ML20245E958
| ML20245E958 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1988 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8905020216 | |
| Download: ML20245E958 (214) | |
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I OYSTER CREEK NUCLEAR GENERATING STATION .v.'
Forked River, New Jersey 'f The 650 MWplant is a single-unit, five-loop General Electric Boiling Water Reactor (BWR). The site, about 800 acres, is in Lacey and Ocean Townships of Ocean County. Located approximately nine miles south of Toms River, it is about 50 miles east of Philadelphia, and 60 miles south of Newark.
Construction began in December 1963. The station began commercial operation on December 23,1969, and at that time was the largest nuclear -b facility in the United States solely financed by a private company.
The Reactor Building, Turbine Building and Ventilation Stack are the most prominent structures at the site. The Reactor Building stands approxi-mately 150 feet high with 42 feet extending below grade. The Reactor Building serves as a secondary containment and houses the primary containment (drywell), the reactor vessel and its auxiliary systems which comprise the Nuclear Steam Supply System. The drywell, which houses the reactor vessel, is constructed of high-density reinforced concrete with an 1 inner steelliner measuring 120 feet high and 70 feet in diameter. ,
The reactor vesselis 63 feet high and 18 feet in diameter.
The 652-ton reacMr contains 560 fuel assemblies, each with 62 fuel rods that are 12 feet long, and 137 control rods. The reactor operates at a nominalpressure of 1,020 pounds per square inch and an average temperature of 540 degrees Fahrenheit.
The Turbine Building houses the turbine-generator, control room, main condensers, power conversion equipment and auxiliary systems. The turbine-
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generator consists of one high-pressure turbine, three low-pressure turbines, a generator and an exciter. The turbines and generator tum at 1,800 revolutions per minute to generate three-phaw, 60-cycle electricity at 24,000 volts. The electricity generated is provided to the grid by two tasformers which boost the voltage to 230,000 volts.
Steam is supplied to the high pressure turbine from the reactor. After being used to drive the turbines andgenerator, the steam is condensed in the
- main condensers and retumed to the reactor vesselin the form of water through the con-l densate and feedwaterpumps.
The main condensers consist of three horizontal, single pass, divided water boxes containing 44,000 tubes having a totallength of about 1,875,000 feet. Cooling wateris provided from Bamegat Bay, through the South Branch of the Forked River and passes through the condensers and discharges into Oyster Creek for return to Bamegat Bay. The water is pumped by four 1,000-horsepowerpumps, each of which moves about 115,000 gallons per minute through the 6-foot-diameterpipes that feed the
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condensers.
The ventilation stack is 368 feet high with 26 feet extend-ing below grade. The stack provides ventilation for the Reactor Building, Turbine Building and Radwaste Facilities.
Oyster Creek is owned by Jersey Central Power & Light (JCP&L) Company and oper-atedby GPU Nuclear (GPUN)
Corporation. JCP&L and GPUN are units of the GPU System.
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l 1988 Radiological Environmental Monitoring Report Prepared By Oyster Creek Environmental Controls GPU Nuclear Corporation i
TABLE OF CONTENTS PAGE TABLE OF CONTENTS i LIST OF TABLES iv LIST OF FIGURES V
SUMMARY
AND CONCLUSIONS 1 INTRODUCTION 4 Characteristics of Radiation 4 Sources of Radiation 5 Nuclear Reactor Operations 8 Sources of Liquid and Airborne Effluents 11 DESCRIPTION OF THE OYSTER CREEK SITE 14 General Information 14 Climatological Summary 14 EFFLUENTS 18 Historical Background 18 Effluent Release Limits 19 Effluent Control Program 22 Effluent Data 23 RADIOLOGICAL ENVIRONMENTAL MONITORING 27 Environmental Exposure Pathways to Humans from Airborne and Liquid Effluents 27 Sampling 28 Analysis 29 Quality Assurance Program 33 i
TABLE OF CONTENTS (Continued)
PAGE DIRECT RADIATION MONITORING 134 Sample Collection and Analysis 134 Results 135 ATMOSPHERIC MONITORING 137 Sample Collection and Analysis 137 Results 138 AQUATIC MONITORING 142 Sample Collection and Analysis 142 Results 143 TERRESTRIAL MONITORING 149 Sample Collection and Analysis 149 Results 150 GROUNDWATER MONITORING 153 Sample Collection and Analysis 153 Results 154 RADIOLOGICAL IMPACT OF OCNGS OPERATIONS 155 Determination of Radiation Doses to the Public 155 Results of Dose calculations 158 REFERENCES 162 APPENDIX A: 1988 REMP Sampling Locations and Description, Synopsis 164 of REMP, and Sampling and Analysis Exceptions APPENDIX B: 1988 Lower Limits of Detection (LLD) Exceptions 176 APPENDIX C: Changes Effected in the 1988 REMP 178 APPENDIX D: 1988 Quality Assurance Results 180 ii
TABLE OF CONTENTS (Continued)
PAGE APPENDIX E: 1988 EPA Cross-Check Results 184 APPENDIX F: 1988 Annual Dairy Census 189 APPENDIX G: Dose Calculation Methodology 191 APPENDIX H: 1988 Groundwater Monitoring Results 196 APPENDIX I: 1988 REMP Sample Collection and Analysis Methods 199 APPENDIX J: 1988 TLD Quarterly Data 203
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LIST OF TABLES TABLE TITLE PAGE ,
1 Sources and Doses of Radiation 6 2 Radionuclides Composition of OCNGS Effluents 24 for 1988 3 Summary of Radionuclides Concentrations in 35 Environmental Samples from OCNGS 4 Species of Fish Caught as 144 Part of the OCNGS REMP in 1988 5 Calculated Maximum Hypothetical Doses to 160 an Individual for Liquid and Airborne Effluent Releases from Oyster Creek for 1988 6 Calculated Maximum Total Radiation Doses 161 to the Population from Liquid and Airborne Effluent from Oyster Creek for 1988 iv
LIST OF FIGURES FIGURE TITLE PAGE 1 Oyster Creek Nuclear Generating 10 Station Simplified Schematic 1.5 Monthly Precipitation at the Oyster Creek Nuclear 17 Generating Station During 1988 Computed with Historical (1946-1981) Atlantic City National Weather Service Precipitation Data 2 Location of Radiological Environmental Monitoring 30 Program (REMP) Stations Within<1 Mile of the Site 3 Location of Radiological Environmental Monitoring 31 Program (REMP) Stations Greater than 1 Mile and Within 2 Miles of the Site 4 Location of Radiological Environmental Monitoring 32 Program (REMP) Stations Greater than 2 Miles From the Site 1 5 Mean TLD Gamma Dose 1984-1988 136 1
6 Monthly Mean Air Particulate Gross 139 Beta Concentrations 7 Air Particulate Gross Beta Concentrations 140 1984-1988 l
8 Cobalt-60 concentration in Clams 145 1984-1988 9 Cobalt-60 Concentration in Sediment 146 1984-1988 10 Cobalt-60 Concentration in Blue Crab 147 1984-1988 11 Monthly Cesium-137 Activity in Cabbage 151 12 Monthly Cesium-137 Activity in Collards 152 13 Exposure Pathways for Routinely Released 157 Radionuclides from the OCNGS 1
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SUMMARY
AND CONCLUSIONS !
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The radiological environmental renitoring performed during 1988 by the GPU
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Nuclear Environmental Controls Department at the Oyster Creek Nuclear
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Generating Station (OCNGS) is discussed in this report. The operation of a.
neclear power plant results in the release of small amounts of radioactive materials to the environment. A radiological environmental monitoring program (REMP) has been established to monitor radiation and radioactive materials in -
the environment around the OCNGS. The program _ evaluates the relationship.
between amounts of radioactive material released in effluents to the environment and resultant radiation doses to individuals. Summaries and .
interpretations of the data were published semiannually from 1969-1985.and annually since 1986 (References I and 2). Additional information 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).
1 During 1988, as in previous years, the radioactive liquid and airborne '
effluents associated with the OCNGS were a small fraction of the applicable federal or state regulatory limits and did not have significant or measurable eff ects on the quality of the environment. Estimated radiation doses to the l public attributable to 1988 operations at the OCNGS were well below all applicable regulatory' limits and were significantly less than doses received from common sources of radiation.
Radioactive materials considered in this report are normally present in the environment, either naturally or as a result of non-OCNGS activities such as prior atmospheric nuclear weapons testing and medical industry activities.
Consequently, measurements made in the vicinity of the site (indicator) were compared to background measurements to determine any impact of OCNGS operations. Samples of air, precipitation, well water, surf ace water, . clams, sediment, fish, crabs, vegetables, and soil were collected. External penetrating radiation dose measurements also were made using thermoluminescent dosimeters (TLD's) in the vicinity of the OCNGS. Samples ~were analyzed for radioactivity including tritium (H-3), gross beta and gamma-emitting radionuclides.
The results of environmental measurements were used to assess the environmental impact c' OCNGS operations, to demonstrate compliance with the Technical Specifications (reference 3) and applicable federal and state regulations, and to verify the adequacy of containment and radioactive effluent control systems. The data collected by the REMP provided a historical record of the levels of radionuclides and radiation attributable to natural causes, worldwide f allout f rom prior nuclear weapons tests, and the OCNGS operations.
Radiological impacts in terms of radiation dose as a result of OCNGS operations were calculated and also are discussed. The results provided in this report are summarized in the following highlights.
o During 1988, over 1,955 samples were taken f rom the aquatic, atmospheric, and terrestrial environments around OCNGS. More than 2,462 analyses were performed on these samples. Two hundred fifty-five (255) direct radiation dose measurements using thermoluminescent dosimeters (TLDs) also were made. Over 77 groundwater samples, including local domestic water supplies, were collected and more than 154 analyses were performed on these samples.
o In addition to natural radioactivity, low levels of radionuclides such as tritium (H-3) and cesium-137 (Cs-137) were detected in various media and were attributed to f allout from prior nuclear weapon testing, and Chernobyl.
o Cobalt-60 (Co-60) was detected in sediment samples as a result of OCNGS operations. Although cobalt-60 had been detected in clams f rom the Barnegat Bay system in prior study years, this nuclide did not appear in clam samples collected during 1988.
o All radioactive effluent releases were small fractions of the Federal l
regulatory and Technical Specification limits. The predominant radionuclides released were xenon-135 (Xe-135) in gases and tritium (H-3) in liquids.
o During 1988, radiation doses to the public from OCNGS operations were well below all applicable regulatory limits, and significantly less I
than doses received from other common sources of radiation. The maximum whole body dose potentially received by an individual f rom liquid and airborne effluents combined' was conservatively calculr.ced to be about 0.29 millirems total. The whole body dose to the succounding population f rom liquid and airborne effluents was calculated to be 1.8 person-rem. This is ff".e hundred and fifty I thousand (550,000) times lower than the de>st that the total t
population in the OCNGS area receives fr.' natural background sources.
