ML20206D255

Annual Radiological Environ Operating Rept for Davis-Besse Nuclear Power Station for 980101-981231

ML20206D255
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Site:	Davis Besse
Issue date:	12/31/1998
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT t

for Davis-Besse Nuclear Power Station January 1,1998 through December 31,1998 Prepared by:

Radiation Protection Section Davis-Besse Nuclear Power Station April 1999 1

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report l

TABLE OF CONTENTS Title Page List of Tables iv List of Figures vi Executive Summary viii INTRODUCTION Fundamentals 1 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 11 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 i

Operational Surveillance Program Objectives 27 Quality Assurance 27 4 Program Description 28 Sample Analysis 32 Sample History Comparison 35 i

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Title Page j i

RADIOLOGICAL ENVTRONMENTAL MONITORING PROGRAM (continued) 1998 Program Deviations 37 Atmospheric Monitoring 39 Terrestrial Monitoring 45

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Aquatic Monitoring 57 I Direct Radiation Monitoring 68 Conclusion 78 References 79 RADIOACTIVE EFFLUENT RELEASE REPORT l

Protection Standards 82 Sources of Radioactivity Released 82 Processing and Monitoring 83 Exposure Pathways 84 Dose Assessment 85 Results 86 Regulatory Limits 87 l

Effluent Concentration Limits 88 Average Energy 88 Measurements of Total Activity 88 Batch Releases 89 Sources ofInput 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 LAND USE CENSUS Program Design 109 Methodology 109 Results 110  ;

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Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report Title Page NON RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring 115 Land and Wetlands Management 140 Water Treatment 141 i Chemical Waste Management 146 Waste Minimization and Recycling 149 APPENDICES Appendix A: Interlaboratory Comparison Program Results 151 l Appendix B: Data Reporting Conventions 174 Appendix C: Emuent Concentration Limit of Radioactivity in Air and Water 177 Above Background in Unrestricted Areas Appendix D: REMP Sampling Summary 179 I

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[ Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report List of Tables Table Page Titic 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 41 Milk Monitoring Location 6 46 Groundwater Monitoring Locations 7 48 Broad Leaf Vegetation and Fruit Locations 8 49 Animal / Wildlife Feed Locations 9 50 Wild and Domestic Meat Locations 10 51 Soil Locations 11 53 Treated Surface Water Locations 12 58 Untreated Surface Water Locations 13 61 Shoreline Sedirnent Locations 14 62 Fish Locations 15 64 Thermoluminescent Dosimeter Locations 16 70 Gaseous Effluents - Summation of All Releases 17 92 Gaseous Effluents - Ground Level Releases - Batch Mode 18 93 Gaseous Effluents - Ground Level Releases - Continuous Mode 18 94 Gaseous Effluents - Mixed Mode Releases - Batch Mode 19 96 Gaseous Effluents - Mixed Mode Releases - Continuous Mode 19 97 Liquid Effluents - Summation of All Releases 20 99 Liquid Effluents - Nuclides Released - Batch Releases 21 100 Liquid Effluents - Nuclides Released - Continuous Releases 21 102 Solid Waste and Irradiated Fuel Shipments 22 104 Doses Due to Gaseous Releases for January through December 1998 23 106 Doses Due to Liquid Releases for January through December 1998 24 107 Annual Dose to The Most Exposed Member of The Public 1998 25 108 j Closest Exposure Pathways Present in 1998 26 112 l Pathway Locations and Corresponding Atmospheric I

Dispersion (X/Q) and Deposition (D/Q) Parameters 27 114 iv s

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Davis Besse Nucl:ar Power Station 1998 Annual Radiological Environmental Operating Report Table Page Title Number Number

- Summary of Meteorological Data Recovery for 1998 28 120 Summary of Meteorological Data Measured for 1998 29 121 Joint Frequency Distribution by Stability Class 30 135 i

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k Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report List of Figures Figure Page Description Number Number The Atom i 1 Principal Decay Scheme of the Uranium Series 2 3 Range and Shielding of Radiation 3 4 Sources of Exposure to the Public 4- 8 Fission Diagram 5 12 Fuel Rod, Fuel Assemby, Reactor Vessel 6 13 Schematics of DBNPS 7 15 Dry Fuel Storage Module Arrangement 8 21  !

Map of Area Surrounding Davis-Besse 9 22 Airborne Particulate: Gross Beta 10 40 Airborne Sampling Locations on Davis-Desse Site 11 42 Airborne Sampling Locations within a Five Mile Radius 12 43 Airborne Sampling Locations within a Twenty-Five Mile Radius 13 44 Groundwater Samples: Gross Beta 14 47  !

Soil Samples: Cesium-137 15 52 j i

Terrestrial Sampling Locations on Davis-Besse Site 16 54 Terrestrial Sampling Locations within a Five Mile Radius 17 55 t

Terrestrial Sampling Locations within a Twenty-Five Mile Radius 18 56 Treated Surface Water Samples: Gross Beta 19 58 Untreated Surface Water Samples: Gross Beta 20 60 Fish Samples: Gross Beta 21 63 Aquatic Sampling Locations on Davis-Besse Site 22 65 Aquatic Sampling Locations within a Five Mile Radius 23 66  ;

1 Aquatic Sampling Locations within a Twenty-Five Mile Radius 24 67 TLD Dose Comparison 1973 - 1998 25 69 Direct Radiation Sampling Locations on Davis-Besse Site 27 75 Direct Radiation Sampling Locations within a Five Mile Radius 28 76 Direct Radiation Sampling Locations within a Twenty-Five Mile Radius 29 77 l Exposure Pathways 30 85 l

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report 1

Figure Page Description Number Number Land Use Census Map 31 111 Wind Rose Annual Average 100M 32 123 Wind Rose Annual Average 75M 33 124  !

Wind Rose Annual Average 10M 34 125 Wind Rose Monthly Average 100M 35 126 Wind Rose Monthly Average 75M 36 129 Wind Rose Monthly Average IOM 37 132 Water Treatment Plant Schematic 38 143 vii

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report i

Executive Summary The Annual Radiological Environmental Operating Report (AREOR) is a detailed report on the Environmental Monitoring Programs conducted at the Davis-Besse Nuclear Power Station from January 1 through December 31,1998. This report meets all of the requirements in Regulatory Guide 4.8, Davis-Besse Technical Specifications 6.9.1.10, and Davis-Besse Offsite Dose Calcu-lation Manual (ODCM) Section 7.1. Reports included are the Radiological Environmental Monitoring Program, Land Use Census, and the Non-Radiological Environmental Programs, which consist of Meteorological Monitoring, Land and Wetland Management, Water Treatment, Chemical Waste Management, and Waste Minimization and Recycling. This report also includes the Radiological Effluent Release Report for the reporting period of January 1 through December 31,1998.

