ML021480052

Part 1 of 2, Ltr Forwarding Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report (AREOR)

ML021480052
Person / Time
Site:	Davis Besse
Issue date:	05/13/2002
From:	Mccloskey P FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Material Safety and Safeguards
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Davis-Besse Nuclear Power Station "Ae 5501 North State Route 2 SnOak Harbor,Ohio 43449-9760 May 13, 2002 I-;J DSC-02-00046 Director, Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission NMSS/OD Mail Stop T-8A23 Washington, D.C. 20555-0001 Ladies and Gentlemen:

Enclosed is a copy of the Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report (AREOR). The 2001 AREOR is similar in format and content to those of previous years, and furthers our effort in educating the public about the compatibility of nuclear power and the environment.

As in previous years' reports, the 2001 AREOR contains information on the Radiological Environmental Monitoring Program, as well as information on meteorological monitoring, hazardous chemical management, water and wastewater treatment, and the management of the 730-acre wetland located on the site. In addition, the Radioactive Effluent Release Report for 2001 and background information on basic health physics, nuclear power generation, and a discussion of the health risks of dose are also included in the report.

If you have any questions or comments, or would like further information, please contact Mr. Bruce Geddes at (419) 321-7388.

Very truly yours, Patrick J. McCloskey Manager- Environmental and Chemistry AMP/ses Enclosure

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Davis-Besse Nuclear Power Station January 1, 2001 through December 31, 2001 Date:_./______

Prepared by:

Bruce L. Geddes Supervisor - Nuclear Chemistry Services Date: 47/29/o, Alfred M/jercival Jr.

Services Nuclear Chemistry Technologist - Nuclear Chemistry Date: 04,/Z /1 Z.

Approved by:

Patrick J. McCloskey Manager - Environmental and Chemistry Davis-Besse Nuclear Power Station April 2002

Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental TABLE OF CONTENTS Page Title iv List of Tables vi List of Figures viii Executive Summary INTRODUCTION I

Fundamentals Radiation and Radioactivity 2 Interaction with Matter 3 Quantities and Units of Measurement 5 Sources of Radiation 7 Health Effects of Radiation 9 Health Risks 10 Benefits of Nuclear Power I1 Nuclear Power Production 11 Station Systems 16 Reactor Safety and Summary 19 Radioactive Waste 19 Description of the Davis-Besse Site 22 References 24 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Introduction 26 Preoperational Surveillance Program 26 Operational Surveillance Program Objectives 27 Quality Assurance 27 Program Description 28 Sample Analysis 32 Sample History Comparison 35 i

________ IL E Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Title Paue RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) 2001 Program Anomalies 36 Atmospheric Monitoring 37 Terrestrial Monitoring 43 Aquatic Monitoring 55 Direct Radiation Monitoring 67 Conclusion 78 References 79 RADIOACTIVE EFFLUENT RELEASE REPORT Protection Standards 82 Sources of Radioactivity Released 82 Processing and Monitoring 83 Exposure Pathways 84 Dose Assessment 85 Results 86 Regulatory Limits 87 Effluent Concentration Limits 88 Average Energy 88 Measurements of Total Activity 88 Batch Releases 89 Sources of Input Data 90 Doses to Public Due to Activities Inside the Site Boundary 90 Inoperable Radioactive Effluent Monitoring Equipment 91 Changes to The ODCM and PCP 91 Borated Water Storage Tank Radionuclide Concentration 91 LAND USE CENSUS Program Design 109 Methodology 109 Results 110 ii

Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Page Title NON-RADIOLOGICAL ENVIRONMENTAL PROGRAMS 115 Meteorological Monitoring 116 On-site Meteorological Monitoring 131 Land and Wetlands Management 132 Water Treatment Plant Operation 136 Chemical Waste Management 137 Other Environmental Regulating Acts 139 Other Environmental Programs APPENDICES 141 Appendix A: Interlaboratorv Comparison Propram Results 163 ADmendix B: Data ReDortine Conventions Air and Water 165 Appendix C: Effluent Concentration Limit of Radioactivity in 167 Appendix D: REMP Sampling Summary iii

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report List of Tables Table Page Title Number Number Risk Factors: Estimated Decrease in Average Life Expectancy 1 10 Sample Codes and Collection Frequencies 2 30 Sample Collection Summary 3 31 Radiochemical Analyses Performed on REMP Samples 4 33 Air Monitoring Locations 5 39 Milk Monitoring Location 6 44 Groundwater Monitoring Locations 7 46 Broadleaf Vegetation and Fruit Locations 8 47 Animal/Wildlife Feed Locations 9 48 Wild and Domestic Meat Locations 10 49 Soil Locations 11 51 Treated Surface Water Locations 12 57 Untreated Surface Water Locations 13 60 Shoreline Sediment Locations 14 61 Fish Locations 15 63 Thermoluminescent Dosimeter Locations 16 69 Gaseous Effluents - Summation of All Releases 17 92 Gaseous Effluents - Ground Level Releases - Batch Mode 18 93 Gaseous Effluents - Ground Level Releases - Continuous Mode 18 94 Gaseous Effluents - Mixed Mode Releases - Batch Mode 19 96 Gaseous Effluents - Mixed Mode Releases - Continuous Mode 19 97 Liquid Effluents - Summation of All Releases 20 99 Liquid Effluents - Nuclides Released - Batch Releases 21 100 Liquid Effluents - Nuclides Released - Continuous Releases 21 102 Solid Waste and Irradiated Fuel Shipments 22 104 Doses Due to Gaseous Releases for January through December 2001 23 106 Doses Due to Liquid Releases for January through December 2001 24 107 Annual Dose to The Most Exposed Member of The Public 2001 25 108 Closest Exposure Pathways Present in 2001 26 112 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters 27 114 iv

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table Page Title Number Number Summary of Meteorological Data Recovery for 2001 28 120 Summary of Meteorological Data Measured for 2001 29 121 Joint Frequency Distribution by Stability Class 30 126 v

n J Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report List of Figures Figure Page Description Number Number The Atom 1 1 Principal Decay Scheme of the Uranium Series 2 3 Range and Shielding of Radiation 3 4 Sources of Exposure to the Public 4 8 Fission Diagram 5 12 Fuel Rod, Fuel Assembly, Reactor Vessel 6 13 Station Systems 7 15 Dry Fuel Storage Module Arrangement 8 21 Map of Area Surrounding Davis-Besse 9 22 2001 Airborne Particulate Gross Beta 10 38 Air Sample Site Map 11 40 Air Sample 5-mile Map 12 41 Air Sample 25-mile Map 13 42 Gross Beta Groundwater 1982-2001 14 45 Cs-I 37 in Soil 1972-2001 15 50 Terrestrial Site Map 16 52 Terrestrial 5-mile Map 17 53 Terrestrial 25-mile Map 18 54 Gross Beta in Treated Surface Water 1977-2001 19 56 Gross Beta Concentration in Untreated Surface Water 1972-2001 20 59 Gross Beta Fish 1972-2001 21 62 Aquatic Site Map 22 64 Aquatic 5-mile Map 23 65 Aquatic 25-mile Map 24 66 Gamma Dose for Environmental TLDs 1973 - 2001 25 68 TLD Site Map 26 75 TLD 5-mile Map 27 76 TLD 25-mile Map 28 77 Exposure Pathways 29 85 Vi

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Figure Page Description Number Number Land Use Census Map 31 111 Wind Rose Annual Average IOOM 32 123 Wind Rose Annual Average 75M 33 124 Wind Rose Annual Average 10M 34 125 Water Treatment Plant Schematic 35 133 vii

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Executive Summary The Annual Radiological Environmental Operating Report (AREOR) is a detailed report on the Environmental Monitoring Programs conducted at the Davis-Besse Nuclear Power Station from January 1 through December 31, 2001. This report meets all of the requirements in Regulatory Guide 4.8, Davis-Besse Technical Specifications 6.9.1.10, and Davis-Besse Offsite Dose Calcu lation Manual (ODCM) Section 7.1. Reports included are the Radiological Environmental Monitoring Program, Land Use Census, and the Non-Radiological Environmental Programs, which consist of Meteorological Monitoring, Land and Wetland Management, Water Treatment, Chemical Waste Management, and Waste Minimization and Recycling. This report also includes the Radiological Effluent Release Report for the reporting period of January 1 through December 31, 2001.

Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is established to monitor the ra diological condition of the environment around Davis-Besse. The REMP is conducted in accor dance with Regulatory Guide 4.8, Davis-Besse Technical Specification 6.8.4.d and the Davis Besse ODCM Section 6.0. This program includes the sampling and analysis of environmental samples and evaluating the effects of releases of radioactivity on the environment.

Radiation levels and radioactivity have been monitored within a 25-mile radius around Davis Besse since 1972. The REMP was established at Davis-Besse about five years before the Station became operational. This pre-operational sampling and analysis program provided data on ra diation and radioactivity normally present in the area as natural background. Davis-Besse has continued to monitor the environment by sampling air, groundwater, milk, edible meat, fruit and vegetables, animal feed, soil, drinking water, surface water, fish, shoreline sediment, and by di rect measurement of radiation.

Samples are collected from indicator and control locations. Indicator locations are within ap proximately 5 miles of the site and are expected to show naturally occurring radioactivity plus any increases of radioactivity that might occur due to the operation of Davis-Besse. Control lo cations are farther away from the Station and are expected to indicate the presence of only natu rally occurring radioactivity. The results obtained from the samples collected from indicator locations are compared with the results from those collected from control locations and with the concentrations present in the environment before Davis-Besse became operational. This allows for the assessment of any impact the operation of Davis-Besse might have had on the surround ing environment.

Over 2000 radiological environmental samples were collected and analyzed in 2001. An expla nation for the sample anomalies for this reporting period is provided on page 36.

The results of the REMP indicate that Davis-Besse continues to be operated safely in accordance with applicable federal regulations. No significant increase above background radiation or radio activity is attributed to the operation of Davis-Besse.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report The sampling results are divided into four sections: atmospheric monitoring, terrestrial monitor ing, aquatic monitoring and direct radiation monitoring:

" Air is continuously being filtered at 10 locations, onsite and up to 25 miles away, and the filters are collected to monitor the atmos phere. The 2001 results are similar to those observed in preopera tional and previous operational programs. Only background and fallout radioactivity normally present in the environment was de tected and only at concentrations normal to the area.

"Terrestrial monitoring includes analysis of milk, ground water, meat, fruits, vegetables, animal feed and soil samples. Samples are collected onsite and up to 25 miles away depending on the type of sample. Results of terrestrial sample analyses indicate concentra tions of radioactivity similar to previous years and indicate no build-up of radioactivity due to the operation of Davis-Besse.

"* Aquatic monitoring includes the collection and analysis of drinking water, untreated surface water, fish and shoreline sediments from onsite and the vicinity of Lake Erie. The 2001 results of analysis for fish, untreated surface water, drinking water and shoreline sediment indicate normal background concentration of radionu clides and show no increase or build-up of radioactivity due to the operation of Davis-Besse.

" Direct radiation averaged 14.4 mrem/91days at indicator locations and 14.8 mrem/91 days at control locations. This is similar to re sults of previous years.

The operation of Davis-Besse in 2001 caused no significant increase in the concentrations of ra dionuclides in the environment and no adverse effect on the quality of the environment. Radio activity released in the Station's effluents was well below the applicable federal regulatory limits.

The estimated radiation dose to the general public due to the operation of Davis-Besse in 2001 was well below all applicable regulatory limits.

In order to estimate radiation dose to the public, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is per formed as part of the REMP. During the census, Station personnel travel every public road within a radius of five miles of Davis-Besse to locate radiological exposure pathways (e.g., resi dences, vegetable gardens, milk cows/goats, etc.). The one pathway of particular interest is the pathway that, for a specific radionuclide, provides the greatest dose to a sector of the population.

This is called the critical pathway. The critical pathway for 2001 was a garden in the West sector 1610 meters from Davis-Besse.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Radiological Effluent Release Report The Radiological Effluent Release Report (RERR) is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period January 1, 2001 through Decem ber 31, 2001. The doses due to radioactivity released during this period were estimated to be:

Liquid Effluents:

Maximum Individual Whole Body Dose 7.75E-02 mrem (0.0775 mrem)

Maximum Individual Significant Organ Dose 8.03E-02 mrem (0.0803 torem)

Total Integrated Population Dose 7.31E-01 person-rem (0.731 person-rem)

Average Dose to the Individual 3.35E-04 mrem (0.000335 mrem)

Gaseous Effluents:

Maximum Individual Whole Body Dose due to 1.99E-03 mrem 1-13 1, H-3 and Particulates with half-lives (0.00199 mrem) greater than 8 days Maximum Significant Organ Dose due to 1-131, 2.54E-03 mrem H-3 and Particulates with half-lives greater than (0.00254 mrem) 8 days Total Integrated Population Dose due to 1-131, 7.02E-03 person-rem H-3 and Particulates with half-lives greater than (0.00702 person-rem) 8 days Average Dose to an individual in the population 3.21E-06 mrem due to 1-131, H-3 and Particulates with half-lives (0.00000321 torem) greater than 8 days Maximum Individual Skin Dose due to noble gases 9.27E-04 mrad (0.000927 nirad)

Maximum Individual Whole Body Dose due to 2.7 1E-04 mrad noble gases (0.000271 mrad)

Total Integrated Population Dose due to noble gases 5.03E-04 person-rem (0.000503 person-rem)

Average Dose to individual in population due to 2.30E-07 mrem noble gases (0.000000230 mrem) x

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating ra The Total Body doses to an individual and population in an unrestricted area due to direct an diation from Davis-Besse is not distinguishable from background. These doses represent extremely small fraction of the limits set by the NRC or the limits set in the ODCM.

The abnormal gaseous releases during this reporting period are listed on page 89.

There were no changes to the Process Control Program (PCP) and two alterations to the ODCM, Revision 14.0 and Revision 15.0, during this reporting period.

Non-Radiological Environmental Programs Meteorological Monitoring the The Meteorological Monitoring Program at Davis-Besse is part of a program for evaluating radiological effects of the routine operation of Davis-Besse on the surrounding environment.

