ML20096A170

Radiological Environ Monitoring Rept

ML20096A170
Person / Time
Site:	Oyster Creek
Issue date:	12/31/1991
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-92-2132, NUDOCS 9205080126
Download: ML20096A170 (170)

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GPU Nuclear Corporation 9 Nucleer  :::on:r388 forked Rwer New Jersey 087310388 609 971-4000 Wrfter's Droct D al Nurnt=r:

April 27,1992 C321-92 2132 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Radiological Environmental Monitoring Program (REMP) Report Enclosed is a copy of the Oyster Creek REMP report for 1991. This submittal is made in accordance with technical specification 6.9.1.e.

If there are any questions regarding this matter, please call Brenda DeMerchant, Licensing Engineer, at (600) 971-4642.

Sincerely, J.J. Barton Vice President and Director Oyster Creek cc: Administrator, NRC Region 1 Senior NRC Resident inspector Oyster Creek NRC Project Manager Chief, Bureau of Nuclear Engineering, NJDEP

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l OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey The 650 M\Vplant is a single unit, five loop General l

Electric Boiling Water Reactor (BWR). The site, about 800 acres, is in Lacey and Ocean g Townships of Ocean County. Located approximately nine miles south of Toms River, it is E about 50 miles east of Philadelphia, and 60 miles south of Newark.

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

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

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

The 652 ton reactor contains 560 fuelassemblies, 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. l The Turbine Building houses the turbine getierator, control room, main condensors, power conversion equipment and auxiliary systems. The turbine-generator consists of one high pressure turbine, three low pressure turbines, a generator l and an exciter. The turbines and generator turn at 1,800 revolutions per minute to generate three phase, 60-cycle electricity at 24.000 volts. The electricity generated is provided to the grid by two transformers which boost the voltage to 230,000 volts.

l 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-l densate and feedwater pumps. y The main condensers consist of three horizontal, single g pass, divided water boxes containing 44,000 tubes having a totallength of about 1,875,000 feet. Cooling water is provided from Bamegal Bay, through the South Branch of the Forked a River and passes through the condensers and discharges into Oyal Creek for retum to l Bamegal Bay. The water is pumped by four 1,000 horsepower pumps, each of which moves about 115,000 gallons per minute through the 6 foot diameter pipes that feed the g condensels. E The ventilation stack is 368 feet high with 26 feet extend-ing below grade. The stack provides ventilation for the Reactor Building, Turbine Building g and Radwaste Facilities. E Oyster Creek is owned by Jersey Central Power & Light (JCP&L) Company and oper- E ated by GPU Nuclear (GPUN) E Corporation. JCP&L and GPUN are units of the GPU System. l l

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I 1991 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT I PREPARED BY OYSTER CREEK ENVIRONMENTAL CONTROLS GPU NUCLEAR CORPORAT10N I

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TABLE OF CONTENTS l

PAGE TABLE OF CONTENTS i LIST Of TABLES 111 LIST OF FIGURES V

SUMMARY

AND CONCLUSIONS 1 INTRODUCTION l

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Charactoristics of Radiation 4 Sourcos of Radiation 6 i Nuclear Reactor Oporations Sourcos of Liquid and Airborno Etfluents 9

13 DESCRIPTION OF THE OYSTER CREEK i NUCLEAR GENERATING STATION S1TE 16 General Information 16 Climatological Summary - 1991 17 EFFLUENTS 19 Historical Background 19 Effluent Roloase Limits 20 Effluent Control Program 23 Effluent Data 24 RADIOLOGICAL ENVIRONMENTAL MONITORING 29 Environmental Exposuro Pathways to Humans from Airborno and Liquid Effluents 30

Japling 31

i. Analysis Quality Assuranco Program 32 36 DIRECT RADIATION MONITORING 78 Sample Collection and Analysis 78 Results 79 ATMOSPHERIC MONITORING 86 l Sample Collection and Analysis Results 86 87 AQUATIC MONITORING 92 Sample Collection and Analysis 92 Results 93 l

I TABLE OF CONTENTS (Continued)

PAGE:

TERRESTRIAL MON 1TORING 100 Samplo Collection and Analysis 101 Rosults 101 GROUNDWATER MONITORING 103 Samplo Collection and Analysia 103 Results 104 RAD 10 LOGICAL IMPACT OF OCNGS OPERATIONS 106 Dotormination of Radiation Donos to the Public 106 Results of Dose Calculations llo REFERENCES 114 APPENDIX A: 19!i PEMP Sampilng Locations and 118 I DescripHon, Synopsia of REMP, and Sampling and Andlysis Exceptions APPENDIX B: 1991 Lower Limits of Datoction (LLD)

I Exceptions 129 APPENDIX C: Changes Elfacted in tho 1991 REMP 131 APPENDIX D: 1991 Quality Assuranco Results 133 I APPENDIX E: 1991 EPA Cross-Check Results 138 APPENDIX F: 1991 Annual Dairy Consus 141 APPENDIX Ga Doso Calculation Methodology 143 APPENDIX H: 1991 Groundwater Monitoring Results 149 APPENDIX I: 1991 REMP Sample Collection and Analysis Methods 152 APPENDIX J: 1991 TLD Quarterly Data 156 I

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LIST OF TABLES TABLE TITLE PAGE 1 Sources and Doses of Radiation 7 2 Radionuc1ide Composition of OCNGS Etfluent3 for 1991 26 3 Radiological invironmental Monitoring ,

. Program Sumte t A stor Creek Nuclear l

. , . Generating Sc2 uct) - January 1991 through December 1991 38 4 TLD Exposure Periods in 1991 79 S Species of Fish Cauthtj as Part

? Of the OCNGS REMP in 1991 97 l

6 Calculatti Maximum Hypothetical Doses to an l Individual from Liquid and Airborne Etfluent '

Roleases from OCNGS for 1991 112 j 7 Calculated Maximum Total Radiation Doses to tne i Populstion from Liquid and Airborne Effluents from the OCNGS for 1991 113 l

i A-1 Radiological Envi::anmental Monitoring Program Sampling Locations 119 A-2 Synopsis of the Oferational Radiological Environmental Monitoring Program 127 l

A-3 Sampling and Anblysis Exceptions - 1991 128 B-1 Technical Specifications Analytical Results Which Failed to Meet the Required LLD During 1991 130 l-1 C-1 Changes Effected in the 1991 REMP 132 D-1 1991 QA Sample Program - Number of Ouplicate l.

Analyses Performed 135 D-2 1991 QA Sample Program - Split Samples 136 D-3 Resolution of OCNGS REMP Split Sample Analytical Non-Ayreements 137 E-1 US EPA Cross-Check Program 1991 139 l

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LIST OF TABLES (Continued)

TABLE TITLE PAGE I G-1 Summary of Maximum Individual and Population Doses from Liquid and Airborne Effluent Releases from the OCNGS fc' 1991 148 H-1 0"NGS - Groundwcter Results . !io I-1 Summary of Sample Collection and Analysis Methodo 1991 153 J-1 1991 Quarterly Environmental TLD Report -

Telodyne Isotopes 157 J-2 1991 Quarterly Environmental TLD Report -

Panasonic I 159 I

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

.i Simplified Schematic il 2 Monthly Precipitation at the Oyster Creek i Nuc1 car Generating Station During 1991 Compared with Historical (1946< 1981)

Atlantic City National Wcather Scrvice Procipitation Data 18 Locatlun of Radiological Environmental l Monitoring Program (REMP) Stations Within One Mile of the Site 33 Location of Radiological Environmental l Monitoring Program (REMP) Stations Greater than One Mlle and Within Two Miles of tho Site 34 5 Location of Radiological Environmental Monitoring Program (REMP) Stations

. Greater than Two Miles From the Site 35 6 Mean Toledyne TLD Gamma Dose 1984 through 1991 Indicator and Background Maan el 7 Mean Toledyne TLD Gamma Dose for 1991 Based on Distance from OCNGS 82 8 Mean Panasonic TLD Gamma Dose for 1991 Based on Distance From OCNGS 83 l- 9 Mean Teledyne and Panasonic TLD Gamma Dose for 1?S1 - Mean Dose in Affected Compass Sector 85 l

10 Weekly Mean Air Particulate Gross Beta Concentrations for 1991 -

Indicator l and Background Mean 88 11 Monthly Mean Air Particulate Gross Beta Concentrations - 1984 through 1991 89 12 Mean Cobalt-60 Concentration in Aquatic Sediment - 1984 through 19.91 95 13 Mean Cobalt-60 Concentration in Clams -

1984 through 1991 96 I

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LI LIST OF FIGURES (Continued)

I FIGURE TITLE PAGE I 14 Mean Cobalt-60 Concentration in Blue Crab - 1984 through 1991 98 15 Exposure Pathways for Routinely Released I Radionuclides from the OCNGS 108 H-1 Locations of On-Site Wells 151 I

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I SUh:aRY AND CONCLUSIONS The radiological environmental monitoring performed during 1991 by the GPU Nuclear Environmental Controls Depaltment 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 I materials to the environment. A radiological environmental monitoring program (REMP) has been established to monitor radiation and radioactive materials in the environment arour.d the OCNGS. The program evaluates the relationship between amounts of radioactive material released in effluents to the environment and resultant cadiation doses to individuals.

Summaries and interpretations of the data were published semiannually from 1969-1985 and annually since 1986 (Ref. 21, 22, 23, 24, and 25). AdditionaA infornation concerning releases of radioactive materials to the environment is contained in the Semi-Annual Effluent Reports submitted to the United States Nuclear Regulatory Commission (USNRC).

During 1991, as in previous years, the radioactive liquid and airborne 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 1991 operations at the OCNGS ranged from 0.00068 percent to a maximum of only 0.508 percent of the applicable regulatory limits. Furthermore, l they were significantly less than dosas received from other j man-made sources and natural background sources of radiation.

Radioactive materials considered in this report are normally l present in the environment, either naturally or as a result of I

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I non-0CNGS activities such as prior atmospheric nuclear weapons testing and medical industry activities. Consequently, measurements made in the vicinity of the site (indicator) were compared to background measurements to determine any impact of I OCNGS operations. Samples of air, precipitation, well water, surface water, clams, sediment, ."sh, crabs, vegetables, and 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 made using thermoluminescent dosimeters (TLDs) in the vicinity of the OCNGS.

I The results of environmental measurements were used to assess I the environmental impact of OCNGS operations, to demonstrate compliance with the Technical Specifications (Ref. 1) and 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 cf the levels of radionuclides and radiation attributable to natural causes, worldwide fallout from prior nuclear weapons tests, and the OCNGS operations.

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

o During 1991, 1751 samples were taken from the aquatic, atmospheric, and terrestrial environments around OCNGS.

A total of 2252 analyses were performed on these samples.

l Five hundred thirty-four (534) direct radiation dose l

l g measureme? ,s using TLDs also were made. Sixty-four (64)

E groundwater samples, including local domestic water

, supplies, were collected and one-hundred ninety-two (192) analyses were performed on these samples.

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

I o Cobalt-60 (Co-60) was detected in sediment samples as a result of OCNGS operations. Although cobalt-60 had been I detected in clams from the Barnegat Bay system in prior study years, this nuclide did not appear in clam samples collected during 1991 and has not been detected since 1987.

I o The predominant radionuclides released in OCNG3 offluents I were xenon-135 in gases and tritium (H-3) in liquids.

Estimated radiation doses to the public, attributable to 1991 effluents, ranged from 0.00068 percent to a maximum of only 0.508 percent of applicable regulatory limits.

o During 1991, the maximum whole body dose potentially received by an individual from liquid and airborne effluents combined was conservatively calculated to be about 0.00708 millirems total. The whole body dose to the Furrounding population from liquid and airborne I effluents was calculated to be 0.222 person-rem. This is approximately 4.5 million times lower than the dose that the total population in the OCNGS area receives from natural background sources.

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INTRODUCTION I Characteristics of Radiation I Instability within the nucleus of a radioactive atom results I in the release of energy in the form of radiation.

is classified according to its nature -

Radiation 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 radioactivity.

Electromagnetic radiations in the form of x-rays and gamma rays have characteristics similar to visible light but are more energetic and, hence, more penetrating. Although x-rays ano 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 l

l their contribution to external radiation exposure.

The rate at which atoms undergo disintegration (radioactive

, %mf varies among radioactive elements, but is uniquely l constant for each specific radionuclide. The term " half-lif e" 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 I radionuclides to millions of years for others. In fact, the natural background radiation to which alJ. mankind has been

'-g exposed is largely due to the radionuclides of uranium, i

B thorium, and potassium. These radioactive elements were

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I 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 has a half-life of 1.3 billion years and exists naturally within our bodies. As a result approximately 4000 atoms of potassium emit radiation internally within each of us every second of our life.

I 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. It represents the radioactivity in one gram of natural radium which is also equal to a decay rate of 37 billion radiation emissions every second. Because of the extremely small amounts of radioactive material in the environment, it is more convenient to use fractions of a curie. Subunits like picoeurie (one trillionth of a curie) are frequently used to express the radioactivity present in environmental and biological samples.

The biological effects of a specific dose of radiation are the same whether the radiation source is external or internal to l

the body. The important factor is how mucn radiation energy

! or dose was deposited. The unit of radiation dose is the rem, which also incorporates the variable effectiveness of l different forms of radiation to produce biological change.

! For environmental radiation exposures, it is convenient to use l the smaller unit of millirem to express dose (1000 millirems equals 1 rem). Wen radiation exposure occurs over periods of time, it is appropriate to refer to the dose rate. Dose rates, therefore, define the total dose for a fixed interval of time, and for environmental exposures, are usually measured with reference to one year of time (millirems per year).

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Sources of Radiation Life on earth has evolved amid the constant exposure to natural radiation. In fact, natural radiation is the single j major source to which the general population is exposed.

Although everyone en the planet is exposed to natural '

radiation, some people receive more than others. Radiation I exposure from natural background has three components (i.e.,

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cosmic, terrestrial, and internal) and varies with altitude and geograpnic 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 less air which acts as a shield. Similarly, terrestrial radiation resulting from the presence of naturally occurring radionuclides in the soil varies and may be I significantly higher in some areas of the country than in others. Even the use of particular building materials for houses, cooking with gas, and home insulation affect exposure to natural radiation.

I 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 cont-ins radioactive potassium. Table i summarizes the common sources of radiation and their average annual doses.

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TABLE 1

g. (Ref 2) g Sources and Doses of Radiation

• Natural (82%) Man-made (18%)

Radiation Dose Radiation Dose Source Imillirems/ year) Source (milliremsf.yrarj Radon 203 (55 %)

Cosmic rays 27 (0%) Medical X-ray 39 (11 %)

Terrestrial 28 (0%) Nuclear Medicine 14 (4%)

internal 40 (11 %) Consumer products 10 (3%)

I Other <1 (< 1%)

(Releases from nat. gas, I phosphate mining, burning of coal, weapons fa!!out,

& nuclear fuel cycle)

APPROXIMATE APPROX! MATE TOTAL 300 TOTAL 63

• Percentage contribution of the total dose 'a shown in parentheses.

I The average person in the United States receives about 300 millirems (0.3 rem) per year from natural background radiation sources. This estimate was revised from about 100 to 300 millirems because of the inclusion of radon gas which has always - been present but has not previously figured 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 millirems per year due to the increase in cosmic and terrestrial radiation I levels. In fact, for every 100 feet above sea level, a person will receive an additional 1 millirem per year from cosmic radiation. In several regions of the world, high concentrations of uranium and radium deposits result in doses of several thousand millirens each year to their residents (Ref. ')

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I Recently, public attention has focused on redon, a naturally occurring radioactive gas produced from uranium and radium decay. These elements are widely distributed in trace amounts in tne earth's crust. Unusually high cor centrations 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 I United States. However, additional surveys are needed to determine the full extent of the problem nationwide. Radon is the largest component of natural background radiation and may be responsible for a substantial number of lung cancer deaths annually. The National Council on Radiation Protection and Measurements (NCRP) estimates that the average individual in I the United States receives an annual dose of about 2,400 millirems to the lung from natural radon gas (Ref. 2). This lung dose is considered to be equivalent to a whole body dose of 200 millirems. The NCRP has recommended actions to control indoor radon sources and reduce exposures.

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

, given radionuclide is also influenced by the quantity and the duration of time that the radionuclide remains in the body, including its physical, biological and chemical l characteristics. Depending on their rate of radioactive decay

! and biological elimination from the body, some radionuclides stay in the body for very short times while others remain for

! years.

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

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I 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 averages about 53 millirems.

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 associated fuel cycle contributes less than 1 millirem to the annual dose of about 300 millirems for the average individual living in the United States.

Fallout commonly refers to the radioactive debris that settles to the surface of the earth following the detonation of nuclear weapons. It is dispersed throughout the environment either by dry deposition or washed down to the earth's surf ace by rain or snow. There are approximately 200 radionuclides I 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 f allout radiation exposures to humans are iodine-131 (I-131), strontium-89 (Sr-89),

cesium-137 (Cs-137) , and strontium-90 (Sr-90) . Tnere has been no atmospheric nuclear weapon testing since 1980 and many of I the radionuclides have decayed significantly. Consequently, doses to the public from fallout have been decreasing.

As a result of the nuclear accident at Chernobyl, USSR, on April 26, 1986, fallout was dispersed throughout the environment and detected in various media such as air, milk, l and soil.

lI l }]aclear Reactor ODerations l-I Common to the <'ammercial production of electriciti is the consumption of fuel which produces heat to make steam which lI turns the turbine-generator which generates electricity.

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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 tha form of uranium onide.

The fuel produces power by the prccess called fissien. 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 I- fissio4 products, along with heat, radiation and free neutrons. The free neutr( is 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 -

I via reactor coolant water - from the fuel to produce steam which drives a turbine-generator to produce electricity. The fission products are mostly radioactive: that is to say they are unstable atoms which emit radiation as they change to stable atoms. Neutrons which are not absorbed by the uranium fuel may be absorbed by stable atoms in the materials which make up the components and structures of the reactor. In such cases, stable atoms of ten become r .oactive. This process is called activation and the radioactive atoms which result are called activation products.

I-l The OCNGS reactor is a Boiling Water Reactor (BWR). The

l. 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 l 1, cooling water boils within the reactor vessel producing steam for use in the turbine, After the energy is extracted from the steam in the turbine, it is cooled and condensed back l -

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

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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 I radioactive materials produced by the fission reaction 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.

I 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 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 otber volatile radionuclides collect and are contained.

-s The primary coolant water is the third barrier. Many of the 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 in the reactor coolant purification system. However, krypton l

and xenon do not readily dissolve in the coolant, particularly at high temperatures. Krypton and xenon collect as a gas above the condensate when the steam is condensed.

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1 The fourth barrier consists of the reactor pressure vassel, turbine, condenser, and associated piping of the coolant system. The reactor pressure vessel is a 63-foot high tank with steel walls about nine inches thick. It encases the reactor core. The remainder of the coolant system includes the turbine and condenser and associated piping. This system provides containment for radioactivity in the primary coolant.

I-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 loops.

I The reactor building provides the sixth barrier. It is a reinforced concrete and steel superstructure which is always maintained at a negative pressure.

Sources of Licuid and Airborne Effluents Although the previously described barriers contain radioactivity with high e f ficier.cy , small amounts of radioective fission products are nevertheless able to dif fuse

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! 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 i chemical properties of noble gas fission products in the l

primary coolant prevent their removal by the demineralizers.

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I Because the reactor system has n.any valves and fittings, an 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, I and/or Turbine Pulldings. The noble gases become part of the gaseous wastes 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 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 recomb!ner, removes the water (vapor) from the process stream, holds up the process stream to allow further decay of short-lived nuclides, and filters the off-gas using charcoal beds and High Efficiency Particulate (HEPA) filters prior to discharge to the base of the stack.

I Once the process stream enters the stack, it is diluted by building ventilation, which averages 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, I demineralization, and distillation. Purified radwaste water is recycled to the plant. Occasionally, it is necessary to discharge this purified water to the environment.

Contaminants removed during the purification process are disposed of via the radioactive solids disposal systems. When purified water is discharged to the environment, it is first I

14

~

sampled, analyzed, assigned a release rate, and then released to the discharge canal which has a flow rate of 460,000 to 960,000 gallons per minute.

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nest;g" npN OF TE OCFGS SITE General Information The Oyster Creek Nuclear Generating Station is located in Lacey Township of Ocean County, New Jersey, about 60 miles south of Newark, 9 miles south of Toms River and 35 miles I 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 wcst. 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 I- 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.

I.

It is estimated that approximately 3.3 million people reside

-within a 50 mile radius of the station (Ref 4). The nearest population center is Ocean Township (population 3731) which lies less than two miles south-southaast of the site. Two miles to the north, 14,161 people reside in Lacey Township.

Dover Township, situated 9.5 miles to the north, is the nearest major population center with a population of 61,287.

I 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 I 16 I

I occurs during the summer. This influx occurs almost exclusively along the waterfront.

Climatolocical Summary Meteorological data for 1991 were obtained from an on-site weather station. Data were routinely quality assured and categorized for further analyses, including historical comparisons to both on-site and off-site sources.