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

j Radiation levels and radioactivity have been monitored within a 25-mile radius around Davis-Besse since 1972. The REMP was established at Davis-Besse about five years before the Station became operational. This pre-operational sampling and analysis program provided data on ra-diation and radioactivity normally present in the area as natural background. Davis-Besse has continued to monitor the environment by sampling air, groundwater, milk, edible meat, egg, fruit and vegetables, animal feed, soil, drinking water, surface water, fish, bottom and shoreline sedi-ment, and by measuring radiation directly. l Samples are collected from indicator and control locations. Indicator locations are within ap- l proximately 5 miles of the site and are expected to show naturally occurring radioactivity plus l any increases of radioactivity that might occur due to the operation of Davis-Besse. Control lo- )

cations are farther away from the Station and are expected to indicate the presence of only natu- i rally occurring radioactivity. The results obtained from the samples collected from indicator l l locations are compared with the results from those collected from control locations and with the I

concentrations present in the environment before Davis-Besse became operational. This allows ,

l for the assessment of any impact the operation of Davis-Besse might have had on the surround- l l ing environment. j Approximately 1700 radiological environmental samples were collected and analyzed in 1998. l An explanation for the sample program deviations for this reporting period is provided on page 37.

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

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report The sampling results are divided into four sections: atmospheric monitoring, terrestrial monitor-

. ing, aquatic monitoring and direct radiation monitoring:

. Air is continuously being filtered at 10 locations, onsite and up to 25 miles away, and the filters are collected to monitor the atmos-phere. The 1998 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. The results of the analyses of the terrestrial samples indi-cate concentrations of radioactivity similar to previous years and j indicates no build-up of radiation 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 1998 results of analysis )

for fish, untreated surface water, drinking water and shoreline I 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 13.8 mrem /91 days at indicator locations and 15.0 mrem /91 days at control locations. This is similar to re-sults of previous years.

The operation of Davis-Besse in 1998 caused no significant increase in the concentrations of ra .

dionuclides in the environment and no adverse effect on the quality of the environment. Radio-activity released in the Station's effluents was well below the applicable federal regulatory limits.

The estimated radiation dose to the general pubi!c due to the operation of Davis-Besse in 1998 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 patneys, an Annual Land Use Census is per-formed as part of the REMP. During the census, Davis-Besse personnel travel every public road within a five mile radius of the Station to locate the radiolegical 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, and is called the critical pathway. The critical pathway for 1998 is a garden in the West sector, 1640 meters from Davis-Besse.

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, Radiological Effluent Release Report I

3e Radiological Emuent Release Report (RERR) is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period, January 1,1998 through Decem-l ~ ber 31,1998. The doses due to radioactivity released during this period were estimated to be: l l

Liquid Emuents:

Maximum Individual Whole Body Dose 1.15E-01 mrem (0.1150 mrem) I Maximum Individual Significant Organ Dose 1.57E-01 mrem I (0.1570 mrem)

Total Integrated Population Dose 2.08E+00 person-rem (2.0800 person-rem)

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Average Dose to the Individual 9.52E-04 mrem l (0.000952 mrem) l Gaseous Emuentst$

Maximum Individual Whole Body Dose due to 8.30E-04 mrem I-131, H-3 and Particulates with half-lives (0.000830 mrem)  !

greater than 8 days Maximum Significant Organ dose due to I-131, 1.17E-03 mrem H-3 and Particulates with half-lives greater than (0.00117 mrem) 8 days Total Integrated Population dose due to I-131, 8.82E-03 person-rem H-3 and Particulates with half-lives greater than (0.00882 person-rem) 8 days Average dose to an Individual in the population 4.05E-06 mrem due to I-131, H-3 and Particulates with half-lives (0.00000405 mrem) greater than 8 days Maximum Individual Skin dose due to noble gases 2.32E-04 mrad (0.000232 mrad)

Maximum Individual Whole Body Dose due to 6.47E-05 mrad noble gases (0.0000647 mrad)

Total Integrated Population dose due to noble gases 1.25E-04 person-rem (0.000125 person-rem)

Average dose to individual in population due to 5.73E-08 mrem i noble gases (0.0000000573 mrem)

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rs Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report These doses represent an extremely small fraction of the limits' set by the NRC or the j 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 one change to the ODCM during this reporting period. 3 i

Non-Radiological Environmental Programs Meteorological Monitoring I J

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.

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Data recovery for the five instruments required to be operational by Davis-Besse Technical Re- )

quirement Manual was 98.6%.

Marsh Management' l l

Toledo Edison and the Cleveland Electric Illuminating Company co-own the Navarre Marsh - i which they lease to the U.S. Fish and Wildlife Service, who manage it as part of the Ottawa Na- )

tional Wildlife Refuge. Davis-Besse personnel are responsible for inspecting the marsh and re-

. porting on its status monthly.

Special projects conducted in 1998 with the cooperation of Ohio Department of Natural Re-sources included Canada goose banding and a Volunteer Eagle Watch Workshop. Davis-Besse hosted the fifth annual Federal Junior Duck Stamp Art Contest for the State of Ohio in coopera-tion with the Ottawa National Wildlife Refuge.

A pair ~of American Bald Eagles used the nest platform that was built in 1996 but failed to pro-duce any young.

- Water Treatment Davis-Besse uses Lake Eric as a source of water for its Water Treatment Plant. The water is

- treated onsite to provide domestic water and to produce high purity water for use in the Station's cooling systems.

I Since December 1,1998, domestic water needs at Davis-Besse have been met by the Carroll Townsh ip Water Treatment Plant.

~ Sewage is treated onsite at the Davis-Besse Waste Water Treatment Plant (WWTP). The sewage is processed and then pumped to a basin where further reduction in solid content takes ~ place.

Following a settling period, the water is discharged, along with other station waste water, back to

- Lake Erie.

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n Davis-Besse Nuclear Power Station 1998 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 of chemical wastes in order to protect human health and the environment.

In 1998, the Davis-Besse Nuclear Power Station maintained small quantity generator status, generating 1,870 pounds of hazardous waste. Davis-Besse personnel also continuously strive to identify alternate ways to reduce hazardous waste generation. There were 5,200 gallons of non-hazardous waste oil generated in 1998. Approximately 1,210 gallons of oil filters and solid oily debris were also generated. Additionally 315 gallons of other chemicals such as microfilm process chemicals and resins were generated in 1998. j 1

As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse reported hazardous products and chemicals to local fire departments and local and state planning commis- i sions. 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- i tion and recycling of paper. This program was expanded and reinforced during 1993 to include j 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 1 Appendix A contains results from the Interlaboratory Comparison Program required by Davis-Besse Technical Specifications. Samples with known concentrations of radioisotopes are pre- j pared by the Environmental Protection Agency (EPA), and then sent (with information on sam-ple type and date of collection only) to the laboratory contracted by the Davis-Besse Nuclear Power Station to analyze its REMP samples. The results are then checked by the EPA to ensure ,

consistency with the known values. The results from both the contracted laboratory and the EPA l

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

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data. Information on counting uncertainties and the calculations of averages and standard devia- I tions is 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 sam-pling results for 1998.

