining this assessment of dispersion and l t

j dilution with effluent data, postulated maximum hypothetical  !

l doses to the public from the OCNGS effluents are calculated. >

i j The maximum individual dose is calculated as well as the dose  ;

j to the total population within 50 miles of OCNGS for gaseous

{

effluents and the entire population downstream of the OCNGS (

j around Barnegat Bay and the Atlantic Ocean for liquid I

i effluents. Values of environmental parameters- and

{ radionuclide concentration factors have been chosen to provide  !

l conservative results. As a result, the doses calculated using  :

t I

this model are conservative estimates (i.e. , overestimates) of  !

1 l the actual exposures.

6

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I i The dose summary table, Table G-1, presents the . maximum  :

4 i hypothetical doses to an individual, as well as the population i j doses, resulting from effluents from OCNGS during the 1994 (

] reporting period.

I 141 t j l 5-

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Individual Doses From Licuid Effluents As recommended in USNRC Regulatory Guide 1.109 (Ref. 27), dose calculations resulting from OCNGS liquid effluents are performed on four age groups and eight organs. The pathways considered are consumption of fish, consumption of shellfish, and shoreline exposure. All pathways are considered to be primary recreational activities associated with Barnegat Bay and the Atlantic Ocean in the' vicinity o'f the OCNGS. The ^

" receptor" would be that individual who eats fish and shellfish that reside in the OCNGS discharge canal, and stands .

on the shoreline influenced by the station discharge. Table ]

G-1 presents the maximum total body dose and critical organ dose for the age group most affected.

No liquid releases were made from the OCNGS in 1994. As a result, there were no doses via liquid effluents to the public.

4 Individual Doses From Gaseous Effluents l

l There are seven major pathways considered in the dose calculation for gaseous effluents. These are: (1) plume i l exposure, (2) inhalation, (3) consumption of cow milk, (4) i goat milk, (5) vegetables, (6) meat, and (7) standing on l contaminated ground. }

I l The maximum plume exposure reported in lines 3 and 4 of Table G-1 generally occurs at, or near, the site boundary. These l " air doses" are not to an individual but are considered to be the maximum dose at a location. The location is not I

necessarily a receptor.

With respect to airborne noble gaseous releases for the 1994 reporting period, the maximum plume exposure (air dose) would l have been 5. 8E-2 and 3.8E-2 mrad for OCNGS gamma and beta radiation, respectively. These doses are equal to only 5.8E-1

! 142

i A-f.

percent and 1.9E-1 percent of the OCNGS Offsite Dose Calculation Manual (ODCM) and Technical Specification annual j- dose limits, respectively.

i The calculated airborne doses to the closest ' individual in the- l l maximally affected sector (SE) for total' body dose and skin' l dose was at a - distance of 522 meters. These data are presented in lines 5 and 6 of Table G-1. Maximum calculated l- __-

plume _ exposures; to_an_ individual, regardless of age,i rom _

f ._

l gaseous effluents.during the 1994 reporting period were 4.4E-3

) mrem to the total body and 3.3E-3 mrem to' the skin. These doses are equivalent to only 8.8E-4 percent and 1.lE-4 percent i

of the ODCM specified annual dose limits, respectively.

i l The dose to the . maximum exposed organ due to radioactive.

i airborne iodine and particulates is presented-in line 7, Table

G-1. This does not include the'whole body plume exposure, .

{ which was separated out 'on line 5. The dose presented in this l section reflects the maximum exposure to:an organ for-the-j appropriate age group. During 1994, gaseous iodines and j particulates from OCNGS would have resulted in a maximum dose  :

l 1

of 3.7E-2 mrem to the thyroid of an inf ant. This dose is only 1

2.5E-1 percent of the OCNGS ODCM specified annual dose limit. I

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'I l' 143

4 i

Population Doses From Licuid and Gaseous Effluents

The population doses resulting from liquid and gaseous effluents are summed over all pathways and the affected l population (Table G-1, lines 8-11) . Liquid population dose is based upon the population located within the region from the OCNGS outfall extending out to the Atlantic Ocean. The-J population dose due to gaseous effluents is based upon the l 1980 population projections of the Final Safety Analysis l Report (FSAR) and considers the population out to a distance of 50 miles around the OCNGS as well as the much larger total population which can be fed by food stuffs grown in the 50 mile radius. Population doses are summed over all distances and sectors to give an aggregate dose.