Wind direction frequencies, in general, were climatologically average, with winds occurring most frequently from the western sectors and the southwest. Seasonal winds were evident, including the summer sea breeze flow (Ref. 20). Northwest winds occurred somewhat less of ten during the winter months of 1991 than in past years and a mild winter was the result.

-In part, due to the mild winter, the average temperature was approximately 1.5 degrees higher in 1991 than in previous years. Higher than average temperatures were recorded in eleven of the twelve months.

I Precipitation totals varied greatly from month to month (Fig. 2). The 1991 yearly total was 43.2 inches which was approximately 2 inches more than the Atlantic City National Weather Service historical average (1946-1981) . Approximately 18 percent of the OCNGS yearly total fell in less than one day when 7.69 inches of rainfall was recorded on July 13, 1991.

During this event, 1.38 inches of rain fell in a fifteen minute period.

I For additional site specific meteorological data, refer to the OCNGS Semiannual Effluent Release Reports for 1991.

I 17 l'

m m m m M M M M M M M M m m m m m M MONTIILY PRECIPITATION.

' OYSTER CREEK NUCLEAR GENERATING STATION

DURING 1991 COMPARED HTill IIISTORICAL (1946-1981)

ATLANTIC CITY NATIONALWEATilER SERVICE AVERAGE PRECIPITATION DATA

< RAINFALL IN INCIIES hionth Oyster Creek Atlantic City l NGS NWS Avg.

MONTIILY PRECIPITATION FOR Jan 5.17 3.5 Feb 0.88 3.2 Mar 5.83 3.8 ATIANTIC CITY IllSTORICAL Apr 3.96 33 .

AVERAGE (1946-1981)

May 1.10 3.4 Jun 2.01 2.7 10 - 0 OvSTER Jul 8.79 4.1 ,

Aug 5.17 4.6 9 CREEK NGS

~

Sep 2.74 2.8 $

8 E ATLANTIC g y Oct 2.48 2.9 CITY Nov 1.17 3.7 7- g Dec IU N 3.91 3.5 y u DAILY RAINFALL IN EXCESS OF ONE INCII PER DAY 5 -

Date Total 15-Min Event 4 _ ,

p

! s P n 3~ f 11-Jan-91 1.52 0.07 Low pressure (NE storm)

, j  ; p 2-Mar-91 1.23 0.53 Warm front convection '

((

3-M ar-91 1.51 0.25 low pressure (NE storm) 2f 1

=

g j I~

21-Apr-91 1.54 ON, Low pressure (NE storm) f j q y ,

13-Jul-91 7.69' 138* Warm front convection 0

,  ; ':  :  : U i --

d i E b b:

19-Aug-91 2.79 0.29 11urricane Bob gi t; &Q 5 Ei go @t E; 8

• ^

20-Aug-91 1.79 031 Cold front passage 10m 17-ON-92 1.79 0.24 Low pressure (NE storm) 29-D;c-92 1.16 0.12 low possure (NE storn.)

• Denotes record rainfall amount.

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EFFLUENTS Historical Background Almost from the outset of the discovery of x-rays in 1895 by Wilhelm Roentgen the potential hazard of ionizing radiation I was recognized and efforts were made to establish radiation protection standards. The International Commission on Radiological Protection (ICRP) and the National Council on Radiation protection and Measurements (NCRP) were established in 1928 and 1929, respectively, and have the longest continuous experience in the review of radiation health effects and with recommendations on guidelines for radiological protection and radiation exposure limits. In 1955, the United Nations created a Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) to summarize reports I received on radiation levels and the effects on man and his environment. The National Academy of Sciences (NAS) formed a committee in 1956 to review the biological effects of atomic radiation (BEAR). A ser3es of reports have been issued by this and succeeding NAS committees on the biological effects of ionizing radiation (BEIR), the most recent being 1990 I (known as BEIR V).

formed in 1959 to provide a federal policy on human radiation The Federal Radiation Council (FRC) was exposures. These federal policies are approved by th' President of the United States.

These committees and commissions of nationally and internationally recognized scientific experts have been dedicated to the understanding of the health effects of radiation by investigating all sources of relevant knowledge and scientific data and by providing guidance for radiological protection. 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, 19

I 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 recommendations of the ICRP, the NCRP, and the FRC (incorporated in the United States Environmental Protection Agency in 1970) for basic radiation protection standards and guidance in establishing regulations for the nuclear industry I (Ref. S through 8).

Effluent Release Limits As part of routine plant operations, limited quantities of radioactivity are released to the environment in liquid and I airborne effluents. An effluent implemented to ensure radioactivity released to the control program is environment is minimal and does not exceed release .imits.

Radioactive effluent releases at Ofster Creek are under the regulatory jurisdiction of the USNRC. Regulations through the years have changed and reflect operating experience and advances in nuclear technology. Federal regulations as defined by Title 10 of the Code of Federal Regulations, Part 20 (10 CFR 20) establish limits on the concentrations of I radioactive effluents released to the environment.

effluent limits are set at low levels to protect the health Federal _

and safety of the public. GPU Nuclear conducts operations in a manner that holds radioactive ef fluents to small percentages of the federal limits.

A recommendation of the.ICRP, NCRP, and FRC is that radiation exposures should be maintained at levels which are "as low as reasonably achievable" (ALARA) and commensurate with the I societal benefit derived from the activities resulting in such exposures. For this reason, dose limit guidelines were established by the USNRC for releases of radioactive ef fluents from nuclear power plants. These guidelines are presented in the Oyster Creek Technical Specifications. Maintaining I

20 I

releases within these operation guidelines demonstrates that radioactive effluents are being maintained "as low as reasonably achievable".

The Oyster Creek Technical Specification dose limit guidelines are as follows:

I-. o Technical Specification 3.6.K.1 The dose equivalent rate outside of the EXCLUSION 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.

I o Technical Specification 3.6.L.1 The air dose outside of the EXCLUSION AREA due to noble gas released in gaseous effluent shall not exceed:

5 mrad / calendar quarter due to gamma radiation, 10 mrad / calendar quarter due to beta radiation, 10 mrad / calendar year due to gamma radiation, or 20 mrad / calendar year due to beta radiation, o Technical Specification 3.6.N.1 The annual dose to a MEMBER OF THE PUBLIC due to radiation and radioactive material in effluents from the OCNGS outside of the EXCLUSION AREA shall not exceed 75 mrem to his thyroid or 25 mrem to his total body or to any other organ.

o Technical Specification 3.6.K.2 The dose equivalent rate outside of the EXCLUSION I_ AREA due to H-3, I-131, I-133, and to radioactive l

21 I

I 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 more than 3 months and the dose rato due to other radionuclides is averaged over no more than 31 days.

o Technical Specification 3.6.M 1 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, and from radionuclides in particulate form having half-lives of 8 days or more in gaseous effluents, outside of the EXCLUSION AREA shall not exceed 7.5 mrem to any body organ por calendar quarter or 15 mrem to any body organ per calendar I year.

o Technical Specification 3.6.I.1 The concentration of radioactive material, other than noble gases, in liquid effluent in the discharge canal at the Route 9 bridge shall not -

exceed the concentrations specified in 10 CFR Part 20, Appendix B, Table II, column 2.

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o Technical Specification 3.6.I.2 The concentration of noble gases dissolved or entrained in liquid effluent in the discharge canal at the Route 9 bridge shall not exceed 2 x 10-4 microcuries/ milliliter.

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, 22 1 _ - - _ - - _ - _ - - - _ - - - - - - - - - - - - - - -

d ' - - - - -

I o Technical Specification 3.6.J.1 The dose to a MEMBER OF THE PUBLIC due to radioactive material in liquid effluents beyond the outside of the EXCLUSION AREA shall not exceed:

1.5 mrem to the total body during any calendar I quarter, 5 mrem to any body organ during any calendar quarter, 3 mrem to the total body during any calendar year, or 10 mrem to any body organ during any calendar year.

Ef fluent Control Proc 7 ram Effluent control includes plant components such as the ventilation system and filters, off gas holdup components, demineralizers, and an evaporator system. In addition to minimizing the release of radioactivity, the ef fluent control program includes all aspects of effluent and environmental monitoring. This includes the operation and data analysis associated with. a complex radiation monitoring system, I environmental sampling and monitoring, and a comprehensive quality assurance program. Over the years, the program has evolved in response to changing regulatory requirements and plant conditions. For example, additional instruments and samplers have been installed to provide that measurements of l effluents remain onscale in the event of any accidental release of radioactivity.

l l Effluent Instrumentation: Liquid and airborne effluent i

measuring instrumentation is designed to detect the presence 1

l and the amount of radioactivity in effluents. Many of these instruments provide continuous surveillance of radioactivity releases. Calibrations of effluent instruments are performed 23 lI

I using reference standards certified by the United States National Institute of Standards and Technology. Where continuous survei] lance is not practicable or possible, contingenci.es are spelled out in the Technical Specifications.

If pre-designated setpoints are reached, releases are immediately terminated.

Effluent Samnlina and Analysis: In addition to continuous radiation monitoring instruments, samples of effluents are taken and subjected to laboratory analysis to identify the specific radionuclide quantities being released. A sample must be representative of the effluent from which it is taken.

Sampling and analysis provide a sensitive and precise method I of determining effluent composition. Samples are analyzed using the highest quality laboratory counting equipment.

Radiation instrument readings and sample results are ccmpared to ensure correct correlation.

Effluent Data As part of routine plant operations, limited quantities of radioactivity are relea.med to the environment in liquid and I airborne effluents.

vary and are dependent The amounts of radioactivity released in operating conditions, power levels, fuel condition' afficiency of liquid and -gas processing systems, and p1 :er functioning of plant equipment.

The largest variations occur in the airborne effluents of fission and activation gases which are proportional to the augmented off gas system operation in the gas processing system and to the integrity of the fuel cladding. In general, effluents have been decreasing with time due to improved fuel I integrity and increased efficiency of processing systems.

With respect to activity released during 1991, the predominant radionuclide was Xe-135 in gases and H-3 in liquids. The amount of rcdioactivity released is summarized and reported 24 I

I semiannual'y to the USNRC. Estimai'd radiation doses to the public, attributable to those offluents, were Icos than one percent of the applicable regulatory limita (Tables 6 and 7) .

A summary of the OCNGS liquid and airborne effluents for 1991 I is provided in Table 2. Radioactive constituents of those effluents are discussed in the following occtions.

Noble Gases: The predominant radionuclides released in airbotme ef fluents are the noble gases krypton (Kr) and xenon (Xo). Small amounts are also released in liquid effluents.

The total amounts of krypton and xenon released into the atmosphere in 1991 were 241 curies and 219 curlea respectively. These noble gases were readily dispersed into I the atmosphere when released and because of their short half-lives, quickly decayed into stable forms. The total quantity of xenon activity released in liquid effluents was 0.016 curies.

Iodines and Particulates: The discharge of iodines and particulates to the environment is minimized by factors such as thenr high chemical reactivity and solubility in water combined wit) the high removal officioicy of airborne and liquid procer sing systems.

of he gaseous radioiodines, iodine-131 is of particular concern becaune of its relatively long half-life of 8 days.

Particulates of relative concern are the radiocesiums (Cs-134 and Cs-137), radiostrontiums (Sr-89 and Sr-90), and activation products, manganese-54 (Mn-54) and cobalt-60 (Co-60). The total amount of iodines and particulates released from the station in 1991 was 0.21 curies in airborne effluents and 0.00016 curies in liquid offluents.

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Tritium: Tritium is the predominant radionuclide released in liquid effluents and also u oleased in airbort,w effluents.

l Tritium is a radioactive isotope of hydrogen. It is produced 25

(

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TABLE 2 I RADIOL 4UCUDE COMPOSITION OF OCNGS EFFLUENTS FOR 1991 Uquki Effluents (Ci) Paseous Effiuents (Ci)

OCNGS OCNGS I

Radionuclide _ , _ Hatf.Ufe 0.03 E 1 7.G4 H-3 12.3 years ND 2.40 E 2 Ar-41 i.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 27.8 days ND 7.19 E-5 Cr Si 312 days ND 1.30 E4 1

Mn-54 5.3 years 1.34 E 4 1.25 E4 Co-00 ND 3,71 E1 Kr-85m 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> I Kr-87 76 minutes ND ND 1.17 E2 8.73 E1 Kr48 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 50.5 days ND 5.51 E 3

_St89 28.8 years ND 2.15 E 5 St 00 __

I Tc@9m G.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 8.0 days ND ND 8 84 E-3 2.55 E 2 l131 I Xo-131m 11.8 days 20.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> ND F:

2.72 E1 8 73 E 2 l133 I Xe 133 5.2 days 6.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />

/ >>

N' 1 a 5.76 7.74 E 2 l135 I Xo-135 9.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 30.2 years 1.42 E 2 2.68 E 5 186 E2 4.44 E 5 Cs 137 12.8 days ND 1.10 E-3 Ba 140 32.5 days ND 4.24 E 7 Co 141 2B4 days ND 1.55 E-6 Ce 144 ND 1.82 E 5 Gross Alpha - ,

Note: All effluents expressed in scientific notation.

ND - Noctw Detected I

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I in the reactor coolant an a result of neutron interaction with the naturally-occurring douterium (also a hydrogen isotope) present in water. The total amount of H-3 released in liquid and airborne effluents was 8.24 curies. To place this number in port.pective, the world inventory of natural cosmic ray produced tritium is 70 million curies, which corresponds to a production rate of 4 million curies per year (Ref. 9).

I Tritium contributions to the environment from nuclear power production are sufficiently small that they have no measurable effect on the existing environmental concentrations.

Transuranica: Transuranics are produced by neutron capture in the fual, and typically omit alpha and beta particles as they I decay. Important transuranic isotopen produced in reactors are uranium-239 (U-239), plutonium-238 (Pu-238) , plutonium-239 (Pu-239), plutonium-240 (Pu-240), plutonium-241 (Pu-241),

americium-241 (Am-241), plutonium-243 (Pu-243), plus other isotopes of simericium and curium. They have half-lives ranging from tons to millions of years. Transuranics are a mostly retained within the nuclear fuel. Because they are so insoluble and non-volatile, they are not readily transported through plant pathways to the environment. Gas and liquid processing systems remove greater than 90% of any transuranics I outsida the reactor coolant. Since greater than 99% of all transuranics are retained within the fuel and transuranic removal pror sses are extremely efficient, releases in airborne and liquid effluents are not monitored.

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 and nitrogen. Estimates for all nuclear power production worldwide show that 235,000 I curies were released from 1970 through 1990 (Ref. 10).

Carbon-14 also is produced naturally by the interactions of cosmic radiation with oxygen and nitrogen in the upper I ,

1

atmosphere. The worldwide inventory of natural C-14 is estimated at 241 million curies (Ref.10) . Since the inventory of natural carbon-14 is so large, releases from nuclear power plants do not result in a measurabic change in the background concentration of carbon-14. Consequently, carbon-14 is not routinoly monitcred in plant nffluents.

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I RADIOLOGICAL ElfyIRONMENTAL_ MONITORING GPUN conducts a comprehensivo radiological environmental monitoring program (REMP) at Oyster Crook to monitor radiation and radioactivo materials in the environmont. This program provides information on radioactivity in the environment from I OCNGS releases and information on the potential principal pathways of exposure to humans.

The USNRC has established regulatory guidos which contain acceptable monitoring practicos (Ref.11) . The OCNGS REMP was designed on the basis of those regulatory guidos along with the USNRC Radiological Assessment Branch Technical Position on I Environmental Monitoring (Ref. 12). All of those guidelines have been mot and in most casos the OCNGS program greatly exceeds them. The important objectivos of the REMP are:

o to assess impacts to the public from oCNGS operatiens l o to verify in-plant controls for the containment of radicactive materials o to determine buildup of long-lived radionuclidos in the environment and changes in background radiation l levels 1

o to provide reassurance to the public that the program is capable of adequately assessing 4.mpacts and identifying noteworthy changer in the radiological status of the environment.

I I 29 .

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I IRY_ir9DR2atal _fRDEure PatitvAya_to llumana from Airiprnp and Licuid Effluenta I Environmental transport pathways is the term for movement of 1

radionuclidos through the environment and transport to humans.

The airborno pathways have basically fivo routes of importance (1) direct radiation, (2) deposition on I vegetation, (3) deposition on soll, (4) consumption by animals and (5) inhalation by humans. Liquid pathways have three basic routes of importances (1) ingostion cf drinking water, (2) fish and shellfish consumption and (3) oxposure from shorelin9 sedimonts. Each of those possible routes that can load to radiation exposure to humans is tormed an exposure i

pathway. As can be soon, those routes are b;. numerous and varies. While some pathways are relatively simplo, such an inhalation of airborno radioactive materials, others may be complex. For examplo, radioactive airborno particulatos may deposit onto forage which when oaton by cows may be secroted into milk, which is subsequently consumed by man. This is known as the air-grass-cow-milk pathway.

I Although radionuclidos can reach humans by a number of I pathways, some are more important tnan others. The critical pathway for a given radionuclido 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 ago, dietary, or other cultural factors. The dose may be delivered to the wholo body or confined to a specific organ; the orgcn receiving the greatest fraction of the dose is known as the critical organ.

This information was used to develop the Oyster Creek program.

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LI Samplina The OCNGS radiological environmental monitoring program consists of two phases -- the preoperational ar:d the I operational. The preoperational phase provided data which is used as a basis for evaluating increases in radiation levels and radioactivity in the vicinity of the plant af ter the plant I became operational. The operational phane began in 1969 when the OCNGS began power generation.

The program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and interpreting the results. With I emphasis on the critical pathways to humans, samples from the aquatic, atuospheric, and terrestrial environments are collected. These samples include air, precipitation, well water, surface water, clams, sediment, fish, crabs, vegetables, and soil. Thermoluminescent dosimeters (TLDs) are placed in the envaronment to measure gamma radiation levels.

The Technical Specifications and recommendations from the scientific staff of GPUN specify the sample types to be collected and analyses to be performed.

Sampling locations were established by considering meteorology, population distribution, hydrology, and land use characteristics of the local area. The sampling locations are divided into two classes, indicator and background. Indicator locations are those which are expected to show effects from OCNGS operations, if any exist. These locations were 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 ';1 ant, the I background stations are generally at distances greater than 10 miles from the OCNGS. Therefore, background samples are collected at locations which are expectnd to be unaf fected by i

31 I

I station operations. They provide a basis on which to evaluate fluctuations at indicator locations relative to natural background radiation and natural radioactivity and fallout from prior nuclear weapon tests. Figures 3, 4, and 5 show the current sampling locations bround the OCNGS. Tabic A-1 in Appendix A describes the sampling locations by distance and azimuth (compass direction) from the OCNGS.

I Analysis I In addition to specifying the minimum media to be collected and the minimum number of sampling locations, the Technical Specifications also specify the frequency of samp2e collection and the types of analyses to be performed Additjen311y, analytical sensitivities (detection limits) and reporting levels also are specified. Table A-2 in Appendix A provides a syriopsis of the sample types, number of sampling locations, collection frequencies, number of samples collected, types of analyses and frequencies, and number of sampics analyzed.

Table A-3 in Appendix A presents problems encountered during 1991 in sample collection and analysis. Sample analyses which did not meet the required analytical sensitivities are presented in Appendix B. Changes in sample collection and I analysis are described in Appendix C.

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

All analytical results are subjected to an automated review process which ensures that Technical Specification-required lcwor limits of detection are met and that reporting levels are not exceeded. Investigations are conducted when anomalous (gm l

values are discovered.

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I Iecation ofItadiological Emimamental Monitoring I'mgmm OtEMP)

Stations greater than 2 mihw fmm Ole site l

i 3s 1 _ _

Table 3 provides a summary of radionuclido concentrations in environmental samples from the OCNGS in 1991. The data are summarized in a format that closely resembles the suggested format presented in the USNRC Branch Technical Position (Ref.

12).

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

Analytical laboratories utilized for the OCNGS REMP uso state-of-the-art laboratory equipment designed to detect beta ard gaama radiation. This equipment must meet the required analytical sensitivities. Examples of the specialized laboratory equipment used are germanium detectors with I multichannel analyzers for determining specific gamma emitting radionuclides, liquid scintillatio' letectors f or tritium, low level alpha and beta counters, anu 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 discussed in more detail in references 13, 14, and 15 and are also described in Appendix I.

Ouality Assurance Procrajn I

A quality assurance program is conducted in accordance with guidelines provided in Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs" (Ref. 16) and as required by the Technical Specifications. The OC program is documented by GPUN written policies, procedures, anL records. This 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 Il I 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 media is implemented by:

36 L_

I  !

o auditing analytical laboratories o requiring analytical laboratories to participate in the USEPA Cross-Check Program o requiring analytical contractor laboratories to split sampics for separate analysis (recounts are performed when samples are not able to be split) o splitting samples, having the samples analyzed by I independent laboratories, and then comparing the results for agreement o requiring analytical laboratories to provide quality assurance reports showing laboratory instrument calibration and maintenance tests and results of blind, split, and duplicate analyses I The quality assurance program and the results of the USEPA Cross-Check Program are outlined in Appendices D and E, respectively.

Procedures were written and approved by the Oyster Creek Environmental Controls Department, the Quality Assurance Department, and analytical laboratories to cover all aspects of the radiological environmental monitoring program. These procedures cover such areas as sample collection, sampling I equipment calibration and maintenance, laboratory analysis, and data review.

