ML030210229

Addendum to Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report & Radiological Effluent Release Report

ML030210229
Person / Time
Site:	Davis Besse  (NPF-003)
Issue date:	12/10/2002
From:	Myers L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
-nr, 2810
Download: ML030210229 (196)

Text

FENOC FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, Ohio 43449 Low W Myers Chief Operating Officer December 10, 419-321-7599 Fax 419-321-7582 P-7 Addendum 2002 Docket Number 50-346 License Number NPF-3 Serial 2810 RP 1.7.13 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Addendum to the Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report and Radiological Effluent Release Report Ladies and Gentlemen:

On April 29, 2002 (Serial 2781), FENOC submitted Davis-Besse 2001 Annual Radiological Environmental Operating Report and Radiological Effluent Release Report, During a recent review, we identified a typographical error on page 92, Table 17, Gaseous Effluents - Summation of All Releases, where we incorrectly reported a higher value for "Total lodines (1-131)" than actually released for the 3rd quarter, 2001. Please replace the previous copy of the 2001 Annual Radiological Environmental Operating Report with the enclosed corrected revision to the report.

Should you have any questions or require additional information, please contact Mr. Bruce L. Geddes, Supervisor - Nuclear Chemistry Services, at (419) 321-7388.

Very truly yours, AMP:AWB/ses Enclosures cc:

J. E. Dyer, Region III Administrator C. S. Thomas, DB-I Senior Resident Inspector J. B. Hopkins, DB-1 NRC/NRR Senior Project Manager Utility Radiological Safety Board of Ohio

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Serial 2810 Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station in this document. Any other actions discussed in the submittal represent intended or planned actions by Davis-Besse. They are described only as information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs (419-321-8450) at Davis-Besse of any questions regarding this document or associated regulatory commitments.

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Revision 1 Davis-Besse Nuclear Power Station January 1, 2001 through December 31, 2001 Davis-Besse Nuclear Power Station November 2002

Davis-Besse Nuclear Power Station 2003 Anlual Radiological Environmental Operating Report TABLE OF CONTENTS Title Page List of Tables iv List of Figures vi Executive Summary viii INTRODUCTION Fundamentals I

Radiation and Radioactivity 2

Interaction with Matter 3

Quantities and Units of Measurement 5

Sources of Radiation 7

Health Effects of Radiation 9

Health Risks 10 Benefits of Nuclear Power I

Nuclear Power Production 11 Station Systems 16 Reactor Safety and Summary 19 Radioactive Waste 19 Description of the Davis-Besse Site 22 References 24 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Introduction 26 Preoperational Surveillance Program 26 Operational Surveillance Program Objectives 27 Quality Assuranice 27 Program Description 28 Sample Analysis 32 Sample History Comparison 35 i

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

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

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environnental Operating Report List of Tables Table Page Title Number Number Risk Factors: Estimated Decrease in Average Life Expectancy 1

10 Sample Codes and Collection Frequencies 2

30 Sample Collection Summary 3

31 Radiochemical Analyses Performed on REMP Samples 4

33 Air Monitoring Locations 5

39 Milk Monitoring Location 6

44 Groundwater Monitoring Locations 7

46 Broadleaf Vegetation and Fruit Locations 8

47 Animal/Wildlife Feed Locations 9

48 Wild and Domestic Meat Locations 10 49 Soil Locations 11 51 Treated Surface Water Locations 12 57 Untreated Surface Water Locations 13 60 Shoreline Sediment Locations 14 61 Fish Locations 15 63 Themoluminescent Dosimeter Locations 16 69 Gaseous Effluents - Summation of All Releases 17 92 Gaseous Effluents - Ground Level Releases - Batch Mode 18 93 Gaseous Effluents - Grotund Level Releases - Continuous Mode 18 94 Gaseous Effluents - Mixed Mode Releases - Batch Mode 19 96 Gaseous Effluents - Mixed Mode Releases - Continuous Mode 19 97 Liquid Effluents - Summation of All Releases 20 99 Liquid Effluents - Nuclides Released - Batch Releases 21 100 Liquid Effluents - Nuclides Released - Continuous Releases 21 102 Solid Waste and Irradiated Fuel Shipments 22 104 Doses Due to Gaseous Releases for January through December 2001 23 106 Doses Due to Liquid Releases for January through December 2001 24 107 Annual Dose to The Most Exposed Member of The Public 2001 25 108 Closest Exposure Pathways Present in 2001 26 112 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters 27 114 iv

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

Davis-Besse Nuclear Powver Station 2001 Arnnual Radiological Environental Operating Report List of Figures Figure Page Description Number Number The Atom I

I Principal Decay Scheme of the Uranium Series 2

3 Range and Shielding of Radiation 3

4 Sources of Exposure to the Public 4

8 Fission Diagram 5

12 Fuel Rod, Fuel Assembly, Reactor Vessel 6

13 Station Systems 7

15 Dry Fuel Storage Module Arrangement 8

21 Map of Area Surrounding Davis-Besse 9

22 2001 Airborne Particulate Gross Beta 10 38 Air Sample Site Map 11 40 Air Sample 5-mile Map 12 41 Air Sample 25-mile Map 13 42 Gross Beta Groundwater 1982-2001 14 45 Cs-1 37 in Soil 1972-2001 15 50 Terrestrial Site Map 16 52 Terrestrial 5-mile Map 17 53 Terrestrial 25-mile Map 18 54 Gross Beta in Treated Surface Water 1977-2001 19 56 Gross Beta Concentration in Untreated Surface Water 1972-2001 20 59 Gross Beta Fish 1972-2001 21 62 Aquatic Site Map 22 64 Aquatic 5-mile Map 23 65 Aquatic 25-mile Map 24 66 Gamma Dose for Environmental TLDs 1973-2001 25 68 TLD Site Map 26 75 TLD 5-mile Map 27 76 TLD 25-mile Map 28 77 Exposure Pathways 29 85 vi

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

Davis-Besse Nuclear Power Station 2001 Aal Radiological Environmental Operating Report Executive Summary The Annual Radiological Environmenital Operating Report (AREOR) is a detailed report on the Environmental Monitoring Programs conducted at the Davis-Besse Nuclear Power Station from January 1 through December 31, 2001. This report meets all of the requirements in Regulatory Guide 4.8, Davis-Besse Teclnical Specifications 6.9.1.10, and Davis-Besse Offsite Dose Calcu-lation Manual (ODCM) Section 7.1.

Reports included are the Radiological Environmental Monitoring Program, Land Use Census, and the Non-Radiological Environmental Programs, which consist of Meteorological Monitoring, Land and Wetland Management, Water Treatment, Chemical Waste Management, and Waste Minimization and Recycling. This report also includes the Radiological Effluent Release Report for the reporting period of January 1 through December 31, 2001.

Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is established to monitor the ra-diological condition of the environment around Davis-Besse. The REMP is conducted in accor-dance with Regulatory Guide 4.8, Davis-Besse Technical Specification 6.8.4.d and the Davis-Besse ODCM Section 6.0. This program includes the sampling and analysis of enviromnental 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 ad analysis progran provided data on ra-diation and radioactivity normally present in the area as natural background. Davis-Besse has continued to monitor the environment by sampling air, groundwater, milk, edible meat, fruit and vegetables, animal feed, soil, drinking water, surface water, fish, shoreline sediment, and by di-rect measurement of radiation.

Samples are collected from indicator and control locations. Indicator locations are within ap-proximately 5 miles of the site and are expected to show naturally occurring radioactivity plus any increases of radioactivity that might occur due to the operation of Davis-Besse. Control lo-cations are farther avay from the Station and are expected to indicate the presence of only natu-rally occurring radioactivity. The results obtained from the samples collected from indicator locations are compared with the results from those collected from control locations and with the concentrations present in the environment before Davis-Besse became operational. This allows for the assessment of any impact the operation of Davis-Besse might have had on the surround-ing environment, Over 2000 radiological environmental samples were collected and analyzed in 2001. An expla-nation for the sample anomalies for this reporting period is provided on page 36.

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

viii

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

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

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

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

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

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

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

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

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

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

Liquid Effluents:

Maximum Individual Whole Body Dose Maximum Individual Significant Organ Dose Total Integrated Population Dose Average Dose to the Individual 7.75E-02 mrem (0.0775 mrem) 8.03E-02 mrem (0.0803 mrem) 7.31E-01 person-rem (0.731 person-rem) 3.35E-04 mrem (0.000335 mrem)

Gaseous Effluents:

Maximum Individual Whole Body Dose due to 1-131, H-3 and Particulates with half-lives greater than 8 days Maximum Significant Organ Dose due to 1-131, H-3 and Particulates with half-lives greater than 8 days Total Integrated Population Dose due to 1-131, H-3 and Particulates with half-lives greater than 8 days Average Dose to an individual in the population due to 1-13 1, H-3 and Particulates with half-lives greater than 8 days Maximum Individual Skin Dose due to noble gases Maximum individual Whole Body Dose due to noble gases Total Integrated Population Dose due to noble gases Average Dose to individual in population due to noble gases 1.99E-03 mrem (0.00199 mrem) 2.54E-03 mrem (0.00254 mrem) 7.02E-03 person-rem (0.00702 person-rem) 3.2 1E-06 mrem (0.00000321 mrem) 9.27E-04 mrad (0.000927 inrad) 2.7 1E-04 mrad (0.000271 mrad) 5.03E-04 person-rem (0.000503 person-rem) 2.30E-07 mrem (0.000000230 inrem) x

Davis-Besse Nuclear PoweL Station 2001 Annual Radiological Environmental Operating Report The Total Body doses to an individual and population in an unrestricted area due to direct ra-diation from Davis-Biesse 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.

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

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

Non-Radiological Environmental Programs Meteorological Monitoring The 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, 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 99.27 %.

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

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

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

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

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

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

xi

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

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

As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse re-ported hazardous products and chemicals to local fire departments and local and state plan-ning commissions.

As part of the program to remove PCB fluid from Davis-Besse, all electrical transformers have been retrofilled and reclassified as non-PCB transformers.

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

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

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

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

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

xii

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

the number and types of analyses performed, the lower limit of detection for each analysis,

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

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

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

xiii

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Introduction~~~~~~~~~~~~~~~~~~~

i

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Introduction Coal, oil, natural gas and hydropower are used to run ibis nation's electric generating stations; however, each method has its drawbacks.

C'oal-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. Hydropower 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 stations has a very small inpact 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 Wild-life Refuge. In order to provide better understanding of this unique sotrce of energy, background information 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-cleis 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

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er have a strong attraction for each other. 'This holds the atom together. Other attractive forces between the protons and neutrons Fgu : An atom conists of two pans a nucleus forces between th rtn n

etosconaining positively charged protoms and electrically keep the densely packed protons from repel-eural neutrons and one or mo negativly chared electons orbiting the nucleus. Pto n d neutrons ling each other, and prevent the nucleus are nerly identical in size and weight, while eath is from breaking apart.

about 2000 dotes heavier than an electron.

I

Davis-Besse Nuclear Power Station 2001 Annual Radiological Eivironmental 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 forrn of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation is another type of radiation and has similar properties to those of the examples listed above.

Ionizing radiation consists of both electromagnetic radiation and particulate radiation. Elec-tromagnetic radiation is energy with no measturable 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 filly in the Range and Shielding section.

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

2

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

23su 4.5x 10 v 234U

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

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

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

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

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

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

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Neutrun lAC InAC`TIVE MATERIAL PAPER ALUrIINUtM LeAD CONCRETE Figure 3: As radiation travels, it collides and interacts with other atomrs and loses energy. Alpha panicles can be stopped by a sheet of paper, and beta particles by a thin sheet of atumirnum. Gamma radiation is shielded by highly dense naterials such as lead, while hydrogenous materials (those containing hydrogcn atoms), such aS water and concete, arc used to stop ncuons.

Gamma rays are pure energy anid 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.

4

Davis-Besse Niclear Power Station 2001 Annual Radiological ELvironmental 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, neutrons are not of environmental concem 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 radlioactivity and its ef-fects. Tree 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. Each 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, te amount of material required to produce one curie varies. For example, one gram (1/28th of an ounce) of radiun-226 is the equivalent of one curie of activity, but it would take 9,170,000 grams (about 10 tons) of thorium-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.

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 5

Davis-Besse Nuclear Power Stationi 2001 Anntal Radiological Environmental Operating Report Rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material (I Rad = 100 ergtgm).

The rate of absorbed dose is usually given in Radlhr.

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).

Aa MWnuqie tWzSerKqmWq,R te qiSscoru9srdivalent uses the quality factor for alpha radiation, which is equal to 20. Thus, I Rad of alpha radiation is approximately equal to 20 rem. Beta and gamma radiation each have a quality factor of 1, therefore one Rad of either beta or ganuna radiation is approximately equal to one rem. Neutrons have a quality factor ranging from 2 to 0. One rem produces the same anount of biological damage, regardless of the source. In terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit, the millirem, is oflen used. One millirem (mrei) 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 measued 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 lose equivalent is a measure of the dose received from any radioactive ma-terial taken into the body. It is calculated from the sum of the products of the committed dose equivalent to the organ or tissue multiplied by the organ or tissue-weighting factor. CEDE ac-counts for all the dose delivered during the entire tine the radioactive material is in the body.

6

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report 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. hi 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 natturally 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 re-sults from the decay of radium-226, a member of the uranium-238 decay series. Since uranium 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 concerns stem from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it de-cays, 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 witl exposure to radon is an in-creased 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 Protection and Measurement (NCRP), over half of the radiation dose the average American receives is attributed to radon.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operatinig Report TERRE L

8%

RADON 55%

SOURCES OF EXPOSURE COSMIC TO THE PUBLIC E%

INTERNL rrTh.M.

11%

MANMADE 1i%

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

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

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

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

Man-Made Radiation In addition to naturally occurring cosmic radiation and radiation from naturally occurring radio-activity, people are also exposed to man-made radiation. The largest sources of exposure include medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man-made exposure.

Fallout radionuclides include strontium-90, cesium-137, and tritium. Less than one percent of the annual dose a member of the public re-ceives is a result of having electricity generated by nuclear power.

8 MANMADE

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Health Effects of Radiation The effects of ionizing radiation on human health have been under study for more than 80 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 re-late the biological effects of irradiated laboratory animals to the potential health effects on hu-mans.

The effects of radiation on humans can be divided ito two categories, somatic and genetic. So-matic effects are those which develop in the directly exposed individual, including an unbom 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 long periods of time.

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

Genetic effects could occur as a result of ionizing radiation interacting with the genes in the hu-man cells. Radiation (as well as common chemicals) can cause physical changes or mutations in the genes. Chromosome fibers can break and rearrange, causing interference with the nonmal 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, tle broken ends from one break could join incorrectly with those from another. This could cause translocations, inversions, rings, and other types of structural rearrangements. When this 9

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

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

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

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

Table 1: Risk Factors: Estimated Decrease in Average Life Expectancy Overweight by 30%:

3.6 years Cigarette smoking:

I pack/day 7.0 years 2 packs/day 10.0 years Heart Disease:

5.8 years Cancer:

2.7 years City Living (not rural):

5.0 years All operating commercial nuclear power plants totaled:

less than 12 minutes 10

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

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

nuclear power has an excellent safety record dating back to 1957, when the first commercial nuclear power station began operating, uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States, Nuclear power is the cleanest energy source for power stations that use steam to produce electricity. There are no greenhouse gases or acid gases produced when using nuclear fuel.

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

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

What is Fission?

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

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Davis-Besse Nuclear Power Stationi 2001 Annual Radiological Environimental Operating Report h.t

/

af Bombangg Neutron 1T Atom

/

~j'~%r~g heatroe Fragment\\A Figur S: Whcn

• heavy aon, such s utnium-235 is split or fissioned, het, free neutrons. and fission fragments nsult. The fre neutrons can then strike neighboring Aoms causing them o fission also. In te proper cnvitrtnment.

this process cas continue indefinitely in chain reaction.

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

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

After milling the ore to a granular form and dissolving out the uranium with acid, the uranium is converted to uranium hexafluoride (UF6). U 6 is a chemical form of uranium that exists as 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 concentration of U-235. The enriched gaseous UF6 is then converted into powdered uranium dioxide (UO 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 these pellets are placed into a 12-foot long metal tube made of zirconium alloy. The tubes constitute the fuel cladding. The fuel cladding is highly resistant to heat, radiation, and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods.

The Reactor Core Two hundred eight fuel rods comprise a single fuel assembly. The reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fiel rods, the fuel assembly also contains 16 vacant holes for the in-sertion of control rods, and one vacant hole for an incore-monitoring probe. This probe monitors temperature and neutron levels in the fuel assembly. The Davis-Besse reactor vessel, which contains all the fuel assemblies, weighs 838,000 pounds, has a diameter of 14 feet, is 39 feet high, and has steel walls that are 8 V2 inches thick.

ID Li 1Q11 I0 REAclo%VEsl.

Figure 6: The reactor core at Davis-Besse contains 177 fuel assemblies. Each assembly contains 208 fuel rods.

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

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

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

In 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 2001 Annual Radiological Enviromnental Operating Report Davis-Besse Nuclear Power Station Unit No. 1 AUXILIARY BUILDING CONTAINMENT COOLING TOWER Figure 7: Station Systems C (0-15

1..

Davis-Besse Nuclear Power Station 2001 Annual Radiological Enviroimental 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 contaimnent vessel. In the event that the integrity of the containment vessel is compromised (e.g., a crack develops), this negative pressure boundary ensures that any airborne radioactive contamination present in the containment vessel is prevented from leaking out into the environ-ment. This is accomplished by maintaining the pressure inside the shield building lower than that outdoors, thus forcing clean outside air to leak in, while making it impossible for the con-taminated air between the containment vessel and the shield building to leak out. The contain-ment vessel is the third in a series of barriers that prevent the release of fission products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel clad-ding itself The second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and associated piping.

Tle 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 tLbes 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 and under 1,100 psi pressure. At this pressure, the water can easily boil into steam as it passes over the tubes containing the primary coolant water.

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

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Davis-Besse Nuclear Power Station 2001 AnnLual 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 Figrure 7) to rotational energy of the turbine generator shaft. The turbine at Davis-Besse is actually composed of one six-stage high-pressure trbine 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 northem Ohio.

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

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

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

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

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

In order to cool the water back down to around 700F, the Circulating Water enters the Cooling Tower about 40 feet above the ground. The water is sprayed evenly over a series of baffles called filsheets, which are suspended vertically in the base of the tower. A natural draft of air blowing upward through these baffles cools the water by the process of 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 wanner 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 upon 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 Figture 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 2001 Annial Radiological Environmental Operating Report Reactor Safety and Summary Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. Also, many safety features are equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the local environment. Davis-Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features. If one system should fail, there are still back-up systems to assure the safe operation of the Station.

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

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

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

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

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

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

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

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Davis-Besse Nuclear Power Station 2001 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 fiuel every 24 months. All the used fiel 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 supposed 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 canisters. 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.

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

Ii Figure 8: Dry Fuel Storage Module Arrangement 21

Davis-Besse Nuclear Power Station 2001 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 (Figire 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 fanned 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.

L.k. ErK.

.. 6 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.

n 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 Refiuge.

22

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

Port Clinton - 10 miles southeast, population 6,391 Oak Harbor - 7 miles south, population 2,841 Rocky Ridge - 7 miles west southwest, population 389 Toledo (nearest major city) - 25 miles west, population 313,619 There are some residences along the lakeshore used mainly as summer homes. However, the major resort area of the county is farther east, around Port Clinton, Lakeside, and the Bass Is-lands.

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

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

23

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmenital Operating Report References I. "Basic Radiation Protection Criteria," Report No. 39, National Council on Radiation Protec-tion and Measurement, Washington, D.C. (January 1971).

2. "Cesium-l 37 from the Environment to Man: Metabolism and Dose," Report No. 52, National Council on Radiation Protection and Measurements, Washington, D.C. (January 1977).

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

Columbia, MD. (1987).

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

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

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

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

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

Seminars in Nuclear Medicine, Vol. XVIIJ, 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 2001 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," Fdison 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 Measuremet, Washington, D.C. (De-cember 1987).

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

(July 1989).

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

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

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

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

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

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

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

25. " Exposure 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 Environtmnental Monitoring Program

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at Davis-Besse for several reasonis: 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 surrotunding area, and to determine compliance with applicable radiation protection guides and standards. The REMP was established in 1972, five years before the Station became operational. This preop-erational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of Davis-Besse. After Davis-Besse became op-erational in 1977, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas.

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

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 detailed summary of the analyses performed during this reporting period, is also provided.

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

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

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

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

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

• to fulfill the obligations of the radiological surveillance sections of the Sta-tion's Technical Specifications and Offsite Dose Calculation Manual to determine whether any significant increase in the concentration of radionu-clides in critical pathways occurs to identify and evaluate the buildup, if any, of radionuclides in the local envi-ronment, or any changes in normal background radiation levels

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

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

• performing audits of contractor laboratories which analyze the environmental

samples,

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

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

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

Davis-Besse Nuclear Power Station 2001 Annual Radiological 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 NRC and the Ohio Department of Health (ODH) also perform independent environmental monitoring in the vicinity of Davis-Besse. The types of samples collected and the sampling locations used by the NRC and ODH were incorporated in Davis-Besse's REMP. Hence, the analytical results from the different prograns can be compared. This practice of comparing results from identical samples, collected and analyzed by different parties, provides a valuable too] to verify the quality of the laboratories analytical procedures and the data generated.

In 1987, 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 pairing 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 airbome particulates and airbome radio-iodine terrestrial -- including samples of milk, groundwater, broad leaf vegetation, fruits, animal/wildlife feed, soil, and wild and domestic meat aquatic -- including samples of treated and untreated surface water, fish, and shoreline sediments direct radiation -- measured by thermoluminescent dosimeters All environmental samples are labeled using a sampling code. Table 2 provides the sample codes and collection frequency for each sample type.

