ML061230398

2005 Annual Radiological Environmental Operating Report

ML061230398
Person / Time
Site:	Davis Besse
Issue date:	12/31/2005
From:	FirstEnergy Corp
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209
Download: ML061230398 (189)

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Davis-Besse Nuclear Power Station Davis-Besse Nuclear Power Station January 1, 2005 through December 31, 2005 Davis-Besse Nuclear Power Station April 2006

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE OF CONTENTS Title P.-e List of Tables iv List of Figures vi Executive Summary viii INTRODUCTION Fundamentals Radiation and Radioactivity '

Interaction with Matter 3 Quantities and Units of Measurement 5 Sources of Radiation 7 Health Effects of Radiation 9 H-alth Risks II)

Benefits of Nuclear Power 1 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 Psre-Operational Surveillance Program 26 Operational Surveillance Program Objectives 27 Quality Assurance 27 Program Description 28 Sample Analysis 32 Sample History Comparison 34 i

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Title Pag RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) 2005 Program Anomalies 36 Atmospheric Monitoring 37 Terrestrial Monitoring 43 Aquatic Monitoring 55 Direct Radiation Monitoring 67 Conclusion 78 References 78 RADIOACTIVE EFFLUENT RELEASE REPORT Protection Standards 81 Sources of Radioactivity Released 81 Processing and Monitoring 82 Exposure Pathways 83 Dose Assessment 84 Results 85 Regulatory Limits 86 Effluent Concentration Limits 87 Average Energy 87 Measurements of Total Activity 87 Batch Releases 88 Sources of Input Data 89 Abnormal Releases 88 Doses to Public Due to Activities Inside the Site Boundary 89 Inoperable Radioactive Effluent Monitoring Equipment 90 Changes to The ODCM and PCP 90 Borated Water Storage Tank Radionuclide Concentrations 90 LAND USE CENSUS Program Design 109 Methodology 109 Results 110 ii

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Title Pa NON-Y'ADIOLOGICAL ENVIRONMENTAL PROGRAMIS Meteorological Monitoring 115 On-Site Meteorological Monitoring 116 Land and Wetlands Management 121 WAater Treatment Plant Operation 132 Chemical Waste Management I $5 Other Environmental Regulating Acts 1-$6 Other Environmental Programs 1$8 APPENDICES Appendix A: Interlaboratory Comparison Program Results 1,9 Appendix B: Data Reporting Conventions 158 Appendix C: Maximum Permissible Concentrations of Radioactivity in Air 160 and Water Above Natural Background in Unrestricted Areas Appendix D: REMIP Sampling Summary 162 iii

Davis-Besse Nuclear Power Station 2005 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 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 70 Gaseous Effluents - Summation of All Releases 17 91 Gaseous Effluents - Ground Level Releases - Batch Mode 18 92 Gaseous Effluents - Ground Level Releases - Continuous Mode 18 93 Ground Level Releases - LLDs for Continuous and Batch Mode 18 94 Gaseous Effluents - Mixed Mode Releases - Batch Mode 19 95 Gaseous Effluents - Mixed Mode Releases - Continuous Mode 19 96 LLDs for Gaseous Effluents - Mixed Mode Releases 19 97 Liquid Effluents - Summation of All Releases 20 98 Liquid Effluents - Nuclides Released - Batch Releases 21 99 Liquid Effluents - Nuclides Released - Continuous Releases 21 101 Liquid Effluents - LLDs for Nuclides Released 21 102 Solid Waste and Irradiated Fuel Shipments 22 103 Doses Due to Gaseous Releases for January through December 2005 23 106 Doses Due to Liquid Releases for January through December 2005 24 107 Annual Dose to The Most Exposed (from all pathways) Member of The 25 108 Public 2005 iv

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table Page Title Number Number Closest Exposure Pathways in 2005 26 112 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters 27 114 Summary of Meteorological Data Recovery for 2005 28 120 Summary of Meteorological Data Measured for 2005 29 121 Joint Frequency Distribution by Stability Class 30 126 v

Davis-Besse Nuclear Power Station 2005 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 2005 Airborne Particulate Gross Beta 10 38 Air Sample Site Map 11 40 Air Samples 5-mile Map 12 41 Air Sample 25-mile Map 13 42 Gross Beta Groundwater 1982-2005 14 45 Cs-137 in Soil 1972-2005 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 1972-2005 19 56 Gross Beta Concentration in Untreated Surface Water 1977-2005 20 59 Gross Beta Fish 1972-2005 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 - 2005 25 68 TLD Site Map 26 75 TLD 5-mile Map 27 76 TLD 25-mile Map 28 77 Exposure Pathways 29 84 vi

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Figure Page Description Number Number Land Use Census Map 30 111 Wind Rose Annual Average 1OOM 31 123 Wind Rose Annual Average 75M 32 124 Wind Rose Annual Average 101M 33 125 vii

Davis-Besse Nuclear Power Station 2005 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, 2005. 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, 2005.

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.e 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 radia-tion and radioactivity normally present in the area as natural background. Davis-Besse has con-tinued 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 2005. 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 2005 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 samples are collected continuously at ten locations. Four samplers are col-lected onsite. The other six are located offsite between one-half mile to twenty-two miles away. Particulate filters and iodine cartridges are collected weekly. The 2005 indicator results were in close agreement with the samples collected at control locations.

• 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 sam-ple analyses indicate concentrations 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, un-treated surface water, fish and shoreline sediments from onsite and the vicinity of Lake Erie. The 2005 results of analysis for fish, untreated surface water, drinking water and shoreline sediment indicate normal background concentra-ticn of radionuclides and show no increase or build-up of radioactivity due to th - operation of Davis-Besse.

• Direct radiation averaged 14.1 mrem/9ldays at indicator locations and 14.9 mrem/91 days at control locations. This is similar to results of previous years.

The operation of Davis-Besse in 2005 caused no significant increase in the concentrations cfra-dionuzlides in the environment and no adverse effect on the quality of the environment. Radio-activi,.y 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 2005 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 2005 was a garden in the West sector 1560 meters from Davis-Besse.

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Davis-Besse Nuclear Power Station 2005 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 through December 31, 2005. The doses due to radioactivity released during this period were estimated to be:

Liquid Effluents:

Maximum Individual Whole Body Dose 4.23E-03 mrem Maximum Individual Significant Organ Dose (liver) 5.64E-03 mrem Total Integrated Population Dose 2.84E-02 person-rem Average Dose to the Individual 1.30E-05 mrem Gaseous Effluents:

Maximum Individual Whole Body Dose due to 6.64E-04 mrem I-131, H-3 and Particulates with half-lives greater than 8 days Maximum Significant Organ Dose due to I-131, 8.13E-04 mrem H-3 and Particulates with half-lives greater than 8 days Total Integrated Population Dose due to I-131, 6.29E-03 person-rem H-3 and Particulates with half-lives greater than 8 days Average Dose to an individual in the population 2.88E-06 mrem due to I-131, H-3 and Particulates with half-lives greater than 8 days Maximum Individual Skin Dose due to noble gases 6.65E-04 mrem Maximum Individual Whole Body Dose due to 1.37E-04 mrem noble gases Total Integrated Population Dose due to noble gases 1.20E-04 person-rem Average Dose to individual in population due to 5.51E-08 mrem noble gases x

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report The Total Body doses to an individual and population in an unrestricted area due to direct radiation from Davis-Besse is not distinguishable from background. These doses represent an extremely small fraction of the limits set by the NRC or the limits set in the ODCM.

There was one abnormal liquid release of 6.4E-5 Curies of Tritium during this reporting pe-riod, resulting in a calculated dose of 1.7 millirem.

There was one revision of the Process Control Program (PCP) during this reporting period Revision 7), and one revision of the Offsite Dose Calculation Manual during 2005 (Revision 20.0).

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

Meteorological monitoring began in October of 1968.

Meteorological data recorded at Davis-Besse include wind speed, wind direction, sigma theta (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 99.17%.

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.

Davis-Besse's resident pair of American Bald Eagles was unsuccessful in fledging any eagl.ets in 2005. Thirteen healthy eaglets have been fledged from this location since 1995.

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

Since December 1, 1998, the Carroll Township Water Treatment Plant has provided site domes-tic water to Davis-Besse.

Sewage is treated at the Davis-Besse Wastewater Treatment Plant (WWTP) and pumped to a large basin. Following a retention period, the treated water is discharged with other Station liquid effluent back to Lake Erie.

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Davis-Besse Nuclear Power Station 2005 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 2005, the Davis-Besse Nuclear Power Station generated 4,000 pounds of hazardous waste.

Other non-hazardous wastes generated include 3,865 gallons of used oil, 75 cubic yards of oil filters and solid oily debris, and 60 gallons of microfilm process chemicals.

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 Resources Associates (ERA), 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. The Environmental Resources Associates (ERA) compares results to known standards.

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 2005.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Enviromnental Operating Report Appendix D provides a REMP sampling summary from 2005. 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 Davis-Besse (Febru-ary, 2005).

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Introduction Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Introduction Coal, oil, natural gas and hydropower are used to run this nation's electric generating stations; how-ever, each method has its drawbacks. Coal-fired power can affect the environment through mining, acid rain and air pollution. Oil and natural gas are in limited supply and are, therefore, costly. Hy-dropower is limited due to the environmental impact of damming our waterways and the scarcity of suitable sites.

Nuclear power provides a readily available source of energy. The operation of nuclear power sta-tions has a very small impact on the environment. In fact, the Davis-Besse Nuclear Power Station is surrounded by hundreds of acres of marshland, which make up part of the Ottawa National Wildlife Refuge. In order to provide better understanding of this unique source of energy, background infor-mation on basic radiation characteristics, risk assessment, reactor operation and effluent control 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 protons, electrons, and neutrons, respec-tively (Figure 1). The relatively large pro-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 dissimilar charges, the protons and electrons have a strong attraction for each other. This holds the atom together. Other attractive Figure 1: An atom consists of two parts- a nucleus forces between the protons and neutrons containing positively charged protons and electrically keep ihe densely packed protons from repel- neutral neutrons and one or more negatively charged electrons orbiting the nucleus. Protons and neutrons ling each other, and prevent the nucleus are nearly identical in size and weight, while each is from breaking apart. about 2000 times heavier than an electron.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Enviromnental 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. Ion-izing radiation consists of both electromagnetic radiation and particulate radiation. Electro-magnetic 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 deter-mines 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 succes-sive 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 2005 Annual Radiological Environmental Operating Report This example is part of a known radioactive decay series, called the Uranium series, which be-gins with Uranium-238 and ends with Lead-206 (Figure 2).

2 34 2z8U U 4.5 x 109Yr 2 5

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23 4 2 30 Th Th 24d 8.0 x 104 Yr 4 Beta Decay Alpha Decay l 226 Ra l 1 1600 Yr I 7I 222Rn l l 3.82 d l 2 10 218 Po 2146Po Po 3.05 min 3f 1.6 x104 S _f 138.4 d I 214Bi / 210 4-

, A19.7 minm , 5.01 d 20 214Pb 210 Pb 6Pb 26.8 min 23 Yr stable 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 2005 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 may be stopped by a thin piece of metal or wood.

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RADICOACTIVE rsATERIAL PAPER ALUMINUM LEAD CONCRETE Figure 3: As radiation travels, it collides and interacts with other atoms and loses energy. Alpha particles can be stopped by a sheet of paper. and beta particles by a thin sheet of aluminum. Gammna radiation is shielded by highly dense materials such as lead, while hydrogenous materials (those containing hydrogen atoms), such as water and concrete, arm 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 ray's 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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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within operating nuclear power reactors. However, neu-trons are not of environmental concern since the neutron source at nuclear power stations is sealed within the containment building.

Because neutrons have no charge, they are able to pass very close to the nuclei of the material through which they are traveling. As a result, neutrons may be captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some of its energy. After a series of these deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal. neu-tron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons.

Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron shielding materials commonly used to slow neutrons down are water or polyethylene. The shield is then completed with a material such as Cadmium, to absorb the now thermal neutrons. At Davis-Besse, concrete is used to form an effective neutron shield because it contains water mole-cules and can be easily molded around odd shapes.

Quantities and Units of Measurement There are several quantities and units of measurement used to describe radioactivity and its ef-fects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent.

Activity: Curie Activity is the number of atoms in a sample that disintegrate (decay) per unit of time. Eaca time an atom disintegrates, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms of a radioactive substance are decaying.

One curie indicates the disintegration of 37 billion atoms per second.

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

Smaller units of the curie are often used, especially when discussing the low concentrations of radioactivity detected in environmental samples. For instance, the microcurie (uCi) is equal to one millionth of a curie, while the picocurie (pCi) represents one trillionth of a curie.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environxmental Operating Report Absorbed Dose: Rad Absorbed dose is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation. The 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).

An example of this conversion from absorbed dose to dose equivalent uses the quality factor for alpha radiation, which is equal to 20. Thus, 1 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 rang-ing 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 mil-lirem, 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 6

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report 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.

Total Effective Dose Equivalent (TEDE)

Total effective dose equivalent is the sum of the deep dose equivalent (for dose from sources, ex-ternal to the body) and the committed effective dose equivalent (for internal dose). Since they are both doses to the body, they are not tracked separately. The NRC limits occupational dose to a radiation worker to five rem (5000 mrem) TEDE per year.

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

The earth is being showered by a steady stream of high-energy gamma rays and particulate radia-tion that come from space known as cosmic radiation. The atmosphere shields us from most of this radiation, but everyone still receives about 20 to 50 mrem each year from this source The thinner air at higher altitudes provides less protection against cosmic radiation. People living at higher altitudes or flying in an airplane are exposed to even higher levels cosmic radiation. Ra-dionuclides commonly found in the atmosphere as a result of cosmic ray interactions include Be-ryllium-7, Carbon-14, tritium (H-3), and Sodium-22.

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

The major source of background radiation is Radon, a colorless, odorless, radioactive gas that results from the decay of Radium-226, a member of the Uranium-238 decay series. Since Ura-nium occurs naturally in all soils and rocks, everyone is continuously exposed to Radon and its daughter products. Radon is not considered to pose a health hazard unless it is concentrated in a confined area, such as buildings, basements or underground mines. Radon-related health con-cerns stem from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it decays, which can cause damage to internal tissues when inhaled. As a result, exposure to the lungs is a concern, since the only recognized health effect associated with exposure to Ra-don is an increased risk of lung cancer. This effect has been seen when Radon is present at levels common in uranium mines. According to the National Council on Radiation Protecticn and Measuarement (NCRP), more than half of the radiation dose the average American receives is at-tributed to Radon.

7

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report SOURCES OF EXPOSURE TO THE PUBLIC Terrestrial 8%

Internal 11%

Radon 55%

Manmade 18% (X-Rays 10%, Nuclear Medicine 4%,

- Consumer Products 3%,

Nuclear Power <0.2%)

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 ad-dress:

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 8 co

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report 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.

Health Effects of Radiation The effects of ionizing radiation on human health have been under study for more than ninety years. Scientists have obtained valuable knowledge through the study of laboratory animals that were exposed to radiation under extremely controlled conditions. However, it has been difficult to relate the biological effects of irradiated laboratory animals to the potential health effects on humans.

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

Somatic effects can be divided further into acute and chronic effects. Acute effects develop shortly after exposure to large amount of radiation. Much study has been done with human populations that were exposed to ionizing radiation under various circumstances. These groups include the survivors of the atomic bomb, persons undergoing medical radiation treatment, and early radiologists, who accumulated large doses of radiation, unaware of the potential hazards.

Chronic effects are a result of exposure to radiation over an extended period of time. Examples of such groups are clock dial painters, who ingested large amounts of Radium by "tipping" the paint brushes with their lips, and Uranium miners, who inhaled large amounts of radioactive dust 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 Ibng 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 determ.ne 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 occar as a result of ionizing radiation interacting with the genes in the human 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 9

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report break could join incorrectly with those from another. This could cause translocations, inversions, rings, and other types of structural rearrangements. When this 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 driv-ing to work each day, they are less inclined to accept the risk inherent in producing electricity.

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 realistic as-sessment of the risks, and on placing these risks in perspective. The perceptions of risk associ-ated 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 1 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 2005 Annual 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 fi)llowing 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, primar-ily uranium, replaces the furnace. Heat is produced when the atoms of Uranium are split, or fissioned, inside the reactor.

Whai: 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.

11

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Bombarding .c - I- a Neutron Free F

Atom /

Fission. Q Fragment Figure 5: When a heavy atom, such as uranium-235 is split or fissioned, heat, free neutrons, and fission fragments resulL The free 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 2005 Annual Radiological Environmental Operating Report After the Uranium ore is separated from the earth and rock, it is concentrated in a milling proc-ess. After milling the ore to a granular form and dissolving out the Uranium with acid, the Ura-nium is converted to Uranium hexafluoride (UF6 ). UF 6 is a chemical form of Uranium that exists Es a gas at temperatures slightly above room temperature. The UF6 is then highly purified and shipped to an enrichment facility where gaseous diffusion converters increase the cor.cen-tration of U-235. The enriched gaseous UF6 is then converted into powdered Uranium dioxide (U0 2 ), 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 ihese 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 inser-tion 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 con-tains 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 inches thick.

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REAC1TOR VESSEL 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 diameter and 5/8 inch long.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Fission Control Raising or lowering control rod assemblies into the reactor core controls the fission rate. Each assembly consists 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-l1, removing the absorbed neutrons from the chain reaction.

Reactor Types Virtually all of the commercial reactors in this country are either boiling water reactors (BWA'Rs) or pressurized water reactors (PWN'Rs). Both types are also called light water reac-tors (LNWRs) 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 (HWVRs).

In BWRs, 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 2005 Annual Radiological Environmental 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 concrete walls 2 feet thick. The shield building protects the containment vessel from a variety of 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 com-promised (e.g., a crack develops), this negative pressure boundary ensures that any airborne ra-dioactive contamination present in the containment vessel is prevented from leaking out into the environment. 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 contaminated air between the Containment vessel and the Shield Building to leak out. The Con-tainment 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 cladding 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 558'F 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 cool-ing 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 2005 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 cf 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 the condenser, which is several stories tall and contains 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 Pres-sure Turbines 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, which is pumped through the tubes in the Water Box, is able to cool the water in the Condenser by the processes of conduction and convection.

Even in the event of a primary-to-secondary leak, the water vapor exiting the Davis-Besse Cool-ing Tower would remain non-radioactive. Closed loops are an integral part of the design of any nuclear facility. This 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 circu-late 480,000 gallons of water per minute to the tower. Its purpose is to recycle water from the Condenser by cooling and returning it.

17

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report After passing through the Condenser, the Circulating Water has warmed to approximately I00F.

In order to cool the water back down to 70'F, the Circulating Water enters the Cooling Tower forty feet above the ground. It is then sprayed evenly over a series of baffles called flllsheets, which are suspended vertically in the base of the tower. A natural draft of air is swept upward through these baffles and cools the water by evaporation. The evaporated water exits the top of the Cooling Tower as water vapor.

As much as 10,000 gallons of water per minute are lost to the atmosphere via the Cooling Tower.

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

Miscellaneous Station Safety Systems The orange system in Figure 7 is part of the Emergency Core Cooling System (ECCS) housed in the Auxiliary Building of the station. The ECCS consists of three overlapping means of keeping the reactor core covered with water, in the unlikely event of a Loss-of-Coolant Accident (LOCA), thereby protecting the fuel cladding barrier against high-temperature failure. Depend-ing on the severity of the loss of pressure inside the Primary System, the ECCS will automati-cally channel borated water into the Reactor by using High Pressure Injection Pumps, a Core Flood Tank, or Low Pressure Injection Pumps. Borated water can also be sprayed from the ceiling of the Containment Vessel to cool and condense any steam that escapes the Primary Sys-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.

18

Davis-Besse Nuclear Power Station 2005 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 sys-tem 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 posi-tion of the control rods. The Reactor can be automatically shut down by a separate Reactor Pro-tection System, which 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 wa-ter into the reactor automatically if the reactor coolant pressure drops below a predetennined 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 ma-terials in less than 300 years.

Davis-Besse currently ships low-level radioactive waste to facilities in South Carolina and Ten-nessee for processing waste minimization prior to disposal. Davis-Besse has the capacity to store low-level waste produced on site for several years in the Low Level Radioactive Waste Storage Facility (LLRWSF), should these facilities close.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report High Level Nuclear Waste Like any industrial or scientific process, nuclear energy does produce waste. The most radioac-tive is defined as "high-level" waste (because it has high levels of radioactivity). Ninety-nine percent of high-level waste from nuclear plants is used nuclear fuel. The fuel undergoes certain changes during fission. Most of the fragments of fission, pieces that are left over after the atom is split, are radioactive. After a period of time, the fission fragments trapped in the fuel assem-blies reduce the efficiency of the chain reaction. Every 18 to 24 months, the oldest fuel assem-blies are removed from the reactor and replaced with fresh fuel.

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

Davis-Besse presently stores most of its used fuel in a steel-lined water-filled concrete vault in-side the plant. The Department of Energy is charged with constructing a permanent high-level waste repository for all of the nation's nuclear plants. By law, the Department of Energy was required to accept fuel from utilities by the end of 1998. Currently, Yucca Mountain, Nevada, is being considered as a possible site. Until the permanent DOE site is developed, nuclear plants will be responsible for the continued safe storage of high-level waste. At Davis-Besse, the fuel pool reached its capacity in 1996. At the end of 1996, Davis-Besse began the process of moving the older fuel assemblies that no longer require water cooling to air-cooled concrete shielded can-isters. These will remain onsite until the Department of Energy facilities are ready to receive them. Dry fuel storage is already used in many countries, including Canada, and in the U.S. at nuclear plants in Arkansas, Colorado, Maryland, Michigan, Minnesota, Virginia, Wisconsin and 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 the configuration of storage, and allows the site to safely hold all the fuel used during its 40 year expected life. This modification was completed in April of 2002.

20

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Description of the Davis-Besse Site The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the south-western shore of Lake Erie, just north of the Toussaint River. The site lies north and east of Ohio 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).

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

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

The Davis-Besse site is mainly comprised of marshland, with a small portion consisting of farm-land. The marshes are part of a valuable ecological resource, providing a breeding ground for a variety of wildlife, and a refuge for migratory birds. The site includes a tract known as Navarre Marsh, which was acquired from the U.S. Bureau of Sport Fisheries and Wildlife, Department of the Interior. In 1971, Toledo Edison purchased the 188-acre Toussaint River Marsh. The Tous-saint River Marsh is contiguous with the 610-acre Navarre Marsh section of the Ottawa National Wildlife Refuge.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report The immediate area near Davis-Besse is sparsely populated. The year 2000 Census listed the population of Ottawa County at 40,985. 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 ma-jor resort area of the county is farther east, around Port Clinton, Lakeside, and the Bass Islar.ds.

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 2005 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, Wash-ington, 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

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental 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. Sit~e Environmental Report, Fernald Environmental Management Project, United States De-partment of Energy (June 1993).

25. " IExposure 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 Environmental Monitoring Program Davis-Besse Nuclear Power Station 2005 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 pre-operatlional 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 operational in 1977, the operational surveillance program continued to measure radiation and radioa tivity in the surrounding areas.

A variety of environmental samples are collected as part of the REMP at Davis-Besse. The se-lectior 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 REMP 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 de:ailed summary of the analyses performed during this reporting period, is also provided.

Pre-operational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental moni-toring prior to constructing the facility. This pre-operational 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 operations begin. Ra-diochemical analyses performed on samples should include nuclides that are expected to be re-leased during normal facility operations, as well as typical fallout radionuclides and natural background radioactivity. All environmental media with a potential to be affected by facility op-eration., as well as those media directly in the critical pathways, should be sampled during the pre-operational phase of the environmental surveillance program.

The pre-operational 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-26

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report ner, data can be compared in a variety of ways (for example: from year to year, location to loca-tion, etc.) in order to detect any radiological impact the facility has on the surrounding environ-ment. Data collection during the pre-operational phase should be planned to provide a comprehensive database for evaluating any future changes in the environment surrounding the nuclear facility.

Davis-Besse began its pre-operational environmental surveillance program five years before the Station began producing power for commercial use in 1977. Data accumulated during that time provides an extensive database from which Station personnel are able to identify trends in the radiological characteristics of the local environment. The environmental surveillance program at Davis-Besse will continue after the Station has reached the end of its economically useful 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 27

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report requiring analytical contractor laboratories to perform in-house spiked sample analyses Quality Assessment audits, and inspections of the Davis-Besse REMP are performed by the FirstEnergy Nuclear Operating Company QA Department and the NRC. In addition, the Ohio Department of Health (ODH) also performs independent environmental monitoring in the vicin-ity of Davis-Besse. The types of samples collected and the sampling locations used by the ODH was incorporated in Davis-Besse's REMP, and the analytical results from their program can be compared to Davis-Besse's. This practice of comparing results from identical samples, which are collected and analyzed by different parties, provides a valuable tool to verify the quality of the laboratories' analytical procedures and data generated.

In 19F7, environmental sampling personnel at Davis-Besse incorporated their own QA program into the REMP. Duplicate samples, called quality control samples, were collected at several lo-cations. These duplicate samples were assigned different identification numbers than the num-bers assigned to the routine samples. This ensured that the analytical laboratory would not know the samples were identical. The laboratory results from analysis of the quality control samples and the routine samples could then be compared for agreement. Quality control sampling has been integrated into the program and has become an important part of the REMP since 1987.

Quality control sampling locations are changed frequently in order to duplicate as many sampling locations as possible, and to ensure the contractor laboratory has no way of correctly paiiing a quality control sample with its routine sample counterpart.

Program Description The Radiological Environmental Monitoring Program (REMP) at Davis-Besse is conducted in 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 sample type and nature of the radionuclides of interest. Environmental samples collected by Davis-Besse personnel are divided into four general types:

• atmospheric -- including samples of airborne particulate 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.