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INTRODUCTION l
I Characteristics of Radiation Instability within the nucleus of a radioactive atom results in the release of energy in the form of radiation. Radiation is classified according to its nature - particulate and electromagnetic. Particulate radiation consists of energetic subatomic particles such as electrons (beta particles), protons, neut rons, 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 and gamma rays are penetrating and can pass through varying thicknesses of materials, once they are absorbed they produce energetic electrons which release their energy in a manner that is identical to beta particles. The principal concern for gamma radiation f rom radionuclides in the environment is their contribution to external radiation exposure.
The rate at which atoms undergo disintegration (radioactive decay) varies among radioactive elements, but is uniquely constant for each specific radionuclides. The term
- half-life" defines the time it takes for half of any amount of an element to decay and can vary from a fraction of a second for some radionuclides to millions of years for others. In fact, the natural background radiation to which all mankind has been exposed is largely due to the radionuclides of uranium, thorium, and potassium. These radioactive elements were formed with the creation of the universe and, owing to their long half-lives, will continue to be present for millions of years to come.
For example, potassium-40 has a half-life of 1.3 billion years and exists naturally within our bodies. As a result approximately 4000 atoms of potassium emit radiation internally within each of us every second of our life.
In assessing the impact of radioactivity on the environment, it is important to know the quantity of radioactivity released and the resultant radiation I 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 l
rate of 37 billion radiation emissions every second. Because of the extremely small amounts of radioactive material in the environment, it is more l convenient to use fractions of a curie. Subunits like pi:ocurie (one 1
trillionth of a curie) are frequently used to express the radioactivity l' present in environmental and biological samples.
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The biological effects of a specific dose of radiation are the same whether the radiation source is external or internal to the body. The important factor is how much radiation energy or dose was deposited. The unit of radiation dose is the rem, which also incorporates the variable effectiveness of different forms of radiation to produce biological change. For l environmental radiation exposures, it is convenient to use the smaller unit of I
millitem to express dose (1000 millirems equals I rem). When radiation
, exposure occurs over periods of time, it is appropriate to refer to the dose rate. Dose rates, therefore, define the total dose for a fixed interval of time and for environmental exposures are usually measured with reference to one year of time (millirems per year).
I Sources of Radiation Life on earth has evolved amid the constant exposure to natural radiation. In f fact, natural radiation is the single major source to which the general population is exposed. Although everyone on the planet is exposed to natural radiation, some people receive more than others. Radiation exposure from j natural background has three components (i.e. , cosmic, terrestrial, and internal) and varies with altitude and geographic location, as well as with j living habits.
l For example, cosmic radiation originating f rom deep interstellar space and the l sun increases with altitude, since there is less air which acts as a shield.
Similarly, terrestrial radiation r3sulting f rom the presence of naturally
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occurring radionuclides in the soil varies and may be significantly higher in some areas of the country than in others. Even the use of particular building materials for houses, cooking with gas, and home insulation aff ect exposure to natural radiation.
The presence of radioactivity in the human body results f rom the inhalation and ingestion of air, f ood, and water containing naturally occurring radionuclides. For example, drinking water contains trace amounts of uranium j and radium and milk contains radioactive potassium. Table 1 summarizes the common sources of radiation and their average annual doses.
1 TABLE 1 (Ref. 5)
Sources and Doses of Radiation
- Natural (82%) Man-made (18%) s Radiation Dose Radiation Dose Sou rce (milli rems / yea r ) Source (milli rems / yea r )
Radon 200 (55%)
Cosmic rays 27 (8%) Medical X-rays 39 (11%)
Terrestrial 28 (8%) Nuclear Medicine 14 (4%)
Internal 40 (11%) Consumer products 10 (3%)
Other Less than 1 ( 1%)
(Releases from nat. gas, phosphate mining, burning of coal, weapons fallout,
& nuclea r f uel cycle)
APPROXIMATE APPROXIMATE TOTAL 300 TOTAL 63
- Percentage contribution of the total dose is shown in parentheses.
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 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 millirems each year to their residents (Ref. 6).
Recently, public attention has focused on radon, a naturally occurring radioactive gas produced from uranium and radium decay. These elements are widely distributed in trace amounts in the earth's crust. Unusually high concentrations have been found in certain parts of eastern Pennsylvania and northern New Jersey. Radon levels in some homes in these areas are hundreds of times greater than levels found elsewhere in the United States. 3owever, 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 the United States receives an annual dose of about 2,400 milli. rems to the lung f rom natural radon gas (Ref.
5). 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 thyroid gland, radioactive cesium is distributed throughout the body water and muscles, and radioactive strontium concentrates in the bones. The total dose to organs by a given radionuclides is also influenced by the quantity and the duration of time that the radionuclides remains in the body, including its physical, biological and chemical characteristics. Depending on their rate of radioactive decay and biological elimination f rom the body, some radionuclides stay in the body for very short times while others remain for years.
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In addition to natural radiation, we are exposed to radiation f rom a number of man-made sources. The single largest of these sources comes from diagnostic medical x-rays, and nuclea r medicine procedu ree. Soae 180 million Americans receive medical x-rays each year. The annual dose to an individual from such radiation averages about 53 mill, rems. Much smaller doses come f rom nuclear weapons f allout and consumer products such as televisions, smoke detectors, i and fertilizers. Production of nuclear power and its associated fuel cycle contributes less than 1 millirem to the annual dose of about 300 millirems for l the average individual living in the United States.
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Fallout commonly refers tr, 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 i
earth's surface by rain or snow. There are approximately 200 radionuclides !
produced in the nuclear weapon detonation process; a number of these are detected in fallout. The radionuclides found in f allout which produce most of the fallout radiation exposures to humans are iodine-131 (I-131), strontium-89 (Sr-89), cesium-137 (Cs-137), and strontium-90 (Sr-90). There has been no atmospheric nuclear weapon testing since 1980 and many of the radionuclides i 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, and soil.
Nuclear Reactor Operations, Common to the commercial production of electricity is the consumption of fuel which produces heat to make steam which turns the turbine-generator which generates electricity. Unlike the burning of coal, oil, or gas in f ossil-f uel powered plants to generate heat, the fuel of most nuclear reactors is comprised of the element uranium in the form of uranium oxide. The fuel produces power by the process called fission. In fission the uranium atom absorbs a neutron (an atomic particle found in nature and also produced by the
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-fissioning of uranium in the reactor) and splits to produce smaller _ atoms i termed fission products, along with heat, radiation and free neutrons. The i
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free neutrons travel through the reactor and are similarly absorbed by the
! uranium, permitting the fission process to continue. As this process continues, more fission products, radiation, heat and neutrons are produced-and a surtained reaction occurs. The heat produced is transferred 'via i
reactor coolant water - f rom the f uel to produce steam which drives a '
turbine-generator to produce electricity. The fission products are mostly radioactit'e : 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 f uel may be absorbed by stable atoms in the materials which make, up the components and structures of the reactor. In an6a cases, stable atoms often' become radioactive. This process is called activation and the radioactive-atoms which result are called activation products.
-l The Oyster Creek Reactor is a Boiling Water Reactor (BWR). The nuclear f uel- l 1
is designed to be contained within sealed fuel rods arranged in arrays called- l l bundles which are located within a massive steel pressure vessel.- As depicted in Figure 1, cooling water boils within the reactor vessel producing steam'for use in the turbine. After the energy is extracted from the steam'in the turbine, it is cooled and condensed back into water in the main condensers.
This condensate is then pumped back into the reactor vessel.
i 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. ,
1 The Oyster Creek reactor has six independent barriers that confine-radioactive 3 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. Most of the fission products are either trapped or chemically bound in the f uel where they l 9
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The second barrier consists of zirconium alloy tubes that resist corrosion and degradation due to high temperatures. The fuel pellets are contained within these tubes. There is a small gap between the fuel and the cladding, in which the noble gases and other volatile radionuclides collect.
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 purification system of the reactor. However, krypton 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.
The fourth barrier consists of the reactor pressure vessel, turbine, condenser, and associated piping of the coolant system. The reactor pressure ]
vessel is a 63-foot high tank with steel walls about nine inches thick. It encases the reactor core. The remainder of the coolant system includes the i turbine and condenser and associated piping. This system provides containment l for radioactivity in the primary coolant. I iI i
The drywell provides the fif th barrier. It has steel-lined thick concrete j walls that enclose the reactor pressure vessel and recirculation pumps and loops.
The reactor building provides the sixth barrier. It is a reinforced concrete i and steel superstructure which is always maintained at a negative pressure.
Sources of Liquid and Airborne Ef fluents Although the previously described barriers contain radioactivity with high efficiency, small amounts of radioactive fission products are nevertheless able to dif fuse or migrate through minor flaws in the f uel cladding and into
1 the reactor coolant. Trace quantities : reactor system component and ,
l structural materials which have been activated, also get into the reactor j coolant water. Many of the soluble fission and activation products such as iodines, strontiums, cobalts, and cesiums are removed by demineralizers in the 1 purification system of the reactor coolant. The physical and chemical properties of noble gas fission products in the primary coolant prevent their removal by the demineralizers. I Because the reactor system has many 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 l
Reactor, and/or Turbine Buildings. The noble gases become part of the gaseous I 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 f rom the reactor primary system by steam jet ai r ejectors. These air ejectors drive the process stream through a 60 minute holdup pipe at approximately 110 cubic f eet 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 recombiner, removes the water (vapor) from the process stream, holds up the process stream to allow further decay of short-lived nuclides, and filters the off-gas using charcoal beds and High Efficiency particulate (HEPA) filters prior to discharge to the base of the stack. Once the process stream enters the stack, it is diluted by building ventilation, which averages 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 cr.itaminated with radioactivity and processes it by filtration, demineralization, and distillation. Purified radwaste water is recycled to the plant.
Occasionally, it is necessary to discharge this purified water to the
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I environment. Contaminants removed during the purification process are disposed of via the solids disposal systems. When purified water is discharged to the environment, it is first r.ampled, analyzed, assigned a release rate, as then discharged to a receiving stream which has a flow rate of 460,000 to 960,000 gallons per minute.