Total OCNGS liquid and gaseous effluents resulted in a population dose of 3.5E-1 person-rem total body for the 1994

, reporting period. This is approximately 2.83 million times lower than the doses to the same population resulting from j natural background sources.

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1 144

4 TABLE G-1

SUMMARY

OF MAXIMUM HYPOTHETICAL INDIVIDUAL AND POPULATION DOSES FROM LIOUID AND AIRBORNE EFFLUENT EELEASES i, FROM THE OCNGS FOR 1994 ,

5 4

2 JNDIVIDUAL DOSES'

, Effluent ODCM Soecification Calculated Agg- Dist. Sector % Reg.

Released Limit Desc Qg (m) Limit ,

Liquid -* * *

• j 3 mrem-Total Body

• Liquid * * * *

• 10 mrem-Organ i  ;

i Airbome .10 mrad-Gamma 5.8E-2 -

522 SE 5.8E-1 4

l Airborne - 20 mrad-Beta 3.8E-2 -

522 SE 1.9E-1 Airborne 500 mrem-Total Body. 4.4E-3 ' All 522 SE 8.8E-4 l Airborne 3000 mrem-Skin 3.3E-3 All 522 SE 1. lE-4

Airborne 15 mrem 3.7E-2 Infant - 522 - SE 2.5E-1 i

POPULATION DOSES 2 i

Effluent calculated i Released Dose (Person-rem)

. Liquid Total Body

• i i

j Liquid Any Organ

• 4 i

)- Gaseous Total Body 3.5E-1 i

Gaseous Skin 5.4E-1 No individual or population doses were calculated for liquid releases because there were no liquid releases during 1994.

) 8 Individual doses for the calendar year were calculated using the EFFECTS software.

4 These calculations utilize default meteorology referenced in the OCNGS Offsite Dose l Calculation Manual.

2 Population doses were calculated using the SEEDS software.

)

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.c APPENDIX H 1994 Groundwater Monitoring Results  ;

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l TABLE H 1 1994 OCNGS GROUNDWATER RESU11S i CONCENTRATION IN oCi! LITER +l- 2 STANDARD DEVIATION MARCH 1994 STATION TRITIUM RESULTS GAMMA ISOTOPIC RESULTS l

OCWW1 < 180 All NUCLIDES < LLD OC WW-2 < 180 ALL NUCLIDES < LLD OC-WW 3 < 180 ALL NUCLlDES < LLD OCWW4 < 180 ALL NUCLIDES < LLD OC WW-5 < 180 ALL NUCLIDES < LLD OC WW-6 < 180 ALL NUCLIDES < LLD OC-WW 7 < 160 K40 48 +/- 40 ALL OTHER NUCLIDES ARE< LLD OC WW-9 220 +/ 120 ALL NUCLIDES < LLD OC WW 10 < 180 ALL NUCLIDES < LLD OC WW 12 < 180 Co-60 2.3 +/ 1.3 K40 27 +/- 18

! Th-23211 +I 6 f ALL OTHER NUCLIDES ARE < LLD l 00-WW 13 < 180 K40 21 +/ 15 ALL OTHER NUCLIDES ARE < LLD OC-WW 14 < 180 ALL NUCLlDES < LLD I OC WW-15 < 180 ALL NUCLIDES < LLD I OC WW 16 < 180 '

ALL NUCLIDES < LLD OC WW-17 < 180 ALL NUCLIDES < LLD l OCTOBER 1994 l

STATION TRITIUM RESULTS 0AMMA ISOTOPIC RESULTS OC-WW 1 < 150 ALL NUCLlDES < LLD OC WW-3 < 150 ALL NUCLIDES < LLD OC-WW4 < 150 ALL NUCLIDES < LLD OC-WW 5 < 150 ALL NUCLlDES < LLD OC-WW 6 < 150 ALL NUCLIDES < LLD OCWW7 < 150 ALL NUCLIDES < LtD OCWW9 < 160 ALL NUCLIDES < LLD 1 OC WW 10 < 160 ALL NUCLIDES < LLD l 00-WW 12 < 150 Th 232 7.6 +/ 6.2 ALL OTHER NUCLIDES ARE < LLD OC WW 13 < 160 ALL NUCLIDES < LLD OC-WW 14 < 160 ALL NUCLIDES < LLD OC-WW-15 < 160 ALL NUCLIDES < LLD OC WW 16 < 160 ALL NUCLIDES < LLD OC WW 17 < 150 ALL NUCLIDES < LLD 147

Figure H-1

~

Locations Of On-Site Wells I

Building Key 1 Turbine Generator 6 Warehouse 2 Reactor Bldg. 7 Rad Waste 3 Maintenance Bldg. 8 Guard House i 4 Off-Gas Bldg. 9 Office Bldg.