REM!' 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 2005 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 pre-operational 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 2005. 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

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 2: Sample Codes and Collection Frequencies Sample Collection Sample Type Code Frequency Airborne Particulate AP Weekly Airborne Iodine AI Weekly Thermoluminescent TLD Quarterly, Annually Dosimeter Milk MIL Monthly (semi-monthly during grazing season)

Groundwater WW Quarterly Broadleaf Vegetation BLV Monthly (when available)

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

Fish FIS Annually Shoreline Sediment SED Semiannually Soil So' Annually Wildlife Feed WFE Annually Meat-Wild WME Annually Fruit FRU Annually 30

Davis-Besse Nuclear Power Station 2005 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 10 529 1l Airborne Radioiodine C/W 10 529 Terrestrial Milk (Jan.-Dec.) G/M 1 12 0 Groundwater GIQ*** 2 11 1 Wild Meat GIA 2 2 0 Broadleaf Vegetation G/M 3 11 0 Fruit G/A 3 3 0 Soil G/A 10 10 0 Animal/Wildlife Feed G/A 3 3 0 Aquatic Treated Comp/WM 4 212 0 Surface Water G/WM*** 1 53 0 Untreated G/WM*** 3 159 0 Surface Water Comp/WM 3 159 0 G/M 5 35 0 Fish (3 species) G/A 2 6 0 Shoreline Sediments G/SA 5 10 0 Direct Radiation Thermoluminescent C/Q*** 89 354 2 Dosimeters (TLD) C/A*** 89 86 3

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

• • Frequency of Collection: WM = Weekly composite Monthly; W = Weekly, M = Monthly; Q = Quarterly; SA =

Semiannually; A = Annually

• • • Includes quality control location. SWU and SWT QC included in weekly grab sample/composited monthly 31

Davis-Besse Nuclear Power Station 2005 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 sample. Beta radiation may be released by many different radionuclides. Since beta decay gives a continuous energy spectrum rather than the discrete lines or "peaks" associated with gamma 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 radionuclides. Gross beta analy-sis merely acts as a tool to identify samples that may require further analysis.

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

Gammra spectral analysis identifies each gamma emitting radionuclide present in the sample, and the amount of each nuclide present. Each radionuclide has a very specific "fingerprint" that al-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 :ow 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 pool of the biosphere. In other words, it accumulates in living organisms, where it is stored in the bone tissue. The princi-pal 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 -hat the radioactivity is so low that it cannot be accurately measured with any degree of confidence by a particular method for an individual analysis.

32

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples Sample Type Analyses Performed Atmospheric Monitoring Airborne Particulate Gross Beta Gamma Spectroscopy Strontium-89 Strontium-90 Airborne Radioiodine Iodine-l 31 Terrestrial Monitoring Milk Gamma Spectroscopy Iodine-13 1 Strontium-89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectroscopy Tritium Strontium-89 Strontium-90 Broadleaf Vegetation Gamma Spectroscopy and Fruits Iodine-131 Strontium-89 Strontium-90 Wildlife Feed Gamma Spectroscopy Soil Gamma Spectroscopy Wild Animal Meat Gamma Spectroscopy 33

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP SampleS (continued)

Sample Type Analyses Performed Aquatic monitoring Untreated Surface Water Gross Beta Gamma Spectroscopy Tritium Strontium-89 Strontium-90 Treated Surface Water Gross Beta Gamma Spectroscopy Tritium Strontium-89 Strontium-90 Iodine-i 31 Fish Gross Beta Gamma Spectroscopy Shoreline Sediment Gamma Spectroscopy 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 pre-operational 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

Davis-Besse Nuclear Power Station 2005 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 Chernobyl 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 picocuries per cubic meter) from the nuclear accident at Chemobyl.

Terrestrial Monitoring:

• Groundwater: Tritium was not detected above the lower limit of detection during 2005.

• Milk: Iodine-1 31 from nuclear weapons testing fallout was detected in 1976 and 1977 at concentrations of 1.36 and 23.9 picocuries/liter respectively. In 1986, con-centrations of 8.5 picocuries/liter were detected from the nuclear accident at Cherno-byl. No Iodine-131 detected has been attributable to the operation of Davis-Besse.

• Wild Meat: Only naturally-occurring Potassium-40 and very low Cesium-137 from fallout activity has been detected in meat samples. Potassium-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 weapons testing.

• Broadleaf Vegetation and Fruits: Only naturally-occurring radioactive material 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.

• Animalffilildlife 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 2005, tritium was detected at sample indi-cator location T-3 at 5.29E-07 uCi/mL, and again at sample location T-134 in untreated lake water, and is likely attributable to the operation of the Davis-Besse Nuclear Power Station.

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

• Shoreline Sediments: Only natural background radiation, material from nuclear test-ing and the 1986 nuclear accident at Chernobyl have been detected.

35

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Direct Radiation Monitoring

• Thermoluminescent Dosimeters (TLDs): The annual average gamma dose rates for the current reporting period recorded by TLDs ranged from 38.2 to 74.1 millirem per year at Control locations and between 32.2 and 80.9 millirem per year at Indicator lo-cations. No increase above natural background radiation attributable to the operation of Davis-Besse has been observed.

200.5 Program Anomalies One ODCM-required air sample was missed during 2005 due to an equipment malfunction. An-other sample was substituted in place of the missed sample, and the intent of the ODCM was met. Provided below is a description of all sample collection irregularities:

Well Water sample T-225 was not collected during the first quarter of 2005, since the residents at the sample location are seasonal, and the sample pump was not energized. Well Water samples are no longer required, since all area residents are using the Carroll Township domestic water system. Well Water samples will still be collected as enhancements when they are available.

On 7/6/06, Broadleaf Vegetation (BLV) was missed at ODCM-required location T-17, resulting from a change in property ownership and the absence of a garden at this location. An alternate sample, T-227, was collected to satisfy the ODCM requirements.

On 7/13/05, both the quarterly and annual TLDs were missing at location T-207. The TLD cage may have been disturbed during grass mowing operations along the marsh dike. The quarterly TLD was replaced at this location, which is not ODCM-required.

On 7/26/05, ODCM-required air sample at T-1 was missed due to a sample pump malfunction. It is suspected that the sampler failed to restart after weekly maintenance was performed on the temporary generator supplying power to marsh sampling equipment. Another sample was substi-tuted:hn place of this one to meet ODCM requirements.

On 9/14/05, air sample pump T-1 was found shut down due to a blown fuse. It is suspected that weekly maintenance on a temporary generator supplying power to the sampler caused the prob-lem. .A sufficient volume of sample had been collected before the blown fuse had occurred.

On I C/4/05 air sample pump T-I was found seized up with a blown fuse. The pump was re-placed with a new pump. Once again, the temporary generator was suspected as the cause. The sample size that had been collected was sufficient.

During annual collection of TLDs on 1/4/06, ODCM-required TLD T-41 was missing, as well as enhancement TLDs T-81 and T-83. Vandalism is suspected. TLD T-142, which is in the same sector as T-41, was substituted in its place, thus satisfying ODCM requirements.

Note: There were no abnormal releases during any of the above-listed anomalies.

36

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Atmospheric Monitoring "C 1, tA I ',;

". f..

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.

37

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report 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-1, 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-1 1), 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 comnined (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-centralion of 0.025 pCi/M3 and 0.025 pCi/M3 , respectively. Beryllium-7 was the only gEmma emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites.

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 and Strontium-90 were not detected above their LLDs. These results show no ad-verse echange in radioactivity in air samples attributable to the operation of the Davis-Besse Nu-clear Power Station in 2005.

Airborne Iodine-1 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 to the laboratory for gamma analysis. There was no detectable iodine-131 above the LLD of 0.07 pCi/M3 .

2005 AIr Gross Beta 0.04 0.035 0.03 '0/

0.025 .- Z \ /

V c) 0.02 0.015 0.01 0.005 0 .1 January March May July September November date

-Control -U-Indicator Figure 10. Concentrations of beta-emitting radionuclides in airborne particulate samples were nearly identical at indicator and control locations.

38

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 5: Air Monitoring 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 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, 20.7 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 2005 Annual Radiological Environmental Operating Report Terrestrial Monitoring The collection and analysis of groundwater, milk, meat, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. Animal and wildlife feed samples provide additional information on radionuclides that may be present in the food chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere.

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

• tritium, present as a result of the interaction of cosmic radiation with the upper 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 environment, (for example, in surface soils) as a result of fallout from nu-clear weapons testing and routine releases from nuclear facilities

• Potassium-40, a naturally occurring radionuclide normally found through-out 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 facilities 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 pre-operational 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

Davis-Besse Nuclear Power Station 2005 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 indica:or sites.

The 2005 milk samples were analyzed for Strontium-89, Strontium-90, Iodine-131, other gamma-emitting radionuclides, stable Calcium and Potassium. A total of 12 milk samples were collected in 2005. Strontium-89 was not detected above its LLD. The annual average concentra-tion of Strontium-90 was 0.87 pCi/l. For all sample sites, the annual average concentration was similar to those measured in the previous years.

Iodine-131 was not detected in any of the milk samples above the LLD of 0.4 pCi/l. The concen-trations of Barium-140 and Cesium-137 were below their respective LLDs in all sample; col-lected.

Since the chemistries of Calcium and Strontium are similar, as are Potassium and Cesium, organ-isms te nd 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/I) 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, tritiu::n 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.

During the fall of 1998, the Carroll Township Water Plant began operation and offered residents a reliable source of high-quality, inexpensive drinking water. This facility has replaced all of the 44

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report drinking water wells within five miles of Davis-Besse, as verified by the Ottawa County Health Department, and the indicator groundwater sampling was discontinued for a year. During the third quarter of 2001, a beach well was located within five miles of the Station. Although the residents are seasonal, and only use the township system for their drinking water needs, this well was added to our sampling program as an Indicator location during the fall of 2001. The gross beta averaged 5.6 pCi/l at the Indicator site. Control location is still sampled quarterly at T-27, and the gross beta averaged 4.5 pCi/l gross beta for the year 2005. Groundwater samples did not appear to be affected by the operation of the Davis-Besse Nuclear Power Station.

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45

Davis-Besse Nuclear Power Station 2005 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 airborne radioactivity (nuclear weapons fallout or airborne releases from nuclear facilities), or from irrigation water drawn from lake wa-ter wlich receives 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 orchards in the vicinity of Davis-Besse.

In 2005, 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 dur-ing the growing season and consisted of cabbage. The fruit that was collected was apples. All samples were analyzed for gamma-emitting radionuclides, Strontium-89, Strontium-90, and Io-dine-131.

Iodine- 131 was not detected above the LLD of 0.023 pCi/g (wet) in any broadleaf vegetation nor above the LLD of 0.025 pCi/g (wet) in fruit samples. The only gamma-emitting radionuclide de-tected in the fruit and broadleaf vegetation samples was Potassium-40, which is naturally occur-ring. In broadleaf vegetation, Strontium-90 (Sr-90) was detected at indicator location T-19 at 0.003 pCi/g (wet) and 0.002 pCi/g (wet) at the control location. In fruit samples, Sr-90 was de-tected at 0.001 pCi/g (wet) at the control location and was not detected at the indicator sites.

Resuls of broadleaf vegetation and fruit samples were similar to results observed in previous years. Operation of Davis-Besse had no observable adverse radiological effect on the surround-ing environment in 2005.

46

Davis-Besse Nuclear Power Station 2005 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-19 I L. Bowyer Jr., 1.0 mile W of Station T-25 I Witt Farm, 1.6 miles S of Station T-37 C Bench Farm, 13.0 miles SW of Station T-209 C Roving Control Fruit location T-227 I Roving BLV location I = indicator, C = control AnimalAllildlife Feed Samples Vegetation consumed by wildlife can provide an indication of airborne radionuclides deposited in the vicinity of the Station. Analyses of wildlife feed samples can also provide data for deter-mining radionuclide concentration in the food chain. 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 Beryl-lium-7, and fallout radionuclides such as Strontium 89 and Strontium 90 from nuclear weapons testing may be present in the feed samples.

Wildlife feed was at three locations (T-31, T-32 and T-198), and consisted of the edible portions of cattails. Samples were analyzed for gamma-emitting radionuclides. Naturally occurring Potassium-40 was detected in all samples. Beryllium-7 was detected at both control and indicator locations at 0.78 and 1.38 pCi/g wet, respectively. All other ra-dionuclides were below their respective LLDs. These samples indicate that the operation of Davis-Besse had no observable adverse effects on the surrounding environment.

47

Davis-Besse Nuclear Power Station 2005 Annual Radiological Enviromnental 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, 7.0 miles W of station in 2004 T-198 I Toussaint Creek Wildlife Area, 4.0 miles WSW of the Station I = indicator C = control Wild Meat Samples Sampling of wild meat provides information on environmental radionuclide concentrations that humans may be exposed to through an ingestion pathway. The principle pathways for radionu-clide 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 on an annual basis. Wild animals commonly consumed by residents in the vicinity of Davis-Besse include waterfowl, deer, rabbits and muskrats. Analy-ses 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 conclusions from radionuclide concentrations in the local environment or in a species as a whole.

Meat samples were taken in 2005 as follows:

• Wild Meat: Muskrat samples were collected on Station property and showed only naturally occurring activity.

48

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 10: Wild Meat Locations Sample Location Type of Number Location Location Description T-3 1 I Onsite roving location T-210 C Roving offsite location (5.5 mi. WNW of the Station in 2005)

I = indicator C = control Soil Samples Soil samples are generally collected once 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 represen-tative of the actual deposition in the area. Ideally, there should be little or no vegetation present, 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 Be-ryllium-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) and Ce-sium-137 (Cs-137).

Soil was collected at ten sites in May of 2005. The indicator locations included T-1, T-2, T-3, T-4, T-7, and T-8. The control locations were T-9, T-11, T-12, and T-27. All soil samples were analyzed for gamma-emitting radionuclides. The only gamma emitter detected (in addition to naturally occurring Be-7 and K-40) was Cs-137. Cs-137 was found in Indicator and Control lo-cations at average concentrations of 0.13 pCi/g (dry) and 0.16 pCi/g (dry), respectively. The con-centrations were similar to that observed in previous years (Figure 15).

49

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50

Davis-Besse Nuclear Power Station 2005 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-1I C Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant, 20.7 miles WNW of Station T-27 C Crane Creek State Park, 5.3 miles \VNW of Station I = indicator C = control 51

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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 ra-dionuclides, 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-l1 and T-12). These locations include the water treatment facilities for Car-roll 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 2.0 and 1.7 pCi/l, respectively. These results are similar to previous years shown in Figure 19. Tritium 55

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report was not detected above the LLD of 330 pCi/i during 2005. Strontium-89 was not detected above the LLD of 1.1I pCi/I. Strontium-90 activity was not detected above its LLD of 0.8 pCi/i. These results are similar to those of previous years and indicate no adverse impact on the environmrent resulting from the operation of Davis-Besse during 2005.

Each month, weekly quality control samples were collected at different locations. The resuIlts 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 1.8 pCi/i.

There was good agreement between the routine and QC locations.

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56

Davis-Besse Nuclear Power Station 2005 Annual Radiological Enviromnental Operating Report Table 12: Treated Surface Water Locations Sample Location Type of Number Location Location Description T-l1 C Port Clinton Water Treatment Plant 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant 20.7 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 57

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report 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.

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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 months of high lake recreational activ-ity, such as boating, fishing, and swimming. These samples are obtained monthly in areas along 58

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmnental Operating Report 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 that are composited weekly, the beta emitting radionuclides had an average concentration of 2.3 pCi/L at indicator locations during 2005. Con-trol locations averaged 2.2 pCi/L during this period. The average concentration of beta-emitting radionuclides in monthly summer lakewater samples was 1.8 pCi/L at indicator and 2.2 pCi/L at control locations.

On 8/16/05, tritium was detected at a concentration of 976 pCi/l at untreated surface water indi-cator site T-134, and 529 pCi/ml at indicator site T-3 on 11/29/05. It is likely that this is attribut-able to the operation of the Plant. Cesium-137 was not detectable in samples of untreated water above the LLD. Each month, weekly quality control samples were collected at different loca-tions. The results of the analyses from the quality control samples were consistent with the rou-tine samples.

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_ _ _ _ _ _ ON N N CN ON ON INDICATOR -u-CONTROLl Figure 20: The average concentration of beta-emitting radionuclides in untreated water was similar between control and indicator locations. This demonstrates that Davis-Besse had no significant radiological impact on the surround-ing environment.

59

Davis-Besse Nuclear Power Station 2005 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 I C Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant, sample taken from intake crib, 12.6 miles NW of Station T-22A I Carroll Township Water Plant, State Route 2, 2.1 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-158 C Lake Erie, 10.0 miles WNW of Station T-162 C Lake Erie, 5.4 miles SE of Station I = indizator, C = control 60

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Shoreline Sediment The sampling of shoreline sediments can provide an indication of the accumulation of insoluble radionuclides which could lead to internal exposure to humans through the ingestion of fish, through re-suspension into drinking water supplies, or as an external radiation source from shore-line exposure to fishermen and swimmers.

Samples of deposited sediments in water along the shore were collected at various times from three indicator sites (T-3, T-4, and T-132) and one control location (T-27), and were analyzed for gamrnma-emitting radionuclides. Naturally occurring Potassium-40 was detected at both control and indicator 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 I Lake Erie, 1.0 miles E of Station I = indicator C = control 61

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Fish Sample Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondar-ily to serve as indicators of radioactivity in the aquatic ecosystem. The principal nuclide:3 that 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 predatbr), 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 liquid 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 of being a popular sport fish and white perch or white bass are collected because their importance as a commercial fish. Carp are collected be-cause hey are bottom feeders where contaminants may settle.

The average concentration of beta-emitting radionuclides in fish was similar for indicator and control locations (4.40 pCi/g and 4.06 pCi/g wet weight, respectively). No other gamma emitters were detected above their respective LLDs.

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62

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental 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 2005 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 Sulfate:Dysprosium (CaSO4 :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 (77 indicator and 12 control locations). TLDs are collected and replaced on a quarterly and annual basis. Nineteen QC TLDs are also collected on this schedule. There are a total of 214 TLDs in the environment surrounding Davis-Besse. By col-lecting them 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 92%

of the annual TLDs placed in the field were retrieved and evaluated during the current reporting period.

In 2005, the average dose equivalent for quarterly TLDs at indicator locations was 14.1 mrem/91 days, and for control locations was 14.9 mrem/91 days. The average dose equiva-lent for annual TLDs in 2005 was 54.9 mrem/365 days at indicator locations and 57.4 mrem/365 days for control locations.

Quality Control TLDs Duplicate TLDs have been placed at 18 sites. These TLDs are placed in the field at the same time and location as some of the routine TLDs, but are assigned quality control site numbers.

This allows us to take several measurements at the location without the laboratory being aware that they are the same. A comparison of the quality control and routine results provides a method to check the accuracy of the measurements. The average dose equivalent of indicator quality control TLDs averaged 12.9 mrem/91 days while the quality control TLDs at control locations yielded an average dose equivalent of 14.7 mrem/91 days.

67

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Gamma Dose for Environmental TLDs 1973-2005 24 II 22 20 18 16 I

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-Indicator -Ucontrol Figure 25: The similarity between indicator and control results demonstrated that the operation of Davis-Besst, has not caused any abnormal gamma dose.

68

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations Sample Location Type of Number Location Location Description T-1 I Site boundary, 0.6 miles ENE of Staticon T-2 I Site boundary, 0.9 miles E of Station T-3 I Site boundary, 1.4 miles ESE of Static on T-4 I Site boundary, 0.8 miles S of Station T-5 I Site boundary, 0.5 miles W of Station T-6 I Site boundary, 0.5 miles NNE of StatiiDn T-7 I Sand Beach entrance, 0.9 miles NW ocf Statiom 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, 20.7 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 T-39 I Site boundary 1.2 miles ENE of Station T-40 I Site boundary, 0.7 miles SE of Station T-41 I Site boundary, 0.6 miles SSE of Station T-42 I Site boundary, 0.8 miles SW of Station 69

Davis-Besse Nuclear Power Station 2005 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 2005 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 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 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

Davis-Besse Nuclear Power Station 2005 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-111 C Toussaint North Road, 8.3 miles WSW of Station T-112 I Thompson Road, 1.5 miles SSW of Station T-113 QC Quality Control Site T-114 QC Quality Control Site T-115 QC Quality Control Site T-116 QC Quality Control Site T-117 QC Quality Control Site T-118 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 T-124 C Church and Walnut Street, Oak Harbor, 6.5 miles SSW of Station T-125 I Behlman and Bier Roads, 4.4 miles SSW of Stiation T-126 I Camp Perry Western and Toussaint South Road, 3.7 miles S of Station T-127 I Camp Perry Western and Rymers Road, 4.0 miles SSE of Station 72

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location Location Description T-128 I Erie Industrial Park, Port Clinton Road, 4.0 miles SE of Station T-142 I Site Boundary, 0.8 miles SSE of Station T-150 I Humphrey and Hollywood Road, 2.1 miles NW of Station T-151 I State Route 2 and Humphrey Road, 1.8 miles WNW of Station T-153 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

Davis-Besse Nuclear Power Station 2005 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

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Davis-Besse Nuclear Power Station 2005 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-tions measured at indicator locations were compared with concentrations measured at control lo-cations in previous operational studies and in the pre-operational surveillance program. These comparisons indicate normal concentrations of radioactivity in all environmental samples col-lected in 2005. Davis-Besse's operation in 2005 indicated no observable adverse radiological impac: on the residents and environment surrounding the station. The results of the sample analyses performed during the period of January through December 2005 are summarized in Ap-pendix D of this report.

References

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

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

3. "Exposure of the Population in the United States and Canada from Natural Background Ra-diation," Report No.94, National Council on Radiation Protection and Measurement, Wash-ington, D.C. (December 1987).

4. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy Instal-lations," DOE/EP-0023, Department of Energy, Washington, D.C. (July 1981).

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

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

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 I (1988).

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

American National Standards Institute, Inc., ANSI-N45-1975, New York, New York (I 975).

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

78

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report

10. "Radiological Assessment: Predicting the Transport, Bioaccumulation and Uptake by Man of Radionuclides Released to the Environment," Report No.76, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1984).

11. Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," US NRC (April 1975).

12. Regulatory Guide 4.13, "Performance, Testing, and Procedural Specifications for Thermolu-minescent Dosimetry: Environmental Applications," US NRC (July 1977).

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

14. Regulatory Guide 0475, "Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities," US NRC (September 1978).

15. "Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, Part 20 (1993).

16. Teledyne Isotopes Midwest Laboratory, "Operational Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No.1, Oak Harbor, OH," Annual Report, Parts I and II (1977 through 1990).

17. Teledyne Isotopes Midwest Laboratory, "Final Monthly Progress Report to Toledo Edison Company", (I991-1999).

18. Environmental, Inc. Midwest Laboratory, "Final Report to FirstEnergy Corporation", (2000-2005)

19. Teledyne Isotopes Midwest Laboratory, "Pre-operational Environmental Radiological Moni-toring for the Davis-Besse Power Station Unit No. 1", Oak Harbor, OH (1972-1977).

20. Toledo Edison Company, "Davis-Besse: Nuclear Energy for Northern Ohio."

21. Toledo Edison Company, "Davis-Besse Nuclear Power Station, Unit No. 1, Radiological Effluent Technical Specifications", Volume 1, Appendix A to License No. NPF-3.

22. Toledo Edison Company, "Final Environmental Statement -Related to the Construction of Davis-Besse Nuclear Power Station," Docket #50-346 (1987).

23. Toledo Edison Company, "Performance Specifications for Radiological Environmental Monitoring Program," S-72N.

24. Davis-Besse Nuclear Power Station, "Radiological Environmental Monitoring Program,"

DB-CN-00015.

79

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report

25. Davis-Besse Nuclear Power Station, "Radiological Environmental Monitoring Quarterly, Semiannual, and Annual Sampling", DB-CN-03004.

26. Davis-Besse Nuclear Power Station, "Radiological Monitoring Weekly, Semimonthly, and Monthly Sampling," DB-CN-03005.

27. Davis-Besse Nuclear Power Station, "REMP Enhancement Sampling", DB-CN-I 0101.

28. Toledo Edison Company, "Updated Safety Analysis for the Offsite Radiological Monitoring Program", USAR 11.6, Revision 14, (1992).

29. Davis-Besse Nuclear Power Station, "Annual Radiological Environmental Operating Report Preparation and Submittal", DB-CN-00014.

30. Davis-Besse Nuclear Power Station, "Preparation of Radioactive Effluent Release Report",

DB-CN-00012.

31. Davis-Besse Nuclear Power Station, "Offsite Dose Calculation Manual".

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

80

.~. ~

A_1 I-.

Radioactive Effluent Release Report

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environrnental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2005 Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ioniz-ing radiation were recognized and efforts were made to establish radiation protection standards.

The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recommendations have been given legislative authority by being published in the Code of Federal Regulations by the Nuclear Regulatory Commission.

The main objective in the control of radiation is to ensure that any dose is kept not only within regulatory limits, but kept as low as reasonably achievable (ALARA). The ALARA principle applies to reducing radiation dose both to the individual working at Davis-Besse and to the gen-eral public. "Reasonably achievable" means that exposure reduction is based on sound economic decisions and operating practices. By practicing ALARA, Davis-Besse minimizes health risk and environmental detriment and ensures that doses are maintained well below regulatory limits.

Sources of Radioactivity Released During the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces, which have been activated, are pres nt in the primary coolant water. The three types of radioactive material released are noble gases, Io-dine aid particulates, and tritium.

The noble gas fission products in the primary coolant are given off as a gas when the coolant is depressurized. These gases are then collected by a system designed for gas collection and stored for racioactive decay prior to release.

Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primary coolant system. These liquids are collected through a series of floor and equipment drains and sumps. All liquids of this nature are monitored and processed, if reces-sary, prior to release.

Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as Xenon and Krypton. Noble gases are biologically and chemically inert.

They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an external source of radiation exposure to the body. Xenon-133 and Xenon-135, with 81

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report half-lives of approximately five days and nine hours, respectively, are the major radioactive no-ble gases released. They are readily dispersed in the atmosphere.

Iodine and Particulates Annual releases of radioisotopes of Iodine, and those particulates with half-lives greater than 8 days, in gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing sys-tems, minimize their discharge. The predominant radioiodine released is Iodine-131 with a half-life of approximately eight days. The main contribution of radioactive Iodine to human dose is to the thyroid gland, where the body concentrates Iodine.

The principal radioactive particulates released are fission products (e.g., Cesium-134 and Ce-sium-137) and activation products (e.g., Cobalt-58 and Cobalt-60). Radioactive Cesium and Co-balt contribute to internal radiation exposure of tissues such as the muscle, liver, and intestines.

These particulates are also a source of external radiation exposure if deposited on the ground.