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l DESCRIPTION OF THE OCNGS SITE General Information The Oyster Creek Nuclear Generating Station is located in Lacey Township of Ocean County, about 60 miles South of Newark, 9 miles south of Toms River and l 35 miles north of Atlantic City. It lies approximately 2 miles inland from Barnegat Bay. The site, covering 1416 acres, is situated partly in Lacey Township and, to a lesser extent, in Ocean Township. The Garden State Parkway bounds the site on the west. Overland access is provided by U. S. Route 9, passing through the site and separating a 661-acre eastern portion from the balance of the property west of the highway. The station is about 1/4 mile west of the highway and 1-1/4 miles east of the Parkway. The site property extends about 3-1/2 miles inland from the bay; the maximum width in the north-south direction is almost 1 mile. The site location is part of the New Jersey shore arei with its relatively flat topography and extensive freshwater and saltwater marshlands. The south branch of Forked River runs across the northern side of the site, and Oyster Creek partly borders the southern side.
It is estimated that approximately 3.3 million people reside within a 50 mile radius of the plant (Reference 4). The nearest population center is Ocean Tcwnship (population 3731) which lies less than two miles south-southeast of the site. Two miles to the north,14,161 people reside in La.ey Township.
Dover Township, situated 9. 5 miles to the north, is the nearest major population center with a population of 61,287. The region adjacent to Barnegat Bay is one of the State's most rapidly developing areas. In addition to the resident population, a sizeable seasonal influx of people occurs during the summer. This influx occurs almost exclusively along the waterf ront.
Climatological Summary The reporti.ig period of 1988 provided some interesting meteorological situations. Larger than normal annual temperature ranges were present along with overall lower amounts of precipitation.
l' i For the first half of the period, the predominant wind directions were from 1
the west-northwest and the south-southwest. The normal- northwest wind l l
directions are expected during the winter months as the polar-jet stream l normally pushes southward and allows Canadian air masses to dominate the 1 . ,
region. A small maxima of east-northeast direction was present. This was due- ']
to the influence of extratropical low pressure systems (northeastern storms)~
f which are common to the region, especially during the winter months, and the
' airflow around large high pressure systems. Periods with this onshore fetch
- i. have characteristic low clouds, drizzle and fog (stable atmospheres). 'From April through June, the wind directions took on a summer-like pattern as wind directions from the southwest became commonplace. This is referred to as the transition time when the jet stream begins ' its retreat northward. The summer months were an anomaly. The predominant wind direction during the early, I second half of the period was f rom the west-southwest. Normal summer months have maxima from the south and the west, the latter direction due to modified continental polar air masses that follow cold f rontal passages. The former maximum is due mainly to the end result of the sea breeze phenomenon. At the l
height of this mesoscale effect (approximately 2:00 to 4:00 in the af ternoon) the wind will parallel the coast - the result created from uneven heating-between land and sea coupled with the natural rotation of the earth. The lack )
of any appreciable sea breeze (southerly wind component) was mainly due to the northward drif t of the subtropical high pressure center, a fixture common to the southeast coast. The northward movement caused increased southwest wind 1 which acted to hinder the development of the sea breeze. The period ' f rom October through December was fairly normal as the predominant wind direction .]
was from the northwest, reflecting the southerly return of the polar jet )
stream.
l Although considered as one of the warmest summers in the area, the average g monthly temperatures during July and August were only slightly in excess of the normal Atlantic City monthly mean. The warm summer was not apparent alon the immediate coast as predominant southwest winds acted to enhance oceanic upwelling. This is caused by colder water f rom below the surf ace replacing i the warmer upper layers. The abnormally strong offshore wind directions apparent during the summer months caused the surface water to be " pushed" out
to sea, only to be replaced by colder, deeper waters. Upwelling is common along the west coast of the United States. The colder water caused colder, j more stable air to exist only along the immediate coastline. The more common thermally-induced sea breeze is usually strong enough to penetrate inland to at least 6 miles. Very little sea breeze effect was experienced at Oyster Creek during the summer of 1988. Temperatures averaged near normal for the l t
! remainder of the year with the exception of May, September and October when j k
temperatures were actually below normal. Over the year, the average monthly temperature ranged from 28 degrees F in January to 77 degrees F in August.
h A total of 27.04 (water equivalent) inches of precipitation fell during 1988,
! which amounts to approximately 16.15 inches below the annual average (Figure 1.5). Highlights for the period include only trace amounts of-precipitation i
during the month of April, less than 5 inches for the months of July and Augt at combined and a total of 12 inches of measurable snow for the entire year. The lack of summertime precipitation is directly correlated with the position of the previously mentioned northward shifting of the subtropical high prnssure region. The bulk of the Gulf of Mexico moisture, the source of summertime precipitation, was shifted westward as the bubble of high pressure blocked its advection into the region. For the period of July through December, precipitation was below normal (13.64 inches). The same six-month average from Atlantic City National Weather Service historical record is 22.0 inches. During the summer months precipitation is generally characterized by l events of short duration but strong intensity (convective showers). With this type of precipitation event, there will be increased particulate fallout (washout) from the atmosphere, which has implications for radionuclides deposition. During the summer, marine air, which is stable, will generally suppress these convective storms and decrease precipitation at most coastal locations. The sea breeze can produce the same result. However, during this particular summer solstice the sea breeze ef f ect was limited. The remainder of the six-month period's contribution to rainfall was due to extratropical storms of light to moderate intensity and long duration, especially during the f ou rth qua rter (October-December) .
For a more complete meteorological summary ref t . to the Semiannual Effluent Release Reports for 1988.
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l EFFLUENTS
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! Historical Background Almost f rom the outset of the discovery of x-rays in 1895 by Wilhelm Roentgen the potential hazard of ionizing radiation 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 L 1929, respectively, and have the longest continuous experience in the review of radiation health ef fects 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 received on radiation levels and the effects on 1
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 series of reports have been issued by this and succeeding NAS committees on the biological effects of ionizing radiation (BEIR), the most "
recent being 1987 (known as BEIR IV). The Federal Radiation Council (FRC) was formed in 1959 to provide a f ederal policy on human radiation exposures.
These federal policies are approved by the 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 ef f ects of radiation by investigating all sources of relevant knowledge and scientific data and by providing guidance for radiological protection. Their members are selected f rom universities, scientific research centers and other national and international research organizations. The committee reports contain scientific data obtained f rom physical, biological, and I i
epidemiological studies on radiation health effects and serve as scientific references for information presented in this report. Since its inception, the l USNRC has depended upon the recommendations of the ICRP, the NCRP, and the 1 FRC (incorporated in the United States Environmental Protection Agency in i 1970) f or basic radiation protection standards and guidance in establishing regulations for the nuclear industry (Ref. 7 through 10).
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Effluent Release Limits
) As part of routine plant operations, limited quantities of radioactivity are released to the *nvironment in liquid and airborne effluents. An effluent control program is implemented to ensure r. radioactivity released to the environment is minimal and does not exceed release limits. Radioactive effluent releases at Oyster Creek are under the regulatory jurisdiction of the USNRC. Regulations through the years have changed and reflect operating .
I experience and advances in nuclear technology. Federal regulations as defined i by Title 10 of the Code of Federal Regulations, Part 20 (10 CFR 20) establish limits on the concentrations of radioactive effluents released to the environment. Federal effluant limits cre set at low levels to protect the health and safety of the public. GPU Nuclear conducts operations in a manner that holds radioactive effluents to small percentages of the f ederal limits.
l A recommendation of tne ICRP, NCRP, 3nd FRC is that radiation exposures should be maintained at levels which are 'as low as reasonally achievable" (ALARA) and commensurate with the societal benefit derived from the activities resulting in such exposures. For this reason, dose limit guidelines were j l established by the USNRC f or releases of radioactive ef fluents f rom nuclear {
power plants. These guidelines are presented in the Oycter Creek Technical Specifications. Maintaining 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 ere as follows:
l o Technical Specification 3.6.K.1 The dose equivalent rate outside of the EXCLOFION AREA due to I radioactive noble gas in gaseous effluent shall not exceed 500 mrem / yea r to the total body or 3000 mrem / year to the skin.
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i-l I
l o Technical Specification 3.6.L.1 1
The air dose outside of the EXCLUSION AREA 'due to noble gas released.
in gaseous effluent shall not exceed:
L 5 mrad / calendar quarter due to gamma radiation,
( 10 mead /calen tar quarter .due : to beta radiation, .!
10 mrad / calendar year due to gamma radiation, or j 20 mead / calendar year due to beta radiation, l- I o Technica1' Specification 3.6.N.1 l
4 l
4 The annual dose to a MEMBER OF THE PUBLIC due to radiation and radioactive material in effluents from the OCNGS outside of the I 1
f EXCLUSION AREA shall not exceed 75 mrem to his thyroid or 25 mrem to
]
his total body or to any other organ. l I
o Technical Specification 3.6.K.2 a
The dose equivalent rate outside of the EXCLUSION AREA-due. to H-3,-
I-131, I-133, and to radioactive material in particulate' form having i
half-lives of 8 days or more in gaseous ef fluents shall not exceed l 1500 mrem / year to any body organ when the dose rate due to H-3, l
St-89, Sr-90, and c?pha-emitting radionuclides is averaged over no more than 3 months and the dose rate due to other radionuclides is i averaged over no more than 31 days.
1 1
l o Technical Specification 3.6.M.1 i l The dose to a MEMBER OP THE PUBLIC f rom iodine-131, iodine-133, and 1 !
frax radionuclides in particulate fork having half-lives of 8 days or o morc in gaseous effluents, outside of the EXCLUSION AREA shall not l
l exceed 7.5 mrem to any body organ per calendar quarter' or -15 mrem to -
any. body organ per calendar year.
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I o Technical Specification 3.6.I.1' The' concentration of radioactive material, other than noble gases, in' y
liquid effluent in ,the discharge canal'. at' the Route 9 bridge shall
)-' not exceed the concentrations specified in.10 CPR Part 20, Appendix B, Table II, Column 2.
i
~
I' o Technical Specification'3.6.I.2' l
l .l
). .The concentration of noble gases dissolved.or. entrained in liquid: <
ef fluent in the discharge canal at the Route 9 bridge' shall.. not.
~
)
[
oxceed 2 x 10 microcuries/ milliliter. ..
l o Technical Specification'3.6.J.1 The dose to a MEMBER OF THE PUBLIC due to radioactive material'in liquid ef fluents beyond the oui. side of the EXCLUSION: AREA shall not exceed:
1.5 mrem to the total body during any calendar quarter, 5 mrem to any body organ during any calendat quarter, 3 mrem to the total body during any calendar year,. or 10 mrem to any body organ.during any calendar year.