I I

I I

l I 37 lI

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M M M M E E E E E E E E E E TABLE 3 . . ,

,-f -

RADIOtDGICAL ENVIRONMIM AL MONTTORLNG PROGRAM

SUMMARY

j OYSTER CREIINtJCIEAR GCNERATING STAT 10N l

• - " JANUARY,1891 TIIROUCII DECINBER,1991 -

UIE FOLLOWING PAGES ARE A

SUMMARY

OF REMP DATA FORTitE SCIIEDULED COllECIlON PERIOD JANUARY,1991111ROUGII DECEMBER,199L DATA ARE StJMMARIZED ON AN ANNUAL BASIS, WIIERE:

SAMP11 TYPE-> Media teing anaryred.

ANALYSIS -> Type et analysis beir g gerformed on the perticular medn.

1. OF ANALYSES PERIVRMED -> The total number of analyses performed for a particular sample type.

11D -> De mean lower lewl of detecten. I1 ease note that tids value is based on sarrples whose results showed no detectabk activity.

INDICATDR STAT 10NS -> The spean, mimmum and max: mum teed on detectable actinues of all indrator stations-IIaGIIEST ANNUAL MEAN -> The mean, minimum and maximum baud om detectable actmeies of the station with the bqrhest annual mean.

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

IIAGGROUND STAT 10NS -> The mean, minimum and maxarnum based on detectable actmties of att twkground statnns.

r (N/ TOT)-> The fracton of detestable activitiesfrotal number o analvves performed.

IMCKGRot N9 STATIONS ATOCNGS STATION A C.II,14 38,44 18 36 SAMPLE TYPE AIR PART1CUIATE SEDIMENT WELL WATER STIGITABtf5 AIR IODINE CIAMS SOIL PRECIITTAT10N SUFFACE WATER ITSII**

DLUE CRAR**

• An asterisk (*) indates no data.

• • Station 94 only 3R

M M M M M M m m e m m m W W M M M M TAB 12 3 -

.. RADIO 1DGICAL MTRGVM6fAL MONTIDRING PROGRAM

~

OnTEM CREFX NUC1 EAR GEM ENATING STATION -

JANUARY.1Mt THROUGH DECEMBER,1M1 ANNUsLSt:MMARY 1 INDICATUR STATIONS - HIGHESTANNUALMEAN . BACKGROUNDSTATIONS -

r SAMPII. ANALWIS - NUCUDE # OF - 11D :

ANA1. MIN : _ MEAN LMAX: _.( N/IUT) MIN MEAN . mar l (N/ TUT) MIN MEAN . Mir . (N/ TUT)

! GTE D _

PERF. - $narien4 -

AIR

• 674 NollD 6.70tM3 1.60tM2 3.10tM2 (467/47) 9.201343 1.67FA2 3.10tM2 ($2/52) 6.MM3 1MIM2 2.90FA2 (207/207)

PAR 11C LA111 Grms Beta Statam-d 4 (pO/m3) Reported AIR <LLD 936FA3 < llD <11D < llD (0/117) + LLD < t1D < LID (0/13) < TID < flD (0/52)

PAR 11CUIA111 Gamma Scan Ac-228 169 (rO/m3)

I AIR < 11D <IlD 196EM2 <11D < IlD <IID (0/117) < 11D < 11D < 11D (0/D) <IID (0/52)

P/.RTICUIAlli Gamma Seaa Ba-140 169 (PG/m3)

AIR 3 001M2 3.201M2 8.21tM2 120tW1 (117/117) 5.101W2 8.71FA2 12E41 (13/13) 510FA2 8 011'-02 L20FA1 (31/52)

PAR 11CUIA1TI Gamma Scan De.7 169 Matum-# 71 (pO/m3)

MR <11D < 11D

< 11D <LLD < 11D (0/I17) < LID <11D < IJD (0/13) <IlD (0/$2)

PARTICULA 11! Gamna Scar. Co-58 169 2.8IIM3 (pCi/m3)

AIR < TID

< 1lD < 11D < IID (0/117) <LLD < llD <11D (0/13) <ILD < tlD (0/$2)

PAR 11CULAT11 Gamma Scan Co#4 169 3.331M3 (pCi/m3)

MR <IlD <11D (0/$2) 2 tCIM3 < L1D < 11D < 11D (0/117) < IlD <LLD <11D (0/13) < eld PAR 11CUIA111 Gamma Scan Cs-134 169 (pO/m3) 39

m e e m e m W W W W W m m M m m W 'm TABE 3-RADIO!IEh ENVIRONMENTAL MONITORING F5tOGRAM -

OYSTER C1tEEK NtX1Eut CENDIATING STATION -

' JANUARY.1991TRitOUGH DECEMBEst,1991 ANNUAL SLNMARY '

'UD _INDICATUR STATIONS HIGUESTANNUALMTAN . RACKGIRODSTATIONS -

SAlbM - ANAI.TS19." NUCUDE a OF-MEAN' . MAY - (N/IUT) .. MIN ' MEAN MAX. (NftUT) '* IN MEAN MAX - (N/IVO M7b l - " ANA1. " MIN . '

% /PERP. Sawlo a AIR (

< TID < 11D < llD <llD (0/13) < IlD < LID < 11D (0/52)

PART1CUIATE Gamme Scan Cs-137 169 2.37E.03 < 11D < TID (0/117) l (pG/m3) l AIR < 11D <UD

<UD < t3D <uD '0/11M <11D <11D < 11D (0/13) <IID (0/52)

PART1CUIATE Gamma Scan l'e-59 169 4L96E43 (pCi/m3)

AIR 169 9.95F 03 < 1lD < llD  %.l.D (0/117) <llD <UD < TID (0/13) <UD < flD < !lD (0/52)

PARTIC11 ATE Gamma Scan I-131 (pG/m3)

AIR < TID <uD <11D 3.61EM2 1.60fM2 1.60fM2 1#fM2 (1/117) 1.60F4 160fM2 1.60E42 (1/13) (c/32)

PART1CULATE Gamma Scan K-40 169 Stations 20 (pCi/m3)

AIR < tlD <!l1# (C/52)12-140 169 109EJC <UD < 1lD <11D (0/117) < tlD <11D <!1D (0/13) < tlD PAR 11CUIATE Gamma Scan (pG/m3)

AIR <IID <IlD 2360 43 <UD <IID <11D 10/117) < llD < IID <UD (0/13) < 11D (0/52)

PART1CULATE Gamma Scan Mn-54 169 (pC/m3)

AIR <t1D <UD < 11D (0/52)

Nb-95 169 33E43 <1lD < llD < TID (0/117) < t1D <UD < 11D (O '13) f PAR 11CUIATE Gamma Scan (pO/m3) 40

E E E E E E E E E O E E M M E E

TABIJt 3 .

RADIOEDCICAL ENV1810MMENTAL MONITORINC PROGRAM -

OYSTERCREEK NUC1 EAR CP:NERATING STATION '

. JANt!ARY. .Mt THROUGH DECEMBER.1*P1; .

( mut.stwARv INDICATDR STA110NS - HIGHESTANNt:ALMEAN MCKGROGD STATIONS SAMPIE i ANALYST $ -. NUCllDE - # OF ' ilD : ,

i TITE '

- MIN - ' MEAN . MAX (N/rorr) ~ ~ MIN -. ~ MFAN ? M4% L (N/ TOT) MIN MEAN MAX (N/'MPT)

ANat. f ,

rtRt. =[ Seanon-e AIR Ra-226 169 1.04FA2 2.40fic3 2.40FA3 2AE03 (t/117) 1AXMJ3 140FA3 140GC3 (1/73) < 11D 'LD <1lD (0/32)

PARTICUIATE Gamma Scan Station-# 73 (pCi/m3)

AIR 7345 169 7.43FA3 <11D < llD < 11D (0/117) < 11D < IlD <IID (0/13) <IID < IlD < llD (0/$2)

PARTICUlf.1II Gamma Scan (pG/m3)

AlR 4.94FA3 <UD <UD <IlD (0/117) <11D <LLD <11D (0/13) < LtD <11D <11D (0/32)

PART1CUIAll! Gamma Scan Zr-95 169 (ro/m3)

AIR <111, 674 LW <UD <IID < LID (0/467) < IID <IID <11D (0/52) < IlD < IlD (0/20')

toDINE todme-131

(;Ci/m3) 24 IME + 02 IEE + 02 1.7JE + 02 1RE + 02 (3/12) IRE +02 1 RE+02 .JIDE +02 (1/4) 1RE + 02 tvE + 02 2.50f!+ 02 (5/12)

PRECtlTTAT10N Trnam Sta+wn-s 73 (pG/L) 129E + 01 <11D <UD <11D (0/12) < llD < IlD <11D (0/4) <11D <IID < ilD (0/12)

FREGITTAT10N Gamma Scan Ac-228 24 (PG/L) 24 1.42E + 01 <11D < 11D < TID to/12) < t1D < LID < 11D (0/4) < TID < LI D < llD (0/12)

PREGITTAT10N Gemma &sa 11a-140 (pCi/L) 2.59E + 01 1R+01 1.20E+01 L20E*01 (1/12) IM +01 1.20E+01 Il0E+01 (1/4) 120E +01 120E + 01 2M +01 (1/12)

PREOPsTAT10N Gamma Scan Be-7 24 Seatsm-4 72 (pG/t )

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. JANUAK$ IW1 THROCGli DECEMSDt,1991 ANWAL SUMhtotY HIGHDTT ANNUAL MEAN BACKGROUND STADONS

. SAMPIE . ANALYSIS : NUCUM . . # OF,,

11D f .

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TYPE- .ANAC ' .~ MIN 3 : MEAN : MAX ' (N/1UT) - MLN N MEAN - MAX '. '(N/IUT) f M3- L MEAN ' MAX . '(N/ TUT)

~ Seselon #

PERP.

3.40E &00 <llD <llD < 11D (0/12) < tlD <11D <11D (0/4) <UD < IlD <UD (0/12)

PRECTITATION Gamma Scan Nt*-95 24 (PG/L)

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PRECIPITATION Gamme Scan Ra @ 24 2.20E + 01 (PG/L)

<LLD <IID (0/12) <11D <UD 11D (0/4) < ILD < IlD <!1D (0/12)

PREOrrTAT10N Gamma Scan Zn45 24 9.33E + 00 < llD (pO/L)

< llD < llD < 11D (0/12) < 11D < TID <llD (0/4) < t1D < !lD <UD (0/12)

PREOPTTATION Gamma Scan Zr 95 24 5.75E + 00 (po/L) 1.90E+02 L900+02 L90E+02 (1/13) < tlD < t1D < I1D (C/26)

SURFACE WATER Trrtium 404 136E + 02 1.70E + 02 18E + 02 190E + 02 (2/B)

Statsm-d 32 (pCi/L)

< 11D < Ls.D < 11D (0/78) <UD <11D <11D (C/13) <UD < tlD <UD (0/26)

SURFACE WATER Gamma Scan Ac-22s 104 1.17E + 01 (PG/L)

< 11D (np8) <11D <UD < tlD (0/13) < TID <LLD < 11D (0/26)

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<LLD <LLD < TID < flD (0/13) < !1D < t1D <UD (0/26)

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(PG/L) i

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-TABLE 3 ~

MDiotDCICAL ENVIltOMMENTAL MONITORING F9eoCMM -

OYSTTI CREEK MUCLEAR GENEftATING STA110N

.'; JANUARY,1991T1fROUGH DECEMBER 1991 j

~ AW1AL

SUMMARY

IJD - - INDICAIDR STATIONS -- tilG1113TANNUAI,MEAN ' E4CKGRDOD STATIONS

.- SetFLE - ANALYSI$ D NUCL1DE # OF TYPE; .ANA1.i - MIN ~ MEAN " 1 MLY t ' (N/IUT) ; MIN , ML4N _ . MAX ' (N/IUT) MIN MEAN MAX' (N/IUT)

PERP. sesense-a 4 35'i+ 00 < LID < 11D < 11D (9/51) < 11D <llD < LID (0/13) <11D <11D <LLD (0/13)

WEliWATER Gemma Scan Cs-134 64

(;Ci/L) 64 3.16E + 00 <11D < LID <11D (0/51) < 11D < 11D < 11D (J/13) <UD <IID <IID (0/13)

Will WATER Gamma Scan Cs-137 (rCi/L) l 6.75E + 00 <UD <11D < t1D (0/51) < t1D < t1D < llD (0/13) <LLD < TID <11D (0/11)

WELL WATER Gamma Scan l'e-59 64 (PCi/L) l 64 7ME + 01 < L1D <11D <llD (0/51) < TID < TID < t1D (0/I3) < t1D < tJ D < llD (0/13) l WE11 WATER Gemma Scan I-131 (pCi/L) 64 130E + 01 2.3tt+0i 23nE+01 (1/51) 230E + 01 230E + 01 2J0E +01 (1/12) < LLD < 11D <IlD (0/13)

%TLL WATER Gamma Scan K 40 4.25E + 01 Statsm-# 19 (pCi/L) l

< 1lD <11D < LLD (0/31) < t1D < t1D <UD (0/13) <LLD < TID <!1D (0/13)

WE11 WATER Gamma Scan t#140 64 tk16E + 00 (PC3/L)

< tlD < 11D (0/51) < tlD <llD < ll D (ciu) <tlD <11D < 11D (0/13)

WE11 WATER Gemma Scan Ma-M 64 113E + 0) < tlD (FCi/L)

< I1D < LID < 11D (0/11) <UD < TID < 11D (eju WELL WATER Gamma Scan Nb-95 64 130E+00 < 11D < LID < llD (0/51)

(pCi/L) l <11D < LID < 11D (0/13)

Ra-2% 64 1.97E + 01 4.10E + 00 4.75E + 00 5 40E + 00 (2/51) 5 40E + 00 5 40E + 00 5 40E + 00 (1/13)

WELL WATER Gemma Scan Statum.# 1 ,

frCi/L) 46

m e e m W W W m M e m M M m M m e m M

~

TABIE 3 -

- RADIOUJGsCALENVERONMENTALMOMf!ORIMC FROGRAM OWIER CREEK NLCLEAR GENDIATING STATION '

JAM;ARY,1991 THROUGH DECEMBfA 1991 f ANNUAL SE*MMARY -

.UD- LNDICATUK STATIONS HIGHElJTANNUALMEAN BACKEROGD STATRMS l SAMP12 ~ ANALYST $ --. NLCIDE # OF

. ANAL ?.  ? MIN M2AN _ . _ MAX ' (N[IUT). . MIN . MEAN. MAX (N/ TUT) : MIN MEAN . MAX' (N/ TUT)

--1TPE rEur.

~

w q Ze45 64 1DE + 01 <IID <IID <UD (0/51) <IID <IID <IlD (0/13) <UD < flD <11D (0/13)

%TilWATIIR Gamma Scan (pCi/L) 5 45E + 00 < IID < TID < IID (0/51) < TID <t1D <UD (0/13) <uD < tlD < tlD (0/13)

%Tll. WATER Gamma Scan Zr 95 64 (PG/L) 7EE + 01 7.20E+01 7EE + 01 (1/10) 7.20E + 01 72E + 01 7.20E

• 01 (1/6) < tlD < TID < IlD (0/3) l CABBAGE Gamma Scan Ac-228 13 53RE +01 SN M M l (FO/4(41T))

I 5 69E+ 01 <IID <11D <UD (0/10) <IID < IID <IlD (0/6) <IID <11D <UD (0/3)

CABRAGE Gamme Scan Ba-140 13 (P G/k E(%1T))

Ik-7 13 9.44E + 01 210E+02 2!CE+02 3 ROE +02 (3/10) 2.100 + 02 230E + 02 3 NDE

• 02 (3/6) 1.20E + 02 1EE + 02 IEE + 02 (1/3)

CABRAGE Gamma Scan Statand M (pO/kg%1T))

<UD <11D < IlD (0/10) <llD <UD < 11D (0/6) < IlD < IlD < IlD (0/3)

CABRAGE Gamma Scan Ca58 13 131E + 01 (pO/kg(%1T))

<11D <IID < 11D (0/10) <IID <tLD < IID (0/6) <IID <UD <11D (0/3)

CABRAGE Gamma Scan Co40 13 1.82E + 01 (PG/kg(%1T))

<IID < IlD <UD (0/10) <11D <UD <IID (0/6) <UD <UD < flD (0/3)

CABBAGE Gatema Scan Cs-134 13 1.74E + 01 (pO/kg(WLT))

<IID < 11D <UD (0/10) <IlD <UD <LLD (0/6) < 11D <UD < LID (0/3)

CABBAGE Gemma Scan Cs-137 13 132E + 01 (P G/kt(%1T) 47

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T4BLE 7 RAIMO1DGICALENVIRONMENTALMONITORING FROGRAM

~ ..OYSITR CREEK NUCIEAR CENERATIN") STA110N -

.. JANIIARY, L991 TBitOLUM DECEMBE341991 ANNUAL $UMM4RY SAMPLE. . ANALYSIS - . NUCUDE s OF :- LED LNDICA1DR STATIONS HIGHESTANNUAL MFAN BACKGROLM3 STAY =h3 TYPE' . ANAL.

~

i MIM - MEA *3 = : MW l (NftUT)

- MIN MEei M4Y :- (N/IUI)

MIN : MEAM MW s . (N/IUI) cot IARD Gamma Scan K-40 14 NoIID 380E+03 437E+03 EIDE+03 (10/10) 430E+03 5.13E+03 6.10E+03 (3/3) 3M + C3 4.15E + 03 4 40E + 03 (4/4)

Reported Statxm-# 35 (pO/kg(%1T))

collard Gamma Scan 12-140 14 237E + 01 < 11D <UD < 11D (0/10) < 11D < LID <LLD (oft) s TID < 1lD < 11D (0/4)

(#/kg(41T))

< 11D < 11D < 11D (0/;0) <LLD < TID < 11D (Of7) <UD < LID < LID (0/4)

COIJARD Gamma Scan Mn-54 14 131E + 01 (pO/kg(%1T))

137E + 01 < 11D <UD < 11D (0/10) <UD < 11D <uD (0/7) <UD < 11D < !1D (0/4)

COUARD Gamma Scan Nb-95 (rO/kafw1T)

< llD < 11D < TID (0/10) < IID < tlD <llD (0/7) < tlD < 11D <UD (0/4)

COUARD Gamma Scan Ra-Z26 14 L10E + C2 i

(pCi/bg(MIT))

t 7m45 14 5.yE + 01 <11D <11D <tLD (0/10) < 11D < 11D <11D (0/7) < tlD < UA) < IlD (0/4) collard Gamma Scae (pO/kg(W1T))

200E + 01 < tlD < 11D <UD (0/10) < 11D <UD <11D (Of7) <LLD <llD < TID (0/4)

COLLARD Gamme Scan Zr-95 14 (pO/kg(%1T) 433E + 01

(*/*)

i'/*) <11D < LID <UD (0/3)

SWISS ClIARD Gamma Scan Ac-225 3 (pO/bg(%1m) 533E + 01

(*/*)

(*/*) < LLD < 11D <11D (0/3) 5%1SS CIIARD Gamma Sean Ba-140  ?

@DMwTT))

50

M M M M MM M M M M M W W W J m m M &

, - TASTE 7 '

j^ RADIOLOGICALENNMontTFDEDeGFROGRef OYSTER CREEK NUC1 EAR GEPERA11NG STATION y

~ JANUARY.19M TIEROUGE MM typt "

.g y m:

~ 3AMPIE t  ? ANALY9ts ? NUCUDE - s OF , UD- INDICATOR STAT 10PE5 HIGHE5T ANMt!AL M'I.AN j BACKGROL3sDSTATIONS

• 1-:TirrE? s , ANAI. : MIM MEAN :

2 MAK . (N/for) :

MIN : MEAN MAX - (M.. /1ttr) - - MIN: .MEAM- - MAK ' (N/ IUD . .-

SWES O LARD Gamma Scan Be-7 3 600E + 01 * * * *

(*/*) * *

(*/*) ISE+02115E+02 2.80E+02 (2/3)

(pO/kst4TT))

SWISS OIARD Gamma Scan Os58 3 i 23E + 01 * * *

(*/*) * * *

(*/*) <M < L1D <M @/3)

(FGAE(%1T)

SWISS O LARD GammaSrma Co40 3 130E+ 01 * * * * *

(*/*) *

(*/*) < t1D < 11D <LLO (0/3)

(FG,W lT)

SWISS OLARD Gamma Scan Cs-134 3 1.43E + 01 * * *

(*/*) * * *

<UD

(*/*) < 11D <UD (0/3)

(pG/kg(%1T)

SWISS GIARD Gamma Scan Cs-137 3 1.17E + 01 * * *

(*/*) * * *

<11D

(*/*) <11D <UD (0/3)

(PG/kg(41T)

SWISS GIARD Gamma Scan Fe-59 3 3 00E+ 01 * * *

(*/*) * * *

<UD

(*/*) < llD < LLD (0/3)

(PG/k(%TO) K SWISS GIARD Gamma Scan I-131 3 1.63E + 01 * * *

(*/*) * * *

<uD

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

(FG/ka(*1T))

Sw1S3 OIARD Gemme Scan K-40 3 NoL1D * * *

(*/*) * * * '

(*/*) 410E +C3 6 0T +03 7AnE +03 (3/3)

, (PG/kst%ET)) Re;=M SWI3S atARD Gamme Scan 12-140 3 1.90E + 01 * * *

(*/*) * * *

(*/*) <p <p <@ (0/3)

GCs/kt t(WIT))

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13ADKM.DGICAL ENVIRONMENTAL 1140NITORING FNOGRAM D g h0MER @ M N gem M,stp%

p' -p:epW [JANM 39911PROtJGH DECEhfEERiffrif eAgtrLstgggggyf:

^

ta 1-n IM*1CATUR STATIONS - J ~ HIGMDirTANNUALMEAN ' BACKGROUND STATIONS J c SAMPLE s -!. ANALYSI$ 5r NUCIJDZ q r # OF i CD

s.