Tritium Tritium, a radioactive isotope of Hydrogen, is the predominant radionuclide in liquid effluents. It is also present in gaseous effluents. Tritium is produced in the reactor coolant as a result of neu-tron interaction with deuterium (also a Hydrogen isotope) present in the water and with the Bo-ron in the primary coolant. When tritium, in the form of water or water vapor, is ingested or in-haled it is dispersed throughout the body until eliminated.

Processing and Monitoring Effluents are strictly controlled to ensure radioactivity released to the environment is minimal and does not exceed regulatory limits. Effluent control includes the operation of monitoring sys-tems, in-plant and environmental sampling and analyses programs, quality assurance programs for effluent and environmental programs, and procedures covering all aspects of effluent and en-vironmental monitoring.

The radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gaseous wastes that contain radioactivity. For example, the Waste Gas Decay Tanks allow radioactivity in gases to decay prior to release via the station vent.

Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits.

These instruments provide a continuous indication of the radioactivity present. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure the limits will not be exceeded. If a monitor alarms, a release from a tank is automati-cally stopped.

All wastes are sampled prior to release and analyzed in a laboratory to identify the specific con-centrations of radionuclides being released. Sampling and analysis provide a more sensitive and precise method of determining effluent composition than with monitoring instruments alone.

82

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report A met orological tower is located in the southwest sector of the Station. It is linked to computers that record the meteorological data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public.

Beyond the plant, devices maintained in conjunction with the Radiological Environmental Moni-toring Program continuously sample the air in the surrounding environment. Frequent samples of other environmental media, such as water and vegetation, are also taken to determi.ne if buildup of deposited radioactive material has occurred in the area.

Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to ra-dioactive material. The major pathways of concern are those which could cause the highest cal-culated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the envi-ronment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An an-nual average on the water flow, wind speed, and wind direction are used to evaluate how the ra-dionuclides will be distributed in an area for gaseous or liquid releases. An important factor in evaluating the exposure pathways is the use of the environment. Many factors are considered such as dietary intake of residents, recreational use of the area, and the locations of homes and farms in the area.

The external and internal exposure pathways considered are shown in Figure 29. The release of radioactive gaseous effluents involves pathways such as external whole body exposure, deposi-tion of radioactive material on plants, deposition on soil, inhalation by animals destined for hu-man consumption, and inhalation by humans. The release of radioactive material in liquid efflu-ents involves pathways such as drinking water, fish consumption, and direct exposure from the lake al: the shoreline while swimming.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Figure 29: The exposure pathways shown here are monitored through the Radiological Environmental Monitoring Program (REMP) and are considered when calculating doses to the public.

Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure route that will provide, for a specific radionu-clide, the greatest dose to a population, or to a specific group of the population called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, or other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ.

Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body exposure to ra-diation involves the exposure of all organs. Most background exposures are of this form. Both non-radioactive and radioactive elements can enter the body through inhalation or ingestion.

When they do, they are usually not distributed evenly. For example, Iodine concentrates in the thyroid gland, Cesium collects in muscle and liver tissue, and Strontium collects in bone tissue.

The total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the amount of time that the radionuclide remains in the organ. Some ra-dionuclides remain for very short times due to their rapid radioactive decay and/or elimination rate from the body, while other radionuclides may remain in the body for longer periods of time.

The dose to the general public in the area surrounding Davis-Besse is calculated for each liquid or gaseous release. The dose due to radioactive material released in gaseous effluents is calcu-84

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report lated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the average weather conditions at the time of the release, the locations of expo-sure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inha-lation: food consumption). The dose due to radioactive material released in liquid effluents is calculated by using factors such as the total volume of the liquid released, the total volume of di-lution water (near field dilution), and usage factors, such as water and fish consumption, and shoreline and swimming factors. These calculations produce a conservative estimation of the dose.

Results The Radioactive Effluent Release Report is a detailed listing of radioactivity released from the Davis.-Besse Nuclear Power Station during the period from January 1 through December 31, 2005.

• Summation of the quantities of radioactive material released in gaseous and liquid effluents (Tables 17-21)

• Summation of the quantities of radioactive material contained in solid waste packaged. and shipped for offsite disposal at federally approved sites (Table 22)

• A listing of all radioactive effluent monitoring instrumentation required by the Offsite Dose Calculation Manual, but which were inoperable for more than 30 days During this reporting period, the estimated maximum individual offsite dose due to radioactivity released in effluent was:

Liquid Effluents:

• 4.23E-03 mrem, maximum individual whole body

• 5.64E-03 mrem, maximum significant organ dose (liver)

Gaseous Effluents:

Noble Gas:

• 1.37E-04 mrem, whole body

• 6.65E-04 mrem, skin Iodine - 131, Tritium, and Particulates with Half-lives greater than 8 Days:

• 6.64E-04 mrem, whole body dose

• 8.13E-04 mrem, significant organ dose (thyroid)

These doses are a small fraction of the limits set by the NRC in the Davis-Besse ODCM.

85

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Additional normal release pathways from the secondary system exist. For gaseous effluents, these pathways include the Auxiliary Feed Pump Turbines exhaust, the main steam safety valve system and the atmospheric vent valve system, steam packing exhaust and main feed water. For liquid effluents, the additional pathways include the Turbine Building drains via the settling ba-sins. Releases via these pathways are included in the normal release tables in this report.

Regulatory Limits Gaseous Effluents In accordance with Offsite Dose Calculation Manual, dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

Noble gases:

• Released at a rate equal to or less than 500 mrem TEDE per year.

. Released at a rate such that the total dose to the skin will be less than or equal to 3000 mrem in a year.

Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:

• Released at a rate such that the total dose to any organ will be less than or equal to 1500 mrem in a year.

In accordance with 10CFR50, Appendix I, Sec. IIB. 1, air dose due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

• Less than or equal to 10 mrad total for gamma radiation and less than or equal to 20 mrad total for beta radiation in any calendar year.

In accordance with IOCFR50, Appendix I, Sec. IIC, dose to a member of the public from Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gase-ous effluents released to areas at and beyond the site boundary shall be limited to the following:

• Less than or equal to 15 total mrem to any organ in any calendar year.

Liquid Effluents In accordance with 10CFR50, Appendix I, Sec IIA, the dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to accumulated doses of:

• Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ in any calendar year.

86

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Effluent Concentration Limits The Effluent Concentration Limits (ECs) for gaseous and liquid effluents at and beyond the site boundary are listed in I OCFR20, Appendix B, Table II, Columns I and 2, with the most restric-tive EC being used in all cases. For dissolved and entrained gases in liquids, the EC of 2.OE-04 uCi/ml is applied. This EC is based on the Xe-135 DAC of IE-05 uCi/ml of air (submersion dose) converted to an equivalent concentration in water as discussed in the International 'Coin-mission on Radiological Protection (ICRP), Publication 2.

Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and a-tiva-tion products to less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radio-activity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable.

Measurements of Total Activity Fission and Activation Gases:

These gases, excluding tritium, are collected in Marinelli beakers specially modified for gas sampripng, in steel flasks, or in glass vials, and are counted on a Germanium detector for principal gamma emitters. Radionuclides detected are quantified via gamma spectroscopy.

Tritiuin gas is collected using a bubbler apparatus and counted by liquid scintillation.

Iodine Iodine is collected on a charcoal cartridge filter and counted on a germanium detector. Specific quantification of each iodine radionuclide is performed using gamma spectroscopy.

Particulates Particulates are collected on filter paper and counted on a germanium detector. Specific quantifi-cation of each radionuclide present on the filter paper is performed by using gamma spectros-copy.

Liquid Effluents Liquid effluents are collected in a Marinelli beaker and counted on a germanium detector. Quan-tification of each gamma-emitting radionuclide present in liquid samples is via gamma spectros-copy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system.

87

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Batch Releases Liquid from 1/1/05 through 12/31/05

1. Number of batch releases: 41

2. Total time period for the batch releases: 71.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

3. Maximum time period for a batch release: 202 minutes

4. Minimum time period for a batch release: 84 minutes

5. Average time period for a batch release: 104 minutes Gaseous from 1/1/05 through 12/31/05

1. Number of batch releases: 16

2. Total time period for the batch releases: 225.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />

3. Maximum time period for a batch release: 1882 minutes

4. Minimum time period for a batch release: 177 minutes

5. Average time period for batch release: 846 minutes Abnormal Releases On September 11, 2005, approximately 400 gallons of condensate from the Auxiliary Boiler was drained to the onsite Training Center Pond, containing 6.4E-05 Curies of Tritium. The release had a calculated whole body dose of 1.7E-07 millirem, which is significantly lower than the an-nual ODCM limit of 3 millirem.

Percent of ODCM Release Limits The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent of limits, for January 1, 2005 through December 31, 2005.

IPERCENT OF I SPECIFICATION IANNUAL DOSE _ LIMIT P CLIMIT Report Period: January 1, 2005- December 31, 2005 (gaseous)

_ Noble gases (gamma) 1.25E-04 mnrad I 10 mrad 1.25E-03

_ Noble gases (beta) 6.05E-04 mrad 20 mrad 3.03E-03 I-131, tritium and particulates 8.13E-04 mrem 15 mrem 5.42E-03 Report Period: January 1, 2005 - December 31, 2005 (liquid)

I Total body I 4.23E-03 mrem 3 mrem I 1.41E-01 I Organ I 5.64E-03 mrem 10 mrem I 5.64E-02 88

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Sources of Input Data

• Water Usage: Survey of Water Treatment Plants (DSR-95-00347)

. 0-50 mile meat, milk, vegetable production, and population data was taken from 1982 Annual Environmental Operating Report entitled, "Evaluation of Compliance with Appendix I to 10CFR50: Updated Population, Agricultural, Meat - Animal, and Milk Production Data Tables for 1982". This evaluation was based on the 1980 Census, the Agricultural Ministry of Ontario 1980 report entitled "Agricul-tural Statistics and Livestock Marketing Account", the Agricultural Ministry of Ontario report entitled "Agricultural Statistics for Ontario, Publication 21, 1980",

the Michigan Department of Agriculture report entitled "Michigan Agricultural Statistics, 1981", and the Ohio Crop Reporting Service report entitled "Ohio Agri-cultural Statistics, 1981".

• Gaseous and liquid source terms: Tables 17 through 21 of this report.

• Location of the nearest individuals and pathways by sector within 5 miles, see Land Use Census Section of the report.

• Population of the 50-mile Radius of Davis-Besse (DSR-95-00398).

Dose to Public Due to Activities Inside the Site Boundary In accordance with ODCM Section 7.2, the Radioactive Effluent Release Report includes am as-sessment of radiation doses from radioactivity released in liquid and gaseous effluents to mem-bers of the public from activities inside the site boundary.

The Wellness Center, Pavilion, Training Center pond and the intake forebay/canal area located inside DBNPS Owner Controlled Area are accessible to employees and their families. The Pavil-ion may be accessible to the public for certain social activities. The Training Center pond allows employees and their families to fish on site under a "catch-and-release" program; therefore the fish pathway is not considered applicable. Considering the frequency and duration of the visits, the resultant dose would be a small fraction of the calculated maximum site boundary dose. For purposes of assessing the dose to members of the public in accordance with ODCM Section 7.2, the following exposure assumptions are used:

• Exposure time for maximally-exposed visitors is 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> (I hr/day, 5 day/ week, 50 wk/yr)

• Annual average meteorological dispersion (conservative, default use of maximum site boundary dispersion).

. For direct "shine" from the Independent Spent Fuel Storage Installation (ISFSI),

default use of the maximum dose rate for a completed (full) ISFSI, and a distance of 950 feet.

89

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report The equations in the ODCM may be used for calculating the potential dose to a member of the*

public for activities inside the site boundary. Based on these assumptions, this dose would be at least a factor of 35 less than the maximum site boundary air dose, as calculated in the ODCM.

Nowhere onsite are areas accessible to the public where exposure to liquid effluents could occur.

Therefore, the modeling of the ODCM conservatively estimates the maximum potential dose to members of the public.

Inoperable Radioactive Effluent Monitoring Equipment Miscellaneous Liquid Radwaste Effluent Monitor RE1 878A was declared inoperable on 10/5/05, and was not returned to service until February 7, 2006. The rate meter was found to be defective, and had to be returned to the vendor for repair. Redundant monitor RE1 878B was in service dur-ing this time.

Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Procedure (PCP)

There was one alteration to the OCDM (Revision 20.0), and one change to the PCP (Revision 7) during this reporting period.

Borated Water Storage Tank Radionuclide Concentrations During the Reporting Period of 2005, the BWST tank concentration did not exceed the ODCM Section 2.2.4 sum of the limiting fraction of nuclides. The sum of limiting nuclides is a unitless number, and the BWST total activity did not exceed the upper limit of 1.

90

Davis-Besse Nuclear Powver Station 2005 Annual Radiological Environmental Operating Report Table 17 Gaseous Effluents - Summation of All Releases Type Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total %

2005 2005 2005 2005 Error Fission and Activation Gases Total Release Ci 5.98E+00 6.86E-01 5.39E-01 1.91 E+00 2.5E+01 Average Release Rate for Period pCi/sec 7.07E-01 8.53E-02 6.77E-02 2.42E-01 Percent of ODCIM Limits See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination lodines Total lodines (1-131) Ci 5.96E-05 4.75E-05 8.01E-05 5.71 E-05 2.5E+01 Average Release Rate for Period pCi/sec 7.05E-06 5.91E-06 1.01E-05 7.23E-06 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Particulates Particulates with half-lives greater Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2.5E+01 than 8 days Average Release Rate for Period pCi/sec 0.OOE+00 0.OOE+00 O.OOE+0 0.OOE+00 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination 2.5E+01 Gross Alpha Activity Ci O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Tritium Total Release Ci 8.53E+00 4.90E+00 4.27E+00 5.08E+00 2.5E+01 Average Release3 Rate for Period pCi/sec 1.01E+00 6.10E-01 5.37E-01 6.43E-01 Percent of ODClvl Limits See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination NotelThe average release rate is taken over the entire quarter, not over the time period of the releases.

91

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 18 Gaseous Effluents - Ground Level Releases Batch Modea 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2005 2005 2005 2005 Fission Gases Ci Kr-85 LLD LLD LLD LLD Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xe-135 LLD LLD LLD LLD Xe-135m LLD LLD LLD LLD Xe-138 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A lodines Ci I-131 LLD LLD LLD LLD I-133 LLD LLD LLD LLD I-135 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A Particulates and Tritium Ci H-3 3.74E-03 3.77E-03 6.25E-03 3.98E-03 Sr-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD LLD LLD Ba-La-140 LLD LLD LLD LLD Total for Period: 3.74E-03 3.77E-03 1.88E-02 1.23E-02 92

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 18 (Continued)

Gaseous Effluents - Ground Level Releases Continuous Modeb 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2005 2005 2005 2005 Fission Gases Ci Kr-85 LLD LLD LLD LLD Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xe-135 LLD LLD LLD LLD "e-135m LLD LLD LLD LLD Xe-138 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A lodines Ci 1-131 LLD LLD LLD LLD 1-133 LLD LLD LLD LLD 1-135 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A Particulates and Tritium Ci 11-3 1.07E-02 1.58E-02 1.88E-02 1.23E-02 Sr-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD C's-137 LLD LLD LLD LLD Ba-La-140 LLD LLD LLD LLD Total for Period: 1.07E-02 1.58E-02 1.88E-02 1.23E-02 93

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 18 (Continued)

Gaseous Effluents - Ground Level Releases LLDs for Continuousb and Batcha Mode Kr-85: <1.6E-06 V.Ci/ml Kr-85m: <5.3E-09 pCi'inl Kr-87: <1.6E-08 giiCml Kr-88: <1.8E-08 g.rrinl Xe-133: <9.7E-09 jIci/mI Xe-135: <5.4E-09 pci/ml Xe-135m: <1.7E-07 pci/mi Xe-138: <5.3E-07 jIi/iml I-131: <2.3E-12 gci/mi I-133: <3.3E-12 pi/iml I-135: <8.8E-12 pCi/ml Cs-134: <9.5E-13 pCi/mi Cs-137: <4.4E-12 [pCi/mi Ba-140: <8.9E-12 gci'rml La-140: <2.7E-12 ptCi/mi Sr-89: <5.2E-1 I gCi/mi Sr-90: <5.2E- Il pCi/mi a Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, and Auxiliary Boiler Outage Release are listed as batch releases b Atmospheric Vent Valve weepage and Steam Packing Exhaust are continuous releases.

94

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 19 Gaseous Effluents - Mixed Mode Releases Batch Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2005 2005 2005 2005 Fission Gases Ar-41 Ci 3.04E-02 2.65E-02 LLD LID Kr-85 Ci 3.61E+00 2.45E-01 5.25E-01 4.99E-01 Kr-85m Ci LLD LLD LLD LID Kr-87 Ci LLD LLD LLD LID Kr-88 Ci LLD LLD LLD LID Xe-133 Ci 1.40E+00 4.08E-01 1.40E-02 8.35E-02 Xe-133m Ci 1.21E-03 2.85E-03 LLD LID Xe-135 Ci 9.89E-03 3.50E-03 LLD LID Xe-135m Ci LLD LLD LLD LID Xe-138 Ci LLD LLD LLD LID Xe-131m Ci LLD LLD LLD LID Total for Period: 5.05E+00 6.86E-01 5.39E-01 5.37E-01

• Iodincs I-131 Ci LLD LLD LLD LID 1-133 Ci LLD LLD LLD LID I-135 Ci LLD LLD LLD LID Total for Period: Ci N/A N/A N/A N/A

• Particulates & Tritium H-3 Ci 2.03E-01 5.36E-02 7.42E-03 5. 19E-02 Sr-89 Ci LLD LLD LLD LLD Sr-90 Ci LLD LLD LLD LID Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci LLD LLD LLD LID Ba-La-140 Ci LLD LLD LLD LID Total for Period: Ci 2.03E-01 5.36E-02 7.42E-03 5.19E-02

• Relecse of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Sta-tion Vent) 95

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 19 (Continued)

Gaseous Effluents - Mixed Mode Releases Continuous Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2005 2005 2005 2005 Fission Gases Kr-85 Ci LLD LLD LLD LLD Kr-85m Ci LLD LLD LLD LLD Kr-87 Ci LLD LLD LLD LLD Kr-88 Ci LLD LLD LLD LLD Xe-133 Ci 9.27E-01 LLD LLD 9.75E-01 Xe-133m Ci LLD LLD LLD LLD Xe-135 Ci LLD LLD LLD 3.52E-01 Xe-135m Ci LLD LLD LLD LLD Xe-138 Ci LLD LLD LLD LLD Total for Period: 9.27E-01 N/A N/A 1.33E+00 lodines I-131 Ci 2.23E-05 1.24E-05 2.10E-05 1.61E-05 I-133 Ci 3.73E-05 3.51 E-05 5.91E-05 4.10E-05 I-135 Ci LLD LLD LLD LLD Total for Period: 5.96E-O5 4.75E-05 8.01E-05 5.7 1E-05 Particulates and Tritium H-3 Ci L.33E+00 4.85E+00 4.27E+00 5.03E+00 Sr-89 Ci LLD LLD LLD LLD Sr-90 Ci LLD LLD LLD LLD Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci LLD LLD LLD LLD Ba-La-140 Ci LLD LLD LLD LLD Total for Period: 8.33E+00 4.85E+00 4.27E+00 4.68E+00 96

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 19 (Continued)

LLDs for Gaseous Effluents - Mixed Mode Releases Continuous Mode' Batch Mode' Kr-85 <1.6E-06 pCi/ml Ar-41 <2.4E-06 pCi/ml Kr-85m <5.3E-09 pCi/ml Kr-85m <3.4E-06 pCi/ml Kr-87 <1.6E-08 pCi/ml Kr-87 <5.3E-06 pCi/mi Kr-88 <1.SE-08 jtCi/mil Sr-89 <I.OE-15 pCi/ml Xe-133 <3.0E-06 .xCi/ml Sr-90 <1.OE-15 pCi/ml Xe-133m <9.7E-08 pLCi/ml Kr-88 <5.4E-06 pCi/ml Xe-135 <5.4E-09 jiCi/ml I-131 <1.8E-06 pCi/ml Xe-135m <1.7E-07 pCi/m1 1-133 <2.2E-06 pCi/ml Xe-138 <5.3E-07 pCi/ml 1-135 <8.9E-06 piCi/ml I-131 <8.3E-15 pCi/ml Xe-133m <9.3E-06 pCi/ml I-133 <9.5E-15 pCi/ml Cs-134 <1.5E-06 pCi/ml I-135 <7.2E-14 pCi/ml Cs-137 <2.0E-06 p[Ci/mI Cs-134 <1.6E-14 PCi/mI Xe-135 <1.2E-06 pCi/ml Cs-137 <1.9E-14 pCi/ml Xe-135m <8.9E-05 pCi/mI Ba-140 <5.3E-14 jtCi/ml Xe-138 <5.4E-05 pCi/ml La-140 <1.9E-14 pCi/ml Ba-140 <5.3E-14 pCi/mI Sr-89 <i.OE-15 pCi/mli La-140 <1.9E-14 PCi/mI Sr-90 <l.OE-15 pCi/ml Mn-54 <1.4E-14 pCi/ml Fe-59 <3.6E-14 pCi/mil Co-58 <1.6E-14 pCi/mI Co-60 <2.2E-14 PCi/mI Zn-65 <4.9E-14 pCi/ml Mo-99 <1.OE-13 PCi/ml Cs-134 <1.6E-14 pCi'ml Cs-137 <1.9E-14 pCi/ml Ce-141 <2.1E-14 tiCi/ml a These radionuclides were not identified in every quarter in concentrations above the lower limit of detection (LLD). The largest LLD value is listed.

97

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 20 Liquid Effluents - Summation of All Releases Type Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total 2005 2005 2005 2005  % Error Fission and Activation Products Total Release (without Tritium, Ci 1.I OE-02 1.67E-03 1.20E-03 4.18E-04 2.OE+0 I Gases, Alpha)

Average Diluted Concentration g.Ci/ml 1.04E-09 1.50E-10 1.03E-10 4.13E-I I During Perioda Percent of ODCM Limits See Supplemental information in ODCM Section 2.3, Release Limits Percent of IOCFR20 Limit 9.08E-03 1.57E-03 1.37E-03 6.35E-04 Tritium Total Release Ci 7.42E+01 3.50E+01 1.02E+02 1.96E+02 2.OE+0I Average Diluted Concentration RtCi'ml 7.03E-06 3.19E-06 8.78E-06 1.94E-05 During Perioda Percent of I OCFR20 Limit 7.03E-01 3.19E-01 8.78E-01 1.94E+00 Dissolved and Entrained Gases Total Release Ci 8.45E-05 O.OOE+00 O.OOE+00 1.55E-02 2.OE+Ol Average Diluted Concentration gCilml 8.OOE-12 O.OOE+00 O.OOE+00 1.53E-09 During Perioda Percent of IOCFR20 Limit 4.00E-06 O.OOE+00 0.00E+00 7.64E-04 Gross Alpha Total Release Ci 3.08E-06 O.OOE+00 5.25E-06 O.OOE+00 2.OE+0O Volume of WVaste Released (prior to dilution)

Batch liter 3.37E+05 1.97E+05 3.61 E+05 4.30E3+05 2.OE3+0 Continuous liter 7.99E+07 1.66E+08 8.54E+07 9.65E+07 2.0OE+01 Volume of Dilution Water Batch liter 1.20E+08 5.51 E+07 9.95E+07 1.04E+08 2,0OE+01 Continuous liter 1.03E+10 1.09E+10 1.14E+10 9.92E+09 2.01E+01 Total Volume of Water Released liter 1.06E+10 1.1 IE+1O 1.16E+10 l.OlE+l0 a Tritium and alpha are found in both continuous and batch releases. Average diluted concentrations are based on total volume of water released during the quarter. Fission and Activation products and Dissolved and Entrained Gases are normally only detected in batch releases.