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~ 21 -
~l Effluent Contro1' Program i
i f 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' effluent control-program includes all aspects of effluent'and environmental monitoring. . This, i
' includes the operation and data analysis associated with a complex radiation- .1 monitoring system, environmental- sampling and . monitoring, and a. comprehensive quality assurance program. Over the years, the program , has. evolved.' in x
) response to changing regulatory requirements and- plant conditions.. For: j
.A example, additional-instruments-and samplerr have been installed to provide ]
q that measurements of effluents remain onseale in the event of-'any accidental' .j release of radioactivity.
)
Effluent Instrumentation: Liquid and airborne effluent measuring instrumentation is designed to detect the presence and the amount of l radioactivitysin effluents. Many of'these instruments provide continuous' surve'11ance of radioactivity releases. Calibrations of effluent instruments are performed using reference standards certified by the United States National Bureau of Standards. Where continuous surveillance is not practicable or possible, contingencies are spelled- out in the Technical l
Specifications. If pre-deeignated setpoints are reached, releases are immediately terminated.
I Effluent Sampling and Analysis: In addition to continuous radiation' monitoring inst rume nt s, samples of effluents are taken and subjected to '.aboratory i
l analysis to identify the specific radionuclides quantities being released. A l
sample must be representative of the effluent from which it is taken.
Sampling and analysis provide a sensitive and precise method of determining -
effluent composition. Samples are analyzed using the highest quality j laboratory counting equipment. Radiation instrument readings and sample results are compared to ensure correct correlation.
I
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Effluent Data ]4 1
As part of routine plant operations, limited quantities of radioactivity are .
released to the environment in liquid and airborne effluents. Amounts of
- radioactivity released varies and is dependent upon operating conditions, power levels, fuel conditions, efficiency of liquid and gas processing )i systems, and proper functioning of plant equipment. The largest variations !
L occur in the airborne effluents of fission and activation gases which are proportional to the augmented off gas system operation in the gas processing h system and to the integrity of the fuel cladding. In general effluents have been decreasing with time due to improved fuel integrity and increased efficiency of processing systems,
[
i f During 1988, the radioactive liquid and airborne releases f rom the OCNGS were j small fractions of Federal regulatory and Technical Specification limits.
(
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With respect to activity released, the predominant radionuc?i-des were ]
f xenon-135 in gases and H-3 in liquids. The amount of radioactivity released as well as the associated calculated doses to the public are summarized and reported semiannually to the USNRC. A summary of the OCNGS liquid and ai rborne ef fluents f or 1988 is provided in Table 2. Radioactive constituents of these effluents are discussed in the following sections.
Noble Cases: The predominant radionuclides released in airborne effluents are the noble gases xenon (Xe) and krypton (Kr). Small amounts are also released in liquid effluents. The total amounts of xenon and krypton released into the atmosphere in 1988 was 3055 curies and 1998 curies respectively. These noble gases were readily dispersed into the atmosphere when released and because of their short half-lives, quickly decayed into stable forms, i
Iodines and Particulate: The discharge of iodines and particulate to the envi ronme nt is minimized by f actors such as their high chemical reactivity and solubility in water combined with the high efficiency removal of airborne and liquid processing systems.
i i
TABLE 2 RADIONUCLIDES COMPOSITION OF OCNGS EFFLUENTS FOR 1988 I 1
Liquid Effluents (Ci) Gaseous Effluents (Ci) ,
Radionuclides Half-Life OCNGS OCNGS j 1
> H-3 12. 3 yea rs 1.62 El 1.25 El ,
I Cr-51 27.7 days 4.90 E-3 ND Mn-54 312 days 6.62 E-4 5.42 E-4
(
Co-58 70.8 days 1.18 E-3 ND Co-60 5. 3 yea rs 1.37 E-2 1.43 E-4
)
Kr-85m 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ND 3.40 E2 Kr-87 76 minutes RD 7.72 E2 Kr-88 2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ND 8.86 E2 Sr-89 50.5 days 8.40 E-4 5.40 E-3 i
Sr-90 28.8 years 2.08 E-5 3.13 E-5 !
1 Tc-99m 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 4.14 E-4 3.70 E-3 j i
I-1 31 8.0 days 5.38 E-5 5.28 E-2 l 1 I-133 20.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> ND 2.34 E-1 )
Xe-133 5.2 days 2.21 E-3 9.00 E2
]
Cs-134 2.1 yea rs 3.77 E-4 ND I-135 6.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ND 2.00 E-1 Xe-135 9.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 3.21 E-3 1.79 E3 i l
Xe-135m 15.6 minutes ND 1.61 E2 Cs-137 30.2 years 3.96 E-3 ND j Xe-138 17 minutes ND 2.04 E2 I Ba-140 12.8 days ND 5.60 E-4 La-140 40.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 6.59 E-4 2.87 E-4 Gross Alpha 1.58 E-5 1.72 E-5 Note: All effluents expressed in scientific notation.
ND = No Activity Detected of the gaseous radioiodines, iodine-131 is of particular concern because of its relatively long half-life of 8 days. Particulate of relative concern are
}
the radiocesiums (Cs-134 and Cs-137), radiostrontium (Sr-89 and Sr-90) and activation products manganese-54 (Mn-54) and cobalt-60 (Co-60). The total j
amount of iodines and particulate released from Oyster Creek in 1988 was 0.497 curies in airborne effluents and 0.0268 curies in liquid effluents.
Tritium: Tritium is the predominant radionuclides released in liquid effluents and also is released in airborne effluents. Tritium is a radioactive isotope ;
) of hydrogen. It is produced in the reactor coolant as a result of neutron j interaction with the naturally occurring deuterium (also a hydrogen isotope) present in water. The total amount of H-3 released in liquid and airborne ;
effluents was 28.7 curies. All releases of H-3 have been substantially below the Federal effluent limits. To place this number in perspective, the world inventory of natural cosmic ray produced tritium is 70 million curies, which corresponds to a production rate of 4 million curies p&r year (Ref.11).
Tritium contributions to the environment f rom nuclear power production are sufficiently small that they have no measurable effect on the existing environmental concentrations.
Transuranic: Transuranic are produced by neutron capture in the fuel, and typically emit alpha and beta particles as they decay. Important transuranic >
isotopes produced in reactors are uranium-239 (U-239), plutonium-238 (Pu-238),
plutonium-239 (Pu-239), plutonium-240 (Pu-240), plutonium-241 (Pu-241),
americium-241 (Am-241), plutonium-243 (Pu-243), plus other isotopes of americium and curium. They have half-lives ranging from tens to millions of years. Transuranic are mostly retained within the nuclear f uel. 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 transuranic outside the reactor coolant.
Since greater than 99% of all transuranic are retained within the f uel and transuranic removal processes are extremely efficient, releases in airborne and liquid effluents are not monitored.
ca r bon-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 curies will be released f rom 1970 through 1990 (Ref.12).
I Carbon-14 also is produced naturally by the interactions of cosmic radiation with oxygen aa' nitrogen in the upper atmosphere. The worldwide inventory of
)
natural C-14 is estimated at 241 million curies (Ref. 12). Since the inventory of natural carbon-14 is so large, releases f rom nuclear power plants do not result in a measurable change in the background concentration of carbon-14. Consequently, carbon-14 is not routinely monitored in plant effluents.
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RADIOLOGICAL ENVIRONMENTAL MONITORING 1
). .I l GPUN conducts a comprehensive radiological environmental monitoring program (REMP) at Oyster Creek to monitor radiation and radioactive materials in' the i
environment. This program provides information on radioactivity in the environment f rom OCNGS releases and information'on the potential principal pathways of exposure to humans.-
The USNRC has established regulatory guides which.contain acceptable
- i. monitoring practices (Ref.13). The Oyster Creek program was designed on the basis of these regulatory guides along' with .the USNRC Radiological Assessment Branch Technical Position on Environmental' Monitoring (Ref.14). A11Lof these i i
guidelines have been met and in most cases the OCNGS program greatly exceeds them. The important objectives of the REMP are:
o to assess impacts to the public.from OCNGS operations o to verify in-plant controls for the containment of radioactive materials j o to determine buildup of long-lived radionuclides in the environment '
I and changes in background radiation levels !
1 o to provide reassurance to the public that the program is capable of adequately assessing impacts.and identifying noteworthy changes in l 1
the radiological status of the environment. 1 Environmental Exposure Pathways to Humans f rom tirborne and Liquid Effluents .
I Environmental transport pathways is the term f or movement of radionuclides l
through the environment and trar. sport to humans. The' airborne pathways have basically five routes of importance: (1) direct radiation, (2) deposition on plants, (3) deposition on soil, (4) consumption by animals and (5) inhalation by humans. Liquid pathways have three basic routes of importance: (1) i ingestion of drinking water, (2) fish and shellfish consumption and (3)
l l
exposure from shoreline sediments. Each of these possible routes that can 1
lead to radiation exposure to humans is termed an exposure pathway. As can be I I
t seen, these routes are both numerous and varied. . While some pathways are l l
relatively simple, such as inhalation of airborne radioactive materials, others may be complex. For example, radioactive airborne particulate may deposit ]
onto forage which when eaten by cows may be secreted into milk, which is subsequently consumed by man. This is known as the air-grass-cow--milk pathway.
Although radionuclides can reach humans by a numbar of pathways, some are more I
) important than others. The critical pathway for a given radionuclides, is the one that produces the greatest dose to a population, or to a specific segment of the population. This segment of the population is known as the critical group, and may be defined by age, dietary, or other cultural f actors. The dose may be delivered to the whole body or confined to a specific organg the i organ receiving the greatest f raction of the dose is known as the critical organ. This information was used to develop the Oyster Creek program.
1 l
Sampiing l The Oyster Creek radiological environmental monitoring program consists of two '
t phases -- the preoperational and the 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 after the plant becomes
?
operational. The operational phase began in 1969 when Oyster Creek began power generation.
The program consists of taking radiation measurements and collecting samples f rom the environment, analyzing them for radioactivity content, and l interpreting the results. With emphasis on the critical pathways to humans, 1
samples from the aquatic, atmospheric, and terrestrial environments are collected. These samples include air, precipitation, well water, surf ace water, clams, sediment, fish, c rabs, vegetables, and soil. Thermoluminescent dosimeters (TLDs) are placed in the environment to measure gamma radiation levels. The Technical Specifications and recommendations from the scientific l
l staf f at Oyster Creek specify the sample types to be collected and analyses to j j
be performed.
l Sampling locations were established by considering meteorology, population f
distribution, hydrology, and land use characteristics of the local area. The sampling locations are divided into two classes, indicator and background.
j Indicator locations are those which are aroected to show effects from OCNGS i 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 l plant, the background stations are generally at least 10 miles from the plant. Therefore, background samples are collected at locations which are '
expected to be unaf f ected by plant 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 2, 3, and 4 show the current sampling locations around the OCNGS. Table A-1 in Appendix A describes the sampling locations by distance and azimuth.
i Analysis
)
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 sample collection and the types of analyses to be performed.