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c yggy, g -

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M; ' -(MLC j MEdi  : nMMMN@:

QQ ' . ,,

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<llD <UD <UD (0/4) < IID <llD < LID (0/2) < LID <UD <UD (0#)

SOIL Gamma sean Ca60 6 2F7E +91 l i

(pCi/kg(DRY))

l l

3.1 h ot < LLD <UD <UD (0/4) <LLD <11D < tin (0/2) <UD <1LD <UD (0/2)

SOIL Gan ma Scan Cs-iM 6 (pCi/kg(DRY))

6 NollD 430E+01835E+0! ISE+02 (4/4) 9.00E+01 120E+02 130E+02 (2/2) 8.4GE v 01 1.22E + 02 140E + 02 (2/2)

SOIL Gamma Scan Cs-D1 Repor ed Station-# 35 (pCi/kg(DRY))

433E 01 < 11D < 11D < 11D (0/4) < 11D < L1D < tlD (0/2) < tlD <UD <UD (0/2)

SOIL Gamma Scan Fe-59 6 (pCi/kg(DRYJ)

<llD < L1D <11D (0/2) <UD < flD < 11D (0/2)

SOIL Gamma Scat I-131 6 2.7BE + ul <UD <1lD < 11D (0/4)

(PC2/kg(DRY)) .

6 No LLD 130E + 03 2.40E + 03 330E + 03 (4/4) 3.20E+03 3.25E+93 33C::4 (2/2) 4.80E+03 5.05E+03 530E+03 (2/2)

SOIL Gamma Scan K-40 Statxm-# e6 (pCi/kg' DRY)) Reported

<11D < 1lD < 11D <UD <LLD <11D (0/2J <UD < LID < LID (0/2)

SOIL Gamma Scan La-140 6 4.83E + 01 (0/4)

(pCi/kg(DRY))

< LID < 11D <LLD (0/4) <lll) < LID <IlE (0/2) < IlD <LLD <UD (0/2)

SOIL Gamma Scan Mn-54 6 1.98E + 01 (pCi/kg(DRY))

< t1D < LID <llD < t1D <uD (0/2) <!lD <UD <11D (0/2)

SOIL Gamma Scan Nb 95 6 2.27E + 01 <LLD (0/4)

(pCi/kg(DRY)) _

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                                                               ' RADIOLOCICALENWMDfYALMOMITORIMCFROGRAM I OWIER CREEK MUC1 EAR CENERATING STATION 1
                                                                      , (JANUAR%191111 ROUGH DECEMBER.1M11
                                                                                                                                 ~

' ANNUAL $UMMARY SAMPII:: , ANU,Y$18 :m NUCIlDE J . # OF +. v11D : - , f INDICATDR STATIONS a

• iMIGHTETANNUALMEAN t

 -~ g-g,            '
                                             '[ ANMI                     'l MLN ] ElMEAN.2 EmCKGROUNDSTATIONS ' e
                                                                                                                             ' MIN;! f MEAN ) f.MM JJ(N/IUT) i 9 MIN %MEANk 5MAXQ(N/1UT)
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TAtJTOG Gamma Scan Fe-59 8 5.63E + 01 <WD <UD <UD (0/7) <UD

                                                                                                                              < tlD                 < L? D   (0/5)         < 11D   <11D      < LLD      (0/1)

(pG/kg(%EO) TAIJIT)G Gamma Scan I-131 8 2ME + 01 <UD <LLD < LID (0/7) < 11D < LLD < IlD <LLD < 11D (0/5) <1lD (0/1) (pCi/kg(%ET)) TAUTOG Gamma Scan K-40 8 No11D 170E + 03 42rE + 03 4 EE + 03 (7/7) 3.70E + 03 4.16E + 03 4.80E+03 (5/5) 3.40E + 03 3.40E + 03 3.40E + 03 (1/1) (pO/kg(W1'T)) Reported Station 4 93 TAIJI'OG Gamma Senn Ia-140 8 3EE + 01 <11D <IlD <11D <UD <UD <UD <UD <UD (0/7) (0/5) <RD (0/1) (pCi/kg(%ED) TAUIDG Gamma Scan Mn-54 8 1.89E + 01 < 1lD < IlD <1lD (0/7) < 11D < IlD <11D <11D < 1lD (0/5) < IlD (0/1) (PG/kSt%T D) TAIJIOG Gamma Scan NM5 8 2.05E + 01 < 11D <UD < tlD (0/7) < TID < IID <!1D < 11D <11D <11D (0/5) (0/1) (pCi/kg(%ET)) TAIJIUG 'immma Scan Ra-226 8 8.00E + 01 < LID < LID <LLD (0/7) < 1lD < llD <IJ D < 11D < 11D (0/5) < 11D (0/1) (PG/kg(% TIT)) TAtJTOG Gamma Scan Zn-65 8 7.13E + 01 < 1lD < LID < IlD (0/7) < 11D < 11D < 11D < 1lD (0/5) < tlD < IlD (0/1) (PG/iR(% LIT)) TAUTOG Gamma Scan Zr 95 8 3,25E + 01 <11D < 11D <LLD (0/7) <LLD <LLD <llD < 1lD <11D (0/5) <11D (0/1) (PG/hgt%TD) , 65

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                                                                                                                                       +

IRA 110LOGICALENVIROMMENTALMOattT0RL9G FROGRAM ' 3 V m CREEK MUCLEAR'GENERAT1NC STA110N 5' - t [JAMtRR% 159111fROUGH DECEM8EN,19Mi

?; ;Q@tgtstyqARY'5 " '

SAMPLE ,s ANALYS18 MNUCllDE? / d UN 8 LID s flNDICATURSTA110NS ^ ;lilCHENTANNUALMEAN :.

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• 8.60E+00 8.60E +00 8.60E+00 (1/2) (*/*)

(pCi/kg(WIN)) Station-d 93 Wilfl11 PERGI Gamma Scan Fe-59 2 4.00E + 01 <LLD < 1lD < 1lE (0/2) <LLD < 11D < 11D * * * (0/2) (*/*) (pCi/kg(WITO)

%11TITI PERGI Gamma Scan     I-131                         2  4.00E + 01          <llD         <1lD      <llD     (0/2)         < LID     < llD    <LLD                    *         *       *

(0/2) (*/*) (pCi/kg(WTTO) WitTTII PERGI Gamma Scan K-40 2 No LLD 37013 + 03 3.75E + 03 3.80E + 03 (2/21 * *

• 3]DE + 03 3.75E + 03 3.80E + 03 (2/2) (*/*)

(pCi/kg(WLT) Reported Station-# 93 WilrII! PERCII Gamma Scan 12-140 2 4.00E + 01 :7 <llD <ilD (3/2) < LID < llD <llD * * * (0/2) (*/*) (pCi/kg(WI?O) 68

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                                                          , RADIOthCICAL ESTiltOMMENEALMOMf1DRL'eG FRbCRAMN4 I o

IOYSIER CREEK NUC1 EAR GEMNN11NG STA110M-- Ib: w W #NUARY,19M TffROlQt DECEMBER,19M :: . _ lM Q} gNI'M'MM*i

                                                                                                          ~'
     ~ SAMP!E ?- ;: ANALYSisu NUC11 der 4 OFj iLLD?            ..a .     ; INDICATOR STATIONS i                 '

RIGHEST ANNUAL MEAN ' BACKGit01:ND STA110MS i

       .[TYPEI
                       ^
                                      /ANAj{;                 Eh(IMl 7MEAN[ i MAX.h(N/IUT){                    f MIN} F MEAN ) iMAX d (N/IOT) U VU MIN 'c jMEANl ;[ MAX i(M/1UI)

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BLO%TISil Gamma Scan Ra-225 1_ 2 00E + 02 <1lD <LU) <LLD (0/1) <LLD <llD <1ll) * * * (0/1) (*/*) (pCi/hg(%ET)) DLO%T1SII Gamma Scan Zn45 1 6 00li+ 0! < LLD < 11D <11D (0/1) <1lD <11D < 11D * * * (0/1) (*/*) (pCi/kg(%ET)) BLO%71SII Gamma Scan Zr-95 1 3.00E + 01 < 11D <LLD <LLD <11D <LLD < 11D (0/1) (0/I) * * * (*/*) (pCi/kg(WL9) AQUA 11C SEDIMENT Gamme Scan Ac-228 32 No LU - 2.10E + 02 3.77E + 02 6.10E + 02 (24/24) $.00E + 02 5.17E + 02 5.40E + 02 (4/4) 4.10E + 02 6.06E + 02 7.7DE + 02 (8/8) (pO/kg(DRY)) Reported Station-d 33

     /    .AllC SEDIMENT     Gamma Scan  Ba-140      32     9.47E + 01          <11D       < IID    <LLD      (0/24)        < LID      < 11D    < llD                <llD      <LLD      <11D (0/4)                                   (0/8)

(p:/kg' DRY)) AQUA 11C SEDIMENT Gamma Scan Be-7 32 132E +02 1 2 + 02 3.23E + 02 8h0E + 02 (7/24) 2 50E + 02 42)E + 02 8.60E + 02 (4/4) 530E + 02 5.30E + 02 530E + 02 (t/8)

  'pCi/kg(DRY))                                                                                                                   Station-#     33 AQUA 11C SEDIMENT     Gamma Scan   Ca58       32     2.02E + 01          < 11D      < LLD    <1lD      (0/24)        < L1D      < 11D    < 11D               < 11D      <tu)      < 11D (0/4)                                    (0/8)

(pCi/t gtDRY)) AQUA 11C SEDIMENT Gamma Scan Co40 32 2.46E + 01 L50E+01 1.02E+02 2.00E+02 (6/24) <llD < 11D <11D 2.00E + 02 2.00E + 02 2.00E + 02 (1/4) (0/8) (pCi/kg(DRY)) Station-# 32 71

6TABIE37. .

ItADIOIDGICALENViRONMEPrfALMONflU"11NC FROGRAM

                                                        ~
                                                                 ~ 1 OWITR CREEK NUC1 EAR GENERATING STATION

JANUARY,U91THROUGM DECEMBER,1991 1

P M'UAL SUMM3

                                                                                                                               % HIGHESTANNUALMEAN .                     BACKGROUND $TATIONS .:

J:SAMPIE !. / ANALYS18 2.NUCUDE ; s.0F(. jllD - .. ilt:DICATUR STATIONS '

ANA14 ! ' MIN 1 :.MEAN f l MAX ;; (N/ ~ROT) ~ MIN - 2 hsEAN;; 4 MAX & (N/NTT) .  ; MIN . MEAN ' MAX ,[(N/IVT) i i:Tn?El ~ ~ ' ' '

                                                                                                                                                              ~
                                                                                                                                                                                                    ~ 

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M MM M &M S& & WN 5 M & W & S & S M

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                                                                                                                                                                                              < llD           (0/8)'

(pCi/kg(DRY)) AQUABC SEDIMENT Gamma Scan Ra-226 32 NollD .$.70E +01 3_22E + 02 1.50E +03 (24/24) 1.30E + 02 4.77F. + 02 130E + 03 (4/4) 110E+02 431E+02 130E+03 (5/8) (pCi/kg(DRY)) Reponed Station-# ?3 AQUA 11C SEDIMENT Gamma Scan Za-65 32 8.09E + 01 < LLD <UD < llD (0/24) <LLD < llD <llD (0/4) <UD < llD <UD (0/8) - (pCi/kg(DRY)) AQUATIC SEDIMENT Gamma Scan Zr-95 32 3.52E + 01 < llD < llD < LID (0/24) <llD < llD < llD (0/4) <llD <llD <UD (0/8) (pCi/kg(DRY)) WEAKilsil Gamma Scan Ac-228 7 637E+01 < llD < llD < L1D (0/6) < LI.D <llD <llD (0/6) < llD < llD <!lD (0/1) (pCi/kg(%TU)) WEAKFISII Gamma Scan Ba-140 7 7.86E + 01 <IID <IID < L1D (0/6) < LID < L1D <llD (0/6) < IiD < LLD <IID (0/1) (pCi/kg(MTIT)) W'3AKilSil Gamme Scan lle-7 7 1.23E + 02 < llD < llD < LLD (0/6) < llD < llD < llD (0/6) < LLD < llD < llD (0/1) (p0/kg(%TT)) WEAKTISil Gamma Scan Co-58 7 1.66E + 01 < LLD <llD < LID (0/6) <llD <LLD <llD (0/6) < llD <LLD <llD (0/1) (pO/kg(%TA) 73

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I DIRECT RADIATION MONITORING

       ~

Dose rates from external radiation sources were moacured at a number of locations in the vicinity of the OCNGS using thermoluminescent dosimeters (TLDs). Naturally occurring sources, including radiations of cosmic origin and natural radioactive materials in the air and ground, as well as fallout from prior nuclear weapon testing, resulted in a 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 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 hiw , in areas of public interest, population centers, a in background locations which are typically greater than ten miles distant from the Or:NGS and generally in an upwind direction. Sample Collection and Annivsis I A state-of-the-art thermoluminescent dosimeter is used. I Thermoluminescence is a process in which ionizing radiation, upon interacting with the sensitive material of the TLD (the phosphor or ' element') causes some of the energy deposited in the phosphor to be stored in stable ' traps' in the TLD material. These TLD traps are so stable that they do not decay appreciably over the course of months or even 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 neating process in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy as light. The amount of light given off is ( directly proportional to the radiation dose the TLD received. l The reading process ' zeros' the TLD and prepares it for reuse. ! 78 LI

1

• I The TLDs in use for environmental monitoring at the OCNGS are capable of accurately measuring exposures between 1 mrem (well below normal environmenh1 levels for the quarterly monitoring periods) and 1000 REM.

I During 1991, TLDs ere collect .I every twelve weeks from locations ranging from less than 0.2 miles to 35.1 miles from I the OCNGS. Prior to July 1991, four GPUN Panasonic TLDs and one Teledyne Isotopes (vendor supplied) TLD were exposed at each of 63 monitoring locations. Two of the 63 monitoring locations were used as quality control (QC) stations at which 4 additional GPUN Panasonic TLDs and one Teledyne Isotopes TLD were exposed. A program change occurred in July 1991 in which I *te Teledyne Isotopes TLD network was scaled down from 63 monitoring locations to 10 monitoring locations (Appendix C). The 10 remaining monitoring locations are being used as quality control stations. The GPUN Panasonic TLD network was not altered. GPUN Panasonic TLDs provide sixteen independent detectors at each station. Teledyne Isotopes TLDs provide an additional four independent measurements. I TLDs were exposed on a 12 week basis (84 days). Because five I collection dates occurred in 1991, five periods of data are listed in Tables J-1 and J-2 in Appendix J. Scheduled exposure period; were: TLD EXPOSURE PERIODS IN 1991 Start Date Collection Date 29 Oct 90 21 Jan 91 21 Jan 91 15 Apr 91 15 Apr 91 08 Jul 91 08 Jul 91 30 Sep 91 30 Sep 91 23 Dec 91 All TLD dose rate data presented in this report have been normalized to eliminate differences caused by slightly 79 I

I differing exposure periods. GPUN Panasonic TLD results were normalized to a standard quarter (91.3 days) and Telodyne

  =

Isotopes data to a standard month (30.4 days). TLD dose rate data are presented in Tables J-1 and J-2 in Appendix J. Results In 1991, the dose rate measured at indicator stations using Teledyne Isotopes TLDs averaged 3.9 mrem / standard month and ranged from 2.6 to 6.2 mrem / standard month (Table J-1). The dose at background TLD stations averaged 3.9 mrem / standard month and ranged from 2.8 to 5.6 mrem / standard month. The mean dose rates from indicator and background stations were the same suggesting that OCNGS operation contributed little if I any to off-site exposure. These results are consistent with the results of measurements from previous years (Fig. 6). Considering that the standard daviation of dose rates was as high as 1.1 mrem / standard month, the data indicate that dose rates are not significantly higher close to the OCNGS , (Fig. 7). I Regarding GPUN Panasonic TLD data, the mean dose rate from indicator stations was 10.50 mrem / standard quarter with a _ range from 8.35 to 15.83 mrem / standard quarter. The , background mean dose was 11.40 mrem / standard quarter Pith doses ranging from 9.36 to 14.69 mrem / standard quarter. The mean background dose exceeded the mean indicator dose again suggesting OCNGS had little if any affect on off-site exposure. The standard deviation of dose rates ranged from I 0.23 to 10.70 mrem / standard quarter. When GPUN Panasonic TLD data were converted to mrem / standard month for comparison with Teledyne TLD data, no relationship between dose rate and distance from the OCNGS was observed (Fig. 8). A comparison of dose per affected compass sector between Teledyne Isotopes and GPWI Panasonic TLDs was performed using I 80

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. I 1991 data (Tig. 9). The results indicate good correlation between the dose por sector as recorded by the two independent TLD networks. In addition, the data indicate that the north-northwest sector had the highest *,'31 done. Based upon [ on-site meteorology for 1991, the highest air dispersion (X/Q) factors were in the southeast sector. The north-northwest sector is almost directly opposite the southeast sector thich is further evidence that the OCliGS had little if any offect on f off-site exposure. I

I

'I I

I I

I I

 .I

.I I I I 84 I

m m m M 'm . W m m m M m e e e e m MEAN TELEDYNE AND PANASONIC TLD GAMMA DOSE FOR 1991 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MEAN DOSE IN AFFECTED COMPASS SECTOR i DOSE IN MILLIREM PER STANDARD QUARTER O PANASONICTLD E TELEDYNETLD 15 -

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I ATMOSPHERIC MONI9'ORING A primary exposure path'.Ty to man is the inhalation and ingestion of radionuclides released to the atmosphere. I Radioactivity in ambient air was sampled by a network of thirteen continuously operating air camplers. Precipitation samples were also collected at these thirteen locations. I 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 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 I Hammonton, NJ. Sample Collection and Analysis Mechanical air samplers are used to continuously draw a recorded volume of cir through n glass fiber (particulate) filter and then through a charcoal cartridge. A dry gas meter, which is temperature coupensated, is used inside the air, sampler to record air volumes. Internal vacuums are also measured in order to pressure enrrect the indicated vc'ume. 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. i g W Charcoal cartridges, used to collect gaseous radiciodines, i contain activated charcoal. Charcoal cartridges were collected weekly and analyzed for iodine-131 (I-131) activity. 9 I 86 I .