Meteorological monitoring began in October, 1968.

theta Meteorological data recorded at Davis-Besse include wind speed, wind direction, sigma (standard deviation of wind direction), ambient temperature, differential temperature, dew point and precipitation. Two instrument-equipped meteorological towers are used to collect data. Data recovery for the five instruments that are operationally required by Davis-Besse Technical Re quirement Manual was 99.27 %.

Marsh Management The FirstEnergy Company owns the Navarre Marsh. It is leased to the U.S. Fish and Wildlife Service, who manage it as part of the Ottawa National Wildlife Refuge.

Special projects conducted in 2001 with the cooperation of Ohio Department of Natural Re sources included Canada goose banding and a Volunteer Eagle Watcher Workshop. Davis-Besse hosted the seventh annual Federal Junior Duck Stamp Art Contest for the State of Ohio in coop eration with the Ottawa National Wildlife Refuge.

Davis-Besse's resident pair of American Bald Eagles built a new nest and fledged three eaglets.

Water and Wastewater Treatment Davis-Besse withdraws water from Lake Erie and processes it through its Water Treatment Plant to produce high-purity water for use in the Station's cooling systems.

Since December 1, 1998, domestic water at the site has been provided by the Carroll Township Water Treatment Plant.

Sewage is treated at the Davis-Besse Wastewater Treatment Plant (WWTP) and pumped to a large basin where, following a holdup period, the water is discharged with other station waste water back to Lake Erie.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Chemical Waste Management The Chemical Waste Management Program at Davis-Besse was developed to ensure that the off site disposal of non-radioactive hazardous and nonhazardous chemical wastes is performed in accordance with all applicable state and federal regulations. Chemical waste disposal vendors contracted by Davis-Besse use advanced technology for offsite disposal, including recycling of chemical wastes, in order to protect human health and the environment.

In 2001, the Davis-Besse Nuclear Power Station qualified as a small quantity generator status, generating 5,770 pounds of hazardous waste. Other non-hazardous wastes generated include 2,250 gallons of used oil, 385 gallons of oil filters and solid oily debris, and 505 gal lons of microfilm process chemicals and water treatment resins.

As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse re ported hazardous products and chemicals to local fire departments and local and state plan ning commissions. As part of the program to remove PCB fluid from Davis-Besse, all electrical transformers have been retrofilled and reclassified as non-PCB transformers.

Waste Minimization and Recycling The Waste Minimization and Recycling Program at Davis-Besse began in 1991 with the collec tion and recycling of paper. This program was expanded and reinforced during 1993 to include the recycling of paper, aluminum cans, cardboard, and metal. Paper and cardboard recycling typically exceeds 50 tons annually. The scrap metal collected onsite is sold to scrap companies.

Appendices Appendix A contains results from the Interlaboratory Comparison Program required by Davis Besse Technical Specifications. Samples with known concentrations of radioisotopes are pre pared by the Environmental Protection Agency (EPA), and then sent (with information on sample type and date of collection only) to the laboratory contracted by the Davis-Besse Nuclear Power Station to analyze its REMP samples. Results are checked against known standards by the EPA.

The results from both the contracted laboratory and the EPA are provided in Appendix A.

Appendix B contains data reporting conversions used in the REMP at Davis-Besse. The appen dix provides an explanation of the format and computational methods used in reporting REMP data. Information on counting uncertainties and the calculations of averages and standard devia tions are also provided.

Appendix C lists the effluent concentration limits for alpha and beta-emitting radioisotopes and for certain other radioisotopes in air and water samples. These concentrations are taken directly from the Code of Federal Regulations, and provide comparison values for actual REMP sampling results for 2001.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Appendix D provides a REMP sampling summary from 2001. The appendix provides a listing of the following for each sample type:

• the number and types of analyses performed,

• the lower limit of detection for each analysis,

• the mean and range of results for control and indicator locations,

• the mean, range, and description of location with highest annual mean

• the number of non-routine results For detailed studies, Appendix D provides more specific information than that listed in Chapter 2 of this report. The information presented in Appendices A through D was provided by Environmental, Inc. Midwest Laboratory in their Final Progress Report to Toledo Edison (Febru ary, 2002).

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Introduction Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Introduction electric generating stations; Coal, oil, natural gas and hydropower are used to run this nation's affect the environment through however, each method has its drawbacks. Coal-fired power can supply and are, therefore, mining, acid rain and air pollution. Oil and natural gas are in limited our waterways and the costly. Hydropower is limited due to the environmental impact of damming scarcity of suitable sites.

operation of nuclear power Nuclear power provides a readily available source of energy. The Nuclear Power Station stations has a very small impact on the environment. In fact, the Davis-Besse the Ottawa National Wild is surrounded by hundreds of acres of marshland, which make up part of source of energy, background life Refuge. In order to provide better understanding of this unique and effluent control information on basic radiation characteristics, risk assessment, reactor operation is provided in this section.

Fundamentals The Atom All matter consists of atoms. Simply de scribed, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called 0 "Urn)"

"OnA protons, electrons, and neutrons, respec-tons and neutrons are packed tightly to gether in a cluster at the center of the atom

• called the nucleus. Orbiting around the nu cleus are one or more smaller electrons. In /

an electrically neutral atom the negative charges of the electrons are balanced by the positive charges of the protons. Due to their \

otEr dissimilar charges, the protons and electrons have a strong attraction for each other. This holds the atom together. Other attractive forces between the protons and neutrons Figure 1: An atom consists of two pars: a nucleus cor*tainig positively charged protons and electrically repel- orbitingamd theone or more negatively charged keep the densely packed ad lingeachothr, protons thfromnuceuselectrons peven netral neurons nucleus. Protons and neutrons ling each other, and prevent the nucleus ar nearly identical in size and weight, while each is about 2; times heavier than an elctronT from breaking apart.

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__________ll Davis-Besse Nuclear Power Station 2001 Annual Radiological Enviroranental Operating Report Radiation and Radioactivity Isotopes and Radionuclides A group of identical atoms containing the same number of protons make up an element In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms with one proton are hydrogen atoms, and all atoms with eight protons are oxygen atoms. How ever, the number of neutrons in the nucleus of an element may vary. Atoms with the same num ber of protons but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties, and many are stable or nonradioactive. An un stable or radioactive isotope of an element is called a radioisotope, a radioactive atom, or a radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess energy is usually due to a surplus or deficit in the number of neutrons in the nucleus. Ra dionuclides such as uranium-238, Berylium-7 and potassium-40 occur naturally. Others are man made, such as iodine-131, cesium-137, and cobalt-60.

Radiation Radiation is simply the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation is another type of radiation and has similar properties to those of the examples listed above.

Ionizing radiation consists of both electromagnetic radiation and particulate radiation. Elec tromagnetic radiation is energy with no measurable mass that travels with a wave-like motion through space. Included in this category are gamma rays and X-rays. Particulate radiation con sists of tiny, fast moving particles which, if unhindered, travel in a straight line through space.

The three types of particulate radiation of concern to us are alpha particles, which are made up of 2 protons and 2 neutrons; beta particles, which are essentially free electrons; and neutrons.

The properties of these types of radiation will be described more fully in the Range and Shielding section.

Radioactive Decay Radioactive atoms, over time, will reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of energy from an atom through the emis sion of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daugh ter products that eventually result in a stable atom. The loss of energy and/or matter through radioactive decay may transform the atom into a chemically different element. For example, when uranium-238 decays, it emits an alpha particle and, as a result, the atom loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom determines its chemical identity. Therefore, when the uranium-238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of thorium-234. Thorium-234 is one of the 14 successive daughter products of uranium-238. Radon is another daughter product, and the series ends with stable lead-206.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report This example is part of a known radioactive decay series, called the uranium series, which begins with uranium-238 and ends with lead-206 (Figure 2).

Beta Decay Alpha Decay 226 Ra P",

1600 wr L222Rn 3.82 d 1,

Figure 2: Principal Decay Scheme of the Uranium Series.

Half-life Most radionuclides vary greatly in the frequency with which their atoms release radiation. Some radioactive materials, in which there are only infrequent emissions, tend to have a very long half lives. Those radioactive materials that are very active, emitting radiation more frequently, tend to have comparably shorter half-lives. The length of time an atom remains radioactive is defined in terms of half-lives. Half-life is the amount of time required for a radioactive substance to lose half of its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years.

Interaction with Matter Ionization Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When these forms of radiation interact with any form of material, the energy they impart may cause 3

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report atoms in that material to become ions, or charged particles. Normally, an atom has the same number of protons as electrons. Thus, the number of positive and negative charges cancel, and the atom is electrically neutral. When one or more electrons are'removed an ion is formed. Ioni zation is one of the processes that may result in damage to biological systems.

Range and Shielding Particulate and electromagnetic radiation each travel through matter differently because of their different properties. Alpha particles contain 2 protons and 2 neutrons, are relatively large, and carry an electrical charge of +2. Alpha particles are ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its compara tively large size, an alpha particle usually does not travel very far before it loses most of its en ergy through collisions and interactions with other atoms. As a result, a sheet of paper or a few centimeters of air can easily stop alpha particles (Figure 3).

Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed of light (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1.

Because they are so small and have a low charge, they do not collide and interact as often as al pha particles, so they can travel farther. Beta particles can usually travel through several meters of air, but maybe stopped by a thin piece of metal or wood.

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PtD I CACTVK mA'ERIAL PAPER ALUMINUM1 LiAD CONCR.TES Figuxe 3: As radiation travels. it collides and interacts with odher atoms and loses energy. Alpha particles can be stopped by a sheet of paper, and beta particles by a thin sheet of aluminum. Gamma radiation is shielded by highly and dense materials such as lead. while bydrogenous materials (those containing hydrogen atoms), such as water concrete, are used to stop neutrons.

Gamma rays are pure energy and travel at the speed of light. They have no measurable charge or mass, and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray finally loses all of its energy and vanishes. The range of a gamma ray in air varies, depending on the rays energy and interactions. Very high energy gamma radiation can travel a considerable distance, whereas low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of lead or concrete may be needed to effectively shield gamma rays.

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Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating cosmic radiation with the Neutrons come from several sources, including the interactions of power reactors. However, earth's atmosphere and nuclear reactions within operating nuclear at nuclear power stations is neutrons are not of environmental concern since the neutron source sealed within the containment building.

to the nuclei of the material Because neutrons have no charge, they are able to pass very close by one of these nuclei or through which they are traveling. As a result, neutrons may be captured its energy. After a series of they may be deflected. When deflected, the neutron loses some of the neutron moves about these deflections, the neutron has lost most of its energy. At this point, is called a thermal neu as slowly as the atoms of the material through which it is traveling, and thermal neutrons and have tron. In comparison, fast neutrons are much more energetic than they travel. Fast neutrons can greater potential for causing damage to the material through which neutrons.

have from 200 thousand to 200 million times the energy of thermal neutrons. Neutron Neutron shielding is designed to slow fast neutrons and absorb thermal The shield shielding materials commonly used to slow neutrons down are water or polyethylene.

thermal neutrons. At is then completed with a material such as cadmium, to absorb the now it contains water mole Davis-Besse, concrete is used to form an effective neutron shield because cules and can be easily molded around odd shapes.

Quantities and Units of Measurement and its ef There are several quantities and units of measurement used to describe radioactivity dose equivalent.

fects. Three terms of particular usefulness are activity, absorbed dose, and Activity: Curie time. Each time Activity is the number of atoms in a sample that disintegrate (decay) per unit of to describe the activity an atom disintegrates, radiation is emitted. The curie (Ci) is the unit used are decaying.

of a material and indicates the rate at which the atoms of a radioactive substance One curie indicates the disintegration of 37 billion atoms per second.

required to A curie is a unit of activity, not a quantity of material. Thus, the amount of material is the produce one curie varies. For example, one gram (1/28th of an ounce) of radium-226 10 tons) of equivalent of one curie of activity, but it would take 9,170,000 grams (about thorium-232 to equal one curie.

concentrations of Smaller units of the curie are often used, especially when discussing the low (uCi) is equal to radioactivity detected in environmental samples. For instance, the microcurie curie.

one millionth of a curie, while the picocurie (pCi) represents one trillionth of a Absorbed Dose: Rad exposed Absorbed dose is a term used to describe the radiation energy absorbed by any material radiation. The to ionizing radiation, and can be used for both particulate and electromagnetic 5

I] _ il L Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material (1 Rad = 100 erg/gm).

The rate of absorbed dose is usually given in Rad/hr.

If the biological effect of radiation is directly proportional to the energy deposited by radiation in an organism, the Rad would be a suitable measurement of the biological effect. However, bio logical effects depend not only on the total energy deposited per gram of tissue, but on how this energy is distributed along its path. Experiments have shown that certain types of radiation are more damaging per unit path of travel than are others. Thus, another unit is needed to quantify the biological damage caused by ionizing radiation.

Dose Equivalent: Rem Biological damage due to alpha, beta, gamma and neutron radiation may result from the ioniza tion caused by this radiation. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or X-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to a particular type of ionizing radia tion. The dose equivalent is measured in rem (radiation equivalent man).

AnV t 'ilv9i ,A dq~valent uses the quality factor for alpha radiation, which is equal to 20. Thus, I Rad of alpha radiation is approximately equal to 20 rem. Beta and gamma radiation each have a quality factor of 1, therefore one Rad of either beta or gamma radiation is approximately equal to one rem. Neutrons have a quality factor ranging from 2 to 10. One rem produces the same amount of biological damage, regardless of the source. In terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit, the millirem, is often used. One millirem (mrem) is equal to 1/1000 of a rem.

Deep Dose Equivalent (DDE)

Deep dose equivalent is the measurement of dose within the body, from sources of radiation that are external to the body. It is what is measured and recorded on thermoluminescent dosimeters (TLDs), film badges or other dosimeters. For example, at Davis-Besse or at any hospital that has x-ray equipment, you will see people wearing these devices. These instruments are worn to measure DDE.

Committed Effective Dose Equivalent (CEDE)

Committed effective dose equivalent is a measure of the dose received from any radioactive ma terial taken into the body. It is calculated from the sum of the products of the committed dose equivalent to the organ or tissue multiplied by the organ or tissue-weighting factor. CEDE ac counts for all the dose delivered during the entire time the radioactive material is in the body.