Additionally, analytical sensitivities (detection limit) and reporting levels also are specified. Table A-2 in Appendix A provides a synopsis of the sample types, number of sampling locations, collection f requencies, number of samples collected, types of analyses and frequencies, and number of samples analyzed.
Table A-3 in Appendix A presents problems encountered 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 analysis are described in Appendix C.
The analytical results are routinely reviewed by department scientists to assure that sensitivities have been achieved and that the proper analyses have
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l been performed. All analytical results are subjected to an automated review process which ensures that Technical Specification required lower limits of ! detection are met and that reporting levels are not exceeded. Investigations are conducted when anomalous values are discovered. l l Table 3 provides a summary of radionuclides concentrations in environmental
].
, samples from Oyster Creek in 1988. The dat' are summarized in the format I suggested in the USNRC Branch Technical Position (Ref. 14). i I Measurement of low radionuclides concentrations in environt. ental media requires f special analysis techniques. Analytical laboratories use state-of-the-art l laboratory equipment designed to detect beta and gamma radiation. This equipment must meet the required analytical sensitivities. Examples of the I
\
specialized laboratory equipment used are germanium detectors with multichannel analyzers for determining specific gamma emitting radionuclides, liquid scintillation detectors for tritium, low level alpha and beta counters, and coincidence counters for low level 1-131 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 l references 15, 16, and 17 and are also described in Appendix I.
Quality Assurance Program A quality assurance program is conducted in accordance with guidelines provided in Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring programs" (Ref. 18) and as required by the Technical Specifications. It is documented by written policies, procedures, and records. This program is designed to identify possible deficiencies so that immediate corrective action can be taken. It alsn provides a measure of confidence in the results of the monitoring program in order to assure the regulatory agencies and the public that the results are valid. The quality assurance program for the measurement of radioactivity in environmental media is implemented by: i a o auditing analytical laboratories o requiring analytical laboratories to participate in the USEPA l > Cross-Check Program o requiring analytical contractor laboratories.to split samples for l l separate analysis (recounts are performed when samples are not able l 1 to be split) o splitting samples, having the samples analyzed by independent 4 laboratories, and then comparing the results for agreement f l o requiring analytical laboratories to provide quality assurance 1 i reports showing laboratory instrument calibration and maintenance tests and results of blind, split, and duplicate analyses The quality assurance program and the results of the USEPA Cross-Check program I are outlined in Appendices D and E, respectively. ] I l procedures were written and approved by Environmental Controls, Quality ! 1 Assurance, and analytical laboratories to cover all aspects of the l radiological environmental monitoring program. These procedures cover such areaa as sample collection, sampling equipment calibration and maintenance, laboratory analysis, and data review. I 1 l i j
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L l DIRECT RADIATION MONITORING l Dose rates from external radiation sources were measured 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 f rom prior nuclear weapon testing, resulted in a certain amount of penetrating radiation being recorded at all monitoring locations. Indicator TLD's were placed systematically with at least one station in each compass sector (in a ring) at the site boundary. TLD's were also placed within a five mile radius ! of the OCNGS, in locations where the potential for deposition of radioactivity is known to be high, in areas of public interest, population centers, and in background locations which are typically greater than ten miles distant from the OCNGS. Sample Collection and Analysis l A state-of-the-art thermoluminescent dosimeter is used. Ther.noluminescence 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 l integrating the exposure received over a period of time. The energy stored in the TLDs as a result of interactions with radiation is removed and measured by a controlled heating process in a calibrated reading system. As 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. The readi ng process ' zeros' the TLD and prepares it for reuse. The TLDs in use f or environmental monitoring at Oyster Creek are capable of accurately measuring exposures between 1 mrem (well below normal environmental levels for the quarterly monitoring periods) and 1000 REM.
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1, i 1 l During 1988, TLD's were collected every twelve weeks from locations ranging I from less than 0.2 miles to 35.1 miles from the OCNGS. One TLD is exposed at i
~
each of 63 monitoring locations. Each TLD has four elements that respond to radiation independently. This provides three redundant detectors at each station. In addition, two of the 63 monitoring locations are quality control l (OC) stations at which one additional TLD is exposed for quality control l, purposes. Eight independent exposure measurements are made at these locations. l l Results l All TLD' dose rate data presented in this report have been normalized to a standard month (30.4 days) to eliminate differences caused by slightly ! differing exposure periods. TLD dose rate data are presented in Table J-l in l Appendix J.
-l In 1988, the dose rate measured at indicator TLD stations averaged 3.9 J mrem / standard month and ranged f rom 2.6 to 6.7 mrem /std. month. The dose rate at background TLD stations, located more than 30 miles from the OCNGS, averaged 3.8 mrem /std. month and ranged f rom 2.8 to 5.2 mrem /std. month. I Given the fact that the standard deviation of the quarterly TLD dose rates ranged f rom 0.05 to 0.7 mrem /std. month, these data indicate that there is no significant difference between the indicator and background mean dose rates.
These results are consistent with the results of TLD measurements from previous years (Fig. 5).
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M - A I 88 R G 88 O I R P I 88 G N I I 87 - R N _ O A 8 IT E N I 87 A - 8N 9 M E O M 87 D 1 I M N R 4A L U O 87 8T O T A g I 9N R G C _ 1 E K I e I 86 EM D C N SN A I 86 OO I B DRI w AV - I 86 MN ME 86 AL I s GA DI C 1 85 LG TO NL l 85 AO I E D i 65 _ MA R - K I 85 E E R 1 84 C R 1 84_ E T S Y O [x 1 1 84_ 84_ 0 9 8 7 6 5 3 2 1 1
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1 ) 1 ) l ATMOSPHERIC MONITORING I ) l A primary exposure pathway to man is the inhalation and ingestion of l radionuclides released to the atmosphere. Radioactivity in ambient air was sampled by a network of thirteen continuously operating air samplers. , i Precipitation samples were also collected at these thirteen locations. J t 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 Oyster Creek. Background air sampling and precipitation stations are located greater than 17 miles from the site in Lakewood, Allenburst, Cookstown, and Hammonton, NJ. l Sample Collection and Analysis ) Mechanical air samplers are used to continuously draw a recordei volume of air through a glass fiber (particulate) filter and then through a charcoal cartridge. A dry gas meter, which is temperature compensated, is used inside the air sampler to record air volumes. Internal vacuums are also measured in order to pressure correct the indicated volume. All air samplers are maintained and calibrated by GPU Nuclear instrument and control technicians. The particulate filters were collected weekly and analyzed for gross - Ja radioactivity. The filters were then combined monthly by individual station locations and anaP; zed for gamma-emitting radionuclides. 1 Charcoal cartridges, used to collect gaseous radioiodines, contain activated l charcoal. Charcoal cartridges were collected weekly and analyzed for iodine-131 (I-131) activity. l Precipitation samples were collected monthly using an eight inch diameter funnel that drains into a collection container. Each sample was analyzed for tritium and gamma-emitting radionuclides.
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f Results During 1988, 676 gross beta analyses were performed on air particulate filters (Table 3). The background mean gross beta activity (0.0158 pCi/m ) was f slightly higher than the indicator mean (0.0153 pCi/m ) and all gross beta analysis results were within two standard deviations of the historical mean. There was one gross beta LLD violation in February 1988. This was caused when the air sampling tpparatus at a background station in Allenburst, NJ failed ) af ter drawing 10.4 cubic meters of air (an average volume of approximately 500 i ! cubic meters is normally collected during the sampling period). Figure 6 presents the 1988 monthly mean gross beta concentrations for indicator and background stations. Note that the indicator station means are virtually identical to the background station means. These results are consistent with j the results of gross beta ar.alyses of air samples from previous years (Figure 7). The air particulate gross beta analysis results clearly show that effluent containing gross beta radioactivity from OCNGS operation did not have any measurable impact on the local environment. l Air charcoal cartridges (675 samples) were analyzed for iodine-131 (I-131) and no radioiodine was detected in any of the samples (Table 3). One iodine-131 result could not meet the required sensitivity. This was caused when the air sampling apparatus at a background station f ailed as described above. Gamma isotopic analyses were performed on 169 air particulate filter composites (Table 3). Only one sample result was f ound to be outside the range of two standard deviations around the historical mean. This occurred at the Hammonton air sampling station, a background station located 35 miles f rom the OCNGS. The nuclide identified was naturally occurring beryllium-7 (Be-7) which cannot be attributed to effluents f rom the OCNGS. With regard to precipitation sampling, 159 gamma isotopic and 162 tritium analyses were performed during 1988 (Table 3). Tritium activity was detected in thrce indicator and three background samples. The maximum tritium actirity (232 pCi/ liter) occurred at a background station and was only 12 percent of the lower limit of detection specified by the USNRC's Technical Specifications,
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jllI - N$m* C - a I E D - M V A - i O SR N NG OO I TR T AP = I C RG N O T NIN A ER E . CO M = P NTI i E D S O C NO N U N AM T O R A G U E I EL = A BA G M T K SN C R S E A O L 8 B T = i U 8 OM R A J 9 G NO C I 1 ER D R TI N N A AV I = I U E LN J Y UE - C L I Y TA = I A RC I M AG PO R OL I = R AI.D I P A NA AR - E : R ME K 1 A YE M LR - HC T R N E b-1 B E F OT MS Y 2 N - O d - - l l A 0 5 J 0 5 0 5 0 5 0 4 3 3 2, 2 1 1 0 0 0 0 0 0 0 0 0 0 0 mMEM:s5oNDoM$ k
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M A N - A E A I 88 _ 3 R M E 8G D M 8O I 88 _ 2 9R N R 1 P U O
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9 R K D 1 TO C N A I . 87 _ 3 B I SI NN OO L I 87_2 T M I Y AL B RA O I 87 _ 1 TT N NN R EE E I 86 _ 4 CM H NN C 86 _ 3 OO I CRI 1 E 3 , gu ' AV I 86 _ 2 TN E B E L I 86 _ 1 SA SC I 85 _ 4 OI RG GO L I 85 _ 3 EO TI AD I 85 _ 2 LA UR CK I I 85 _ 1 TE RE 84_4 AR I PC RR I 84_3 I E A T S I 84_2 Y O I 84_1 5 4 3 2 1 0 0 0 0 0 c* oMpO %% Um gpE$ L9 1
and 1.2 percent of the EPA's drinking water limit. Considering the large environmental inventory of tritium due to cosmic ray interactions and nuclear weapons testing, it is highly unlikely that the relatively minute amounts of tritium in OCNCS's effluents could have a measurable effect on existing } environmental concentrations. Detectable levels of beryllium-7 were also observed in precipitation samples (Table 3). This nuclide is naturally occurring and cannot be attributed to OCNGS operations. 1 I i 1 l
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} AQUATIC MONITORING Brackish water. f rom Barnegat Bay is drawn in through the south branch of Forked River, pumped.into the OCNGS cooling systems, and then discharged to l Barnegat Bay via Oyster Creek. Fish, clams, and crabs are harvested f rom the bay ( a recreational and, to a limited extent, commercial basis. LThe ingestion pathway is addressed because of fish, clam, and crab consumption. l On occasion, a radioactive liquid release is discharged under the ' limits established in the OCNGS Technical Specifications and 10CFR20. Highly l purified water, containing traces of radios ctivity, is discharged into Oyster ! Creek which has a minimum flow rate of slightly under one half million gallons
~
i per minute. There were 67 liquid releases made f rom the OCNGS during 1988. Samples of surface water, sediment, fish, blue crab, and hard clams were routinely collected from the OCNGS intake and discharge canals, Barnegat Bay, l l ?- Manahawkin Bay, and Great Bay in order to monitor any environmental impact J that may be associated with these releases. 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 sarf ace water and sediment are located in the OCNGS' discharge canal - 1 Oyster Creek. No clams are available to be collected 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 Bay, ! approximately 11 miles south of the OCNGS. A second background station is located approximately 22 miles south of the OCNGS in Great Bay. ! Blue crab and fish samples were collected every four weeks (when available) from two indicator stations and one background station. Both indicator stations are located in the OCNGS discharge canal and the background station is located-in Great Bay. Crab pots were~used to catch blue crab. The hook and line technique was used to catch fish.