98

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Reporil:

Table 21 Liquid Effluents - Nuclides Released Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2005 2005 2005 2005 Fission and Activation Products Cr-SI Ci LLD LLD LLD ILD Mn-54 Ci LLD LLD LLD ILD Fe-55b Ci 1.41E-03 2.76E-04 LLD ILD Co-57 Ci 5.73E-06 1.56E-06 3.66E-06 ].73E-06 Co-58 Ci 7.42E-03 7.45E-04 9.61 E-04 1.73E-04 Fe-59 Ci 2.91E-05 LLD LLD ILD Co-60 Ci 8.59E-04 1.65E-04 1.09E-04 L..98E-05 Zn-65 Ci LLD LLD LLD LLD Sr-89b Ci LLD 4.15E-05 LLD ].55E-04 Sr-90b Ci LLD LLD LLD ILD Sr-92 Ci LLD 3.47E-06 LLD ILD Nb-95 Ci 9.40E-05 LLD LLD ILD Zr-95 Ci 6.31 E-05 LLD LLD ILD Zr-97 Ci LLD 3.80E-06 LLD ILD Mo-99 Ci LLD LLD LLD ILD Tc-99m Ci LLD LLD LLD LLD Ru-:103 Ci 1.88E-05 LLD LLD ILD Ru-106 Ci 1.36E-04 LLD LLD ILD Ag-llOm Ci 5.32E-04 2.00E-04 2.91E-05 9.79E-06 Sb-] 24 Ci 9.79E-06 1.85E-06 LLD ILD Sb-]25 Ci 2.16E-04 1.98E-04 3.03E-05 1.1OE-05 I-131 Ci LLD LLD LLD LLD I-13:2 Ci 3.72E-05 LLD LLD LLD Te-132 Ci 3.81E-05 LLD LLD ILD Cs-134 Ci 3.87E-05 9.83E-06 1.93E-05 9.25E-07 Cs-137 Ci 8.69E-05 2.30E-05 4.75E-05 I .66E-05 Ba/La-140 Ci LLD LLD LLD ILD Ce-I 41 Ci LLD LLD LLD ILD Total for Period: Ci 1.1OE-02 1.67E-03 1.20E-03 .18E-04 99

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - Nuclides Released Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2005 2005 2005 2005 H-3 Ci 7.42E+01 3.52E+01 1.02E+02 1.96E+02 Dissolved and Entrained Gases Xe-131m Ci LLD LLD LLD 2.69E-04 Xe-133 Ci 8.45E-05 LLD LLD 1.51 E-02 Xe-133m Ci LLD LLD LLD 8.19E-05 Xe-135 Ci LLD LLD LLD LLD Total for Period: Ci 8.45E-05 0.OOE+00 0.00E+00 1.55E-02 100

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - Nuclidesa Released Continuous Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2005 2005 2005 2005 Fission arid Activation Products Cr-51 Ci LLD LLD LLD LLD Mn-54 Ci LLD LLD LLD LLD Fe-59 Ci LLD LLD LLD LLD Co-58 Ci LLD LLD LLD LLD Co-60 Ci LLD LLD LLD LLD Zn-65 Ci LLD LLD LLD LLD Sr-89b Ci LLD LLD LLD LLD Sr-9Ob Ci LLD LLD LLD ILD Nb-95 Ci LLD LLD LLD LLD Zr-95 Ci LLD LLD LLD LLD Mo-99 Ci LLD LLD LLD LLD Tc-9m Ci LLD LLD LLD LLD I-131 Ci LLD LLD LLD LLD Cs-] 34 Ci LLD LLD LLD LLD Cs-] 37 Ci LLD LLD LLD LLD Ba/La-140 Ci LLD LLD LLD LLD Ce-1]41 Ci LLD LLD LLD LLD Total for Period: O.OOE+0O O.OOE+00 O.OOE+OO O.OOE+OO Tritium Ci 6.71E-02 3.57E-01 4.18E-O1 6.77E-01 Dissolved and Entrained Gases Xe-l 33 Ci LLD LLD LLD LLD Xe-I 35 Ci LLD LLD LLD lLD Total for Period: Ci O.OOE+O0 0.OOE+OO O.OOE+O0 (.OOE+O0 101

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - LLDs for Nuclides Releaseda Cr-51 <5.9E-08 jiCi/ml Sb-124 <8.OE-09 giCi/ml Mn-54 <9.1 E-09 fiCi/ml Te-132 <6.3E-09 pCi/ml Fe-55b <9.5E-07 gci/iml Ce-1 41 <l.lE-08 pjCi/ml Fe-59 <1.5E-08 i~Ici/ml Cs-134 <8.7E-07 pCi/mi Co-57 <5.3E-09 gCi/ml Cs-137 <8.9E-09 pCi/ml Co-58 <l.IE-08 .iCi/ml Ba-140 <2.4E-08 pCi/ml Co-60 <1.3E-08 PCi/ml La-140 <I.OE-08 pCi/ml Zn-65 <1.9E-08 jiCi/mi I-131 <8.1E-09 piCi/ml Sr-89b <3.6E-07 gCi/lm 1-132 <l.IE-08 pCi/ml Sr_90b <4.4E-08 jtCi/ml Xe-131m <4.4E-07 pCi/ml Sr-92 <1.3E-08 pCi/ml Xe-133 <3.5E-08 VCi/ml Zr-95 <1.6E-08 giCi/ml Xe-133m <9.1 E-08 pCi/ml Zr-97 <8.6E-09 giCi/ml Xe-135 <1.2E-08 pCi/ml Nb-95 <8.3E-09 jiCi/mi Tc-99m <1.2E-08 piCi/ml Mo-99 <8.7E-08 jtCi/rnl Ru-106 <8.2E-08 jiCi/mI a These radionuclides were not identified every quarter in concentrations above the lower limit of detection (LLD). The largest LLD value is used for each radionuclide. LLDs are applicable to both batch and continuous modes due to identical sample and analysis methods.

b Quarterly composite sample 102

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 22 Solid Waste and Irradiated Fuel Shipments A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 12-month Est. Total

1. Te of Waste Unit Period Error, %

a. Spent resins, filter sludges, ml 3.444E+01 2.5E401 evaporator bottoms, etc. Ci 4.538E-01 2.5E401

b. Dry compressible waste, m3 5.535E+02 2.5E+01 contaminated equip., etc. Ci 4.059E+00 2.5E4 01

c. Irradiated components, m control rods, etc. Ci N/A N/A

d. Others: dewatered primary m3 1.334E+01 2.5E401 system cartridge filters Ci 1.662E+01 2.5E+01

e. Others: Spent Resin Storage m' 1.716E+01 2.5E401 Tank Liquor Ci 5.650E+00 2.5E401

2. Estimaite of major nuclide composition (by type of -waste)

Es-'. Total Type Percent (%)

a. Spent Resins Ni 6 3 3.06E+01 2.5*OE+01 Cs13 7 2.40E+01 2.5.OE+01 Fe 55 2.27E+01 2.50E+0 1 Co 6 0 7.72E+00 2.5OE+0 1 6.OOE+00 Cs'3 4 2.5013+01 5.42E+00 2.50OE+01 c14 9.81E-01 2.5.0E+01I Sr9 0 5.72E-01 Co57 2.5 OE+01 5.44E-01 2.5*OE+01 H3 5.17E-01 2.50E+01 14 4 Ce 3.90E-01 0m 2.5S13+01 Ag '° 2.72E-01 2.50E+01 Mn 54 2.51E-01 Pu 2 4 1 2.50E+01 1.80E-01 2.50E+0 1 Ni 59 1.35E-01

b. Dry compressible waste, contaminated 2.5 ;OE+0 1 equipment, etc. Cs'3 7 2.66E+01 Ni 6 3 2.30E+01 2.50E+01 Fe5 5 1.88E+01 2.5OE+/-01 H3 1.07E+01 Co 6 0 2.50E+01 6.77E+00 Sb'125 3.69E+00 2.5OE+01 C' 4 2.68E+00 Pu2 4 2.50E+01I 1 2.12E+00 2.5013+01 Ag"lo0m 1.44E+00 Tc99 1.13E+00 2.50E+01 103

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 22 Solid Waste and Irradiated Fuel Shipments (Continued)

Ni59 9.04E-01 2.50E+01 Mn 54 2.26E-01 2.50E+01 Co57 1.25E-01 2.50E+01

c. None

d. Others: dewatered primary system cartridge filters Fe55 4.42E+01 2.50E+01 Ce14 4 1.67E+01 2.50E+01 Ni6 3 1.56E+01 2.50E+01 6 0 co 8.95E+00 2.50E+01 H3 5.29E+00 2.50E+01 58 Co 4.1 E+00 2.50E+01 Nb 95 8.49E-01 2.50E+01 Pu2 41 8.07E-01 2.50E+01 Sb12 5 7.99E-01 2.50E+01 Ru10 6 4.72E-01 2.50E+01 Co57 4.45E-01 2.50E+01 Mn54 3.88E-01 2.50E+01 c14 3.59E-01 2.50E+01 Zr95 3.50E-01 2.50E+01 Cm2 4 2 2.25E-01 2.50E+01 Cm2 4 4 1.74E-01 2.50E+01 Cs137 1.64E-01 2.50E+01 Tc 99 1.1 lE-01 2.50E+01

e. Others: Spent Resin Storage Tank Liquor H3 8.75E+01 2.50E+01 Ag!lo1m 4.66E+00 2.50E+01 Cs' 3 7 2.15E+00 2.50E+01 Co5 8 2.04E+00 2.50E+01 Ni6 3 1.60E+00 2.50E+01 Ru10 6 1.46E+00 2.50E+01 Co6 0 2.64E-01 2.50E+01 Fe55 2.60E-01 2.50E+01 104

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Reporn:

Table 22 (Continued)

Solid Waste and Irradiated Fuel Shipments

3. Solid Waste Disposition Number of Shipments: 13 Mode of Transportation: Truck Destination: Duratek, Oak Ridge, TN for processing then disposal at Envirocare of Utah or Barnwell S.C.

Type of Container (Container Volume): Metal boxes (assorted sizes, 3.12-10.8 mi3 )

Volume shipped for processing 314.8 M3 Number of Shipments: 4 Mode of Transportation: Truck Destination: Duratek, Kingston, TN for processing then disposal at Envirocare of Utah Type of Container (Container Volume): Metal boxes (assorted sizes, 3.12-10.8 in3 )

Volume shipped for processing 246.8 m3 Number of Shipments: 5 Mode of Transportation: Truck Destination: Studsvik, Erwin, TN for processing for processing then disposal at Envirocare of Utah or Barnwell S.C.

Type of Container (Container Volume): High Integrity Container (3.75 in3 )

Volume shipped for processing 39.67 m3 Number of Shipments 3 Mode of Transportation Truck Destination Duratek, Oak Ridge, TN for processing then disposal at Envirocare of Utah Type of Container (Container Volume): High Integrity Container (5.942 in3 )

Volume Shipped for Processing 17.2 in3 B. IRRADIATED FUEL SHIPMENTS There were no shipments of irradiated fuel.

105

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 23 Doses Due to Gaseous Releases for January through December 2005 Maximum Individual Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.

Whole Body Dose 6.64E-04 mrem Significant Organ Dose (thyroid) 8.13E-04 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 1.37E-04 mrem Skin Dose 6.65E-04 mrem Population Dose Due to I-131, H-3 and Particulates with Half-Lives Greater than 8 days.

Total Integrated Population Dose 6.29E-03 person-rem Average Dose to Individual in Population 2.88E-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 1.20E-04 person-rem Average Dose to Individual in Population 5.51 E-08 mrem 106

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 24 Doses Due to Liquid Releases for January through December 2005 Maximum Individual Whole Body Dose 4.23E-03 mrem Maximum Individual Significant Organ Dose (liver) 5.64E-03 mrem Population Dose Total Integrated Population Dose 2.84E-02 person-rem Average Dose to Individual 1.30E-05 mrem 107

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 25 Annual Dose to The Most Exposed (from all pathways) Member of the Public 2005 ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem) (mrem) LIMIT Whole Body Dose*

Noble Gas 1.37E-04 Iodine, Tritium, Particulates 6.64E-04 Liquid 4.23E-03 Total Whole Body Dose 5.02E-03 25 2.01E-02 Thyroid Dose Iodine, Tritium, Particulates 3.02E-03 75 4.03E-03 Skin Dose Noble Gas 6.65E-04 25 2.66E-03 Significant Organ Dose (liver) 5.64E-03 25 2.26E-02 Meteorological Data Meteorological data, stored on a 3V2 inch microdisk for January through December 31, 2005, has been submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555.

• Direct radiation from the facility is not distinguishable from natural background and is, therefore, not included in this compilation.

108

j -7 Land Use Census

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmnental Operating Report Land Use Census Program Design Each year a Land Use Census is conducted by Davis-Besse in order to update information rneces-sary to estimate radiation dose to the general public and to determine if any modifications are necessary to the Radiological Environmental Monitoring Program (REMP). The Land Use Cen-sus is required by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis-Besse Nuclear Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use Census Data. The Land Use Census identifies gaseous pathways by which radioactive :mate-rial may reach the general population around Davis-Besse. The information gathered during the Land Use Census for dose assessment and input into the REMP ensure these programs are as cur-rent as possible. The pathways of concern are listed below:

• Inhalation Pathway - Internal exposure as a result of breathing radionuclides car-ried in the air.

• Ground Exposure Pathway - External exposure from radionuclides deposited on the ground a' Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.

• , Vegetation Pathway - Internal exposure as a result of eating vegetables, fruit, etc.

which have a build up of deposited radioactive material or which have absorbed ra-dionuclides through the soil.

. Milk Pathway - Internal exposure as a result of drinking milk, which may contain radioactive material as a result of a cow or goat grazing on a pasture contaminated by radionuclides.

Methodology The Land Use Census consists of recording and mapping the locations of the closest residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) in each me-teorological sector within a five mile radius of Davis-Besse.

The surveillance portion of the 2005 Land Use Census was performed during the month of Au-gust. In order to gather as much information as possible, the locations of residences, dairy cows, dairy goats, and vegetable gardens were recorded. The residences, vegetable gardens, and milk animals are used in the dose assessment program. The gardens must be at least 500 square feet in size, with at least 20% of the vegetables being broadleaf plants (such as lettuce and cabbage6.

Each residence is tabulated as being an inhalation pathway, as well as ground and plume expo-sure pathways. Each garden is tabulated as a vegetation pathway.

109

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 mi-nute series of the relevant quadrangles) which has been divided into 16 equal sectors correspond-ing to the 16 cardinal compass points (Figure 31). The closest residence, milk animal, and vege-table garden in each sector are determined by measuring the distance from each to the Station Vent at Davis-Besse.

Results The following changes in the pathways were recorded in the 2005 census:

SSE Sector - A garden at 6970 meters replaced a garden at 2800 meters.

S Sector - a residence at 1090 meters replaced a residence 1030 meters.

S Sector - A garden at 5020 meters replaced a garden at 3410 meters SSW Sector - A garden at 5020 meters replaced a garden at 2350 meters SW Sector - A garden at 6050 meters replaced a garden at 4250 meters WSW Sector - A garden at 6450 meters replaced a garden at 4960 meters NNTNW Sector - A residence at 1520 meters replaced a residence at 1640 meters The critical receptor is a garden in the W sector at 1560 meters from Davis-Besse, and is unchanged from 2004.

The detailed list in Table 26 was used to update the database of the effluent dispersion model used in dose calculations. Table 26 is divided by sectors and lists the distance (in meters) of the closest pathway in each meteorological sector.

Table 27 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and deposition (D/Q) parameters for each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and in cal-culating liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints.

110

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 26 Closest Exposure Pathways Present in 2005 Sector Distance from Station (meters) Closest Pathways N 880 Inhalation Ground Exposure Plume Exposure NNE 880 Inhalation Ground Exposure Plume Exposure NE 900 Inhalation Ground Exposure Plume Exposure ENE, E, ESE N/A Located over Lake Erie SE 8000 Inhalation Ground Exposure Plume Exposure SSE** 6970 Vegetation SSE 1500 Inhalation Ground Exposure Plume Exposure S** 5020 Vegetation S** 1090 Inhalation Ground Exposure Plume Exposure SSW** 5020 Vegetation SSW 980 Inhalation Ground Exposure Plume Exposure SW 1070 Inhalation Ground Exposure Plume Exposure

• • changed since 2004 112

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 26 Closest Exposure Pathways Present in 2005 Sector Distance from Station (meters) Closest Pathways SW** 6050 Vegetation WSW 1540 Inhalation Ground Exposure Plume Exposure WSW'* 6450 Vegetation W 980 Inhalation Ground Exposure Plume Exposure W 1560 Vegetation WNW** 1520 Inhalation Ground Exposure Plume Exposure NW 1490 Inhalation Ground Exposure Plume Exposure NNW 1290 Inhalation Ground Exposure Plume Exposure

• • Changed since 2004 113

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 27 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q)

Parameters SECTOR METERS CRITICAL AGE X/Q D/Q PATHWAY GROUP (SEC/l3 ) ( 2)

N 880 Inhalation Child 9.15E-07 8.40E-09 NNE 880 Inhalation Child 1.24E-06 1.44E-08 NE 900 Inhalation Child 1.26E-06 1.58E-08 ENE* --- --- --- --- ---

E* --- --

ESE* --- --- --- ---

SE 8000 Inhalation Child 3.43E-08 1.45E-10 SSE** 6970 Vegetation Child 3.02E-08 1.45E-10 S** 5020 Vegetation Child 3.25E-08 2.23E-10 SSW** 5020 Vegetation Child 2.92E-08 2.54E-09 SW** 6050 Vegetation Child 3.34E-08 2.52E-10 WSW** 6450 Vegetation Child 3.89E-08 2.39E-10 W 1560 Vegetation Child 2.94E-07 4.67E-09 WNW** 1520 Inhalation Child 1.89E-07 2.27E-09 NW 1490 Inhalation Child 1.43E-07 1.35E-09 NNW 1290 Inhalation Child 2.31 E-07 1.67E-09

• Since these sectors are located over marsh areas and Lake Erie, no ingestion pathways are present.

• • Changed since 2004 114

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Non-Radiological Environmental Programs Melteorological Monitoring' The Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nu-clear power stations on the surrounding environment. Both NRC regulations and the Davis-Besse Technical Requirements Manual provide guidelines for the Meteorological Moniloring Program. These guidelines ensure that Davis-Besse has the proper equipment, in good wcrking order, to support the many programs utilizing meteorological data.

Meteorological observations at Davis-Besse began in October 1968. The Meteorological Moni-toring Program at Davis-Besse has an extensive record of data with which to perform clima-tological studies which are used to determine whether Davis-Besse has had any impact upon the local climate. After extensive statistical comparative research the meteorological personnel have found no impact upon local climate or short-term weather patterns.

The Meteorological Monitoring Program also provides data that can be used by many other groups and programs: Radiological Environmental Monitoring Program, The Emergency Prepar-edness Program, The Chemistry Unit, and groups such as Plant Operations, Plant Security, Mate-rials Management, Industrial Safety Program, plant personnel and members of the surrounding community.

The Radiological Environmental Monitoring Program uses meteorological data to aid in evaluat-ing the radiological impact, if any, of radioactivity released in Station effluents. The meleoro-logical data is used to evaluate radiological environmental monitoring sites to assure the program is as current as possible. The Emergency Preparedness Program uses meteorological data to cal-culate emergency dose scenarios for emergency drills and exercises and uses weather data to plan evacuations or station isolation during adverse weather. The Chemistry Unit uses meteorological data for chemical spill response activities, marsh management studies, and wastewater discharge flow calculations. Plant Operations uses meteorological data for cooling tower efficiency calcu-lations, forebay water level availability and plant work which needs certain environmental condi-tions to be met before work begins. Plant Security utilizes weather data in their routine planning and activities. Materials Management plans certain Plant shipments around adverse weather conditions to avoid high winds and precipitation, which would cause delays in material deliveries and safety concerns. Industrial Safety uses weather and climatological data to advise personnel of unsafe working conditions due to environmental conditions, providing a safer place to work.

Regulatory Affairs uses climatological data for their investigation into adverse weather accidents in relation to the Plant and personnel.

i. More detailed weather information is available upon request.

115

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report On-site Meteorological Monitoring

System Description

At Davis-Besse there are two meteorological systems, a primary and a backup. Both are housed in separate environmentally controlled buildings with independent power supplies. Both primary and backup systems have been analyzed to be statistically identical, so that if a redundant system in one unit fails, the other system can take its place. The instrumentation of each system follows:

PRIMARY BACKUP 100 Meter Wind Speed 100 Meter Wind Speed 75 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 100 Meter Wind Direction 75 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 100 Meter Delta Temperature 75 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Ambient Temperature 10 Meter Dew Point 10 Meter Solar Incidence Precipitation Meteorological Instrumentation The meteorological system consists of one monitoring site located at an elevation of 577 feet above mean sea level (IGLD 1955)*. It contains a lOOm free-standing tower located about 3,000 feet SSW of the Cooling Tower and a lOnm auxiliary tower located 100 feet west of the 100 m tower. Both are used to gather the meteorological data. The l QOm tower has primary and backup instruments for wind speed and wind direction at I QOm and 75m. The 1QOm tower also measures differential temperature (delta Ts): 100-IOm and 75-1Om. The IOm tower has instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the 1Om tower.

According to the Davis-Besse Nuclear Power Station Technical Requirements Manual, a mini-mum of five instruments are required to be operable at the two lower levels (75m and I Om) to measure temperature, wind speed, and wind direction. During 2005, annual data recoveries for all required instruments were 99.17 percent. Minor losses of data occurred during routine in-strument maintenance, calibration, and data validation.

Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly. Data is reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required. Tower instrumentation maintenance and semiannual calibrations are performed by in-house facilities and by an outside consulting firm. These instruments are wind tunnel tested to assure compliance with applicable regulations and plant specifications.

• International Great Lakes Data - 1955 116

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Meteorological Data Handling and Reduction Each :meteorological system, primary and backup, have two Campbell Scientific Dataloggers (model 21XL) assigned to them. The primary system has a first datalogger to communicate 900 second averages to the control room via a Digital Alpha computer system. This is a dedicated line. :'f a failure occurs at any point between the primary meteorological system and the control room -he control room can utilize the second data logger in the primary shelter. Each datal] gger has its own dedicated communication link with battery backup. The backup meteorological sys-tem is designed the same as the primary; so to lose all meteorological data the primary and backup meteorological systems would have to lose all four dataloggers. However, this would be difficidt since each is powered by a different power supply and equipped with lightning and surge protection, plus four independent communication lines and datalogger battery backup.

The data from the primary and backup meteorological systems are stored in a 30-day circular storage module with permanent storage held by the Digital Alpha computer. Data goes back to 1988 in this format and to 1968 in both digital and hardcopy formats. All data points are scruti-nized every 900 seconds by meteorological statistics programs running continuously. These are then reviewed by meteorological personnel daily for validity based on actual weather conditions.

A monthly review is performed using 21 NRC computer codes, which statistically analyze all data points for their availability and validity. If questionable data on the primary system can not be co1roborated by the backup system, the data in question is eliminated and not incorporated into the final database. All validated data is then documented and stored on hard copy end in digital format for a permanent record of meteorological conditions.

Meteorological Data Summaries This section contains Tables 28-30, which summarize meteorological data collected from the on-site monitoring program in 2005.

Wind Speed and Wind Direction Wind sector graphics represent the frequency of wind direction by sector and the wind speed in mph by sector. This data is used by the NRC to better understand local wind patterns as they relate to defined past climatological wind patterns reported in Davis-Besse's Updated Safety Analysis Report. The maximum measured sustained wind speeds for 2005 occurred on Novem-ber 6, when they were measured at 49.63 mph at the lOOm level, 47.69 mph at the 75m level, and 37.84 mph at the lOm level.

Figures 32-34 give an annual sector graphic of average wind speed and percent frequency by di-rection measured at the three monitoring levels. Each wind sector graphic has two radial bars.

The darker bar represents the percent of time the wind blew from that direction. The hatched bar represents the average wind speed from that direction. Wind direction sectors are classified us-ing Pasquill Stabilities. Percent calms (less than or equal to 1.0 mph) are shown in the middle of the wind sector graphic.

117

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2005 are given in Table 29.

These data are measured at the 1Om level; with differential temperatures taken from 1OOm and 75m levels. The yearly average ambient temperature was 50.890 F. The maximum 0

temperature was 90.68 F on June 25 with a minimum temperature of -0.34 F on January 24.0 Yearly average differential temperatures were -0.4480 F (1OOm), and -0.1970 F (75m). Maximum differential temperatures for lO0m and 75m levels were 7.990 F on October 29, (1OOm), and 7.990 F on November 7, (75m). Minimum differential temperatures for lOOm and 75m levels were -4.000 F on July 21, (lOOm) and -4.000 F on December 25 (75m). Differential temperatures are a measurement of atmospheric stability and used to calculate radioactive plume dispersions based on Gaussian Plume Models of continuous effluent releases.

Dew Point Temperatures and Relative Humidity Monthly average and extreme dew point and humidity temperatures for 2005 are provided in Table 29. These data are measured at the lOm level. The average dew point temperature was 36.80'F with a maximum dew point temperature of 72.57 0 F on August 20. Please note that dew point temperatures above 750 F are highly suspect and are possibly due to calm winds and high solar heating allowing the aspirated dew point processor to retain heat. The minimum dew point (dew point under 320 F is frost point) temperature was -8.82 on January 18. Average relative humidity was 59.65 percent for the year. The maximum relative humidity was 99.24 percent on Februaryl. The minimum relative humidity was 17.04 on December 25. It is possible to have relative humidity above 100 percent, which is known as supersaturation. Conditions for super-saturation have been met a few times at Davis-Besse due to its close proximity to Lake Erie, and the evaporative pool of moisture available from such a large body of water.

Precipitation Monthly totals and extremes of precipitation at Davis-Besse for 2005 are given in Table 29. To-tal precipitation for the year was 32.10 inches. The maximum daily precipitation total was 1.99 inches on August 10. There were many days on which no precipitation was recorded. It is likely that precipitation totals recorded in colder months are somewhat less than actual due to snow/sleet blowing across the collection unit rather than accumulating in the gauge.

Lake Breeze and Lake Level Monitoring Lake Breeze is monitored at Davis-Besse because of its potential to cause major atmospheric/

dispersion problems during an unlikely radioactive release. A lake breeze event occurs during the daytime, usually during the summer, where the land surface heats up faster than the water, and therefore reaches higher temperatures than the water. The warmer air above the land rises faster because it is less dense than the cooler air over the lake. This leads to rising air currents over the land with descending denser air over the lake. This starts a wind circulation, which draws air from the water to the land during the daytime, creating a "Lake Breeze" effect. This event could be problematic if a release were to occur because diffusion would be slow thus creat-ing an adverse atmosphere to the surrounding site.

118

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Lake and forebay levels are monitored at Davis-Besse to observe, evaluate, predict and dissemi-nate high or low lake level information. This data is critical in the running of the plant due 1o the large amounts of water needed to cool plant components. If water levels get too low the plant operators can take measures for the safe shutdown of the plant. Since Lake Erie is the shallowest of the Great Lakes, it is not uncommon for five feet lake level fluctuation to occur within an eight to ten hour period (plus or minus). High water levels also effect the plant due to emergency transportation and evacuation pathways.

119

Davis-Bcsse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 28 Summary of Mcteorological Data Recovery for 2005 JAN FEB MIAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2005 lOOm Wind Speed 94.62 94.35 90.32 99.44 100 100 100 100 100 100 100 100 98.08 lOOM Wind Direction 92.07 94.05 100 99.89 100 100 100 100 100 100 100 100 98.67 75M Wind Speed 88.98 93.01 100 100 100 100 100 100 100 100 100 100 98.39 75M Wind Direction 91.94 98.36 100 100 100 100 100 100 100 100 100 100 99.11 lOM Wind Speed 89.38 97.77 100 100 100 100 100 100 100 100 100 99.73 98.83 lOM Wind Direction 95.43 99.55 100 100 100 100 100 100 100 100 100 100 99.54 1OMAmbientAirTemp 100 100 100 100 100 100 100 100 100 100 100 100 100 1OMDewPointTemp 100 100 100 100 100 100 100 100 100 100 100 100 100 DeltaT(IOOM-1OM) 100 100 100 100 100 100 100 100 100 100 100 100 100 DeltaT (75M-1OM) 100 100 100 100 100 100 100 100 100 100 100 99.73 100 Joint 1OOM Winds and DeltaT (lOOM-IOM) 91.67 93.60 90.32 98.33 100 100 100 100 100 100 100 100 97.64 Joint 75M Winds and DeltaT(1OOM-1OM) 88.98 93.01 100 100 100 100 100 100 100 100 100 99.73 98.39 Joint IOM Winds and Delta T (75M-1OM) 89.25 97.47 100 100 100 100 100 100 100 100 100 99.46 98.79

• all data for individual months expressed as percent of time instrument was operable during the month, divided by the maximum number of hours in that month that the instrument could be operable. Values for annual data recoveries equals the percent of time instrument was operable during the year, divided by the number of hours in the year that the instrument was operable.