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Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Total Effective Dose Equivalent (TEDE) dose from sources ex Total effective dose equivalent is the sum of the deep dose equivalent (for dose). Since they ternal to the body) and the committed effective dose equivalent (for internal occupational dose to are both doses to the body, they are not tracked separately. The NRC limits a radiation worker to five rem (5000 mrem) TEDE per year.

Sources of Radiation Background Radiation naturally on earth. It is Radiation did not begin with the nuclear power industry, and occurs radiation and proba probably the most "natural" thing in nature. Mankind has always lived with radioactive decay bly always will. In fact, during every second of life, over 7,000 atoms undergooccurs naturally in "naturally" in the body of the average adult. In addition, radioactive decay the natural back soil, water, air and space. All these common sources of radiation contribute to ground radiation to which we are all exposed.

and particulate radia The earth is being showered by a steady stream of high-energy gamma rays us from most of tion that come from space known as cosmic radiation. The atmosphere shields this source. The this radiation, but everyone still receives about 20 to 50 mrem each year from People living at thinner air at higher altitudes provides less protection against cosmic radiation.

radiation. Ra higher altitudes or flying in an airplane are exposed to even higher levels cosmic include be dionuclides commonly found in the atmosphere as a result of cosmic ray interactions ryllium-7, carbon-14, tritium (H-3), and sodium-22.

of the ex Another common naturally occurring radionuclide is potassium-40. About one-third to this radio ternal and internal dose from naturally occurring background radiation is attributed active isotope of potassium.

gas that re The major source of background radiation is radon, a colorless, odorless, radioactive uranium sults from the decay of radium-226, a member of the uranium-238 decay series. Since to radon and its daughter occurs naturally in all soils and rocks, everyone is continuously exposed confined products. Radon is not considered to pose a health hazard unless it is concentrated in a concerns stem area, such as buildings, basements or underground mines. Radon-related health it de from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when to the lungs cays, which can cause damage to internal tissues when inhaled. As a result, exposure in is a concern, since the only recognized health effect associated with exposure to radon is an in creased risk of lung cancer. This effect has been seen when radon is present at levels common uranium mines. According to the National Council on Radiation Protection and Measurement (NCRP), over half of the radiation dose the average American receives is attributed to radon.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Envirorunental Operating Report SOURCES OF EXPOSURE COSMIC 8%

TO THE PUBLIC rENRES'IAL INTERNAL 8% 11%

[

MAMADE 10%

alum RADON TOTAL MANMADE Figure 4: The most significant annual dose received by an individual of the public is that received from naturally occurring radon. A very small annual dose to the public results from producing electricity by nuclear power.

Further information on radon, its measurement, and actions to reduce the radon concentration in buildings can be obtained by contacting the state radon program office at the following address:

Ohio Department of Health, Bureau of Radiation Protection P.O. Box 118, 35 East Chestnut Building 7 th Floor Columbus, Ohio 43216-0118 614) 481-5800 (800) 523-4439 (in Ohio Only)

The approximate average background radiation in this area (see Figure 4) is 300 mrem/year.

Man-Made Radiation In addition to naturally occurring cosmic radiation and radiation from naturally occurring radio activity, people are also exposed to man-made radiation. The largest sources of exposure include medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium-90, cesium-137, and tritium. Less than one percent of the annual dose a member of the public re ceives is a result of having electricity generated by nuclear power.

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Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Health Effects of Radiation than 80 years.

The effects of ionizing radiation on human health have been under study for more animals that were Scientists have obtained valuable knowledge through the study of laboratory difficult to re exposed to radiation under extremely controlled conditions. However, it has been health effects on hu late the biological effects of irradiated laboratory animals to the potential mans.

genetic. So The effects of radiation on humans can be divided into two categories, somatic and unborn matic effects are those which develop in the directly exposed individual, including an individual.

child. Genetic effects are those which are observed in the offspring of the exposed develop Somatic effects can be divided further into acute and chronic effects. Acute effects human shortly after exposure to large amount of radiation. Much study has been done with These groups populations that were exposed to ionizing radiation under various circumstances.

and include the survivors of the atomic bomb, persons undergoing medical radiation treatment, early radiologists, who accumulated large doses of radiation, unaware of the potential hazards.

Examples Chronic effects are a result of exposure to radiation over an extended period of time.

the of such groups are clock dial painters, who ingested large amounts of radium by "tipping" dust paint brushes with their lips, and uranium miners, who inhaled large amounts of radioactive while mining pitchblende (uranium ore). The studies performed on these groups have increased our knowledge of the health effects from comparatively very large doses of radiation received over long periods of time.

Continuous exposure to low levels of radiation may produce somatic changes over an extended period of time. For example, someone may develop cancer from man-made radiation, back ground radiation, or some other source not related to radiation. Because all illnesses caused by low level radiation can also be caused by other factors, it is virtually impossible to determine in dividual health effects of low level radiation. Even though no effects have been observed at doses less than 50 rem, to be conservative, we assume the health effects resulting from low doses of radiation occur proportionally to those observed following large doses of radiation. Most ra diation scientists agree that this assumption over-estimates the risks associated with a low-level radiation exposure. The effects predicted in this manner have never been actually observed in any individuals exposed to low level radiation. Therefore, the most likely somatic effect of low level radiation is believed to be a small increased risk of cancer.

Genetic effects could occur as a result of ionizing radiation interacting with the genes in the hu man cells. Radiation (as well as common chemicals) can cause physical changes or mutations in the genes. Chromosome fibers can break and rearrange, causing interference with the normal cell division of the chromosome by affecting their number and structure. A cell is able to rejoin the ends of a broken chromosome, but if there are two breaks close enough together in space and time, the broken ends from one break could join incorrectly with those from another. This could cause translocations, inversions, rings, and other types of structural rearrangements. When this 9

.1 ilAL Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report happens, new mutated genes are created. Radiation is not the only mechanism by which such changes can occur. Spontaneous mutations and chemically induced mutations also have been observed. These mutated genes may be passed from parent to offspring. Viable mutations due to low level, low dose radiation have not been observed in humans.

Health Risks While people may accept the risks inherent in their personal activities, such as smoking and driving to work each day, they are less inclined to accept the risk inherent in producing electric ity. As with any industrial environment, it is not possible to guarantee a risk free environment.

Thus, attention should be focused on taking steps to safeguard the public, on developing a realis tic assessment of the risks, and on placing these risks in perspective. The perceptions of risk as sociated with exposure to radiation may have the greatest misunderstanding. Because people may not understand ionizing radiation and its associated risks, they may fear it. This fear is com pounded by the fact that we cannot hear, smell, taste or feel ionizing radiation.

We do not fear other potentially hazardous things for which we have the same lack of sensory perception, such as radio waves, carbon monoxide, and small concentrations of numerous cancer causing substances. These risks are larger and measurable compared to those presumed to be as sociated with exposure to low level, low dose radiation. Most of these risks are with us through out our lives, and can be added up over a lifetime to obtain a total effect. Table I shows a number of different factors that decrease the average life expectancy of individuals in the United States.

Table 1: Risk Factors: Estimated Decrease in Average Life Expectancy Overweight by 30%: 3.6 years Cigarette smoking: 1 pack/day 7.0 years 2 packs/day 10.0 years Heart Disease: 5.8 years Cancer: 2.7 years City Living (not rural): 5.0 years All operating commercial nuclear power plants totaled: less than 12 minutes 10

Davis-Besse Nuclear Power Station 2001 Aninal Radiological Environmental Operating Report Benefits of Nuclear Power Nuclear power plays an important part in meeting today's electricity needs, and will continue to serve as an important source of electric energy well into the future. Today more than twenty per cent of the electricity produced in the United States is from nuclear powered electrical generating stations.

Nuclear power offers several advantages over alternative sources of electric energy:

"* nuclear power has an excellent safety record dating back to 1957, when the first commercial nuclear power station began operating,

"* uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States,

"* Nuclear power is the cleanest energy source for power stations that use steam to produce electricity. There are no greenhouse gases or acid gases produced when using nuclear fuel.

The following sections provide information on the fundamentals of how Davis-Besse uses nu clear fuel and the fission process to produce electricity.

Nuclear Power Production Electricity is produced in a nuclear power station in the same way as in a fossil-fueled station with the exception of the source of heat. Heat changes water to steam that turns a turbine. In a fossil-fueled station, the fuel is burned in a furnace, which is also a boiler. Inside the boiler, wa ter is turned into steam. In a nuclear station, a reactor that contains a core of nuclear fuel, pri marily uranium, replaces the furnace. Heat is produced when the atoms of uranium are split, or fissioned, inside the reactor.

What is Fission?

A special force called the binding force holds the protons and neutrons together in the nucleus of the atom. The strength of this binding force varies from atom to atom. If the bond is weak enough, the nucleus can be split when bombarded by a free neutron (Figure 5). This causes the entire atom to split, producing smaller atoms, more free neutrons, and heat. In a nuclear reactor, a chain reaction of fission events provides the heat necessary to boil the water to produce steam.

it

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Sambard* g I

• k~tom Fragment Figure 5: When a heavy atom, such as uranium-235 is split or fissioned, heat, free neutrons, and fussion fragments result. The hfe neutrons can then strike neighboring atoms causing them to fission also. In the proper environment.

this process can continue indefinitely in a chain reaction.

Nuclear Fuel The fissioning of one uranium atom releases approximately-50 million times more energy than the combustion of a single carbon atom common to all fossil fuels. Since a single small reactor fuel pellet contains trillions of atoms, each pellet can release an extremely large amount of en ergy. The amount of electricity that can be generated from three small fuel pellets would require about 3.5 tons of coal or 12 barrels of oil to generate.

Nuclear fission occurs spontaneously in nature, but these natural occurrences cannot sustain themselves because the freed neutrons either are absorbed by non-fissionable atoms or quickly decay. In contrast, a nuclear reactor minimizes neutron losses, thus sustaining the fission proc ess by several means:

"* using fuel that is free of impurities that might absorb the free neutrons,

"* enriching the concentration of the rarer fissionable isotope of uranium (U-235) relative to the concentration of U-238, a more common isotope that does not fis sion easily,

"* slowing down neutron by providing a "moderator" such as water to increase the probability of fission.

Natural uranium contains less than one percent U-235 compared to the more abundant U-238 when it's mined. Before it can be economically used in a reactor, it is enriched to three to five percent U-235, in contrast to nuclear material used in nuclear weapons which is enriched to over 97 percent. Because of the low levels of U-235 in nuclear fuel, a nuclear power station cannot explode like a bomb.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report After the uranium ore is separated from the earth and rock, it is concentrated in a milling process.

After milling the ore to a granular form and dissolving out the uranium with acid, the uranium is converted to uranium hexafluoride (UF 6 ). UF 6 is a chemical form of uranium that exists as a gas at temperatures slightly above room temperature. The UF 6 is then highly purified and shipped to an enrichment facility where gaseous diffusion converters increase the concentration of U-235. The enriched gaseous UF 6 is then converted into powdered uranium dioxide (UO2 ), a highly stable ceramic material. The U0 2 powder is put under high pressure to form fuel pellets, each about 5/8 inch long and 3/8 inch in diameter. Approximately five pounds of these pellets are placed into a 12-foot long metal tube made of zirconium alloy. The tubes constitute the fuel cladding. The fuel cladding is highly resistant to heat, radiation, and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods.

The Reactor Core Two hundred eight fuel rods comprise a single fuel assembly. The reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fuel rods, the fuel assembly also contains 16 vacant holes for the in sertion of control rods, and one vacant hole for an incore-monitoring probe. This probe monitors temperature and neutron levels in the fuel assembly. The Davis-Besse reactor vessel, which contains all the fuel assemblies, weighs 838,000 pounds, has a diameter of 14 feet, is 39 feet high, and has steel walls that are 8 1/2/2 inches thick.

P.m r.0 11-A~W REACIOB VESEL Figure 6: The reactor core at Davis-Besse contains 177 fuel assemblies. Each assembly contains 208 fuel rods.

Each fuel rod is filled with approximately five pounds of fuel pellets, each pellet is approximately 3/8 inch in diameter and 5/8 inch long.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Fission Control Raising or lowering control rod assemblies into the reactor core controls the fission rate. Each assembly consist of "fingers" containing silver, indium, and cadmium metals that absorb free neutrons, thus disrupting the fission chain reaction. When control rod assemblies are slowly withdrawn from the core, fissioning begins and heat is produced. If the control rod assemblies are inserted rapidly into the reactor core, as during a plant "trip", the chain reaction ceases. A slower acting (but more evenly distributed) method of fission control is achieved by the addition of a neutron poison to the reactor coolant water. At Davis-Besse, high-purity boric acid is con centrated or diluted in the coolant to achieve the desired level of fission. Boron-10 readily ab sorbs free neutrons, forming boron- 11, removing the absorbed neutrons from the chain reaction.

Reactor Types Virtually all of the commercial reactors in this country are either boiling water reactors (BWRs) or pressurized water reactors (PWRs). Both types are also called light water reac tors (LWRs) because their coolant, or medium to transfer heat, is ordinary water, which contains the light isotope of hydrogen. Some reactors use the heavy isotope of hydrogen (deuterium) in the reactor coolant. Such reactors are called heavy water reactors (HWRs).

In BW-Rs, water passes through the core and boils into steam. The steam passes through separa tors which remove water droplets. The steam then travels to dryers before entering the turbine.

After passing though the turbine the steam is condensed back into water and returns to the core to repeat the cycle.

In PWRs, the reactor water or coolant is pressurized to prevent it from boiling. The reactor water is then pumped to a steam generator (heat exchanger) where its heat is transferred to a secon dary water supply. The secondary water inside the generator boils into steam, which is then used to turn the turbine. This steam is then condensed back into water and returned to the steam gen erator. Davis-Besse uses a PWR design.