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E l-All samples were analyzed for gamma-emitting radionuclides; water samples were also subjected to tritium analyses. Results ) Surf ace water was sampled 101. times at eight different locations during 1988. No tritium activity was detected in any of these sample,s (Table 3). Regarding surf ace water gamma isotopic analyses, only two nuclides, ' potassium-40 (K-40)^ and radium-226 (Ra-226),.were detected and each of these nuclides is naturally occurring (Table 3). Based upon these data, operation of the OCNGS had no detectable affect upon the local surface water. Sixty two clam samples were collected from five different locations during 1988. Gamma isotopic analyses indicated that the only gamma-emitting nuclide-present was potassium-40 (K-40) which is naturally occurring and commonly found in abundance in salt water (Table 3). Seven gamma-emitting nuclides were detected in the 101 sediment samples collected during 1988 (Table 3) . Five of these nuclides, bery111um-7, potassium-40, radium-224, radium-226, and actinina-228 are naturally occurring and were seen f requently at both background and indicator stations. Cesium-137, which is a fission fallout product and also occurred in OCNGS effluents during 1988, was also seen at both' background and indicator stations. Cesium-137 has been detected in considerable abundance af ter I weapons tests and the Chernobyl accident. The presence of this.nuclide-in. similar concentrations in 92 percent of the background samples and only 50 percent of the indicator samples (Table 3) suggests that most of the t cesium-137 in Barnegat Bay sediments originated from the latter two sources.
- Cobalt-60 was detected in thirty percent of the indicator station samples and' L{
none of the background station samples (Table 3). The presence of this ' nuclide in Barnegat Bay sediments is of' interest because it can be' attributed to OCNGS liquid effluents. As documented in previous reports, OCNGS related cobalt-60 has been found in sediment and clams f rom Barnegat Bay since at least the mid-1970's. The volume of liquid effluents has been significantly
-143-i
} reduced since that time and this decrease in the rate of input of cobalt-60 to the environment, combined with the radioactive decay of the existing inventory, has resulted in a gradual decline in the cobsit-60 concentration in sediment i and clams (Figs. 8 and 9) . The last detectable concentration of this nuclide in clams was during the third quarter of 1987 (Fig. 8). 1 Nineteen blue crab samples were collected from three locations during 1988. A gamma isotopic analysis was performed on each sample of crab meat and f naturally occurring potassium-40 (K-40) was the only nuclide identified (Table 3). The close association of this species with Barnegat Bay sediments could I make it susceptible to cobalt-60 uptake. However no detectable cobalt-60 activity has been observed in blue crab samples collected since 1985 (Fig.10). l ( Forty-one fish samples, yielding nine species, were collected f rom 3 sampling locations during 1988. The species and number of samples collected are listed below: l TABLE 4 SPECIES OF FISH CAUGHT AS PART OF THE OCNGS REMP IN 1988 l Fish Number of Samples Tautog 10 ) Summer Flounder 7 White Perch 7 Bluefish 6 Winter Flounder 4 American Eel 3 Blowfish 2 Sea Bass 1 Weakfish 1 Naturally occurring potassium-40 (K-40) was detected in each of the 41 gamma isotopic analyses (Table 3). One bluefish sample, collected f rom indicator station 93, had a detectable quantity of cesium-137 (Cs-137) radioactivity. As discussed above, cesium-137 is a ubiquitous fission f allout product and has been detected in considerable abundance after weapons tests and the Chernobyl
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I 88 - 4 N - M A N A E A I 88 - 3 T R M E H - G M G O D I 88 - 2 R N R U P U O A 8 O T I 88 - 1 C 8G R A A 9N G C I D 1 I R K I D I 87 - 4 E
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nuclear accident. It was also discharged in very small quantities (Table 2) from the OCNGS during 1988. The level of Cs-137 activity in this fish (22.5 > pCi/kg (wet)) was only 15 percent of the lower limit of detection and one pe rce nt of the reporting level specified by the USNRC's Technical f Specifications. Similar low levels of this nuclide are found in fish throughout the world as a result of f allout (Ref.20). )
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a TERRESTRIAL MONITORING' l t Radionuclides released to the atmosphere may be deposited on ' soil and jl r vegetation and may be incorporated into milk, vegetables, and/or other food f products. To assess the impact of dose to humans from the ingestion pathway,. food product samples such as green leafy vegetablos, were collected and
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analyzed during 1988. Surf ace soil samples were ruso collected and analyzed f or the purpose of monitoring the potential buildup' of atmospherically deposited radionuclides. The contribution of radionuclides from the OCNGS operation was assessed by comparing the results of samples collected in prevalent downwind locations, primarily to the southeast of the. site, with background samples eq11ected f rom distant and generally upwind directions. I A dairy census was conducted to determine the locetions of commercial dairy operations and milk producing animals in dach of the 16 meteorological sectors out to a distance of five miles from the OCNGS. The' census showed that there-were no dairy animals within a 5 mile radius of the plant ( Appendix F). I i GPUN Oyster Creek Environmental Controls established and maintained two gardens at the site boundary in the two sectors with the highest potential for ; radioactive deposition in lisa of performing an annual garden' census. Both gardens are greater than 50 equare meters in size end produce green leafy vegetables. A commercial f arm located approximately 24 milia northwest of the site was used as a background station. Sample Collection and Analysis Broadleaf vegetab'.es, specifically cabbage and collards, were collected on a monthly basis beginning in June and ending in November 1988. A gamma isotopic analysis was. performed on each sample. Surface soil samples from the gardens were collected during July and October.
.Each soil' sample was subjected to a gamma isotopic analysis. 1
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p Results Naturally occurring potaFsium-40 activity and beryllium-7 activity was detected in cabbage and collard samples at both indicator and background stations (Table 3). . Cesuam-137 activity was also detected in twelve of the thirty-six vegetable samples, but only in samples collected. at the indicator ststions (Figs. 11 and 12). The maximum concentration of this nuclide-observed in vegetable samples was .44.5 pCi/kg (wet) which is only 56 percent of-the lower limit of detection (80 pCi/kg (wet)).and 2.2 percent'of the reporting level (2,000pci/kg (wet)) specified by the USNRC's Technical Specifications. Cesium-137 was detected,:in similar concentrations, in both background and indicator soil samples collected from the gardens in which the' vegetables were grown (Table 3) . It is well established that root. uptake of' l Cs-137 from the soil'is minimal and that foliar absorption is the main pathway. of Cs-137 to the f ood chain (Ref. 20) . These results:suggest that the cesium-137 detected in the vegetables collected at the indicator stations was atmospherically deposited rather than taken up from the soil. As no cesium-137 activity was detected in OCNGS gaseous effluents during 1988, it is likely that the trace amounts of this nuclide found in vegetables originated f rom previous weapons testing and the Chernobyl nuclear accident. In addition to the cesium-137 activity, naturally occurring potassium-40, radium-228, and actinium-228 activity was observed in all soil samples collected from indicator and t'ackground stations (Table 3). l
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M I E - R A 5 D - G - V _ O 1 O R N P e G N T EI I C _ GR e O AO N G BTI A N E P B A N M I D __ I E CO A S M R E N I L O R A T G YT A D N I U T I N C I U A VE I D O T M N R L CN I G I U AO K J 7I R C 3V A 1 N B N
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I. y. r l GROUNDWATER MONITORING The ' Oyster Creek Nuclear Generating. Station is located on the Atlantic Coastal l Plain Physiographic Province. This. Province extends southeastward from the Fall Zone, a topographic break that marks the boundary between the Atlantic Coastal Plain and the more rugged topography of the Piedmont Province. ' The Fall Zone is also where the crystalline and sedimentary--rocks of the Piedmont and the unconsolidated coastal plain sediments meet. At least five distinct bodies of fresh groundwater or aquifers exist in the ' vicinity of the OCNGS. From the surface downward, they are:
- 1. Unconfined, Recent and Upper Cape May Formation-
- 2. Confined, Lower Cape May Formation
- 3. Confined, Cohansey Sand
- 4. Confined, Jpper Zone in the Kirkwood Formation
- 5. Conf aned, Lower Zone in the Kirkwood Formation l
The unconfined Recent and Cape May Formations are replenished directly by local precipitation. The recharge to the confined aquifers occurs primarily f rom direct rainf all penetration on the onerop areas, which are generally to the west of the site at higher elevations. Sample Collection and Analysis As part of the routine-REMP, six wells were sampled on a monthly baPis. Grab samples were obtained from five loca1 residences and one OCNGS well. The depths of the residential wells are unknown but most local domestic wells draw upon the Cohansey aquifart the OCFTS well is approximately 380 f eet deep, in the Kirkwood formation. Each sample was subjected to a tritium and gamma isotopic analysis. In addition, a well network was installed around the OCNGS in 1983 to serve as an early detection and monitoring system for spills, separate from routine-REMP sampling. During 1988, fifteen of these walls located in the Cape May,
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Cohansey and Kirkwood aquifers, were sampled semiannually using grab sample l methodology. The samples were analyzed for tritium and gamma emitting nuclides. Results Seventy-seven routine REMP well water samples were collected during 1988 (Table 3). No gamma-emitting nuclides were detected in any sample. Tritium activity was detected in only one sample and this was not considered significant because the level of tritium was less than one percent of the EPA drinking water limit and less than 10 percent of the lower limit of detection required by the USNRC's Technical Specifications. The results of the analyses of 26 samples from the OCNGS spill monitoring well network were similar (Appendix H). No gamma-emitting nuclides were detected and tritium activity was detected in only two sanples. The maximum tritium level (500 pCi/ liter) was less than three percent of the EPA drinking water limit and only 25 percent of the lower limit of detection required by the Technical Specifications. Considering the very large environmental inver. tory of tritium due to cosmic ray interactions and nuclear weapons testing, it is highly unlikely that the relatively minute amounts of tritium in the OCNGS's effluents could have a measurable erfect on existing environmental ) concentrations.