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

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

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

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

29

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 2: Sample Codes and Collection Frequencies Sample Type Airbome Particulate Airbome Iodine Thermoluminescent Dosimeter Milk Groundwater Broadleaf Vegetation Surface Water - Treated Surface Water -

Untreated Fish Shoreline Sediment Soil Animal/Wildlife Feed Meat-Domestic Meat-Wild Fruit Sample Code AP Al TLD MEL WW BLV SWT sWU FIS SED Sol DFE/WFE DME WME FRU Collection Frequency Weekly Weekly Quarterly, Annually Monthly (semi-monthly during grazing season)

Quarterly Monthly (when available)

Weekly Weekly (lake water - monthly in summer)

Annually Semiannually Semiannually Annually Annually Annual]ly Annually 30

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 3: Sample Collection Summary Collection Type*/

Frequency**

Number of Locations Number of Samples Collected Number of Samples Missed Atmospheric Airbome Particulates Airbome Radioiodine Terrestrial Milk (Jan.-Dec.)

Groundwater Domestic Meat Wild Meat Broadleaf Vegetation Fruit Soil Animal/Wildlife Feed Aquatic Treated Surface Water Untreated Surface Water Fish (3 species)

Shoreline Sediments Direct Radiation Themnoluminescent Dosimeters (TLD)

C/W CAW G/M G/Q***

G/A G/A G/M G/A G/SA G/A Comp/WM G/WM***

G/WM***

Comp/WM G/M G/A G/SA C/Q***

C/A***

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

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

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

• • • • Hazardous weather conditions prevented sample collection SM Senimonthly; M = Monthly; Q Quarterly; SA = Seniannually; A = Annually 31 Sample Type (Remarks) 10 10 1

2 2

2 3

3 to 5

4 1

3 3

5 2

4 89 89 519 519 12 7

2 2

9 3

20 5

208 52 156 156 35 6

8 339 82 l

1 0

0 0

0 0

0 0

0 0

0 0

0 0

0 3

7

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

Gross beta analysis measures the total amount of beta emitting radioactive material present in a 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.

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

Gamma spectral analysis identifies each gamma emitting radionuclide present in the sample, and 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 hItroduction Section, tritium is an isotope of hydrogen that emits low energy beta particles.

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

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

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

32

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

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

Sample Type Analyses Performed Aquatic monitoring Untreated Surface Water Treated Surface Water Fish Shoreline Sediment Direct Radiation Monitoring Thermoluminescent Dosimeters Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Iodine-13 1 Gross Beta Gamma Spectral Gamma Spectral Ganma Dose Sample History Comparison The measurement of radioactive materials present in the environment will depend on factors such as weather or variations in sample collection techniques or sample analysis. This is one reason why the results of sample analyses are compared with results from other locations and from ear-lier years. Generally, the results of sample analyses are compared with preoperational and op-erational data. Additionally, the results of indicator and control locations are also compared.

This allows REMP personnel to track and trend the radionuclides present in the environrment, to assess whether a buildup of radionuclides is occurring and to deternine the effects, if any, the operation of Davis-Besse is having on the environmenit. 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 2001 Aual Radiological Environmenital Opeiting 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 1.978 from nuclear weapons testing, and in 1986 (0.12 to L2 pico-curies per cubic meter) from the nuclear accident at Chenobyl.

Terrestrial Monitoring:

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

This beach well is not used for drinking water purposes.

Milk:

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

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

Broadleaf Vegetation and Fruits: Only naturally occtuing radioactive mate-rial and material from nuclear weapons testing have been detected.

• Soil: Only natural background and material from nuclear weapons testing and the 1986 nuclear accident at Chemobyl have been detected.

AnimaUWildlife Feed: Only natural background and material from weapons testing have been detected.

Aquatic Monitoring

• Surface Water (Treated and Untreated): Historically, tritium has been de-tected sporadically at low levels in treated and untreated surface water at both control and indicator locations. In 2001, it was detected once above the de-tection limit of 330 pCi/L at T-22 Treated Surface Water indicator site at a concentration of 593 pCi/L, and twice at Indicator site T-3 for Untreated Sur-face Water (439 and 986 pCi/L). This could be from the operation of Davis-Besse, however, it is only a fraction of the allowable effluent concentration limit of 20,000 pCi/L in an uirestricted area, as stated in 40CFRI41.

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

35

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

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

2001 Program Anomalies Provided below is a

description of 2001 environmental sample collection irregularities:

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

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

On 3115101, the tygon tubing on the T-22 automatic water sampler failed. The sample size was sufficient, but smaller than usual. New tubing was installed on the sampler.

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

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

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

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

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

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

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

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

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

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

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

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

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

The airbome samples are sent to an offsite contract laboratory for analysis. At the laboratory, the airbome 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 occuring short-lived radionuclides. However, due to the short half-life of iodine-131 (approximately eight days), the airborne radioiodine cartridges are analyzed upon receipt by the contract laboratory.

Airborne Particulate Davis-Besse continuously sanples air for airbome radionuclides at ten locations. There are six indicator locations including four around the site boundary (T-l, T-2, T-3, and T-4), one at Sand Beach (T-7), and another at a local farm (T-8). There are four control locations, Oak Harbor (T-9), Port Clinton (T-l1), Toledo (T-12) and Crane Creek (T-27). Gross beta analysis is per-formed on each of the weekly samples. Each quarter, the filters from each location are combined (composite) and analyzed for gamma emitting radionuclides, strontium-89 and strontium-90 beta-emitting radionuclides were detected at the indicator and control locations at average con-centration of 0.025 pCi/m3 and 0.025 pCi/m3, respectively. Beryllium-7 was the only gamma emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites.

37

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

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

Airbome 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 garmnma analysis. There was no detectable iodine-I 31 above the LLD of 0.07 pCi/m 3.

2001 Atom NIUeAD Gross Bida 0.04 aoss 0.03 0025 QaG2 0D.D......................

Oam.--

Jmary FdXLW K

A Ibl MN lvJr J"S 5,y AMxt wr W

Nerb 1wnta 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 2001 Almual Radiological Environmental Operating Report Table 5: Air Monitoring Locations Sample Location Number T-1 T-2 T-3 T-4 T-7 T-8 T.-9 Type of Location I

I I

I I

I C

T-l1 C

T-12 C

T-27 C

Location Description Site boundary, 0.6 miles ENE of Station Site boundary, 0.9 miles E of Station Site boundary, 1.4 miles ESE of Station Site boundary, 0.8 miles S of Station Sand Beach, main entrance, 0.9 miles NW of Station Earl Moore Farm, 2.7 miles WSW of Station Oak Harbor Substation, 6.8 miles SW of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 23.5 miles WNW of Station Crane Creek State Park, 5.3 miles WNW of Station I = Indicator C Control 39

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Davis-Besse Nuclear Power Stution 2001 Annual Radiological Environrnental Operatilg RepoTt 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 infonnation 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 up-per atmosphere and as a result of routine release from nuclear facilities Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere Cesium-137, a manmade radionuclide which has been deposited in the envi-ronment, (for example, in surface soils) as a result of fallout from nuclear weapons testing and routine releases from nuclear facilities Potassium40, a naturally occurring radionuclide nonnally found throughout the environment (including in the hunan 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 amotunts from nuclear fa-cilities The radionuclides listed above are expected to be present in many of the environmental samples collected in the vicinity of the Davis-Besse Station. The contribution of radionuclides from the operation of Davis-Besse is assessed by comparing sample results with preoperational data, op-erational data from previous years, control location data, and the types and amounts of radioac-tivity normally released from the Station in liquid and gaseous effluents.

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

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

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

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

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

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

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

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

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

Table 6: Milk Monitoring Location Sample Location Type of Number Location Location Description T-24 C

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

44

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

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

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 7: Groundwater Monitoring Locations Sample Location Type of Number Location Location Description T-27 C

Crane Creek State Park, 5.3 miles WNW of Station T-225 I

Ben Shultz residence, 1.55 miles NW of Station C = control I= indicator Broadleaf Vegetation and Fruit Samples Fruits and broadleaf vegetation also represent a direct pathway to humans. Fruits and broadleaf vegetation may become contaminated by deposition of airborne radioactivity (nuclear weapons fallout or airborne releases from nuclear facilities) or from irrigation water drawn from lake wa-ter receiving liquid effluents (hospitals, nuclear facilities, etc.). Radionuclides from the soil may be absorbed by the roots of the plants and become incorporated into the edible portions. During the growing season, edible broadleaf vegetation samples, such as kale and cabbage, are collected from gardens and farms in the vicin-ity of the Station. Fruit, such as apples, is collected from or-chards in the vicinity of Davis-Besse.

In 2001, broadleaf vegetation samples were collected at two indicator locations (T-17 and T-19) and one control location (T-37). Fruit samples were collected at two indicator locations (T-8 and T-25) and one control location (T-209).

Broadleaf vegetation was collected once per month during the growing season and consisted of cabbage. The fruit collected was apples. All samples were analyzed for gamma emitting radionuclides, strontium-89, strontiuni-90, and iodine-131.

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

46

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 8: Broadleaf Vegetation and Fmit Locations Sample Location Type of Number Location Location Description T-8 I

Moore Farm, 2.7 miles WSW of Station T-17 I

J. Sobieralski, 1.8 miles SSE of Station T-19 I

B. Skinner, 1.0 mile W of Station T-25 I

Witt Farm, 1.6 miles south of Station T-37 C

Bench Farm, 13.0 miles SW of Station T-209 C

Roving Control Location I = indicator, C = control Animal/Wildlife Feed Samples Vegetation consumed by wildlife, and feed consumed by domestic animals can provide an indi-cation of airborne radionuclides deposited in the vicinity of the Station. Analyses of ani-mal/wildlife feed samples can also provide data for determining radionuclide concentration in the food chain. Domestic animals feed samples are collected at two domestic meat-sampling loca-tions. Wildlife feed samples are collected from the Navarre Marsh and from a local marsh within five miles of the Station. As in all terrestrial samples, naturally occurring potassium-40, cosmic ray-produced radionuclides such as beryllium-7, and fallout radionuclides from nuclear weapons testing may be present in the feed samples.

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

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

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

47

Davis-Besse Nuclear Povev Stationi 2001 Annual Radiological Environnental Operating Report Table 9: Animal/Wildlife Feed Locations Sample Location Type of Number Location Location Description T-3 1 I

Davis-Besse, onsite roving location T-32 C

Roving offsite location - collected 7.0 miles W of station in 2001 T-34 C

Brian Lowe residence, 8.2 miles W of the Station T-197 I

Lochotzki residence 4.0 miles W of the Station Lemon Road T-198 I

Toussaint Creek Wildlife Area 4.0 miles WSW of the Station I = indicator C = control Wild and Domestic Meat Samples Sampling of domestic and wild meat provides information on environmental radionuclide con-centrations that humanis may be exposed to through an ingestion pathway. The principle path-ways for radionuclide contamination of meat animals include deposition of airbome radioactivity in their food and drinking water and contamination of their drinking water from radionuclides released in liquid effluents.

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

Meat samples were taken in 2001 as follows:

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

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

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

48

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environnental Operating Report Table 10: Wild and Domestic Meat Locations Sample Location Type of Number Location Location Description T-31 1

Onsite roving location T-34 C

Brian Lowe residence, 8.2 miles W of the the Station T-197 I

Lochotzki residence, Lemon Road, 4.0 miles W of the Station T-210 C

Roving offsite location (5.5 mi. WNW of the Station in 2001)

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

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

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

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

All soil samples were analyzed for gamma emitting radionuclides. The results show that the only gailma emitter detected in addition to naturally occurring Be-7 and.K-40 was Cs-137. Cs-137 was found in both indicator and control locations at average concentrations of 0.13 pCi/g dry and 0.23 pCi/g dry, respectively. The concentrations were similar to that observed in previous years (Figure 15).

49

Davis-Besse Nuclear Power Station 2001 Anual Radiological Enviromuental Operating Report Cs-137 in Soil 1972-2001 1.15 1.1 1.05 1

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Location Description Site boundary, 0.6 miles ENE of Station Site boundary, 0.9 miles E of Station Site boundary 1.4 miles ESE of Station Site boundary 0.8 miles S of Station Sand Beach, main entrance, 0.9 miles NW of Station Moore Farm, 2.7 miles WSW of Station Oak Harbor Substation, 6.8 miles SW of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 23.5 miles WNW of Station Crane Creek State Park, 5.3 miles WNW of Stationi 51

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Davis-Besse Nuclear Power Station 2001 AnmlS Radiological Environmental Operating Report Aquatic Monitoring Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-offlsoil 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 intemal. External exposure can occur from the surface of the water, shoreline sediments and from immersion (swimming) in the water. Internal exposure can occur from ingestion of radio-nuclides, either directly from drinking water, or as a result of the transfer of radionuclides through the aquatic food chain with eventual consumption of aquatic organisms, such as fish. To monitor these pathways, Davis-Besse samples treated surface water (drinking water), untreated surface water (lake or river water), fish, and shoreline sediments.

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

Samples of treated surface water were collected from two indicators (T-22B and T-50) and two control locations (T-II and T-I 2A). These locations include the water treatment facilities for Carroll Township, Erie industrial Park, Port Clinton and Toledo. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta emitting radionu-clides. The samples were also composited in a quarterly sample and analyzed for strontium-89, strontium-90, gamma emitting radionuclides, and tritium. One QC sample was collected from a routine location, which was changed each month.

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

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

There was good agreement between the routine and QC locations.

55

Davis-Besse Nuclear Power Station 2001 Amiual Radiological Environmental Operating Report GoSs Bea in Truted Surw Vier 1972-2301 4.5

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56

Davis-Besse Nuclear Power Station 2001 Annual Radiological Envirornental 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 23.5 miles WNW of Station T-22B I

Carroll Township water sampled at Davis-Besse T-50 I

Erie Industrial Park, Port Clinton, 4.5 miles SE of Station T-143 QC Quality Control Site I = indicator, C = control, QC = quality control Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to hu-mans from extemal expostue from the lake surface as well as from immersion in the water. It also provides information on the radionuclides present, which may affect drinking water, fish, and irrigated crops.

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

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

57

Davis-Besse Nuclear Power Station 2001 Annual Radiological Enviromnental Operating Report Summer Program The sunmer 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, anld swimming. These samples are obtained monthly in areas along the shoreline of Lake Erie, and analyzed for beta emitting radioactivity, tritium, strontium-89, strontium-90 and gamma-emitting radioniclides.

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

During 2001, tritium was detected in 2 untreated surface water samples, ranging from 439 pCi/L to 986 pCi/L (well below the established 40CFR141 limit of 20,000 pCi/L). Both were at indi-cator locations, and could be due to the operation of the Davis-Besse Nuclear Power Station.

Cesium-I 37 was not detectable in samples of untreated water above the LLD of 6.4 pCi/L.

58

Davis-Besse Nuclear Power Station 2001 Ariual Radiological Euvironmental Operating Report Gross Beta Concentration in Untreated Surface Water 1977-2001 4

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

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Davis-Besse Nuclear Power Station 2001 Aual Radiological Environmental Operating Report Table 13: Untreated Surface Water Locations Sample Location Type of Number Location Location Description T-3 I

Site boundary, 1.4 miles ESE of Station T-1 1 C

Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 C

Toledo Water Treatment Plant, sample taken from intake crib, 11.25 miles NW of Station T-22A I

Carroll Township Water Intake, Humphrey Rd.,

3.0 miles NW of Station T-50 I

Erie Industrial Park, Port Clinton, 4.5 miles SE of Station T-132 I

Lake Eric, 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 = indicator, C control 60

Davis-Besse Nuclear Power Station 2001 Anual Radiological Environmental Operating Report Shoreline Sediment The sampling of shoreline sediments can provide an indication of the accumulation of undis-solved radionuclides which may lead to internal exposure to humans through the ingestion of fish, through resuspension into drinking water supplies, or as an external radiation source from shoreline exposure to fishennen 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). Shoreline sediment was collected with a shovel. All samples were analyzed for ganima emitting radionuclides.

Naturally occurring potassium-40 was detected at both control and indicator locations. Cs-137 was not detected at any locations. These results are similar to previous years.

Table 14:

Sample Location Number T-3 Type of Location I

I C

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

Davis-Besse Nuclear Power Station 2001 Aunual 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 nuclides which may be detected in fish include naturally occurring potassium-40, as well as cesium-l 37, and strontium-90.

Depending upon the feeding habit of the species (e.g., bottom-feeder versus predator), results from sample analyses may vary.

With the aid of a local commercial fishemiani, 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 they are a popular sport fish and white perch or white bass are collected because they are an important commercial fish. Carp are collected be-cause they are bottom feeders where contaminants may settle.

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

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Lake Erie, within 5 miles radius of Station T-35 C

Lake Erie, greater than 10 mile radius of Station I = indicator C= control 63

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Davis-Besse Nuclear Power Station 2001 Aniual 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 (T.LDs). TLDs are small devices which store radiation dose information.

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

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

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

67

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Gamma Dose for Environmental TLDs 1973-2001

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I I

I I

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I I

Location Description Site boundary, 0.6 miles ENE of Station Site boundary, 0.9 miles E of Station Site boundary, 1.4 miles ESE of Station Site boundary, 0.8 miles S of Station Site boundary, 0.5 miles W of Station Site boundary, 0.5 miles NNE of Station Sand Beach, main entrance, 0.9 miles NW of Station Earl Moore Farm, 2.7 miles WSW of Station Oak Harbor Substation, 6.8 miles SW of Station Site boundary, 0.5 miles SSW of Station near warehouse Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 23.5 miles WNW of Station Sandusky, 21.0 miles SE of Station Crane Creek State Park, 5.3 miles WNW of Station Site boundary, 0.6 miles ENE of Station Site boundary 1.2 miles ENE of Station Site boundary, 0.7 miles SE of Station Site boundary, 0.6 miles SSE of Station Site boundary, 0.8 miles SW of Station 69

Davis-Besse Nuclear Power Station 2001 Anual Radiological Environmental Operating Report Table 16:

Sample Location Number T-43 T-44 T-45 T-46 T-47 T-48 T-49 T-50 Thermoluminescent Dosimeter Locations (continued)

Type of Location I

I I

I I

I I

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

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

Sample Location Type of Number Location Location Description T-71 I

Site boundary, 0.1 mile NNW of Station T-73 I

Site boundary, 0.1 mile WSW of Station T-74 I

Site boundary, 0.1 mile SSW of Station T-75 I

Site boundary, 0.2 mile SSE of Station T-76 I

Site boundary, 0.1 mile SE of Station T-80 QC Quality Control Site T-81 QC Quality Control Site T-82 QC Quality Control Site T-83 QC Quality Control Site T-84 QC Quality Control Site T-85 QC Quality Control Site T-86 QC Quality Control Site T-88 QC Quality Control Site T-87 QC Quality Control currently located in lead pig, DBAB annex T-89 QC Quality Control Site T-90 I

Site Persornel Processing Facility T-91 I

State Route 2 and Rankie Road, 2.5 miles SSE of Station T-92 1

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 2001 Annual Radiological Environmental Operating Report Table 16:

Sample Location Number T-100 T-111 T-112 T-113 T-114 T-115 T-116 T-117 T-118 T-1 19 T-120 T-121 T-122 T-123 T-124 T-125 T-126 T-127 Thermoluminescent Dosimeter Locations (continued)

Type of Location C

C I

QC QC QC QC QC QC QC QC I

I I

C I

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Location Description Ottawa County Highway Garage, Oak Harbor, 6.0 miles S of Station Toussaint North Road, 8.3 miles WSW of Station Thompson Road, 1.5 miles SSW of Station Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site State Route 19, 2.0 miles W of Station Duff Washa and Humphrey Road, 1.7 miles W of Station Zetzer Road, 1.6 miles WSW of Station Church and Walnut Street, Oak Harbor, 6.5 miles SSW of Station Behlman and Bier Roads, 4.4 miles SSW of Station Carnp Perry Western and Toussaint South Road, 3.7 miles S of Station Camp Peny Western and Rymers Road, 4.0 miles SSE of Station 72

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

Sample Location Type of Number Location T-128 I

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I I

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C QC I

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I C = control, QC = quality conitrol Location Description Erie Industrial Park, Port Clinton Road, 4.0 miles SE of Station Site Boundary, 0.8 miles SSE of Station Humphrey and Hollywood Road, 2.1 miles NW of Station State Route 2 and Humphrey Road, 1.8 miles WNW of Station Leutz Road, 1.4 miles SSW of Station State Route 2, 0.7 miles SW of Station Fourth and Madison Streets, Port Clinton, 9.5 miles SE of Station Quality Control Site Sand Beach, 1. I miles NNW of Station Sand Beach, 0.8 miles NNW of Station Sand Beach, 0.7 miles N of Station Sand Beach, 0.7 miles N of Station Sand Beach, 0.5 miles NNE of Station Site Boundary, 0.6 miles NW of Station Site Boundary, 0.5 miles N of Station Site Boundary, 0.5 miles NNE of Station.

73

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

Sample Location Type of Number Location Location Description T-211 I

Site boundary, 0.79 miles E of Station T-212 I

Site boundary, 1.2 miles ESE of Station T-213 I

Site boundary, 0.6 miles SSW of Station T-214 I

Site boundary, 0.7 miles SW of Station T-215 I

Site boundary, 0.5 miles W of Station T-216 I

Site boundary, 0.7 miles NW of station T-217 I

Salem-Carroll Rd., 4.7 miles SSW of Station T-218 I

Toussaint East Rd., 4.0 miles WSW of Station T-219 I

Toussaint Portage Rd., 4.8 miles WSW of Station T-220 I

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

78

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

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

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 Thcrmoluminescent Dosimetry,"

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

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

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, "Perfonnance, Testing, and Procedural Specifications for Thermolu-minescent Dosimetry: Environmental Applications," US NRC (July 1977).

79

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

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., Oak Harbor, OH," Annual Report, Parts and I (1977 through 1990).