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Divis-Besse Nuclear Power Station 1998 Annual Radiologic:.1 Environmental Operating Report I 1

- Appendh: D provides a REMP sampling summary from 1998. The appendix provides a listing of the following for each sample type:

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e the number and types of analyses performed, 1 e the lower limit of detection for each analysis, e the mean and range of results for control and indicator locations, e the mean, range, and location description for the location with the highest annual mean,

! e the number of non-routine results.

For detailed studies, Appendix D provides more specific information than that listed in Chapter 2 of this report. The infonnation presented in Appendices A through D was provided by i Teledyne Isotopes Midwest Laboratories in their Final Progress Report to Toledo Edison (Febru-ary 1999).

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Introduction Coal, oil, natural gas and hydropower are used to run this nation's electric generating stations; however, each method has its drawbacks. Coal-fired power can affect the environment through mining, acid rain and air pollution. Oil and natural gas are in limited supply and are therefore costly, and hydropower is limited due to the environmental impact of damming our waterways and the ,

scarcity of suitable sites in our country.  !

Nuclear energy provides an alternate source of energy, which is readily available. The operation of nuclear power stations has a very small impact on the environment. In fact, the Davis-Besse Nuclear Power Station is surrounded by hundreds of acres of marshland, which make up part of the Ottawa National Wildlife Refuge, the only national refuge in Ohio. In order to more fully understand this unique source 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 ed which are neutral. These particles are called To ,.o.

protons, electrons, and neutrons, respec- e aa=>'

tively (Figure 1). The relatively large pro- t * """5 tons and neutrons are packed tightly to- .,,,,,

gether in a cluster at the center of the atom called the nucleus. Orbiting around this nu-cleus are one or more smaller electrons. In / ~

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an electrically neutral atom the negative charges of the electrons are balanced by the ,

8 positive charges of the protons. Due to their y dissimilar charges, the protons and e'ectrons have a strong attraction for erb other, which helps hold the atom togeth:r. Other Fige l: An som eonusts of two parts: a nucleus

. conwnmg posinvely charged protons and electncally attractive forces between the protons and on:,,ro,, and o or m. g.u eiy eh,r,ea neutrons keep the densely packed protons *caa"*** *c auclen Pens ud umm are nearly identical in sue and weight. while e,ch is j from repellm, g each other, preventing the abom m umes heavier em m eiectron.

l nucleus from breaking apart.

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environrnental 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.

However, the number of neutrons in the nucleus of an element may vary. Atoms with the same number 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 unstable or radioactive isotope of an element is called a radioisotope, radioactive atom, or ra-dionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The ex-cess energy is usually due to a surplus or deficit in the number of neutrons in the nucleus.

Radionuclides can be naturally occurring such as uranium-238, beryllium-7 and potassium-40, or man-made, such as iodine-131, cesium-137, and cobalt-60.

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

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

The three types of particulate radiation of concern to us are alpha particles, made up of 2 pro- l tons and 2 neutrons; beta particles, which are essentially free electrons (electrons not attached to an atom); and neutrons. The properties of these types of radiation will be described more fully in the kage and Shielding section.

Radioactive Decay Radioactive utams attempt to reach a stable, non-radioactive state through a process known as j radioactive ds cay. 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 which eventually result in a stable atom. The loss of energy and/or matter through l radioactive decay may transform the atom into a chemically different element. For example, j 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 l- its chemical identity. Therefore, when the uranium-238 atom loses the 2 protons and 2 neutrons, 4 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 1 lead-2%. 1 2

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! This example is part of a known radioactive decay series, called the uranium senes, which begins j

! with uranium-238 and ends with lead-206 (Figure 2).  :

i 8 'u 8 'u 4.5 x 10'v y 2.5 x 10'v 234Pa 1.2 min 234 eso Th Th 24 d 8.0 x 10' v I Beta Docay '

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"'Ra h 1600 vr 222 Rn 3.82 d

Po Pod *Po 3.05 min g 16 x 10 a y 138.4 d

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Bi y 19.7 min h g 5.01 d BI 214 21 20e po Pb Pb l 26.8 min 21 y stable Figure 2: Principle Decay Scheme of the Uranium Series.

Half-life Most radionuclides vary greatly in the frequency with which their atoms release radiation. Some radioactive materials, in which there are only infrequent emissions, tend to have a very long half- ,

lives. Those radioactive materials that are very active, emitting radiation more frequently, tend to have comparably short 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 j half its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years.

Interaction with Matter Ionization i

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

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Davis.Besse Nuclear Power Station 1998 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 which 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 other interactions with atoms. As a result, alpha particles can easily be stopped by a sheet of paper or a few centimeters of air (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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-r,, ;;~ - m , . , a u ss, n... . . ........

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Figure 3: As radiation travels. It collides and interacts with other atoms and loses energy. Alpha particles c.an be stopped by a sheet of paper. and beta particles by a thin sheet of aluminum. Gamma radiation is shielded by highly dense materials such as lead while hydrogenous materials (those containing hydrogen atoms). such as water and concrete. are used to stop neutrons.-

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

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. 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 concern since the neutron source at nuclear power stations is

. sealed within the containment building.

Because neutrons have no charge, they are able to pass very close to the nuclei of the material

- through which they are traveling. As a result, neutrons may be captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some of its energy. After a series of these deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal neu-tron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons.

Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron j shielding materials commonly used to slow neutrons down are water or polyethylene. The shield j 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 i There are several quantities and units of measurement used to describe radioactivity and its ef-fects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent.

Activity: Curie Activity is the number of atoms in a sample that disintegrate (decay) per unit of time. 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, the amount of material required to produce one curie varies. For example, one gram (1/28 th of an ounce) of radium-226 is the equivalent of one curie of activity, but it would take 9,170,000 grams (about 10 tons) of 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 picoeurie (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

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material (1 Rad = 100 erg /gm).

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

' If the biological effect of radiation was directly proportional to the energy deposited by radiation in an organism, the Rad would be a suitable measurement of the biological effect. However, biological 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 some types of radiation are more damaging per unit path of travel than 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 these radiation's. 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- l tion. The dose equivalent is measured in rem (radiation equivalent man). I An example of this conversion from absorbed dose to dose equivalent uses the quality factor for alpha radiation, which is 20. Thus, i Rad of alpha radiation is approximately equal to 20 rem.

Beta and gamma radiation each have a quality factor of 1, therefore one Rad of either beta or gamma radiation is approximately equal to one rem. Neutrons have a quality factor ranging from 2 to 10. One rem produces the same amount of biological damage, regardless of the source. In terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit, the millirem, is often used. One millirem (mrem) is equal to 1/1000 of a rem.