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RADIOLOGICAL IMPACT OF OCNGS OPERATIONS An assessment of potential radiological' impact indicated that radiation doses to the public from 1988 operations at OCNGS were well below all applicable regulatory limits and were significantly less than doses received f rom common sources of radiation. The 1988 whole -body dose potentially received by an f assumed maximum exposed individual f rom OCNGS liquid and. airborne effluents was conservatively calculated to be about 0.29 millirem total. These doses were significantly less than the 10CFR50, Appendix I guidelines. The 1988 whole body dose to the surrounding population f rom OCNGS liquid and airborne ef fluents was calculated to be 0.3 person-rem and 1.5 person-rem respectively. This is more than five hundred and fifty thousand (550,000) times lover than the doses to the total population within a 50-mile radius of the OCNGS resulting from natural background sources. l Determination of Radiation Doses co the Public To the extent possible, doses to the public are based on direct- measurement of dose rates from external sources and measurements of radionuclides concentrations in the environment which may contribute to an internal dose of radiation. Thermoluminescent dosimeters (TLDs) positioned'in the environment around Oyster Creek provide measurements to determine external radiation doses to humans. Samples of air, water, food productu, etc. are used to determine internal doses. During normal plant operations the quantities of radionuclides releases are typically too small to be measured once distributed in the offsite environment. As a result, the potential offsite doses are calculated-using a computerized model that predicts concentrations of radioactive materials in the environment and subsequent radiation doses on the basis of radionuclides ! released to the environment. GPUN calculates doses using an advanced dispersion model called MIDAS (Meteorological Information and Dose Assessment System). This model incorporates the guidelines and methodology set forth by _ the.USNRC in Regulatory Guideline 1.109. Due to the conservative assumptions
]
3 that are used in the model, the calculated doses are considerably higher than
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the actual doses to people. Generally, when levels of radioactivity in environmental samples were compared to levels predicted by the model, the i resultant doses predicted by the model were higher than the actual environmental samples. The type and amount of radioactivity released f rom Oyster Creek is calculated using measurements f rom effluent radiation monitoring instruments and effluent sample analysis. Once released, the dispersion of radionuclides in the environment is readily determined by ccmputer modelling. Airborne releases i are diluted and carried away from the site by atmospheric diffusion which continuously acts to disperse radioactivity. Variables which affect l atmospheric dispersion include wind speed and direction, temperature at different elevations, and terrain. A meteorological monitoring station l l northwest of the reactor site at Oyster Creek is linked to a computer terminal l which permanently records all necessary meteorological data. Computer models also are used to predict the downstream dilution and travel times for liquid l 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 13. The exposure pathways considered for the discharge of Oyster Creek liquid effluent are fish and shellfish consumption and shoreline exposure. The exposure pathways considered for airborne effluents include plume exposure, inhalation, vegetable consumption (during growing season) and land deposition. MIDAS employs numerous data files which describe the area around Oyster Creek in terms of demography and foodstuffs production. Data files include such information as the distance from the plant stack to the site boundary in each compass sector (sixteen in all), the population groupings, gardens of more than 500 square f eet, meat animals, and crop yields. When determining the dose to humans, it is necessary to consider all pathways and all exposed tissues, sumuing the dose from each to provide the total dose I for each organ as well as the whole body f rom a given radionuclides in the 'l environment. Dose calculations. involve determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides taken into the
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- _ _ _ _ _ - - 0
FIGURE 13 EXPOSURE PATHWAYS FOR ROUTINELY RELEAS 3 RADIONUCLIDES FROM.THE OCNGS Geseous Effluents - l l Oyster Creek Station - Liquid Effluents - -. 40 f ,
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b[Tj PREDOMINANT RADIONUCLIDES NOBLE GASES (Xe, Kr) ACTIVATION PRODUCTS (Co-60, Mn-54) . Plume Exposure Shoreline Exposure and Consumption RADI0 IODINES (I-131. I-133) f Seafood i Inhalation and Consumption RADIOCESIUMS (Cs-134, Cs-137) of Vegetables Shoreline Exposure and Consumption of Seafood and Vegetables- ; TRITIUM (H-3) l Inhalation and Consumption of Vegetables.
1 body, the metabolism of the radionuclido in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted and half-life. MICAS also contains dose conversion factors for 75 radionuclides for each of fcur age groupe sadults, teenagers, children and infants) and eight organs (total body, thyroid, liver, skin, kidney, lung, bone and gastro-intestinal tract). l Doses are calculated for what is termed the " maximum hypothetical ! individual." This individual is atsumed to be aff ected by the combined maximum environmental concentrations wherever they occur. For liquid releases, the maximum hypothetical individual woult be one who stands at the U.S. Roate 9 discharge canal shoreline for 67 hours per year while eating 43 prands of fish and shellfish. For airborne releases, the maximum hypothetical ( individual would live at the location of highest radionuclides concentration } l for inhalation and direct plume exposure while eating 1,389 pounds of i ) vegetables per year. This location is 966 meters to the southeast and 966 i meters to the north-northeast based on the meteorological conditions at the 1 l time of releases. The conservative usage factors and other assumptions used
- in the model result in a conservative overestimation of dose. Doses to the l
population within 50 miles of Oyster Creek for airborne effluents and the ) ! entire population using the Barnegat estuary and Atlantic Ocean are calculated. ) Appendix G contains a more detailed discussion of the dose calculation methodology.
}.esults of Dc.se Calculations Doses from n<tural background radiation provide a baseline for assessing the potential public health significance of radioactive effluents. The average person in tb9 United States receives about 300 millirem (mR) per year f rom natural background radiation sources. Natural background radiation from cosmic, terrestrial and natural radionuclides in the human body (not including radon), averages about 100 mR/yr. The natural background radiation from cosmic and terrestrial sources varies with geographic location, ranging from a low of about 6S mR/yr on the Atlantic and Gulf coastal plains to as much as 350 mR/yr on the Colorado plateau (Ref. 6). The National Council of Radiation
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i
- Protection and Measurements (NCRP) now estimates that the average individual in the United States receives an annual dose of about-2,400 milliremo to the lung from natural radon gas. This:1ung dose is considered to be equivalent to a whole body dose of 20G millirems (Ref. 5). Effluent releases from the OCNGS-
) I and other nuclear power plants contribute but a very small percentage to the i natural radioactivity which has always been present in the-air, water, soil j and even in our bodies. In general, the annual population doses.from natural I background radiation (excluding radon) are 1,000 to 1,000,000 tinies larger than the doses to the same population resulting from nuclear power plant operations (Ref. 19). Results of the dose calculations are summarized in Tables 5 and 6. Table 5
~
compares the calculated maximum. dose to an individual of the public to the l OCNGS Technical Specifications dose limits. Table 6 presents the maximum total body radiation doses to the population within 50 miles of the plant from airborne releases and to the entire population using Barnegat Bay and Atlantic Ocean biota for liquid releases. These conservative calculations of the doses to members of the public from the Oyster Creek Nuclear Generating Station are small fractions of those specified in 40 CFR 190 (EPA standard 25 mrem per site), 10 CTR 20 (500 mrem per year), and the Oyster Creek Technical Specification T.6.N. They are also considerably lower than the doses from natut 7 background and f allout f rom prior nuclear weapon tests.
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t TABLE 5 CALCULATyD MAXIMUM HYPOTHETICAL D01ES TO AN biaIVIDUAL FROM LIQUID AND AIRBORNE EPPLUENT RELEASES PROM OLTTER CREEK- - POR 1988 Maximum Hypothetical Dose To An Individual Calculated Value Pe rcen't ' of - Oyster Creek NGS Tech. Spec. Limit ' millirem /yehr, Tech..jSpec. ' milli rem / yea r OCNCS Limit From Radionuclides 3 total body, or 0.005. 'O.17' In Liquid Releases 10 any organ' O.021'- 0.21-From Radionuclides 5 total body, or 0.280 5.60
'In Airborne Releases 15 skin 0.290- 1.93 (Noble Gas)
From Radionuclides 15 any organ 0.260 :1.73 In Airborne Releases (Iodine and. Particulate) , Calculated.Value Percent of 40 CFR 190 millirem / year Tech.' Spec. milli rem / yea r OCNGS~ Limit Total From Site 15 whole body 0.285 1.14-75 thyroid 0.260 0.35 25 other organs '0.311- 1.24'
'_150.- 'M____ > ; >. ,
TABLE 6 CALCULATED MAXIMUM TOTAL RADIATION DOSES TO THE POPULATION FROM LIQUID AND AIRBORNE EFFLUENT PROM OYSTER CREEK ) FOR 1988 )- Calculated Population ) Total Body Dose l Person-Rem / Year \ OCNGS Pror Radionuclides in Liquid Releases 0.3 (Barnegat Bay and Atlantic Ocean Users) From Radionuclides in Airborne Releases 1.5 (Within 50-Mile Radius of OCNGS) DOSE DUE TO NATURAL BACKGROUND RADIATION Approximately 990,000 Person-Rem Per Year l
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REFERENCES (1) GPU Nuclear Corporation. "1986 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station." May 1987. (2) GPU Nuclear Corporation. "1987 Radiological Environmental Monitoring Report for Oyster Creek Nuclear Generating Station.' May 1988. (3) Jersey Central Power and Light Company. ' Oyster Creek Nuclear Generating Station Operating License and Technical Specifications," Appendix A, DPR-16, April 1969. (4) GPU Nuclear Corporation. " Oyster Creek Nuclear Generating Station Emergency Plan," Document Number 2000-PLN-1300.1, Revision 8, January 1983. (5) National Council on Radiation Protection and Measurements, Report No. 93,
" Ionizing Radiation Exposure of the Population of the United States," 1987.