120

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 29 Summarv of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1, 2005 through December 31,2005 JAN FE13 iMAR APR MAY JUN .JUL AUG SEP oC r NOV DEC 2005 100M WIND Max Speed (mph) 41.10 34.24 42.34 43.94 32.53 34.04 28.59 31.47 40.15 38.11 49.63 38.14 49.63 Date of Max Speed 01/13 02/14 03/31 04/02 05/12 06/05 07/24 08/31 09/29 10/24 11/06 12/09 11/06 Min Speed (mph) 0.35 0.27 1.45 2.22 1.96 1.93 2.43 1.83 2.63 1.87 1.82 1.47 0.27 Date of Min Speed 01/08 02/01 03/15 04/30 05/06 06/23 07/31 08/16 09/17 10/12 11/15 12/01 02/01 Ave Wind Speed 16.46 15.00 15.82 19.53 14.48 14.33 11.47 12.23 14.32 16.57 21.38 16.92 15.71 75M WIND Max Speed (mph) 39.05 32.33 40.84 42.07 31.90 30.90 26.82 29.97 37.36 33.67 47.69 36.75 47.69 Date of Max Speed 01/13 02/14 03/31 04/02 05/12 06/05 07/24 08/31 09/29 10/24 11/06 12/09 11/06 Min Speed (mph) 1.89 0.64 2.06 2.19 1.63 1.44 1.93 1.14 2.35 1.74 2.26 1.51 0.64 Date of Min Speed 01/31 02/01 03/04 04/29 05/11 06/23 07/31 08/16 09/23 10/12 11/26 12/01 02/01 Ave Wind Speed 15.84 13.71 15.22 17.87 13.39 13.14 10.74 11.27 13.10 14.89 19.70 15.47 14.53 1OM WIND Max Speed (mph) 24.60 22.50 32.37 31.78 24.94 20.84 19.97 22.87 26.01 27.17 37.84 29.59 37.84 Date ofMax Speed 01/22 02/14 03/31 04/02 05/11 06/05 07/26 08/31 09/29 10/24 11/06 12/09 11/06 Min Speed (mph) 1.25 1.50 1.53 1.32 1.26 1.56 1.40 1.60 1.37 1.37 1.74 0.88 0.88 Date of Min Speed 01/29 02/19 03/25 04/29 05/21 06/27 07/13 08/15 09/14 10/13 11/14 12/01 12/01 Ave Wind Speed 10.91 8.56 10.67 11.95 8.91 8.08 7.08 6.70 7.41 9.55 12.10 10.00 9.33 121

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmcntal Operating Report Table 29 (continued)

Summary of Meteorological Data Measured at Davis-Bcssc Nuclear Power Station January 1, 2005 through December 31, 2005 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2005 10M AMBIENT TEMP Max (F) 61.95 53.02 71.38 79.00 80.93 90.68 90.10 89.93 86.10 83.70 69.94 48.00 90.68 Date of Max 01/13 02/15 03/30 04/19 05/10 06/25 07/26 08/12 09/22 10/03 11/03 12/28 06/25 Min (F) -0.34 15.12 14.94 31.79 33.42 56.94 63.15 59.66 43.05 33.80 13.72 4.97 -0.34 Date of Min 01/24 02/18 03/03 04/24 05/04 06/23 07/02 08/28 09/30 10/29 11/24 12/06 01/24 Ave Tcmp 25.65 29.93 33.50 48.98 56.43 73.08 75.04 74.42 68.34 55.69 43.69 25.93 50.89 10M DEW POINT TEMP Mean (F) 17.29 20.94 21.52 33.03 39.30 56.70 58.43 59.85 52.00 40.38 28.10 14.09 36.80 Max (F) 55.58 40.52 45.64 55.63 56.39 68.10 71.63 72.57 62.96 60.32 55.14 34.74 72.57

- Datc of Max 01/12 02/14 03/31 04/20 05/10 06/27 07/16 08/20 09/25 10/03 11/09 12/28 08/20 Min (F) -8.82 1.52 1.53 20.45 20.96 42.51 45.05 45.73 30.82 24.66 -2.94 -5.99 -8.82 Date of Min 01/18 02/18 03/09 04/04 05/04 06/16 07/02 08/02 09/30 10/29 11/24 12/20 01/18 PRECIPITATION Total (inches) 3.57 2.47 0.57 4.86 0.95 1.95 4.60 4.93 1.95 0.83 2.74 2.68 32.10 Max. in One Day 0.9 1 0.48 0.14 1.57 0.25 0.64 1.62 1.99 0.77 0.69 0.85 0.91 1.99 Date 01/03 02/20 03/11 04/02 05/13 06/09 07/27 08/10 09/26 10/24 11/15 12/25 08/10 MAXIMUM PRECIPITATION IN (1) HOUR WAS 0.91 INCHES ON 08/10 (i), HOUR 18 122

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Figure 31 Wind Rose Annual Average lOOM W E-WIND SPEED (MPH)

DIRECTION FREGUENCY (%)

DAVI S-BESSE ANNUAL 2005 lOOM LEVEL 123

Davis-Besse Nuclear Power Station 2005 Annual Radiological Envirornental Operating Report Figure 32 Wind Rose Annual Average 75M DIRECTION FREQUENCY (X)

DAVIS-BESSE ANNUAL 2005 75M LEVEL 124

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average lOM E

g x WIND SPEED (MPH) S

• M DIRECTION FREQUENCY (%)

DAVIS-BESSE ANNUAL 2005 10M LEVEL 125

Davis-Besse Nuclear Power Station 2005 Annual Radiological Envirornental Operating Report Table 30 Joint Frequency Distribution by Stability Class DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 13-Feb-06 PAGE 91 TIME OF DAY: 10:02:00 PROGRAM: JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP SITE IDENTIFIER: 4 DATA PERIOD EXAMINED: 01/01/2005 - 12/31/2005

• • • ANNUAL ***

STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 1.01- 3.49 0 0 1 3 2 1 1 10 6 10 6 3 3 0 0 1 47 3.50- 7.49 3 2 5 10 16 10 7 13 18 25 17 9 5 9 10 6 165 7.50-12.49 1 1 4 11 18 2 3 1 4 23 21 16 6 8 26 3 148 12.50-18.49 0 1 0 3 1 0 0 0 0 1 8 8 6 8 10 3 49 18.50-24.49 0 1 0 0 0 0 0 0 0 0 7 1 6 3 0 0 18

>24.49 0 1 0 0 0 0 0 0 0 0 1 0 1 0 0 0 3 TOTAL 4 6 10 27 37 13 11 24 28 59 60 37 27 28 46 13 430 STABILITY CLASS B STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 1.01- 3.49 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 0 3.50- 7.49 1 1 0 0 1 0 0 3 0 0 1 3 1 2 5 8 26 7.50-12.49 0 0 1 5 10 2 0 0 2 1 6 9 0 2 3 8 49 12.50-18.49 5 0 0 9 6 0 0 0 0 2 0 11 2 1 4 3 43 18.50-24.49 0 4 2 5 1 0 0 0 0 0 0 2 1 0 0 0 15

>24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 6 5 3 19 18 3 0 3 2 3 7 25 4 5 12 19 134 126

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 30 (continued)

Joint Frequency Distribution by Stability Class DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 13-Feb-06 PAGE 92 TIME OF DAY: 10:25:00 PROGRAM: JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP SITE IDENTIFIER: 4 DATA PERIOD EXAMINED: 01/01/2005 - 12/31/2005

• • • ANNUAL ***

STABILITY CLASS C STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAI CALM 1.01-3.49 0 0 1 0 0 0 1 0 0 0 0 0 0 0 0 0 2 3.50- 7.49 2 4 I 1 3 1 0 0 3 1 3 5 2 1 6 4 37 7.50-12.49 1 0 2 17 21 S 0 0 2 5 15 16 8 2 15 13 122 12.50-18.49 2 0 5 17 7 2 0 0 o 5 13 20 3 6 8 5 93 18.50-24.49 0 2 1 6 1 0 0 0 0 0 1 4 0 2 0 0 17

>24.49 0 0 0 0 0 0 0 0 0 0 3 I 0 1 0 0 5 TOTAL 5 6 10 41 32 8 1 0 5 11 35 46 13 12 29 22 276 STABILITY CLASS D STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTA]

CALM 1.01-3.49 2 5 4 5 13 9 9 11 7 8 4 6 5 6 2 4 100 3.50-7.49 46 27 62 123 137 51 48 35 69 101 69 45 27 19 28 35 922 7.50-12.49 56 106 191 230 183 59 34 17 48 135 183 152 106 71 101 109 1781 12.50-18.49 19 70 193 71 50 5 5 7 9 65 159 186 69 64 86 72 1130 18.50-24.49 16 40 36 27 13 0 0 0 2 6 30 48 10 26 28 29 311

>24.49 8 12 1 1 0 0 0 0 0 0 13 23 2 0 5 9 74 TOTAL 147 260 487 457 396 124 96 70 135 315 458 460 219 186 250 258 4319 127

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 30 (continued)

Joint Frequency Distribution by Stability Class DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 13-Feb-06 PAGE 93 TIME OF DAY: 10:36:00 PROGRAM: JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP SITE IDENTIFIER: 4 DATA PERIOD EXAMINED: 01/01/2005 - 12/31/2005

• • • ANNUAL ***

STABILITY CLASS E STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 1.01-3.49 7 7 6 7 14 10 . 21 36 27 28 24 12 8 3 3 3 216 3.50- 7.49 24 26 33 61 91 101 87 57 124 205 113 71 52 27 18 15 1105 7.50-12.49 14 22 31 57 73 31 15 10 30 106 125 75 43 37 34 29 732 12.50-18.49 1 18 10 9 II 2 3 9 22 7 36 21 3 12 20 7 191 18.50-24.49 1 4 3 1 0 0 0 2 4 7 6 9 0 0 2 2 41

>24.49 1 2 0 0 0 0 0 0 0 0 5 0 0 0 1 9 TOTAL 48 79 83 135 189 144 126 114 207 353 304 193 106 79 77 57 2294 STABILITY CLASS F STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 1.01-3.49 0 2 2 0 0 3 10 43 60 38 22 14 8 7 4 2 215 3.50-7.49 1 3 3 5 10 24 25 47 84 163 80 38 37 2 2 2 526 7.50-12.49 2 5 8 3 14 10 2 1 3 13 11 4 3 2 1 0 82 12.50-18.49 0 1 0 0 0 0 0 0 0 2 1 0 0 2 0 0 6 18.50-24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3 11 13 8 24 37 37 91 147 216 114 56 48 13 7 4 829 128

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 30 (continued)

Joint Frequency Distribution by Stability Class DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 13-Feb-06 PAGE 94 TIME OF DAY: 10:46:03 PROGRAM: JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP SITE IDENTIFIER: 4 DATA PERIOD EXAMINED: 01/01/2005 -12/31/2005

• • • ANNUAL ***

STABILITY CLASS G STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 1.01-3.49) 0 0 0 0 1 2 7 12 36 23 25 12 7 0 1 1 127 3.50- 7.49) 0 1 3 5 11 31 21 16 39 67 30 7 1 0 *) 0 232 7.50-12.49 1 1 0 0 2 4 0 1 0 3 0 0 0 0 ') 0 12 12.50-18.49 0 0 0 0 0 0 0 0 0 3 2 0 0 0 ') 0 5 18.50-24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

>24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 l) 0 0 TOTAL 1 2 3 5 14 37 28 29 75 96 57 19 8 0 1 1 376 STABILITY CLASS ALL STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM I 1.01-3.49 9 14 14 15 30 26 49 112 136 107 81 47 31 16 10 11 708 3.50-7.49 77 64 107 205 269 218 188 171 337 562 313 178 125 60 69 70 3013 7.50-12.49 75 135 237 323 321 113 54 30 89 286 361 272 166 122 180 162 2926 12.50-18.49 27 90 208 109 75 9 8 16 31 85 219 246 83 93 128 90 1517 18.50-24.49 17 51 42 39 15 0 0 2 6 13 44 64 17 31 30 31 402

>24.49 9 15 1 1 0 0 0 0 0 0 17 29 3 1 5 10 91 TOTAL 214 369 609 692 710 366 299 331 599 1053 1035 836 425 323 422 374 8658 129

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 30 (continued)

Joint Frequency Distribution by Stability Class DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 13-Feb-06 PAGE 95 TIME OF DAY: 10:55:00 PROGRAM: JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP SITE IDENTIFIER: 4 DATA PERIOD EXAMINED: 01/01/2005 - 12/31/2005

• • • ANNUAL ***

STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WINDTHRESHOLD AT: 1.00MPH TOTAL NUMBER OF OBSERVATIONS: 8759 TOTAL NUMBER OF VALID OBSERVATIONS: 8658 TOTAL NUMBER OF MISSING OBSERVATIONS: 101 PERCENT DATA RECOVERY FOR THIS PERIOD: 98.8 %

MEAN WIND SPEED FOR THIS PERIOD: 9.3 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 PERCENTAGE OCCURRENCE OF STABILITY CLASSES A B C D E F G 4.97 1.55 3.19 49.88 26.50 9.57 4.34 DISTRIBUTION OF WIND DIRECTION VS. STABILITY SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW CALM A 4 6 10 27 37 13 11 24 28 59 60 37 27 28 46 13 0 B 6 5 3 19 18 3 0 3 2 3 7 25 4 5 12 19 0 C 5 6 10 41 32 8 1 0 5 11 35 46 13 12 29 22 0 D 147 260 487 457 396 124 96 70 135 315 458 460 219 186 250 258 1 E 48 79 83 135 189 144 126 114 207 353 304 193 106 79 77 57 0 F 3 11 13 8 24 37 37 91 147 216 114 56 48 13 7 4 0 G 1 2 3 5 14 37 28 29 75 96 57 19 8 0 1 1 0 TOTAL 214 369 609 692 710 366 299 331 599 1053 1035 836 425 323 422 374 1 130

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Land and Wetlands Management The Navarre Marsh, which is part of the Ottawa National Wildlife Refuge, makes up 733 ac.zes of wetlands on the southwestern shore of Lake Erie and surrounds the Davis-Besse Nuclear Power Station. The marsh is owned by FirstEnergy and jointly managed by the U.S. Fish and Wildlife Service and FirstEnergy. Navarre Marsh is divided into three pools. The pools are separated from Lake Erie and each other by a series of dikes and revetments. Davis-Besse is responsible for the maintenance and repair of the dikes and controlling the water levels in each of the pools.

A revetment is a retaining structure designed to hold water back for the purposes of erosion con-trol and beach formation. Revetments are built with a gradual slope, which causes waves to dis-sipate their energy when they strike their large surface area. Beach formation is encouraged through the passive deposition of sediment. A dike is a retaining structure designed to hold wa-ter for the purpose of flood control and to aid in the management of wetland habitat. When. used as a marsh management tool, dikes help in controlling water levels in order to maintain desired vegetation and animal species. Manipulating water levels is one of the most important marsh management techniques used in the Navarre Marsh. Three major types of wetland communities exist in Navarre Marsh, the freshwater marsh, the swamp forest, and the wet meadow. Also, there exists a narrow dry beach ridge along the lakefront, with a sandbar extending out into Lake Erie. All these areas provide essential food, shelter and nesting habitat, as well as a resting area for migratory birds.

Davis.Besse personnel combine their efforts with a number of conservation agencies and organi-zations. The Ottawa National Wildlife Refuge, the Ohio Department of Natural Resources (ODNR), and the Black Swamp Bird Observatory work to preserve and enhance existing habitat.

Knowledge is gained through research and is used to help educate the public about the impor-tance Df preserving wetlands.

With its location along two major migratory flyways, the Navarre Marsh serves as a refuge for a variety of birds in the spring and fall, giving them an area to rest and restore energy reserves be-fore continuing their migration. The Black Swamp Bird Observatory, a volunteer research group, captures, bands, catalogues, and releases songbirds in the marsh during these periods.

Navarre Marsh is also home to wildlife that is typical of much of the marshland in this area, in-cluding deer, fox, coyote, muskrats, mink, rabbits, groundhogs, hawks, owls, ducks, geese, her-ons, slakes and turtles. For the first time in recent history, a pair of mature American Bald Ea-gles chose the Navarre Marsh as their nesting site in late 1994, and fledged a healthy eaglet in July 1995. A new nest was built in 1999-2000, from which a dozen eaglets were fledged. In fall of 2005 two pairs of eagles built new nests on Davis-Besse property. Ohio has gone from a low of 4 nests in 1978 to a record of 125 nests in 2005, when 135 eaglets (also a record) were fl.zdged statewide.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Water Treatment Plant Operation Description The Davis-Besse Nuclear Power Station draws water from Lake Erie for its water treatment plant. The lake water is treated with sodium hypochlorite and/or sodium hypobromite, coagulant aid, filtration, electrolysis and demineralization to produce high-purity water used in many of the Station's cooling systems.

Water from the Carroll Township Water Treatment Plant is used in Davis-Besse's Fire Protection System.

Water Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which remove debris greater than one-half inch in size. The water is then pumped to chlorine detention tanks. Next, the water is sent to the pre-treatment system, which is comprised of coagulation and filtration to remove sediment, organic debris, and certain dissolved compounds from the raw wa-ter. The next step of the process is reverse osmosis, where pressure is used to remove certain im-purities by passing the water through a selectively-permeable membrane. The water is then stripped of dissolved gases, softened, electrolytically deionized and finally, is routed through a polishing demineralization process before being sent to storage.

Domestic Water When Davis-Besse began operation over 25 years ago, all site domestic water was produced in the Water Treatment Facility. Operation of the domestic water treatment and distribution system, including the collection and analysis of daily samples, was reportable to the Ohio Environmental Protection Agency.

Since December of 1998, the Carroll Township Water Treatment Plant has supplied domestic water to Davis-Besse. Carroll Township Water and Wastewater District follow all applicable regulatory requirements for the sampling and analysis of Station drinking water.

Zebra Mussel Control With the exception of its drinking water, the Plant withdraws all of its water through an intake system from Lake Erie. Zebra mussels can severely impact the availability of water for Plant processes. Dreissenapolymorpha, commonly known as the zebra mussel, is a native European bivalve that was introduced into the Great Lakes in 1986 and was discovered in Lake Erie in 1989. Zebra mussels are prolific breeders that rapidly colonize an area by forming byssal threads, which enable them to attach to solid surfaces and to each other. Because of their ability to attach in this manner, they may form layers several inches deep. This poses a problem to fa-cilities that rely on water intakes from Lake Erie because mussels may attach to the intake struc-tures and restrict water flow.

132

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Zebra mussels have not caused any significant problems at Davis-Besse, but mussels have been found attached to the intake crib (the structure that allows water to be withdrawn from the lake) and the first section of the intake conduit (the pipe that connects the crib to the intake canal).

Mussels have also been found on the trash racks and on the walls of intake bay #3 prior to the traveli:ng screens, and are periodically cleaned off by using high-pressure water. Davis-Besse uses continuous low level chlorination/bromination of the intake bays to control the mussels.

At present, the mussel population appears to be leveling off or declining. This is likely due lO the increasing clarity of Lake Erie, since the mussels remove much of the algae. As the food source for the zebra mussel declines, mussel populations should continue to decline correspondingly.

Wastewater Treatment Plant (WWTP) Operation The W-\VTP operation is supervised by an Ohio licensed Wastewater Operator. Wastewater gen-erated by site personnel is treated in an onsite extended aeration package treatment facility de-signed to accommodate up to 38,000 gallons per day. In the treatment process, wastewater from the various collection points around the site enters the facility through a grinder, from wherc it is distributed to the surge tanks of one or both of the treatment plants.

The wastewater is then pumped into aeration tanks, where it is digested by microorganisms.

Oxygen is necessary for good sewage treatment, and is provided to the microbes by blowers and diffusers. The mixture of organics, microorganisms, and decomposed wastes is called activated sludge. The treated wastewater settles in a clarifier, and the clear liquid leaves the clarifier under a weir and exits the plant through an effluent trough. The activated sludge contains the organ-isms necessary for continued treatment, and is pumped back to the aeration tank to digest incom-ing wastewater. The effluent leaving the plant is drained to the wastewater basin (NPDES Out-fall 601) where further treatment takes place.

Summary of 2005 Wastewater Treatment Plant Operations All wastewater parameters were within specifications during the year 2005.

National Pollutant Discharge Elimination System (NPDES) Reporting The Ohio Environmental Protection Agency (OEPA) has established limits on the amount of pol-lutants that Davis-Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 211300011. Parameters such as chlorine, suspended solids and pH are monitored under the NPDES permit. Davis-Besse personnel prepare the NPDES Reports and submit them to the OEPA each month.

Davis.-Besse has eight sampling points described in the NPDES permit. Seven of these locations are discharge points, or outfalls, and one is a temperature monitoring location. Descriptions of these sampling points follow:

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Outfall 001 Collection Box: a point representative of discharge to Lake Erie Source of Wastes: Low volume wastes (Outfalls 601 and 602), Circulating Water system blowdown and service water Outfall 002 Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water runoff, Circulating Water pump house sumps Outfall 003 Screenwash Catch Basin: Outfall to Navarre Marsh Source of Wastes: Backwash water and debris from water intake screens Outfall 004 Cooling Tower Basin Ponds: Outfall to State Route 2 Ditch Source of Wastes: Circulating Water System drain (only during system outages)

Outfall 588 Sludge Monitoring Source of Wlastes: Wastewater Plant sludge shipped for offsite processing Outfall 601 Wastewater Plant Tertiary Treatment Basin: Discharge from Wastewater Treatment Plant Sources of Wastes: Wastewater Treatment Plant Outfall 602 Low volume wastes: Discharge from settling basins Sources of wastes: Water treatment residues, Condensate Polishing Holdup Tank decanta-tion and Condensate Pit sumps Sampling Point 801 Intake Temperature: Intake water prior to cooling operation 2005 NPDES Summary During 2005, Davis-Besse Nuclear Power Station did not experience any reportable events con-cerning the NPDES program.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Chemical Waste Management The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes generated at the Davis-Besse Nuclear Power Station was developed to ensure wastes are man-aged and disposed of in accordance with all applicable state and federal regulations.

Resource Conservation and Recovery Act The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid. haz-ardous waste. Solid waste is defined as a solid, liquid, semi-solid, or contained gaseous material.

The major goals of RCRA are to establish a hazardous waste regulatory program to protect hu-man health and the environment and to encourage the establishment of solid waste management, resource recovery, and resource conservation systems. The intent of the hazardous waste man-agement program is to control hazardous wastes from the time they are generated until they are properly disposed of, commonly referred to as "cradle to grave" management. Anyone who gen-erates, transports, stores, treats, or disposes of hazardous waste are subject to regulation under RCRA.

Under RCRA, there are essentially three categories of waste generators:

. Large quantity Generators - A facility which generates 1,000 kilograms/month (2,200 lbs./month) or more.

• Small quantity Generators - A facility which generates less than 1,000 kilograms/

month (2,200 lbs./month).

• Conditionally Exempt Small Quantity Generators - A facility which generates 100 kilo-grams/month (220 lbs./month).

In 2005, the Davis-Besse Nuclear Power Station generated 4,000 pounds of hazardous waste.

Davis.-Besse personnel continually strive to identify ways to reduce hazardous waste.

Non-hazardous waste generated in 2005 included 3,865 gallons of used oil and 75 cubic yards of oil filters and solid oily debris. Other non-hazardous regulated waste generated included 60 gal-lons of microfilm process chemicals.

RCRA mandates other requirements such as the use of proper storage and shipping containers, labels., manifests, reports, personnel training, a spill control plan and an accident contingency plan. These are part of the Chemical Management Program at Davis-Besse. The following are completed as part of the hazardous waste management program and RCRA regulations:

• Weekly Inspections of the Chemical Waste Accumulation Areas are designated through-out the site to ensure proper handling and disposal of chemical waste. These, along with the Chemical Waste Storage Area, are routinely patrolled by security personnel and in-spected weekly by Environmental and Chemistry personnel. All areas used for storage or accumulation of hazardous waste are posted with warning signs and drums are color-coded for easy identification of waste categories.

• Waste Inventory Forms are placed on waste accumulation drums or provided in the ac-cumulation area for employees to record the waste type and amount when chemicals are 135

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report added to the drum. This ensures that incompatible wastes are not mixed and also identi-fies the drum contents for proper disposal.

Other Environmental Regulating Acts Comprehensive Environmental Response, Compensation and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, or Superfund) established a federal authority and source of funding for responding to spills and other releases of hazardous materials, pollutants and contaminants into the environment. Super-fund establishes "reportable quantities" for several hundred hazardous materials and regulates the cleanup of abandoned hazardous waste disposal sites.

Superfund Amendment and Reauthorization Act (SARA)

Superfund was amended in October 1986 to establish new reporting programs dealing with emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enhanced by ensuring that the potential for release of hazardous substances is minimized, and that adequate and timely responses are made to protect surrounding populations.

Davis-Besse conducts site-wide inspections to identify and record all hazardous products and chemicals onsite as required by SARA. Determinations are made as to which products and chemicals are present in reportable quantities.

Annual SARA reports are submitted to local fire departments and state and local planning com-missions by March I for the preceding calendar year.

Toxic Substances Control Act (TSCA)

The Toxic Substance Control Act (TSCA) was enacted to provide the USEPA with the authority to require testing of new chemical substances for potential health effects before they are intro-duced into the environment, and to regulate them where necessary. This law would have little impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management sys-tem, very similar to the hazardous waste management system established under RCRA.

In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers onsite.

PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with non-PCB liquid.

Retro-filling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with PCB-leaching solvents and allowing the solvent to circulate in the transformer during operation. The entire retro-fill process takes several years and will extract almost all of the PCB.

In all, Davis-Besse performed retro-fill activities on eleven PCB transformers between 1987 and 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors.

These capacitors are being replaced and disposed of during scheduled maintenance activities.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Enviromnental Operating Report Clean Air Act The Clean Air Act identifies substances that are considered air pollutants. Davis-Besse holds an OEPA permit to operate an Air Contaminant Source for the station Auxiliary Boiler. This boiler is used to heat the station and provide steam to plant systems when the reactor is not operating.