Deep Dose Equivalent (DDE)

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

Committed Effective Dose Equivalent (CEDE)

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

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Davia-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Total Effective Dose Equivalent (TEDE) 1 Total effective dose equivalent means the sum of the deep dose equivalent (for dose from sources external to the body) and the committed effective dose equivalent (for internal dose). As these 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 is not a new creation of the nuclear power industry; it is a natural occurrence on the earth. It is probably the most " natural" thing in nature.' Mankind has always lived with radiation and always will.- In fact, during every second of life, over 7,000 atoms undergo radioactive decay

" naturally" in the body of the average adult.' In addition, radioactive decay also occurs naturally in soil, water, air, and space. All these common sources of radiation contribute to the natural background radiation to which everyone is exposed.

The earth is constantly showered by a steady stream of high energy gamma rays and particulate radiation 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. So

. people living at higher altitudes or flying in an airplane are exposed to more cosmic radiation.

Radionuclides commonly found in the atmosphere as a result of cosmic ray interactions include beryllium-7, carbon-14, tritium (H-3), and sodium-22.

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

The major source of background radiation is radon, a colorless, odorless, radioactive gas that re-suits 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 would not be considered to pose a health hazard unless it is concentrated in a confined area, such as buildings, basements or underground mines. Radon-related health con-cerns stem from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it decays, this could cause damage to internal tissues when inhaled. As a result, exposure to the lungs is of concern, as the only recognized health effect associated with exposure to radon is an increased risk oflung cancer. This effect has been seen when the 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 l to radon.

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i 7

1 Divis-Besss Nuclear Power Station 1998 Annual Radiological Environmental Operating Report SOURCES OF EXPOSURE ,

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

Further information on radon, its measurement, and actions to reduce the radon concentration in '

buildings can be obtained by contacting the state radon program office at the following address: j l

Radiological Health Program l Ohio Department of Health  !

P.O. Box 118 i Columbus, Ohio 43266-0118 (614) 481-5800 (800) 523-4439 (in Ohio Only) I 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- l activity, people are also exposed to man-made radiation. The largest sources of exposure include j medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer l

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, j 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

Davis-Besse Nuclear Power Station 1998 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. l The effects of radiation on humans can be divided into two categories, somatic and genetic. So-matic effects are those which develop in the directly exposed individual, including a developing fetus. 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 or radium by " tipping" the paint brushes with their lips, and uranium miners, who inhaled large amounts of radioactive dust I 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. I 1

Genetic effects could occur as a result of ionizing radiation interacting with the genes in the hu- 4 man cells. Radiation (as well as common chemicals) can cause physical changes or mutations in the genes. Chromosome fibers can break and rearrange, causing interference with the normal cell j 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 i time, the broken ends from one break could join incorrectly with those from another. This could cause translocations, inversions, rings, and other types of structural rearrangements. When this 9

1

. Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report .

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1 l

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.

j r

Health Risks l 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. j 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 has, perhaps, 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. I I

However, 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 numer-ous cancer causing substances. These risks are larger and measurable compared to those pre-sumed to be associated with exposure to low level, low dose radiation. Most of these risks are

-with us throughout our lives, and can be added up over a lifetime to obtain a total effect. Table i shows a number of different factors that decrease the average life expectancy of individuals in the United States.

Table 1: Risk Factors: Estimated Decrease in Average Life Expectancy Overweight by 30% : 3.6 years Cigarette smoking: : 1 pack / day . 7.0 years 2 packs / day 10.0 years Heart diseases : 5.8 years Cancer  : 2.7 years L

City Living (not rural)  : 5.0 years L ~All operating commercial nuclear less than 12 minutes l' power plants totaled  :

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= Davis Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Benefits of Nuclear Power Nuclear power plays an important part in meeting today's electricity needs, and will continue to serve as an important source of electric energy well into the future. Today more than twenty percent of the electricity produced in the United States is from nuclear powered electrical gener-ating stations.

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

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

e. uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States, e nuclear power is the cleanest energy source for power stations that use steam to produce electricity. There are no " greenhouse" gases or acid gases produced when using nuclear fuel.

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

Nuclear Power Production Electricity is produced in a nuclear power station in the same way as in a fossil-fueled station with the exception of the source of heat. Heat changes water to steam that turns a turbine. In a fossil-fueled station, the fuel is burned in a furnace, which is also a boiler. Inside the boiler, wa-ter is turned into steam. In a nuclear station, the furnace is replaced by a reactor containing a core of nuclear fuel, primarily uranium. 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.

I1

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report .

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/Fission Fragment Figure 5: When a heavy atom, uh as uranium-235 is split or fissioned. heat. free neutrons, and fission fragments result. The free neutrons can then strike neighbonng atoms causing them to fission also. In the proper environment.

this process can continue indennitely in a chain reaction.

Nuclear Fuel The fissioning of ov ".ranium 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 mec.ns:

e using fuel that is free of impurities that might absorb the free neutrons, e 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, e slowing neutrons down by providing a " moderator" such as water to increase the probability of fission.

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

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1 l

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report After the uranium ore is separated from the earth and rock, it is concentrated by a milling proc-ess. After milling the ore to a granular form and dissolving out the uranium with acid, the ura-nium is converted to uranium hexafluoride (UF 6). UF6 is a chemical form of uranium that exists as a gas at temperatures slightly above room temperature. The UF 6 is then highly purified and shipped to an enrichment facility where gaseous diffusion converters increase the concen-tration of U-235. The enriched gaseous UF6 is then converted into powdered uranium dioxide (UO 2), a highly stable ceramic material. The UO2 Powder is put under high pressure to form fuel pellets, each about 5/8 inch long and 3/8 inch in diameter . Approximately five pounds of these pellets are placed into a 12 foot long metal tube made of zirconium alloy. The tubes constitute the fuel cladding. The fuel cladding is highly resistant to heat, radiation, and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods.

The Reactor Core Two hundred eight fuel rods comprise a single fuel assembly. The reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fuel rods, the fuel ,sembly 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 81/2 inch thick steel walls, f

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

13

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Fission Control The fission rate inside the reactor core is controlled by raising or lowering control rod assem-blies into the reactor core. Each assembly consist of " fingers" containing silver, indium, and cadmium metals that absorb free neutrons, thus disrupting the fission chain reaction. When con-trol 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 concentrated or diluted in the coolant to achieve the desired level of fission.

l Boron-10 readily absorbs free neutrons, forming boron-11, removing the absorbed neutrons from l the chain reaction. i 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.

l 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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l Station Systems L

l Containment Building and Fission Product Release Barriers l

l The containment building houses the reactor vessel, the pressurizer, two steam generators, the l reactor coolant pumps and reactor coolant system piping. The building is constructed of an inner 1 inch thick steel liner or containment vessel, and the shield building with steel reinforced con-crete walls 2 feet thick. The shield building protects the containment vessel from a variety of environmental factors and provides an area for a negative pressure boundary around the steel containment vessel. In the event that the integrity of the containment vessel is 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- I 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 free-standing containment vessel is the third in a series of barriers that prevent the release of fission products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel cladding itself. The second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and associated piping.