(6) CRC Handbook, "Radioecology: Nuclear Energy and the Environment," F. Ward Whicker and Vincent Schultz, Volume I, 1982. (7) National Council on Radiation Protection and Measurements, Report No. 22,
" Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, Issued June 1959, superseding Handbook 52).
(8) International Commission on Radiological Protection, Publication 2, ' Report of Committee II on Permissible Dose for Internal Radiation (1959)," with 1962 Supplement :ssued in ICRP Publication 6; Publication 9,
' Recommendations on Radiation Exposure," (1965): ICRP Publication 7 (1965),
amplifying specific recommendations of Publication 9 concerning environmental monitoring; and ICRP Publication 26 (1977). (9) Federal Radiation Council Report No. 1, " Background Material for the l Development of Radiation Protection Standards," May 13, 1960.
.-162-l
. . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ j
t - 1 , (10) National Council on Radiation Protection and Measurements, Report No. 39, 1 ) ' Basic Radiation Protection Criteria,"-January 1971. j j y (11) National Council on Radiation Protection and Measurements, Report No. 62,'
' Tritium in the Environment," March 1979.
L l I (12) National Council on Radiation Protection and Measurements, Report No. 81,
" Carbon-14 in the Environment," May 1985. j 1
l (13) United States Nuclear Regulatory Commission. Regulatory Guide 4.1,
" Programs for Monitoring Radioactivity in The Environs of Nuclear Power. J Plants," Revision 1, April 1975.
(14) United States' Nuclear Regulatory Commission Branch Technical Position, 'An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979. (15) Teledyne Isotopes. " Procedures and Quality Assurance Handbook." IWL-00320365, 1975. (16) Radiation Management Corporation. " Analytical and Quality Control Program." RMC-TM-75-3, 1975. 1 (17) Teledyne .aotopes. " Environmental Radiation Analysis Quality Control i s Manual." IWL-00320161, 1975. '] I (18) United States Nuclear Regulatory Commission. Regulatory Guide 4.15,
" Quality Assurance for Radiological Monitoring Programs (Normal Operations)
- Effluent Streams and the Environment," Revision 1, February 1979. I i
(19) NUREG/CR-4068 " Summary of Historical Experience with Releases of Radioactive Materials from Commercial Nuclear Power Plants'in the United ; States', 1985. (20) Eisenbud, Merril, 1987. " Environmental Radioactivity." Academic Press. j
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) I f l APPENDIX A 1988 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions i
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TABLE A-2 SWDPSIS OP 'IHE OPERATIQiAL RADIOUXIICAL DNIPG#DfIAL MOUERI?G EXJRAM C200CIED BY GPUN DUIR2&DTIAL (DNIROLS FOR OYS'IER CREEK NUCLEAR GDIERATI!C S'IATIQ1 1988 (3) NUMrER OF NUMBER OF PJMBER OF SAMPLE SAMPLItG mrnrTION SAMPLE TYPE OF ANALYSIS SAMPLES TYPE IDCATIQG FREQUDC' O_V1Mm ANALYSIS FRD3UfNCY ANALYZED (2) Air Ibrticulate 13 weekly 676 GI-Beta weekly 676 Guma 4 week 169 canpocite Air Icdine 13 weekly 675 I-1 31 weekly 675 Precipitation 13 4-week 162 Gunma 4+eek 159 ccxiposite H-3 4-week 162 cocposite Well Water 6 4-week 77 Gwma 4-week 77 H-3 4-week 77 Surface Water 8 4-week 101 Gmma 4-week 1 01 H-3 4 veek 101 Clam 5 4-week 62 Guma 4-week 62 Sediment 8 4-week 101 Grma 4-week 1 01 Vegetables 3 4-week 36 Gsma 4-week 36 Soll (3) 3 12-week 6 Gmma 12-week 6 Pish 3 4-week 41 Guma 4-week 41 Crab 3 4-week 19 Gzma 4-week 19 TLD-Ouarterly 63 12-week 255 Irm= raion 12-week 255 Icse (1) Itis table does not i:rhale OL'ality cbntrol (OC) results. (2) 'Ihe rumber of synples araly7ed does tot irchde Japlicate ara.yses, recounts, or reanalyses. (3) Only when vegetables collected.
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TABLE A-3 SAMPLING AWD ANALYSIS EXCEPTIOMS 1988 More than the minimum number of samples and analyses required by the Technical Specifications were collected and performed so that none of the exceptions noted in this table resulted in any violations of the Technical specifications.
.1. January 4,1988 to A11enhurst Air Sampler (A) had a blown f use.
January 5,1988 The unit operated for 141.1 hours during the sampling period. s I
- 2. Janua ry 11, 1988 Precipitation collection apparatus Station 72 found vandalized. Sample was lost.
l 3. Janua ry 11, 1988 Precipitation collection apoaratus at Station 73 was disturbed when JCP&L Company moved apparatus. Sample was Irat.
- 4. January 11, 1988 to Well water sample at Station 22 could not bo Januat; 15, 1980 collected due to the occupants not being home (extended vacation).
- 5. January 11,1988 to January 16, 1988 Surface water, clam, and sediment samples from Stations 23, 31, and 94 could not be collected because the respective bays were frozen over.
6 January 11, 1988 to An air iodine sample from Station 66 was not January 18, 1988 taken due to the technician failing to install a filter in the sampler. February 1,1988 to A11enhurst Air Sampler (A) had a blown fuse. February 10, 1988 The unit operated for 2.7 hours during the sampling period.
- 8. January 11, 1988 to February 8, 1988 Precipitation Stations 71 and 72 collected an extremelf small quantity of sample - no gamma isotopic analysis could be performed,
- 9. March 1, 1988 Station 71 precipitatica collection apparatus partially destroyed when it was hit by construction equipment. The sample collected to date was lost. The apparatus was repaired and reloaded. !
- 10. March 4, 1988 to A calibration check was performed on the March 8,1988 Cookstown Air Sampler (C). The technician inadvertently f ailed to turn the station on af ter completion.
)
i
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l i TABLE A-3 (Continued) S AMPLING AND ANALYSIS EXCEPTIONS 1988 , 11. March 6, 1988 to Station 5 air sampler pump f ailed. The unit i March.9, 1988 ' operated for 139.4 hours duri.0 the campling I- period.. 3 l 12. March 7, 8, 1988 No precipitation collected at Station 20 and 73.
- 13. March 10, 1988 All precipitation samples inadvertently f
7' preserved with HCL acid. As a result,.the { iodine and tritium analysis results are ir. valid. j s
- 14. March 19,1980 to Station .73 air sampler pump f ailed. The unit March 23,1988 operated for 115.5 hours during the sampling -1 l period. -
]
- 15. March 28, 1988 to Station 3 air particulate filter not seated April 4, 1988 properly. Approximately 70% of the filter
'l covered the opening.
- 16. January 25, 1988 to Station 78 quarterly TLD lost due te vandalism.
April 20,1988
- 17. January 27, 1988 to Station 82 r,uarterly TLD lost due to vandalism.
April 22, 1988
- 18. May 7, 1988 to Station C air sampler pump failed. The un.i.t May 11, 1988 operated for 110.7 hours.
- 19. June 11, 1988 to Station 20 air sampler not operating.
June 15, 1988 Vandalism - the breaker box switch was turned off. 20 June 2,1988 to No precipitation collected at Station 73. June 27, 1988
- 21. April 22, 1988 to The quarterly TLD at Station 83 was lost due to July 13,1988 vandalism.
- 22. July 26, 1988 Cabbage and collard samples from Station 36 rotted in transit to the OC lab in Northbrook, Illinois - had to be discarded prior to analysis.
- 23. July 25, 1988 to No p Tainitation collected at Station A.
August 22, 1988
- 24. December 15, 1988 No fish collected at Station 94 in 4.25 hours.
- 25. December 18, 1988 No fish collected at Station 93 in 2 hours.
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. _ _ _ _ _ - _ _ - - _ - _ _ ~
l APPENDIX B 1988 Lower Limits of Detection (LLD) Exceptions l l
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TABLE B-1 TECHNICAL SPECIFICATIONS ANALYTICAL RESULTS WHICH FAILED TO MEET THE REQUIRED LLD DURING 1988 No. of Samples Out Sample Media Analysis Required LLD of Compliance Comments Air Particulate Gross Beta 0,01 pCi/m3 1 Low Sample Volume Air Iodine I-131 0.07 pCi/m3 1 Low Sample Volume FISH Fe-59 260 pCi/kg (wet) 1 Low Sample Volume (White Perch) Zn-65 260 pCi/kg (wet) 1 Low Sample volume Cs-134 130 pCi/kg (wet) 1 Low Sample volume \ NOTE: More than the minimum number of samples and analyses required by the Technical Specifications were collected and performed so that none of the missed LLD values listed ao'ove resulted in any violations of the Technical Specifications, i l
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I \ l l l l l APPENDIX C Changes Eff ected in the 1988 REMP
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APPENDIX C Changes Effected in the 1988 REMP January, 1988 The utility pole that supported the rain water co11setion apparatus at station 73 was removed. Another utility pole was - installed in close proximity and the collection apparatus reinstalled. 1 May, 1988 Began yearly planting of gardens at st?tions 35 and 66. November, 1988 The utility poles used to' hold TLDs at stations 61 and 63 were ) removed and not replaced. Utility poles across U.S. Route 99 { from the previous respective locations were used as new TLD stations. December, 1988 The number of clams collected per station was reduced from 72 clams to 36 clams. Enough sample is collected in 36 clams to achieve the minimum required aliquot.
-1
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W v'" --wm-, ---- ._ _, .._.._ i i l
.1 APPENDIX D 1 1988 Quality Assurance Recults 1
i l I 1
.l
)
1 1 1 l
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_-________a
1 Tr.e Oyster Creek Ertvironmental Controls Quality Assurance (QA) Program consists of three phases, phsse I consists of splitting samples collected at designated stations and having them :.nalized by' separate (independent) l laboratorice, Analysis results f rom the quality control (QC) laboratory are compared to those f rom the primary laboratory as set forth in OC Environmental Controls procedure 9410-ADH-4500.07. Agreement criteria are established in this procedure, If nor.-agreement of}}