The following paragraphs describe the various systems illustrated in Figure 7. Major systems in the Davis-Besse Station are assigned a different color in the figure.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Davis-Besse Nuclear Power Station Unit No. 1 COOLING TOWER CONTAINMENT AUXILIARY BUILDING Figure 7: Station Systems 15 C-Oz-

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environtmental Operating Report Station Systems Containment Building and Fission Product Release Barriers The containment building houses the reactor vessel, the pressurizer, two steam generators, the reactor coolant pumps and reactor coolant system piping. The building is constructed of an inner 1 -1/2 inch thick steel liner or containment vessel, and the shield building with steel reinforced of concrete walls 2 feet thick. The shield building protects the containment vessel from a variety environmental factors and provides an area for a negative pressure boundary around the steel containment vessel. In the event that the integrity of the containment vessel is compromised (e.g., a crack develops), this negative pressure boundary ensures that any airborne radioactive contamination present in the containment vessel is prevented from leaking out into the environ ment. This is accomplished by maintaining the pressure inside the shield building lower than that outdoors, thus forcing clean outside air to leak in, while making it impossible for the con taminated air between the containment vessel and the shield building to leak out. The contain ment vessel is the third in a series of barriers that prevent the release of fission products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel clad ding itself. The second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and associated piping.

The Steam Generators The steam generators perform the same function as a boiler at a fossil-fueled power station.

The steam generator uses the heat of the primary coolant inside the steam generator tubes to boil the secondary side feedwater (secondary coolant). Fission heat from the reactor core is trans ferred to the steam generator in order to provide the steam necessary to drive the turbine. How ever, heat must also be removed from the core even after reactor shutdown in order to prevent damage to the fuel cladding. Therefore, pumps maintain a continuous flow of coolant through the reactor and steam generator. Primary loop water (green in Figure 7) exits the reactor at ap proximately 606*F, passes through the steam generator, transferring some of its heat energy to the secondary loop water (blue in Figure 7) without actually coming in contact with it. Primary coolant water exits the steam generator at approximately 558IF to be circulated back into the re actor where it is again heated to 606°F as it passes up through the fuel assemblies. Under ordi nary conditions, water inside the primary system would boil long before it reached such temperatures. However, it is kept under a pressure of approximately 2,200 pounds-per-square inch (psi) at all times. This prevents the water from boiling and is the reason the reactor at Davis-Besse is called a Pressurized Water Reactor. Secondary loop water enters the base of the steam generator at approximately 450°F and under 1,100 psi pressure. At this pressure, the water can easily boil into steam as it passes over the tubes containing the primary coolant water.

Both the primary and the secondary coolant water are considered closed loop systems. This means that they are designed not to come in physical contact with one another. Rather, the cooling water in each loop transfers heat energy by convection. Convection is a method of heat transfer that can occur between two fluid media. It is the same process by which radiators are used to heat homes. The water circulating inside the radiator is separated from the air (a "fluid" medium) by the metal piping.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report The Turbine - Generator The turbine, main generator, and the condenser are all housed in what is commonly referred to as the Turbine Building. The purpose of the turbine is to convert the thermal energy of the steam produced in the steam generator (referred to as main steam, red in Figure 7) to rotational energy of the turbine generator shaft. The turbine at Davis-Besse is actually composed of one six-stage high-pressure turbine and two seven-stage low-pressure turbines aligned on a common shaft. A turbine stage refers to a set of blades. Steam enters at the center of each turbine and moves outward along the shaft in opposite directions through each successive stage of blading.

As the steam passes over the turbine blades, it loses pressure. Thus, the blades must be propor tionally larger in successive stages to extract enough energy from the steam to rotate the shaft at the correct speed.

The purpose of the main generator is to convert the rotational energy of the shaft to electrical energy for commercial usage and support of station systems. The main generator is composed of two parts, a stationary stator that contains coils of copper conductors, and a rotor that supplies a rotating magnetic field within the coils of the stator. Electrical current is generated in the stator portion of the main generator. From this point, the electric current passes through a series of transformers for transmission and use throughout northern Ohio.

The Condenser After the spent steam in the secondary loop (blue in Figure 7) passes through the high and low pressure turbines, it is collected in a cavernous condenser several stories tall and containing more than 70,000 small tubes. Circulating water (yellow in Figure 7) goes to the cooling tower after passing through the tubes inside the condenser. As the steam from the low-pressure tur bines passes over these tubes, it is cooled and condensed. The condensed water is then purified and reheated before being circulated back into the steam generator again in a closed loop system.

Circulating water forms the third (or tertiary) and final loop of cooling water used at the Davis Besse Station.

Similar to the primary to secondary interface, the secondary to tertiary interface is based on a closed loop design. The circulating water is able to cool the steam in the condenser, without ever actually coming in contact with it, by the process of convection. Even in the event of a primary to secondary leak, the water vapor exiting the Davis-Besse cooling tower would remain non radioactive. Closed loops are an integral part of the design of any nuclear facility. This design feature greatly reduces the chance of environmental impact from station operation.

The Cooling Tower The Cooling Tower at Davis-Besse is easily the most noticeable feature of the plant. The tower stands 493 feet high and the diameter of the base is 411 feet. Two nine-foot diameter pipes cir culate 480,000 gallons of water per minute to the tower. Its purpose is to recycle water from the condenser by cooling and returning it.

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Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental After passing through the condenser, the Circulating Water has warmed to approximately 100°F.

the Cooling In order to cool the water back down to around 70'F, the Circulating Water enters over a series of baffles Tower about 40 feet above the ground. The water is sprayed evenly A natural draft of air called fillsheets, which are suspended vertically in the base of the tower.

of evaporation. The blowing upward through these baffles cools the water by the process evaporated water exits the top of the Cooling Tower as water vapor.

Cooling Tower.

As much as 10,000 gallons of water per minute are lost to the atmosphere via the operation can Even so, approximately 98 percent of the water drawn from Lake Erie for station Water is be recycled through the Cooling Tower for reuse. A small portion of the Circulating earlier. The discharged back to Lake Erie at essentially the same temperature it was withdrawn surrounding the slightly warmer water has no adverse environmental impact on the area of lake discharge point.

Miscellaneous Station Safety Systems housed The orange system in Figure 7 is part of the Emergency Core Cooling System (ECCS) means of in the Auxiliary Building of the station. The ECCS consists of three overlapping keeping the reactor core covered with water, in the unlikely event of a Loss of Coolant Accident Depend (LOCA), thereby protecting the fuel cladding barrier against high temperature failure.

automati ing upon the severity of the loss of pressure inside the primary system, the ECCS will pumps, a core cally channel borated water into the reactor by using high-pressure injection from the flood tank, or low-pressure injection pumps. Borated water can also be sprayed sys ceiling of the containment vessel to cool and condense any steam that escapes the primary tem.

The violet system illustrated in Figure 7 is responsible for maintaining the primary coolant water in a liquid state. It accomplishes this by adjusting the pressure inside the primary system. Heat ers inside the Pressurizer turn water into steam. This steam takes up more space inside the Pres surizer, thereby increasing the overall pressure inside the primary system. The Pressurizer is equipped with spray heads that shower cool water over the steam in the unit. In this case, the steam condenses and the overall pressure inside the primary system drops. The Quench Tank pictured in Figure 8 is simply where excess steam is directed and condensed for storage.

The scarlet system in Figure 7 is part of the Auxiliary Feedwater System, a key safety system in event the main feedwater supply (blue in Figure 7) to the Steam Generator is lost. Following a reactor shutdown, the Auxiliary Feedwater System can supply water to the Steam Generators from the Condensate Storage Tanks. The Auxiliary Feedwater System is housed in the Turbine Building along with the Turbine, Main Generator, and the Condenser.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Reactor Safety and Summary Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. Also, many safety features are equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the local environment. Davis Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features. If one system should fail, there are still back-up systems to assure the safe operation of the Station.

During normal operation, the Reactor Control System regulates the power output by adjusting the position of the control rods. The reactor can be automatically shut down by a separate Reac tor Protection System that causes all the control rod assemblies to be quickly and completely inserted into the reactor core, stopping the chain reaction. To guard against the possibility of a Loss of Coolant Accident, the Emergency Core Cooling System is designed to pump reserve water into the reactor automatically if the reactor coolant pressure drops below a predetermined level.

The Davis-Besse Nuclear Power Station was designed, constructed, and operates to produce a reliable, safe, and environmentally sound source of electricity.

Radioactive Waste Many of the activities we depend on in our everyday lives produce radioactive waste by-products.

Nuclear energy, industrial processes, and medical treatments are some of these activities. These by-products are managed and disposed of under strict requirements set by the federal govern ment. With the exception of used nuclear fuel assemblies, these by-products produced at com mercial power plants are referred to as low level radioactive waste.

Low Level Radioactive Waste Low level radioactive waste consists mainly of ordinary trash and other items that have become contaminated with radioactive materials. It includes plastic gloves and other protective clothing, machine parts and tools, medical and laboratory equipment, filters, resins, and general scrap.

The radioactive material in low level radioactive waste emits the same types of radiation that naturally occurring radioactive materials tend to emit. Most low level radioactive waste "decays" to background levels of radioactivity in months or years. Nearly all of it diminishes to stable materials in less than 300 years.

Davis-Besse presently ships low level radioactive waste to a South Carolina disposal facility lo cated at Bamwell, South Carolina. This facility was closed to out-of-compact generators from July 1, 1994 to July 1, 1996. It was reopened to all generators on July 1, 1996. At this time, Davis-Besse resumed shipping of low-level radioactive waste to the facility. Davis-Besse has the capacity to store low-level waste produced on site in the Low Level Radioactive Waste Storage Facility (LLRWSF) for several years, should the Bamwell facility close again.

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Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental High Level Nuclear Waste The most radioac Like any industrial or scientific process, nuclear energy does produce waste. Ninety-nine five is defined as "high-level" waste (because it has high levels of radioactivity).

fuel undergoes certain percent of high-level waste from nuclear plants is used nuclear fuel. The left over after the atom changes during fission. Most of the fragments of fission, pieces that are trapped in the fuel assem is split, are radioactive. After a period of time, the fission fragments the oldest fuel assem blies reduce the efficiency of the chain reaction. Every 18 to 24 months, blies are removed from the reactor and replaced with fresh fuel.

30 tons of used fuel High-level nuclear waste volumes are small. Davis-Besse produces about energy plants since the every 24 months. All the used fuel produced by all America's nuclear size of a football field first plant started operating over 30 years ago would cover an area the 3,000 tons of used about five yards deep. All of America's nuclear plants combined produce only waste annu fuel each year. By contrast, the U.S. produces about 300,000,000 tons of chemical remains hazard ally. Also, nuclear waste slowly loses its radioactivity, but some chemical waste ous indefinitely.

concrete vault in Davis-Besse presently stores most of its used fuel in a steel-lined water-filled high-level side the plant. The Department of Energy is charged with constructing a permanent Energy was waste repository for all of the nation's nuclear plants. By law, the Department of Nevada, is supposed to accept fuel from utilities by the end of 1998. Currently, Yucca Mountain, nuclear plants being considered as a possible site. Until the permanent DOE site is developed, the fuel will be responsible for the continued safe storage of high-level waste. At Davis-Besse, of moving pool reached its capacity in 1996. At the end of 1996, Davis-Besse began the process shielded the older fuel assemblies that no longer require water cooling to air-cooled concrete ready to receive canisters. These will remain onsite until the Department of Energy facilities are and in the U.S. at them. Dry fuel storage is already used in many countries, including Canada, Wisconsin and nuclear plants in Arkansas, Colorado, Maryland, Michigan, Minnesota, Virginia, South Carolina. Figure 8 illustrates the Dry Fuel Storage module arrangement at Davis-Besse.

In 2001, work began to increase the storage capacity of the Spent Fuel Pool. The pool remains the same size, however, removing old storage racks and replacing them with new ones changed its 40 year the configuration of storage, and allows the site to safely hold all the fuel used during expected life. This modification was completed in April of 2002.

20

I ---- tiLIL.

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report x

LU S

at 3ff Figure 8: Dry Fuel Storage Module Arrangement 21

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Description of the Davis-Besse Site It is on the south The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio.

north and east of Ohio western shore of Lake Erie, just north of the Toussaint River. The site lies State Route 2, approximately 10 miles northwest of Port Clinton, 7 miles north of Oak Harbor, and 25 miles east of Toledo, Ohio (Figure 9).

only a few feet above the This section of Ohio is flat and marshy, with maximum elevations of marshland, rich in wildlife level of Lake Erie. The area originally consisted of swamp forest and the land was cleared but unsuitable for settlement and farming. During the nineteenth century, consists of farmland and drained, and has been farmed successfully since. Today, the terrain Sandusky Lake Shore with marshes extending in some places for up to two miles inland from the Ridge.

LakA Fri'Ze 40 Figure 9: Davis-Besse is near Oak Harbor, Port Clinton, and the Ottawa National Wildlife Refuge.

farm The Davis-Besse site is mainly comprised of marshland, with a small portion consisting of for a land. The marshes are part of a valuable ecological resource, providing a breeding ground variety of wildlife, and a refuge for migratory birds. The site includes a tract known as Navarre of Marsh, which was acquired from the U.S. Bureau of Sport Fisheries and Wildlife, Department The Tous the Interior. In 1971, Toledo Edison purchased the 188-acre Toussaint River Marsh.

section of the Ottawa National saint River Marsh is contiguous with the 610-acre Navarre Marsh Wildlife Refuge.

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JL___ - WALL-Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report The immediate area near Davis-Besse is sparsely populated. Ottawa County had a population of 40,985 according to the 2000 Census. The incorporated communities nearest to Davis-Besse are:

• Port Clinton - 10 miles southeast, population 6,391

"* Oak Harbor - 7 miles south, population 2,841

"* Rocky Ridge - 7 miles west southwest, population 389

"* Toledo (nearest major city) - 25 miles west, population 313,619 There are some residences along the lakeshore used mainly as summer homes. However, the major resort area of the county is farther east, around Port Clinton, Lakeside, and the Bass Is lands.

The majority of non-marsh areas around the Davis-Besse site are used for farming. The major crops include soybeans, corn, wheat, oats, hay, fruits and vegetables. Meat and dairy animals are not major sources of income in the area. The main industries within five miles of the site are lo cated in Erie Industrial Park, about four miles southeast of the station.