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

The steam generator uses the heat of the primary coolant inside the steam generator tubes to boil l the secondary side feedwater (secondary coolant). Fission heat from the reactor core is trans- I 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 j the secondary loop water (blue in Figure 7) without actually coming in contact with it. Primary l coolant water exits the steam generator at approximately 558 F to be circulated back into the re-actor where it is again heated to 606 F as it passes up through the fuel assemblies. Under ordi-nary conditions, water inside the primary system would boil long before it reached such temperatures. However, it is kept under a pressure of approximately 2,200 pounds-per-square-inch (psi) at all times. This prevents the water from boiling and is the reason the reactor at Davis-Besse is called a Pressurized Water Reactor. Secondary loop water enters the base of the steam generator at approximately 450 F and under 1,100 psi pressure. At this pressure, the water can easily boil into steam as it passes over the tubes containing the primary coolant water.

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

16 L

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Davis-Desse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report I 1

The Turbine - Generator l The turbine, main generator, and the condenser are all housed in what is commonly referred to as the Turbine Building. The purpose of the turbine is to convert the thermal energy of the steam produced in the steam generator (referred to as main steam, red in Figure 7) to rotational energy of the turbine generator shaft. The turbine at Davis-Besse is actually composed of one six-stage high pressure turbine and two seven-stage low pressure turbines aligned on a common shaft. A turbine stage refers to a set of blades. Steam enters at the center of each turbine and flows 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. l 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 j rotating magnetic field within the coils of the stator. Electrical current is generated in the stator 1 portion of the main generator. From this point, the electric current passes through a series of J transformers for transmission and use throughout northern Ohio. I The Condenser After the spent steam in the secondary loop (blue in Figure 7) passes through the high and low l 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 turbines passes over these tubes, it is cooled and condensed. The condensed water is then purified and reheated before being circulated back into the steam generator again in a closed loop system.

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

Similar to the primary to secondary interface, the secondary to tertiary interface is based on a closed loop design. The circulating water is able to cool the steam in the condenser, without ever actually coming in contact with it, by the process of convection. Even in the event of a primary to secondary leak, the water vapor exiting the Davis-Besse cooling tower would remain non-  ;

radioactive. Closed loops are an integral part of the design of any nuclear facility. This design feature greatly reduces the chance of environmental impact from station operation.

The Cooling Tower The cooling tower at Davis-Besse is easily the most noticeable feature of the plant. The tower stands 493 feet high and the diameter of the base is 411 feet. The two pipes circulating 480,000 gallons of water per minute to the tower are 9 feet in diameter. The purpose of the tower is to recycle water from the condenser by cooling it.

17

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report l

After passing through the condenser, the circulating water has warmed to approximately 100 F.

In order to cool the water back down to around 70 F, the circulating water enters the cooling tower about 40 feet above the ground. The water is sprayed evenly over a series of baffles called

. fillsheets which are suspended vertically in the base of the tower. A natural draft of air blowing up through these baffles cools the water through the process of evaporation. The evaporated water exits the top of the cooling tower in the form of 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 dis-charged back to Lake Erie at essentially the same temperature it was withdrawn earlier. The slightly warmer discharge water had no adverse environmental impact on the area of lake sur-rounding the discharge point.

Miscellaneous Station Safety Systems The orange system in Figure 7 is part of the Emergency Core Cooling System (ECCS) housed l 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 either high pressure injection pumps, a core flood tank, or low pressure injection pumps. Borated water can also be sprayed from the ceil- l ing of the containment vessel to cool and condense any steam that may escape from the primary system.

l 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-l ers inside the pressurizer turn water into steam. This steam takes up more space inside the pres-l surizer, thus 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.

l l The scarlet system in Figure 7 is part of the Auxiliary Feedwater System, a key safety system in l 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 l

Building along with the turbine, main generator, and the condenser.

l l

18 L I

r Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report j Reactor Safety and Summary l

l Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear ,

i power plants cannot explode like a bomb because the concentration of fissionable material is far l less than is necessary for such a nuclear explosion. Also, many safety features are equipped with  !

l 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 l

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 l

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

Nuclear energy, industrial processes, and medical treatments are some of these activities. These by-products are managed and disposed of under strict requirements set by the federal govern-l 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. j l

Low Level Radioactive Waste Low level radioactive waste consists mainly of ordinary trash and other items that have become j 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.

l 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.

l Davis-Besse presently ships low level radioactive waste to a South Carolina disposal facility lo-cated at Barnwell, South Carolina. This facility was closed to out of compact generators from July 1,1994 to July 1,1996. The facility was reopened by South Carolina 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 it produced on site, in the Low i Level Radioactive Waste Storage Facility (LLRWSF) for several years in the event the Barnwell facility closes again.

l 19 L--_-_----------

E Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report High Level Nuclear Waste 1

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.

I High-level nuclear waste volumes are small. Davis-Besse produces about 30 tons of used fuel every 24 months. All the used fuel produced by all America's nuclear energy plants since the first plant started operating over 30 years ago would cover an area the size of a football field about five yards deep. All of America's nuclear plants combined produce only 3,000 tons of used fuel each year. By contrast, the U.S. produces about 300 million tons of chemical waste annu-ally. Also, nuclear waste slowly loses its radioactivity, but some chemical waste remains hazard-ous indefinitely. i l Davis-Besse presently stores its used fuel in a steel-lined concrete vault, filled with water, inside l 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 must accept fuel from utilities by the end of 1998. Currently, Yucca Mountain, Nevada, is being considered j as a possible site. Until the permanent DOE site is developed, nuclear plants will be responsible j for the continued safe storage of high level waste. At Davis-Besse, the fuel pool reached its ca-pacity in 1996. At the end of 1996, Davis-Besse began the process of moving the older fuel as-semblies that no longer require water cooling to air cooled concrete shielded canisters. These will remain stored onsite until the Department of Energy facilities are ready to receive them. Dry j l

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 Caro- j lina. Figure 8 illustrates the dry fuel storage module arrangement at Davis-Besse, j l

20

r Davis-Besse Nuclear Power Station' 1998 Annual Rr:liological Environmental Operating Report I

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Figure 8: Dry Fuel Storage Module 21 1.