17. Teledyne Isotopes Midwest Laboratory, "Final Monthly Progress Report to Toledo Edison Company', (1991-1999).

18. Environmental, Inc. Midwest Laboratory, "Final Report to FirstEnergy Corporation", (2000, 2001)

19. Teledyne Isotopes Midwest Laboratory, "Preoperational Enviromnental Radiological Moni-toring for the Davis-Besse Power Station Unit No. I", 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, 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. Toledo Edison Company, "Radiological Environmental Monitoring Program," DB-HP-00015.

25. Toledo Edison Company, "Radiological Environmental Monitoring Quarterly, Semiannual, and Annual Sampling", DB-HP-03004.

26. Toledo Edison Company, "Radiological Monitoring Weekly, Semimonthly, and Monthly Sampling," DB-HP-03005.

27. Toledo Edison Company, "REMP Enhancemenit Sampling", DB-HP-10101.

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

80

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

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

30. Toledo Edison Company, Davis-Besse Nuclear Power Station, Offsite Dose Calculation Manual

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

81

Radioactive Effluent Release Report

Davis-Besse Nuclear Power Station 2001 Aniual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2001 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 through publication in the Code of Fed-eral Regulations (CFR) by the Nuclear Regulatory Commission (NRC).

The main objective in the control of radiation is to ensure that any dose is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA). The ALARA principle ap-plies to reducing radiation dose both to the individual working at Davis-Besse and to the general public. "Reasonably achievable" means that exposure reduction is based on sound economic de-cisions 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 amotuts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in the primary coolant water. The three types of radioactive nmaterial released are noble gases, io-dine and 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 radioactive 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 neces-sary, prior to release.

Noble Gas Some of the fission products released in airbome effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologically and chemically nonreactive.

82

Davis-Besse Nuclear Power Station 2001 Annual Radiological Enviroimental Operating Report 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-i 33 and xenon-135, with 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 Amual 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-13 I 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 cesium-137) and activation products (e.g., cobalt-58 and cobalt-60). Radioactive cesium and cobalt con-tribute 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 boron in the primary coolant. When tritium, in the form of water or water vapor, is ingested or inhaled 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 regulatoly limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance pro-grams for effluent and environmental programs, and procedures covering all aspects of effluent and enviromnental monitoring.

The radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gaseous wastes which contain radioactivity. For example, the Waste Gas Decay Tanks are holding tanks which 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.

83

Davis-Besse Nuclear Power Station 2001 Aual Radiological Environmenital Operating Report 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.

A meteorological tower is located in the southwest sector of the Station. It is linked to computers which 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 Monitoring Program constantly sample the air in the surrounding environment. Frequent sam-ples of other environmental media, such as water and vegetation, are also taken to determine 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 concem 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 environimental transport mechanism, and the use of the envi-romnment. 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 arc 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 extemal and intemal exposure pathways considered are shown in Figure 30. The release of radioactive gaseous effluents involves pathways such as extemal 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 consunption, and direct exposure from the lake at the shoreline while swimming.

84

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environrmental 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.

Althougb 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 ivolves 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-85

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report lated using factors such as the amotunt 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 using factors such as the total volume of liquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption, shoreline and swimming fac-tors). 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, 2001 through December 31, 2001.

• 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:

• 7.75E-02 mrem, whole body

• 8.03E-02 mrem, thyroid Gaseous Effluents:

Noble Gas:

• 2.71E-04 mrad, whole body

• 9.27E-04 mrad, skin Iodine - 131, Tritium, and Particulates with Half-lives greater than 8 Days:

• 1.99E-03 mrem, whole body

• 2.54E-03 mrem, thyroid These doses are an extremely small fraction of the limits set by the NRC in the Davis-Besse ODCM.

86

Davis-Besse Nuclear Power Station 2001 Anual Radiological Environmental Operating Report Additional normal release pathways from the secondary system exist. For gaseous effluents, these pathways include the auxiliary feed pump turbine exhausts, 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. (Note: the total dose due to these releases is also limited to 50 mrem in any calendar 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 IOCFR50, Appendix I, Sec. IB. 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 10CFR50, Appendix 1, Sec. IIC, dose to a member of the public from lodine-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 1, 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.

87

Davis-Besse Nuclear Power Station 2001 Anual Radiological Environmental Operating Report Effluent Concentration Limits The Effluent Concentration Limits (ECs) for liquid and gaseous effluents at and beyond the site boundary are listed in IOCFR20, Appendix B, Table 11, Column 2, with the most restrictive EC being used in all cases. For dissolved and entrained gases the EC of 2.0E-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 i water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2.

Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and activa-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 (B) 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 a marinelli beaker specially modified for gas sampling, steel flasks, or glass vials and are counted on a germanium detector for principal gamma emitters. Radionuclides that are detected are quantified via gamma spectroscopy.

Tritium gas is collected using a bubbler apparatus and cotunted 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 via 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 via gamma spectroscopy.

Liquid Effluents Liquid effluents are collected in a marincili beaker and counted on a genmanium 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.

88

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Batch Releases Liquid from 11/01 through 12/31/01 I. Number of batch releases:

2. Total time period for the batch releases:

3. Maximum time period for a batch release:

4. Minimum time period for a batch release:

5. Average time period for a batch release:

Gaseous from 1/1/01 through 12/31/01

1. Number of batch releases:

2. Total time period for tie batch releases:

3. Maximum time period for a batch release:

4. Minimum time period for a batch release:

5. Averge time period for batch release:

51 85.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 133 minutes 81 minutes 100.6 minutes 6

61.92 hours0.00106 days <br />0.0256 hours <br />1.521164e-4 weeks <br />3.5006e-5 months <br /> 2473 minutes 172 minutes 619.2 minutes Abnormal Releases Total 2001 activity due to Abnormal Releases 0.0 Total 2001 Dose due to Abnormal Releases is 0.OOE+00 mRem 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, 2001 tlrough December 31, 2001.

TI I

I______ ~~~~~~~PER CENT OF SPECIFICATION ANNUAL DOSE LIMIT I

LIMIT Report Period: January 1, 2001-December 31,2001 (gaseous)

Noble gases (gamma)

I 6.71E-04 mrad 10 mrad 2.71E-03 Noble gases (ba) t6.56E-04 mrad 20 mrad 3.28E-03 1-131, tritium and particulates I.99E-03 mrem 15 mrem 1.33E-02 Report Period: January 1, 2001 - December 31, 2001 (liquid)

Total body J 7.75E-02 mrem 3 mrem l 2.58E+00 Organ 8.03E-02 mrem 10 mrem l 8.03E-01 89

Davis-Basse Nuclear Power Station 200 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 Departnent 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 an as-sessment of radiation doses from radioactivity released in liquid and gaseous effluents to mem-bers of the public due to activities inside the site boundary.

In special instances, members of the public are permitted access to the Radiologically Restricted Area within the Davis-Besse Station. Tours for the public are conducted with the assurance that no individual will receive any appreciable dose due to radioactivity released in gaseous or liquid effluents (i.e., not more than a small fraction of the 40 CFR 190 standards.)

The Wellness Center, Pavilion, Training Center pond and the forebay/canal area located inside DBNPS Owner Controlled Area are accessible to members of the public. The Pavilion is acces-sible to the public for social activities. The Training Center pond, forebay/canal area allows the member of the public to fish on site under a "catch-an-release" program; therefore the fish path-way is not considered applicable. Considering the frequency and duration of the visits, the re-sultant dose would be a small fraction of the calculated maximum site boundary dose. For pur-poses 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 Idependent Spent Fuel Storage Installation (ISFS),

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

90

Davis-Besse Nuclear Power Station 2001 Aual Radiological Fnvironmental 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 There were no radioactive effluent monitoring equipment required to be operable that was in operable for greater than 30 days during the reporting period.

Changes to the ODCM and PCP There were two alterations to the OCDM, Revision 14.0 and Rev. 15.0. The Process Control Program (PCP) had no changes in the reporting period.

Borated Water Storage Tank Radionuclide Concentration During the Reporting Period of 2001, the BWST tank concentration did not exceed the ODCM specification of Section 2.2.4. The sum of the limiting fraction of nuclides, a unitless number between 0 and, the BWST tank did not exceed the limit of 1. Of the ten samples taken for the reporting period of 2001, all samples analyzed for the sum of the limiting fractions of nuclides reported were <0.05.

91

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 17 Gaseous Effluents - Summation of All Releases Type Fission and Activation Gases Total Release Unit 1st Qtr 2001 2nd Qtr 3rd Qtr 2001 2001 Ci 3.33E+00 3.09E+00 2.75E+00 Average Release Rate for Period' Percent of ODCM Limits gCi/sec 4.22E-01 3.93E-01 3.49E-01 7.52E-01 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination lodines Total lodines (1-131)

Average Release Rate for Period' Percent of ODCM Limits Ci 5.24E-06 2.97E-05 5.66E-05 pCi/sec 6.65E-07 3.77E-06 7.1SE-06 1.13E-04 1.43E-05 2.51E+011 Rev. 1 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination Particulates Particulates with half-lives greater than 8 days Average Release Rate for Period' Percent of ODCM Limits Ci 0.OOE+00 pCi/sec 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OE+00 7.33E-07 2.5E+01 9.30E-08 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination Gross Alpha Activity Ci 0.OOE+00 0.OOE+00 0.00E+00 Tritium Total Release Ci 1.02E+01 7.33E+00 5.62E+00 Average Release Rate for Period' Percent of ODCM Limits pCi/sec 1.2913+00 9.21E-01 7.12E-01 6.07E-01 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination a The average release rate is taken over the entire quarter. It is NOT averaged over the time period of the releases.

92 4th Qtr 2001 5.93E+00 Est. Total

% Error 2.5E+01 0.00E+00 2.5E+01 4.78E+00 2.5E+01

Davis-Besse Nuclear Power Station 2001 Annual Radiological Enviroimenital Operating Report Table 18 Gaseous Effluents - Grotmd Level Releases Batch Mode' Unit Fission Gases Ist Qtr 2001 2nd Qtr 2001 3rd Qtr 2001 Ci Kr-85 Kr-SSm Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 LLD' LLD LLD LLD LLD LLD LLD LLD N/A Total for Period:

LLDb LLD LLD LLD LLD LLD LLD LLD N/A LLDb LLD LLD LLD lLD LLD LLD LLD N/A Ci 1-131 1-132 1-133 1-135 LLD ILD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Total for Period:

Particulates and Tritium H-3 Sr-89 Sr-90 Cs-134 Cs-137 Ba-140 Co-58 Total for Period:

9.65E-03 8.69E-03 1.IOE-02 6.35E-03 93 Nuelide 4th Qtr 2001 lodines LLDb LLD LLD LLD LLD LLD LLD LLD N/A LLD LLD LLD LLD NIA ci N/A N/A N/A 9.65E-03 LLD LLD LLD LLD LLD LLD 8.69E-03 ID LLD LLD LILD LLD LLD L.IOE-02 LLD LLD LLD LLD LLD LLD 6.35E-03 LLD LLD LLD LLD LLD LLD

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 18 (Continued)

Gaseous Effluents - Ground Level Releases Continuous Modec Unit Fission Gases Ist Qtr 2001 2nd Qtr 2001 3rd Qtr 2001 Ci Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-I 35 Xe-135m Xe-138 LLD LLD LLD LLD LLD LLD LLD LD N/A Total for Period:

lodines LLD LLD LLD LLD LLD LLD LLD LID N/A LLD" LLD LLD LLD LLD LLD LLD LLD N/A ci 1-131 1-133 1-135 LLD LLD LD LID LLD LLD LLD LLD LLD Total for Period:

Particulates and Tritium 11-3 Sr-89 Sr-90 Cs-134 Cs-137 Ba-140 Total for Period:

1.11E-02 1.13E-02 1.88E-02 2.34E-02 94 Nulide 4th Qtr 2001 LLD LLD LLD LLD LLD LLD LLD LLD NIA N/A LLD LLD LLD ci N/A N/A N/A 1.1 E-02 LLD LLD LLD LLD LLD L 13E-02 LLD LLD LLD LLD LLD 1.88E-02 LLD LLD LLD LLD LLD 2.34E-02 LLD LLD LLD LLD LLD

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 18 (Continued)

Gaseous Effluents - Ground Level Releases Continuous and Batch Mode Ar41:

Kr-85:

Kr-85m:

Kr-87:

Kr-88:

Xe-13 Im:

Xe-133:

Xe-133m:

Xe-135:

Xe-135m:

Xe-138:

1-131:

1-133:

1-135:

Mn-54 Fe-59:

Co-58:

Co-60:

Zn-65:

Mo-99:

Cs-134:

Cs-137:

Ce-141:

Ce-144:

Ba-140:

La-140:

Sr-89:

Sr-90:

<2.2E-08

<6.2E-06

<2.0E-08

<3.4E-08

<4.OE-08 c9.OE-08

<4.6E-08

<1.6E-07

<1.9E-08

<4OE-07

<2.5E-07

<I.OE-07

<2. IE-08

<2.1E-08

<2.0E-08

<4.0E-08

<3.0E-08

<2.0E-08

<4.OE-08

<2.OE-07

<2. E-08

<3.0E-08

<3,0E-08

<1.2E-07

<7OE-08

<3.OE-08

<5.0E-08

<6.0E-09

,Ci/mi pCi/mil ItC/mnl Ci/nl pCi/ni fiCi/ll itCi/nl pCi/mnl pCi/ni pCi/mi pCi/nil Ci/ml Ci/ml uCi/mi pCi/nil uCiUml pci/mi pci/mi pCi/ml pCi/mil pCi/nI pCi/ml pCi/ml pCi/nil pCi/nil

,Ci/ml a

Auxiliary Feed Pump Turbine Exhaust, Main are listed as batch releases.

Steam Safety Valves, and Auxiliary Boiler Outage Release b

These radionuclides were not identified in concentrations above the lower limit of detection (LLD).

c Atmospheric Vent Valve weepage and Steam Packing Exhaust are continuous releases.

95

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 19 Gaseous Effluents - Mixed Mode Releases Batch Mode lst Qtr 2nd Qtr 3rd Qtr 4th Qtr Unit 2001 2001 2001 2001 Fission Gases Ci LLD ci 1.061-01 Ci LLD Ci LLD Ci LLD Ci LLD Ci LLD Ci LLD Ci LLD Ci LLD Ci LLD LLD LLD LLD LLD LLD 1.74E-02 LLD LLD LLD LLD LLD LLD 2.OSE-01 LLD LLD LLD IL)

LLD LLD LLD LLD LLD LLD 3.54E-01 LLD LLD LLD 7.24E-01 LLD LLD LLD LLD 4.IE-02 Total for Period:

1.06E-03 1.74E-02 2.05E-01 1 12E+00

• Todines 1-131 1-132 1-133 Ci LLD Ci LLD Ci LLD 1-135 Ci LLD Total for Period:

Ci LLD LLD LD LlD LLD LLD

• Particulates H-3 Ci 1.21E-03 5.85E-04 3.06E-02 4.65E-03 Ci 1.2113-03 5,85E-04 3.06E-02 4.65E-03 Total for Period:

• Release of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Sta-tion Vent) 96 Nuclide Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Xe-131In LLD LLD LLD LLD LlD LLD LLD LLD LLD LLD

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 19 (Continued)

Gaseous Effluents - Mixed Mode Releases Continuous Mode Unit Ist Qtr 2001 2nd Qtr 2000 3rd Qtr 2000 Fission Gases Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Ci Ci ai Ci Ci Ci Ci Ci ci Ci LLD LLD LLD LLD LLD 2.88E+00 LLD 3.39E-01 LLD LLD LLD LLD LLD LLD LLD 2.65E+00 LLD 4.23E-01 LLD LD LLD LLD LLD LLD LLD 1.84i00 LLD 7.11E-01 LLD LLD Total for Period:

3.22E+00 3.07+00 2.55E+00 4.81E+00 lodines 1-131 1-133 1-135 1-132 ci ci ci ci 5.24,06 LLD LLD LLD 2.97E-05 3.52E-06 LLD LLD 5.66-05 5.39E-05 LLD LLD 1.13E-04 1.49E-04 LLD LLD Total for Period:

Particulates and Tritium H-3 Sr-8 9b,c s-90, Cs-134 Cs-137 Ba-140 Co-58 La-140 Co-60 Total for Period:

1.02EO1 7.31E+00 5.563.+00 4.75E+00 97 Nuclide 4th Qtr 2000 LLD LLD LLD LLD LLD 4.57E+00 LLD 2.40E-01 LLD LLD 5.24E-6 ci ci ci ci ci ci ci ci ci 3.32E-05 7.3 1 E+00 LLD LlD LLD LLD LLD LLD LLD LLD 1.02E+01 LLD LLD LLD LLD LLD LLD LLD LLD 1.II E-04 5.56E-00 LLD LLD LLD LLD LLD LLD LLD LLD 2.62E-04 4.75Ef+00 LLD LLD LLD LLD LLD 7.33E-07 LID LLD

Davis-Besse Nuclear Power Station 2001 Anual Radiological Environmental Operating Report Table 19 (Continued)

Gaseous Effluents - Mixed Mode Releases Continuous Mode

<2.9E-08

<3.313-06

<1.3E-08

<6.0E-08

<6.0-08

<4.4E-07

<7.213-08

<I.IE-08

<5.9E-06

<.OE-05

<3.9E-10

<2.613-14

<3.013-14

<3.0E-14

<2.5E-14

<1.OE-13

<I.8E-14

<1.6F,14

<1.3E-14

<1.2E-13

<1.2E-14

<4.0E-14

<I.OE-14

<9.3E-16

<3.1E-16 Batch Mode Kr-87 Kr-88 Xe-135 Xe-135m Xe-138 Ar-41 Kr-85 Xe-133 Xe-133m pCi/nil pCi/rnil pCUiln pCi/ml pci/mi pCi/mi pCi/mi

.CUmi pCi/mi pCi/ni pCi/mi

,Ci/ni pICUmi pCimi pCi/mi pci/mi

,uCi'mi

.Ci/ml p.i/mi

,uCUmi pCi/mI pCi/mi pCi/ml pci/mi uCi/mi

<4.5E-06

<6.6E-06

<1.413-05

<2.1 E-06

<2.8E-05

<1.8E-06

<1.2E-06

<2.4E-06

<1.OE-05 pCini pCi/mi pCi/ni

,ci/mi tci'rni uCi/mi pCi/mi uCUiml a

These radionuclides were uot identified in every quarter in concentrations above the lower Imit of detection (LLD).

The largest LLD value is listed.

b Quarterly composite sample for continuous mode.

c Analysis not required for batch release.

98 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133m Xe-135 Xe-135m Xe-138 1-135' Mn-54' Fe-5f9 Co-58' Co-60' Zn-65'

.Uo-99' Cs-134' Cs-137' Ce-141' Ce-144' Ba-140' La-140' Sr-89b,C Sr-obtc

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 20 Liquid Effluents - Summation of All Releases Type Fission and Activation Products Total Release (without Tritium, Gases, Alpha)

Average Diluted Concentration During Peiod' Percent of ODCM Limits Percent of 10CFR20 Limit Unit Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total 2001 2001 2001 2001

% Error Ci 3.37E-03 1.08E-03 1.20-03 pCi/ml 3.24E-10 1.01E-10 9.75-11 5.55E-04 2.0E+01 5.1 8E-II See Supplement information in ODCM Release Linits Sece tion 2.16E-03 1.61 E-03 1.65E-03 3.26E03 Tritium Total Release Ci 1.65E+02 1.36E+02 1.29E+02 1.36E+02 2.013+01 Average Diluted Concentration During Period' Percent of IOCFR20 Limit Dissolved and Entrained Gases Total Release Average Diluted Concentration During Period' Percent of I OCFR20 Limit Gross Alnha Total Release Volume of Waste Released (prior to dilution)

Batch Continuous Volume of Dilution Water Batch Continuous Total Volumne of Water Released pCi/ml I.58E-05 1.271-05 1.05E-05 1.27E-05 1.58E+00 1.2713+00 1.05E+00 1.27E+0 Ci 1.39E-05 4.68E-04 5.462-05 1.99E-03 2.0E+01 pCilml 1.33E-12 4.36E-11 4.44E-12 1.86-10 6.67E-07 2.18E-05 2.22f-06 9.30E-05 Ci 0.00E+00 0.00E+00 0.00E+00 4.61E-03 2.0E+01 liter 3.45E+05 3.42E+05 3.73F+05 3.96E+05 20E+01 liter 9.0513+07 8.04E+07 7.97E+07 1.02E+08 2.01E+01 liter 1.01E+08 1.01E+08 1.101E+08 1.1713+08 2.0E+01 liter 1.02E+10 E06E+10 1.21E+10 1.05E+10 2.0E+01 liter 1.041E+10 1.07E+ 10 1.23E+10 1.07E+10

' 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.