Precipitation samples woro collected monthly using an eight-inch diameter funnel that drains into a collection container. A quarterly composite per statior was then prepared. Six of the thirteen composito sampics woro analyzed for tritium and gamma-omitting radionuclides. The remaining seven samples were stored pending the outcomo of the six analyzed samples. I Ef1Mita The results of the atmospheric monitoring during 1991 demonstrated that, as in previous years, the radioactive airborne effluents associated with the OCNGS did not have any I measurable offects on the environment. During 1991, 675 gross beta analyses were performed on air particulate filters (Tabic 3). One of these analysjs could not meet the required LLD because an air sampler malfunction yielded a very low total volume (Appnndix B). For the purposes of the descriptive statistical analyses reported in Table 3, thaso results woro excluded. The background mean gross beta activity (0.0165 pC1/m3) was slightly higher than the indicator mean (0.0160 pCi/m3) and all gross beta analysis I results were within two standard deviations of the historical mean. Comparison of the 1991 weekly mean air particulate gross beta concentrations for indicator and background stations indicates that indicator and background concentrations were essential.ly identical (Figure 10). These results are consistent with the results of gross beta analyses of air samples from previous years (Figure 11). l I The air particulate gross beta ar.alysis results clearly show that effluent containing gross beta radioactivity f rom OCNGS operation did not have any measurable impact on the local environment. l I 87 I .-

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m m m m m m' m e m m em m m m m M M e m MONTHLY MEAN AIR PARTICULATE GROSS BETA CONCENTRATIONS 1984 THROUGH 1991 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS IN PICOCURIES PER CU.BIC METER 0.2 0.18 -- 0.16 y CIIERNOlnL ACCIDENT [ j . 0.14 -- 8 0.12 -- E e

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Gamma isotopic analyses woro performed on 169 air particulate filter composites (Table 3). Three naturally occurring radionuclides, beryllium ' potassium-40, and radium-226 were detected. Be-7 activity was consistently seen at both I indicator and background stations in similar concentrations. Potassiun-40 and radium-226 wero each detected only once at indicator stations. The concentrations of each radionuclide was less than the respective yearly mean LLD and were within two standard deviations of the historical mean. None of these nuclides can be attributed to effluents from the OCNGS. Air charcoal cartridges (675) were analyzed for iodine-131 (I-131) and no radiolodine was detected in any of the samples (Table 3). One result did not meet the required sensitivity I when a malfunctioning sampler yielded a low sample volume. This result was excluded from Table 3 (Appendix B). All 13 air iodine cartridges collected from both background and indicator stations on December 30, 1991 were found to be contaminated with a trace quantity of xenon-133 activity. Exact gaantities could not be determined because of cartridge and detector unknowns. Strict compliance to procedures regarding the handling of these filters was maintained throughout the collection and pre-shipment process, suggesting the contamination source to be other than the OCNGS. Inadvertent contamination most likely occurred when the shipment of the filters, in transit via overnight air courier to the analysis laboratory, came in close proximity to this nuclido (Xe-133) which is used as a radiopharmaceutical. I With regard to precipitation sampling, 24 gamma isotopic and 24 tritium analyses were performed in 1991 (Table 3) . Tritiun activity was detected in 3 of 12 indicator samples and 5 of 12 background samples. The maximum and mean results from the background samples were 250 and 198 pCi/ liter respectively. I 90 I

The maximum and mean results from the indicator stations were slightly lower, 180 and 170 pC1/ liter respectively. Considering those data, in addition to the large environmental inventory of tritium due to cosmic ray interactions and I nuclear waapons testing, it is highly unlikely that the relatively minute amount of tritium in the OCliGS offluents could have had a measurable effect on c.xisting environmental concentrations. The only other radionuclide detected was naturally occurring beryllium-7, which was identified in one indicator sample and one background sample (Table 3). The concentration detected in the background sample was 22 pCi/ liter while the indicator station concentration was 12 pol / liter. This radionuclido cannot be attributed to OC11GS I effluents. I I I I l I  ! I I B I I 91 I

AOUATIC MONITORING Lrackish water from Barnegat Bay is drawn in through the south branch of Forked River, pumped into the OCNGS cooling systems, and then discharged to Barnegat Bay via Oyster Crock. I clams, and crabs are harvested from the bay on a recreational Fish, and, to a limited extent, commercial basis. Tne ingestion pathway is addressed because of fish, clam, and crab Conf 41mption . I On occasion, a radioactive liquid release is discharged under the limits established in the OCNGS Technical Specifications and 10CFR20. Highly purified water, containing traces of I radioactivity, is discharged into Oyster Creek which has a minimum flow rate of slightly under one-half million gallons per minute. Samples of surface water, sediment, fish, blue crab, and hard clams were routinely collected from the OCNGS intake and discharge canals, Barnegat Bay, Manahawkin Bay, and Great Bay in ceder to monitor any environmental impact that may be associated with thesa releases. I Sample collection and Analysis Surface water, sediment, and clam samples were collected every four weeks. Grab samples of surface water and sediment were collected from six indicator stations and two background stations. Grab samples of clams were collected from three indicator and two background stations. Three indicator ) stations for surface water and sediment are located in the l OCNGS discharge canal - Oyster Creek. No clams are available l- for collection at these stations. Three indicator stations are located in Barnegat Bay in close proximity to the mouth of Oyster Creek. One background station is located in Manahawkin

I I 92 I

Bay, approximately 11 miles south of the OC11GS . A second background station is located apprcximately 22 miles south of the CCliGS in Great Bay. Blue crab and fish samples were collected every four weeks (when available) from two indicator stations and one background station. Both indicator stations are located in I th? OCliGS discharge canal and the background station is located in Great Bay. Crab pots were used to catch blue crab. The hook and line technique was used to catch fish. _ All samples were analyzed for gamma-emicting nuclides; water samples were also subjected to tritium analysen. I Resultn operation of the OC11GS had no detectable ef fect upon the local surface water which was sac ad 104 times at eight different locations during 1991. Two gamma-omitting nuclides, potassium-40 (K-40) and radium-226 (Ra-226), were detected in 101 and 4 samples respectively (Table 3). Tritium 01-3) activity was also detected in 2 samples (Table 3). These three radionuclides are naturally occurring and commonly found I in seit water at or abovat the observed concentrations. lio other radionuclides were detected in surface water samples. Six gamma-omitting nuclides were detected in the 32 sediment samples collected during 1991 (Table 3). Four of these radionuclides. beryllium-7, potassium-40, radium 226, and actinium-228 are naturally ocuurring and were detected at both background and indicator stations. Cesium-137, which is a fission product, was also detected in 75 percent of background I samples and 67 percent of indicator samples. As fallout, Cs-337 was widely distributed and detected in considerable abundance following atmospheric weapons tests and the I 93 I

__ - _ _ _ - _ =- . . _ _ _ _ . _ . . . . - - _ - .I Chernobyl accident. It was also released in small quantities from the OCNGS in liquid effluents in 1991, as well as in past years. The presence of this radionuclide in a higher percentage of background samples than indicator samples I suggests that the cesium-137 activity detected in Barnegat Bay sediments originated from the former sources and not OCNJS operatd.on. I Cobalt-f) war detected in twenty-five percent of the aquatic sediment indicator station samples and none of the background station samples (Table 3). The presence of this radionuclide in Barnegat Bay sediments is of interest because it can be attributed to OCNGS liquid effluents. As documented in I previous reports, OCNGS related cobalt-60 activity has been found in sediment and clams from Barnegat Bay since at least the mid-1970's. The volume of liquid effluents has been significantly red' ,cd since that time and this decrease in the rate of input of cobalt-60 to the environment, combined with radioactive decay of the existing inventory, has resulted in a gradual decline in the cobalt-60 concentration in sediment and clams (Fig.12 and 13) . The last detectable concentration of this radionuclide in clams was during the third quarter of I 1987 (Fig. 13). Sixty-five clam samples were collected from five different locations during 1991. Gamma isotopic analyses indicated that the only gama-emitting nuclide present was potassium-40 (I;-

40) which is naturally occurring and found in great cbundance in salt water (Table 3).

I Nine blue crab samples were collected from three locations during-1991. A gamma isotopic analysis was performed on each I sample of crab meat and naturally occurring potassium-40 (K-

40) was the only radionuclide identified (Table 3) . The close association of this species with Barnegat bay sediments could I 94 I

                                                                                          ~

M M M M M M M M M M M M M M M M M M M MEAN COBALT-60 CONCENTRATION IN AQUATIC SEDIMENT- 1984 THROUGH 1991 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS IN PICOCURIES PER KILOGRAM (DRY) 500 - 450 -- 400 L 350 -- 399 __ 4NDICATOR MEAN s

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I  ! make it susceptible to cobalt-60 uptake. Ilowever, no detectable co-60 activity has been observed in blue crab samples since routine collection began in 1985 (Fig. 14). I Thirty-nine fish sarples, yielding 9 species, were collected from 3 campling locations during 1991. The species and number i l of samples collected are listed belows I - TABLE 5 SPECIES Of flSH CAUGHT AS PART OF THE OCNGS REMP IN 1991 fish Number of Samples summer flounder 8 tautog 8 weak (ish 7 blue 5 ui 6

         ~

wintei flounder 3 American eel 2 striped bass 2 white perch 2 blowfish 1 Naturally occurring potassium-40 was detected in each of the 39 fish samples (Table 3). A detectable quantity of cesium-337 activity was observed in 2 of 6 weakfish, 1 of 5 blucfish, and 1 of 2 white perch samples, all collecteu from indicator station >3 (Table 3) . The results ranged from a maximum of 19 pCi/kg (wet) to a minimum of 8 pC1/kg (wet). As discussed I above, Cs-137 is a ubiquitous fission fallout product and has been detected in considerable abundance following atmospheric weapons tests and the Chernobyl nuclear accident. It was also discharged in very small quantities (Table 2) from the OCNGS during 1991. The maximum level of Cs-137 activity (19 pCi/kg (wet)) was only 13 percent of the lower limit of detection and lI 97 I

__o M M M M M M M M M M M M M M M- M M M M MEAN COBALT-60 CONCENTRATION IN BLUE CRAB - 1984 THROUGH 1991 OYSTER CREEK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS IN PICOCURIES PER KILOGRAM OVET)

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a_.. NO CORALT40 FOUND IN BLUE CRAB

                                                                            -*- INDICATOR MEAN               g 3o __                                                                                                c-M
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I O.95 percent of the reporting level specified by the OC11GS Technical !7ecifications. Similar low levels of this radionuclido are found in fish throughout the world as a result of fallout (Ref. 17). t l I I I , I I I I .I I I I I I 99 lI

1 I TERRESTRIAL M0!i1TORIt1G Radionuclides released to the atmosphere may be deposited on soil and vegetation and may be incorporated into milk, I vegetables, and/or other food products. To assess the impact of dc,o to humans from the ingestion pathway, food product samples such as green leafy vegetables were collected and I analyzed during 1991. Surface soil samples were also collected and analyzed for the purpose of monitoring the potential buildup of atmospherically deposited radionuclides. The contribution of radionuclides from the OCliGS operation was assessed by comparing the results of samples collected in I prevalent downwind locations, primarily to the southeact of the site, with background sampics collected from distant and generally upwind directions. A dairy census was conducted to determine the locations of commercial dairy operations and milk producing animals in each of the 16 mateorological sectors out to a distance of five miles from the OC11GS. The census showed that there were no commercial dairy operations and no dairy animals producing milk for human consumption within a 5 mile radius of the plant 8 (Appendix F) . GPUlf Oyster Creek Environmental Controls established and maintained two gardens near the site boundary in the two sectors with the highest potential for radioautive deposition in lieu of performing an annual garden census. Both gardens are greater than 50 square meters in size and produce green leafy vegetables. A commercial farm located approximately 24 I miles northwest of the site was used as a background station. I !I l 100

e Egnple Collection and Analyrig Broadleaf vegetables, specifically cabbage, collards, and Swiss chard, were collected on a monthly basis beginning in I June and ending in December 1991. was performed on each sample. A gamma isotopic analysis Surface soil samples from the gardens were collected during July and October. Each soil carr, la was subjected to a gamma isotopic analysis. Results The I results of the terrestrial monitoring during demonztrated that the radioactive offluents associated with 1991 the OCNGS did not have any measurable effects on vegetation or soil. 1 Naturally occurring radionuclides accounted for the only radioactisity identified in vegetable samplec (Table 3). Potassium-40 was detected in 100 percent of the cabbage, collard, and Swiss chard samples collected from both indicator and background stations. Beryllium-7 was identified in 3 of i I 10 cabbage samples collected from indicator gardens and in 1 l of 3 cabbage samples collected from the background location. Beryllium-7 was also identified in 6 of 10 collard samples obtained from the indicator stations and in 3 of 4 samples ( collected from the background garden. Swiss chard, which was l only 011ected at the background station, had naturally l l occurring Be -7 activity in 2 of 3 samples. Actinium-228 was detected in 1 of 10 cabbage samples collected from the indicator gardens and radium-226 was identified in 1 of 3 Swiss chard samples harvested from the background station. No other radionuclides were identified. Of the radionuclides detected, none are associated with OCNGS operation. I 101 I

I Cesium-137 activity was detected in all indicator and background soll samples collected from the gardens in which vegetables were grown (Table 3). The mean concentration of Cs-137 at the background station was 122 pCi/Kg(dry) while the I mean concentration found at the indicator stations was 83.5 pCi/Kg(dry). This trend, in which the background mean has been slightly higher than the indicator mean, has continued since 1989 (References 24 and 25). Gaseous cesium-137 was released in OCNGS effluents in 1991 and 1990, (0.43% and 0.026% of total particulate activity released, respectively). None was released in 1989. Even though a slightly larger quantity of gaseous cesium-137 was released in 1991 (44.4 microcuries - Table 2) than in 1990 (4.56 microcuries - Reference 25), the indicator mean (83.5 pCi/Kg(dry)) for soil I, in 1991 was less than the indicator mean for 1990 (142 pci/Kg(dry)) and 1989 (120 pCi/Kg(dry)). These results indicate that the minute concentrations of cesium-137 detected in soil samples 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, naturally occurring radionuclides, beryllium-7, potassium-40, radium-226, and actinium-228 were detected in soil sampics (Table 3). t I I I I . I 102 I

i GROUNDWATER MONITORIILQ 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 l the more rugged topography of the Piedmont Province. The Fall I. Zone is also where the crystalline and sedimentary rocks of the Piedmont and the unconsolidated coastal plain sediments l 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 i

4. Confined, Upper Zone in the Kirkwood Formation

5. Confined, Lower Zone in the Kirkwood Formation E The unconfined Recent and Cape May Formations are replenished I

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 site at higher elevations. Samole Collection and Analysis i As part of the routine REMP, five wells were sampled on a monthly basis. Grab samples were obtained from four local residences and one OCNGS well. The depths of the residential I wells are unknown but most local domestic wells draw upon the Cohansey aquifer; the OCNGS well is approximately 380 feet deep, in the Kirkwood formation. Each sample was subjected to a tritium and gamma isotopic analysis. I 103 I

In addition, a well network (17 wells) was installed around the OCNGS in 1983 to serve as an early detection and inonitoring system for spills, separate from routine REMP ^ sampling. During 1991, fourteen 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. I Results The results of the groundwater ruonitoring during 1991 demonstrated that, as in previous years, the radioactive effluents associated with the OCNGS did not have any measurable effects on offsite groundwater quality. Sixty-four routine REMP well water samples were collected during 1991 (Tabic 3). Naturally occurring potassium-40 and radium-226 were the only gamma-omitting radionuclides identified. Potassium-40 was detected in only one of 51 indicator samples and radium-226 was identified in two of 51 samples. Neither of these radionuclides can be attributed to effluents frem the OCNGS. Another naturally occurring radionuclide, tritium, was detected in 2 of 51 indicator samples. These results were not considered significant because the maximum tritium concentration (170 pCi/ liter) was I less than one percent of the EPA drinking water limit and only 8.5 percent of tht lower limit of detection required by the OCNGS Technical Specifications. The results of the analyses of 26 samples from the onsite spill monitoring well network were similar (Appendix H). No I gamma-emitting nuclides were detected and tritium was detected in only seven samples. The maximum tritium level was 220 pCi/ liter, which is only 1.1 percent of the EPA drinking water limit. Considering the very large environmental inventory of tritium due to cosmic ray interactions and nuclear weapons I 104 I l

J.2 a.d.,-J.-n-, ..hW- .,4. .. - -Ah,ms., -a-S eA-AW -m.*mL-.Weda 4-AAm. h -p 4.46-- eh Xmim .%-_-.shA4 44+44444.-4%_.aea3a_m.haAh..mAaM_aau hA.-h4 m aA.ad, l testing, it is highly unlikely that the relatively minute amounts Of tritium in the OCNGS's effluents could have a g measurable effect on existing environmental concentrations. I I I I I l l I E t

 >I I

I g

RADIOLOGICAL IMPACT OF OC11GS OPERATIO!!S An assessment of potential radiological impact indicated that radiation doses to the public from 1991 eperations at OC11GS I were well below all applicable regulatory limits and were significantly less than do: ceived from comAon sources of radiation. The 199A whole / dose potentially recei'/ed by an assumed maximum exposed individual from OCliGS liquid and airborne effluents was conservatively calculated to be about 7.08 E-3 millirem tocal or only 2.83 E-2 percent of the OC11GS Technical Specification limit. The 1991 whole body dose to the I surrounding population from OCllGS liquid and airborne ef fluents was calculated to be 2.41 E-3 person-rem and 2.20 E-1 I person-rem respectively. This is approximately 4.5 million times lower than the doses to the total population within a 50-mile radius of the OCliGS resulting from natural background sources. Determination of Radiation Doses to the Public I To the extent possible, doses to the public are based on direct measurement of dose rates from external sources and measurements of radionuclide concentrations in the environment . which may contribute to an internal dose of radiation. Thermoluminescent dosimeters (TLDs) positioned in the environment around Oyster Creek provide measurements to determine external radiation doses to humans. Samples of air, water, food products, etc. are used to determine internal doses. I During normal plant operations the quantities of radionuclide releases are typically too small to be measured once I 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 I 106 I

l l l the environment and subsequent radiation doses on the basis of radionuclides released to the environment. GPUli calculates doses using an advanced dispersion model called SEEDS (Simplified Effluent Environmental Dosimetry System) . This model incorporates the guidelines and methodology set forth by I the USliRC in Regulatory Guide 1.109. Due to the conservative assumptions that are used in the model, the calculated doses are considerably higher than the actual doses to people. The type and amount of radioactivity released f rom the OCliGS is calculated using measurements from effluent radiation monitoring instruments and effluent sample analysis. I released, the dispersion of radionuclides in the environment Once is readily determined by computer modelling. I releases are diluted and carried away from the site by Airbcrne atmospheric diffusion which continuously acts to disperse radioactivity. Variables which af fect atmospheric dispersion include wind speed and direction, temperature at different elevations, and terrain. A meteorological monitoring station northwest of the reactor site is linked to a computer terminal which permanently records all necessary meteorological data. Computer models also are used to predict the downstream dilution and travel times for liquid releases into the Barnegat Bay estuary and Atlantic Ocean. The pathways to human exposure also are included in the model. These pathways are depicted in Figure 15. The exposure pathways considered for the discharge of the station's liquid effluent are fish and shellfish consumption and shoreline I exposure. effluents include plume exposure, The exposure pathways considered for airborne inhalation, vegetable consumption (during growing season) and land deposition. SEEDS employs numerous data files which describe the area around the OCliGS in terms of demography and foodstuf fs I 107 I

'l FIGUFFE 15 EXPOSURE PATHWAYS FOR ROUTINELY l RELEASED RADIONUCLIDES FROM THE OCNGS I Gaseous Effluents I Oyster Creek Station _ u> 5 o I Liquid Effluents g g g 8 _8 m a 5' g-

                 //            g                                                     5' Direct v l   [

4/ Irradiation l > 4-

    /
                                                                                                v I
                                                                      )

4 Consumption o n e> n immersion - e -> ^ ^ (Boating / Swimming) 4 Shoreline ( Irradiation b (Boach/ Fishing) Ingestion Seafood Consumption N l - n-PREDOMINANT RADIONUCLIDES I =,=..- ggg===:- ggg_

                                                                                 ~~"

l %2ii"&= B2i?iEE-108

I proo ation. Data files include such information as the dis'ance from the plant stack to the site boundary in each g -

                           -rpass sector (sixteen in all), the population groupings,
 , ip                   gardens of more than 500 square feet, meat animals, arid crop

• yields.

         .g j;
                            -   datermining the dose to     humans, it is .wcessary to e all pathways and all    exposed tissues, summing the ise   <om each to provide the    total dose for each organ as 5

g 7- as the whole body from a given radionuclide in the a mnnent. Dose calculations involve determining the energy - s.u s ad per unit mass ir the various tissues. Thus, for radionuclides taken into the body, the metabolism of the A radionuclide in the body must be known along with the physical characteristics u the nuclide such as energies, types of radiations emitted and half-life. SEEDS also contains dose conversion factors for over 75 radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body. thyroid, liver, skin, kidney, lung, bone and % astro-intu:t?aal tract). Doses are Mculated for what is termed the " maximum hypothetical individual." I This individual is assutrod 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-discharg3 canal shoreline for 67 hours per year while

             ~

eating 43 pounds of fish and shellfish. For airborne releases, the maximun 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. I Th.is location is 522 meters to the southeast based on the meteorological conditions at the time of releases. The conservative usage factors and other

                    ,    assumptian.; used in the model result in a conservative I                                      109 l

overestimation of dose. Doses are calculated for the population within 50 miles of the OCNGS for 81rborno effluents and the entire population ucing the Barnegat Bay estuary and Atlantic Ocean for liquid effluents. Appendix G contains a more detailed discussion of the dose calculation methodology. Respits of Dose Calculations Dosos from natural background radiation provide a baseline for assessing the potential public health significance of radioactive effluents. The average person in the United States receives about 300 millirem (mR) per year from natural background radiation sourcas. Natural background radiation from cosmic, terrestrial and natural radionuclides in the I- human body (not including radon), averages about 100 uR/yr. The natural background radiation from cosmic and terrestrial sources varies with geographic location, ranging from a low of about 65 rR/yr on thu ? M. antic and Gulf coastal plains to as much as 350 mR/yr on the Colorado plateau (Ref. 3). The National Council on Radiation Protection and Measurements (NCRP) now estintes that the average individual in the United States receives an annual dose of about 2,400 millirems to the lung from natural radon gas. This lunLJ dose is censidered to be equivalent to a whole body dose of 200 millirems (Ref. 2). Effluent releases from the OCNGS and other nuclear power plants contribute but a very small percentage to the natural radioactivity which has always been present in the air, water, soil and even in our bodies. In general, the annual population doses from natural background radiation (excluding l radon) are 1,000 to 1,000,000 time:., larger than the doses to the same population resulting from nuclear power plant l- 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 I 110 l

individual of the public to the OCNGS Technical Specifications, 40CFR190, and 10CFR50 Appendix I dose limits. Table 7 presents the maximum total body radiation doses to the population within 50 miles of the olant from airbor.e releases, and to the entire population using Barnegat Bay and the Atlantic Ocean, for liquid releases. These conservative calculations of the doses to m oers of the public from the OCNGS ranged from 0.00068 percent to a maximum of only 0.508 percent of the applicable regulatory limits. They cre also considerably lower than the doses from natural background and fallout from prior nuclear weapon tests. I I I I I I I I I I 111 .