( Davis-Besse Nuclear Power Stationi i998 Annual Radiological Environmental Operating Report Description of the Davis-Besse Site .,

l l The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the south-l western shore of Lake Erie,just north of the Toussaint River. The site lies north and east of Ohio l State Route 2, approximately 10 miles northwest of Port Clinton,7 miles north of Oak Harbor, and 25 miles east of Toledo, Ohio (Figure 9),

i 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 l but unsuitable for settlement and farming. During the nineteenth century, the land was cleared and drained, and has been farmed successfully since. Today, the terrain consists of farmland with marshes extending in some places for up to two miles inland from the Sandusky Lake Shore Ridge.

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

Davis-Besse site is mainly comprised of marshland with a small portion consisting of farmland.

l- 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 In-terior. _In 1971, Toledo Edison purchased the 188-acre Toussaint River Marsh. The Toussaint River Marsh is contiguous with the 610-acre Navarre Marsh section of the Ottawa National Wildlife Refuge.

r 22 l

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report The immediate area near Davis-Besse is sparsely populated; Ottawa County had a population of 40,029 in the 1990 census. The nearest incorporated communities are:

• Port Clinton - 10 miles southeast, population 7,106

• Oak Harbor - 7 miles south, population 2,637

• Rocky Ridge - 7 miles west southwest, population 425 e Toledo (the nearest major city) - 25 miles west, population 322,943 l

There are some residences along the lake shore used mainly as summer homes. However, the  !

major resort area of the county is farther east, around Port Clinton, Lakeside, and the Bass Is- j lands.  !

I The non-marsh areas around the Davis-Besse site are utilized primarily for farming. The major crops include soybeans, corn, wheat, oats, hay, fruits and vegetables. Meat and dairy animals are {

not major sources ofincome 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-

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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 allowir:g public fishing, nature study, and controlled hunting season. Turtle Creek, a wooded area at the southern end of Magee Marsh, offers boating and fishing. Crane Creek State Park is adjacent to Magee Marsh and is a popular picnicking , swimming, and fishing area. The Ottawa National Wildlife Refuge lies four to nine miles WNW of the Site,immediately west of Magee Marsh.

i l

i I i 23

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report J

l References

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

' I l

2. " Cesium-137 from the Environment to Man: Metabolism and Dose," Report No. 52, Na-tional 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, l Washington, D.C. (December 1987).

7 " Health Effects of Exposure to Low 12vels of Ionizing Radiation: BEIR V," Committee on the Biological Effects ofIonizing Radiations, Board on Radiation Effects Research Commis-sion on Life Sciences, National Research Council, National Academy Press, Washington, D.C. (1990).

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

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

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

(1982).

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

I1. 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, Washingten, D.C. (September 1987).

l-

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

24 e

Davis-Besse Nuclear' Power Station 1998 Annual Radiological Environmental Operating Report L 14. " Nuclear Energy Emerges from 1980's Poised for New Growth," U.S. Council for Energy

_ ' Awareness, Washington, D.C. (1989).

!- {

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

l (1987).

L

16. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report  !

No. 92, National Council on Radiation Protection and Measurement, Washington, D.C. (De-cember 1987). l I

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 Nu-clear Corporation, Middletown, PA. (1985).

19. " Sources, Effects and Risk ofIonizing Radiation," United Natias 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).

i

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

24. Site Environmental Report, Fernald Environmental Management Project, U.S. Department 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

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring )

Program Introduction l i

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

radioactivity in the surrounding areas. l 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 l various environmental media is based on the radionuclides of interest, their respective half-lives, )

and their behavior in both the biological and physical environment. I I

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 government requires nuclear facilities to conduct radiological environmental moni-toring prior to constructing the facility. This preoperational surveillance program is aimed at collecting.the data needed to identify critical pathways, including selection of the radioisotope and sample media combinations to be included in the surveillance program conducted after facil-ity operation begins. Radiochemical analyses performed on the environmental samples should include not only those nuclides expected to be released during facility operation, but should also include 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 on at least an annual basis during the preoperational phase of the environmental surveillance program, t

26 j

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report 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-tion, etc.) in order to detect any radiological impact the facility has on the surrounding environment. Data collection during the preoperational phase should be planned to provide a comprehensive database for evaluating any future changes in the environment surrounding the nuclear facility.

Davis-Besse began its 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:

e to fulfill the obligations of the radiological surveillance sections of the Sta-tion's Technical Specifications and Offsite Dose Calculation Manual; e to determine whether any significant increase occurs in the concentration of radionuclides in critical pathways; e to identify and evaluate the buildup, if any, of radionuclides in the local envi-ronment, or any changes in normal background radiation levels; and e 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. It 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 l results of the REMP through:

e performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keepmg; i l

• performing audits of contractor laboratories which analyze the environmental samples; e requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross-Check Program; l

1 27 I l

1

)

Dwis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report j e requiring analytical contractor laboratories to split samples for separate analy-sis followed by a comparison of results; e splitting samples prior to analysis by independent laboratories, and then com-paring the results for agreement, and, finally; e requiring analytical contractor laboratories to perform in-house spiked sample analyses.

Quality Assessment audits and inspections of the Davis-Besse REMP are performed by Davis-Besse's 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 incorpo-rated in Davis-Besse's REMP. Hence, the analytical results from the different programs can be compared. This practice of comparing results from identical samples, collected and analyzed by different parties, provides a valuable tool to verify the quality of the laboratories analytical pro-cedures 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 rest its from analysis of the quality control samples and the routine samples could then be com,nned for agreement. Quality control sampling has been integrated into the program and ha. become an important part of the REMP since 1987.

Quality control sampling locations are ;nanged 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 rostme sample counterpart.

Program Description Overview 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:

e atmospheric -- including samples of airborne particulates and airborne radioiodine e terrestrial -- including samples of milk, groundwater, broad leaf vegetation, fruits animal / wildlife feed, soil, eggs, and wild and domestic meat e aquatic -- including samples of treated and untreated surface water, fish, and shoreline sediments e direct radiation -- measured by thermoluminescent dosimeters 28 m _ - - - _ - - _

Davis-Besse Nuclear Power Station 1998 Anr.ual Radiological Environmental Operating Report 1 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- 1 Besse. Generally, they are located within five miles of the station. Control locations are those which should be unaffected by Station operations. Typically, these are more than five miles away from the Station Data obtained from the 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 environment. Data from indicator and control loca-tions 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- i ber of analyses performed on each sample. Besides adding new locations, duplicate or Qua'ity Control (QC) sample collection was initiated to verify the accuracy of the lab analyzing the envi- l ronmental samples. These additional samples are referred to as the REMP Enhancement Sam-ples. Approximately 1700 samples were collected and over 2300 analyses were performed

' during 1998. 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. l t

29

! Divis-Besse Nuclear Power Station 1998 Annu11 Radiological Environmental operating Report L Table 2: Sample Codes and Collection Frequencies Sample Collection  :