Most of the remaining marshes in the area have been maintained by private hunting clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife. The State of Ohio Department of Natural Resources operates many wildlife and recrea tional areas within 10 miles of the Station. These include Magee Marsh, Turtle Creek, Crane Creek State Park, and the Ottawa National Wildlife Refuge. Magee Marsh and Turtle Creek lie between three and six miles WNW of the Station. Magee Marsh is a wildlife preserve that al lows public fishing, nature study, and a controlled hunting season. Turtle Creek, a wooded area at the southern end of Magee Marsh, offers boating and fishing. Crane Creek State Park is adja cent to Magee Marsh and is a popular picnicking, swimming, and fishing area. The Ottawa Na tional Wildlife Refuge lies four to nine miles WNW of the Site, immediately west of Magee Marsh.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report References

1. "Basic Radiation Protection Criteria,'"Report No. 39, National Council on Radiation Protec tion and Measurement, Washington, D.C. (January 1971).

2. "Cesium-137 from the Environment to Man: Metabolism and Dose," Report No. 52, National Council on Radiation Protection and Measurements, Washington, D.C. (January 1977).

3. Deutch, R., "Nuclear Power, A Rational Approach," Fourth edition, GP Courseware, Inc.,

Columbia, MD. (1987).

4. Eisenbud, M., "Environmental Radioactivity," Academic Press, Inc., Orlando, FL. (1987).

5. "Environmental Radiation Measurements," Report No. 50, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1976).

6. "Exposure of the Population in the United States and Canada from Natural Background Ra diation," Report No. 94, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1987).

7. "Health Effects of Exposure to Low Levels of Ionizing Radiation: BEIR V," Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects Research Commis sion on Life Sciences, National Research Council, National Academy Press, Washington, D.C. (1990).

8. Hendee, William R., and Doege, Theodore C., "Origin and Health Risks of Indoor Radon,"

Seminars in Nuclear Medicine, Vol. XVIII, No. 1, American Medical Association, Chicago, IL. (January 1987).

9. Hurley, P., "Living with Nuclear Radiation," University of Michigan Press, Ann Arbor, MI.

(1982).

10. "Indoor Air Quality Environmental Information Handbook: Radon," prepared for the United States Department of Energy, Assistant Secretary for Environment, Safety and Health, by Mueller Associated, Inc., Baltimore, MD. (January 1986).

11. Introduction to Davis-Besse Nuclear Power Station Plant Technology, July 1992, Rev. 4, Pg.2-9.

12. "Ionizing Radiation Exposure of the Population of the United States," Report No. 93, Na tional Council on Radiation Protection and Measurements, Washington, D.C. (September 1987).

13. "Natural Background Radiation in the United States," Report No. 45, National Council on Radiation Protection and Measurements, Washington, D.C. (November 1975).

24

IL ILL.

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environrmental Operating Report

14. "Nuclear Energy Emerges from 1980's Poised for New Growth," U.S. Council for Energy Awareness, Washington, D.C. (1989).

15. "Nuclear Power: Answers to Your Questions," Edison Electric Institute, Washington, D.C.

(1987).

16. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurement, Washington, D.C. (De cember 1987).

17. "Radiation Protection Standards," Department of Environmental Sciences and Physiology and the Office of Continuing Education, Harvard School Of Public Health, Boston, MA.

(July 1989).

18. Radiological Environmental Monitoring Report for Three Mile Island Station," GPU Nuclear Corporation, Middletown, PA. (1985).

19. "Sources, Effects and Risk of Ionizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation, 1988 Report to the General Assembly, United Nations, New York (1988).

20. "Standards for Protection Against Radiation," Title 10, Part 20, Code of Federal Regulation, Washington, D.C. (1988).

21. "Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50, Code of Federal Regulations, Washington, D.C. (1988).

22. "Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40, Part 190, Code of Federal Regulations, Washington, D.C. (1988).

23. "Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1979).

24. Site Environmental Report, Fernald Environmental Management Project, United States De partment of Energy (June 1993).

25. "1Exposure from the Uranium Series with Emphasis on Radon and it's daughters" Report No. 77, National Council on Radiation Protection and Measurements, Washington, D.C.

(1984).

26. "Evaluation of Occupational and Environmental Exposures to Radon and Radon daughter in the United States, "Report No. 78, National Council on Radiation Protection and Measure ments, Washington, D.C. (1984).

25

Radiological Envirorunental Monitoring Program Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at Davis Besse for several reasons: to provide a supplementary check on the adequacy of containment and effluent controls, to assess the radiological impact of the Station's operation on the surrounding area, and to determine compliance with applicable radiation protection guides and standards. The REMP was established in 1972, five years before the Station became operational. This preop erational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of Davis-Besse. After Davis-Besse became op erational in 1977, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas.

A variety of environmental samples are collected as part of the REMP at Davis-Besse. The se lection of sample types is based on the established critical pathways for the transfer of radionu clides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population char acteristics, and land usage in the area of interest. The selection of sampling frequencies for the various environmental media is based on the radionuclides of interest, their respective half-lives, and their effect in both biological and physical environments.

A description of the REM? at Davis-Besse is provided in the following section. In addition, a brief history of analytical results for each sample type collected since 1972, and a more detailed summary of the analyses performed during this reporting period, is also provided.

Preoperational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental moni toring prior to constructing the facility. This preoperational surveillance program is for the col lection of data needed to identify critical pathways, including selection of radioisotope and sample media combinations for the surveillance conducted after facility operation begins. Ra diochemical analyses performed on the samples should include both nuclides expected to be re leased during facility operation, and typical fallout radionuclides and natural background radioactivity. All environmental media with a potential to be affected by facility operation, as well as those media directly in the critical pathways, should be sampled during the preoperational phase of the environmental surveillance program.

The preoperational surveillance design, including nuclide/media combinations, sampling fre quencies and locations, collection techniques, and radioanalyses performed, should be carefully considered and incorporated in the design of the operational surveillance program. In this man ner, data can be compared in a variety of ways (for example: from year to year, location to loca-26

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environnental Operating Report tion, etc.) in order to detect any radiological impact the facility has on the surrounding environ ment. Data collection during the preoperational phase should be planned to provide a compre hensive database for evaluating any future changes in the environment surrounding the nuclear facility.

Davis-Besse began its preoperational environmental surveillance program five years before the Station began producing power for commercial use in 1977. Data accumulated during those early years provide an extensive database from which Station personnel are able to identify trends in the radiological characteristics of the local environment. The environmental surveillance pro gram at Davis-Besse will continue after the Station has reached the end of its economically use ful life and decommissioning has begun.

Operational Surveillance Program Objectives The operational phase of the environmental surveillance program at Davis-Besse was designed with the following objectives in mind:

"* to fulfill the obligations of the radiological surveillance sections of the Sta tion's Technical Specifications and Offsite Dose Calculation Manual

"* to determine whether any significant increase in the concentration of radionu clides in critical pathways occurs

"* to identify and evaluate the buildup, if any, of radionuclides in the local envi ronment, or any changes in normal background radiation levels

"* to verify the adequacy of Station controls for the release of radioactive mate rials Quality Assurance An important part of the environmental monitoring program at Davis-Besse is the Quality Assurance (QA) Program, which is conducted in accordance with the guidelines specified in NRC Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs." The QA Program is designed to identify possible deficiencies in the REMP so that corrective actions can be initiated promptly. Davis-Besse's Quality Assurance program also provides confidence in the results of the REMP through:

"* performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keeping;

• performing audits of contractor laboratories which analyze the environmental samples,

"* requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross-Check Program,

"* requiring analytical contractor laboratories to split samples for separate analy sis followed by a comparison of results,

"* splitting samples prior to analysis by independent laboratories, and then com paring the results for agreement, and, finally, 27

Davis-Besse Nuclear Power Station 2001 Annual Radiological Enviromnental Operating Report requiring analytical contractor laboratories to perform in-house spiked sample analyses.

by the Quality Assessment audits and inspections of the Davis-Besse REMP are performed In addition, the NRC FirstEnergy Nuclear Operating Company QA Department and the NRC.

and the Ohio Department of Health (ODH) also perform independent environmental monitoring locations used in the vicinity of Davis-Besse. The types of samples collected and the sampling results by the NRC and ODH were incorporated in Davis-Besse's REMP. Hence, the analytical from identical from the different programs can be compared. This practice of comparing results the quality samples, collected and analyzed by different parties, provides a valuable tool to verify of the laboratories analytical procedures and the data generated.

program In 1987, environmental sampling personnel at Davis-Besse incorporated their own QA were collected at several lo into the REMP. Duplicate samples, called quality control samples, num cations. These duplicate samples were assigned different identification numbers than the laboratory would not know bers assigned to the routine samples. This ensured that the analytical the samples were identical. The laboratory results from analysis of the quality control samples has and the routine samples could then be compared for agreement. Quality control sampling 1987.

been integrated into the program and has become an important part of the REMP since Quality control sampling locations are changed frequently in order to duplicate as many sampling pairing a locations as possible, and to ensure the contractor laboratory has no way of correctly quality control sample with its routine sample counterpart.

Program Description in The Radiological Environmental Monitoring Program (REMP) at Davis-Besse is conducted accordance with Title 10, Code of Federal Regulations, Part 50; Regulatory Guide 4.8; the Davis Besse Nuclear Power Station Operating License, Appendix A (Technical Specifications); the Davis-Besse Offsite Dose Calculation Manual (ODCM) and Station Operating Procedures.

Samples are collected weekly, monthly, quarterly, semiannually, or annually, depending upon the by sample type and nature of the radionuclides of interest. Environmental samples collected Davis-Besse personnel are divided into four general types:

" atmospheric -- including samples of airborne particulates and airborne radio-iodine

"* terrestrial -- including samples of milk, groundwater, broad leaf vegetation, fruits, animal/wildlife feed, soil, and wild and domestic meat

" aquatic -- including samples of treated and untreated surface water, fish, and shoreline sediments

" direct radiation -- measured by thermoluminescent dosimeters All environmental samples are labeled using a sampling code. Table 2 provides the sample codes and collection frequency for each sample type.

REMP samples are collected onsite and offsite up to 25 miles away from the Station. Sampling locations may be divided into two general categories: indicator and control. Indicator locations are those which would be most likely to display the effects caused by the operation of Davis-28

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Besse, and are located within five miles of the station. Control locations are those which should be unaffected by Station operations, and are more than five miles from the Station. Data from indicator locations are compared with data from the control locations. This comparison allows REMP personnel to take into account naturally-occurring background radiation or fallout from weapons testing in evaluating any radiological impact Davis-Besse has on the surrounding envi ronment. Data from indicator and control locations are also compared with preoperational data to determine whether significant variations or trends exist.

Since 1987 the REMP has been reviewed and modified to develop a comprehensive sampling program adjusted to the current needs of the utility. Modifications have included additions of sampling locations above the minimum amount required in the ODCM and increasing the num ber of analyses performed on each sample. Besides adding new locations, duplicate or Quality Control (QC) sample collection was initiated to verify the accuracy of the lab analyzing the envi ronmental samples. These additional samples are referred to as the REMP Enhancement Sam ples. Approximately 2000 samples were collected and over 2300 analyses were performed during 2001. In addition, 15% of the sampling locations were quality control sampling locations.

Table 3 shows the number of the sampling location and number collected for each type.

29

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Table 2: Sample Codes and Collection Frequencies Sample Collection Code Frequency Sample Type AP Weekly Airborne Particulate Al Weekly Airborne Iodine TLD Quarterly, Annually Thermoluminescent Dosimeter Monthly (semi-monthly during Milk MIL grazing season)

WW Quarterly Groundwater BLV Monthly (when available)

Broadleaf Vegetation SWT Weekly Surface Water - Treated SWU Weekly Surface Water Untreated (lake water - monthly in summer)

FIS Annually Fish SED Semiannually Shoreline Sediment Soil SOi Semiannually DFE/VWFE Annually Animal/Wildlife Feed DME Annually Meat-Domestic WME Annually Meat-Wild FRU Annually Fruit 30

.-. I-LL-Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 3: Sample Collection Summary Sample Collection Number of Number of Number of Type Type*/ Locations Samples Samples (Remarks) Frequency** Collected Missed Atmospheric Airborne Particulates C/W 10 519 1 Airborne Radioiodine C/W 10 519 Terrestrial Milk (Jan.-Dec.) G/M 1 12 0 Groundwater G/Q*** 2 7 0 Domestic Meat G/A 2 2 0 Wild Meat G/A 2 2 Broadleaf Vegetation G/M 3 9 0 Fruit G/A 3 3 0 Soil G/SA 10 20 0 Animal/Wildlife Feed G/A 5 5 0 Aquatic Treated Comp/WM 4 208 0 Surface Water G/WM*** 1 52 0 Untreated G/WM*** 3 156 0 Surface Water Comp/WM 3 156 0 G/M 5 35 0 Fish (3 species) G/A 2 6 0 Shoreline Sediments G/SA 4 8 0 Direct Radiation Thermoluminescent C/Q*** 89 339 3 Dosimeters (TLD) C!A*** 89 82 7

• Type of Collection: C = Continuous; G = Grab; Comp = Composite

• • Frequency of Collection: WM = Weekly composite Monthly; W = Weekly

• • • Includes quality control location, SWU and SWT QC included in weekly grab sample/composited monthly

• • • • Hazardous weather conditions prevented sample collection SM = Semimonthly; M = Monthly; Q = Quarterly; SA = Semiannually; A = Annually 31

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Sample Analysis When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Davis-Besse REMP include:

Gross beta analysis measures the total amount of beta emitting radioactive material present in a gives sample. Beta radiation may be released by many different radionuclides. Since beta decay associated with gamma a continuous energy spectrum rather than the discrete lines or "peaks" radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal concentra tions of beta emitting radionuclides; it does not identify specific radionuelides. Gross beta analy sis merely acts as a toot to identify samples that may require further analysis.

Gamma spectral analysis provides more specific information than does gross beta analysis.

Gamma spectral analysis identifies each gamma emitting radionuclide present in the sample, and al the amount of each nuclide present. Each radionuclide has a very specific "fingerprint" that lows for swift and accurate identification. For example, gamma spectral analysis can be used to identify the presence and amount of iodine-131 in a sample. Iodine-131 is a man-made radioac tive isotope of iodine that may be present in the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power stations.

Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the amount present. As discussed in the Introduction Section, tritium is an isotope of hydrogen that emits low energy beta particles.

Strontium analysis identifies the presence and amount of strontium-89 and strontium-90 in a sample. These man-made radionuclides are found in the environment as a result of fallout from nuclear weapons testing. Strontium is usually incorporated into the calcium pool of the bio sphere. In other words, strontium tends to replace calcium in living organisms and becomes in corporated in bone tissue. The principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from airborne releases.

Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure. Table 4 provides a list of the analyses performed on environ mental samples collected for the Davis-Besse REMP.

Often samples will contain little radioactivity, and may be below the lower limit of detection for the particular type of analysis used. The lower limit of detection (LLD) is the smallest amount of sample activity that can be detected with a reasonable degree of confidence, at a predetermined level. When a measurement of radioactivity is reported as less than LLD (<LLD), it means that the radioactivity is so low that it cannot be accurately measured with any degree of confidence by that particular method for an individual analysis.

32

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples Sample Type Analyses Performed Atmospheric Monitoring Airborne Particulate Gross Beta Gamma Spectral Strontium-89 Strontium-90 Airborne Radioiodine Iodine-131 Terrestrial Monitoring Milk Gamma Spectral Iodine-131 Strontium-89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Broadleaf Vegetation Gamma Spectral and Fruits Iodine-131 Strontium-89 Strontium-90 Animal/Wildlife Feed Gamma Spectral Soil Gamma Spectral Wild and Domestic Meat Gamma Spectral 33

Davis-Besse Nuclear Power Station 2001 Annual RadiologicaI Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples (continued)

Sample Type Analyses Performed Aquatic monitoring Untreated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Treated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Iodine-13l Gross Beta Fish Gamma Spectral Shoreline Sediment Gamma Spectral Direct Radiation Monitoring Thermoluminescent Dosimeters Gamma Dose Sample History Comparison The measurement of radioactive materials present in the environment will depend on factors such as weather or variations in sample collection techniques or sample analysis. This is one reason why the results of sample analyses are compared with results from other locations and from ear lier years. Generally, the results of sample analyses are compared with preoperational and op erational data. Additionally, the results of indicator and control locations are also compared.

This allows REMP personnel to track and trend the radionuclides present in the environment, to assess whether a buildup of radionuclides is occurring and to determine the effects, if any, the operation of Davis-Besse is having on the environment. If any unusual activity is detected, it is investigated to determine whether it is attributable to the operation of Davis-Besse, or to some other source such as nuclear weapons testing.

34

E - 8_11 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Atmospheric Monitoring

" Airborne Particulates: No radioactive particulates have been detected as a result of Davis-Besse's operation. Only natural and fallout radioactivity from nuclear weapons testing and the 1986 nuclear accident at Chemobyl have been detected.

" Airborne Radioiodine: Radioactive iodine-131 fallout was detected in 1976, 1977, and 1978 from nuclear weapons testing, and in 1986 (0.12 to 1.2 pico curies per cubic meter) from the nuclear accident at Chernobyl.

Terrestrial Monitoring:

" Groundwater: Tritium was detected at indicator site T-225 at 416 pCi/L in October, and could be attributable to the operation of the Davis-Besse plant.

This beach well is not used for drinking water purposes.

" Milk: Iodine-131 from nuclear weapons testing fallout was detected in 1976 and 1977 at concentrations of 1.36 and 23.9 picocuries/liter respectively. In 1986, concentrations of 8.5 picocuries/liter were detected from the nuclear accident at Chernobyl. No iodine-131 detected has been attributable to the operation of Davis-Besse.

"* Domestic and Wild Meat: Only naturally occurring potassium-40 and very low cesium-137 from fallout activity has been detected in meat samples. Po tassium-40 has ranged from 1.1 to 4.6 picocuries/gram weight (wet). Cesium 137 was detected in 1974, 1975, and 1981 due to fallout from nuclear weap ons testing.

"* Broadleaf Vegetation and Fruits: Only naturally occurring radioactive mate rial and material from nuclear weapons testing have been detected.

"* Soil: Only natural background and material from nuclear weapons testing and the 1986 nuclear accident at Chernobyl have been detected.

"* Animal/Wildlife Feed: Only natural background and material from weapons testing have been detected.

Aquatic Monitoring Surface Water (Treated and Untreated): Historically, tritium has been de tected sporadically at low levels in treated and untreated surface water at both control and indicator locations. In 2001, it was detected once above the de tection limit of 330 pCi/L at T-22 Treated Surface Water indicator site at a concentration of 593 pCi!L, and twice at Indicator site T-3 for Untreated Sur face Water (439 and 986 pCi/L). This could be from the operation of Davis Besse, however, it is only a fraction of the allowable effluent concentration limit of 20,000 pCi/L in an unrestricted area, as stated in 40CFR141.

9 Fish: Only natural background radioactive material and material from nuclear testing have been detected.

35

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report and Shoreline Sediments: Only natural background, material from nuclear testing from the 1986 nuclear accident at Chemobyl have been detected.

Direct Radiation Monitoring dose Thermoluminescent Dosimeters (TLDs): The annual average gamma rates for the current reporting period recorded by TLDs have ranged from 38.4 to 78.8 millirem per year at control locations and between 25.6 and 96.4 mil lirem per year at indicator locations. No increase above natural background radiation attributable to the operation of Davis-Besse has been observed.

2001 Program Anomalies is a description of 2001 environmental sample collection Provided below irregularities:

because of Broadleaf vegetation was only collected during the months of July through September seasonal availability.

en On 1/11/01, the quarterly TLD at sample site T-207 was missing. This is a non-required hancement sample and it was replaced with a new TLD.

size was On 3/15/01, the tygon tubing on the T-22 automatic water sampler failed. The sample sufficient, but smaller than usual. New tubing was installed on the sampler.

outage on On 4/17/01, the air sampler at T-8 was found stopped due to a blown fuse. A power sample size 4/12/01 likely caused the failure. The pump restarted after fuse replacement, and the affected by was sufficient for analysis. Enhancement air sampler T-4 also appears to have been time the power interruption on 4/12/01, since its run time was about 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> short of the actual of 167.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

14 During replacement of second quarter TLDs, quarterly and annual TLDs at sample point T-1 and co-located QC sample T-124 were missing. Third quarter TLDs for these two non-required enhancement samples were installed.

On 8/7/01, ODCM-required air sampler T-7 was found inoperable. The cause of the problem was a fault in the underground electrical supply line, which was replaced the following day. All other air samplers were evaluated for the same potential problem. Plans are in place to rewire five other samplers in 2002 as preventative maintenance.

During August, several utility poles containing Emergency Preparedness sirens were replaced.

Two poles had TLD cages with annual and quarterly TLDs in them (eight in total), which were lost. The quarterly TLDs were replaced. All of the TLDs were non-required enhancements.

A power interruption at air sampler T-4 caused a difference of greater than 1% between measured and elapsed time during the week of 9/17/01.

During planned maintenance on an underground electrical supply cable on 10/30/01, three air samplers were being temporarily supplied by portable generators. Upon restoration of the normal electrical supply, the sampler at T-3 failed to restart and was replaced. The other two samplers 36

fli ý _LI Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report restarted satisfactorily, but the timer on at T-1 did not advance after restart. The actual elapsed time was used with this sample, and the sampler was replaced during the next sampling period.

On 11/27/01, the T-1 air sampler was found inoperable due to a blown fuse. A power interrup tion was the suspected cause of failure. The run time was sufficient to obtain a valid sample, and the pump operated correctly after fuse replacement.

A power outage at sampler T-4 during the week of 11/26/01 may have caused the timer on this sampling pump to stick. The pump was replaced with a spare, as was the questionable timer.

On 12/26/01, an obstruction in the sample tubing on untreated water sampler T-22 prevented the collection of a weekly composite. The recent low lake level caused an increase of solids in the Carroll Township wet well resulted in the obstruction. The sample tubing was relocated further from the bottom in order to keep it in an area of cleaner water. A grab sample was collected, which satisfied sampling requirements.

Atmospheric Monitoring Air Samples Environmental air sampling is conducted to detect any increase in the concentration of airborne radionuclides that may be inhaled by humans or serve as an external radiation source. Inhaled radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air sam ples collected by the Davis-Besse REMP include both airborne particulate and airborne ra dioiodine.

Samples are collected weekly with low volume vacuum pumps, which draw a continuous sample through a glass fiber filter and charcoal cartridge at a rate of approximately one cubic foot per minute. Airborne particulate samples are collected on 47mm diameter filters. Charcoal car tridges are installed downstream of the particulate filters to sample for the airborne radioiodine.

The airborne samples are sent to an offsite contract laboratory for analysis. At the laboratory, the airborne particulate filters are stored for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before they are analyzed to allow for the decay of naturally occurring short-lived radionuclides. However, due to the short half-life of iodine 131 (approximately eight days), the airborne radioiodine cartridges are analyzed upon receipt by the contract laboratory.

Airborne Particulate Davis-Besse continuously samples air for airborne radionuclides at ten locations. There are six indicator locations including four around the site boundary (T-l, T-2, T-3, and T-4), one at Sand Beach (T-7), and another at a local farm (T-8). There are four control locations, Oak Harbor (T-9), Port Clinton (T-11), Toledo (T-12) and Crane Creek (T-27). Gross beta analysis is per formed on each of the weekly samples. Each quarter, the filters from each location are combined (composite) and analyzed for gamma emitting radionuclides, strontium-89 and strontium-90 beta-emitting radionuclides were detected at the indicator and control locations at average con centration of 0.025 pCi/m3 and 0.025 pCi/m 3, respectively. Beryllium-7 was the only gamma emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites.

37

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Beryllium-7 is a naturally occurring radionuclide produced in the upper atmosphere by cosmic radiation. No other gamma emitting radionuclides were detected above their respective LLDs.

Strontium-89 (Sr-89) and Strontium-90 (Sr-90) were not detected above their LLDs. These re sults show no adverse change in radioactivity in air samples attibutable to the operation of the Davis-Besse Nuclear Power Station in 2001.

Airborne Iodine-I 31 Airborne iodine- 131 samples are collected at the same ten locations as the airborne particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly, sealed in separate collection bags and sent topCi/m the laboratory 3.

for gamma iodine-]31 above the LLD of 0.07 analysis. There was no detectable 2001 Albo Paud GrossIBob 0.04.

6 02 0.015 aml 0.005.

Figure 10: Concentrations of beta-emitting radionuclides in airbome particulate samples were nearly identical at indicator and control locations.

38

.1 ý. - --

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 5: Air Monitoring Locations Sample Location Type of Number Location Location Description T-1 I Site boundary, 0Q6 miles ENE of Station T-2 I Site boundary, 049 miles E of Station "TI-3 I Site boundary, 1.4 miles ESE of Station T-4 I Site boundary, 0.8 miles S of Station T-7 I Sand Beach, main entrance, 0.9 miles NW of Station T-8 I Earl Moore Farm, 2.7 miles WSW of Station T-9 C Oak Harbor Substation, 6.8 miles SW of Station T-1I C Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant, 23.5 miles WNW of Station T-27 C Crane Creek State Park, 5.3 miles WNW of Station I = Indicator C = Control 39

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Terrestrial Monitoring provides The collection and analysis of groundwater, milk, meat, fruits and broad leaf vegetation Animal and wildlife data to assess the buildup of radionuclides that may be ingested by humans.

food feed samples provide additional information on radionuclides that may be present in the chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere.

and Many radionuclides are present in the environment due to sources such as cosmic radiation fallout from nuclear weapons testing. Some of the radionuclides present are:

"* tritium, present as a result of the interaction of cosmic radiation with the up per atmosphere and as a result of routine release from nuclear facilities

" Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere

" Cesium-137, a manmade radionuclide which has been deposited in the envi ronment, (for example, in surface soils) as a result of fallout from nuclear weapons testing and routine releases from nuclear facilities

"* Potassium-40, a naturally occurring radionuclide normally found throughout the environment (including in the human body)

"* fallout radionuclides from nuclear weapons testing, including strontium-89, strontium-90, cesium-137, cerium-141, cerium-144, and ruthenium-106.

These radionuclides may also be released in minute amounts from nuclear fa cilities The radionuclides listed above are expected to be present in many of the environmental samples collected in the vicinity of the Davis-Besse Station. The contribution of radionuclides from the operation of Davis-Besse is assessed by comparing sample results with preoperational data, op erational data from previous years, control location data, and the types and amounts of radioac tivity normally released from the Station in liquid and gaseous effluents.

Milk Samples Milk sampling is a valuable tool in environmental surveillance because it provides a direct basis for assessing the build up of radionuclides in the environment that may be ingested by humans.

Milk-is collected and analyzed because it is one of the few foods commonly consumed soon after production. The milk pathway involves the deposition of radionuclides from atmospheric re leases onto forage consumed by cows. The radionuclides present in the forage-eating cow be come incorporated into the milk, which is then consumed by humans.

When available, milk samples are collected at indicator and control locations once a month from November through April, and twice a month between May and October. Sampling is increased in the summer when the herds are usually outside on pasture and not on stored feed. In Decem ber of 1993, indicator location T-8 was eliminated from the sampling program, and no other in dicator milk site has existed since that time. The control location will continue to be sampled 43

fl ELJL Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report monthly in order to gather additional baseline data. If any dairy animals are discovered within five miles of the station, efforts will be made to include them in the milk-sampling program as indicator sites.

The 2001 milk samples were analyzed for strontium-89, strontium-90, iodine-131 and other gamma emitting radionuclides, stable calcium and potassium., A total of 12 milk samples were collected in 2001. Strontium-89 was not detected above its LLD. Strontium-90 was detected in all but one sample collected. The annual average concentration of strontium-90 was 1.00 pCi/l.

For all sample sites, the annual average concentration was similar to those measured in the previ ous years.

Iodine-131 was not detected in any of the milk samples above the LLD of 0.40 pCi/l. The con centrations of barium-140 and cesium-137 were below their respective LLDs in all samples col lected.

Since the chemistries of calcium and strontium are similar, as are potassium and cesium, organ isms tend to deposit cesium radioisotopes in muscle tissue and strontium radioisotopes in bones.

In order to detect the potential environmental accumulation of these radionuclides, the ratios of the strontium radioactivity (pCi/I) to the concentration of calcium (g/l), and the cesium radioac tivity (pCi/l) compared to the concentration of potassium (g/l) were monitored in milk. These ratios are compared to standard values to determine if buildup is occurring. No statistically sig nificant variations in the ratios were observed.