99

Annual Radiological Environmental Operating Report Table 21 Liquid Effluents - Nuclides Released Batch Releases Nuclide Fission and Activation Products Unit Co-58 Co-60 Ag-110m Sb-125 Cs-134 Cs-137 Sr_89a' b Sr-90'b Fe-55 Cr-51 1-131 1-132 1-133 Te-132 Tc-99m Sb-124 Sn-1 13 Ru-103 Mn-54 Np-239 Co-57 Nb-95 Zr-95 Se-75 Fe-59 Zn-65 Ce-144 Na-24 Zr-97 Ce-141 Nb-97 La-140 Ba-140 Ru-106 Ba-139 Mo-99 Total for Period:

Ci I st Qtr 2001 6.40E-05 7,42E-05 5.55E-04 2.36E-03 6.90E-06 1.32E-05 LLD LLD 1.97E-04 7.11E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 2.53E-05 LLD LLD LLD LLD LLD LLD LLD 2" Qtr 2001 3.95E-05 1.37E-04 3.84E-04 4.6 7E-04 LLD LLD LLD LLD LLD LLD 4.44E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 7.73E-06 LLD LLD LLD LLD LLD LLD LLD 3rd Qtr 4th Qtr 2001 2001 1.24E-04 1.28E-04 7.96E-04 LLD LLD 8.17E-07 LLD LLD 1.32E-04 LLD 1.88E-05 LLD LLD LID LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.34E-03 1.80E-05 7.52E-05 LLD LLD 4.23E-07 LLD LLD 1.ISE-04 LLD 3.12E-04 LLD 2.OOE-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.43E-06 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.37E-03 1.08E-03 1.20E-03 5.55E-04 100 Davis-Besse Nclear Power Station 2001

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - Nuclides Released Batch Releases Unit ci I st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2001 2001 2001 2001 1.65E+02 1.36E+02 1.29E+02 1.36E+2 Dissolved and Entrained Gases Ci Ci Ci Ci Ci Ci Ci LLDa LLD LLD 1.39E-05 LLD LLD LLD LLDa LLD LLD 4.68E-04 LLD LLD LLD LLDa LLD LLD 5.38E-05 8.69E-07 LLD LLD LLD' LLD LLD 1.94E-03 4.68E-05 LLD LLD Total for Period:

ci 1.39E-05 4.68E-04 5.47E-05 1.99E-03 101 Nuclide Tritium Kr-85m Kr-85 Xe-131m Xe-133 Xe-135 Xe-133m 1-135

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - Nuclides Released Continuous Releases Nuclide Unit I st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2001 2001 2001 2001 Fission and Activation Products Cr-51 Fe-59 Co-58 Co-60 Zn-65 Sr-89'b Sr-90Pb Nb-95 Zr-95 Mo-99 Tc-99m 1-131 Cs-134 Cs-137 Ba-140/La-140 Ce-141 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci ci LLDa LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD N/A LLDa LLD LLD LLD LLD LLD LLD LLD LED LLD LLD LLD LLD LLD LLD LLD N/A LLD LLD LLD LLD LLD LLD LLD LLD LLD LED LLD LLD LLD LLD LLD LD N/A LLDa LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD N/A 2.37E-01 1.29E-01 2.97E-01 9.45E-02 Dissolved and Entrained Gases Kr-85 Xe-131m Xe-133 Xe-133m Xe-135 Total for Period:

Total for Period:

Tritium Ci Ci Ci Ci Ci LLD LLD LLD LLD LLD N/A LLD LLD LLD LLD LLD N/A ci LLD LLD LLD LLD LLD N/A LLD LLD LLD LLD LLD N/A 102

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - Nuclides Released' Na-24 Cr-51 Mn-54 Fe-55' Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Sr-89' Sr-90b Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Ru-103 Ag-I 10m Si-1 13

<2.0E-08

<1.7E-07

<2.lE-08

<7.0E-07

<4.2E-08

<1.6E-08

<1.9E-08

<2.5E-08

<5.2E-08 c2.4E-08

<3.E08-O

<8.OE-09

<4.0E-08

<2.5E-08

<2,IE-08

<1.6E-07

<1.8E-08

<2.2E-08

<2.5E-08

<2.8E-08 pCilmn]

pCi/rn!

pCi/mi pCi/mi pCi/mi 1iCiml pCi/in!

.LC i/mi pCi/mi pCi/mi ptCi/rmi pCi/mi tci/mi piCi/nd ptCi/rni pCi/rn]

pCi/ml pLCi/rni pCi/mi piCi/mi Sb-124 Sb-125 Te-132 Ce-141 Ce-144 Cs-134 Ce-136 Cs-137 Ba-140 La-140 Np-239 1-131 1-132 1-133 I-135 Kr-85 Xe-131 Xe-133 Xe-133m Xe-135

<I.OE-08

<1.7E-08

<1.88-08

<3.0E-08

<1.78-07

<2. E-08

<2.8E-08

<2.7E-08

<7.018-O8

<3.0B-08

<1.2E-07

<2.5-08

<I.OE-08

<2.1E-08

<1.7E-07

<6.2E-06

<7.7E-07

<4.6E-08

<1.6E-07

<1.9E-08 i+/-Ci/inI pCi/mi pLCi/nd MCI/mi pCi/mi pCi/mi l.Ci/mi pCi/mi ptCi/mi pCi/mi piCi/mi pCi/mi pCi/mi MCI/mi pLCi/rni piCi/mi pCi/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 103

Davis-Besse Nuclear Power Station 2001 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 1I e of Waste Unit Period Error, %

a.

Spent resins, filter sludges, in3 5.45E+00 2.5E+01 evaporator bottoms, etc.

Ci 2.03E+02 2.5E+01

b. Dry compressible waste, in3 1.02E+02 2.5E+01 contaminated equip., etc.

Ci 3.85E+o0 2.5E+01

c. Irradiated components, m3 control rods, etc.

Ci N/A N/A

d. Others: dewatered primary m3 9.10E-02 2.5E+0l system cartridge filters Ci 1.44E-02 2.5E+01

2. Estimate of major nuclide composition (by type of waste)

Tvpe

a. Spent Resins

b. Dry compressible waste, contaminated equipment, etc.

c.

None

d. Cartridge filters Fe55 Co60 Ni6 3 Cs' 34 Cs13 7 Fe55 Co60 c14 Ni6 3 Co5 Fe" Co 58 Ni6 3 Ag' 1Oni Zr95 Co60 C14 Percent ()

2.78E+00 7.71E+00 2.93E+01 4.76E+00 5.38E+02 6.38E+01 1.75E+01 3.59E+00 6.54E+00 2.00E+00 2.63E+01 5.26E+01 5.06E+00 2.36E+00 1.49E+00 5.37E+00 1.96E+00 Est. Total

Error, 2.50E+0l 2.50E+01 2.50E+01 2.SOE+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 104

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 22 (continued)

Solid Waste and Irradiated Fuel Shipments

3. Solid Waste Disposition Number of Shipments:

Mode of Transportation:

Destination:

Type of Container (Container Volume):

Volume shipped for processing Voltume disposed Number of Shipments:

Mode of Transportation:

Destination:

Type of Container (Container Voltume):

Volume shipped for processing Volume disposed Number of Shipments:

Mode of Transportation:

Destination:

Type of Container (Container Volume):

Volume shipped for processing Volume disposed Number of Shipments:

Mode ofTl'ransportation:

Destination:

Type of Container (Container Volume):

Volume shipped for processing Volume disposed Number of Shipments Mode of Transportation Destination Type of Container (Container Volume)

Volume shipped for processing Volume disposed 2

Truck STUDSVIK Processing Facility, Erwin TN For processing then disposal at Bamwell S.C.

High Integrity Container (3.75 m3) 7.5 3

0.64 n3 4

Truck US Ecology, Oak Ridge, TN for processing then disposal at Envirocare of Utah Metal boxes (36.3 m3) 194.05 m3 39.96 m3 I

Truck ATG Inc. Richland Washington for processing then disposal at Envirocare of Utah or Bamwell S.C.

Metal Boxes (2.6 m3) 8.15 m3 Processing not complete in 2001 Est. 0.82 m3 Truck ATG Inc, Oak Ridge Tenn. for processing then disposal at Barnwell S.C.

High Integrity Container (5.72m3) 5.72 m3 5.72 n3 9

Truck ALARON Corp., Wampam Pa. For processing then Disposal at Envirocare of Utah.

Metal Boxes (73.42 m3) 259.83 m' (spent fuel racks)

Processing not complete in 2001 Est. 61.28 m3 105 B. IRRADIA'ED FUEI SHIPMEN1'S

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 23 Doses Due to Gaseous Releases for January through December 2001 Maximum Individual Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.

Whole Body Dose 1.99E-03 mrem Significant Organ Dose 2.54E-03 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 2.71F04 nrad Skin Dose 9.27E-04 mrad Population Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.

Total Integrated Population Dose 7.02E-03 person-rem Average Dose to Individual in Population 3.2 1E-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 5.03E-04 person-rem Average Dose to Individual in Population 2.30E-07 mrem 106

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 24 Doses Due to Liquid Releases for January through December 2001 Maximum Individual Whole Body Dose Maximum Individual Significant Organ Dose Population Dose Total Integrated Population Dose Average Dose to Individual 7.75E-02 mrem 8.03E-02 mTen 7.31E-01 person-rem 3.35E-04 mrem 107

Davis-Besse Nuclear Power Station 2001 Anual Radiological Environmental Operating Report Table 25 Annual Dose to The Most Exposed (from all pathways) Menber of The Public 2001 ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem)

(mrem)

LIMIT Whole Body Dose*

Noble Gas 2.98E-04 Iodine, Tritium, Particulates 1.99E-03 Liquid 7.75E-02 Total Whole Body Dose 7.98E-02 25 3.19E-01 Thyroid Dose Iodine, Tritium, Particulates 8.28E-02 75 1.10E-01 Skin Dose Noble Gas 1.02E-03 25 4.08E-03 Significant Organ Dose 8.28E-02 25 3.31E-01 (Thyroid)

Meteorological Data Meteorological data on 31/2 inch microdisk for January through December 31, 2001, 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 ad is, therefore, not included in this compilation.

108

Land Use Census

Davis-Besse Nuclear Power Station 2001 Anual Radiological Environmental Operating Report Land Use Census Program Design Each year a Land Use Census is conducted by Davis-Besse in order to update information neces-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 - Extemal exposure from radionuclides deposited on the ground

• Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.

Vegetation Pathway - hItenal 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 - Intenal 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 meteorological sector within a five mile radius of Davis-Besse.

The surveillance portion of the 2001 Land Use Census was performed during the month of August. 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 cab-bage).

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 2001 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 corre-sponding to the 16 cardinal compass points (Figure 31). The closest residence, milk animal, and vegetable garden in each sector are determined by measuring the distance from each to the vent at Davis-Besse.

Results The following changes in the patlways were recorded in the 2001 census:

S Sector - A garden at 5830 meters replaced a garden at 4960 meters

• SW Sector - The garden at 5400 meters was replaced by a garden at 5180 meters.

• WSW Sector - The garden at 4270 meters was replaced with a garden at 7430 meters.

• SE Sector - a residence at 8000 meters was added.

SW Sector - the former closest residence was replaced with a residence at 1070 meters.

The critical receptor identified by the 2001 Land Use Census is a garden in the W sector at 1610 meters from Davis-Besse.

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 infornation 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

DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PRIMARY PATHWAYS WITHIN A 5 MILE RADIUS ENVIRONMENTAL MONITORING

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Davis-Besse Nuclear Power Station 2001 Anual Radiological Environmental Operating Report Table 26 Closest Exposure Pathways Present in 2001 Sector Distance from Station (meters)

Closest Pathways N

880 hJlalation 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 Groutnd Exposure Plume Exposure SSE 2860 Vegetation SSE 1970 Inhalation Ground Exposure Plume Exposure S**'

5830 Vegetation S

1030 Inhalation Ground Exposure Plume Exposure SSW 2350 Vegetation SSW 980 hnhalation Ground Exposure Plume Exposure SW**

5180 Vegetation SW**

1070 Inhalation Ground Exposure Plume Exposure

"*Changes since 2000 112

Davis-Besse Nuclear Power Station 2001 Anual Radiological Environnental Operating Report Table 26 (continued)

Closest Exposure Pathways Present in 2001 Distance from Station (meters)

Closest Pathways Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure

• • Changes since 2000 113 Sector WSW WSW**

1540 W

7430 980 w

1610 1750 NW 1490 NW 2300 NNW 1270

Davis-Besse Nuclear Power Sation 2001 Annual Radiological Environmental Operating Report Table 27 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q)

Parameters CRITICAL PATHWAY Inhalation Inhalation Inhalation Inhalation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Inhalation Vegetation Inhalation AGE GROUP Child Child Child Child Child Child Child Child Child Child Child Child Child X/Q (SEC/M3) 9.15E-07 1.24E-06 1.26E-06 D/Q (N) 8.40E-09 1.44E-08 1.58E-08 3.43E-8 1.45E-10 6.91E-08 2.90E-08 5.90E-08 3.85E-08 3.40E-08 2.77E-07 1.46E-07 6.98 E-08 2.41E-07 8.13E-10 1.67E-10 1.03E-09 3.40E-I 0 1.80E-10 4.37E-09 1.72E-09 5.79E-10 1.73E-09

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

• • Changes since 2000 114 SECTOR N

NNE NE ENE ESE*

SE**

SSE S**

SSW SW**

WSW**

w WNW NW NNW METERS 880 880 900 8000 2860 5830 2350 5180 7430 1610 1750 2300 1270

Non-Radiological Environmental Programs

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environimental Operating Report Non-Radiological Environmental Programs Meteorological 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 Monitoring Program. These guidelines ensure that Davis-Besse has the proper equipment, in good working 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 prograns: 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 evalu-ating the radiological impact, if any, of radioactivity released in Station effluents. The meteoro-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 con-ditions to be met before work begins. Plant Security utilizes weather data in their routine plan-ning 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.

Legal Affairs uses climatological data for their investigation into adverse weather accidents to the plant and personnel.

115

Davis-Besse Nuclear Power Station 2001 Aniual Radiological Environmental Operating Report On-site Meteorological Monitoring

System Description

At Davis-Besse there are two meteorological systems, a primary and a backup. They are both housed in separate environmentally controlled buildings with independent power supplies. Both primary and backup systems have been analyzed to be "statistically identical" to the other so if one system fails the other 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)*, a 100m free-standing tower located about 3,000 feet SSW of the cooling tower, and an auxiliary IOm foot tower located 100 feet west of the 100 m tower, are used to gather the meteorological data. The lOOm tower has primary and backup instruments for wind speed and wind direction at OOm and 75m. The l OOm tower also measures differential temperature (delta Ts): 100-1Om and 75-1Om. The 1Om tower has instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the l Om 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 1Om) to measure temperature, wind speed, and wind direction. During 2001, annual data recoveries for all required instruments were 99.27 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-Bcsse Nuclear Power Station 2001 Annual Radiological Enivironmental Operating Repon 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 roorn via a Digital Alpha computer system. This is a dedicated line. If a failure occurs at any point between the primary meteorological system and the control room the control room can utilize the second data logger in the primary shelter. Each datalogger 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 difficult 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 corroborated 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 and in digital format for a pennmaent 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 2001.

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 pattems as they relate to defined past climatological wind pattems reported in Davis-Besse's Updated Safety Analysis Report. The maximum measured sustained wind speeds for 2001 were 51.03 mph for the 1 00m level on April 12, 45.85 mph for the 75m level on October 25, and 39.02mph for the Orm level on April 12.

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 2001 Annual Radiological Env ironimental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2001 are given in Table 29.

These data are measured at the lOm level; with diiferential temperatures taken from lOOm and 75m levels. The yearly average ambient temperature for 2001 was 51.86°F. The maximum temperature was 92.28°F on August 8 with the minimum temperature of 4.78°F on January 02.

Yearly average differential temperatures were -0.21°F (100m), and -0.07°F (75m). Maximum differential temperatures for lOOm and 75m levels were 7.99°F on December 11, (100m), and 7.990F on November 11, (75n). Minimum differential temperatures for lOOm and 75m levels were -4.000F on September 8, (lOOm) and -2.86°F on April 18, (75m). Differential tempera-tures are a measurement of atmospheric stability and used to calculate radioactive plume disper-sions 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 2001 are provided in Table 29. These data are measured at the 10 meter level. The average dew point temperature was 43.05°F with a maximum dew point temperature of 77.100F on July 23. Please note that dew point temperatures above 75°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 32°F is frost point) temperature was 3.76°F on January 9. Average rela-tive humidity is 73.52 percent for the year. The maximum relative humidity was 100.00 percent on November 11. The minimum relative humidity was 27.11 on May 4. 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 by such a large body of water.

Precipitation Monthly totals and extremes of precipitation at Davis-Besse for 2001 are given in Table 29. To-tal precipitation for die year was 22.91 inches. The maximum daily precipitation total was 1.34 inches in September. The minimum was 0.19 inches recorded in January. It is likely that pre-cipitation 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 wanmer 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 cre-ating an adverse atmosphere to the surrounding site.

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 to the 118

Davis-Besse Nuclear Power Station 2001 Anual Radiological Ervirormiental Operating Report 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 a plus or minus five feet lake level fluctuation to oc-cur within an eight to ten hour period. High water levels also effect the plant due to emergency transportation and evacuation pathways.

119

JAN FEB MAR APR MAY JUN JUL 100 100 100 100 100 100 100 100 100 100 100 100 100 94.20 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 99.17 99.17 99.17 99.17 99.17 99.17 99.17 99.17 99.17 99.17 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 99.87 100 99.87 99.87 94.20 100 99.17 100 100 99.87 98.92 100 100 99.17 100 100 99.87 98.92 100 100 99.17 100 100 99.87 98.92 AUG SEP OCT NOV DEC 100 100 96.64 100 99.73 100 100 100 100 99.73 100 100 96.91 100 99.73 100 100 100 100 99.73 100 100 97.18 100 99.73 100 100 100 100 99.73 98.92 100 88.31 100 99.73 100 100 99.73 100 99.73 98.92 100 88.17 100 99.73 98.92 100 88.17 100 99.73 2001 99.18 99.91 99.65 99.91 99.67 99.91 98.81 99.89 98.80 98.80 100 87.23 100 99.73 98.28 100 87.37 100 99.73 98.73 100 87.37 100 99.73 98.76

• all data for individual months expressed as percent of time instrument was operable during the month, divided by the maximuim number of hours in that month that te 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 instrumenit was operable.

lOOm Wind Speed lOOM Wind Direction 75M Wind speed 75M Wind Direction I OM Wind Speed IOM Wind Direction I OM Ambient Air Temp I OM Dew Point Temp Delta T (IOOM-IOM)

Delta T (75M-10M)

Joint IOOM Winds and

° Delta T ( OOM-I OM)

Joint 75M Winds and Delta T (IOOM-IOM)

Joint lOM Winds and Delta T (75M-IOM)

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JAN FEB MAR APR MAY JUN JUL IOOM WIND Max Speed (mph) 33.83 48.50 41.33 51.03 34.01 38.54 25.32 Date of Max Speed 01/03 02/25 03/06 04/12 05/04 06/12 07/26 Min Speed (mph) 1.33 2.80 2.12 2.46 2.38 1.44 1.42 Date of Min Speed 01/12 02/13 03/29 04/30 05/17 06/08 07/30 Ave WindSpeed 17.42 18.01 16.88 18.13 15.38 12.44 12.73 75M WIND Max Speed (mph) 31.90 44.76 39.08 42.93 32.17 35.25 23.17 M

Date of Max Speed 01/03 02/25 03/06 04/12 05/21 06/12 07/01 Min Speed (mph) 1.94 2.53 1.32 1.96 2.87 1.47 1.65 Date of Min Speed 01/12 02/13 03/19 04/30 05/18 06/08 07/13 Ave WindSpeed 15.80 16.18 15.45 16.54 14.03 11.52 11.88 10M WIND Max Speed (mph) 23.44 34.71 29.43 39.02 24.70 22.67 18.83 Date of Max Speed 01/03 02/25 03/06 04/12 05/21 06/12 07/26 Min Speed (ph) 0.98 2.16 0.48 1.05 1.13 1.34 1.39 Date of Min Speed 01/12 02/13 03/19 04/01 05/18 6/05 07/31 Ave Wind Speed 10.08 10.70 10.97 10.82 8.48 7.00 7.68 AUG SEP OCT 25.62 32.99 48.35 08/16 09/24 10/25 1.53 0.81 2.13 08/10 09/30 10/21 12.63 15.13 19.73 23.99 31.75 45.85 08/16 09/24 10/25 1.41 1.35 1.94 08/10 09/15 10/21 11.56 13.82 17.99 19.23 22.68 36.02 08/31 09/24 10/25 1.01 1.18 1.57 08/01 09/15 10/21 7:99 8.49 10.66 NOV DEC 2001 40.15 35.89 51.03 11/24 12/14 04/12 2.56 1.46 0.81 11/07 12/11 09/30 18.33 18.06 16.25 38.02 34.49 45.85 11/24 12/14 10/25 2.77 1.43 1.32 11/26 12/11 03/19 16.89 16.55 14.83 28.13 25.86 39.02 11/25 12/14 04/12 1.60 1.60 0.48 11/11 12/17 03/19 9.73 10.91 9/36 V)

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Date of Max 0 1/30 02/09 03/22 04/23 05/04 06/15 07/24 08/08 09/07 10/03 11/01 12/05 08/08 Min (F) 4.78 14.73 12.83 29.71 47.94 47.60 56.43 41.21 41.94 34.19 30.55 11.08 4.78 OS Date of Min 0 1/02 02/18 03/26 04/17 05/23 06/04 07/02 08/23 09/25 10/28 11/12 12/30 01/02 CD p AveTemp 26.93 30.83 34.26 51.09 61.52 69.38 72.97 73.34 62.90 53.21 48.16 36.86 51.86 G

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Max. in One Day 0. 19 0.54 0.22 0.54 0.45 0.38 0.93 1.13 1.34 0.36 0.45 0.91 1.34 Date 01/30 02/09 03112 04106 05/15 06/02 07/25 08/22 09/09 10/24 11/29 12/14 09/09

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Figure 32 Wind Rose Annual Average lOOM N

DIRECTION FREGUENCY ()

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Davis-Besse Nuclear Pover Stationi 2001 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average 75M N

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Davis-Besse Nuclear Power Station 2001 Anual Radiological Envirolunental Operating Report Figure 34 Wind Rose Annual Average lOM N

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 30 (continued)

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Davis-Besse Nuclear Power Station 2001 Anual Radiological Envirormental Operating Report Land and Wetlands Management The Navarre Marsh, which is part of the Ottawa National Wildlife Refuge, makes up 733 acres of wetlands on the southwestern shore of Lake Erie and surrounds the Davis-Besse Nuclear Power Station. The marsh is owned by Toledo Edison and jointly managed by the U.S. Fish and Wild-life Service and Toledo Edison. Navarre Marsh is divided into three pools. The pools are sepa-rated from Lake Erie and each other by a series of dikes and revetments. Toledo Edison is re-sponsible 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 fornation. 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 tlrough research and is used to help educate the public about the impor-tance of 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, snakes 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.

he young eagle was one of record 38 eaglets fledged in Ohio in 1995. A new nest was built in 1999-2000, and fledged a pair of eaglets in the summer of 2000. Three more eaglets were fledged at Davis-Besse in 2001, and were part of a record hatch of 104 Ohio eaglets. The state has gone from a low of 4 nests in 1978 to a record of 73 nests in 2001.