Sample Type Code Frequency l

Airborne Particulate AP Weekly {

l Airborne Iodine Al Weekly

]

Thermoluminescent TLD Quarterly, Annually Dosimeter Milk MIL Monthly (semi-monthly during grazing season)

Groundwater WW Quarterly I

Broad leaf Vegetation BLV Monthly (when available)

Surface Water - Treated SWT Weekly Surface Water - .SWU Weekly Untreated ( lake water , monthly )

Fish FIS Semiannually Shoreline Sediment SED Semiannually Soil SOI Semiannually Animal / Wildlife Feed DFE/WFE Annually Meat-Domestic DME Annually

. Meat-Wild WME Annually Egg EGG Annually Fruits FRU Annually i

L-30

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 3: Sample Collection Summary Sample Collection Number of Number of Number of Type Type */ Locations Samples Samples (Remarks) Frequency ** Collected Missed Atmospheric Airborne Particulates 10 520 0 Airborne Radiciodine C/W 10 520 0 Terrestrial Milk (Jan.-Dec.) G/M 1 12 0 Groundwater G/Q*** 4 16 0 Edible Meat Wild G/A 1 1 0  :

Domestic G/A 2 2 0 Eggs G/A 2 0 2 Broad Leaf Vegetation / Fruit G/M 8 13 0 Soil G/S 10 20 0 Animal / Wildlife Feed G/A 5 5 0 Aquatic Treated Comp /WM 2 24 0 Surface Water G/WM * *

• 4 36 0 Untreated G/WM * *

• 2 24 0 Surface Water G/M 10 70 0 Comp /WM 4 48 0 Fish (3 species) G/SA 2 6 0 Shoreline Sediments G/SA 5 10 0 1

Direct Radiation I Thermoluminescent C/Q* *

• 93 351 21 Dosimeters (TLD) C/A* *

• 93 81 12 r

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

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

• " Includes quality control location, SWU and SWT QC included in weekly grab sample /composited monthly SM = Semimonthly; M = Monthly; Q = Quarterly; SA = Semiannually; A = Annually 31

f Davis-Besse Nuclear Power Station 1998 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:

l l 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- j sis merely acts as a tool to identify samples that may require further analysis, i Gamma spectral analysis provides more specific information than does gross beta analysis.

l 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 Introduction Section, tritium is an isotope of hydrogen that emits low energy beta particles.

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

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

Often samples will contain little radioactivity, and may be below the lower limit of detection for the particular type of analysis used. The lower limit of detection (LLD) is the smallest amount of sample activity which 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 l that particular method for an individual analysis.

L t

32 f'

I I-i Davis-B sse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report L Table 4: Radiochemical Analyses Performed on REMP Samples i Sample Type Analyses Performed Atmospheric Monitoring i

l Airbome Particulate Gross Beta  ;

Gamma Spectral l Strontium-89 Strontium-90 Airborne Radiciodine Iodine-131 Terrestrial Monitoring Milk Gamma Spectral Iodine-131 Strontium-89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectral j Tritium Strontium-89 Strontium-90 Broad Leaf Vegetation Gamma Spectral j and Fruits Iodine-131 i Strontium-89 Strontium-90 Animal / Wildlife Feed Gamma Spectral l Soil Gamma Spectral Wild and Domestic Meat Gamma Spectral Egg Gamma Spectral I

1 i

).

33

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples (continued)

Sample Type Analyses Performed Aquatic monitoring Untreated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Treated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 lodine-131 Fish Gross Beta Gamma Spectral Shoreline Sediment Gamma Spectral Direct Radiation Monitoring

~ Thermoluminescent Dosimeters Gamma Dose 34 i

r' ]

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report

, 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 car-lier years. Generally, the results of sample analyses are compared with preoperational and op-erational data. Additionally, the results of indicator and control locations are also compared.

This allows REMP personnel to track and trend the radionuclides present in the environment, to assess whether a buildup of radionuclides is occurring and to determine the effects, if any, the operation of Davis-Besse is having on the environment. If any unusual activity is detected, it is investigated to determine whether it is attributable to the operation of Davis-Besse, or to some other source such as nuclear weapons testing. A summary of the REMP sample analyses per-formed from 1972 through the current reporting period is provided in the following section.

Atmospheric Monitoring

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

]

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

Terrestrial Monitoring:

• Groundwater: Only naturally occurring radioactive material has been de-tected in groundwater, e Milk: Iodine-131 from nuclea 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 wet weight. Cesium-137 was detected in 1974,1975, and 1981 due to fallout from nuclear weap-ons testing.

• Broad Leaf Vegetation and Fruits: Only naturally occurring radioactive material and material from nuclear weapons testing has been detected.

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

• Animal / Wildlife Feed: Only natural background and material from weapons testing has been detected.

1 35

p l Davis Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report l

l e Eggs: Only natural background radioactive material has been detected.

Aquatic Monitoring )

! -e . Surface Water (Treated and Untreated): In 1979 and 1980, the tritium i j concentrations at location T-7 were above normal background. Location T-7 is a_ beach well fed directly by Lake Erie. The fourth quarter sample in 1979 read 590 picocuries per liter, and the first quarter sample in 1980 had a con-centration of_960 picocuries per liter. A follow-up sample was collected in Lake Erie between T-7 and the Davis-Besse liquid discharge point. This sam-ple contained tritium at a concentration of 2737 picocuries per liter. These concentrations could be attributed to the operation of Davis-Besse. Even so, these results at T-7 were more than 39 times lower than the annual average concentration allowed by the EPA National Interim Primary Drinking Water Regulations (40CFR141), and were only 0.032% of the Maximum Permissible ,

Concentration (MPC of 3,000,000 picocuries per liter) for tritium in unre-stricted areas. The follow-up sample was less than 0.1% of the MPC. None of the subsequent samples indicate any significant difference between the background tritium concentration and the concentration at T-7.

In 1991, the tritium concentration in the untreated surface water at T-130 was above normal background levels. T-130 is located in Lake Erie approximately

? ? yards from the mouth of the Toussaint River. The August composite was 884 picocuries per liter. Follow up samples were less than the LLD of 330 pi-cocuries per liter. Although this concentration may be attributed to the opera-tion of Davis-Besse, it was only. 0.029% of the maximum permissible concentration for tritium in an unrestricted area. This did not have any sig-nificant adverse effect on the environment and the population near the station.

The December 1992 composite for tritium at T-3 (mouth of Toussaint River) showed trace amounts of activity which may be attributed to the normal op-eration of the station. The tritium concentration for the composite was 950 pCiM. This is only 0.032 percent of the maximum permissible concentration of 3,000,000 pCin for tritium in an unrestricted area, as stated in 10 CFR 20,

. Appendix B, Table 2. Subsequent samples collected during January 1993 showed that the tritium had returned to below the LLD of 330 pCiM.