A report detailing the Auxiliary Boiler operation is submitted annually.

The Ohio EPA has granted an exemption from permitting our six emergency diesel engines, in-cluding the Station Blackout Diesel Generator, the 2 Emergency Diesel Generators, the Eimer-gency Response Facility Diesel Generator, the Miscellaneous Diesel, and the Fire Pump Diesel.

These sources are operated infrequently to verify their reliability, and would only be used in the event of an emergency.

In response to recent "Clean Air Act Title V" legislation, an independent study identifying and quantifying all of the air pollution sources onsite was performed. Of particular significance is asbestos removal from renovation and demolition projects for which USEPA has outlined spe-cific regulations concerning handling, removal, environmental protection, and disposal. Also, the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concern for worker protection. Removal teams must meet medical surveillance, respirator fit tests, and training requirements prior to removing asbestos-containing material. Asbestos is not considered a hazardous waste by RCRA, but the EPA does require special handling and dis-posal of this waste under the Clean Air Act.

Transportation Safety Act The transportation of hazardous chemicals, including chemical waste, is regulated by the Trans-portation Safety Act of 1976. These regulations are enforced by the United States Department of Transportation (DOT) and cover all aspects of transporting hazardous materials, including pack-ing, handling, labeling, marking, and placarding. Before any wastes are transported of. site, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations, including verification that the vehicle has appropriate placards and it is in good oper-ating condition.

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Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Other Environmental Programs Underground Storage Tanks According to RCRA, facilities with Underground Storage Tanks (USTs) are required to notify the State. This regulation was implemented in order to provided protection from tank contents leaking and causing damage to the environment. Additional standards require leak detection sys-tems and performance standards for new tanks. At Davis-Besse two 40,000 gallon and one 8,000 gallon diesel fuel storage tanks are registered USTs.

Spill Kits Spill control equipment is maintained throughout the Station at chemical storage areas and haz-ardous chemical and oil use areas. Equipment in the kits may include chemical-resistant cover-alls, gloves, boots, decontamination agents, absorbent cloth, goggles and warning signs.

Waste Minimization and Recycling Municipal Solid Waste (MSW) is normal trash produced by individuals at home and by indus-tries. In some communities, MSW is burned in specially designed incinerators to produce power or is separated into waste types (such as aluminum, glass, and paper) and recycled. The vast ma-jority of MSW is sent to landfills for disposal. As the population increases and older landfills reach their capacity, MSW disposal becomes an important economic, health, and resource issue.

The State of Ohio has addressed the issue with the State Solid Waste Management Plan, other-wise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing land-fills by reducing the amount of MSW produced, by reusing certain waste material, and by recy-cling other wastes. This is frequently referred to as "Reduce, Reuse, and Recycle."

Davis-Besse has implemented and participated in company wide programs that emphasize the reduction, reuse, recycle approach to MSW management. An active Investment Recovery Pro-gram has greatly contributed to the reduction of both hazardous and municipal waste generated by evaluating options for uses of surplus materials prior to the materials entering Davis-Besse's waste streams. Such programs include paper, cardboard, aluminum cans, used tires, and metals recycling or recovery. Paper and cardboard recycling is typically in excess of 50 tons annually.

This represents a large volume of recyclable resources, which would have otherwise been placed in a landfill. Aluminum soft drink cans are collected for the Boy Scouts of America to recycle.

Additionally, lead-acid batteries are recycled and tires are returned to the seller for proper dis-posal.

Although scrap metal is not usually considered part of the MSW stream, Davis-Besse collects and recycles scrap metals, which are sold at market price to a scrap dealer for resource recovery.

138

Appendices Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Reporl APPENDIX A INTERLABORATORYCOMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Einvironmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2005 through December, 2005 139

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations or radionuclides known to the issuing agency but not to participate laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U. S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

Table A-3 lists results of the analyses on in-house 'spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house 'blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 list results of the in-house 'duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for 'spiked" samples.

Out-of-limit results are explained directly below the result 140

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Attachment A ACCEPTANCE CRITERIA FOR 'SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One standard deviatibn Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5%of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter

> 50 pCi/liter or kg 10% of known value Strontium_90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium-40 2 0.1 g/liter or kg 5%of known value Gross alpha s 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value Gross beta s 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5%of known value Tritium s 4,000 pCi/liter + ca = (pCi/liter) =

169.85 x (known)"'0933

> 4,000 pCi/liter 10% of known value Radium-226,-228 2 0.1 pCi/liter 15% of known value 2 0.1 pCi/liter, gram, or Plutonium sample 10% of known value lodine-1 31, < 55 pCi/liter 6.0 pCi/liter lod'ne-1 2 9 b > 55 pCi/liter 10% of known value Uranium-238, s 35 pCi/liter 6.0 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium_99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Othe .sb 20% of known value a Fron EPA publication, 'Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1'982, EPA-600/4-1 004.

b Laboratory limit.

141

Davis-Besse Nuclear Power Station 2005 Annual Radiological Envirornental Operating Report TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)".

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1051 02/15/05 Sr-89 28.0 +/- 1.2 29.4 20.7 - 38.1 Pass STW-1051 02/15/05 Sr-90 25.1 +/- 0.7 24.4 15.7 - 33.1 Pass STW-1052 02/15/05 Ba-133 52.9 +/- 2.8 53.4 44.2 - 62.6 Pass STW-1 052 02/15/05 Co-60 54.4 +/- 0.4 56.6 47.9 - 65.3 Pass STW-1 052 02/15/05 Cs-134 67.7 +/- 1.8 64.9 56.2 - 73.6 Pass STW-1052 02/15/05 Cs-1 37 39.6 +/- 1.8 40.2 31.5 - 48.9 Pass STW-1052 02/15/05 Zn-65 159.7 + 3.0 161.0 133.0 - 189.0 Pass STW-1053 02/15/05 Gr. Alpha 55.1 + 1.8 67.9 38.5 - 97.3 Pass STW-1053 02/15/05 Gr. Beta 46.8 +/- 1.3 51.1 38.5 - 97.3 Pass STW-1 054 02/15/05 Ra-226 13.7 + 1.5 14.1 10.4 - 17.8 Pass STW-1 054 02/15/05 Ra-228 13.3 0.6 13.7 7.8- 19.6 Pass STW-1 054 02/15/05 Uranium 5.1 +/-0.2 5.0 0.0 - 10.2 Pass STW-1 055 05/17/05 Sr-89 45.1 +/-4.1 41.3 32.6 - 50.0 Pass STW-1055 05/17/05 Sr-90 7.5 0.9 5.9 0.0- 14.6 Pass STW-1 056 05/17/05 Ba-133 87.1 +/-2.0 88.4 73.1 - 104.0 Pass STW-1056 05/17/05 Co-60 38.4 + 0.8 37.0 28.3 - 45.7 Pass STW-1 056 05/17/05 Cs-1 34 75.3 +/- 0.7 78.6 69.9 - 87.3 Pass STW-1 056 05/17/05 Cs-1 37 201.0 +/- 8.4 194.0 184.0 - 218.0 Pass STW-1056 05/17/05 Zn-65 130.0 +/- 6.7 118.0 97.6 - 138.0 Pass STW-1 057 05/17/05 Gr. Alpha 42.7 +/- 2.9 37.0 21.0 - 53.0 Pass STW-1057 05/17/05 Gr. Beta 34.0 +/- 0.4 34.2 25.5 - 42.9 Pass STW-1 058 05/17/05 1-131 14.7+/- 0.5 15.5 10.3 - 20.7 Pass STW-1 059 05/17/05 Ra-226 6.6 0.1 7.6 5.6 - 9.5 Pass STW-1059 05/17/05 Ra-228 19.3 0.7 18.9 10.7 - 27.1 Pass STW-1 059 05/17/05 Uranium 9.6 0.1 10.1 4.9- 15.3 Pass STW-1060 05/17/05 H-3 24100.0 +/- 109.0 24400.0 20200.0 - 28600.0 Pass S-W-1067 08/16/05 Sr-89 29.1 +/- 3.0 28.0 19.3 - 36.7 Pass STW-1067 08/16/05 Sr-90 36.0 + 0.6 33.8 25.1 - 42.5 Pass STW-1068 08/16/05 Ba-133 107.0 +/- 1.7 106.0 87.7 - 124.0 Pass STW-1 068 08/16/05 Co-60 15.2 +/- 0.2 13.5 4.8 - 22.2 Pass STW-1 068 08116/05 Cs-1 34 89.1 +/- 0.3 92.1 83.4- 101.0 Pass STW-1068 08!16/05 Cs-137 72.1 +/-1.0 72.7 64.0 - 81.4 Pass STW-1 068 08/16/05 Zn-65 67.4 +/- 1.4 65.7 54.3 - 77.1 Pass STW-1 069 08/16/05 Gr. Alpha 44.3 +/- 1.5 55.7 31.6 - 79.8 Pass STW-1 069 08/16/05 Gr. Beta 58.4 +/- 2.1 61.3 44.0 - 78.6 Pass STW-1 070 08/16/05 Ra-226 16.6 +/- 1.5 16.6 12.3 - 20.9 Pass STW-1 070 08/16/05 Ra-228 6.2 +/- 0.3 6.2 3.5 - 8.9 Pass STW-1 070 08/16/05 Uranium 4.5 +/- 0.1 4.5 0.0 - 9.7 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean +/-tstandard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA 142

Davis-Besse Nuclear Powver Station 2005 Annual Radiological Environmental Operating Report TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result Result' Limits Acceptance STW-1072 11/15/05 Sr-89 20.6 + 0.4 19.0 10.3 - 27.7 Pass STW-1072 11/15/05 Sr-90 15.0+/-0.3 16.0 7.3 - 24.7 Pass STW-1073 11/15/05 Ba-1 33 31.8 +/- 1.8 31.2 22.5 - 39.9 Pass STW-1073 11/15/05 Co-60 85.0 +/- 1.4 84.1 75.4 - 92.8 Pass STW-1073 11/15/05 Cs-1 34 37.2 +/- 2.1 33.9 25.2 - 42.6 Pass STW-1073 11/15/05 Cs-1 37 27.8 +/- 0.7 28.3 19.6 - 37.0 Pass STW-1073 11/15/05 Zn-65 109.0 +/- 1.0 105.0 86.8 - 123.0 Pass STW-1074d 11/15/05 Gr. Alpha 41.1 +/- 1.2 23.3 13.2 - 33.4 Fail STW-1074 11/15/05 Gr. Beta 42.7 +/- 0.5 39.1 30.4 - 47.8 Pass STW-1075 11/15/05 1-131 20.5 +/- 0.6 17.4 12.2 - 22.6 Pass STW-1 076 11/15/05 Ra-226 7.8 +/- 0.6 8.3 6.2- 10.5 Pass STW-1 076 e 11/15/05 Ra-228 5.5 +/- 0.6 3.5 2.0 - 5.0 Fail STW-1076 11/15/05 Uranium 15.5 +/- 0.3 16.1 10.9 - 21.3 Pass STW-1 077 11/15/05 H-3 12500.0 +/- 238.0 12200.0 10100.0- 14300.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing In drinking water conducted by Environmental Resources Associates (ERA).

b Unless olherwise indicated, the laboratory result is given as the mean i standard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as dprovided by ERA.

The original samples were calculated using an Am-241 efficiency. The samples were spiked with Th-232. Samples were recounted and calculated using the Th-232 efficiency. Results of the recount: 27.01+/- 2.35 pCi/L.

e Decay of short-lived Radium daughters contributed to a higher counting rate. Delay of counting for 100 minutes provided better results. The report result was the average of the first cycle of 100 minutes, the average of the second cycle counts was 4.01 pCi/L.

143

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).

mR Lab Code Date Known Lab Result Control Description Value +/- 2 sigma Limits Acceptance Environmental, Inc.

2005-1 4/4/2005 30 cm 55.01 64.02 +/- 2.86 38.51 - 71.51 Pass 2005-1 4/4/2005 60 cm 13.75 15.43 +/- 1.02 9.63 - 17.88 Pass 2005-1 4/4/2005 60 cm 13.75 14.98 +/- 0.80 9.63 - 17.88 Pass 2005-1 4/4/2005 90 cm 6.11 6.24 +/- 0.16 4.28 - 7.94 Pass 2005-1 4/4/2005 90 cm 6.11 5.45 +/- 0.48 4.28 - 7.94 Pass 2005-1 4/4/2005 120 cm 3.44 3.50 +/- 0.35 2.41 - 4.47 Pass 2005-1 4/4/2005 120 cm 3.44 3.15 +/- 0.18 2.41 - 4.47 Pass 2005-1 4/4/2005 150 cm 2.2 2.31 +/- 0.25 1.54 - 2.86 Pass 2005-1 4/4/2005 180 cm 1.53 1.65 +/- 0.41 1.07- 1.99 Pass Environmental. Inc.

2005-2 9/12/2005 30 cm 54.84 59.30 +/- 2.66 38.39 - 71.29 Pass 2005-2 9/12/2005 60 cm 13.71 17.55 +/- 1.30 9.60 - 17.82 Pass 2005-2 9/12/2005 75 cm 8.77 8.24 +/- 0.38 6.14- 11.40 Pass 2005-2 9/12/2005 90 cm 6.09 5.94 +/- 0.49 4.26 - 7.92 Pass 2005-2 9/12/2005 90 cm 6.09 5.93 +/- 0.37 4.26 - 7.92 Pass 2005-2 9/12/2005 120 cm 3.43 3.42 +/- 0.18 2.40 - 4.46 Pass 2005-2 9/12/2005 150 cm 2.19 1.71 +/- 0.14 1.53 - 2.85 Pass 2005-2 9/12/2005 150 cm 2.19 1.87 +/- 0.27 1.53 - 2.85 Pass 2005-2 9/12/2005 180 cm 1.52 1.58 +/- 0.99 1.06-1.98 Pass 144

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-3. In-House 'Spike' Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n-1 C Activity Limits d Acceptance W-11105 1/11/2005 Gr. Alpha 24.05 +/- 1.01 20.08 10.04 - 30.12 Pass W-11105 1/11/2005 Gr. Beta 61.59 +/- 1.11 65.70 55.70 - 75.70 'ass SPW-7E34 2/18/2005 H-3 77595.00 +/- 764.00 80543.00 64434.40 - 96651.60 Pass SPAP-766 2/18/2005 Gr. Beta 416.08 +/- 5.52 463.00 370.40 - 509.30 Pass STW-2887 2/28/2005 Tc-99 32.91 +/- 1.23 32.98 20.98 - 44.98 Pass W-301C5 3/1/2005 Gr. Alpha 25.22 +/- 0.45 20.08 10.04 - 30.12 Pass W-301C5 3/1/2005 Gr. Beta 62.27 +/- 0.48 65.73 55.73 - 75.73 Pass SPW-11336 4/15/2005 1-131 109.79 +/- 0.94 106.30 85.04 - 127.56 Pass SPW-1 336 4/15/2005 1-131 (G) 110.25 +/- 9.68 106.30 95.67 - 116.93 Pass SPMI-1 B38 4/15/2005 Cs-134 25.94 + 1.28 26.60 16.60 - 36.60 Pass SPMI-1 B38 4/15/2005 Cs-1 37 59.31 +/- 3.66 60.90 50.90 - 70.90 Pass SPMI-1 838 4/15/2005 1-131 97.71 +/- 0.81 106.30 85.04- 127.56 Pass SPMI-1838 4/15/2005 1-131 (G) 109.45 +/- 3.06 106.30 95.67 - 116.93 Pass SPMI-1838 4/15/2005 Sr-89 104.44 +/- 2.89 108.20 86.56- 129.84 Pass SPMI-1 838 4/15/2005 Sr-90 8.97 +/- 0.79 7.53 0.00 - 17.53 Pass SPVE-'i932 4/18/2005 1-131 (G) 1.00 +/- 0.04 0.73 0.44 - 1.02 Pass SPCH-I 935 4/18/2005 1-131 382.40 +/- 14.95 328.64 262.91 - 394.37 Pass SPAP-i1966 4/18/2005 Cs-1 34 52.10 +/- 7.27 53.35 43.35 - 63.35 Pass SPAP-1 966 4/18/2005 Cs-134 57.28 + 13.47 53.35 43.35 - 63.35 Pass SPAP-1966 4/1812005 Cs-137 124.68 +/- 18.41 121.77 109.59- 133.95 Pass SPAP-1 968 4/18/2005 Cs-1 34 52.10 +/- 7.27 53.35 43.35 - 63.35 Pass SPAP-1 968 4/18/2005 Cs-1 37 116.79 +/- 14.00 121.77 109.59 - 133.95 Pass SPW-2098 4/26/2005 Fe-55 2565.20 +/- 63.66 3017.60 2414.08 - 3621.12 Pass SPW-2922 5/31/2005 Cs-1 34 27.01 +/- 1.09 25.54 15.54 - 35.54 Pass SPW-2922 5/31/2005 Cs-134 65.38 +/- 2.92 60.71 50.71 - 70.71 Pass SPW-2922 5/31/2005 Sr-89 107.90 + 3.60 113.90 91.12 - 136.68 Pass SPW-2922 5/31/2005 Sr-90 11.11 +/- 1.13 6.90 0.00 - 16.90 Pass SPAP-2892 6/1/2005 Gr. Beta 420.32 + 5.55 448.00 358.40 - 492.80 Pass SPW-2895 6/1/2005 H-3 75271.00 + 724.00 78676.00 62940.80 - 94411.20 Pass w-601 05 611/2005 Gr. Alpha 23.69 +/- 0.52 20.08 10.04 - 30.12 Pass w-601 05 6/1/2005 Gr. Beta 60.08 +/- 0.57 65.73 55.73 - 75.73 Pass a Liquid sample results are reported In pCi/Liter, air filters (pCi/filter), charcoal (pCi/mi3), and solid samples (pCi/g).

b Laboratory codes as follows: W (water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister, F (fish).

c Results are based on single determinations.

d Control limits are based on Attachment A, Page A2 of this report.

NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

145

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-3. In-House 'Spike Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n-1 C Activity Lmits d Acceptance SPF-3089 6/7/2005 Cs-134 1.08 +/- 0.05 1.02 0.61 - 1.43 Pass SPF-3089 6/7/2005 Cs-137 2.54 +/- 0.10 2.43 1.46 - 3.40 Pass SPW- 7/1/2005 Ni-63 20.57 i 1.10 16.75 10.05 - 23.45 Pass SPW-47731 8/24/2005 C-14 2112.30 +/- 9.13 2370.80 1422.48 - 3319.12 Pass SPW-47732 8/24/2005 C-14 2294.10 +/- 10.37 2370.80 1422.48 - 3319.12 Pass SPW-4775 8/24/2005 Fe-55 2633.50 +/- 62.40 2777.50 2222.00 - 3333.00 Pass SPMI-4834 8/30/2005 Cs-1 34 49.27 +/- 4.68 47.02 37.02 - 57.02 Pass SPMI-4834 8/30/2005 Cs-1 37 58.17 i 8.18 60.37 50.37 - 70.37 Pass SPMI-4834 8/30/2005 Sr-89 66.39 +/- 3.13 65.90 52.72 - 79.08 Pass SPMI-4834 8/30/2005 Sr-90 11.15 +/- 1.13 9.60 0.00 - 19.60 Pass SPW-4836 8/30/2005 Cs-134 47.35 +/- 5.19 47.02 37.02 - 57.02 Pass SPW-4836 8/30/2005 Cs-137 62.91 +/- 9.08 60.37 50.37 - 70.37 Pass SPW-4836 8/30/2005 Sr-89 11.04 +/- 0.98 9.60 0.00 - 19.60 Pass SPW-4836 8/30/2005 Sr-90 65.89 +/- 2.79 65.90 52.72 - 79.08 Pass SPW-5014 8/30/2005 H-3 77518.20 +/- 753.80 77602.52 62082.02 - 93123.02 Pass W-90705 9/7/2005 Gr. Alpha 24.61 +/- 0.48 20.08 10.04 - 30.12 Pass W-90705 9/7/2005 Gr. Beta 58.35 +/- 0.49 65.73 55.73 - 75.73 Pass SPW-5237 9/22/2005 C-1 4 2387.40 +/- 11.00 2370.80 1422.48 - 3319.12 Pass SPW-5508 9/26/2005 Ni-63 20.64 +/- 1.23 16.70 10.02 - 23.38 Pass SPW-6019 10/24/2005 Tc-99 547.99 +/- 6.69 539.22 377.45 - 700.99 Pass SPF-6293 11/4/2005 Cs-134 941.30 +/- 44.10 886.00 797.40 - 974.60 Pass SPF-6293 11/4/2005 Cs-137 2570.40 +/- 105.30 2400.00 2160.00 - 2640.00 Pass SPAP-6309 11M/2005 Cs-1 34 41.24 +/- 1.91 44.03 34.03 - 54.03 Pass SPAP-6309 11/7/2005 Cs-137 114.03 i 5.01 120.24 108.22 - 132.26 Pass SPAP-6311 11/7/2005 Gr. Beta 1.58 +/- 0.02 1.42 1.14- 11.42 Pass SPW-6451 11/10/2005 H-3 77126.00 +/- 747.00 76749.00 61399.20 - 92098.80 Pass W-120105 12/1/2005 Gr. Alpha 25.16 0.45 20.08 10.04 - 30.12 Pass W-120105 12/1/2005 Gr. Beta 74.58 +/- 0.81 65.73 55.73 - 75.73 Pass SPW-7440 12/30/2005 Cs-1 34 42.67 +/- 4.22 42.03 32.03 - 52.03 Pass SPW-7440 12/30/2005 Cs-1 37 61.19 +/- 7.20 59.91 49.91 - 69.91 Pass SPMI-7442 12/31/2005 Cs-1 34 40.41 +/- 5.66 42.03 32.03 - 52.03 Pass SPMI-7442 12/31/2005 Cs-137 60.05 +/- 7.80 59.91 49.91 - 69.91 Pass

' Liquid sample results are reported in pCi/Liter, air filters (pCi/filter), charcoal (pCi/m 3), and solid samples (pCi/g).

b Laboratory codes as follows: W (water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister, F (fish).

c Results are based on single determinations.

d Control limits are based on Attachment A, Page A2 of this report.

NOTE: For fish, Jello Is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

146

Davis-Besse Nuclear Powver Station 2005 Annual Radiological Environmental Operating Report TABLE A-4. In-House "Blank" Samples Concentration (pCiIL)a Lab Code Sample Date Analysisb Laboratory results (4.66a)

Type Acceptanca LLD Activityc Criteria (4.66 a)

W-11105 water 1/1112005 Gr. Alpha 0.055 0.00 +/- 0.038 1 W-11105 water 1/11/2005 Gr. Beta 0.15 -0.016 +/- 0.10 3.2 SPW-765 water 2/18/2005 H-3 165.8 7.4 +/- 82.5 200 SPAP-7613 Air Filter 2/18/2005 Gr. Beta 0.72 0.29 +/- 0.48 3.2 STW-2888 water 2/28/2005 Tc-99 1.32 0.45 +/- 0.81 10 W-30105 water 3/1/2005 Gr. Alpha 0.067 -0.007 +/- 0.043 1 W-30105 water 3/1/2005 Gr. Beta 0.18 -0.04 +/- 0.11 3.2 SPW-1827 water 4/15/2005 Cs-134 4.66 10 SPW-1837 water 4/15/2005 Cs-1 37 5.38 10 SPW-1883.7 water 4/15/2005 1-131 0.30 -0.13 +/- 0.16 0.5 SPW-1837 water 4/15/2005 1-131 (G) 6.56 20 SPMI-1839 Milk 4/15/2005 1-131 0.26 -0.083 +/- 0.14 0.5 SPMI-1839 Milk 4/15/2005 Sr-89 0.54 -0.069 +/- 0.56 5 SPMI-1839 Milk 4/15/2005 Sr-90 0.53 0.88 +/- 0.34 1 SPCH-1934 Charcoal 4/18/2005 1-131 (G) 2.34 9.6 SPW-2097 water 4/26/2005 Fe-55 859.0 96.1 +/- 528.4 1000 SPW-29'23 water 5/31/2005 Cs-134 3.29 10 SPW-2923 water 5/31/2005 Cs-137 3.87 10 SPW-2896 water 6/1/2005 H-3 138.30 48.1 +/- 85.9 200 w-60105 water 6/1/2005 Gr. Alpha 0.061 0.002 +/- 0.043 1 w-60105 water 6/1/2005 Gr. Beta 0.16 0.056 +/- 0.11 3.2 SPF-309) Fish 6/1/2005 Cs-134 15.69 100 SPF-309D Fish 6/7/2005 Cs-137 11.71 100 SPW- water 7/1/2005 Ni-63 1.60 0.79 +/- 0.99 20 SPW-4774 water 8/24/2005 C-1 4 12.18 2.84 +/- 6.45 200 SPW-47.76 water 8/24/2005 Fe-55 833 275 +/- 525 1000 SPMI-48:35 Milk 8/30/2005 Co-60 4.42 10 SPMI-4835 Milk 8/30/2005 Cs-134 4.18 10 SPMI-4835 Milk 8/30/2005 Cs-137 6.25 10 SPMI-4835 Milk 8/30/2005 1-131(G) 5.37 20 SPMI-4835 Milk 8/30/2005 Sr-89 0.66 -0.23 +/- 0.65 5 3

a Liquid sample results are reported in pCi/Liter, air filters (pCi/filter), charcoal (pCi/im ), and solid samples (pCi/g).

b 1-131(G); iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.