Ohio's seventh Federal Junior Duck Stamp Art Contest was held at Davis-Besse. Young Ohio artists in grades K-12 submitted nearly 600 entries in four age brackets. The Junior Duck Stamp Art Contest was designed to teach conservation through the arts and give students a chance to experience the beauty and diversity of wildlife. A total of 101 ribbons were awarded to young Ohio artists, with the state Best-of-Show entry submitted to Washington, D.C. to compete in the 131

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report national contest with other state Best-of-Show entries. The winner of this competition will be used to make this year's Junior Duck Stamp. The 1996 Ohio Junior Duck Stamp Art Contest winner of Best-of-Show, Adam Grimm, became the youngest artist ever to win the adult Federal Duck Stamp contest. His artwork was displayed on the 2000 federal duck stamp.

Davis-Besse also hosted a Volunteer Eagle Watchers Workshop. Training was given to over 80 volunteers who will be observing Ohio's expanding eagle population during the current breeding and nesting season.

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 chlorine, lime, and other chemicals to produce high purity water, which is used by many of the Station's cooling systems.

Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which will remove debris greater than one-half inch in size. The water is then pumped to chlorine de-tention tanks. Next, the water passes through one of two clarifiers. Davis-Besse uses upflow clarifiers, or precipitators, to remove sediment, organic debris, and dissolved agents from the raw water prior to filtration. Clarifiers combine the conventional treatment steps of coagulation, flocculation, and sedimentation into a single unit. Coagulation is the process by which a chemi-cal, called a coagulant, is added, causing the small particles in the water to adhere to each other and form larger particles. During flocculation, the water is gently circulated, allowing these con-glomerate particles to mass together further. Finally, during sedimentation, large conglomerate particles settle to the bottom of the clarifier. These processes nonnally require large separate tanks. However, the use of clarifiers saves both space and the manpower needed to operate the treatment plant.

132

Davis-Besse Nuclear Power Station 2001 Ammial Radiological Environmental Operating Report RAWWWATER N..ThtEAfAJ ITT4 OSM STPURE~~~~~~~~~~~~~~UP TO Ffl WATER VALVELESS~~~~~~~~~~~~~~~~WAE TO OSMIJERJAEOF WATER $YSTDA Figure 35: At Davis-Besse, raw water is drawn into thle water treatment plant and processed to nake water for plant systems.

After the clarifier, the water goes through a flow-splitting box, which equally divides the water flow to the Automatic Valveless Gravity Filters (AVGFs). The AVGFs contain of a 50:50 ratio of anthracite to filter sand. During this filtration process, suspended matter is removed from the water and turbidity is reduced.

After filtration, the water goes to a 32,000-gallon clearwell. The clearwell acts as a reservoir from which water can be drawn as needed for all systems, including firewater and demineralized water.

Domestic Water When Davis-Besse began operation over 20 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.

Beginning in December 1998, domestic water needs at Davis-Besse have been met by the Carroll Township Water District. Since the Station no longer produces its own domestic water, these regulatory requirements have been discontinued.

Zebra Mussel Control Introduction The plant receives all of its water from an intake system from Lake Erie. Zebra mussels can se-verely impact the availability of water for plant processes. Dreissena polymorpha, commonly known as the zebra mussel, is a native European bivalve that was introduced into North 133

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report American waters in 1986 and was discovered in Lake Eric in 1989. Zebra mussels are prolific breeders that rapidly colonize an area by forming byssal threads that 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 facilities that rely on water intakes from Lake Erie because mussels may attach to the intake structures and restrict water flow.

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 pulled in 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 the intake bay #3 walls prior to the travel-ing screens. These mussels are periodically cleaned using high-pressure water. Davis-Besse uses continuous low level chlorination of the intake bays to control the mussels.

The mussel population appears to be leveling off or declining. This is likely due to the increas-ing clarity of Lake Erie. As the food source for the zebra mussel declines, mussel populations decline correspondingly.

Wastewater Treatment Plant Operation The WWTP operation is supervised by an Ohio licensed Wastewater Operator. Wastewater gen-erated by site personnel is treated at 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 where 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 over a weir and exits the plant through an effluent trough. The activated sludge contains the organisms necessary for continued treatment, and is pumped back to the aeration tank to digest incoming wastewater. The effluent leaving the plant is pumped to the wastewater basin (NPDES Outfall 601) where further treatment takes place.

Summary of 2001 Wastewater Treatment Plant Operations All wastewater parameters were within specifications during the year 2001.

134

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Repon National Pollutant Discharge Elimination System (NPDES) Reporting The OEPA has established limits on the amount of pollutants that Davis-Besse may discharge to the enviroment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 2B0001 1. Parameters such as chlorine, sus-pended solids and pH are monitored under the NPDES permit. Toledo Edison 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:

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 Wastes: Wastewater Plant sludge shipped for offsite processing Outfall 601 Wastewater Plant Tertiary Treatnent Basin: Discharge from Wastewater Treatment Plant Sources of Wastes: Wastewater Treatment Plant 135

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report 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 2001 NPDES Summary During 2001, the NPDES permit was renewed by the Ohio EPA.

This permit expired on October 31, 2000, and a renewal application was submitted in May, 2000. The permit will be effective for 5 years, after which a new permit will be negotiated. A new sampling requirement with outfall designation 004 was added to the permit renewal application. This will be used to monitor water drained from the Circulating Water System during outages. Two violations of the NPDES permit occurred dtuing 2001. The discharge limitation for Total Suspended Solids at Outfall 601 and the Total Residual Chlorine at Outfall 001 were each exceeded once.

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 1000 kilograns/month (2200 lbs./month) or more.

Small quantity Generators - A facility which generates less than 1000 kilograms/

month (2200 bs./month).

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

136

Davis-Besse Nuclear Power Station 2001 Amiial Radiological Fnvironmental Operating Report In 2001, the Davis-Besse Nuclear Power Station qualified as a small quantity generator, generat-ing 5,770 pounds of hazardous waste. Davis-Besse personnel also continuously strives to iden-tify altemate ways of reducing hazardous waste generation.

Non-hazardous waste disposed of in 2001 included 2,250 gallons of used oil, 385 gallons of oil filters and solid oily debris. Other non-hazardous regulated vaste generated included 505 gallons of other chemicals such as microfilm process chemicals and polystyrene resins.

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 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 enviromnent. 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.

137

Davis-Besse Nuclear Power Station 2001 Amual Radiological Environmental Operatiig Report Annual SARA reports are submitted to local fire departrnents and state and local planning com-missions by March I for the preceding calendar year. One additional water treatment chemical product was identified for calendar year 2001.

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 system, 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 op-eration. 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.

Clean Air Act The Clean Air Act identifies substances that are considered air pollutants. Davis-Besse holds an OEPA penmit 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 Emer-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, anl independent study identifying and quantifying all of the air pollution sources onsite was perfonmed. Of particular significance is asbestos removal from renovation and demolition projects for which USEPA has outlined spe-cific regulations conceming handling, removal, environmental protection, and disposal. Also, the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concem 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.

138

Davis-Besse Nuclear Power Stationl 2001 Annual Radiological Environmental Operating Report 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 off 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.

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 systems 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 nornal 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 majority 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 nvestment 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 139

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report 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 retumed to the seller for proper dis-posal.

Although scrap metal is not usually considered part of the MSW stream, Davis-Besse does col-lect and recycle scrap metals, which are sold at current market price to a scrap dealer for resource recovery. These programs are continuously being expanded and reinforced as other components of MSW stream are targeted for reduction.

140

A Appendices

Davis-3esse Nuclear Pover Station 2001 Annual Radiological PI.vironniental Operating Report APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental, Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental 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 tmes a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2001 through December, 2001 141

Davis-lesse Nuclear Power Station 2001 Annual Radiological Environmental Operatinig Repon As.penIix A Interlaboratorv Cou ariso Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Fnvironmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs sincp the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant 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.

The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.

This program was conducted by the U.S. Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada.

The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various Intemational Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2.

Results of crosscheck testing with Teledyne Brown Engineering are also listed.

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.

142

Davis-Besse Nuclear Power Stationi 2001 Anual Radiological nvironmental Operating Report 12-31-01 ATErACHMENTI A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for single determrinations Gamna Emitters 5 to 100 pCi/liter or kg

> 100 pCi/liter or kg 5.0 pCi/liter 5% of known value Strontium-89b Strontium-90b Potassium-40 5 to 50 pCi/liter or kg

> 50 pCi/liter or kg 2 to 30 pCi/liter or kg

> 30 pCi/liter or kg

> 0.1 g/liter or kg 5.0 pCi/liter 10% of known value 5.0 pCi/liter 10% of known value 5% of known value Gross alpha Gross beta Tritiurn 20, pCi/liter

> 20 pCi/liter 100 pCi/liter

> 100 pCi/liter 4,000 pCi/liter

> 4,000 pCi/liter Radium-226,-228 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value Is = (pCi/liter) =

169.85 x (knownfa 10% of known value 0.1 pCi/liter 15% of known value a1 pCi/liter, gram, or sample 10% of known value Iodine-131, lodine-129b 55 pCi/liter

>55 pCi/liter 6.0 pCi/liter 10% of known valuF Uraniutm-238, Nickel63b Technetium-99b 35 pci/liter

> 35 pCi/liter 6.0 pCi/liter 15% of known value 50 to 100 pCi/liter

> 100 pCi/liter 10 pCi/liter 10% of known value 20% of known value 143 Plutonium Iron-55b Othersb

' From EPA publication, Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

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

'able A-.

Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.

Concentration in pCi/Lb Lab Code STW-897 STW-897 STW-900 STW-902 STW-902 STW-902 STW-903.

STW-917 STW-917 STW-917 STW-917 STW-918 STW-918 STW-918 STW-918 STW-91 STW-918 STW-919 STW-919 STW-919 STW-919 STW-919 STW-920 STW-920 STW-920 STW-921 Delay in Result of STW-921 STW-922 STW-922 STW-924 STW-931 STW-931 STW-931 STW-932 STW-933 STW-933 Sample Type WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER Date Collected Jan, 2001 Jan, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Mar, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Jun,2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun,2001 Jur, 201 Jun, 2001 WATER Jul, 2001 Analysis Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-134 Cs-137 Gr. Beta Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Ra-226 Ra-228 Uranium Sr-89 processing may have attributed to devia reanalysis; Sr-89, 35.3 +/- 4.4 pCi/L. Sr-9C WATER Jul, 2001 Sr-90 WATER Jul, 2001 Gr. Alpha WATER Jul, 2001 Gr. Beta WATER Aug, 2001 11-3 WATER Sep, 2001 Ra-226 WATER Sep, 2001 Ra-228 WATER Sep, 2001 Uranium WATER Oct, 2001 1-131 WATER Oct, 2001 Gr. Alpha WATER Oct, 2001 Ra-226 Laboratory result' 31.9 2.1 25.3 +/- 2.7 27.2 +/- 0.8 4.04-0.1 13.8 +/-0.4 17.0+/-0.3 17,400.0+/- 69.7 57.4 +/-3.5 13.5 0.4 10.1 +/- 0.6 14.2+/- 0.2 27.9 1.4 16.0+/-t 0.4 195.4 +/-1.5 340.0:t51.0 62.8+/- 5.7 34.2 *: 1.6 37.8 +/- 1.2 49.9 +/- 0.7 16.0+/-1.4 208.0 +/- 1.7 37.8 +/-0.7 14.6 +/- 0.4 6.2+/-0.2 49.0 +/- 1.0 19.8+/-1.5 tion.

, 25.0 +/- 2.8 pCi/L.

26.3 +/- 1.1 23.3 +/- 1.9 48.5 +/- 4.6 2,680.0 +/- 41.9 10.9 +/-0.2 9.7t

+/-1.1 11.2 +/-0.1 7.7 +/- 0.3 82.2+/- 4.0 9.5 +/- 1.2 ERA Resultd 45.7 +/- 11.4 16.7 +/- 5.0 28.3 +/- 3.0 4.7 0.7 14.4 +/- 3.6 20.4 t3.0 17,800.0 +/- 1,780.0 56.0 +/- 14.0 17.7 +/-2.7 8.1 +/-2.0 15.6+/-3.0 26.4+/-5.0 16.9 +/-t 5.0 186.0 +/- 9.3 343.0 1.7 64.1 +/-5.0 33.8+/- 5.0 36.0 +/- 5.0 46.8 : 5.0 15.9 +/- 5.0 197.0 +/- 9.9 36.2 +/- 5.0 15.4+/- 2.3 4.5 +/- 1.1 55.7 +/-5.6 31.2+/-t 5.0 25.9 +/-5.0 17.8 +/- 5.0 53.0 +/-10.0 2,730.0 +/- 356.0 10.8 1.6 9.0 +/-t2.2 13.1:t+/-3.0 7.7+/-2.0 97.5 +/- 24.4 10.8 +/- 1.6 Control Limits 25.9-65.5 8.0 - 25.4 23.1 - 33.5 3.4 - 5.9 8.2 - 20.6 15.2 - 25.6 14,700.0 - 20,900.0 31.8 -80.2 13.1 - 22.3 4.6 - 11.6 10.4 - 20.8 17.7-35.1 8.2-25.6 170.0 - 202.0 252.0 - 428.0 55.5 - 72.8 25.1 - 42.5 27.3 - 44.7 38.1 - 55.5 7.2 - 24.6 180.0 - 214.0 27.5 - 44.9 11.4-19.4 2.6 - 6.5 46.1 - 65.3 22.5 - 39.9 17.2 -

9.1 -

35.7 -

2,110.0 -

8.0 -

5.1 -

7.9 -

4.2 -

55.3 -

8.0 -

34.6 26.5 70.3 3,350.0 13.6 12.8 18.3 11.2 140.0 13.6 144

l)avis-lksse Nuclear lower Station 2001 Anniual Radiological Environmental Operating Report Table A-1.

Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.

Concentration in pCi/Lb Lab Sample Date Control Code Type Collected Analysis Laboratory result ERA Result' Limits STW-933 WATER Oct, 2001 Ra-228 17.0 +/- 0.8 15.6 3.9 8.9 - 22.4 STW-933 WATER Oct.2001 Uranium 32.2+/-1.4 37.2+3.7 30.7 - 43.6 STW-934 WATER Oct, 2001 Co-60 82.4t

+/-0.9 78.4

• 5.0 69.7 - 87.1 STW-934 WATER Oct, 2001 Cs-134 52.2+/-1.3 54.1+/-5.0 45.4-62.8 STW-934 WATER Oct, 2001 Cs-137 39.4h 0.6 37.9++/-5.0 26.3 - 43.7 STW-934 WATER Oct, 2001 Gr. Beta 166.0 +/- 7.1 192.0+/-28.8 142.0 - 242.0 STW-934 WATER Oct, 2001 Sr-89 12.8+/-0.8 16.7+/-5.0 8.0 - 25.4 STW-934 WATER Oct, 2001 Sr-90 6.8 +/- 0.7 7.7+/-5.0

-1.0 - 16.4 STW-935 WATER Oct, 2001 Gr. Alpha 63.5 + 2.5 64.0 +/- 16.0 36.5 - 91.5 STW-935 WATER Oct, 2001 Gr. Beta 26.0+/- 1.2 21.5+ 5.0 12.8 - 30.2 STW-938 WATER Nov, 2001 Ba-133 66.7-1.2 69.3 6.9 57.5 - 81.1 STW-938 WATER Nov, 2001 Co-60 59.3+/-0.6 59.7+5.0 51.0 - 68.4 STW-938 WATER Nov,2001 Cs-134 86.7+/-1.5 93.9t

+/-5.0 85.2 - 103.0 STW-938 WATER Nov, 2001 Cs-137 45.0 +1.0 42.0++/- 5.0 33.3 - 50.7 STW-938 WATER Nov, 2001 Zn-65 80.7+/-0.6 77.3 +/- 7.7 63.9 - 90.7 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).

b All results are in pCi/L, except for elemental potassium (K) data in rnilk, which are in mg/L; air filter samples, which are in pCi/Pilter.

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

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

145

Davis-Besse Nuclear Power Station 2001 Aial Radiological Enviroarnental Operating Rep)ort Table A-2. Crosscleck program resilts; Thermoluminescent Dosimeters. (TLDs).

unR Lab Known Lab result Code TLD Type Date Measurement Value

+/- 2 Sigma Control Linits Telede Brown Engineering 2000-1 LiF-100 Chips 2000-1 LiF-100 Chips 2000-1 LiF-100 Chips Mar, 2000 Mar, 2000 Mar, 2000 Reader 1, #1 Reader 1, #2 Reader 1, #3 17.8 35.5 62.2 14.4 +/- 0.2 32.4+/-0.1 61.8+/-0.9 12.46 - 23.14 24.85 - 46.15 43.54 - 80.86 Talyn 2000-2 2000-2 2000-2 CeO Dy Cardins CaSO4: Dy Cards CaSO4: Dy Cards CaSO,: Dy Cards Mar, 2000 Mar, 2000 Mar, 2000 Chips and cards irradiated by Teledyne Reader 1, #1 Reader l, #2 Reader 1, #3 Brown 1ngineering, 17.8 35.5 62.2 21.3 +/-0.3 40.1+/-1.9 69.9 3.5 Westwood, New Jersey, in 12.46 - 23.14 24.85 - 46.15 43.54 - 80.86 March of 2000.

12th International Intercomparison 022-1 CaSO4: Dy Cards 022-1 CaSQ4 : Dy Cards 022-1 022-1 022-1 CaSO: Dy CaSO4: Dy CaSO,: Dy Cards Cards Cards Jun,2000 Jun,2000 Jun,2000 Jun,2000 Jun,2000 Field Field 1 Field 2 Field 3 Lab, 1 161.0 548.0 391.0 623.0 391.0 184.9+/-t 1.9 502.2 + 1.7 412.0 +/- 2.9 643.2 +/- 2.9 442.8+/--L2.5 112.70 - 209.30 383.60 - 712.40 273.70 - 508.30 436.10 - 809.90 273.70 - 508.30 Fnvironmental. Inc.

2001-1 CaSO4: Dy 2001-1 CaSO4: Dy 2001-1 CaSO,: Dy 2001-1 CaSO4: Dy 2001-1 CaSO4: Dy 2001-1 CaSO4: Dy 2001-1 2001-1 Cards Cards Cards Cards Cards Cards CaSO4: Dy Cards CaSO4: Dy Cards Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Reader 1, #1 Reader 1, #1 Reader 1, #12 Reader 1, #2 Reader 1, #3 Reader 1, #3 Reader l, #4 Reader 1, #4 4.0 4.0 7.1 7.1 15.9 15.9 63.6 63.6 3.7+/-0.1 3.4 +/-O.1 7.9t 0.2 7.6+/-0.3 18.6 +/- 0.4 19.6 +/- 0.1 78.2+1.2 79.9 +/- 2.5 2.79 - 5.17 2.79 - 5.17 4.95-9.19 4.95 ; 9.19 11.13 - 20.67 11.13 - 20.67 44.53 - 82.69 44.53 - 82.69 146

Davis-Besse Nuclear lower Station 2001 Aual Radiological Environrnental Operating Report Table A-3. In-house "spike" samples.

Concentration in pCi/L' Lab Code SPAP-477 SPW-479 SPW-481 SPW-481 SPW-482 SPW-482 SPW-483 SPW-483 Sample SPW-485 SPW-485 SPW-485 SPW-485 SPAP-754 SPW-1037 SPW-1037 SPW-1224 SPW-1224 SPW-1225 SPW-1225 SPW-1272 SPW-1272 SPVE-1274 SPCH-1276 SPMI-1270 SPMI-1270 The Cs-:

SPMI-1270 SPU-2901 SPW-2161 SPU-3128 SPW-3129 Sample Type Air Filter Water Water Water Water Water Water Water was lost during an; Water Water Water Water Air Filter Water Water Water Water Water Water Water Water Vegetation Charcoal Milk Milk 137 spike is suspect; Milk Urine Water Urine Water Date Laboratory results Collected Analysis 2s, n=lb Jan, 2001 Cs-137 Jan, 2001 H-3 Jan, 2001 Gr. Alpha Jan, 2001 Gr. Beta Jan, 2001 Gr. Alpha Jan, 2001 Gr. Beta Jan, 2001 Ra-226 Jan, 2001 Ra-228 Ilysis.

Jan, 2001 Co-60 Jan, 2001 Cs-134 Jan, 2001 Cs-137 Jan, 2001 Sr-90 Jan, 2001 Gr. Beta Feb, 2001 U-233/4 Feb, 2001 U-238 Feb, 2001 Ra-226 Feb,2001 Ra-228 Feb, 2001 Cr. Alpha Feb, 2001 Gr. Beta Feb,2001 1-131 Feb,2001 1-131(g)

Feb,2001 1-13 1(g)

Feb,2001 1-131 (g)

Mar, 2001 Cs-134 Mar, 2001 Cs-137 A new cesium spike has Mar, 2001 1-131(g)

Mar, 2001 H-3 Mar, 2001 Ra-228 Apr, 2001 1-1-3 Apr, 2001 Gr. Alpha 1.76 +/- 0.02 54702.00 +/- 644.00 5&08+/-t 2.79 213.83 +/- 3.07 51.77 +/- 2.18 202.48 +/- 2.98 20.11 +/-0.34 10.55 +/- 2.02 33.53 +/- 3.40 32.80.+/- 2.54 42.10+/-3.60 154.34+/-+ 3.49 8.53 +/-t 0.02 3.74 + 0.10 3.81 +/- 0.10 21.25 + 0.50 21.76 +/- 2.65 71.87+/-3.07 36.30+/- 1.47 56.82+/-0.71 65.69 t 10.21 0.78 +/- 0.05 1.57+0.05 31.89 +/- 4.71 46.61+/-8.81 been prepared.