TABLE 6 CALCULATED MAXIMUM HYPOTHETICAL DOSES TO AN INDIVIDUAL FROM LIOUID AND AIRBORNE EFFLUENT RELEASL'S FROM THE OCNGS E9R 1991 I REGULATORY UM6TS PERCENT OF EFFLUENT CALCULATED DOSE REGULATORY RELEASED mrem / YEAR SOURCE mrem / YEAR UM:T LIQUID 3 TOTN. DODY TECH SPEC 3.6.J.1 2.04 E-5 6.80 E-4 , UQUID 10- ANY ORGAN TECH SPEC 3.6.J.1 8.65 E 5 845 F 4 6 AIRBORNE 5 TOTAL BODY 10 CFR 50 APP. I 6.19 E-3 1.24 E 1 (NOBLE GAS) A!RBORNE 15 - SKIN 10 CFR 50 APP. I 7.64 E-3 5.09 E-2 (NOBLE GAS) AIRSORNE 15 #NY ORGAN TECH SPEC 3.6.M.1 7.62 E 2 5.08 E-1 (IODINE AND PARTICULATE) TOTAL-UQUID 25 - TOTAL BODY TECH SPEC 3,6.N.1* 7.08 E 3 2.83 E-2 AND AIRBORNE TOTAL UQUID 75 THYROID TECH SPEC 3.6.N.1* 7.C2 E-2 1.02 E 1 AND A!RSORNE I TOTAL LIQUID 25 ANY OTHER TECH SPEC 3.6.N.1* 7,63 E-2 3 05 E 1 AND AIRBORNE ORGAN

• 40 CFR 190 I

I 112 I

l I l l TABLE 7 j l FALCULATED MAXIMUM TOTAL RADIATION DOSES TO THE POPULATION FROM LIOUID AND AIRBORNE EFFLUENT RELEASES l FROM THE OCNGS FQR 1991 I l I I Calculated Population , Total Body Dose I Person-Rem / Year O_QNGS l From Radionuclides in L. quid Releases 2.41 E-3 I

 .I    (Barnegat Bay and Atlantic Ocean Users)

From Radionuclides in Airborne Releases 2.20 E-1 (Uithin 50-Mile Radius of OCNGS) l DOSE DUE TO NATURAL BACKGROUNn_ RADIATION j Approximately 990,000 Person-ht. Per Year l i i I l f L I I 113 lI i

I: REFERENCES (1) Jersey Central Power and Light Company. " Oyster Creek Nuclear Generating Station Operating License and I Technical Specifications," Appendix A, DPR-16, April 1969. (2) National Council on Radiation Protection and Measurements, Report No. 93, " Ionizing Radiation Exposure of the Population of the United States," 1987. (3) CRC Handbook, "Radioecology: Nuclear Energy and the Environment," F. Ward Whicker and Vincent Schultz, Volume I I, 1982. (4) GPU Nuclear Corporation. " Oyster Creek Nuclear Generating Station Emergency Plan," Document Number 2000-PLN-1300.1, Revision 8, January 1983. I (5) National Council on Radiation Protection and Measurements, Report No. 22, " Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water

     'I                                                      for    Occupational Exposure," (Published as National Bureau of Standar:1s Handbook 69, Issued June 1959, supersedinj Handbook 52).

(6) International Commission on Radiological Protection, PubJ.ication 2, " Report of Committee II on Permissible ^ Dose for Internal Radiation (1959)," with 1962 Supplement Issued in ICRP Publication- 6; Publication 9,

               " Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations I.        of Publication 9 concerning environmental monitoring; and ICRP Publication 26 (1977).

. I 114

  ;            (7)  Federal Radiation Council Report No. 1, " Background Material for the Development of Radiation Protectico Standards," May 13, 1960.

(8) National Council on Radiation Protection and Measurements, Report No. 39, " Basic Radiation Protection Criteria," January 1971.

       ,+

(9) National Council on Radiation Protection and Measurements, Report No. 62, " Tritium in the Environment," March 1979. (10) National Council on Radiation Protection and I Measurements, Report Envir.vment," May 1985. No. 81, " Carbon-14 in the (11) United States Nuclear Regulatory Commission. Pcgulatory Guide 4.1, "Pr:cytams for Monitoring Radioactivity in The Environs of Nuclear Power Plants," Revision 1, April 1975. (12) United States Nuclear Regulatory Commission Branch

Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

(13) Teledyne Isotopes. " Procedures and Quality Assurance Handbook." IWL-00320365, 1975. (14) Radiation Management Corporation. " Analytical and Quality Control Program."

  ~

RMC-TM-75-3, 1975. (15) Toledyne Isotopes. " Environmental Psdiation Analysis Quality Control Manual." IWL-00320361, 1975. LI !. 115 l

I ' (16) United States Nuclear Regulatory Com.ission. Regulatory Guide 4.15, " Quality Assurance for Radiological l Monitoring Programs (Normal Operations) - Effluent Streams and the Environment," Revision 1, February 1979. I 1 I (17) NUREG/CR-4068 " Summary of Historical Experience with Releases of Radioactive Materials from Commercial Nuclear Power Plants in the United States", 1985. (18) Eisenbud, Merril, 1987. " Environmental Radioactivity." Academic Press. I (10) Weinstein, Roy, 1964. " Nuclear Physics." McGraw-Hill Book Company.

          0) GPU Nucler.r Corporation.
                                            " Final Safety Analysis Report,  j Oyster Creek Nuclear Generating Station," December 1991.

(21) GPU Nuclear Corporation. "1986 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1987. I (22) GPU Nuclear Corporation. "1987 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1998.

        .(23) GPU     Fuclear    Corporation.         "1988   Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station."    May 1980 t

lI ' ~ (24) GPU Nuclear Corporation. "1989 Radiological ( Environmental Mc,nitoring Report for Oyster Creek Nuclear !- Generating Station." May 1990. I 116 LI

.i ' !~ (25) GPU Nuclear Corporation. "1990 Radiological Environmental Monitoring Report for Oyster Creek Nuclear I Generating Station." May 1991. i i u-LI 4

I I l I

LI pg.

Il ri

;:I I

117 I

u

   .O I

I g APPENDIX A 1991 REMP Sampling Locations and Descriptionu, Synopsis of RDiP, and Sampling e.nd Analysis Exceptions

.I I

g I-I I I I 118 g.

                                                                                                                                                                                                                               - 3.
               ~~

i l TABLE A-1 l RADIOLOGICAL ENVIPONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS i Sample Station Medium Code Distance A=imuth 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, et Oyster Creek Pretreatment Building Lab, Forked River, NJ APT, AIO, RWA, 3 6.1 94 E of site, near Coast Guard Station TLD Island Beach State Park APT, AIO, RWA, 4. 4.5 215 SW of site, where Route 554 and the TLD Garden State Parkway meet, Barnega  ? ~' l a APT, AIO, itWA, 5 4.2 355 N of site, Carden State Parkway [ TLD Service Area, Forked River, NJ e TLD t 2.2 14 NNE of site, Lane Place, behind St. Pius Church, Forked River, NJ TLD 7 1.8 111 ESE of site, Bay Parkway, Sands Point Harbor, Waretown, NJ TLD 8 2.3 180 S of site, Route 9 at the 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 9ubstation, Allenhurst, NJ APT, AIO, RWA, C 35.1 309 NW of site, JCP&L office rear TLD parking lot, Cookstown, NJ

TABLE A-1 (continued) pat,IOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sampla Station Medium Code Dietance . Azimuth DescriptiSr APT, ATO, 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 SSU of site, 80th and Anchor Streets at Water Tower, Harvey Cedars, NJ TLD 12 9.4 192 SSW of site, Atlantic Electric substation l access road, Cedar Run, NJ [ TLD 13 e.3 345 NNW of site, Dover Road, next to last pole C) traveling west, South Toms River, *iJ APT, AIO, RWA, 15 18 1 N of site, Larrabee Substation on TLD Randolph Road, Lakewood, NJ TLD 15 19 509 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

l. high voltage line, New Gretna, NJ WWA 18 1.7 42 NE of site, Townsend's Macina, Lacey Road. Forked River, MJ

em as SWI asa sus sus ans saa aus e amp sus a m m uns sus ses seus TABLE A-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample Station Description Medium Code Distance Azimuth _ WWA 19 1.6 73* ENE of site, 1015 Inland Road, Forked l River Beach, Forked River, NJ APT, AIO, RWA, 20 0.7 .niles 93 E of site, on Finninger Farm on south side j of access road, Pole BT17, Forked River, NJ TLD 21 1.0 115 ESE of site. at 215 Dock Avenue, WWA Waretown, F. TLL, WWA 22 1.6 146 SE of site, at 27 Long John 511v2r way, Skipper's Cove, Pole #BT152 ON, Waretown, NJ SWA, CLAM, AQS 23 4.0 63 ENE of site, Barnegat Bay off Stouts Creek [ 4 0 yards SE of FL"1* w SWA, CLAM, AQS 24 2.0 104 ESE of site, Barnegat Bay, 250 yards SE of FL"3" SWA, CLAM, ACS 25 1.6 127 SE of site, Barnegat Bay off Moliday Harbor, 200 yards SE of lagoon mouth SWA, CLAM, AQS 31 10.5 183 S of site, Manahawkin Bay 25 yards SE of C ~23" and N ~24" SWA, AQS 32 1.9 98 E of site, mouth of Oyster Creek I discharge canal SWA, AQS, 33 0.7 104 ESE of site, 1200 yards east of Poute 9 FISH, CRAB Bridge in Oyster Creek Discharge Canal 35 0.4 110 4SE of site, east of Route 9 and North of the VEG, SOIL Discharge Canal, Forked River, NJ

                                                           =
                                                                                             ' i

M M .M M E E E .' E E E 'E E .E 'E E' E E E E I TABLE A-1 (continued)

                                                                   >OJ OGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Sample       Station Med'_um       Code        Distance      Azimuth                Description VGTN, SOIL       36         24 miles       325'        NW of site, at DeWolf's U-Pick Farm, New Egypt, NJ TLD              51         0.4            358         N of site, on the access road to Forked Riv2r site, Forked River, NJ TLD              52         0.4            340         NNW of site, on the access road to Forhed River site, Forked River, NJ TLD              53         e.3            310         NW of site, at the JCP&L Visitor's Center, Forked River, NJ

[ TLD 54 0.3 294 WNW of site, on the access road to rnrked u River si'e, Forked River, NJ TLD 55 1.5 273 W of site, next to Basin #1 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 roc.d , Pole BT 375, L, Forked River, NJ TLD 58 0.4 180 S of site, on Southern Area Stores access road, Pole JC-7-L, Forked River, NJ TLD 59 0.3 163 SSE of site, on Southern Area Stores access road, on gray post, Waretown, NJ TLD 60 0.4 136 SE of site, on Southern Area Stores access road entrance, Waretown, NJ l if

m m m m W W W m W W m m e e m m m W TABLE A-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S VPLING LOCATIONS Sample Station Medium Code Cistance Azimuth Description TLD 61 0.3 miles 116' ESE of site, on Route 9 south of Oyster Creek Main Ent ance, Pole BT1458, Forked River, NJ TLD 62 0.2 99 E of site, on Route 9 at access road to Main Gate, Pole PT-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 o' site, on Route 9 north of North Gate access road on Pole JC407X, Forked Risar, NJ [ TLD 65 0.4 22 NNF of site, on Route 9 at Intake Canal u Eridge on Pole JC406L, Forked River, NJ APT, AIO, RWA, 66 0.5 127 SE of s!te, east cf Route 9 and south of the TLD, VEG, SOIL Discharge Canal, inside fence, Waretown, NJ TLD 67 1.0 161 SSE of eite, on Routu 9 at waretown Plaza, Waretown, NJ l . TLD 69 1.3 70 ENE of site, at the intersection of h 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 Martin residence, Waretown, NJ i APT, AIO, RWA, 71 1.7 165 SSE of site, on Route 532 at the Waretown TLD Municipal Building, Waretown, NJ APT, AIO, RWA 72 1.9 27 NNE of site, at Community Hall, .

Forked River, NJ i

l i

m m a m W m M M m' W W m .m a mM W. M m-

                                                                                                                                                                    )

TABLE A-1 (continueo) RADIOLOGICAL ENVIRONMENTAL MOriITORING PROGPJ04 SAMPLING LOCATIONS Sample Station Medium Code Dietance azimuth Description APT, AIO RWA, 73 1.8 miles 111* ESE of site, on Bay Parkway, Sands Point TLD Harbor, Waretown, NJ TLD 74 2.0 90 E of site, Orlando Crive 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 TLD 76 1.7 51 NE of site, on Lacey RO*4 ceroes from Captain's Inn Restaurant, 2orked River, NJ [ TLD 77 1.5 26 NNE of site, NJ 5 tate Marina parking lot, A Forked River, NJ TLD 78 1.8 2 N of site,1514 Arient Road, Forked River, NJ TLD 79 2.9 162 SSE of site, Hightide E:ive and Bonita Drive Pole JCl24 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 arid School Streets, Pole JC257BGT, Barnegat, NJ fLD 82 4.4 38 NE of site, Bay Way and Clairmore Avenue, Pole JC1273L, Lanoka Harbor, NJ TLD 80 5.8 29 NNE of site, Route 9 and Harbor Inn Road, Pole BT666B, Berkeley, NJ

M M M M G M M M M M M M M M M M M M M m m.x _ TABLE A-1 (continued) RADIOLOGICAL ENVIRONMENTAL MO!!ITORING PROGRAM SAMP!.ING LOCATIONS Sample Station Medium Code Distance h.zimuth Description TLD 84 4.3 miles 339' NNW of site, on Lacey Road,1.3 miles west of the Gardea State Parkway on JCP&L siren pole, Forked River, NJ TLD 85 3.8 254 WSW of site, on Route 532 West, just prior tc landfill, Pola BT354, Waretown, NJ TLD 86 4.8 226 SW of site, on Route 554, 1 mile west of the Garden State Parkway, Barnegat, NJ TLD 87 7.2 143 SE of site, north of Seaview Drive on siren V 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 Par-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 Gut.d Shack / Toll Booth, Island Beach State Park SWA, AQS                                                             93         0.25             150             SSE of site, Oystar Creek Discharge Canal, west of the confluence of freshwater Oyster Creek

m M M M M M M ~M M W W W M M M M M. M M TABLE A-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITOR 7.NG PROGRAM SAMPLING LOCATIONS Sample Station Medium Code Distance &;imuth 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 Jimmies , CLAM, FIF9 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 95 2.5 243 WSW of site, at Ocean County VoTech School on JCP&L siren pole, Waretown, NJ to m TLD 96 1.1 15 NNE of site, at sewage pumping station across fr om Oyster Bay Restaurant, Forked River, NJ TLD 97 1.3 43 NE of site, at Twin Rivers sewage pumping station, Forked River, NJ g TLD T1 0.2 228 SW of site, at Oyster Creek Fire Pond, Forked River, NJ SAMPLE MEDIUM IDENTIFICATION KEY APT = Air Particulate SWA = Surface Water SOIL = Soil AIO = Air Iodine AQS = Aquatic Sediment FISH = Fish RWA = Precipitation CLAM = Clams CRAh = Crab WWA = Well Water VEG = Vegetables TLD = Thermoluminescent Dosimeter

I I TABLE A-2 g I SYNOPSIS OF THE OPERATIONAL RADIOLOGlG&fNVIRONtaENTR MONITORING PROGA2.:j CONDUCTED BY GPLIN ENVIRONMENTAL CONTROLS FOR OYSTER CREEK NUCLEAR GENERATING STATION I M l l I NU'ABER OF NUMBER OF NUMBER OF i SAMPLE SAMPUNG COLLECTION SAMPLES TYPE OF ANALYSIS SAMPLES TYPE LOCATIONS FREQUENCY COLLECTED ANALYSIS FREQUENCY ANALYZED (2) I Air Particulate 1? weekly 675 GR Beta Gamma weekly 4 week composite 675 169 Air lodine 13 weekly 675 1-131 weekly 675 Precipitation 13 4-week 52 Gamma 12-week 24 (2; combined for composite a 12 week 43 12 week 24 (3) 1 composite com;;; site j i Well Water 5 4 week 04 Gamma 4-week 64  !

 ~I                                                                                       H4 l131 4-week 4-week 64 64 l

4 l I Surface Water 8 4-week 104 Gamma H-3 l-131 4-week 4-week 4 week 104 104 104 l I l l I Clam Sediment 5 8 4 week 4-week 65 32 Gamma Gamr a 4-week 12-week composite 65 32 l Vegetables 3 4-week 30 Crmma 4-week D Soil (4) 3 12 week 6 Gamma 12-week .6  ; Fish 3 4-we ek 39 Ga mma 4-week 33 Crab 3 4-week 9 Gamma 4 week 9 63 12*ek

 -I     TLD-Teledyne isotopes 211           i.tvTiersion Dose 12 week      211 TLD-Panasonio             63                    12 week             323           Immersion          10-week      323 Dow
 -I                                                                                                                                      l (1)      This table does not include Ouality Control (OC) resutts.

(2) The number of samples analyzed does not include duplicate analyses, recounts or reanalyses. (3) Only composites from stations A, C, H,66,72, and 73 were analyze <t. (4) Onty collected when vegetables are collected. I

     -.                                               -        r~ aa -

l l 127 l

TABLE A-3 SAMPLING AND ANALYSIS EXCEPTIONS 1991 More than the minimum number of samples and analyses required by the Technical Specifications were collected and performed I No sampling and or analysis exception occurred during 1991. ia 1991 that resulted in a deviation from or violation of the requirements of the Technical Specifications. I I iI I I I I lI l E I I I 128 I ,

_ - .,a,- -,u+ I I I I I I I E I APPENDIX B 1991 f ower Limits of Detection (LLD) Exceptions 1 I I g i I. I 129

I I , TABLE B-1 TECHNICAL SPECIFICATIONS ANALYTICAL RESULTP NH:CH FAILED TO MEET THE REQUIRED LLD DURING 1991 No. of I Sample Media Analysis Required LLD Samples Out of Compliance Comments Air Particulate Gross Beta 0.01 pCl/m 3 1 Low Sample Volume Air lodine 1131 0.07 pCl/m 3 1 Low Sample Volume I I NOTE: More than the minimum number of samples and analyses required by the I Technical Specificatic were collected and performed so that none of the missed LLD values listed above tesulted in any violations of the Technical Specifications. I I I I I E l5 I i 130 lI-

I I I I-I I I I APPENDIX C Changes Effected in the 1991 REMP I I g I , I lI 1 131

I TABLE C-1 CHANGES EFFECTED IN THE 1991 REMP April, 1991 TLD station #79, originally located at on Bonita Drive at Barnegat Bay was relocated due to recurring vandalism. Tne station was relocated at the intersection of Bonita I and Hightide Drives, approximately 300 feet west of the original location. This station is a co-location with both NRC and NJDEPE TLDs. Both regulatory agencies were notified in writing prior to the ralocation providing applicable data. I July, 1 Tr4e REMP TLD network surrounding the OCNGS consists of 63 field stations. Prior to this date, both GPUN Panasonic and Teledyne Isotopes (vendor supplied) TLDs were exposed at each location. Years of data and numerous comparison studies indicated that the Teledyne Isotopes network was redundant and unnecessary. Therefore, i.nis TLD network was downgraded from 63 to 10 monitoring locations. Seven of these stations are located with NRC a nd; ' -- NJDEPE I dosimeters while the remaining three dosimeters are located at background stations. These 10 monitoring locations are quality control stations. The Panasonic ,. TLD network was not altered in any way. I I I I I 132 I

I 3 I I I I I g l I APPENDIX D 1991 Quality Ass *1rance Results I I , . I I E I I

 !                               133

L The Oyster Creek Environmental Controls REMP Quality Assurance (QA) Program consists of three phases. Phase I consists of splitting samples collected at designated stations and having t them analyzed by separate (independent) laboratories. I Analysis results from the ciuality control (QC) laboratory are compared to those from the primary laboratory as set forth in OC Environmental Cvitrols procedure 6635-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 samples in question. I Phase II requires that laboratories analyzing REMP aamples f or I Oyster creek participate in the USEPA Cross-Check Program. This serves as independent verification of their ability to correctly perform sample analyses. Results of this interlaboratory comparison program are presented in Appendix E. I Phase III requires that the REMP analytical laboratories perform duplicate analyses on every twentieth sample. The number of duplicate analyses performvd in 1991 is outlined in Table D-1. Results of the two analyses were reviewed per I procedure 663 5-ADM-4 500. 07. No non-agreements occurred during 1991 regarding duplicate analyses of OCNGS REMP samples. Table D-2 outlines the split sample portion (Phase I) of the QA program 'or the media collected during 1991. Three non-agreem . 's occurred between analyses in 1991. All of the I non-agreements involved the naturally-occarring isotope K-40. Investigations were conducted in an attempt to resolve these non-agreements. The results of these investigations are i summarized in Table D-3. I 134 I