5 Waste Storage 10 Engineering Bldg.

11 Parking Lot j

l SUBSTATION W-1 @ '..........................................

DISCIIARGE CANAL l INTAKE CANAL l

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W-14 11 g W-17 148

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l APPENDIX I 1994 REMP Sample Collection and Analysis Methods I

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149

TABLE I-1 RADIOLOGICAL ENSIRONMENTAI MONITORING PROGRAM

SUMMARY

OF SAMPLE COLLECTION AND ANALYSIS METHODS 1994 l Approximate l Cottection Sample size Analysis Analysis Sanple Medium Sangling Method Procedure Ntsber Collected Procedure Ntaber Proced.are Abstract l

Gr-Beta Air Continuous weekly or more frequent air CC-EC 1 filter TMI-E9 Low background gas Particulate sanpting through filter paper 6530-IMP-4522.05 (approximately 6510-IC-4592.05 flow proportional 600 cubic counting meters weekly)

Gama Spectrosccoy Air Four week conposite of each station OC-EC 4 filters TMI-EC Gama Isotopic Particulate 6530-IMP-4522.05 (approximately 6510-IMP-4592.05 analysis 2400 cubic meters)

Gamma Spectroscopy Air Continuous weekly or more frequent air OC-EC 1 cartridge TMI-EC Gama Isotopic lodine sanpling through charcoat cartridges 6530-!MP-4522.05 (approximately 6510-OPS-4591.04 analysis 600 cubic meters weekly)

Ganrna Spectroscopy Surface Four week grab sample OC-EC 7.5 t iters TMI-EC Gamma Isotopic Water 6530-IMP-4522.06 6510-IMP-4592.06 analysis 6510-OPS-4591.04 TI-Westwood Gama Isotopic

@ PRO-042-5 analysis w

o Gansna Spectroscopy Rain Twelve week composite OC-EC Minista of 0.5 TMI-EC Ganrna Isotopic Water 6530-IMP-4522.07 titers 6510-!MP-4592.06 analysis 6510-OPS-4591.04 TI-Westwood Gansna Isotopic PRO-042-5 analysis Ganima Spectroscopy Well Four week grab sanple OC-EC 7.5 liters TMI-EC Ganina Isotopic water 6530-IMP-4522.10 6510-IMP-4592.06 analysis 6510-OPS 4591.04 TI-Westwood Gansna Isotopic PRO-042-5 analysis Gama Spectroscopy Ctams Four week grab sanple OC-EC 1 kg TMI-EC Gamma Isotopic Fish Semiannual grab sample or more frequent 6530-IMP-4522.14 (if possible) 6510-IMP-4592.03 analysis Crabs Semiannual grab sanple or more frequent 6530-IMP-4522.16 6510-OPS-4591.04 TI-Westwood Gansna Isotopic PRO-042-5 analysis Gansna Spectroscopy Sediment Twelve week conposite of each station DC-EC 3.8 titers TMI-EC Ganena Isotopic Soit Twelve week grab sample (when 6530-IMP-4522.03 (if possible) 6510-lMP-4592.04 analysis vegetables are available) 6530-IMP-4522.08 6510-OPS-4591.04 TI-Westwood Gansna Isotopic PRO-042-5 analysis

TABLE I-1 (continued) l RQDIOLOGICAL EtMIRONMENTAL MC]ITC3tNG PRCSRAM SUMMAR7 OF SAMPLE COLLECTICJ AND ATALYSIS METHODS .

1994 Approximate Collection Sanple size Analysis Analysis Sample Meditan Sancting Method Procedure Ntaber Collected Procedure Nunber Procedure Abstract Gansna Spectroscopy Vegetables Four week grab saapte OC-EC 1 kg or more TMI-EC Gansaa Isotopic 6530 IMP-4522.04 (if possible) 6510-lMP-4592.03 analysis 6510 OPS 4591.04 TI-Westwood Gamma Isotopic PRO 042 5 analysis Tritium Surface Water Four week grab sample OC-EC 7.5 liters TMI-EC Sample mixed with 6530-IMP-4522.06 6510-IMP-4592.02 seintitiation 6510-CPS-4591.05 fluid for scintittation counting.