81.92+/- 10.80 51512.00 +/- 1369.00 29.92+/- 5.13 2065.00 +/- 408.00 37.94 +/- 2.42 Known Activity 1.68 54549.00 69.14 220.26 69.14 220.26 20.86 19.43 31.13 30.81 36.00 137.66 7.88 4.17 4.17 20.68 19.27 69.14 28.75 63.05 63.05 0.76 1.58 29.77 35.90 81.95 50189.00 31.75 2008.00 34.57 Control' Limits 1.01 -

43639.20 -

34.57 -

198.23 -

34.57 -

198.23 -

14.60 -

13.60 -

2.35 65458.80 103.71 242.29 103.71 242.29 27.12 25.26 21.13-41.13 20S1 - 40.81 26.00 - 46.00 110.13 - 165.19

-2.12 - 17.88 2.50 - 5.84

-7.83-16.17 14.48 - 26.88 13.49 - 25.05 34.57-103.71 18.75 - 38.75 50.44 - 75.66 53.05 - 73.05 0.45 -1.06 0.95 - 2.21 19.77 - 39.77 25.90 - 45.90 71.95-91.95 40151.20- 60226.80 22.23 - 41.28 1317.37 - 2698.63 17.29 - 51.86 147

Davis-Blesse Nuciear Power Station 2.001 Annul Radiological Envirornmectal Operating Report Table A-3. In-house "spike" samples.

Concentration in pCi/L' Lab Sample Date Laboratory results Known Control' Code Type Collected Analysis 2s,n=1b Activity Limits SPW-3129 SPAP-3508 SPMI-3232 SPMI-3232 SPMI-3232 SPMI-3232 SPMI-3232 SPSO-3356 SPSO-3356 SPAP-3359 SPW-3376 SPW-3376 SPW-3376 SPW-3377 SPW-3129/1 SPW-3129/ 1 SPW-3129/2 SPW-3129/2 SPVE-3303 SPSO-5701 SPSO-5701 SPW-5779 SPW-5779 SPW-5779 SPF-5781 SPF-5781 SPW-5937 SPW-59441 SPW-59441 SPAP-5703 SPW-3129/3 Water Air Filter Milk Milk Milk Milk Milk Soil Soil Air Filter Water Water Water Water Water Water Water Water Vegetation Soil Soil Water Water Water Fish Fish Water Water Water Air Filter Water Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 May, 2001 May, 2001 Jun, 2001 Jun, 2001 Jun. 2001 Jul, 2001 JuL 2001 Jul, 2001 Jul 2001 Jul, 2001 JuL 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 JuL 2001 Jul, 2001 Cr. Beta Gr. Beta Cs-134 Cs-137 1-131 1-131 (g)

Sr-90 Co-60 Cs-137 Cs-137 Co-60 Cs-134 Sr-90 1-131 Gr. Alpha Gr. Beta Cr. Alpha Gr. Beta 1-131(g)

Co-60 Cs-137 Co-60 Cs-137 Sr-90 Co-60 Cs-137 H-3 Ra-226 Ra-228 Cs-137 Gr. Alpha 117.83 +/- 2.37 0.80 +/- 0.01 32.69 +/-6.50 44.20 +/- 9.08 48.05 +/- 0.90 55.64 +/-11.39 143.77 +/- 3.04 18.49 +/- 0.21 18.71 +/- 0.24 1.80+/-0.01 48.17 +/- 4.85 37.14+/-3.90 159.84 +/- 3.42 68.60+/-2.63 37.94+/-2.42 117.83+/-2.37 34.42 +/- 2.14 119.99 +/-2.45 0.81+/-0.03 17.42 +/- 0.19 16.03 +/-i 0.22 250.05+/-18.63 178.68 +/-19.89 72.12 +/-2.24 1.87 +/- 0.08 1.43+/-0.07 51177.00+/-631.00 36.62 +/- 1.74 41.46 +/- 6.44 1.81 +/- 0.02 35.31 +/-: 3.04 148 109.46 0.78 33.96 35.79 56.68 56.68 136.82 19.57 16.61 1.67 45.19 33.96 136.82 85.02 34.57 109.46 34.57 109.46 0.86 19.05 16.52 233.26 175.91 68.12 1.79 1.39 50189.00 34.46 36.06 1.67 34.75 98.51 -

-9.22 -

23.96 -

25.79 -

45.34 -

46.68 -

109.46 -

9.57 -

6.61 -

1.00 -

35.19 -

23.96 -

109.46 -

68.02 -

17.29 -

98.51 -

17.29 -

98.51 -

0.51 -

9.05 -

6.52 -

209.93 -

158.32 -

54.50 -

1.07 -

0.83 -

40151.20-24.12 -

25.24 -

1.00-17.38-120.41 10.78 43.96 45.79 68.02 66.68 164.18 29.57 26.61 2.34 55.19 43.96 164.18 102.02 51.86 120.41 51.86 120.41 1.20 29.05 26.52 256.59 193.50 81.74 2.51 1.95 60226.80 44.80 46.88 2.34

-52.13

Davis-13esse Nuclear Power Station 2001 Annual Radiological Fnvironmental Operating Report Table A-3. In-house "spike" samples.

Concentration in pCi/L Lab Sample Date Laboratory results Known Control' Code Type Collected Analysis 2s, n=lb Activity Limits SPW-3129/3 Water Jul, 2001 Gr. Beta 113.28 +3.65 109.46 98.51 - 120.41 SPMI-6145 Milk Jul, 2001 Cs-137 188.45

• 19.10 175.91 158.32 - 193.50 SPW-6604 Water Jul, 2001 Gr. Alpha 35.36+/-1.94 34.57 17.29 - 51.86 SPW-6604 Water Jul, 2001 Gr. Beta 11256 +/-2.46 108.82 97.94 - 119.70 SPW-9008 Water Oct, 2001 H-3 48285.00+/-606.10 50189.00 40151.20-60226.80 SPAP-9010 Air Filter Oct, 2001 Cs-137 1.91+/-0.01 1.67 1.00- 2.34 SPW-10723 Water Dec, 2001 U-233/4 40.12+1.09 41.73 25.04-58.42 SPW-10723 Water Dec, 2001 U-238 40.16: 1.09 41.73 29.21 - 54.25 SPAP-115S0 Air Filter Dec, 2001 Gr. Beta 1.58 +/-0.02 1.56

-8.44 - 11.56 SFW-11757 Water Dec, 2001 Co-60 43.82+/-3.14 41.36 31.36-51.36 SPW-1 1757 Water Dec,2001 Cs-134 24.11 +/- 2.42 22.59 12.59 - 32.59 SPW-11757 Water Dec, 2001 Cs-137 52.11 +/-4.40 50.89 40.89-60.89 SPMI-11759 Milk Dec, 2001 Cs-134 28.03+/-2.64 27.10 17.10 - 37.10 SPMI-11759 Milk Dec, 2001 Cs-137 54.59+/-t5.08 50.89 40.89-60.89 SPF-11761 Fish Dec,2001 Cs-134 0.94++/- 0.02 0.90 0.54 - 1.26 SPF-11761 Fish Dec, 2001 Cs-137 1.43+/-0.04 1.43 0.86-2.00

' All results are in pCi/L, except for elemental potassium (K) in milk, which which are in pCi/Filter; and food products, which are in pCi/kg.

bResults are based on single determinations.

'Control limits are based on Attachmient A, Page A2 of this report.

are in mg/L.; air filter samples, NOTE: For fish, Jel'o is used for the spike matrix. For vegetation, coleslaw is used for the spike matrix.

149

Davis-Besse Nuclear Power Station 2001 Annnail Radiological Enviromental Operating Report Table A-4.

In-house "blank" samples.

Lab Code SPAP-478 SPAP-478 SPAP-478 SPW-480 SPW-484 SPW-484 SPW-484 SPW-484 SPW-486 SPW-486 SPW-486 SPW-486 SPAP-755 SPW-1038 SPW-1038 SPW-1223 SPW-1223 SPW-1223 SPW-1223 SPMI-1268 SPMI-1268 SPMI-1268 SPW-1271 SPW-1271 SPW-1271 SPVE-1273 SPVE-1273 SPCH-1275 SPW-2164 SPU-3126 Sample Type AIR FILTER AIR FILTER AIR FILTER WATER WATER WATER WATER WATER WATER WATER WATER WATER AIR FILTER WATER WATER WATER WATER WATER WATER MILK MILK MILK WATER WATER WATER VEGETATION VEGETATION CHARCOAL CANISTER WATER URINE Sample Date Jaii 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Mar 2001 Apr 2001 Analysis Co-60 Cs-134 Cs-137 H-3 Gr. Alpha Gr. Beta Ra-226 Ra-228 Co-60 Cs-134 Cs-137 Sr-90 Gr. Beta U-238 U-238 Gr. Alpha Gr. Beta Ra-226 Ra-228 Cs-134 Cs-137 1-131(g)

Co-60 Cs-134 Cs-137 Cs-134 Cs-137 1-131(g)

Ra-226 H-3 Concentration pCi/L`.

Laboratory results Acceptance (4.66 Sigma)

Criteria LLD Activityb (4.66 Sigma)

< 1.12

< 100.0

< 1.66

< 100.0

< 2.46

< 100.0

<162.00

-1.86 80.40

< 200.0

<0.68

<1.0

< 1.35

< 3.2

<0.02 0.03 0.01

<1.0

< 0.97 0.43 : 0.50

< 2.0

< 2.68

< 10.0

< 3.46

< 10.0

< 5.43

< 10.0

< 0.65 0.06 +/-L0.31

< 1.0

< 1.60 0.16 +/-0.90

<3.2

<0.03

<1.0

<0.00

<1.0

< 0.46

< 1.0

< 1.50

< 3.2

< 0.02 0.03 +/-0.01

< 1.0

<0.95 0.45 t 0.49

<2.0

< 5.86

< 10.0

< 3.02

< 10.0

< 7.46

< 20.0

< 1.06

<10.0

< 2.61

< 10.0

< 2.37

< 10.0

< 10.04

< 100.0

< 6.00

< 100.0

< 0.01

< 9.6

< 0.02

< 642.00 0.05 0.01

-66.00 +/- 335.00

<1.0

< 200.0 Z0 ml. sample volume.

150

DavislBesse Nucle.ar Powver Station 2001 Atial Radiological Environnental Operating Itlolt

'T'able A-4.

In-house "blank" samples.

Lab Code SPDW-3130 SPDW-3130 SPMI-3233 SPMI-3233 SPMI-3233 SPMI-3233 SPMI-3233 Low level of SPS0-3357 SPSO-3357 SPAP-3358 SPW-3375 SPW-3375 SPW-3375 SPW-3375 SPVW-3130 SPDW-3130 SPDW-3130 SPDW-3130 SPVE-3304 SPVE-3304 SPVE-3304 SPSO-5702 SPSO-S702 SPSO-5702 SPAP-5704 SPAP-5704 SPAP-5704 SPW-5780 SPW-5780 SPW-5780 Sample Type WATER WATER MILK MILK MILK MILK MILK Sr-90 concentration SOIL SOIL AIR FILTER WATER WATER WAtER WATER WATER WATER WATER WATER VEGETATION VEGETATION VEGETATION SOIL SOIL SOIL AIR FILTER AIR FILTER AIR FILTER WATER WATER WATER Concentration pCi/L'.

Laboratory results Acceptance Sample (4.66 Sigma)

Criteria Date Analysis L ILD Activityb (4.66 Sigma)

Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 in milk (1-5 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001.

Apr 2001 Apr 2001 May 2001 May 2001 Jun 2001 Jtm 2001 Jun2001 Jun 2001 Jun 2001 Jul 2001 Jul2001 Jul 2001 Jul 2001 Jul 2001.

Juil 2001 Jul2001 Jtul 20)01 Jil 2001 Gr. Alpha Gr. Beta Cs-137 1-131

]-13 1(g)

Sr-89 Sr-90 pCi/L) is not Cs-134 Cs-13?

Cs-137 Co-60 Cs-134 1-131(g)

Sr-90 Cr. Alpha Cr. Beta Or. Alpha Gr. Beta Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137

< 0.54 c 1.46

< 2.66

< 0.26

< 3.91

< 0.79 unusual.

< 14.77

< 11.72

< a55

< 2.90

< 3.71

< 0.39

< 0.56

< 0.45

< 1.26

< 0.44

<1.46

< 7.06

< 11.56

< 8.30

< 12.80

< 13.96

<8.10 c 0.79

< 0.84

< 0.60

< 1.86

< 2.46

< 3.77 0.04 +/- 0.38 0.67 +/- 1.04

-0.06 0.14

-0.32 1.18 0.02 0.05 0.15 0.34 0.09 0.66

+0.79

+/- 0.35

+/-t 0.22

+/- 0.27 j +/-0.34

+/- 0.95 1 0.32

+/-t 1.04

<1.0

<3.2

< 10.0

<0.5

< 20.0

<5.0

<1.0

< 100.0

< 100.0

< 100.0

<10.0

< 10.0

< 20.0

<1.0

<1.0

<3.2

<1.0

<3.2

< 100.0

< 100.0

< 100.0

< 100.0

< 100.0

< 100.0

< 100.0

< 100.0

< 100.0

< 10.0

<10.0

< 10.0 151

Davis-Bessc Nuclear 'ower Statior 2001 Aual Radiological Envirojunntal Opcrating Report Table A-4.

In-house "blauik" samples.

Concentration pCi/I'.

Laboratory results Acceptance Lab Sample Sample (4.66 Sigma)

Criteria Code Type Date Analysis LLD Activity (4.66 Sigma)

SPF-5782 FISH Jul2001 Co-60

<5.64

<100.0 SPF-5782 FISH Ju12001 Cs-134

< 7.51

< 100.0 SPW-5938 WATER Jul2001 H-3

< 163.22

-16.21 +/-85.07

<200.0 SPW-59451 WATER Ju12001 Ra-226

<0.01 0.04 0.01

<1.0 SPW-59451 WATER Jul2001 Ra-228

<0.77 0.70 +/-0.44

<2.0 SPDW-3130 WATER Jul2001 Gr. Alpha

< 0.54 0.36 +/- 0.40

<1.0 SPDW-3130 WATER Jul2001 Gr. Beta

<2.27

-0.78 +/- 1.35

<3.2 SPMI-6146 MILK Jul 2001 Sr-90

< 0.50 1.09 +/- 0.36

< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-6605 WATER Jul2001 Gr. Beta

< 1.34 0.55 +/- 1.01

<3.2 SPW-9009 WATER Oct2001 H-3

< 160.00

-56.70 f 76.50

<200.0 SPAP-9011 AIR FILTER Oct2001 Co-60

<0.76

<100.0 SPAP-9011 AIR FILTER Oct2001 Cs-137

<0.58

<100.0 SPW-5780 WATER Oct 2001 Sr-90

< 0.54 0.36 0.30

< 1.0 SPW-10724 WATER Dec 2001 U-238

< 0.13 0.04 o 0.10

< 1.0 SPAP-11549 AIR FILTER Dec2001 Gr. Beta

<0.00 0.01 0.00

<3.2 SPW-11756 WATER Dec2001 Cs-137

<2.62

<10.0 SPMI-11758 MILK Dec2001 Cs-137

<4.00

<10.0 SPMI-11758 MILK Dec2001 1-131(g)

< 16.57

<20.0 SPF-11760 FISH Dec 2001 Cs-137

<7.96

<100.0

' Liquid sample results are reported in pCi/Liter, air filter sample results are in pCi/filter, charcoal sample results are in pC/charcoal, and solid sample results are in pCi/kilogram.

b The activity reported is the net activity result.

152

Davis-Besse Nuclear Powcr Station 2001 Annual Radiological Environrnental Operating Report Table A-5.

In-house "duplicate" samples.

Concentration in pCi/L Lab Codes AP-10675, 10676 AP-10803, 10804 AP-10833,10834 WW-51, 52 MI-72, 73 MI-96, 97 U-858, 859 MI-389, 390 DW-879, 880 SWU-813, 814 MI-708, 709 Ml-740, 741 Ml-740, 741 MI-789, 790 DW-901, 902 SWU-1544, 1545 DW-1426, 1427 DW-1426, 1427 Wt2-1476, 1477 MI-1523, 1524 MI-1523, 1524 MI-1572, 1573 MI-1572, 1573 SW-1648, 1649 MI-1800, 1801 SW-1779, 1780 SW-1779, 1780 Ml-1447, 1448 MI-1447, 1448 WW-2115, 2116 SW-1698, 1699 DW-2272, 2273 WM-2356, 2357 AP-2812, 2813 AP-2812, 2813 LW-2217, 2218 Sample Date Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Analysis Be-7 Be-7 Be-7 H-3 K-40 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 1-131 K-40 K-40 Gr. Beta Gr. Beta Gr. Beta H-3 H-3 1-131 K-40 K-40 Sr-90 K-40 K-40 Gr. Alpha Gr. Beta 1-131 K-40 H-3 Gr. Beta Gr. Beta Gr. Beta Be-7 Be-7 Gr. Beta First Result 0.06 4 0.02 0.04 +/- 0.01 0.04 +/- 0.01 362.60 +/- 94.70 1,566.90 +/- 196.80 1,418.30 s 117.80 2.17 +/- 2.47 1,489.20 + 141.10 2.63 +/- 0.52 2.48 0.58 1,179.40+/- 103.00 0.01 +/- 0.26 1,434.00 +/- 156.50 1,584.30 +/- 158.80 4.67 +/- 1.08 3.13 +/- 0.63 2.05 +/- 0.92 42.60 +/- 94.23 53.06 +/- 65.79

-0.01 +/- 0.20 1,396.00+/- 184.80 1,499.20 +/- 113.30 1.65 0.44 297.80 +/- 67.20 1,425.80 +/- 183.30 2.22 +/-0.73 6.28 +/- 0.74

-0.65 +/- 0.27 1,496.20 +/- 155.40 540.04 +/- 111.84 6.07 +/- 1.75 2.10 0.86 1.22+/-i 0,50 0.07 +/- 0.02 0.07 +/- 0.02 1.85 : 0.51 Second Result 0.06 +/- 0.02 0.04 +/- 0.01 0.04 +/- 0.01 417.20 +/- 96.80 1,372.40 t 152.50 1,545.70 +/- 162.50 4.23 +/- 2.74 1,463.30 +/- 168.20 2.37 : 0.50 2.46 +/- 0.63 1,280.40 : 90.26

-0.12 0.26 1,435.00 +/- 126.10 1,390.70 +/- 136.50 5.54 +/- 1.13 2.33 +/- 0.52 2.34 +/- 0.93 131.31 + 95.34 53.06+/-93.03

-0.10 +/- 0.37 1,576.00 184.90 1,326.00 118.80 1.51 +/-0.52 344.80 +/- 82.30 1,372.20 +/- 119.70 2.14 +/- 0.69 6.62 +/- 0.70 0.13 t 0.55 1,413.40 +/-F 169.60 500.85 +/-110.46 5.57 +/- 1.85 1.63 +/-0.83 1.32 +/- 0.47 0.05 +/- 0.01 0.05 +/- 0.01 2.23 +/- 0.55 Averaged Result 0.06 +/- 0.01 0.04 +/- 0.01 0.04 +/- 0.01 389.90 +/- 67.71 1,469.65 +/- 124.49 1,482.00 +/- 100.35 3.20+/-1.84 1,476.25 : 109.77 2.50:: 0.36 2.47 +/- 0.43 1,229.90 +/-68.48

-0.05 +/-0.18 1,434.50 +/- 100.49 1,487.50 +/- 104.70 5.11 0.78 2.73 +/- 0.41 2.20:t+/-0.65 86.96 +/- 67.02 53.06 +/- 56.97

-0.06 +/- 0.21 1,486.00 +/- 130.71 1,412.60 82.08 1.58 +/- 0.34 321.30 +/- 53.13 1,399.00 109.46 2.18+/-.50 6.45 +/- 0.51

-0.26 +/- 0.31 1,454.80:+/- 115.01 520.44 +/- 78.59 5.82+/-t 1.27 1.87 +/- 0.60 1.27 : 0.35 0.06 +/- 0.01 0.06 +/- 0.01 2.04 +/- 0.37 153

Davis-Besse Nuclear 'ower Station 2001 Alual Radiological Enivironmental Operating Report Table A-5.

In-house "duplicate" sarnples.