Table 6: Milk Monitoring Location Sample Location Type of Number Location Location Description T-24 C Toft Dairy, Sandusky, 21.0 miles SE of Station C = Control Groundwater Samples Soil acts as a filter and an ion exchange medium for most radionuclides. However, tritium and other radionuclides such as ruthenium-106 have a potential to seep through the soil and could reach groundwater. Davis-Besse does not discharge its liquid effluents directly to the ground. In the past, REMP personnel sampled local wells on a quarterly basis to ensure early detection of any adverse impact on the local groundwater supplies due to Station operation. In addition, a quality control sample was collected at one of the wells each quarter. The groundwater samples were analyzed for beta emitting radionuclides, tritium, strontium-89, strontium-90 and gamma emitting radionuclides.

44

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report During the fall of 1998, the Carroll Township Water Plant was placed into operation, and offered residents a reliable source of high-quality, inexpensive drinking water. This facility has replaced all of the drinking water wells within five miles of Davis-Besse, as verified by the Ottawa County Health Department. During the third quarter of 2001, a beach well was located within five miles of the Station. Although the residents confirmed that they use only the township sys tem for their drinking water needs, they still use the well water for outside purposes. This well was added to our sampling program as an Indicator location during the fall of 2001. One Control location is still sampled quarterly at T-27, and it averaged <3.7 pCi/I gross beta for the year 2001.

Strontium-90 was detected in the Control sample T-27 on one occasion, and tritium was detected above the detection limit at 416 pCi/L at the Indicator location at T-225.

Gross Beta Ground Water 1982-2001 7

6 5

3 0 . iD (0 P 0 0 - (NI C, ID ID P. (0 0

0) 00 0) 00000 0 0) 0 Year Figure 14: Shown above are the annual averages for gross beta in groundwater from 1982 - 2001.

45

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 7: Groundwater Monitoring Locations Sample Location Type of Number Location Location Description T-27 C Crane Creek State Park, 5.3 miles WNW of Station T-225 I Ben Shultz residence, 1.55 miles NW of Station C = control I = indicator Broadleaf Vegetation and Fruit Samples Fruits and broadleaf vegetation also represent a direct pathway to humans. Fruits and broadleaf vegetation may become contaminated by deposition of airbotne radioactivity (nuclear weapons fallout or airborne releases from nuclear facilities) or from irrigation water drawn from lake wa ter receiving liquid effluents (hospitals, nuclear facilities, etc.). Radionuclides from the soil may be absorbed by the roots of the plants and become incorporated into the edible portions. During the growing season, edible broadleaf vegetation samples, such as kale and cabbage, are collected from gardens and farms in the vicinity of the Station. Fruit, such as apples, is collected from or chards in the vicinity of Davis-Besse.

In 2001, broadleaf vegetation samples were collected at two indicator locations (T-17 and T-19) and one control location (T-37). Fruit samples were collected at two indicator locations (T-8 and T-25) and one control location (T-209). Broadleaf vegetation was collected once per month during the growing season and consisted of cabbage. The fruit collected was apples. All samples were analyzed for gamma emitting radionuclides, strontium-89, strontium-90, and iodine- 131.

Iodine-131 was not detected above the LLD of 0.025 pCi/g (wet) in any broadleaf vegetation nor above the LLD of 0.017 pCi/g (wet) in fruit samples. The only gamma-emitting radionuclide detected in the fruit and broadleaf vegetation samples was potassium-40, which is naturally oc curring. In broadleaf vegetation, strontium-90 (Sr-90) was detected at average concentrations of 0.008 pCi/g (wet) for indicator locations and below the LLD of 0.004 pCi/g (wet) for control lo cations. In the fruit samples, Sr-90 was not detected above 0.001 pCi/g (wet) at indicator sites T-8 and T-25, and was detected at 0.001 pCi/g(wet) at control site T-209. Results of broadleaf vegetation and fruit samples were similar to results observed in previous years. The operation of Davis-Besse had no observable adverse radiological effect on the surrounding environment in 2001.

46

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 8: Broadleaf Vegetation and Fruit Locations Sample Location Type of Number Location Location Description T-8 I Moore Farm, 2.7 miles WSW of Station T-17 I J. Sobieralski, 1.8 miles SSE of Station T-19 I B. Skinner, 1.0 mile W of Station T-25 I Witt Farm, 1.6 miles south of Station T-37 C Bench Farm, 13.0 miles SW of Station T-209 C Roving Control Location I = indicator, C control Animal/Wildlife Feed Samples Vegetation consumed by wildlife, and feed consumed by domestic animals can provide an indi cation of airborne radionuclides deposited in the vicinity of the Station. Analyses of ani mal/wildlife feed samples can also provide data for determining radionuclide concentration in the food chain. Domestic animals feed samples are collected at two domestic meat-sampling loca tions. Wildlife feed samples are collected from the Navarre Marsh and from a local marsh within five miles of the Station. As in all terrestrial samples, naturally occurring potassium-40, cosmic ray-produced radionuclides such as beryllium-7, and fallout radionuclides from nuclear weapons testing may be present in the feed samples.

There is one indicator (T-197) and one control location (T-34). The feed collected was chicken feed. All samples were analyzed for gamma-emitting radionuclides.

Wildlife feed was collected annually at three locations (T-31, T-32 and T-198). The samples consisted of the edible portions of cattails. Samples were analyzed for gamma-emitting radionuclides.

In both the animal and wildlife feed, naturally occurring potassium-40 was detected. Be ryllium-7 was detected at T-31 and T-32. All other radionuclides were below their re spective LLDs. The operation of Davis-Besse had no adverse effect on the surrounding environment.

47

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 9: Animal/Wildlife Feed Locations Sample Location Type of Number Location Location Description T-31 I Davis-Besse, onsite roving location T-32 C Roving offsite location- collected 7.0 miles W of station in 2001 T-34 C Brian Lowe residence, 8.2 miles W of the Station T-197 Lochotzki residence 4.0 miles W of the Station Lemon Road T-198 I Toussaint Creek Wildlife Area 4.0 miles WSW of the Station I = indicator C = control Wild and Domestic Meat Samples Sampling of domestic and wild meat provides information oi environmental radionuclide con centrations that humans may be exposed to through an ingestion pathway. The principle path ways for radionuclide contamination of meat animals include deposition of airborne radioactivity in their food and drinking water and contamination of their drinking water from radionuclides released in liquid effluents.

The REMP generally collects wild meat and domestic meat (thicken) on an annual basis. Wild animals commonly consumed by residents in the vicinity of Davis-Besse include waterfowl, deer, rabbits and muskrats. Analyses from these animals provide general information on radionuclide concentration in the food chain. When evaluating the results; from analyses performed on meat animals, it is important to consider the age, diet and mobility of the animal before drawing con clusions on radionuclides concentration in the local environment or in a species as a whole.

Meat samples were taken in 2001 as follows:

" Domestic Meat: Chickens were collected at one indicator location (T-197) and one control location (T-34). The samples were analyzed for gamma emitting nuclides.

Only naturally-occurring radionuclides were detected in the edible portion of the chicken.

" Wild Meat: Muskrat samples were collected on Station property and showed only naturally occurring activity due to Potassium 40.

48

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 10: Wild and Domestic Meat Locations Sample Location Type of Number Location Location Description T-31 I Onsite roving location T-34 C Brian Lowe residence, 8.2 miles W of the the Station T-197 Lochotzki residence, Lemon Road, 4.0 miles W of the Station "T-210 C Roving offsite location (5.5 mi. WNW of the Station in 2001)

I = indicator C = control Soil Samples Soil samples are generally collected twice a year at the sites that are equipped with air samplers.

Only the top layer of soil is sampled in an effort to identify possible trends in the local environ mental nuclide concentration caused by atmospheric deposition of fallout and station-released radionuclides. Generally, the sites are relatively undisturbed, so that the sample will be repre sentative of the actual deposition in the area. Ideally, there should be little or no vegetation pres ent, because the vegetation could affect the results of analyses. Approximately five pounds of soil are taken from the top two inches at each site. Many naturally occurring radionuclides such as beryllium-7 (Be-7), potassium-40 (K-40) and fallout radionuclides from nuclear weapons testing are detected. Fallout radionuclides that are often detected include strontium-90 (Sr-90),

cesium-137 (Cs-137), cerium-141 (Ce-141) and ruthenium-106 (Ru-106).

During 2001, soil was collected at ten sites in April and October. The indicator locations in cluded T-l, T-2, T-3, T-4, T-7, and T-8. The control locations were T-9, T-l 1, T-12, and T-27.

All soil samples were analyzed for gamma emitting radionuclides. The results show that the only gamma emitter detected in addition to naturally occurring Be-7 and K-40 was Cs-137. Cs-137 was found in both indicator and control locations at average concentrations of 0.13 pCi/g dry and 0.23 pCi/g dry, respectively. The concentrations were similar to that observed in previous years (Figurel 5).

49

pCilgram 1972 1973 1974 1975 o,., 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 -'a 1986 0 1987 1988 I.1989 1990 1991 o"~ 1992 s( '2 1993 1994 1995 1996 1997 1998 1999 2000 2001

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 11: Soil Locations Sample Location Type of Number Location Location Description T-1 I Site boundary, 0.6 miles ENE of Station T-2 I Site boundary, 0.9 miles E of Station T-3 I Site boundary 1.4 miles ESE of Station T-4 I Site boundary 0.8 miles S of Station T-7 I Sand Beach, main entrance, 0.9 miles NW of Station "T-8 I Moore Farm, 2.7 miles WSW of Station T-9 C Oak Harbor Substation, 6.8 miles SW of Station T-11 C Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant, 23.5 miles WNW of Station T-27 C Crane Creek State Park, 5.3 miles WNW of Station I = indicator C = control 51

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Aquatic Monitoring Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-off/soil erosion, and releases of radioactive material in liquid effluents from hospitals or nu clear facilities. These sources provide two forms of potential exposure to radiation, external and internal. External exposure can occur from the surface of the water, shoreline sediments and from immersion (swimming) in the water. Internal exposure can occur from ingestion of radio nuclides, either directly from drinking water, or as a result of the transfer of radionuclides through the aquatic food chain with eventual consumption of aquatic organisms, such as fish. To monitor these pathways, Davis-Besse samples treated surface water (drinking water), untreated surface water (lake or river water), fish, and shoreline sediments.

Treated Surface Water Treated surface water is water from Lake Erie, which has been processed for human consump tion. Radiochemical analysis of this processed water provides a direct basis for assessing the dose to humans from ingestion of drinking water.

Samples of treated surface water were collected from two indicators (T-22B and T-50) and two control locations (T-11 and T-12A). These locations include the water treatment facilities for Carroll Township, Erie Industrial Park, Port Clinton and Toledo. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta emitting radionu clides. The samples were also composited in a quarterly sample and analyzed for strontium-89, strontium-90, gamma emitting radionuclides, and tritium. One QC sample was collected from a routine location, which was changed each month.

The annual average of beta-emitting radionuclides for indicator and control locations was 2.5pCi/l and 2.3 pCi/l, respectively. These results are similar to previous years as shown in Fig ure 19. Tritium was detected once above the LLD of 330 pCi/l during the second quarter. The concentration at indicator location T-22 was 593 pCi/l, which is well below the allowable limit of 20,000 pCi/L. Strontium-89 was not detected above the LLD of 1.3 pCi/l. Strontium-90 ac tivity between 0.4 and 1.0 pCi/I was detected five times. These results are similar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse in 2001.

Each month, weekly quality control samples were collected at different locations. The results of the analyses from the quality control samples were consistent with the routine samples. The av erage concentration of beta emitting radionuclides detected at the QC location was 2.52 pCi/l.

There was good agreement between the routine and QC locations.

55

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Gss Bla in Ted SuramaVist 1972-M0I I= M* 0; CO MR Sol0) 0-0 ;0; 0 IS0 0 r r- - - --- -rrrrrrrrrrrrrrrrrrrrrrr

ý r rrrrrrrrrrrrrrrrrr 0- N Id'mat--Catwd Figure 19: Since 1974, the annual concentrations of beta emitting radionuclides in treated surface water samples collected from indicator locations have been consistent with those from control locations. Davis-Besse has had no measurable radiological impact on surface water used to make drinking water.

56

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 12: Treated Surface Water Locations Sample Location Type of Number Location Location Description T-1 1 C Port Clinton Water Treatment Plant 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant 23.5 miles WNW of Station T-22B I Carroll Township water sampled at Davis-Besse T-50 I Erie Industrial Park, Port Clinton, 4.5 miles SE of Station T-143 QC Quality Control Site I = indicator, C = control, QC = quality control Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to hu mans from external exposure from the lake surface as well as from immersion in the water. It also provides information on the radionuclides present, which may affect drinking water, fish, and irrigated crops.

Routine Program The routine program is the basic sampling program that is performed year round. Untreated wa ter samples are collected from water intakes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo, Carroll Township Intake and Erie Industrial Park.

A sample is also collected from Lake Erie at the mouth of the Toussaint River. These samples are collected weekly and composited monthly. The monthly composite is analyzed for beta emitting radionuclides, tritium, and gamma emitting radionuclides. The samples are composited further quarterly and analyzed for strontium-89 and strontium-90. A QC sample is also collected weekly, with the location changing each month.

57

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Summer Program The summer program is designed to supplement the routine untreated water sampling program in order to provide a more comprehensive study during the moniths of high lake recreational activ ity, such as boating, fishing, and swimming. These samples are obtained monthly in areas along the shoreline of Lake Erie, and analyzed for beta emitting radioactivity, tritium, strontium-89, strontium-90 and gamma-emitting radionuclides.

Sample Results For the routine untreated surface water samples composited weekly, the beta emitting radionu clides had an average concentration of 3.1 pCiIL at both indicator and control locations. The av erage concentration of beta-emitting radionuclides in summer lakewater samples was 3.05 pCiIL at indicator and 3.36 pCi/L at control locations.

During 2001, tritium was detected in 2 untreated surface water samples, ranging from 439 pCi/L to 986 pCi/L (well below the established 40CFRI41 limit of 20,000 pCi/L). Both were at indi cator locations, and could be due to the operation of the Davis-Besse Nuclear Power Station.

Cesium-137 was not detectable in samples of untreated water above the LLD of 6.4 pCiIL.