TI-Westwood Water converted to 1 PRO-052-2 hydrogen, methane I added for gas j counting.

Tritius Rain Water Twelve week composite saapte OC-EC Minimum of 0.5 TMI-EC Sample mixed with 6530-IMP-4522.07 titers 6510-IMP-4592.02 scintittation g 6510-OPS-4591.05 fluid for tn scintittation w counting.

! TI-Westwood Water converted to PRO-052-2 hydrogen, methane

' added for gas-i counting.

Tritita Welt Water Four week grab sample OC-EC 7.5 liters TMI-EC Sample mixed with 6530-IMP-4522.10 6510-IMP-4592.02 scintittation 6510-OPS-4591.05 fIutd for scintittation cotaiting.

TI-Westwood Water converted to P90-052-2 hydrogen, methane q added for gas counting.

TLD (Panasonic) Isumersion Dose Desimeters exchanged spaarterly OC-EC Four Badges TMI-Desimetry Thermottminescent 6530-IMP-4522.02 9100-OPS-4243.01 dosimetry TLD (Tetedyne troun Inumersion Dose Dosimeters exchanged quarterly OC-EC One Badge TMI-Westwood Thermoluminescent Engineering) 6530-IMP-4522.02 PRO-342-17 dosimetry 2

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T OYSTER CREEK NtK.1 EAR GENERATING STATION s ENVIRONMENTAL CONTROtE --i

. . . e 1994 QlJARTERLY ENYlRONMENTAL7tA REPORT.PANA80NIC *

' RUNNING TART 2. Mill.lREM PER STANDARD QUARTER AND 3. STANDARD DEVIATIONS Mantest Fire rested 1994 seemed reeled 1994. 1Mrd Perted 1994 .- Fourth Freemd 1994 .

W R IM : W sed. Dry - ^

Reedham-' 7 IInd. DevX ReW feed. Dev A 10.15 I.12 I I.13 0 63 I I.44 I.89 12.23 1.13 C 9.95 1.76 11.09 0.41 18.24 0 61 11.26 1.13 11 937 1.20 9 99 0 75 10.13 1.12 11.19 0 94 I 10 97 1.12 13.12 1.47 12.58 I 72 18.17 1.57 3 9.23 0.59 9.38 I.03 10.58 0.72 10 93 0 62 4 8.49 1.18 8 69 1.19 9.89 I 02 10 60 0 93 5 9.48 0.41 10.12 1 08 1837 0.71 11.55 0 84 6 9.10 1.02 9.71 1.51 10.52 1.12 11.12 1.72 7 8 66 134 1030 133 9.89 0.40 10 14 0 85 8 9.29 1.02 9.55 1.18 10.44 1.13 10 62 0 7f 9 9.83 0.96 10.70 0 62 Il.31 0.88 I I.26 0 88 RA 8.92 0.82 9.50 1.11 10.56 1 00 9.90 031 RC 9.77 0.84 1037 0.75 1131 103- 10.91 1.28 RD 9.20 0 63 9.41 0.90 10.52 0 66 is.58 0.57 RF 9.74 0.65 1032 1.00 10.79 0 83 II .06 0.94 RG 9 04 0 55 9.29 0 67 9.66 0.92 9.84 0.73 A

RII 9.24 1.48 9.72 0 80 035 9.64 0.58 10 28 0 si RI 10 06 1.42 11.26 11.57 038 11.15 0.79 R3 8.78 034 10.29 1.29 10.69 0.96 10.44 0 94 TI 10 63 0.79 12.70 1.09 12.61 1.23 10.93 0.87 10 9.11 0.62 10.05 1.14 1039 0 89 11.06 0.84 II 8.76 0 66 9 66 1.17 10.08 1.13 10.79 0 47 12 9.05 0 68 10 95 1.07 11.10 065 Il 66 1.29