Concentration in pCi/L' Lab Codes AP-2833, 2834 AP-3038, 3039 AP-3038, 3039 DW-2398, 2399 LW-2467, 2468 Ml-2446, 2447 AP-3017, 3018 SW-2423, 2424 8S-3103, 3104 SWU-3239, 3240 SS-3322, 3323 W-3990 3991 BS-4347, 4348 BS-4347, 4348 Ml-3364, 3365 S0-3385, 3386 SO-3385, 3386 S0-3385, 3386 CL-4068, 4069 MI-3475, 3476 WW-3545, 3546 Ml-3681, 3682 SW-3702, 3703 SW-3702, 3703 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 F-3813, 3814 G-4158,4159 SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 Sample Date Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 Analysis Be-7 Be-7 Be-7 Gr. Beta Gr. Beta K-40 Be-7 K-40 Gr. Beta Gr. Beta K-40 Sr-89 K-40 K-40 K-40 Gr. Alpha Cr. Beta K-40 K-40 Gr. Beta Gr. Beta K-40 Gr. Alpha Gr. Beta Cs-137 H-3 K-40 Pu-238 Pu-239/40 Ra-226 Sr-90 K-40 Be-7 Ac-228 Bi-214 Cs-137 First Result 0.04 +/- 0.01 0.07 0.02 0.06 +/- 0.02 1.58 +/- 0.89 2.52

• 0.53 1,285.40 +/- 177.10 0.05 +/- 0.01 255.60 +/- 59.80 7.99 +/-1.80 3.30 +/- 0.60 15.99 + 1.08 91.35 +/- 18.94 3,982.40 +/-489.60 3.26 +/- 0.45 1,325.90 +/- 160.20 6.51 +/-3.09 24.63 +/- 3.15 19.17 +/- 1.08 1.09 +/- 0.27 1,297.10+/-114.60 1.57+/-0.55 1,417.20 +/- 125.70 4.51 +/- 1.66 8.74 +/- 1.36 224.30 +/- 30.20 842.00 +/- 47.00 21,117.00 +/- 953.00 80.30 +/- 36.50 49.40 +/- 31.80 7,436.00 +/- 577.90 10.60 : 2.71 2.10 +/- 0.17 0.37 +/- 0.13 0.45 +/- 0.13 0.31 +/- 0.06 0.46 +/- 0.05 Second Result 0.06+/-0.02 0.07+/-0.02 0.07 + 0.01 1.81 +/- 0.88 2.42 +/- 0.53 1,376.00 175.90 0.05 +/-0.01 268.40+/- 65.40 8.17 +/- 1.73 4.30 ! 0.74 15.59 +/- 1.01 85.29 +/- 23.99 3,255.80 +/- 450.10 3.98 : 0.49 1,453.20 +/- 163.00 9.01 +/-3.44 28.17i 3.12 17.94 +/-0.76 1.13+/-0.23 1,433.60 + 156.60 1.36 +/- 0.53 1,496.20+/-i 124.50 3.22 +/- 1.55 7.11 +/- 1.38 205.90 +43.00 860.00 +/- 48.00 21,629.00 1,357.00 59.50 +/- 22.00 41.10 +/- 19.60 9,126.00 +/- 751.90 16.80+/-t 3.22 2.30 +/- 0.26 0.41 +0.14 0.52 +/-0.14 0.41 +/- 0.06 0.47:t0.04 Averaged Result 0.05 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 1.69 +/- 0.63 2.47 +/- 0.37 1,330.70+/-t 124.81 0.05 +/- 0.00 262.00 +/- 44.31 8.08+/- 1.25 3.80 +/- 0.48 15.79 +/- 0.74 88.32 t 15.28 3,619.10+/-332.53 3.62 +/- 0.33 1,389.55 +/- 114.27 7.76 +/- 2.31 26.40 +/- 2.22 18.56 +/- 0.66 1.11 +/- 0.18 1,365.35 +/-- 97.03 1.47 +/- 0.38 1,456.70

• 88A6 3.87 +/- 1.13 7.93 +/- 0.97 215.10 +/-26.27 851.00 +/-83.59 21,373.00 +/- 829.10 69.90 +/-*21.31 45.25 +/- 18.68 8,281.00 +/-474.16 13.70 +/- 2.10 2.20 +/-0.16 0.39 +/- 0.10 0.49 t 0.10 0.36 +/- 0.04 0.47 +/- 0.03 154

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table A-5.

In-hours "duplicate" samples.

Concentration in pCi / L Lab Codes SO-4179, 4180 50-4179, 4180 S0-4179, 4180 50-4179, 4180 S04179, 4180 BS-4233, 4234 BS-4233, 4234 SWU-4376, 4377 DW-4449, 4450 DW-4397, 4398 MI-4114, 4115 F4284, 4285 DW-4326, 4327 Ml-4470, 4471 SW-4493, 4494 BS-4725, 4726 BS-4725, 4726 BS-4725, 4726 MX4775, 4776 WW-5110, 5111 C-5085, 5086 G-5085, 5086 MI-5259, 5260 MI-5259, 5260 SWU-5422, 5423 VE-5401, 5402 VE-5401, 5402 AP-5830, 5831 SW-5557, 5558 AP-5851, 5852 SW-5636, 5637 LW-5681, 5682 G-5535, 5536 G-5535, 5536 G-5535, 5536 AP-5788, 5789 Sample Date May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun,2001 Jun,2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun,2001 Jun, 2001 Jun, 2001 Jun,2001 Jun,2001 Jun, 2001 Jun, 2001 Jun,2001 Jun,2001 Jun,2001 Jun, 2001 Jun, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Analvsis Gr. Beta K-40 Pb-212 Ra-226 TI-208 Cs-137 K-40 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 Gr. Beta K-40 Gr. Beta Co-60 Cs-137 K-40 K-40 H-3 Be-7 K-40 K-40 Sr-90 Gr. Beta Gr. Beta K-40 Be-7 Gr. Beta Be-7 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Be-7 First Result 26.65 +/- 2.63 16.35 +0.86 0.35 +/- 0.04 0.56+/-0.98 0.14 +/-0.03 0.03 +/-0.01 8.18 +/- 0.48 2.58 +/- 0.55 2.83 +/- 0.55 9.13 +/-1.26 1,325.90 +/- 118.80 2.23 +/- 0.32 2.60 +/- 0.97 1,514.50 +/- 116.60 4.05 1.23 112.00 +/- 24.30 3,083.10 +/- 100.10 8,143.70 +/- 640.40 1,362.20:t71.80 1,173.50 +/-129.10 0.89 +/- 0.17 5.13 +/-0.39 1,529.70 +/- 122.70 1.69 +/-0.42 2.59 +/-0.54 8.12 +/-0.24 6.55 +/-0.52 0.08 +/- 0.01 5.43 +/- 1.70 0.07+/-0.02 4.75 +/- 1.38 2.42 +/- 0.37 0.99 +/-0.29 7.62 +/- 0.12 7.26 +/- 1.03 0.08 +/- 0.02 Second Result 24.68 +/- 2.52 16.05+/-0.82 0.43 +/-:0.05 1.03 +/- 0.31 0.17 +/-0.03 0.03 +/- 0.02 7.80 +/- 0.58 2.94 +/- 0.58 3.74 +/- 0.65 10.20 +/- 1.34 1,394.70 +133.10 2.12 +/- 0.35 1.47 +/- 0.83 1,456.80 +/- 130.90 4.64 +/- 1.32 84.50 +/- 8.70 3,094.80 +/- 35.30 8,083.80+/-i 225.10 1,363.90 +/- 73.40 1,046.80 +/- 125.20 1.14 +/- 0.39 5.22+/- 0.70 1,406.20 + 123.80 1.71 + 0.44 1.91 +/-0.52 8.88 +/- 0.26 6.26 +/-0.65 0.08 +/- 0.01 5.96 +/- 1.56 0.07 +/- 0.02 4.18 1.34 2.18 +/- 0.34 0.97 +/- 0.54 7.72 +/- 0.12 7.64 +/- 0.93 0.07 +/-0.02 Averaged Result 25.67 +/- 1.82 16.20 +/- 0.59 0.39 + 0.03 0.79 - 0.51 0.15 : 0.02 0.03 +/- 0.01 7.99 + 0.38 2.76 +/-0.40 3.29 +/- 0.43 9.66 +/- 0.92 1,360.30 +/- 89.20 2.18 +/- 0.24 2.04 +/- 0.64 1,485.65 +/-87.65 4.35 +/- 0.90 98.25 +/- 12.91 3,088.95 +/- 53.07 8,113.75 +/- 339.40 1,363.05 +/- 51.34 1,110.15 +/- 89.92 1.02 +/- 0.21 5.17 t0.40 1,467.95 +/-87.15 1.70 +/- 0.30 2.25 +/-0.37 8.50_+/-0.18 6.40 t 0.42 0.08 +/- 0.01 5.70 +/- 1.15 0.07 +/-0.01 4.47 +/- 0.96 2.30_0.25 0.98 +/-0.31 7.67 +/- 0.08 7.45 +/-0.69 0.08_ 0.01 155

Davis-Besse Nuclear Power Station 2001 Anriuai tadiological Environmerintal Operating Report Table A-S.

In-house "duplicate" samples.

Concentration in pCi/L' Lab Codes AP-5872, 5873 AP-5893, 5894 Al'-5809, 5810 SW-5724, 5725 SW-5724, 5725 SW-5767, 5768 LW-5920, 5921 SO-6172, 6173 SO-6172, 6173 SO-6172, 6173 M14-6353, 6354 SW-6376, 6377 VE-6424, 6425 VE-6424, 6425 MI-6445, 6446 LW-6489, 6490 M1-6533, 6534 DW-6835, 6836 Ml-6693, 6694 Ml-6693, 6694 WW-6952, 6953 Ml-6906, 6907 VE-6973, 6974 LW-7851, 7852 Ml-7001, 7002 MI-7073, 7074 LW-7145, 7146 MI-7221, 7222 Ml-7221, 7222 SWU-7527, 7528 VE-7485, 7486 DW-7506, 7507 MI-7622, 7623 MI-7664, 7665 Ml-7876, 7877 G-7960, 7961 Sample Date Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul. 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul,2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug. 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001.

Aug, 2001 Aug, 2001 Aug,2001 Aug, 2001 Aug,2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Analysis Be-7 Be-7 Be-7 Gr. Alpha Gr. Beta I-131 Gr. Beta Cs-137 K-40 Sr-90 K-40 1-131 Gr. Beta K-40 K-40 Gr. Beta K-40 Gr. Beta K-40 Sr-90 Gr. Beta K-40 K-40 Gr. Beta K-40 K-40 Gr. Beta K-40 Sr-90 Gr. Beta K-40 Gr. Beta K-40 K-40 K-40 Be-7 First Result 0.07

• 0.02 0.08 +0.02 0.07+/-t 0.02 2.95 +/- 0.70 8.79 0.71 0.79 j 0.31 3.06 0.64 0.30:t 0.05 18.20 +/- 1.08 0.03 + 0.01 966.35 +/-82.28 0.58 +/- 0.16 2.52 +/- 0.05 3.04 +/- 0.26 1,407.40 +/- 97.10 2.61 +/- 0.57 1,498.60 113.90 2.01+/-t0.59 1,294.30 +/-118.70 1.47 +/- 0.42 5,49 +/- 0.69 1,613.80 +/-218.50 4.21 +/- 0.24 2.20 +/- 0.48 1,453.80 +/-t 148.10 1,217.30 +/- 80.83 2.77 +/- 0.53 1,192.90 +/- 95.40 2.10 t0.48 17.51 +/- 3.06 2.12 +/- 0.47 4.25 +/- 1.18 1,340.10 +/- 111.10 1,408.10 +/- 102.70 1,416.40 +/- 192.30 1.27 +/- 0.21 Second Result 0.08 +/- 0.02 0.08 +/- 0.01 0.06 + 0.01 2.89 +/-0.60 8.21 +/- 0.65 0.61 + 0.26 3.15 +/-0.58 0.32 +/-0.04 17.55 +/- 0.82 0.05 +/- 0.02 986.31 +/- 91.91 0.81 +/- 0.17 2.49+/-0.05 3.12 +/- 0.37 1,442.20 +/- 189.60 2.79 +/- 0.54 1,375.50 +/- 129.60 2.36 +/- 0.63 1,417.30 +/- 176.50 1.23 : 0.41 5.80 +/- 0.69 1,532.70+/-135.80 4.29 +/- 0.64 2.12 +/- 0.42 1,285.30 +/- 190.50 1,218.30 +/-99.13 3.60 +/- 0.59 1,388.90 +/- 132.70 1.72 +/- 0.47 20.36 +/-3.31 2.47 +/- 0.34 4.13+/-1.12 1,290.80 +/- 116.50 1,396.90 +/- 114.30 1,318.00 +/- 155.50 1.25 +/-0.25 Averaged Result 0.07 +/- 0.01 0.08 +/- 0.01 0.06 +/- 0.01 2.92 +/-t 0.46 8.50 +/- 0.48 0.70 +/- 0.20 3.11 +/-0.43 0.31 +/- 0.03 17.88 t+/-0.68 0.04 +/- 0.01 976.33 +/- 61.68 0.70 +/-0.12 2.51 +/- 0.03 3.08 +/- 0.23 1,424.80 +/- 106.51 2.70 +/- 0.39 1,437.05 +/- 86.27 2.19 +/- 0.43 1,355.80 +/- 106.35 1.35 +/- 0.29 5.64 +/- 0.49 1,573.25 +/- 128.63 4.25+/-0.34 2.16+/-0.32 1,369.55+/-120.65 1,217.80 +/- 63.95 3.19 +/- 0.39 1,290.90+ 81.72 1.91+/-. 0.34 18.93 2.25 2.30 +/- 0.29 4.19 +/- 0.81 1,315.45 t 80.49 1,402.50 +/- 76.83 1,367.20t

+/-123.65 1.26+/-_0.16 156

Davis-Besse Nuclear lower Station 2001 Arual Radiological Environmental Operating Report Table A-5.

In-house "duplicate" samples.

Concentration in pCi/L Lab Coces G-7960, 7961 F-8011, 8012 F-8011, 8012 F-8011, 8012 Ml-8149, 8150 M-8343, 8344 VE-8319, 8320 VE-8319, 8320 AP-9069, 9070 AP-9566, 9567 VE-8700, 8701 VE-8700, 8701 VE-8700, 8701 AP-9048, 9049 DW-8636, 8637 DW-8615, 8616 AP-9090, 9091 AP-9166, 9167 Al-9187, 9188 VE-10562, 10563 VE-10562, 10563 WW-8636, 8637 DW-8894, 8895 Ml-9232, 9233 VE-9518, 9519 WW-10257, 10258 VE-10333, 10334 VE-10333, 10334 MI-10588, 10589 DW-10688, 10689 WW-10905, 10906 55-10953, 10954 SS-10953, 10954 SS-10953, 10954 SS-10953, 10954 SS-10953, 10954 Sample Date Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct,2001 Oct, 2001 Oct, 2001 Oct 2001 Oct 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Analysis K-40 Cs-137 Gr. Beta K-40 K-40 K-40 Gr. Beta K-40 Be-7 Be-7 Be-7 K-40 Sr-90 Be-7 Gr. Beta Gr. Beta Be-7 Be-7 Be-7 Be-7 K-40 Gr. Beta Gr. Beta K-40 K-40 H-3 Be-7 K-40 K-40 Gr. Beta H-3 Ac-228 Bi-214 Co-58 Co-60 Cs-137 First Result 5.21 +/- 0.57 0.06 :+/-0.02 3.68 +/- 0.12 3.47 +/- 0.49 1,551.70 118.00 1,550.30 +/- 170.60 3.37+/-0.10 2.14 +/-0.46 0.07 +/- 0.02 0.08 +/-:0.02 0.24 +/-0.10 2.03 +/- 0.24 0.01 +/- 0.00 0.07 +/- 0.01 4.74 +/- 1.06 4.65 +/-0.58 0.07 0.01 0.08 +/- 0.02 0.07 +/- 0.01 309.90 158.80 6,407.10 620.70 5.08 +/- 1.20 4.28 40.89 1,440.70 +/- 46.60 1.91 +/-0.22 755.90+/-102.50 068 + 0.26 6.10 +/-0.72 1,428.40 : 114.70 3.49 +/- 0.91 233.90 +90.60 1.10+/-0.25 0.69 +0.08 0.21 +/- 0.05 0.93 +/-0.06 0.13 +/- 0.03 Second Result 5.70 +/- 0.63 0.04 +/- 0.02 3.50+/-0.11 3.38:+/- 0.47 1,489.90+/-123.60 1,368.10 +/- 126.70 3.42 +0.11 2.24 ti 0.37 0.07 +/- 0.01 0.09 +/-0.03 0.19 +/-0.10 2.03:+/- 0.21 0.01 +0.00 0.07+/-0.00 5.08 +/- 1.21 4.28 +/-0.54 0.07+/-0.01 0.08 +/- 0.02 0.05 t 0.01 348.30 +/- 168.10 6,057.50 +/- 660.40 4.74 +/-1.06 3.40 +/- 0.90 1,424.80*76.40 1.97 +/-0.39 684.70 t 99.90 0.99+0.26 5.83 +/- 0.72 1,445.50 +/- 129.40 2.36 : 0.76 226.30:+/- 90.20 0.91 +/- 0.16 0.75 +/- 0.08 0.18:t0 04 0.94+/-0.06 0.16 t 0.03 Averaged Result 5.45 +/- 0.43 C.05 +/- 0.01 3.59 +/- 0.08 3.43 +/- 0.34 1,520.80 t 85.44 1,459.20 +/- 106.25 3.39 t 0.07 2.19 t 0.29 0.07t 0.01 0.09 +/- 0.02 0.22 : 0.07 2.03 +/- 0.16 0.01 +/- 0.00 0.07 +/- 0.01 4.91 +/- 0.80 4.47 +/- 0.40 0.07 +/- 0.01 0.08 : 0.01 0.06 +/- 0.01 329.10 +/- 115.62 6,232.30 +/- 453.15 4.91+/-0.80 3.84+/-0.63 1,432.75:+/-44.75 1.94t

+/-0.22 720.30 +/-71.57 0.84 +/- 0.18 5.97 +/-0.51 1,436.95 +/-86.46 2.93+/-0.60 230.10 +/- 63.92 1.00 +/- 0.15 0.72 +/- 0.06 0.19+/-0.03 0.93 +/-0.04 0.14+/-0.02 157

Davis-Bcssc Nuclear powe. Station 2001 Annual Radiological Environmental Operating Report Table A-5. In-house "duplicate" samples.

Concentration in pCi/L Lab Sample Codes Date Analysis SS-10953, 10954 Dec, 2001 K-40 s

S5-10953, 10954 Dec, 2001 Pb-212 SS-10953, 10954 Dec, 2001 Pb-214 SS-10953, 10954 Dec, 2001 Ra-226 SS-10953, 10954 Dec, 2001 TI-208 MI-11033, 11034 Dec, 2001 K-40 1,33 MI-11033, 11034 Dec, 2001 Sr-90 AP-11888, 11889 Dec, 2001 Be-7 Duplicate analyses are performed on every twentieth analyses with activities that measure below the LLD.

First Result 9.91 +/- 0.83

).94 +/- 0.05 083 +/- 0.08 1.76 +/- 0.37 1.34 +/- 0.05 3.80 128.70 1.31 +/-t 0.41 3.06 +/- 0.02 Second Result 8.36 +/-0.80 0.91 +/- 0.06 0.82 +/- 0.07 1.67 +/- 0.37 0.31 +/- 0.05 1,435.80 +/-117.30 1.38 +/-0.37 0.06 +/- 0.02 Averaged Result 9.13 +/-0.57 0.92 +/- 0.04 0.83 0.05 1.72 +/- 0.26 0.32 +/- 0.04 1,387.80 +/- 87.07 1.35 0.28 0.06 +/- 0.01 sample received in-house. Results are not listed for those

' Results are reported in units of pCi/L, except for elemental potassium (K) in milk (mg/L), air filters (pCi/Filter),

food products and vegetation (pCi/g), soil and sediments (pCi/kg).

158

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environrtental Operating Report Table A-6, Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)-.

Concentrationb Lab Sample Date MAPFP Resulte Control Code Type Collected Analysis Laboratory result' Is, N=1 Limits S'tSO-923 SOIL Jan, 2001 Am-241 0.00 - 2.60 Included as false positive. Result of analyses; < 0.8 Bq/L.

STSO-923 SOIL Jan, 2001 Co-57 100.20:t 3.50 103.00 +/- 10.30 72.10 - 133.90 STSO-923 SOIL Jan, 2001 Co-60 1,285.10 +/- 5.30 1,270.00 +/- 127.00 889.00 - 1,651.00 STSO-923 SOIL Jan, 2001 Cs-134 81.10 +/- 1.80 91.10 +/- 9.11 63.77 - 118.43 STSO-923 SOIL Jan, 2001 Cs-137 1,210.60 +/-6.60 1,240.00 +/- 124.00 868.00- 1,612.00 STSO-923 SOIL Jan, 2001 K-40 732.60 +/- 21.20 652.00 +/- 65.20 456.40 - 847.60 STSO-923 SOIL Jan,2001 Mn-54 212.60+/-6.70 203.00+/-20.30 142.10 -263.90 STSO-923 SOIL Jan, 2001 Pu-238 110.70+/- 7.20 115.00+/- 11.50 80.50 - 14950 STSO-923 SOIL Jan, 2001 Pu-239/40 79.60+/-5.90 83.40- 8.34 58.38 - 108.42 STSO-923 SOIL Jan, 2001 Sr-90 159.80 +/- 9.50 209.00 +/- 20.90 146.30 - 271.70 STSO-923 SOIL Jan, 2001 U-233/4 45.00 +/- 3.90 60.00 + 6.00 42.00 - 78.00 STSO-923 SOIL Jan, 2001 U-238 165.60+ 7.40 191.00+/- 19.10 133.70- 248.30 STSO-923 SOIL Jan, 2001 Zn-65 42850 +/- 10.90 382.00 +/- 38.20 267.40 - 496.60

' Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Departnent of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.

b All results are in Bq/kg or Bq/L as requested by the Departmient of Energy.

' MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 deternination) and control limits as defined by the MAPEP.

159

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table A-7.

Environnental Measurements Laboratory Quality Assessment Program (EML)'.

Lab Code STS0-904 STSO-904 STS0-904 Possible STSO-904 STSO-904 STSO-904 STSO-904 STSO-904 STSO-904 STSO-904 STW-905 STW-905 STW-905 ST W-905 STW-905 STW-905 STW-905 STW-905 STW-905 STW-906 STW-906 STAP-907 STAP-907 STAP-907 STAP-907 STAP-907 STAP-907 STAP-907 Sample

_ye SOIL SOIL SOIL effect of shield SOIL SOIL SOIL SOIL SOIL SOIL SOIL WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER Concentration b Date Control Collected Mar, 2001 Mar, 2001 Mar, 2001 background.

Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Analysis Ac-228 Am-241 Bi-212 Bi-214 Cs-137 K-40 Pb-212 Pb-214 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 H-3 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Gr. Alpha Gr. Beta Am-241 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 Laboratoryresult EMLResult' Limitsd 42.700 14.800 42.000 32.600 1,740.000 468.000 41.500 34.300 25.600 69.000 1.670 98.200 73.000 79.300 1.580 1.640 4.400 1.040 1.040 1,900.000 1,297.000 0.486 19.440 2.830 8.760 6.520 0.215 0.136 0.80 - 1.50 0.63 - 2.64 0.45 - 1.23 0.78 - 1.50 0.80- 1.29 0.80 - 1.37 0.74 - 1.36 0.76 - 1.53 0.71 - 1.33 0.61 - 3.91 0.76 - 1.48 0.80 - 1.20 0.80 - 1.20 0.74 - 2.29 0.74-1.22 0.75 - 1.26 0.64-1.50 0.80 - 1.40 0.80 - 1.29 0.58 - 1.26 0.56 - 1.50 0.69 - 2.40 0.79-1.30 0.74 - 1.21 0.78 - 1.35 0.80- 1.36 0.66-1.35 0.69 - 1.29 45.600+/- 4.000 14.400 +/- 0.500 53.200+/- 3.100 42.100+/-L7.700 1,772.600:+/-79.800 583.800 +/- 52.600 46.600 + 8.500 45.300 8.600 26.000 0.800 55.600+/-t2.200 2.150 0.140 97.000 + 0.800 70.100 +/- 4.000 76.500 5.500 1.690 0.070 1.690 +/- 0.070 3.850 + 0.130 0.900 +/-0.050 0.880 +/-0.050 1,724.600 +/- 141.700 1,246.400 +/- 31.100 0.470 +/- 0.040 20.110 +/-0.160 2.710 0.150 9.860 +/- 0.230 7.250+/- 0.220 0.230 +/-0.030 0.120 +/- 0.020 160

I)avis.Bcssc Nuclearl Power Stationi 2001 Aniua: Radiological Envirorunental Operating Rcport Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)'

Concentration b Lab Sample Date Control Code Type Collected Analysis Laboratory result EML Result' Limitsd AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER SOIL SOIL SOIL SOIL SOIL SOIL Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sr-90 U-233/4 U-238 Gr. Alpha Gr. Beta Am-241 Cm-244 Co-60 Cs-137 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 H-3 Ni-63 Pu-238 Pu-239/40 Sr-90 IJranium Gr. Alpha Gr. Beta Ac-228 Am-241 Bi-212 Bi-214 Cs-137 Sep, 2001 K-40 7.410+/-;0.150 0.050 +/- 0.010 0.050+/- 0.010 2.660 +/- 0.020 2.300 +/- 0.020 6.100 +/-0.200 3.500 +/- 0.500 28.500 +/- 2.100 795.500 +/- 76400 592.600 + 42.500 8.500 +/- 0.600 1,239.600 +/- 130.000 0.700 +/- 0.100 206.700 +/-4.700 46.600 +/- 0.800 254.100 +/- 3.600 50.900 +/-3.000 1.100 +/- 0.100 1.600 +/- 0.100 4.100 +/- 0.300 2.200 0.200 1,220.000 +/- 32.000 8,461.000 +/- 206.000 68.100 t 1.400 5.200 +/- 1.300 65.100 +/- 1.600 47.300 +/- 4.700 659.200 +/- 10.800 737.700 +/-16.600 161 STAP-907 STAP-907 STAP-907 STAP-908 STAP-908 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STW-925 STW-925 STW-925 STW-925 ST W-925 STW-925 STW-925 STW-925 STW-925 STW-926 STW-926 STSO-927 STSO-927 STSO-927 STSO-927 STSO-927 STSO-927 7.100 0.046 0.046 3.970 2.580 6.170 3.690 30.400 842.000 603.000 9.580 1,330.000 0.760 209.000 45.133 207.000 45.250 1.088 1.628 3.729 2.372 1,150.000 7,970.000 59.570 4.432 62.067 36.900 612.330 623.330 0.55 - 2.05 0.80 - 1.92 0.80- 1.59 0.57 - 1.47 0.76-1.52 0.72-2.34 0.61 - 1.61 0.75 - 1.51 0.80- 1.37 0.78-1.43 0.67 - 1.49 0.52 - 1.23 0.76-1.48 0.80 - 1.20 0.80 - 1.24 0.74 - 2.29 0.70 - 1.30 0.74 - 1.22 0.75 - 1.26 0.64-1.50 0.73 - 1.37 0.58 - 1.26 0.56 - 1.50 0.80 - 1.50 0.63 - 2.64 0.45-1.23 0.78 - 1.50 0.80- 1.29 0.80 - 1.37

Davis-Besse Nuclear Power Statio 2001 Aimual Rldiological Environnmental Operating Report Table A-7.

Environmental Measurements Laboratory Quality Assessment Program (EMLr.

Concentration "

Lab Sample Date Control Code Type Collected Analvsis Laboratory result EML Result' Limits4 STSO-927 SOIL Sep, 2001 Pb-212 64.700 3.800 58.330 0.74 - 1.36 STSO-927 SOIL Sep, 2001 Pb-214 53.700 +/- 7.700 39.670 0.76 - 1.53 STSO-927 SOIL Sep, 2001 Pu-239/40 9.300+/-2.900 8.948 0.71 - 1.33 STSO-927 SOIL Sep, 2001 Sr-90 27.400 +/- 6.300 30.596 0.61 - 3.91 STSO-927 SOIL Sep, 201 Uranium 155.600+/-7.800 194.230 0.62 - 1.35 STVE-928 VEGETATION Sep, 2001 Arn-241 7.000+/-0.300 6.915 0.72 - 2.34 STVE-928 VEGETATION Sep, 2001 Cn-244 4.300+/-0.800 4.308 0.61 - 1.61 STVE-928 VEGETATION Sep, 2001 Co-60 40,200 +/- 0.900 35.300 0.75 - 1.51 STVE-928 VEGETATION Sep, 2001 Cs-137 1,184.000+/-2.800 1,030.000 0.80 - 1.37 STVE-928 VEGETATION Sep, 2001 K-40 1,023.000 +/-44.100 898.670 0.78 - 1.43 STVE-928 VEGETATION Sep, 2001 Pu-239/40 8.900+/-1.400 11.022 0.67-1.49 STVE-928 VEGETATION Sep, 2001 Sr-90 1,364.000 +/- 18.400 1,612.800 0.52 - 1.23 STAP-929 AIR FILTER Sep, 2001 Am-241 0.090+30.000 0.088 0.69 - 2.40 STAP-929 AIR FILTER Sep, 2001 Co-60 16.900 0.300 17.500 0.79 - 1.30 STAP-929 AIR FILTER Sep, 2001 Cs-134 11.800 0.200 12.950 0.74-1.21 STAP-929 AIR FILTER Sep, 2001 Cs-137 18.3W +/-0.300 17.100 0.78 - 1.35 STAP-929 AIR FILTER Sep, 2001 Mn-54 85.400+/-1.300 81.150 0.80- 1.36 STAP-929 AIR FILTER Sep, 2001 Pu-238 0.051 :0.010 0.071 0.66 - 1.35 STAP-929 AIR FILTER Sep, 2001 Pu-239/40 0.220 + 0.020 0.229 0.69 - 1.29 STAP-929 AIR FILTER Sep, 2001 Sr-90 3.110+/-0.060 3.481 0.55 - 2.05 STAP-929 AIR FILTER Sep, 2001 Uranium 0.240 +/- 0.050 0.222 0.80 - 2.54 STAP-930 AIR FILTER Sep, 2001 Gr. Alpha 6.300+/-0.100 5.362 0.57-1.47 STAP-930 AIR FILTER Sep, 2001 Gr. Beta 13.800+/-0.100 12.770 0.76 - 1.52 a The Environmental Measurements Laboratory provides the following nuclear species: Air Filters, Soil, Vegetation and Water.

b Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg.

' The EML result listed is the mean of replicate determinations for each nuclide+/-the standard error of the mean.

'Control limits are reported by EML as the ratio of Reported Value / EML value.

162

IDavis-Besce Nuclear Power Siation 2001 Annual Radiologic:l Environmental Operating Report APPENDIX B DATA REPORTING CONVENTIONS 163

Davis-13essc Nuclear Power Station 2001 Annual Radiological Environmental Operatinig 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. Sinele 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 backgrouhd sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xi w sI and 2 w S2 Reported result:

xi:k s; where x= (1/2) (xl +x2) and s= (1/2) 3.2. Individual results:

<LI, <L2 Reported result: <L, where L = lower of LI and L2 3.3, ndividualresults:

x t s, <L Reported result:

x s if x> L;<L otherwise.

4.0.. Computation of Averaes 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 tumbers xi, X2... Xn are defined as follows:

X=

Y-xs=

n s

n-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 figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11A43 is rounded off to 11.44.

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

164

Davis-Tesse Nucilear Power Statioji 2001 Aial Radiological Environmental Operating Report APPENDD C Emuet Concentration limit of Radioactivity in. Air anrd Water Above Natura Backgrmund in Unrestricted Areas 165

Davis-Besse Nuclear Power Station 2001 Aual Radiological Environrmental Operating Report Table C-1 Emuent Concentration umit or Radioactivity In Air and Water Abbve Natursl Background in Unrestricted Area?

Air Water IE-03 pCi/* 3 I pCitmn 2.8iE-01 pClm' Stro*tium-89 Stro*tium-90 Cesium-137 Barium-140 lodinl31 Poaium-40' Gross Alpha Gross Beta Tritium Taken from Code of Federal Regulation Title 10, Part 20, Table H and appropriate footnotes. Concentrations may be averagd over a period not greater than one yar.

From 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-child padtway.

A natural radioucltide.

166 Gtss Alpha Gross Beta lodint-131' 8.000 pcin 500 pcin

,000 pcin 8.000 pCin 1,000 pCi/i 4.000 pai 2 pCinI ico pcin IrlO' pci/

1avis-Bcsse Nutclear ower Station 2001 Aial Radiological Erivironriental Operating Re)ort APPENDIX t REMP SAMPUNG

SUMMARY

167

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name ot Facility Location of Facitly Davis-Besse Nuclear Power Station Ottawa. Ohio Docket No.

Reportng Period 50-346 January-December, 2001 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD Mean (Ff Mean (F Mean (Ff Routine (Units)

Analse Range Locatond Range' Range' ResultL Airbome GB 519 0.005 0.025 (3111311)

T-9, Oak Harbor 0.027 (5252) 0.025 (208208) 0 Partculates (0.009-0.087) 0.8 mi. SW (0.012-0.058)

(0.006-0.04)

(pCi/m3)

Sr-89 0.0016

< LLD

< LLD 0

Sr-9o 0.0017

< LLD

< LLD a

GS 40 Be-7 0.015 0.069 (24124)

T-4, Site Boundary 0.076 (414) 0.069 (18/1) 0 (0.042-0.093) 0.8 mi. S (0.053-0.093)

(0.0474.107)

K-40 0.039

< LLD

< LLD 0

Nb-95 0.0014

< LLD

< LLD 0

Zr-95 0.0017

< LLD

< LLD 0

Ru-103 0.0014

< LLD

< LLD 0

Ru-106 0.0102

< LLD

< LLD 0

Cs-134 0.0140

< LLD

< LLD 0

Cs-137 0.0011

< LLD

< LLD 0

Ce-141 0.0023

< LLD

< LLD 0

Ce-144 0.0075

< LLD

< LLD 0

Airbome Iodine 1-131 519 0.07

< LLD

< LLD 0

(pCi/m3)

TLD (Quarterly) Gamma 340 1.0 14.4 (294/294)

T-45. Site Boundary 20.2 (4/4) 14.8 (46/46) 0 (mR/91 days)

(6.4-24.1) 0.5 mi. WNW (17.4-23.2)

(9.6-19.7)

TLD (Quarterly)

Gamma 4

1.0 6.7 (4/4)

None 0

(mR/91 days)

(5.9-7.1)

(Shield)

TLD (Annual)

Gamma 85 1.0 55.8 (76/76)

T-67, Site boundary 79.6 (111) 58.0 (919) 0 (mR/365 days)

(31.1-79.6) 0.3 mi. NNW (38.6-72.6)

TLD (Annual)

Gamma 1

1.0 21.9 (1/1)

None 0

(mR/365 days)

(Shield) 168

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davs-esse Nuclear Power Stafton Ottawa Ohio Docket No.

50-346 Reporting Penod January-December. 2001 (County. State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Loatons Non-Type Number of LLD' Mean (F)

Mean (F)'

Mean (Ff Routine (Units)

Analysee Range' Locationd Range0 Range' Resulte Milk (pCUL) 1-131 12 0.4 none

< LLD 0

Sr-89 12 1.7 none

< LLD 0

Sr4-0 12 1.0 none T-24, Sandusky 1.2 (/12) 1.2 (5112) 0 21.0 mi. SE (1.1-1.4)

(1.1-14A)

GS 12 K-40 100 none T-24, Sandusky 1378 (1212) 1378 (12112) 0 21.0 ml. SE (111)

(1.1-1A)

Cs-1 34 6.5 Cs-137 6.0 none

<LLD 0

Ba-La-140 9.6 none

< LLD 0

(gL)

Ca 12 0.50 none T-24, Sandusky 0.87 (1212) 0.87 (1212) 0 21.0 mi. SE (0.79-1.00)

(0.79-1.00)

(g/L)

K (stable) 12 0.10 none T-24, Sandusky 1.59 (12112) 1.59 (12/12) 0 21.0 ml. SE (1.45-1.91)

(1.45-1.91)

(pCUg)

Sr-90/Ca 12 0.00 none T-24, Sandusky 1.37 (6/12) 1.37 (6/12) 0 21.0 ml. SE (1.18-1.77)

(1.18-1.77)

(pCIg)

Cs-137/K 12 0.00 none

< < LLD 0

Ground Water GB (TR) 5 3.7

< LLD

< < LLD (pCI/IL)

H4-5 330 416 (1/1)

T-225, residence

< LLD 0

1.55 mi. NW Sr49 5

1.1

< LLD

< LLD 0

Sr-90 5

0.7

< LLD

.L

<LD 0

GS Mn-54 15

< LLD

< c LLD 0

Fe-59 30

< LLD

< LLD 0

Co-43 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

169

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Porr Station Ottawa. Ohio Docket No.

Reporting Perod 50-346 January-December, 2001

( County, State )

Indicator Location with Highest Contrc Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)

Mean (F)'

Mean (Ff Routine (Units)

Analyse Range' Locationd Range' Range' Results' Edible Meat GS 4

(pCUg wet)

K-40 0.10 2.94 (212)

T-34, Offsite 3.44 (22) 3.44 (2/2)

(2.73-3.15)

Roving location (2.844.03)

(2.84-4.03)

Nb-95 0.032

< LLD

< LLD 0

Zr-S 0.033

< LLD

.L

<LD 0

Ru-103 0.032

< LLD

< LLD 0

Ru-106 0.12

< LLD

< LLD 0

Cs-137 0.013

< LLD

< LLD 0

Ce-141 0.072

< LLD

< LLD 0

Ce-144 0.093

< LLD

< LLD 0

Fruits and Sr-89 3

0.002

< LLD

< LLD 0

Vegetables Sr-90 3

0.001

< LLD

< LLD 0

(pcig wet) 1-131 3

0.017

< LLD

< LLD 0

GS 3

K-40 0.50 1.17 (2/2)

T-209, Orchard 1.34 (1) 1.34 (1/1) 0 (0.67-1.66) 18.9 mi. W Nb-95 0.011

< LLD

< LLD 0

Zr-95 0.030

< LLD

< LLD 0

Cs-137 0.010

< LLD

< LLD 0

Ce-141 0.021

< LLD

< LLD 0

Ce-144 0.077

< LLD

< LLD 0

Broad Leaf Sr-89 9

0.007

< LLD

< LLD 0

Vegetation Sr-90 9

0.004 0.008 (2/6)

T-19, Farm 0.009 (1/3)

< LLD 0

(pCilg wet)

(0.0064.009) 0.68 mi. W 1-131 9

0.025

< LLD

< LLD 0

GS 9

K-40 0.50 1.90 (6/6)

T-19, Farm 1.95 (3/3) 1.79 (3/3) 0 (1.48-2.20) 0.68 mi. W (1.48-2.20)

(1.64-1.89)

Nb-95 0.019

< LLD

< LLD 0

Zr-S 0.022

< LLD

< LLD 0

Cs-137 0.015

< LLD

< LLD 0

Ce-141 0.029

< LLD

< LLD 0

Ce-144 0,13

< LLD

< LLD 0

170

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmeitai Operating Report Table 4.5 Radiological Environmental Monitorng Program Summary Name of Facility Localion o Fjaciliy Davis-Besse Nuclear Power Station Ottawa. Ohio

( County, State )

171 Docket No.

Reporting Period 50-346 January-December. 2001 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)'

Mean (F)

Mean (F)

RouUne (Units)

Analvset Range Loain

Range, Range0 Results Animal /

GS 5

Wildlife Feed Be-7 0.33 0.61 (1/3)

T-31, Onsite 0.81 (1/1) 0.70 (1/2) 0 (pCilg wet)

Roving location K-40 0.10 3.15 (3/3)

T-34, Offsite 8.05 (11) 6.09 (22) 0 (1.11-7.01)

Roving location (4.1 34.0$)

Nb-95 0.033

'LLD

< LLD 0

Zr-9S 0.069 cLLD

< LLD 0

Ru-103 0.028

< LLD

<LLD 0

Ru-106 0.20

<LLD c LLD 0

Cs-137 0.019

< LLD

< LLD 0

Ce-141 0.073

< LLD

< LLD 0

Ce-144 0.19 LLD

< LLD 0

Soil GS 20 (pCiVg dry)

Be-7 0.50 1.02 (5/12)

T-4, Site Boundary 1.98 (1/2) 0.92 (2/8) 0 (0.58-1.98) 0.6 mi. S (0.82-1.02)

K-40 0.10 13.35 (12112)

T-9, Oak Harbor 24.76 (2/2) 21.28 (818) 0 (4.68-23.10) 6.8 mi. SW (24.22-25.30)

(18.77-25.30)

Nb-95 0.083

< LLD c LLD 0

Zr-95 0.11

< LLD

< LLD 0

Ru-103 0.064

< LLD

< LLD 0

Ru-106 0.38

< LLD

< LLD 0

Cs-137 0.050 0.13 (7/12)

T-12, Water Treatment 0.23 (212) 0.18 (718)

(0.052-0.25)

Plant, 23.5 ml. WNW (0.20-0.26)

(0.0864.26) 0 Ce-141 0.12

'LLD

< LLD 0

Ce-144 0.19

< LLD

< LLD 0

Davis-Besse Nuclear Power Stationi 2001 Anual Radiological Environmental Operating Repoit Table 4.5 Radiologicai Environmental Monitoing Program Summary Name of Facity Location of Facility Davls-Besse Nuclear Power Staion Ottawa. Ohio Docet No.

50-346 Reporting Period January-December, 2001 (County, State)

Indicator Location with Highest Control Number Sampte Type and Locations Annual Mean Locations Non-Type Number of LLD Mean (Ff Mean (F)

Mean (FJ Routne (Units)

Analvsee Ranqe' Locations Range Range Resutt Treated GB (TR) 48 1.0 2.5 (24124)

T-11, Port Clinton 2.7 (12/12) 2.3 (24124) 0 Surface Water (1.7-3.2)

WTP, 9.5 mi. SE (2.13.5)

(1.6-3.5)

(pCLiL)

H-3 16 330 593 (1/8)

T-22, Caroll Twp.

593 (114) c LLD 0

WTP, 3.0 ml. NW Sr-89 16 1.7

< LLD

<LLD 0

Sr-go 16 1.0

< 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

< cLiD 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 3.1 (50/50)

T-137, Lake Erie 4.4 (717) 3.1 (45145) 0 Surface Water (2.1-5.4) 7.0 mi. WNW (2.1-12.7)

(1.9-12.7)

(pCVL)

H-3 95 330 713 (250)

T3. Site Boundary 986 (1/12)

'LLD 0

330 (439-986) 1.4 nm. ESE Sr-89 20 1.6

< LLD LLD 0

Sr-90 20 0.8 1.9 (1/12)

T-3. Site Boundary 1.9 (1/4)

LLD 0

1.4 mi. ESE GS 95 Mn-54 15

<LLD

< LLD 0

Fe-59 30

< LLD LLD 0

Co43 15

< LLD LLD 0

Co40 IS

< 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

172

Davis-Besse Nuclear Power Station 2001 Aniual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Progam Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa. Ohio Docket No.

Reporting Period 50-346 January-December, 2001

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (Ft Mean (Ff Mean (Ff Routine (Units)

Analyses Range' Locationd Range' Range' Results Fish GB 6

0.1 2.97 (3/3)

T-33, Lake Erie 2.97 (3/3) 2.82 (33) 0 (pci/g wet)

(2.70-3.12) 1.5 mi. NE (2.70-3.12)

(1.86-3,53)

GS 6

K-40 0.10 2.48 (3/3)

T-35, Lake Erie 2.96 (313) 2.95 (3/3) 0 (1.95-3.11)

> l0mi.

(2.76-3.10)

(2.76-3.10)

Mn-54 0.013

< LLD

< LLD 0

Fe-59 0.032

<LLD

< LLD 0

CO-S8 0.013

< LLD

< LLD 0

Co-60 0.014

<LLD

< LLD 0

Zn-65 0.026

< LLD

< LLD 0

Cs-134 0.014 c LLD

< LLD 0

Cs-137 0.020

< LLD

< LLD 0

Shoreline GS a

Sediments K-40 0.10 10.80 (616)

T-278, Crane Creek S.P.

11.87 (2/2) 11.87 (2t2) 0 (pCVg dry)

(8.06-12.82) 5.3 ml. WNW (10.61-13.13)

(10.61-13.13)

Mn-54 0.026

<LLD

< < LLD 0

Co46 0.028

< LLD

< LLD 0

Co-SO 0.025

< LLD

< LLD 0

Cs-134 0.029

< LLD

< LLD 0

Cs-137 0.028

< LLD

< LLD 0

• GB = gross beta, GS = gamma scan.

b LLD nominal lower limit of detection based on a 4.66 sigma counfing 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).

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

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

173