58

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Gross Beta Concentration in Untreated Surface Water 1977-2001 7 . .............. . ~-

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Each month, weekly quality control samples were collected at different locations. The results of the analyses from the quality control samples were consistent with the routine samples. The av erage concentration of beta emitting radionuclides detected at the QC location was 2.98 pCi/1 and 2.99 pCi/i at routine locations.

59

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 13: Untreated Surface Water Locations Sample Location Type of Number Location Location Description T-3 I Site boundary, 1.4 miles ESE of Station T-1 1 C Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant, sample taken from intake crib, 11.25 miles NW of Station T-22A I Carroll Township Water Intake, Humphrey Rd.,

3.0 miles NW of Station T-50 I Erie Industrial Park, Port Clinton, 4.5 miles SE of Station "T-132 I Lake Erie, 1.0 miles E of Station T-134 I Lake Erie, 1.4 miles NW of Station T-137 C Lake Erie, 5.8 miles WNW of Station T-145 QC Roving Quality Control Site T-1 58 C Lake Erie, 10.0 miles WNW of Station T-162 C Lake Erie, 5.4 mriles SE of Station I = indicator, C = control 60

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological En-ironmental Operating Shoreline Sediment of undis The sampling of shoreline sediments can provide an indication of the accumulation the ingestion of solved radionuclides which may lead to internal exposure to humans through radiation source from fish, through resuspension into drinking water supplies, or as an external shoreline exposure to fishermen and swimmers.

at various times from Samples of deposited sediments in water along the shore were collected Shoreline sediment three indicator sites (T-3, T4, and T- 132) and one control location (T-27).

radionuclides.

was collected with a shovel. All samples were analyzed for gamma emitting 4 0 was detected at both control and indicator locations. Cs-137 Naturally occurring potassium-was not detected at any locations. These results are similar to previous years.

Table 14: Shoreline Sediment Locations Sample Location Type of Number Location Location Description T-3 I Site boundary, 1.4 miles ESE of Station T-4 I Site boundary, 0.8 miles S of Station T-27 C Crane Creek State Park, 5.3 miles WNW of Station T-132 Lake Erie, 1.0 miles E of Station I = indicator C = control 61

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Fish Sample Fish are analyzed primarily to quantify the dietary radionuclide *intakeby humans, and secondar ily to serve as indicators of radioactivity in the aquatic ecosystem. The principal nuclides which may be detected in fish include naturally occurring potassium-40, as well as cesium-137, and strontium-90. Depending upon the feeding habit of the species (e.g., bottom-feeder versus predator), results from sample analyses may vary.

With the aid of a local commercial fisherman, Davis-Besse routinely collects three species of fish once per year from sampling locations near the Station's liquidi discharge point and more than ten miles away from the Station where fish populations would not be expected to be impacted by the Station operation. Walleye are collected because they are a popular sport fish and white perch or white bass are collected because they are an important commercial fish. Carp are collected be cause they are bottom feeders where contaminants may settle.

The average concentration of beta emitting radionuclides in fish was similar for indicator and control locations (2.97 pCi/g and 2.82 pCi/g wvet weight, respectively). Cesium-137 was not de tected above the LLD of <0.020 pCi/g for indicator and control locations. No other gamma emitters were detected above their respective LLDs.

Gross Beta In Fish 1972-2001 4.5 3.5 12.5 1.5 0.5

.. P 20 C1 O MO a, M Year 1-- indicatr -a-cCMt0i Figure 21: Average concentrations of beta emitting radionuclides in fish samples were similar at indicator and con trol locations mad were within the range of results of previous years.

62

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environiiental Operating Report Table 15: Fish Locations Sample Location Type of Number Location Location Description T-33 I Lake Erie, within 5 miles radius of Station T-35 C Lake Erie, greater than 10 mile radius of Station I = indicator C= control 63

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Thermoluminescent Dosimeters Radionuclides present in the air and deposited on the ground may directly irradiate individuals.

Direct radiation levels at and around Davis-Besse are constantly monitored by thermo luminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information.

The TLDs used at Davis-Besse contain a calcium sulfate: dysprosium (CaSO 4 :Dy) card with four main readout areas. Multiple readout areas are used to ensure the precision of the measurements.

Thermoluminescence is a process in which ionizing radiation interacts with phosphor, which is the sensitive material in the TLD. Energy is trapped in the TLD material and can be stored for several months or years. This provides an excellent method to measure the dose received over long periods of time. The energy that was stored in the TLD as a result of interaction with radia tion is released and measured by a controlled heating process in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy in the form of light. The amount of light detected is directly proportional to the amount of radiation to which the TLD was exposed.

The reading process re-zeroes the TLD and prepares it for reuse.

TLD Collection Davis-Besse has 89 TLD locations (78 indicator and 11 control) which are collected and replaced on a quarterly and annual basis. Eighteen QC TLDs are also collected on a quarterly and annual basis. There are a total of 214 TLDs in the environment surrounding Davis-Besse at any given time. By collecting TLDs on a quarterly and annual basis from a single site, each measurement serves as a quality control check on the other. Over 99% of the quarterly TLDs placed in the field and 96% of the annual TLDs placed in the field were retrieved and evaluated during the cur rent reporting period.

In 2001, the average dose equivalent for quarterly TLDs at all indicator locations was 14.4 mrem!91 days, and for all control locations was 14.8 mrem/91 days. The average dose equivalent for annual TLDs in 2001 was 55.6 mrem/365 days at indicator locations and 58.0 mrem/365 days for control locations.

Quality Control TLDs Duplicate TLDs have been placed at 18 sites. These TLDs were placed in the field at the same time and at the same location as some of the routine TLDs, but were assigned quality control site numbers. This allows us to take several measurements at the location without the laboratory be ing aware that they are the same. A comparison of the quality control and routine results pro vides a method to check the accuracy of the measurements. The average dose equivalent at the routine TLDs averaged 14.2 mrem/91 days while the quality control TLDs yielded an average dose equivalent of 13.4 mrem/91 days.

67

El I JLJI Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Gamma Dose for Environmental TLDs 1973-2001 25 is 2

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~4 Co4 o g i g i i-4-indicator --*-control Figure 25: The similarity between indicator and control results demonstrated that the operation of Davis-Besse has not caused any abnormal gamma dose.

68

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations Sample Location Type of Number Location Location Description I Site boundary, 0.6 miles ENE of Station T-1 I Site boundary, 0.9 miles E of Station T-2 1 Site boundary, 1.4 miles ESE of Station T-3 I Site boundary, 0.8 miles S of Station T-4 I Site boundary, 0.5 miles W of Station T-5 I Site boundary, 0.5 miles NNE of Station T-6 T-7 I Sand Beach, main entrance, 0.9 miles NW of Station T-8 I Earl Moore Farm, 2.7 miles WSW of Station T-9 C Oak Harbor Substation, 6.8 miles SW of Station T-10 I Site boundary, 0.5 miles SSW of Station near warehouse T-11 C Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant, 23.5 miles WNW of Station T-24 C Sandusky, 21.0 miles SE of Station T-27 C Crane Creek State Park, 5.3 miles WNW of Station T-38 I Site boundary, 0.6 miles ENE of Station I Site boundary 1.2 miles ENE of Station T-39 T-40 I Site boundary, 0.7 miles SE of Station T-41 I Site boundary, 0.6 miles SSE of Station I Site boundary, 0.8 miles SW of Station T-42 69

U1 J _ILL Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location Location Description T-43 I Site boundary, 0.5 miles SW of Station T-44 I Site boundary, 0.5 miles WSW of Station T-45 I Site boundary, 0.5 miles WNW of Station T-46 I Site boundary, 0.5 miles NW of Station T-47 I Site boundary, 0.5 miles N of Station T-48 I Site boundary, 0.5 miles NE of Station T-49 I Site boundary, 0.5 miles NE of Station T-50 I Erie Industrial Park, Port Clinton, 4.5 miles SE of Station T-51 on Siren Pole, 5.5 miles SSE of Station T-52 Miller Farm, 3.7 miles S of Station T-53 Nixon Farm, 4.5 miles S of Station T-54 Weis Farm, 4.8 miles SW of Station T-55 King Farm, 4.5 miles W of Station T-60 Site boundary, 0.3 miles S of Station T-62 Site boundary, 1.0 mile SE of Station T-65 Site boundary, 0.3 miles E of Station T-66 Site boundary, 0.3 miles ENE of Station T-67 Site boundary, 0.3 miles NNW of Station T-68 Site boundary, 0.5 miles WNW of Station T-69 Site boundary, 0.4 miles W of Station 70

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location Location Description T-71 I Site boundary, 0.1 mile NNW of Station T-73 I Site boundary, 0. 1 mile WSW of Station T-74 I Site boundary, 0.1 mile SSW of Station T-75 I Site boundary, 0.2 mile SSE of Station T-76 I Site boundary, 0.1 mile SE of Station T-80 QC Quality Control Site T-81 QC Quality Control Site T-82 QC Quality Control Site T-83 QC Quality Control Site T-84 QC Quality Control Site T-85 QC Quality Control Site T-86 QC Quality Control Site T-88 QC Quality Control Site T-87 QC Quality Control currently located in lead pig, DBAB annex T-89 QC Quality Control Site T-90 I Site Personnel Processing Facility T-91. I State Route 2 and Rankie Road, 2.5 miles SSE of Station T-92 I Locust Point Road, 2.7 miles WNW of Station T-93 I Twelfth Street, Sand Beach, 0.6 miles NNE of Station T-94 I State Route 2, 1.8 miles WNW of Station T-95 C State Route 579, 9.3 miles W of Station 71

0a! ~ U Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location Location Description T-100 C Ottawa County Highway Garage, Oak Harbor, 6.0 miles S of Station T-1l1 C Toussaint North Road, 8.3 miles WSW of Station T-1 12 I Thompson Road, 1.5 miles SSW of Station "T-113 QC Quality Control Site T-114 QC Quality Control Site T-1 15 QC Quality Control Site T-116 QC Quality Control Site T-1 17 QC Quality Control Site T-1 18 QC Quality Control Site T-119 QC Quality Control Site T-120 QC Quality Control Site T-121 I State Route 19, 2.0 miles W of Station T-122 I Duff Washa and Humphrey Road, 1.7 miles W of Station T-123 I Zetzer Road, 1.6 miles WSW of Station Church and Walnut Street, Oak Harbor, 6.5 T-124 C miles SSW of Station T-125 I Behlman and Bier Roads, 4.4 miles SSW of Station T-126 I Camp Perry Western and Toussaint South Road, 3.7 miles S of Station T-127 I Camp Perry Wesern and Rymers Road, 4.0 miles SSE of Station 72

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Table 16: Thermoluminescent Dosimeter Locations (continued)

Samnle Location Type of Number Location Location Description 1 Erie Industrial Park, Port Clinton Road, T-128 4.0 miles SE of Station T-142 I Site Boundary, 0.8 miles SSE of Station I Humphrey and Hollywood Road, 2.1 miles NW T-150 of Station T-151 I State Route 2 and Humphrey Road, 1.8 miles WNW of Station T-1 53 I Leutz Road, 1.4 miles SSW of Station T-154 I State Route 2, 0.7 miles SW of Station T-155 C Fourth and Madison Streets, Port Clinton, 9.5 miles SE of Station T-200 QC Quality Control Site T-201 I Sand Beach, 1.1 miles NNW of Station T-202 I Sand Beach, 0.8 miles NNW of Station T-203 I Sand Beach, 0.7 miles N of Station T-204 I Sand Beach, 0.7 miles N of Station T-205 I Sand Beach, 0.5 miles NNE of Station T-206 I Site Boundary, 0.6 miles NW of Station T-207 I Site Boundary, 0.5 miles N of Station T-208 I Site Boundary, 0.5 miles NNE of Station.

I = indicator, C = control, QC = quality control 73

0 I IILI Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location Location Description T-211 I Site boundary, 0.79 miles E of Station T-212 I Site boundary, 1.2 miles ESE of Station T-213 I Site boundary, 0.6 miles SSW of Station "T-214 I Site boundary, 0.7 miles SW of Station T-215 I Site boundary, 0.5 miles W of Station T-216 I Site boundary, 0.7 miles NW of station T-217 I Salem-Carroll Rd., 4.7 miles SSW of Station T-218 I Toussaint East Rd., 4.0 miles WSW of Station T-219 I Toussaint Portage Rd., 4.8 miles WSW of Station T-220 I Duff-Washa Rd., 4.8 miles W of Station T-221 C Magee Marsh, 5.1 miles WNW of Station T-222 I Turtle Creek Access, 3.7 miles WNW of Station T-223 I Lawrence Rd., 5.0 miles SE of Station T-224 I Erie Industrial Park, 4.4 miles SE of Station 74

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report z* C Ut 0.0

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Conclusion The Radiological Environmental Monitoring Program at Davis-Besse is conducted to determine the radiological impact of the Station's operation on the environment. Radionuclide concentra lo tions measured at indicator locations were compared with concentrations measured at control cations in previous operational studies and in the preoperational surveillance program. These col comparisons indicate normal concentrations of radioactivity in all environmental samples lected in 2001. Davis-Besse's operation in 2001 indicated no observable adverse radiological sample impact on the residents and environment surrounding the station. The results of the in Ap analyses performed during the period of January through December 2001 are summarized pendix D of this report.

78

Ill L2t Davis-Besse Nuclear Power Station 2001 Annual Radiological Enviromnental Operating Report "References

1. "Cesium-137 from the Environment to Man: Metabolism and Dose," Report No.52, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1977).

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7. "Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion 'As Low As Reasonably Achievable' for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents," Code of Federal Regulations, Title 10 Energy, Part 50 "Domestic Licensing of Production and Utilization Facilities," Appendix 1 (1988).

8. "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry,"

American National Standards Institute, Inc., ANSI-N45-1975, New York, New York (1975).

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79

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report

13. Regulafory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment," US NRC (February 1979).

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80

III 3JjJAtL Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report

29. Toledo VEdison Company, "Annual Radiological Environmental Operating Report Preparation and Submittal", DB-HP-00014.

30. Toledo Edison Company, Davis-Besse Nuclear Power Station, Offsite Dose Calculation Manual 3 1. "Tritium in the Environment", Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979).

81