, 13 7.94 0.56 9.63 I.02 9 68 0.49 10 38 0 50 I4 10.85 0 66 12.99 0.64 1237 0.97 13.79 0 00 15 8.76 0.81 10 37 1.13 10.53 0.94 11.29 0 88 16 835 0 67 9.37 0.71 9.40 0.97 10 46 0 67 17 8.93 0.44 10.21 0.70 TLD IDST TID IDST 20 8.51 0.74 10.I4 1.09 9.66 0 61 10 70 0.72 22 831 0.90 9 44 0 68 9.09 1.01 10.18 0.70 SI I I.70 0.28 13.45 1.13 1336 0.72 14.10 1.01 52 12.78 0.40 14 79 1.59 14 36 1.20 14 10 136 33 11.33 0.46 12 84 134 12.46 1.11 11 09 0 61 54 9.46 0.51 10.83 0.78 10 84 1.24 1031 130 55 9 12 0 67 10 31 0 57 10 60 0 60 18 03 0 87

s TABLE J-2 (Camalumed) 3. .. .. >

'OWil!R CREER NtK' LEAR GENEltATING STATION ; ENVIRONMENTAL CUNTftOtA

.m 1994 QUARTERLY ENV15tONMENTALTIE REPORT . PANASONIC ; . s

? i Rt NNINC TAllIX a MilllREM FER #FANDARD QOARTER AND 24TANDARD IW.VIATSONS -

samasse .. First rated 1994 t. . , sovved Futed 19941 .

. TMrd Posted 1994 t. . Fearch rested 1994 _

m : M Dre ~ ^* W ~ 5 M W W 2- M W ** ' M Dev 56 10.06 037 11.91 0.91 1136 0 81 11.97 1.28 57 16 04 2 81 18.37 436 15.57 2.73 18 83 0.66 58 13 23 1.04 14.55 1.12 13.90 1.05 10 05 0 88 59 11.89 1 01 12.80 1.48 1238 1.97 18.82 n.74 i 60 9.77 1.00 9.90 0.76 10 32 1,09 10 68 0.97 61 9.57 0.66 10.01 0 87 1031 1.47 10 05 0.77 62 to 08 033 10.20 0.51 10 89 1.63 10 83 0 45 63 1031 0 37 10 61 0.71 11.11 0.74 11.58 0 60' 64 9.7I 0.64 9.53 0.79 10 46 1.26 10.90 0 32 65 9.81 0.91 9 64 0.98 10.40 2.20 11.18 1.18 66 9.43 1.09 9.38 0.69 10.52 0 65 10.25 1 09 67 9.97 0.82 9.69 0.65 10.75 0.85 10.97 0.75 69 9.11 0.85 9.26 1.15 10.22 0 80 10.70 0.69 70 9.33 1.10 8.76 1.14 10.08 1.08 10.23 0.59 73 9.75 0.57 9.18 0.79 10.82 0 37 11.14 0.81

[ 72 10.29 I39 9.78 0 67 I1.26 0.75 Il.22 0 30 m 73 TID LOST 8 60 0 64 10.09 0 62 10.75 0.58 74 TID IDST 9 65 1.13 10.79 0 80 10.8I I 28 75 9.99 1.58 11.13 132 12.00 0.49 11.83 0.69 76 9.33 0.77 9.53 0.62 10.71 0.41 10.58 0 81 77 8.92 134 10.54 0 84 11.85 1.12 12.00 1.54 7* 8 81 1.06 9.86 1.06 10.43 0.97 10.22 0.48 74 8 89 0.71 9.73 1.16 9 94 0 69 10 04 0.44 80 9 45 0.65 10.09 2.19 10.44 0.91 9.94 0 80 81 9 91 035 11.10 1.20 10.23 0.96 10 43 I.14 82 9.99 1.13 30.20 0 85 10 84 132 10.23 0 67 83 9.74 0.74 10.72 1.44 11.10 0 83 11.02 1.15 84 10.23 1.58 11.95 0.60 11.27 1.28 11.29 1.29 85 9.04 0 57 10 01 0.85 10.46 1.09 10.54 0.72 86 9.43 1.59 10.46 1.54 1036 1.24 I I.09 0.83 87 10.90 0 89 12.13 1.I4 11.53 0 59 12.55 0.38 88 8.74 1.48 9.22 0 84 9.06 0.83 9.78 0.94 39 8.6C 0 62 8.70 1 03 9.44 1.12 9 98 0 98 90 8 67 0.75 8.79 0 32 9.47 0.56 9.98 0.72 91 9.64 1.05 10.05 1.07 10.80 2.26 11.01 0.60 92 1134 0 33 11.24 0.55 12.10 0.82 12.43 0 83

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