147

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-4. In-House 'Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66a)

Type Acceptance LLD Activity c Criteria (4.66 a)

SPMI-4835 d Milk 8/30/2005 Sr-90 0.66 1.02 +/- 0.41 1 SPW-4837 water 8/30/2005 Co-60 2.48 10 SPW-4837 water 8/30/2005 Cs-134 3.85 10 SPW-4837 water 8/30/2005 Cs-1 37 3.00 10 SPW-4837 water 8/30/2005 Sr-89 0.63 0.25 +/- 0.53 5 SPW-4837 water 8/30/2005 Sr-90 0.63 -0.035 +/- 0.29 1 SPW-5015 water 8/30/2005 H-3 142.8 168 +/- 93 200 SPW-5238 water 9/22/2005 C-14 17.10 3.02 +/- 9.04 200 W-90705 water 9/7/2005 Gr. Alpha 0.056 0.034 +/- 0.04 1 W-90705 water 9/7/2005 Gr. Beta 0.16 0.082 +/- 0.11 3.2 SPW-5238 water 9/22/2005 C-14 17.10 3.02 i 9.04 200 SPW-5509 water 9/26/2005 Ni-63 1.25 1.23 +/- 0.79 20 SPW-6020 water 10/24/2005 Tc-99 4.81 -1.75 +/- 2.90 10 SPF-6294 Fish 11/4/2005 Cs-1 34 18.60 100 SPF-6294 Fish 11/4/2005 Cs-137 12.99 100 SPAP-6310 Air Filter 11/7/2005 Cs-134 3.23 100 SPAP-6310 Air Filter 11/7/2005 Cs-137 3.86 100 SPAP-6312 Air Filter 11/7/2005 Gr. Beta 1.22 -0.64 +/- 0.64 3.2 W-120105 water 12/1/2005 Gr. Alpha 0.05 0.033 +/- 0.04 1 W-120105 water 12/1/2005 Gr. Beta 0.15 -0.043 +/- 0.11 3.2 SPMI-7419 Milk 12/22/2005 Co-60 7.24 10 SPMI-7419 Milk 12/22/2005 Cs-137 5.61 10 SPMI-7419 Milk 12/22/2005 1-131 (G) 10.96 20 SPW-7421 water 12/22/2005 Co-60 2.43 10 SPW-7421 water 12/22/2005 Cs-1 37 3.12 10 SPW-7441 water 12/30/2005 Cs-1 34 4.25 10 SPW-7441 water 12/30/2005 Cs-137 1.63 10 SPMI-7443 Milk 12/30/2005 Cs-134 4.74 10 SPMI-7443 Milk 12/30/2005 Cs-1 37 8.53 10 a Liquid sample results are reported in pCi/Liter, air filters (pCi/filter), charcoal (pCi/m 3), and solid samples (pCi/g).

b 1-131(G); iodine-1 31 as analyzed by gamma spectroscopy.

c Activity reported is a net result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.

d Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.

148

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-5. In-House 'Duplicate' Samples Concentration (pC iL)a Averaged Lab Code Date Analysis First Result Second Result Result Acu~eptance SW-62, 63 1/3/2005 Gr. Beta 3.01 +/- 0.57 2.39 +/- 0.58 2.70+/- 0.41 Pass SW-62, 63 1/3/2005 K-40 2.00 +/- 0.20 2.10 +/- 0.20 2.05 +/- 0.14 Pass CF-95, 96 1/3/2005 Gr. Beta 6.26 +/- 0.23 6.28 +/- 0.23 6.27 +/- 0.16 Pass CF-95, 96 1/3/2005 K-40 5.68 +/- 0.59 5.37 +/- 0.48 5.53 +/- 0.38 Plass AP-791, 792 1/14/2005 Be-7 0.057 +/- 0.017 0.07 +/- 0.04 0.06 +/- 0.02 Pass WW-353,354 1/19/2005 Gr. Beta 8.37 +/- 1.21 10.28 i 1.34 9.32 +/- 0.90 Pass SO-383, 384 1/19/2005 H-3 453.50 +/- 107.20 417.90 +/- 106.00 435.70 +/- 75.38 Pass LW-431,432 1/27/2005 Gr. Beta 2.45 +/- 0.54 2.20 + 0.54 2.33 +/- 0.38 Pass MI-486, 437 2/1/2005 K-40 1319.40 + 163.60 1177.20 +/- 179.70 1248.30 i 121.51 Pass SW-511, 512 2/1/2005 1-131 0.37 + 0.22 0.44 + 0.23 0.40 i 0.16 Pass TD-628, E29 2/1/2005 H-3 489663 +/- 1918 491225 +/- 1915 490444 +/- 1355 Pass DW-538, 539 2/3/2005 Gr. Beta 3.93 i 1.18 3.62 +/- 1.10 3.78 +/- 0.81 Pass MI-564, 555 2/8/2005 K-40 1316.20 +/- 171.10 1292.60 i 154.40 1304.40 115.23 Pass DW-50134, 5 2/11/2005 Gr. Beta 18.41 +/- 0.98 16.76 +/- 0.98 17.59 +/- 0.69 Pass SWU-89$,894 2/22/2005 Gr. Beta 4.00 +/- 0.96 4.20 i 0.72 4.10 +/- 0.60 Pass SW-925, 926 2/25/2005 Gr. Beta 5.97 + 1.51 6.14 + 1.55 6.06 +/- 1.08 Pass SW-950, 951 3/1/2005 Gr. Beta 0.92 +/- 0.27 1.21 i 0.27 1.07 +/- 0.19 Pass SW-950, 951 3/1/2005 Gr. Beta 2.06 +/- 0.40 2.29 +/- 0.44 2.18 +/- 0.30 Pass SW-973, 974 3/1/2005 1-131 1.08 +/- 0.19 0.92 i 0.18 1.00 +/- 0.13 Pass DW-50248, 9 3/16/2005 Gr. Alpha 5.27 +/- 1.06 4.17i 0.90 4.72 +/- 0.70 Pass DW-1264, 1265 3/19/2005 1-131 0.54+/- 0.21 0.73 + 0.20 0.63 +/- 0.15 Pass AP-1 955,1956 3/28/2005 Be-7 0.071 +/- 0.009 0.071 +/- 0.009 0.071 +/- 0.006 Pass AP-1890,1891 3/29/2005 Be-7 0.060 +/- 0.013 0.069 +/- 0.013 0.065 +/- 0.009 Pass AP-2025, 2026 3/29/2005 Be-7 0.063 +/- 0.012 0.071 +/- 0.011 0.067 +/- 0.008 Pass MI-1346,1347 3/30/2005 K-40 1252.80 +/- 120.50 1334.10 i 106.60 1293.45 +/- 80.44 Pass AP-2048,2049 3/30/2005 Be-7 0.075 i 0.018 0.071 + 0.015 0.073 +/- 0.012 Pass AP-2081, 2082 3/30/2005 Be-7 0.073 i 0.016 0.061 +/- 0.018 0.067 +/- 0.012 Pass SWU-15,21, 1522 3/31/2005 Gr. Beta 2.83 +/- 1.16 3.46 + 1.23 3.14 +/- 0.85 Pass WW-1733, 1739 4/5/2005 Gr. Beta 11.44 +/- 1.17 11.14 +/- 1.62 11.29 +/- 1.00 Pass SW-1857,1858 4/13/2005 Gr. Beta 7.04 +/- 1.71 9.96 +/- 1.65 8.50 +/- 1.19 Pass LW-1911, 1912 4/14/2005 Gr. Beta 2.50 +/- 0.63 3.23 +/- 0.67 2.86 +/- 0.46 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below LLD.

a Result; are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

149

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-5. In-House 'Duplicate' Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance F-1976, 1977 4/18/2005 K-40 3.09 i 0.60 3.33 +/- 0.40 3.21 +/- 0.36 Pass MI-2111, 2112 4/26/2005 K-40 1291.50 i 177.90 1323.70 +/- 108.80 1307.60 i 104.27 Pass SWU-2158, 2159 4/26/2005 Gr. Beta 3.69 i 0.74 3.54 + 0.66 3.62 i 0.50 Pass DW-2349, 2350 4/29/2005 1-131 0.58 i 0.27 0.49 i 0.27 0.53 +/- 0.19 Pass SO-2305, 2306 5/2/2005 Cs-1 37 0.11 i 0.05 0.11 00.04 0.11 00.03 Pass S0-2305, 2306 5/2/2005 Gr. Alpha 7.55 i 2.88 12.41 +/- 3.38 9.98 +/- 2.22 Pass SO-2305, 2306 5/212005 Gr. Beta 28.74 +/- 2.57 28.17 2.52 28.46 +/- 1.80 Pass S0-2305, 2306 5/2/2005 K-40 21.51 i 1.22 21.42 +/- 1.24 21.47 i 0.87 Pass SO-2305, 2306 5/2/2005 Sr-90 32.90 i 9.90 29.60 i 13.90 31.25 +/- 8.53 Pass MI-2260, 2261 5/3/2005 K-40 1028.10 i 99.36 1206.70 i 118.50 1117.40 +/- 77.32 Pass F-2630,2631 5/5/2005 K-40 3.08 +/- 0.46 3.04 +/- 0.51 3.06 +/- 0.34 Pass VE-2502, 2503 5/10/2005 Gr. Alpha 0.06 +/- 0.03 0.07 +/- 0.04 0.07 +/- 0.03 Pass VE-2502, 2503 5/10/2005 K-40 3.79 +/- 0.40 4.30 i 0.59 4.04 +/- 0.36 Pass G-2546, 2547 5/11/2005 Be-7 0.81 +/- 0.39 1.25 +/- 0.38 1.03 +/- 0.27 Pass G-2546, 2547 5/11/2005 K-40 9.43 +/- 1.00 7.96 +/- 0.85 8.70 +/- 0.66 Pass SS-2787, 2788 5/18/2005 Cs-1 37 0.13 i 0.04 0.14 0.05 0.13 +/- 0.03 Pass SS-2787, 2788 5/18/2005 K-40 12.44 + 0.76 13.33 i 0.83 12.88 +/- 0.56 Pass S0-3056, 3057 5/19/2005 Cs-137 0.18 i 0.04 0.17 0.01 0.18+/- 0.02 Pass S0-3056, 3057 b 5/19/2005 K-40 20.06 1.10 21.73 +/- 0.36 20.90 +/- 0.58 Fail SS-3175, 3176 5/23/2005 K-40 6.06 + 0.44 5.96 i 0.61 6.01 +/- 0.38 Pass S0-2865, 2866 5/25/2005 Cs-137 0.18i 0.04 0.18 0.03 0.18 0.02 Pass S0-2865, 2866 5/25/2005 Gr. Beta 32.95 i 2.48 33.88 +/- 2.36 33.41 i 1.71 Pass S0-2865, 2866 5/25/2005 K-40 21.93 i 0.97 22.32 +/- 0.98 22.13 +/- 0.69 Pass DW-2935,2936 5/27/2005 1-131 0.51 +/- 0.34 0.56 +/- 0.30 0.53 +/- 0.23 Pass SWU-3103, 3104 6/1/2005 Gr. Beta 3.29i 0.49 3.75 +/- 0.66 3.52 i 0.41 Pass G-2958, 2959 6/1/2005 Be-7 1.06 +/- 0.40 1.21 i 0.28 1.14 i 0.24 Pass G-2958, 2959 b 6/1/2005 Gr. Beta 8.06 +/- 0.07 7.79 +/- 0.07 7.93 +/- 0.05 Fail G-2958,2959 6/1/2005 K-40 5.93 +/- 0.73 6.05 i 0.28 5.99 +/- 0.39 Pass BS-4089, 4090 6/3/2005 Co-60 0.11 +/- 0.02 0.10 0.02 0.11 +/- 0.02 Pass BS-4089, 4090 6/3/2005 Cs-1 37 0.60 +/- 0.05 0.62 +/- 0.05 0.61 i 0.04 Pass DW-50527, 8 6/8/2005 Gr. Alpha 11.58 i 1.31 13.52 i 1.43 12.55 +/- 0.97 Pass VE-3278, 3279 6/13/2005 K-40 6.34 i 0.59 7.29 i 0.68 6.81 i 0.45 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

b 600 minute count time or longer, resulting in lower error.

150

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-5. In-House 'Duplicate' Samples Concentration (DCi/L)B Averaged Lab C ode Date Analysis First Result Second Result Result Acceptance MI-3299, 3300 6/15/2005 K-40 1215.40 +/- 110.20 1250.70 +/- 106.70 1233.05 +/- 76.70 Pass BS-3348, 3349 6/17/2005 Co-60 0.20 + 0.04 0.22 0.04 0.21 +/- 0.03 Pass BS-3348, 3349 6/17/2005 Cs-137 2.59 + 0.10 2.51 +/- 0.07 2.55 +/- 0.06 Pass BS-3348, 3349 6/17/2005 K-40 11.57 +/- 0.81 11.82 + 0.76 11.69 + 0.56 Pass DW-3486, 3487 6/28/2005 Gr. Beta 0.97 + 0.54 1.67 +/- 0.58 1.32 +/- 0.40 Pass SWT-3631, 3632 6/28/2005 Gr. Beta 2.12 0.53 1.62 +/- 0.56 1.87 +/- 0.39 Pass W-3507, 3508 6/29/2005 H-3 38717 +/- 382 38017 +/- 535 38367 +/- 329 Pass VE-3555, 3556 6/29/2005 Gr. Beta 7.53 +/- 0.18 7.56 +/- 0.18 7.55 +/- 0.13 Pass VE-3555, 3556 6/29/2005 K-40 5.70 +/- 0.52 5.64 +/- 0.53 5.67 +/- 0.37 Pass AP-3781, 3782 6/29/2005 Be-7 0.09 +/- 0.02 0.08 +/- 0.02 0.09 +/- 0.01 Pass LW-3610, 3611 6/30/2005 Gr. Beta 1.37 0.35 1.40 +/- 0.36 1.39 +/- 0.25 Pass SW-3760, 3761 6/30/2005 Gr. Beta 9.70 +/- 1.63 9.77 +/- 1.61 9.73 +/- 1.15 Pass E-3654, 3655 7/5/2005 Gr. Beta 1.76 + 0.07 1.69 +/- 0.07 1.72 +/- 0.05 Pass E-3654, 3655 7/5/2005 K-40 1.49 +/- 0.25 1.05 +/- 0.21 1.27 +/- 0.16 Pass MI-3676, 3677 7/5/2005 K-40 1383.90 +/- 116.20 1428.20 +/- 125.40 1406.05 +/- 85.48 Pass DW-373K, 3740 7/5/2005 1-131 1.93 0.24 2.18 +/- 0.23 2.05 0.17 Pass W-3808, 3809 7/6/2005 H-3 4189.61 +/- 196.68 4438.33 +/- 201.39 4313.97 +/- 140.75 Pass DW-393E, 3939 7/8/2005 1-131 1.11 +/- 0.30 1.26 +/- 0.31 1.18 _ 0.22 Pass VE-3896, 3897 7/12/2005 K-40 3.44 +/- 0.62 3.60 +/- 0.36 3.52 +/- 0.36 Pass MI-3963, 3964 7/13/2005 K-40 1438.70 +/- 102.80 1351.80 +/- 100.80 1395.25 +/- 71.99 Pass DW-406E, 4069 7/15/2005 1-131 0.64 +/- 0.27 0.91 +/- 0.28 0.78 +/- 0.20 Pass VE-4290, 4291 7/26/2005 Gr. Alpha 0.11 +/- 0.04 0.05 +/- 0.03 0.08 +/- 0.03 Pass VE-4290, 4291 7/26/2005 Gr. Beta 4.55 +/- 0.13 4.69 +/- 0.14 4.62 +/- 0.09 Pass SWU-43' 1, 4312 7/26/2005 Gr. Beta 2.62 +/- 0.64 1.67 +/- 0.37 2.15 +/- 0.37 Pass SWU-43 1,4312 7/26/2005 H-3 192.30 +/- 92.90 304.60 +/- 97.40 248.45 +/- 67.30 Pass G-4383, 4384 8/1/2005 Be-7 2.06 +/- 0.49 1.76 +/- 0.29 1.91 0.28 Pass G-4383, 4384 8/1/2005 Gr. Beta 8.76 +/- 0.22 8.40 + 0.20 8.58 +/- 0.15 Pass G-4383, 4384 8/1/2005 K-40 6.74 +/- 0.64 6.88 +/- 0.92 6.81 +/- 0.56 Pass MI-4425, 4426 8/1/2005 K-40 1358.10 +/- 169.20 1267.90 +/- 164.40 1313.00 _ 117.96 Pass TD-4446, 4447 8/1/2005 H-3 563.00 +/- 252.00 529.00 +/- 251.00 546.00 +/- 177.84 Pass SL-4473, 4474 8/4/2005 Gr. Beta 5.44 +/- 0.48 4.57 +/- 0.42 5.00 _ 0.32 Pass SL-4473, 4474 8/4/2005 K-40 2.91 + 0.83 2.74 +/- 0.54 2.82 _ 0.49 Pass Note: DLplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sedimen': (pCi/g).

151

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-5. In-House 'Duplicate' Samples Concentration (pCi/L)V Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4532, 4533 815/2005 Gr. Beta 31.20 i 1.20 31.70 +/- 1.20 31.45 +/- 0.85 Pass VE-4618, 4619 8/9/2005 Gr. Alpha 0.09 +/- 0.05 0.09 + 0.04 0.09 + 0.03 Pass VE-4618, 4619 8/9/2005 Gr. Beta 4.60 0.13 4.54 0.12 4.57 +/- 0.09 Pass VE-4618, 4619 8/9/2005 K-40 4.19 0.46 4.34 +/- 0.47 4.27 +/- 0.33 Pass F-4639, 4640 8/11/2005 Cs-1 37 0.05 i 0.02 0.05 + 0.02 0.05 + 0.02 Pass F-4639, 4640 8/11/2005 Gr. Beta 3.33 0.11 3.37 +/- 0.10 3.35 +/- 0.07 Pass F-4639, 4640 8/11/2005 K-40 2.62 +/- 0.57 2.58 +/- 0.59 2.60 i 0.41 Pass DW-4730, 4731 8/12/2005 1-131 0.82 +/- 0.23 0.83 +/- 0.25 0.83 0.17 Pass MI-4855, 4856 8/28/2005 K-40 1341.50 +/- 107.70 1340.00 +/- 114.70 1340.75 +/- 78.67 Pass MI-4855, 4856 8/28/2005 Sr-90 0.77 0.37 0.87 + 0.37 0.82 +/- 0.26 Pass MI-4945, 4946 8/31/2005 K-40 1388.90 i 158.90 1307.50 +/- 165.20 1348.20 +/- 114.61 Pass MI-4945, 4946 8/31/2005 Sr-90 0.67 0.34 0.82 +/- 0.36 0.75 +/- 0.25 Pass TD-4921, 4922 9/1/2005 H-3 5737.00 i 266.00 5860.00 +/- 269.00 5798.50 +/- 189.15 Pass VE-4900, 4901 9'2/2005 Gr. Beta 3.40 +/- 0.06 3.51 + 0.06 3.45 +/- 0.04 Pass VE-4900, 4901 9/2/2005 K-40 2.15i 0.27 2.27 + 0.24 2.21 +/- 0.18 Pass DW-50769, 50770 9/212005 Gr. Alpha 6.17 1.42 6.08 +/- 1.46 6.13 1.02 Pass VE-4990, 4991 9/6/2005 K-40 18.81 i 1.12 19.52 +/- 0.86 19.17 +/- 0.71 Pass MI-5011, 5012 9/8/2005 K-40 1584.00 +/- 194.00 1707.60 +/- 173.00 1645.80 +/- 129.97 Pass VE-5119, 5120 9/12/2005 Gr. Alpha 0.10 0.06 0.09 +/- 0.05 0.10 +/- 0.04 Pass VE-5119, 5120 9/12/2005 Gr. Beta 6.05 +/- 0.18 5.92 0.17 5.98 +/- 0.12 Pass VE-5119, 5120 9/12/2005 K-40 4.61 +/- 0.46 4.74 i 0.69 4.68 +/- 0.41 Pass LW-5361, 5362 9/12/2005 Gr. Beta 1.09 +/- 0.33 1.18 i 0.34 1.13 +/- 0.24 Pass SW-5098, 5099 9/13/2005 1-131 0.44 +/- 0.22 0.31 +/-0.20 0.38 0.15 Pass LW-5178, 5179 9/14/2005 Gr. Beta 2.92 +/- 0.56 2.95 +/- 0.59 2.93 0.41 Pass DW-5239, 5240 9/16/2005 1-131 0.45 +/- 0.27 0.55 +/- 0.29 0.50 i 0.20 Pass CF-5432, 5433 9/19/2005 Be-7 0.91 +/- 0.40 0.64 +/- 0.30 0.78 +/- 0.25 Pass CF-5432, 5433 9/19/2005 K-40 1.43 +/- 0.34 1.38 +/- 0.43 1.41 i 0.27 Pass MI-5292, 5293 9/21/2005 K-40 1228.80 i 78.13 1297.00 i 81.03 1262.90 +/- 56.28 Pass BS-5340, 5341 9/23/2005 Be-7 1286.10 i 550.80 1222.90 +/- 394.40 1254.50 i 338.72 Pass BS-5340, 5341 9/23/2005 Cs-137 726.97 +/- 76.24 677.49 i 70.03 702.23 _ 51.76 Pass BS-5340, 5341 9/23/2005 K-40 12404+/- 1154 13033 +/- 983 12719 +/- 758 Pass DW-5382, 5383 9/23/2005 1-131 0.79 +/- 0.31 0.53 +/- 0.31 0.66 +/- 0.22 Pass MI-5405, 5406 9/27/2005 K-40 1324.80 +/- 112.20 1366.80 +/- 99.44 1345.80 +/- 74.96 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below LLD.

e Results are reported in units of pCI/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

152

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Repori TABLE A-5. In-House 'Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-5769, 5770 9/27/2005 Be-7 0.08 +/- 0.01 0.09 +/- 0.02 0.08 +/- 0.01 Pass AP-5983, 5984 9/27/2005 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-5878, 5879 9/29/2005 Be-7 0.06 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass G-5526, E527 10/3/2005 Be-7 4.03 +/- 0.62 4.07 +/- 0.80 4.05 +/- 0.51 Pass G-5526, E527 10/3/2005 Gr. Beta 8.10 +/- 0.30 8.80 +/- 0.40 8.41 +/- 0.24 Pass G-5526, E527 1013/2005 K-40 4.93 +/- 0.67 6.00 +/- 0.72 5.47 +/- 0.49 Pass VE-5721, 5722 10/10/2005 Gr. Alpha 0.07 +/- 0.05 0.08 +/- 0.06 0.08 +/- 0.04 Pass VE-5721, 5722 10110/2005 Gr. Beta 5.09 +/- 0.15 5.00 +/- 0.16 5.05 +/- 0.11 Pass VE-5721, 5722 10/10/2005 K-40 4.27 +/- 0.43 4.20 +/- 0.34 4.23 +/- 0.27 Pass CF-5695, 5696 10/11/2005 Be-7 2.70 +/- 0.37 2.80 +/- 0.34 2.75 +/- 0.25 Pass CF-5695, 5696 10/1112005 K-40 11.79 0.86 13.11 +0.68 12.45 +/- 0.55 Pass LW-6129, 6130 10/11/2005 Gr. Beta 1.34 +/- 0.25 1.85 + 0.29 1.59 +/- 0.19 Pass LW-6129, 6130 10/11/2005 H-3 304.35 + 95.31 369.23 + 97.88 336.79 + 68.31 Pass DW-50844, 5 10/11/2005 Gr. Beta 5.30 +/- 1.50 4.20 +/- 1.40 4.75 +/- 1.03 Pass LW-5748, 5749 ' 10/12/2005 Gr. Beta 1.09 +/- 0.25 1.89 + 0.28 1.49 i 0.19 Fail AP-6485, 6486 10/20/2005 Be-7 0.10 +/- 0.03 0.09 +/- 0.03 0.09 +/- 0.02 Pass SWU-615'6, 6157 10/2512005 Gr. Beta 4.69 +/- 1.34 4.18 + 1.34 4.44 +/- 0.95 Pass VE-6186, 6187 10/26/2005 K-40 2.90 +/- 0.49 2.83 + 0.51 2.87 +/- 0.35 Pass LW-6203, 6204 10/27/2005 Gr. Beta 2.92 +/- 0.62 3.09 +/- 0.66 3.01 +/- 0.45 Pass SO-6270, 6271 10/2812005 Cs-1 37 0.33 +/- 0.03 0.34 + 0.04 0.33 +/- 0.03 Pass SO-62702 6271 10128/2005 Gr. Beta 26.85 +/- 2.78 22.25 +/- 2.41 24.55 +/- 1.84 Pass SO-6270. 6271 10/28/2005 K-40 13.67 +/- 0.74 14.02 +/- 0.76 13.85 +/- 0.53 Pass TD-6320, 6321 11/1/2005 H-3 444202 +/- 1770 446633 +/- 1775 445418 +/- 1253 Pass SO-6605 6606 11/11/2005 Gr. Beta 18.22 +/- 2.23 18.47 + 2.22 18.35 +/- 1.57 Pass CF-6509, 6510 11/14/2005 K-40 0.85 +/- 0.14 0.99 + 0.22 0.92 +/- 0.13 Pass SW-6638, 6639 11/22/2005 1-131 0.95 + 0.35 0.67 0.31 0.81 +/- 0.23 Pass SO-6887. 6888 11/22/2005 Gr. Alpha 6.80 +/- 2.92 10.27 +/- 3.26 8.53 +/- 2.19 Pass SO-6887. 6888 11/22/2005 Gr. Beta 19.27 +/- 2.16 18.43 +/- 2.21 18.85 + 1.54 Pass SO-6887, 6888 11/22/2005 K-40 14.29 + 1.11 13.78 +/- 0.78 14.03 + 0.68 Pass SWT-672 1, 6722 11/29/2005 Gr. Beta 0.98 +/- 0.31 0.87 +/- 0.31 0.93 +/- 0.22 Pass VE-6775, 6776 11/29/2005 Gr. Beta 12.75 +/- 0.28 13.16 0.21 12.96 _ 0.18 Pass LW-6743, 6744 11/30/2005 Gr. Beta 3.19 +/- 0.47 2.50 +/- 0.44 2.85 +/- 0.32 Pass DW-51023, 4 12/2/2005 Gr. Alpha 0.55 +/- 1.40 2.21 +/- 1.31 1.38 +/- 0.96 Pass SWT-7282, 7283 12/27/2005 Gr. Beta 1.62 +/- 0.37 1.85 + 0.38 1.74 +/- 0.27 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

r Recourt of W-5748, 2.38 +/- 0.85 pCi/L Averaged result; 2.14 +/-0.45 pCi/L 153

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP) 8 .