TABLE D-1 1991 OA SAMPLE PROGRAM NUMBER OF DUPLICATE ANALYSES PERFORFlQ ANALYSls SAMPLE GROSS GAMMA-MEDl17M DXTA IL-1 I .1._3.1 ISRT_QPlc I AIR PARTICULATE 22 11 I AIR IODINE 46 I RAIN WATER 1 1 i WELL WATER 5 5 l 1 l SURFACE WATER 5 4 8* I AQUATIC SEDIMENT 2* , CLAMS S* VEGETABLES 1 SOIL 1 FISH l 1

• 1 DUPLICATE ON QC SAMPLE I

E 135 I

TABLE D-2 , 1991 OA SAMPLE PROGRAM SPLIT SAMPLES NUMBER OF NUMBER OF OA SAMPLE SAMPLE MEDIUM REGULAR COLLECTION FREOVENCY QA COLLECTION FREQUENCY STATONS STATONS I PRECIPITATON 13 MONTHLY 1 OUARTERLY COMPOSITE WHEN AVAILABLE SURFACE WATER 8 MON (HLT 1 OUARTERLY WELL WATER 5 MONTHLV CUARTERLY I 1 CLAMS 5 MONTHLY 1 QUARTERLY I SOIL 3 CUARTERLY WHEN VEGETABLES AVAILABLE 1 QUARTERLY WHEN VEGETABLES AVAP.ABLE I SEDIMENT 'l MONTHLY 1 OUARTERLY COMPOSITE I VEGETABLES 3 MONTHLY 1 OUARTERLY I WHEN AVAILABLE WHEN AVAILABLE I I I 136 I

I I I I I TABLE D-3 RESOLUTON OF OCNGS REMP SPUT SAMPLE ANALYTICAL NON-AGREEMENTS AGTEMENT AFTER NMALYSIS I SAMPLE MEDIUM SAMPLE IMTE NUCUDC EASON FOR NON-AGREEMENT SURFACE WATER 2 M 91 K40 YES I -

                                                                                                  )
                                                                                                  \

SURFACE WATER 4-N91 K40 SAMPLE DtSCARDED - I COULD NOT BE RE-ANALYZED I AQUATC SED! MENT 7-22 91 K40 NO NON-HOMOGENEOUS DISTR:BUTON OF RADIOACTMTY lN SEDIMENT I I I I I I 137 I l

.J I I i l-i r l APPENDIX E i l' 1991 US EPA Cross-Check Results l

l. ! .

b j . l- !I i I 138 LI

I I

                                                                                               . .a =
  ~I                                                            1ABLE E-1 OTSTER CREEK NUCLE AR GEhERATING ST ATION US EFA CROSS-CHECK PROGRAM 1991 DATE       MEDIA       NUCLIDE           EPA RESULTS (A)          ERL RESULTS (B)*       T l R E SUL T S ( B )*

• St-89 5.0 t 8.7 I

JAW 1991 WATER No DATA (C) 5.0 s 0.0 Sr 90 5.0 a 8.7 NO DATA (C) 5.0 0.0 Pu 239 3.3 0.5 No DATA (C) 3.6 0.1 Gross Alpha 5.ti 8.7 6.3 1.2 9.0 t 1.0 Cross Beta 5.0 t 8.7 5.7 0.6 7.0 t 1.5

   =

FEB 1991 WATER Ba-133 75.0 : 13.9 79.7 1.2 75.7 1 5.5 co-60 40.0 t 8.7 40.3 0.6 39.3 3.1 Cs 134 8.0 t 8.7 7.7 a 2.1 7.3 2 0.6 Cs-137 8.0 t 8.7 8.7 0.6 7.7 3.2 I Ru-1D6 2n-65 H3 186.0 s 149.0 t 4418.0 s 766.8 33.0 26.0 183.3

                                                                                 '46.7 t 11.6 5.8 4533.3 a 57.7 176.7 t 17.6 147.0 a 4500.0 1.0 173.2 1-131                75.0 t         13.9      77.7 e     1.5           80.0 t      5.3 I         MAR 1991   WATER       Ra 226 Ra 228 U (Nat.)

31.8 1 21.1 7.6 1.3 9.2 5.2 NO DATA (C) No DATA (C) NA SAT A (C) 28.3 2 16.7 a 7.3 s 4.7 2.1 0.2 MAR 1991 AIR ftLTER Cross Alpha 25.0 s 10.4 33.3 0.6 42.7 0.6 (D) Crots Seta 124.0 10.4 123.0 a 2.7 126.7 : 5.8

                                    $r 90                40.0 a           3.7     No DATA (C)            37.0 s      1.0 Cs-137               40.0 t           8.7     48.7 t     1.2         43.0 t      5.3 I          APR 1991 WATER       Gross Alpha cross Beta Ra 226 54.0 e 115.0 t 8.0 e 24.3 29.5 2.1 48.3 107,7 t No DATA (C) 1.5 0.6 59.7 110.0 t 7.3 t 4.0 0.0 0.8 Ra-228                  15.2         6.6     No DATA (C)             10.0 t      0.0 I                               U (Nat.)

sr-89 Sr 90 Cs-134 29.8 28.0 26.0 t 24.0 t 5.2 8.7 8.7 8.7 ho DATA (C) No DATA (C) ho DATA (C) 23.7 e 1.2 30.3 2 31.0 a 21.0 t 25.0 0.6 1.0 0.0 1.0 Cs+137 25.0 t 8? 26.3 1.5 24.0 t 1.7 APR 1991 MILK Sr 89 32.0 t 8.7 No DATA (C) 24.0 t 3.0 Sr-90 32.0 2 8.7 ko DATA (C) 26.3 a 2.1 1-131 49.0 2 10.4 61.7 2 0.6 53.3 a 2.3 I MAY 1991 WATER Cs-13T K 40 (Nat.) Sr-89 49.0 a 1650.0 e 144.0 39.0 t 8.7 8.7 50.3 1.5 1733.3 a 35.1 k0 DATA (D) 52.7 a 1590.0 s 81.9 38.7 2 1.5 4.5

                                     $r 90                     24.0 t      8.7    No DATA (D)             22.0 t      1.7 I         JUN 1991  WATER Cross Alpha Gross Beta Ba 133 24.0 a 46.0 e 62.0 a 10.4 8.7 10.4 33.7 s A7.3 t 65.0 t 1.5 0.6 1.7 24.3 50.3 t 56.3 2.5 1.5 1.5 10.0 t I

Co-60 8.7 10.3 a 0.6 10.3 0.6 Cs 134 15.0 t 8.7 13.7 a 1.5 13.7 a 1.5 Cs 137 14.0 t 8.7 15.7 1.2 13.7 a 1.5 H-3 12480.0 a 2165.2 13000.0 t 0.0 12533.3 115.5 Ru 106 149.0 s 26.0 150.0 10.0 156.7 3.8 2n-65 108.0 19.1 110.0 t 0.0 106.0 s 2.7 JUL 1991 WATER Ra 226 15.9 4.2 No DATA (C) 15.0 1.0 Ra 2E8 16.7

• 8.7 ho DATA (C) 14.3 a 2.3 U (Net.) 14.2 2 5.2 13.3 2 0.6 I

No DATA (C) AUG 1991 6ATER l 131 20.0 t 10.4 20.3 1.5 19.3 s 0.6 Pu-239 19.4 1 3.3 No DATA (C) 20.3 2 0.6 I AUG 1991 AIR FILTER Gross Al@ a Gross Bete Sr 90 Cs 137 25.0 e 92.0 t 30.0 t 30.0 t 10.4 17.3 8.7 8.7 32.7 2 93.7 a No DATA (C) 35.3 : 1.5 0.6 2.1 27.0 2 100.0 t 27.7 a 33.3 1 2.0 0.0 2.9 3.2 I 139 I

~ I 1ABLE E 1 OYSTER CREEK NUCLE AR CEhER AtlkG ST ATION US EPA Cross CHECK PROGR AM 1991 OATE MEDIA NUCL10F [P A RE SUI,TS ( A) E RL RE SULTS (91* Tl RESULTS (B)** I SEP 1991 WATER St-89 49.9 a 8.7 ho DATA (C) 50.7 s 2.9

                                                                                           $r-90               25.0 a                 8.7     NO DATA (C)         26.0 a   1.0 Cross Alpha         10.0 a                 8.7      14.7 2   2.3       11.7     0.6 Cross Ceta          20.0 t                 8.7      21.0 t   0.0       21.0 s   0.0 I    SEP 1991                   MILK                                                      Sr 89
                                                                                           $r-90 1 131 Cs 137 25.0 a 25.0 108.0 a 30.0 :

8.7 8.7 19.1 8.7 NO DATA (C) ho DATA (C) 98.7 a 31.3 t 2.3 0.6 21.0 a 19.9 113.3 s 29.0 a 2.7 0.0 5.8 3.6 s-40 (het.) 1740.0 150.9 1700.0 t 0.0 1503.3 75.1 (E ) OCT 1991 WATER Co 60 29.0 t 8.7 30.7 s 2.5 30.3 2 2.1 2n ^5 13.0 a 12.1 74.3 a 3.1 72.7 : 7.1 Ru 1ld 199.0 a 34.7 199.0 11.1 197.7 7.5 I 10.0 s 8.7 10.0 1.0 0.6 Cs-134 10.3 a Cs-137 10.0 a 8.7 11.0 s 0.0 T 0.6 Ba 133 95.0 17.3 101.7 e 1.5 ' ia 8.7 H3 2454.0 a 610.7 2333.3 2 115.5 L. ,t 57.7 Cross Alpha B2.0 a 36.4 66.7 a 2.3 55.0 4.4 I cross 6 eta Ra-226 Ra 228 U (Nat.) 65.0 22.0 t 22.2 a 13.5 2 17.3 5.7 9.7 5.2 53.7 t Wo DATA (C) ko DATA (C) 1.5 No DATA (C) 56.0 21.0 t 18.0 12.7 1.0 2.7 1.0 0.6 10.0 t 8.7 I Sr-89 ko DATA (C) 10.7 a 2.1 Sr 90 10.0 8.7 No DATA (C) 9.3 0.6 Co-60 20.0 t 8.7 19.3 a 2.1 19.7 0.6 Cs-134 10.0 8.7 10.0 1.0 10.3 2.1 Cs 137 11.0 a 8.7 12.0 t 1.0 13.7 t 0.6 h0V 1991 WATER Ra 226 6.5 1.7 No DATA (C) 5.4 0.3 Ra-228 8.1 2 3.5 No DATA (C) 7.9 s 1.2 O (Nat.) 24.9 e 5.2 he DATA (C) 24.3 0.6

• CPUN ERL - The Ervirorsnental Radioactivity Laboratory located in Middletown, PA.

        ** T1 - Teledyne isotopes Westwood Laboratory located in Westwood, NJ I     A. EPA Results - Expected Laboratory precisten (* 3 sigr a, n=3 control limit). Units are pCi/L for water and milk except K HAT is in mg/L. Units are total pCi for air particulate filters.

Units for food are pCl/kg. B. Results Average one stardard deviation. Units are pCi/L for water and milk except K-HAT is in mg/L. Units are total pCi for air particulate filters. Units for food are pCi/kg. C. No data available. Analysis not performed by laboratory. I 0. The sanple presente a dif f erent counting geometry. The EPA deposits activity in a 3/4 inch diameter circle, en a plastic disk approminately 3/32 inch thick. A special calibration for EPA filters will be cerformed. The laboratory has obtained blank filters f rcen the Las Vegas f acility, and will sinulate their deposits. I E. There is no apparent cause for the low K 40 results. Two other isotopes spiked in the sanple were in good agreement with EPA values. Unit conversions were reviewed arvi f ound to be correctly applied. Possible background errors in geometry were investigated and found to have an insignificant effect. I I I 140 I

I I I I I I I I x ,, ,,, , , 1991 Annual Dairy Census I I ~ I I I I I I 141

I ADnual Dairy Census - 1991 ocean County Agricultural Agent, hs. Deborah Smith-Fiola, was contacted regarding the occurrence of dairy animals within a I five mile radius of the OCNGS. According to her records for 1991, there are neither any commercial dairy operations nor any dairy animals producing milk for human consumption within a five mile radius of OCNGS. I I I I I I I  : I I I I I I 142 I

I i I I I c I I I APPD1 DIX G Dose Calculation Methodology I I I I I I L 8

 .                                1c

To the extent possible, radiological impacts were evaluated based on the direct measurement of dose rates or of radionuclide concentrations in the environment. Ilowever, the i quantities of radionuclide releases associated with 1991 OCNGS operations were often too small to be measured once dispersed I in the offsite environment. As a result, the potential offsite doses could only be estimated by using computerized models that predict concentrations of radioactive materials in the environment and subsequent radiation doses on the basis of radionuclides released to the environment. GPUN calculates doses using an advanced class "A" dispersion model called SEEDS (Simplified Effluent Environmental Dosimetry System). This model incorporates the guidelines and methodology set forth in USNRC Regulatory Guide 1.109. I meteorological information matched to the time of releases to SEEDS uses hourly assess the dispersien of effluents in the discharge canal / estuary system and the atmosphere. Combining this assessment of dispersion and dilution with effluent data, postulated maximum hypothetical doses to the public from the OCNGS effluents are calculated. The maximum individual dose is calculated as well as the dose to the total population within 50 miles of OCNGS for gaseous effluents and the entire population downstream of the OCNGS around Barnegat Bay and the I Atlantic Ocean for liquid effluents. Values of environmental parameters and radionuclide concentration factors have been chosen to provide conservative results. As a result, the doses calculated using this model are conservative estimates (i.e., overestimates) of the actual exposures. I The dose summary table, Table G-1, presents the maximum hypothetical doses to an individual, as well as the population doses, resulting from effluents from OCNGS during the 1991 reporting period. I I 144 I

I Individual Doses From Liauld Effluents As recommended in USNRC Regulatory Guide 1.109, dose calculations are performed on four age groups and eight organs I (Table G-1) . The pathways considered are consumption of fish, consumption of shellfish, and shoreline exposure. All pathways are considered to be primary recreational activities associated with Barnegat Bay and the Atlantic Ocean in the vicinity of the OCNGS. The " receptor" would be that individual who eats fish and shellfish that reside in the station discharge, 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 I affected. For the 1991 reporting period, the calculated maximum hypothetical total body dose received by anyone from liquid effluents would have been 2.04 E-5 mrem to a teenager. This represents 6.80 E-4 percent of the OCNGS Technical Specification annual dose limit. Similarly, the maximum hypothetical organ dose from liquid effluents would have been

8. 65 E-S mrem to the GI-LLI of an adult. This represents 8.65 E-4 percent of the OCNGS Technical Specification annual dose _

limits. Individual Doses From Gaseous Effluents There are seven major pathways considered in the dose calculation for gaseous effluents. These are: (1) plume I exposure, (2) inhalation, (3) consumption of cou milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing on contaminated ground. I The maximum plume exposure reported in lines 3 and 4 of Table G-1 generally occurs at, or near, the site boundary. These

      " air doses" are not to an individual but are considered to be I                                    145 I

the maximum dose at a location. The location is not necessarily a receptor. It should be noted that real-time meteorology was used in all dose calculations for gaseous effluents. With respect to airborne noble gaseous releases for the 1991 reporting period, the maximum pluma exposure (air dose) would have been 1.48 E-2 and 1.12 E-2 mrad for OCNGS gamma and beta D z radiation, respectively. These doses are equal to 1.48 E-1 L percent and 5.60 E-2 percent of the OCNGS Technical Specification annual dose limits, respectively. I The calculated airborne doses to the closest individual was at b I a distance of 1208 meters in the maximally af fected sector (NE) . These data are presented in lines 5 and 6 of Table G-1. Plume exposures to an individual, regardless of age, from gaseous effluents during the 1991 reporting period were 6.19 E-3 mrem to the total body and 7.64 E-3 mrem to the skin. These doses are equivalent to : 4 E-1 percent and 5.09 E-2 percent of the 10CFR50, Appendix I annual dose limits, respectively. 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 l which was separated out on line 5. The dose presented in this section reflects the maximum exposure to an organ for the appropriate age group. During 1991, gaseous iodines and particulates from OCNGS would have resulted in a maximum dose I of 7.62 E-2 mrem to the thyroid of an infant. only 5.08 E-1 percent of the OCNGS Technical Specification This dose is annual dose limit. I I 146 I

l Population Doses From Liauid and Gaseous Effluents The population doses resulting frota liquid and gaseous effluents are summed over all pathways and the affected population (Table C-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 I population dose due to gaseous effluents is based upon the 1980 population projections of the Final Safety Analysis 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 2.22 E-1 person-rem total body for the 1991 reporting period. This is approximately 4.5 million times love- than the doses to the same population resulting from natural background sources. I I - I I I I I I 147 I

I I TABLE G 1 JEM ARY OF man! MUM HYPOTHETICAL INDMDUAL AND POPULATLQN DOSES I LR,QM LOUtD AND AIR 90RNE EFFLUENT REtEASES FROM THE OCNGS FOR 1991 Regulatory Urnits Location Calculated Percent I 1. Effluent Released UQUID mrem / Year 3 mrem Source Tech. Spec. 3 6.J.1 Dose mnem/ year 2.04 E 5 Age Group Teen Dist (m) 610* Dir (toward) SE* Regulatory Umit 6 80 E-4 , , Total Body

2. UOulD 10 mrem Tech, Spec. 3 6 J 1 8 65 E-5 Adult 610* SE' 8 65 E-4 Any Orcan i 3.

4. AIRBORNE (Noble Gas) AIRBORNE 10 mrad Gamma Rad.at.on 20 mrad Tech. Spec. 3 6 L1 Tech Spec. 3 6.L1 1.48 E-2 1.12 E.2 500 400 NE ENE 148 E 1 5 60 2 I P4oble Gas) Beta Rad;ation

5. AIRBORNE 5 mrem 10CFR50 App. I 6.19 E 3 All 1208 NE 1.24 E-1 P4oble Gas) Total Body I 6. AIRBORNE Pbble Gas) 15 mrem Skin 15 mrem 10CFR50 App,1 Tech,Soec.36 M.1 7.64 E-3 A!! 1208 NE 5.09 E 2

7. AIRBORNE 7.02 E 2 Infant 1006 ESE 508E1 (lodine and Any Organ 8

Particulate) Population Deses Calculated I Effluent Applicable Dose Released Organ (Person-rem)

8. UQUID Total Body 2 41 E 3

9. UQUID GLLU 1.30 E-2 I 10.

11. GASEOUS GASEOUS

                                             - Total Body Thyroid 2.20 E-1 5.80 E 1
                      *O S. Route 9 Bridge - OCNGS Discharge Canal I

I 148 I

g I

I I I I I I I APPENDIX H 1991 Groundwater Monitoring Results I .I I I g ,I 149

I TABLE H 1 OCNGS - GROUNDWATER RESULTS CONCENTRATION IN DCi/ LITER * /- 2 STANDARD DEVIATION MARCH 1991 I STATION TRITIUM RESULTS GAMMA ISOTOPIC RESULTS I OC-WW-1 OC-WW 2 OC-\%%3

                                  < 190
                                  < 170
                                  < 190 ALL NUCLIDES < LLD ALL NUCUDES < LLD ALL NUCLIDES < LLD OC-WW-4                    < 190            ALL NUCLIDES < LLD I     OC-VAV-5 OC-VAV4 OC-\%V-7
                                  < 190
                                  < 190 ALL NUCLIDES < LLD ALL NUCUDES < LLD ALL NUCUDES < LLD 210 + /- 110 I    OC-WW-9 OC WW-10 OC-WW 14
                                  < 170 210 + /- 110 210 + / 110 ALL NUCLIDES < LLD ALL NUCL! DES < LLD ALL NUCLIDES < LLD OC-WW-15                                    ALL NUCUDES < LLD I    OC-WW-16 OC-WW 17 190 + /- 110 220 + /.120
                                  < 170 ALL NUCUDES < LLD ALL NUCLIDES < LLD I                                   SEPTEMBER 1991 I    STATION             IRITIUM RESULTS       _G/,MMA ISOTOPIC RESULTS OC-WW-1                    < 150            ALL NUCLlDES < LLD       =

6 OC WW 2 < 150 ALL NUCUDES < LLD OC-WW 3 - < 150 ALL NUCUDES < LLD OC-WW-4 < 150 ALL NUCUDES < LLD E OC4W/-5 < 150 ALL NUCUDES < LLD OC-WW-6 < 150 ALL NUCUDES < LLD OC-WW-9 150 + /- 100 ALL NUCLIDES < LLD I OC-WW 10 OC-WW-12 OC WW-14

                                  < 150 160 + /- 100
                                  < 150 ALL NUCLIDES < LLD ALL NUCUDES < LLD ALL NUCUDES < LLD I  OC-WW-16 OC-\W/17
                                   < 150
                                   < 150 ALL NUCUDES < LLD ALL NUCUDES < LLD
  .I I

I 150 I

i I I Figure 11-1 g Locations Of On-Site Wells l 1 Turbine Generator Buildine Kev 6 Warehouse l I ~ Reactor Bldg 3 Maintenance Oldg 7 Rad Waste 8 Guard llouse 9 Office Uldg 4 Off-Gas Bldg I 5 Waste Storage 10 Engineering Bldg 11 Parking Lo' I O SUBSTATION W-1 r

                                                                   \                     /

l DISCHARGE CANAL

                                                                                     /

8

                                                                                        /                   INTAKE CAh il
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• I g W-2 W-3 W-4 eo W-Go e i

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I W e 1 l F L 7 I

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3 - x I 10 9 E Y ~ W-12 ,e"-13 I oH 3 .. w_9 W-10 F1 e 7 1

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4 W-15 W-14l 6 I 9 11 W- 17 151 I I

.I I I g I I I -

                                                                    -t -

I APPENDIX I 1991 REMP Sample Collection and Analysis Methods I I _ I I I I I I 152 I

M M M M M M M M m m m m M M M M M M i TABLE I-1 l i AAD1010GICAL ENVIROR" ENTAL MOMITORI C FPOGDAM

SUMMARY

OF SMPLE Cott ECTION AND ANALYSIS METHODS f un Collection Appro/ wte Analysis l Procedure Sample Site Procedure Procedure > Sample Semplino Meti d  %+r Co m etad N u-te r Abttract Analysis Medim TMI-EC tow background gas Gr-Beta AP7 Continuous wed.ly or more DC-EC 1 filter , frequent air sampling 6635-!MP-4522.05 (approximately 600 6615-IMP-4592.05 flow proportional  ! cubic meters weekly) counting l through filter paper l kl

            '                     Four week composite of        OC-EC                     4 filters              TMI-EC           Gama isotopic               ,

Gsms API 6635-lMP-4522.05 (approximately 2400 6615-lMP-4592.05 analysis  ! Spectro- each station scopy cubic meters) 1 cartridge TMI-EC da u isotopic Garms A10 Continuous weekly or more OC-EC frequent air sampilng 6635-IMP-4522. 05 (approximately 600 6615-0PS-4591.04 analysis Spectro-scepy through charcoal cart,6dges cubic meters wed ly) 7.5 liters TMI-EC Game isotopic Ga ma SWA Four week grab sanple OC-EC g 6635- 1MP-4 522.06 E615-IMP-4592.06 analysis Ut .5pec t ro-W 6615-095-4591.04 sccpy TI-Vestwood Gama Isotopic PRO-042-5 analysis minimum of 0.5 liters TMI-EC Gama isotopic Gama RVA Twelve week composite OC-EC 6635-IMP-4522.07 6615-IMP-4592.06 analysis Sp ctro-6615-0P5-4591.04 scapy

                                                                                                                                     ,a  Isetopic TI-Wastwood      Ga FRO-042-5        analysis 7.5 liters             TMI-EC           Gama isotopic Gama        WA     Four week grab sample         OC-EC 6635-IMP-4522.10                                 E615-IMP-4592.06 anslysis Spectre-6615-095-4591.04 scopy TI-Westwood      Gama Isotopic F20-042-5        analysis 1 kg                   TMI-EC           Game tsotepic Gama        CLAM   Four week grab sample         OC-EC 6635-IMP-4522.14          (if possible)          6615-IMP-4592.03 enalysis Spectro-    FISH   Semiannual grab sample Semiannual grab sample        E635-IMP-4522.16                                 66I5-0P5-4591.04 scopy       CRAB TI-Westwood      Gama Isotopic PRO-042-5        analysis
                                                                ,                                 ,y

m W M- M M M M M M M M M M m mm e m M TABLE l-1 (Continued) RADIOLOGICAL ENVIPON" ENTAL MONITORING PROGRAM StmARY OF SAMPt.E COLLECTION AND ANALYSIS METHODS 1221 Collection Approximate Analysis Sample Procedure Sample Size Procedure Procedure Analysis Medium Samolino Method Number Collected N'. rte r Abstreet Garuna AQS iwelve week composite DC-EC 3.8 liters TMI-EC Gama isotopic Spectro- of each station analysis scopy SOIL Twelve week grab sample 6635-IMo-4 522.03 (if possible) 6615-IMP-4592.04 Ga-rna isotopic

                                                                                 .(when vegetables             6635-lMF-4522.08                                6615-CPS-4591.04  analysis are avsilable)

TI-Westwood Game Isotopic PRO-042-5 analysis Gama VEG Four week grab sample OC-EC 1 6 g or more Spectro-TMI-EC Game isotopic 0635-lMP-4522.04 (if possible) 6615-Iw?-4592.03 enalysis scopy 6615-0P5-4591.04 g II-Westwood Gama Isotopic Ut a PRO-042-5 analysis Tritium SWA Four week grab sample OC-EC 7.5 liters TMI-EC Sample mined with 6635-luP-4522.06 5615-!MP-4592.02 scintillation 6515-OPS-4591.05 fluid for scintillation count f ng. TI-West-vxt Water converted to P40-052-2 hydrogeft, methane added for gas counting. Tritium RL'A Twelve week OC-EC Minian of TMI-EC Sample mixed with a compostte sample 6635-!MP-4522.07 0.5 liters ES15-!MP-4592.07 scintillation . 6515-CPS-4591.05 fluid for i scir:t i l lation counting. TI-Westw W Water converted to FRG-052-2 hydrogen. methare addad for gas counting.

                                                                                                                                                     ....q M M        M         M         M        M        M         M        M      'M          M   'M M M     M        M.M                M         M TABLE l-1 (Crntinued)

RADIOLOGICAL ENVIPONMENTAL MONITOUNG PR0r4AM StrMAR" 0F SAMPLE C0ttiCTION AND ANALYSIS _fiH005 1221 Collection Approntmate Analysts Sample Size Procedare Proce6;re Sample Procedure Weber Collected N'rber Abstreet Analysis Medium Sam lino Method 7.5 liters TMI-EC Sample mired with Tritium WA Four week grab sample OC-EC 6635-IMF-4522.10 6515-1MP-4592.02 scintillation 6615-095-4591.05 fluid for scintillation counting, l TI-Westwood Water converted to PRO-052-2 hydrogen, cue *,hane added fer gas counting. Imnrsion Dosineters exchanged OC-EC Four Badges TMI-Dosimetry Themoheinescent Tto 9100-OPS-4243.01 dostmetry (Panasonic) Dose quarterly 6635-IMP-4522.02 P One Badge TI-Westwood The m lu=inescent W iLD Iwersion Dosimeters enchanged OC-EC

• quarterly 6635-!MP-4522.02 Pro-342-17 desinetry (Teledyne Dose Isotopes)

 }'

I  ! I- i I l I I  ; I-APPENDIX J 1991 TLD Quarterly Data I I LI ,g . I LI I I 156 E

l. l I TABLE J 1 OYSTER CRifK NUCLIAR GENERAt!hG STATION

• thVlR0hME4fAL CONTROLS 1991 QUARTERLY EkVIR0hMf hTAL TLD REPORT RUNNING TABLE TELEDthf ISOTCT'll MiiLIRIM PER STANDARD MONin AND 2 STANDARD Dtv!A110NS First Period 1901 Second Period 1991 Third Period 199*. Fourth Period 1991 Fifth Period 1991 Station Reading Std. Dev Reading Std. Dev Readirk Std. Dev Reading Std. Dev Reading Std. Dev 3.7 0.4 3.3 0.5 4.5 0.3 3.7 I

A 0.2 5.3 0.3 C 3.6 0.2 3.6 0.2 3.7 0.4 3.4 '0.2 4.1 0.1 W 3.4 0.2 2.8 0.2 5.2 0.3 3.3 0.2 3.8 0.1 1 4.3 0.3 3.3 0.5 4.2 0.7 * * *

• 3 4.6 0.3 3.5 0.3 3.9 0.2 * * *
• 4.0 0.2 2.6 4.3
• I 4 0.1 1.1 * *
• 5 3.4 0.2 3,3 0.4 4.1 0.2 * * *
• j 6 4.4 0.1 3.5 0.3 5.1 0.4 * * *
• 7 3.2 U.7 2.6 0.3 3.8 0.2 * * *
• 8 3.5 0.2 2.9 0.3 4.1 0.1 3.3 0.3 5.. 0.1 9 3.5 0.3 2.9 0.2 4.2 0.3 * * *
• T1 4.7 0.4 3.7 0.5 4.6 0.2 * * *
• to I

4.9 0.5 3.5 0.2 3.9 0.3 * * *

• 11 3.1 ^2. 3.3 0.2 3.8 0.1 * * *
• 12 3.6 0.2 3.7 0.2 5.3 0.4 * *
• e 3.3 0.3 1 g 13 2.6 0.3 5.2 0.3 * *
• 14 4.3 0.3 2.9 0.3 3.5 0.2 4.1 0.4 5.6 0.6 3.5 0.2 3.7 0.4 4.2 I'

15 0.2 * * * *

             '{        4.0          0.3         3.5          0.3        3.8           0.2         *            *          *

• 17 4.0 0.3 2.8 0.2 3.9 0.2 * * *
• 20 3.3 0.1 2.7 0.2 '3 . 8 0.3 * * *
• 22 3.3 0.3 3.5 0.2 3.9 0.1 * * * *

            $1        4.1          0.2          4.3          0.3       4.7            0.4        *            *           *

• 52 4.7 0.3 3.9 0.4 5.2 0.3 * * *
• I 53 4.0 0.2 3.7 0.4 6.2 0.5 * * *
• 54 3.4 0.3 2.7 0.2 3.9 0.4 * * *
• 55 3.5 0.2 3.2 0.2 5.4 0.2 * * *
• 56 4.0 0.3 3.5 0.2 6.1 0.4 * * *
• 57 5.5 0.6 3.9 0.4 5.6 0.8 * * *
• l 58 5.3 0.5 3.2 0.2 4.1 0.2 * * *
• 59 4.4 0.2 4.4 0.1 4.9 0.4 * * *
• I 60 3.4 0.1 3.1 0.1 5.0 0.2 * * *
• l l l 1 NOTE: TeleW ne isotopes TLD Secondary network reduced to ten (10) stations after the third reporting period.

157 I

I fABLt J 1 OY$1[R CR[EK WuCLEAR CEktRAilWG $1AllON - EkylRchutNtAL CONTROL $ 1991 QUARTERLT ftvitowMIk1AL TLD REPORT

• ItLEDYht IS010 Pts RUNN!kG 1 ABLE MILLIREM Pf D ST AND ARD MOhf M AND 2 ST ANDARD DEVI Ai!Dh5 First Period 1991 Second Period 1991 Third Period 1991 Tourth Period 1991 Fifth Period 1991 Station Reading Std. Dev Reading Std. Dev Reading Std. Dev Reading Std. Dev Reading Std. Dev 3.4 0.2 3.0 0.2 5.8 0.2
• I 61 * *
• 62 3.5 0.2 3.8 0.3 5.9 0.1 * * *
• 63 3.6 0.4 3.2 0.2 6.0 0.6 * * *
• 64 4.6 0.9 3.0 0.1 4.2 0.3 * * *
• 65 3.5 0.2 3.2 0.4 4.1 0.3 * * *
• I 66 3.4 0.2 4.1 0.6 4.2 0.2 3.1 0.2 4.8 0.2 67 3.6 0.6 4.0 0.2 4.4 0.2 * * *
• 69 3.3 0.1 3.8 0.2 4.1 0.2 * * *
• 70 3.2 0.4 3.0 0.1 4.0 0.2 * * *
• 71 3.4 0.3 3.4 0.4 4.2 0.2 * * *
• 73 3.2 0.2 3.9 0.2 4.1 0.1 f t.D L OST TLD LOST 74 3.2 0.2 3.1 0.2 5.6 0.9 * * *
• I 75 36. 0.2 4.1 0.4 5.6 0.2 * * *
• 76 3.2 0.1 3.0 0.2 4.2 0.2 * * *
• 77 3.2 0.3 3.1 0.3 5.6 0.5 * * *
• 78 3.3 0.3 3.2 0.2 4.2 0.1 * * *
• 79 TLD LOST 2.9 0.1 4.3 0.3 3.0 C.1 3.7 0.2 80 3.3 0.3 3.6 0.3 4.2 0.1 * * *
• 81 3.6 0.2 3.6 0.3 4.6 0.1 * * *
• 4.7 I

82 0.5 TLD LOST 4.7 0.3 * * *

• 83 3.4 0.6 3.3 0.2 4.7 0.8 * * *
• 84 4.3 0.4 3.4 0.2 4.6 0.1 * * *
• 85 4.7 0.2 3.2 0.2 5.0 0.1 * * *
• 86 4.4 0.3 3.2 0.3 4.6 0.4 * * *
• I 87 4.2 0.3 4.4 0.3 4.3 0.2 * * *
• 88 3.5 0.7 3.0 0.1 3.7 0.1 * * *
• 89 4.3 0.3 3.1 0.3 3.7 0.1 * * *
• 90 4.5 0.3 3.0 0.1 3.8 0.1 2.9 0.1 3.5 0.1 91 4.6 03 3.3 0.2 4.0 0.1 * * *
• 92 5.5 0.2 4.0 0.3 4.8 0.2 * * *
• 95 3.6 0.3 3.1 0.3 4.1 0.2 * * *
• I 96 97 4.0 3.9 1.0 0.8 3.5 3.3 0.4 0.2 4.3 4.1 0.1 0.2 3.5 0.3 4.1 0.1 NOTE: Teledyne Isotor;es TLD Secondary network redxed to ten (10) stations after the third refer ing period.

158 I

I I OYSTER CREEK L NR GENERAllhG $1A110N 1ABLt J 2 EWVIRONMEh1 AL COW 1ROL$ 1991 QUARTERLY ENVIRDhMEh1 AL TLD REPORT - PAhASoh!C I RUhW!hG 1ABLE First Period 1991 Secord Period 1991 MittlREM PER ST AND ARD Q'JARilR AND 2 51 AND ARD DEVI AllDNS Third Period irdi fourth Period 1991 Fifth &criod 1991 I Station Std. Dev Std. Dev Reading Reading Reading Std. Dev Reading Std. Dev Reading Std. Dev A 11.20 0.89 12.09 1.04 11.57 0.79 10.85 0.85 12.B8 0.87 C 10.40 0.75 10.82 1.06 11.29 0.44 10.B6 1.00 12.00 1.19 w 9.50 0.62 9.36 0.73 10.36 0.79 9.94 0.70 11.83 0.34 1 11.60 0.48 10.39 0.39 10.35 0.74 10.82 1.03 13.47 0.48 3 9.39 0.52 9.7 0 i6 10.63 0.82 9.85 0.83 11.91 1.27 4 8.W 0.32 9.43 0.71 8.57 0.73 9.03 1.01 10.88 0.71 10.50 0.87 12.20 0.46 10.77 0.87 10.08 0.94 I 5 12.34 0.33 6 9.56 0.74 9.48 0.60 10.36 0.81 9.62 0.66 11.42 0.77 7 9.57 0.92 8.85 0.64 9.37 0.43 8.93 1.07 10.27 0.6% 8 9.45 0.62 10.22 0. M 10.49 0.86 9.21 0.83 11.25 0.67 9 10.60 0.41 10.99 0.80 10.98 0.68 9.91 0.44 12.65 0.72 I 11 10.90 0.31 10.18 0.94 10.34 0.63 10.61 0.83 12.44 0.75 10 9.66 0.74 10.68 0.43 10.26 0.70 9.70 0.36 12.44 0.78 11 9.08 0.77 9.72 0.69 9.57 0.50 9.37 0.76 11.00 0.58 12 10.30 0.58 9.77 0.28 11.16 0.62 9.89 0.86 13.2' 1.68 13 8.38 0.65 0.02 0.61 9.67 0.29 9.?9 0.82 10.99 1.10 14 12.10 0.76 10.65 0.95 12.86 0.74 12.65 0.77 14.69 1.63 . 15 10.30 0.38 10.50 0.46 11.22 0.96 9.71 0.80 10.71 1.07 I 16 8.93 0.33 9.10 0.51 9.45 0.60 8.80 9.07 11.73 1.11 17 9.69 0.53 9.74 0.66 10.05 0.29 9.43 1.10 11.47 1.35 20 9.52 0.67 9.13 0.76 9.75 0.65 8. 75 S.48 11.14 0.83 22 9.14 0.45 8.61 1.35 9.13 0.37 8.84 0.27 10.40 1.05 51 12.80 0.44 11.21 0.43 11.55 0.40 12.02 0.73 13.65 1.04 I 52 53 14.20 12.00 0.73 0.65 12.85 10.66 0.82 0.51 13.07 10.74 0.53 0.67 12.97 11.37 0.86 0.71

15. 73 13.61 0.31 0.67 54 10.50 0.63 9.94 0.60 9.42 0.65 9.62 0.83 12.57 1.44 55 10.30 0.79 10.27 10.70 10.52 0.83 10.44 0.79 11.32 0.96 56 _ 11.70 0.69 ft0 toS1 9.71 1.38 10.37 0.59 13.00 0.48 57 14.10 2.61 11.48 0.57 11.56 0.43 14.31 1.54 15.83 2.49 58 12.00 1.36 10.22 0.56 9.15 0.55 11.B4 0.88 14.17 0.64 59 12.90 1 32 11.03 0.60 11.17 0.64 11.32 0.59 14.15 0.66 60 10.30 0.69 9.45 0.62 10.05 1.00 9.08 0.74 12.32 1.21 I

159 I

?I 1Atti J 2 OYSTER CREEK huCLEAR GEhERA11hG STAllOh INVIR0hMfhTAL C0hTROLS 1991 QUARTERLt Ekv!RAMENTAL TLD REPORT . PAhA$0h!C I First Period 1991 RUhh!NG TABLE - MILL 1 REM FER 51ANDAR0 QUARTER AND 2 STANDARD DivtAf!Oh5 Secord Period 1991 Third Perled 1991 Fourth Per ind 1991 Fifth Period 1991 j station Reading Std. Dev Reading 5td. Dev Readin0 Std. Dev Readin9 Std. Dev Reading $td. Dev E 61 10.90 0.90 9.35 0.43 10.46 0.89 4.44 0.78 11.47 1.55 62 10.80 1.33 9.98 0.30 10.31 0.33 9.36 0.80 11.09 0.71 63 11.50 0.89 10.23 0.66 10.97 0.51 10.08 0.99 12.78 0.94 64 10.50 0.55 9.32 0.42 9.03 0.67 9.67 0.90 11. M 0.80 65 10.70 0.72 9.58 0.65 10.11 0.?4 10.03 0.67 12.11 0.97 6e 10.40 1.03 9.82 0.68 10.38 0.63 8.76 1.10 11.53 0.98 67 10.30 0.95 10.09 0.44 10.83 0.63 9.79 0.23 14.04 1,42 I 69 70 10.00 9.59 0.47 0.54 9.12 8.69 0.67 0.80 11.10 9.32 0.75 0.M 9.01 8.81 0.61 0.70 11.24 10.79 0.61 0.90 71 10.00 0.87 9.32 0.?9 10.84 0.47 9.70 0.75 10.76 1.19 73 9.15 0.97 9.18 0.34 9.96 0.45 8.93 0.65 10.60 0.99 I 74 75 11.10 11.70 0.89 0.64 9.36 11.03 0.38 0.53 10.83 11.78 0.59 0.M 9.63 10.99 0.92 1.08 11.73 12.96 0.77 0.85 76 9.35 1.10 8.47 0.64 9.78 0.53 9.24 0.55 10.41 1.10 77 10.90 1.07 8.82 0.94 10.36 0.7' 10.44 0.82 11.50 0.69 78 9.88 0.58 8.90 0.88 10.51 0., 9.32 0.67 11.52 0.49 79 TLD Losi 8.35 0.31 10.00 0.99 41 0.54 11.33 0.62 80 11.30 1.14 9.36 0.46 10.31 0.59 8.91 1.10 10.94 0.81 I 11.30 1.23 10.04 0.41 11.46 9.36 81 0.M 0.93 12.67 0.M 82 10.40 1.17 ft0 Lost 11.32 0.63 10.26 0.29 12.26 1.70 83 9.80 0.70 10.21 0.59 11.27 1.08 9.65 0.30 12.59 1.60 84 12.10 1.92 10.34 0.53 11.48 0.54 10.08 0.75 12.13 1.26 85 10.50 0.98 9.49 0.48 10.16 0.76 10.03 0.99 11.76 1.18 I 86 87 10.40 11.00 0.26 1.45 9.27 12.02 0.82 1.03 9.68 11.90 1.13 0.55 9.62 11.98 0.27 0.82 11.34 13.79 0.87 1.43 88 9.46 9.39 I C.62 0.42 10.17 0.66 8.99 0.57 10.86 0.75 89 10.20 1.12 10.02 0.94 10.14 1.07 8.81 0.49 11.25 0.59 90 9.61 1.00 9.43 0.78 9.56 0.62 9.11 0.44 11.01 0.69 91 10.60 0.55 9.65 0.51 11.13 0.59 9.51 1.04 11.04 0.87 92 11.50 1.60 11.46 0.53 11.93 1.22 11.06 0. 72 13.75 1.27 95 9.95 0.48 8.90 0.68 10.10 0.26 P.81 0.83 11.11 0.91

   "                    11 00                                                              1.12 96                                                                                     9.92         0.80      11.77         1.06      10.24         0.66       11.93         1.27 97        10.40                                                             0.58       9.15         0.25      10.91         0.59       9.26         0.75       12.23                #

1.13] 160 I}}