Concentration (pCiIL) b Lab Code c Date Analysis Laboratory Known Control Resultb Activityc Limits d Acceptance STW-1045 01/01/05 Gr.Alpha 0.45 + 0.10 0.53 0.00 -1.05 Pass STW-1045 01/01/05 Gr.Beta 1.90 + 0.10 1.67 0.84 - 2.51 Pass STW-1046 01/01/05 Am-241 1.62+ 0.12 1.72 1.20 - 2.24 Pass STW-1 046 01/01/05 Co-57 239.40+ 1.20 227.00 158.90 - 295.10 Pass STW-1046 01/01/05 Co-60 248.70+/- 1.00 251.00 175.70 - 326.30 Pass STW-1 046 01/01/05 Cs-1 34 115.50+ 1.80 127.00 88.90 - 165.10 Pass STW-1046 01/01/05 Cs-137 328.50 + 1.70 332.00 232.40 - 431.60 Pass STW-1046 01/01/05 Fe-55 64.90 + 7.00 75.90 53.13 - 98.67 Pass STW-1046 01/01/05 H-3 304.00 + 9.70 280.00 196.00 - 364.00 Pass STW-1046 01/01/05 Mn-54 334.80 + 1.90 331.00 231.70 - 430.30 Pass STW-1046 01/01/05 Ni-63 7.10 + 1.60 9.00 0.00 - 20.00 Pass STW-1 046 01/01/05 Pu-238 0.01 + 0.02 0.02 0.00- 1.00 Pass STW-1 046 01/01/05 Pu-239/40 2.50 + 0.14 2.40 1.68 - 3.12 Pass STW-1046 01/01/05 Sr-90 0.70 + 0.80 0.00 0.00 - 5.00 Pass STW-1 046 01101/05 Tc-99 43.20 + 1.40 42.90 30.03 - 55.77 Pass STW-1046 01/01/05 U-23314 3.31 + 0.20 3.24 2.27 4.21 Pass STW-1 046 01/01/05 U-238 3.38 + 0.20 3.33 2.33 - 4.33 Pass STW-1046 01/01/05 Zn-65 538.40 + 3.80 496.00 347.20 - 644.80 Pass STVE-1 047 01/01/05 Co-57 10.60 + .20 9.88 6.92 - 12.84 Pass STVE-1 047 01/01/05 Co-60 3.00 + 0.20 3.15 2.21 - 4.10 Pass STVE-1 047 01/01/05 Cs-1 34 4.80 + 0.40 5.00 3.50 - 6.50 Pass STVE-1 047 01/01/05 Cs-1 37 4.10 + 0.30 4.11 2.88 - 5.34 Pass STVE-1 047 01/01/05 Mn-54 5.10 + 0.30 5.18 3.63 - 6.73 Pass STVE-1 047 01/01/05 Zn-65 6.20 + 0.50 6.29 4.40 - 8.18 Pass STSO-1048 01/01/05 Am-241 96.60 + 10.00 109.00 76.30 -141.70 Pass STSO-1 048 01/01/05 Co-57 264.00 + 2.00 242.00 169.40 - 314.60 Pass STSO-1048 01/01/05 Co-60 226.50 + 2.20 212.00 148.40 - 275.60 Pass STSO-1048 01/01/05 Cs-134 760.60 + 3.70 759.00 531.30 - 986.70 Pass STSO-1048 01/01/05 Cs-1 37 336.20 + 3.60 315.00 220.50 - 409.50 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.

b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) as requested by the Department of Energy.

' Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) 154

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Repori TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration (pCi/L) b Lab Code C Date Analysis Laboratory Known Control Resultb Activityc Limits d Acceptance STAP-1049 01/01/05 Am-241 0.10 +/- 0.04 0.10 0.07 - 0.13 Pass STAP-1049 01/01/05 Co-57 4.76 +/- 0.64 4.92 3.44 - 6.40 Pass STAP-1 049 01/01/05 Co-60 2.84 +/- 0.22 3.03 2.12 - 3.94 Pass STAP-1 049 01/01/05 Cs-134 3.54 +/- 0.37 3.51 2.46 - 4.56 Pass STAP-1 049 01/01/05 Cs-137 2.20 +/- 0.27 2.26 1.58 - 2.94 Pass STAP-1 049 01/01/05 Mn-54 3.15 +/- 0.21 3.33 2.33 - 4.33 Pass STAP-1 049 01/01/05 Pu-238 0.16 +/- 0.04 0.20 0.14 - 0.25 Pass STAP-1049 01(01/05 Pu-239/40 0.17 +/- 0.02 0.17 0.14 - 0.25 Pass STAP-1 049 e 01/01/05 Sr-90 2.24 +/- 0.34 1.35 0.95 - 1.76 Fail STAP-1 049 01/01/05 U-23314 0.34 +/- 0.02 0.34 0.24 - 0.44 Pass STAP-1 049 01/01/05 U-238 0.35 +/- 0.02 0.35 0.25 - 0.46 Pass STAP-1 049 01/01/05 Zn-65 3.12 +/- 0.15 3.14 2.20 - 4.08 Pass STW-1 061 07/01/05 Am-241 2.21 +/- 0.13 2.23 1.56 - 2.90 Pass STW-1 061 07101/05 Co-57 293.20 +/- 7.30 272.00 190.40 - 353.60 Pass STW-1 061 07/01/05 Co-60 275.70 +/- 1.30 261.00 182.70 - 339.30 Pass STW- 1)61 07/01/05 Cs-134 171.80 +/- 4.00 167.00 116.90 - 217.10 Pass STW-11061 07/01/05 Cs-1 37 342.10 +/- 2.20 333.00 233.10 - 432.90 Pass STW-11)61 07/01/05 Fe-55 167.80 +/- 9.30 196.00 137.20 - 254.80 Pass STW-11061 07/01/05 H-3 514.20 +/- 12.60 527.00 368.90 - 685.10 Pass STW-1061 07/01/05 Mn-54 437.00 +/- 2.50 418.00 292.60 - 543.40 Pass STW-1061 07/01/05 Ni-63 105.10 +/- 3.60 100.00 70.00- 130.00 Pass STW-1061 07/01/05 Pu-238 1.64 +/- 0.12 1.91 1.34 - 2.48 Pass STW-1 061 07/01/05 Pu-239/40 2.32 +/- 0.13 2.75 1.93 - 3.58 Pass STW-1 061 07/01/05 Sr-90 9.20 +/- 1.30 8.98 6.29 - 11.67 Pass STW-1 061 07/01/05 Tc-99 72.30 + 2.30 66.50 46.55 - 86.45 Pass STW-1061 07/01/05 U-233/4 4.11 +/- 0.18 4.10 2.87 - 5.33 Pass STW-1061 07/01/05 U-238 4.14 +/- 0.18 4.26 2.98 - 5.54 Pass STW-1061 07/01/05 Zn-65 364.60 +/- 4.90 330.00 231.00 - 429.00 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.

bResults are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) as requested by the Department of Energy.

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determinalion) e The strontium carbonate precipitates were redissolved and processed. The average of the three analyses was 1.34 although the recovery was only 30%. The result of a new analysis was 1.56 pCi/L.

155

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration (pCi/L) b Lab Code ' Date Analysis Laboratory Known Control Resultb Activityc Limits d Acceptance STW-1062 07/01/05 Gr. Alpha 0.57 +/- 0.05 0.79 0.21 - 1.38 Pass STW-1062 07/01/05 Gr. Beta 1.36 +/- 0.05 1.35 0.85 - 1.92 Pass STSO-1 063 f 07/01/05 Am-241 48.40 i 3.90 81.10 56.77- 105.43 Fail STSO-1 063 07/01/05 Co-57 608.30 + 2.80 524.00 366.80 - 681.20 Pass STSO-1063 07/01/05 Co-60 322.70 + 2.40 287.00 200.90 - 373.10 Pass STSO-1063 07/01/05 Cs-1 34 632.10 + 5.20 568.00 397.60 - 738.40 Pass STSO-1063 07/01/05 Cs-1 37 512.40 +/- 4.20 439.00 307.30 - 570.70 Pass STSO-1063 07/01/05 K-40 720.50 + 19.00 604.00 422.80 - 785.20 Pass STSO-1063 07/01/05 Mn-54 516.80 + 5.10 439.00 307.30 - 570.70 Pass STSO-1063 07/01/05 Ni-63 366.50 +/- 13.30 445.00 311.50 - 578.50 Pass STSO-1063 07/01/05 Pu-238 68.80 +/- 15.00 60.80 42.56 - 79.04 Pass STSO-1063 07/01/05 Pu-239/40 0.00 +/- 0.00 0.00 0.00 - 0.00 STSO-1063 07/01/05 Sr-90 602.90 +/- 17.20 757.00 529.90 - 984.10 Pass STSO-1063 07/01/05 U-23314 61.50 +/- 1.00 52.50 36.75 - 68.25 Pass STSO-1063 07/01/05 U-238 164.50 +/- 16.70 168.00 117.60 - 218.40 Pass STSO-1063 07/01/05 Zn-65 874.70 +/- 8.40 823.00 576.10 -1070.00 Pass STVE-1 064 07/01/05 Am-241 0.18 0.03 0.23 0.16 - 0.30 Pass STVE-1064 07/01/05 Co-57 15.90 + 0.20 13.30 9.31 - 17.29 Pass STVE-1 064 07/01/05 Co-60 4.80 + 0.10 4.43 3.10 - 5.76 Pass STVE-1064 07/01/05 Cs-1 34 4.60 +/- 0.20 4.09 2.86 - 5.32 Pass STVE-1 064 07/01/05 Cs-1 37 5.90 +/- 0.30 5.43 3.80 - 7.06 Pass STVE-1 064 07/01/05 Mn-54 7.20 +/- 0.20 6.57 4.60 - 8.54 Pass STVE-1 064 07/01/05 Pu-238 0.04 +/- 0.02 0.00 0.00- 1.00 Pass STVE-1 064 07/01/05 Pu-239/40 0.13 +/- 0.02 0.16 0.11 - 0.21 Pass STVE-1 064 07/01/05 Sr-90 2.80 +/- 0.30 2.42 1.69 - 3.15 Pass STVE-1 064 07/01/05 U-23314 0.28 +/- 0.03 0.33 0.23 - 0.43 Pass STVE-1 064 07/01/05 U-238 0.33 +/- 0.04 0.35 0.24 - 0.45 Pass STVE-1064 07/01/05 Zn-65 11.00 +/- 0.50 10.20 7.14- 13.26 Pass STAP-1065 07/01/05 Gr. Alpha 0.30 +/- 0.04 0.48 0.00 - 0.80 Pass STAP-1 065 07/01/05 Gr. Beta 0.97 +/- 0.06 0.83 0.55 - 1.22 Pass 2 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.

b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) as.requested by the Department of Energy.

' Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) f Incorrect sample weight used in calculation. Result of recalculation: 97.0 +/- 7.8 Bq/kg.

156

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration (pCi/L) b Lab Code c Date Analysis Laboratory Known Control Resultb Activityc Limits d Acceptance STAP-1 066 07/01/05 Am-241 0.14 +/- 0.03 0.16 0.11 - 0.21 Pass STAP-1 066 07/01/05 Co-57 5.81 +/- 0.17 6.20 4.34 - 8.06 Pass STAP-1 066 07/01/05 Co-60 2.79 +/- 0.14 2.85 2.00 - 3.71 Pass STAP-1 066 07/01/05 Cs-1 34 3.67 +/- 0.12 3.85 2.70 - 5.01 Pass STAP-1 366 07/01/05 Cs-137 2.93 +/- 0.23 3.23 2.26 - 4.20 Pass STAP-1 066 07/01/05 Mn-54 4.11 +/- 0.26 4.37 3.06 - 5.68 Pass STAP-1 066 07/01/05 Pu-238 0.11 +/- 0.02 0.10 0.07 - 0.13 Pass STAP-1 066 07/01/05 Pu-239/40 0.10 +/- 0.01 0.09 0.06 - 0.12 Pass STAP-1 066 07/01/05 Sr-90 2.25 +/- 0.29 2.25 1.58 - 2.93 Pass STAP-1 066 07/01/05 U-23314 0.28 +/- 0.02 0.27 0.19 - 0.35 Pass STAP-1066 07/01/05 U-238 0.28 +/- 0.02 0.28 0.20 - 0.37 Pass STAP-1 066 07/01/05 Zn-65 4.11 +/- 0.26 4.33 3.06 - 5.68 Pass a Resulls obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.

b Resul.s are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) as requested by the Department of Energy.

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determinat on) 157

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report APPENDIX B DATA REPORTING CONVENTIONS 158

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows: x +/-s where: x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xi +/- si and X2 +/- S2 2 2 Reported result: x +/- s; where x = (1/2) (xi + x2) and s = (1/2) S1 +S 2 3.2. Individual results: <L1, <L2 Reported result: <L, where L = lower of Li and L2 3.3. Individual results: x + s, <L Reported result: x +/- s if x 2 L; <L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x 1 , x2 . . xn are defined as follows:

-1 _ Z(x-x) 2 X=- X S= JE -

nn1 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.

159

Davis-Besse Nuclear Power Station 2005 Annual Radiological Enviromnental Operating Report APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas 160

Davis-Besse Nuclear Power Station 2005 Annual Radiological Envirornental Operating Report Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.

Air (pCi/m 3 ) Water (pCi/L)

Gross alpha 1 x10-3 Strontium-89 8,000 Gross beta 1 Strontium-90 500 Iodine-1 3 1 b 2.8 x 10-1 Cesium-1 37 1,000 Barium-1 40 8,000 Iodine-1 31 1,000 Potassium-40c 4,000 Gross alpha 2 Gross beta 10 Tritium I x 106 a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

Concentrations may be averaged over a period not greater than one year.

b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.

C A natural radionuclide.

161

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report APPENDIX D REMP SAMPLING

SUMMARY

162

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa. Ohio Reporting Period January-December, 2005 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F) Mean (F)' Routine (Units) Analyses' Rangec Locationd Range' Range' Results*

0.025 0.025 Airbome GB 528' 0.005 (316/316) T-27, Crane Creek S.P. 0.026 (53/53) (212/212) 0 Particulates (0.008-0.058) 5.3 mi. SW (0.009-0.052) (0.007-0.056)

(pCi/m3)

Sr-89 40 0.0014 < LLD < LLD 0 Sr-90 40 0.0008 < LLD <LLD c- 0 GS 40 Be-7 0.015 0.071 (24/24) T-12, Water Treatment 0.075 (4/4) 0.065 (16/16) 0 (0.046-0.094) Plant, 23.5 mi. WNW (0.070-0.083) (0.039-0.092)

K-40 0.027 < LLD - < LLD 0 Nb-95 0.0012 < LLD - < LLD 0 Zr-95 0.0020 < LLD - - < LLD 0 Ru-103 0.0012 c LLD - - < LLD 0 Ru-106 0.0088 < LLD - - < LLD 0 Cs-134 0.0010 < LLD - - < LLD 0 Cs-137 0.0010 < LLD - < LLD 0 Ce-141 0.0019 < LLD - < LLD 0 Ce-144 0.0059 < LLD < LLD 0 Airbome Iodine 1-131 528 0.07 < LLD < LLD 0 (pCim3)

' GB = gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

' Non-routine results are those which exceed ten times the control station value.

I One result was eliminated from the calculation due to low volume. Location T-1 for the week ending 10-04-05.

163

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-343 Location of Facility Ottawa, Ohio Reporting Period Janu ry-December, 2005 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-T)pe Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses' Rangec Locationd Rangec Rangec Results' 14.1 TILD (Quarterly) Gamma 351 1.0 (307/307) T-45, Site Boundary 20.3 (4/4) 14.9 (44144) 0 (mR/91 days) (7.2-24.4) 0.5 mi. WNW (18.5-21.5) (11.2-20.4)

TLD (Quarterly) Gamma 4 1.0 7.2 (4/4) , I'one 0 (mR/91 days) (6.7-8.0)

(Shield)

TLD (Annual) Gamma 87 1.0 54.9 (76/76) T-45, Site Boundary 80.9 (1/1) 57.4 (11/11) 0 (mR/365 days) (32.2-80.9) 0.5 mi. WNW (38.2-74.1)

TLD (Annual) Gamma 1 1.0 25.2 (1/1) -None 0 (mR/365 days)

(Sl ield)

Milk (pCi/L) 1-131 12 0.4 none *: LLD 0 Sr-89 12 0.7 none -: LLD 0 Sr-90 12 0.7 none T-24, Sandusky 0.9 (9/12) 0.9 (9/12) 0 21.0 mi. SE (0.7-1.4) (0.7-1.4)

GS 12 K-40 100 none T-24, Sandusky 1286 (12/12) 1283 (12/12) 0 21.0 mi. SE (1191-1391) (1191-1391)

Cs-134 6.0 none

• LLD 0 Cs-137 6.3 none

• LLD 0 Ba-La-140 5.6 none

• LLD 0

("i/L) Ca 12 0.50 none T-24, Sandusky 0.99 (12/12) 0.93 (12/12) 0 21.0 mi. SE (0.86-1.15) (0.56-1.15)

('/L) K (stable) 12 none T-24, Sandusky 1.49 (12/12) 1.49 (12/12) 0 21.0 mi. SE (1.38-1.61) (1.38-1.61)

(pUVg) Sr-90/Ca 12 none T-24, Sandusky 1.03 (5/12) 1.03 (5/12) 0 21.0 mi. SE (0.83-1.35) (0.83-1.35)

(p:iVg) Cs-137/K 12 none ._ < LLD 0 am GB gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

' Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated In parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

r Non-routine results are those which exceed ten times the control station value.

164

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Ohio Reporting Period January-December, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F) Mean (F)c Routine (Units) Analvses8 Range' Locationd Range' Range' Results Ground Water GB (TR) 7 3.5 5.6 (2/3) T-225, Residence 5.6 (2/3) 4.5 (114)

(pCi/L) (5.5-5.6) 1.55 mi. NW (5.5-5.6)

H-3 7 330 <LLD - <LLD 0 Sr-89 7 0.9 <LLD - - <LLD 0 Sr-90 7 0.7 <LLD - - < LLD 0 GS Mn-54 15 < LLD - - <LLD 0 Fe-59 30 < LLD - <LLD 0 Co-58 15 <LLD - <LLD 0 Co-60 15 < LLD - - <LLD 0 Zn-65 30 <LLD - - <LLD 0 Zr-95 15 <LLD - - <LLD 0 Cs-134 10 <LLD < LLD 0 Cs-137 10 <LLD - <LLD 0 Ba-La-140 15 <LLD - < LLD 0 Edible Meat GS 2 (pCilg wet) K-40 0.10 2.84 (1/1) T-31, Roving 2.84 (1/1) 2.34 (1/1) 0 On-site location Nb-95 0.071 < LLD - < LLD 0 Zr-95 0.070 <LLD - < LLD 0 Ru-103 0.033 <LLD - <LLD 0 Ru-106 0.11 <LLD - <LLD 0 Cs-134 0.009 <LLD .- LLD 0 Cs-137 0.010 <LLD - <LLD 0 Ce-141 0.16 <LLD - <LLD 0 Ce-144 0.12 < LLD - <LLD 0

' GB = gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

• Non-routine results are those which exceed ten times the control station value.

165

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Ohio Reporting Period January-December, 2005

( County, State )

Indicator Location with Highest Control Number Sariple Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Range' Locationd Rangec Rangec Results" Fruit; and Sr-89 3 0.003 < LLD . < LLD 0 Vegetables Sr-90 3 0.002 < LLD < LLD 0 (pCiI.; wet) 1-131 3 0.025 < LLD . < LLD 0 GS 3 K-40 0.50 0.96 (2/2) T-25, Residence 1.01 (1/1) 0.88 (1/1) 0 (0.91-1.01) 1.6 mi. S Nb-95 0.010 < LLD < LLD 0 Zr-95 0.013 < LLD < LLD 0 Cs-134 0.010 < LLD - < LLD 0 Cs-137 0.008 < LLD - < LLD 0 Ce-141 0.014 < LLD < LLD 0 Ce-144 0.056 < LLD < LLD 0 BroaJ Leaf Sr-89 11 0.005 < LLD . < LLD 0 Vegetation Sr-90 11 0.003 0.003 (1/7) T-19, Residence 0.003 (1/4) < LLD 0 (pCUg wet) 1.0 mi. W 1-131 11 0.023 < LLD - < LLD 0 GS 11 K-40 0.50 2.57 (7/7) T-227, Roving 3.82 (3/3) 2.15 (4/4) 0 (1.58-5.07) Off-site location (2.44-5.07) (1.44-2.66)

Nb-95 0.014 < LLD < LLD 0 Zr-95 0.031 < LLD - < LLD 0 Cs-134 0.018 < LLD - - < LLD 0 Cs-137 0.015 < LLD - - < LLD 0 Ce-141 0.028 < LLD - < LLD 0 Ce-144 0.12 < LLD - < LLD 0

• GB = gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

r Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is Indicated in parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

Non-routine results are those which exceed ten times the control station value.

166

Davis-Besse Nuclear Power Station 2005 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program SummaVy.,

Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Ohio Reporting Period January-December, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)0 Mean (F)c Routine (Units) Analysesa Range' Locationd Rangec Rangec Results' Animal / GS 3 Wildlife Feed Be-7 0.31 1.38 (1/2) T-31, Roving 1.38 (1/1) 0.78 (1/1) 0 (pCig wet) On-site location K-40 0.10 1.83 (2/2) T-31, Roving 2.77 (1/1) 1.41 (1/1) 0 (0.89-2.77) On-site location Nb-95 0.028 < LLD <LLD c- 0 Zr-95 0.065 < LLD - < LLD 0 Ru-1103 0.034 < LLD - - <LLD 0 Ru-106 0.21 < LLD - - < LLD 0 Cs-134 0.026 < LLD - - <LLD 0 Cs-137 0.022 < LLD - - <LLD 0 Ce-141 0.073 < LLD - - < LLD 0 Ce-144 0.15 < LLD - < LLD 0 Soil GS 10 T-3, Site (pCVg dry) Be-7 0.64 0.77 (2/6) Boundary 0.80 (1/1) 0.74 (1/4) 0 (0.74-0.80) 1.4 mi. ESE K-40 0.10 10.38 (6/6) T-9, Oak Harbor 23.97 (1/1) 16.74 (4/4) 0 (10.10-(5.41-21.15) 6.8 mi. SW 23.97)

Nb-95 0.13 < LLD - - <LLD 0 Zr-95 0.13 < LLD - < LLD 0 Ru-103 0.068 < LLD - < LLD 0 Ru-106 0.4 < LLD - < LLD 0 Cs-134 0.074 < LLD - < LLD 0 Cs-137 0.019 0.13 (4/6) T-8, Farm 0.32 (1/1) 0.16 (4/4)

(0.042-0.32) 2.7 mi. WSW (0.11-0.23) 0 Ce-141 0.14 < LLD < LLD 0 Ce-144 0.25 < LLD < LLD 0

• GB = gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated In parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

• Non-routine results are those which exceed ten times the control station value.

167

Davis-Besse Nuclear Power Station 2005 Annual Radiological Enviromnental Operating Report Table 4.5 Radiological Environmental Monitoring Proggp Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 5D-346 Location of Facility Ottawa, Ohio Reporting Period January-Dece riber, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-T~pe Number of LLDb Mean (F)r Mean (F)c Mean (F)c Routine (Units) Analysesa Range' Locationd Rangec Rangec Results" Tre3ted GB (TR) 48 0.5 2.0 (24124) T-22, Carroll Twp. 2.2 (12/12) 1.7 (24/24) 0 Surface Water (0.9-3.2) WTP, 3.0 mi. NW (1.4-3.1) (0.7-3.2)

(pC:UL) H-3 16 330 < LLD - - <LLD 0 Sr-89 16 1.1 < LLD - - < LLD 0 Sr-90 16 0.8 < LLD - - < LLD 0 GS 16 Mn-54 15 < LLD - - < LLD 0 Fe-59 30 < LLD - < LLD 0 Co-58 15 < LLD - - < LLD 0 Co-60 15 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD < LLD 0 Cs-137 10 < LLD - < LLD 0 Ba-La-140 15 < LLD - < LLD 0 Untreated GB (TR) 95 1.0 2.3 (50/50) T-3, Site Boundary 3.3 (12/12) 2.2 (45/45) 0 Surface Water (1.0-6.1) 1.4 mi. ESE (1.7-6.1) (1.14.0)

(p',UL) H-3 95 330 753 (2/50) T-134, Lake Erie 976 (1/7) < LLD 0 (529-976) Unassigned Sr-89 20 1.2 < LLD - - < LLD 0 Sr-sO 20 0.9 <LLD - - <LLD 0 GS 95 Mn-54 15 <LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 15 < LLD - - < LLD 0 Co-60 15 < LLD - < LLD 0 Zn-65 30 < LLD - < LLD 0 Zr-Nb-95 15 < LLD - < LLD 0 Cs-134 10 < LLD - < LLD 0 Cs-137 10 < LLD - < LLD 0

_ Ba-La-140 15 < LLD -<LLD 0 a GB gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is Indicated in parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

• Non -routine results are those which exceed ten times the control station value.

168

Davis-Besse Nuclear Power Station 2005 Annual Radiological Enviromnental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary, )

Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Ohio Reporting Period January-December, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F) Mean (F)c Routine (Units) Analyses' Range' Location" Rangec Range' Results*

Fish GB 6 0.10 4.40 (3/3) T-33, Lake Erie 4.40 (3/3) 4.06 (3/3) 0 (pCVg wet) (3.77-5.55) 1.5 mi. NE (3.77-5.55) (3.53-4.49)

GS 6 K-40 0.10 2.69 (3/3) T-35, Lake Erie 2.71 (3/3) 2.71 (3/3) 0 (2.55-2.83) > 10 mi. (2.22-3.37) (2.22-3.37)

Mn-54 0.021 < LLD <c LLD 0 Fe-59 0.094 < LLD < LLD 0 Co-58 0.034 < LLD - <LLD 0 Co-60 0.019 < LLD - <LLD 0 Zn-65 0.064 < LLD <LLD c- 0 Cs-134 0.024 < LLD <LLD c- 0 Cs-137 0.026 <LLD - < LLD 0 Shoreline GS 8 Sediments K-40 0.10 13.10 (6/6) T-4, Site Boundary 14.88 (2/2) 11.66 (2/2) 0 (12.96- (11.40-(pC/g dry) (10.29-16.80) 0.8 mi. S 16.80) 11.91)

Mn-54 0.041 < LLD < LLD 0 Co-58 0.059 < LLD < LLD 0 Co-60 0.05 < LLD < LLD 0 Cs-134 0.08 < LLD < LLD 0 Cs-137 0.027 <LLD n<LLD 0

• GB = gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

• Non-routine results are those which exceed ten times the control station value.

169