'In the fourth quarter of 1994, tritium was detected at 336 94 pCiM, slightly above the lower limit of detection for tritium, at one of the treated water sam-pling locations. Tritium was also detected at several of the untreated water sampling locations at an average concentration of 470 pCin during the 3rd and 4th quarters of 1994. Samples taken in January 1995 indicated that the tritium concentration in untreated water was less than the lower limit of detection for tritium in water. For comparison purposes, tritium concentrations in Lake Erie untreated surface water, determined during the preoperational sampling l . period of July 1972 through June 1974, ranged from 180 pCiM to 590 pCiM with an average concentration of less than 300 pCiM.

36

{

j Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report l'

, In 1995, trace amounts of tritium were detected in six untreated water samples collected in May and one sample collected in October. The tritium detected ranged between 330 to 1234 pCi/l with an average concentration of 681 pCi/1.

This is only 0.12% of the Effluent Concentration Limit of 1,000,000 pCi/l for i

tritium in an unrestricted area, as stated in 10 CFR 20, Appendix B, Table 2.

Subsequent samples taken showed the tritium activity to be <330 pCi/1.

During 1996, tritium was detected ranged between 330 and 589 pCi/l with an

- average concentration of 340.3 pCi/l in 8 untreated surface water samples.

The remainder of the untreated surface water samples were <330 pCi/l.

During 1997, the tritium detected ranged between 340 to 575 pCi/l with an av-erage concentration of 430 pCi/l in 4 untreated surface water samples. Even though these may be attributed to the operation of Davis-Besse, this average concentration is less than 0.06% of Maximum Pemiissible Concentration for tritium in unrestricted areas.

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

• Shoreline Sediments: Only natural background, material from nuclear test-ing and from the 1986 nuclear accident at Chernobyl has 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 55.3 to 73.0 millirem per year at control locations and between 31.8 and 84.6 mil-lirem per year at indicator locations. No increase above natural background radiation attributable to the operation of Davis-Besse has been observed.

1998 Program Deviations Provided below is a description and explanation of 1998 environmental sample collection deviations. l

=

Broadleaf vegetation was not collected during January, February, March, April, May, June, July, November and December because of seasonal unavailability.

=

On 2/10/98, air sample pump at T-12 had a blown fuse. Time lost during sampling period was 17.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Sample media was collected and analyzed as scheduled.

= On 3/10/98, air sample pump at T-3 was found off at time of collection. Faulty fuse assem-

- bly on pump was discovered and replaced. Total run time for sample period was 26.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Sample media was collected and analyzed as scheduled.

( On 3/24/98, air sample pump at T-3 was found off at time of collection. Pump motor was replaced and pump returned to service. Total run time for sample period was 37.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Sample media was collected and analyzed as scheduled.

37

l Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report

=

i On 4/6/98, Air sample pump at T-1 as found off at time of collection. Breaker servicing this site was tripped opened. Breaker was reset and pump returned to service. Total run time for sample period was 33.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Sample media was collected and analyzed as scheduled.

=

The TLDs at T-155, quarterly and annual was missing at time of collection. It is presumed that the TLDs were lost due to vandalism. The new TLDs were installed in a less accessible location.

= On 5/26/98, a composite sample was not available from T-28 untreated water, because the composite sample tubing became clogged. A grab sample was collected. New tubing was l installed and the compositor was returned to service.

=

On 5/26/98, the timer on the air sample pump at T-8 had 0.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> recorded. Upon further investigation it was discovered that the timer was defective. The timer was replaced and the pump returned to service. Sample media was collected and analyzed as scheduled.

=

On 6/24/98, several air sample pumps experienced power outages caused by severe thunder- i storms and tornadoes present in the area. Sites losing power were T-1, T-2, T-3, T-4, T-7, I

'T-8 and T-27. Portable generators were installed at T-1 and T-2 until power was restored.

The other locations power were restored as electrical line were repaired. Run time lost ranged from 18.2 - 93.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Sample media was collected and analyzed at all location as scheduled.

=

On 7/7/98, the timer on the air sample pump at T-8 had 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> recorded. Upon further in-vestigation it was discovered that the timer was defective. The timer was replaced and the pump returned to service. Sample media was collected and analyzed as scheduled, a During 3'd quarter TLD exchange many TLDs were found to be missing, due to severe weather present in the area on 6/24/98. The locations with both 2"d quarter and annual TLDs missing are T-8, T-52, T-53, T-69, T-83, T-91, T-94, T-112, T-119, T-120, T-150, T153, T-205. New TLD cages were installed and the third quarter TLD installed. Also missing were the following 2"d quarter and annual TLDs: T-46, T-48, T-84 and T-200. New locations in the vicinity of these were selected because these sites were destroyed by tornadoes. The 3'd quarter TLDs were installed at the new sites.

• On 9/8/98, a composite sample was not available from T-12 untreated water, because the composite sample tubing became clogged. A grab sample was collected. New tubing was installed and the compositor was retumed to service.

=

On i1/17/98, the timer on the air sample pump at T-1 had 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> recorded. Upon further investigation it was discovered that the timer was stuck. The timer was repaired and the pump returned to service. Sample media was collected and analyzed as scheduled.

On 11/24/98, air sample pump at T-1I was off upon arrival to collect sample media. The power was lost due to construction activities occurring in the vicinity. The timer read 48.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Sample media was collected and analyzed as scheduled.

l = On 12/1/98, the timer on the air sample pump at T-2 had 154.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> recorded instead of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />. Upon further investigation it was discovered that the timer was stuck. The timer was repaired and the pump returned to service. Sample media was collected and analyzed as scheduled.

38

Davis Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report l

l = On 12/1/98, the timer on the air sample pump at T-7 had 120.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> recorded instead of l 168.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Upon further investigation it was discovered that the timer was stuck. The l timer was removed and a different pump returned to service. Sample media was collected l L and analyzed as scheduled. l l

• During 4* quarter change out of TLDs the following TLDs were missing: both annual and quarterly T-4 and T-142. The annual only was missing at the following sites: T-122, T-150 and T-155.

l Atmospheric Monitoring Air Samples  ;

)

Environmental air sampling is conducted to detect any increase in the concentration of airborne I l 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 particulates and airborne ra-diciodine. l Samples are collected weekly with low volume vacuum pumps which draw a continuous sample through a glass fiber filter and charcoal cartridge at a rate of approximately one cubic foat per minute. Airborne particulate samples are collected on 47 mm diameter filters. Charcoal car-tridges are installed downstream of the particulate filters to sample for the airborne radioiodine.

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

Airborne Particulates Davis-Besse continuously samples air for airborne radionuclides at ten locations. There are six indicator locations including four around the site boundary (T-1, T-2, T-3, and T-4), one at Sand Beach (T-7), and another at a local farm (T-8). There are four control locations, Oak Harbor (T-9), Port Clinton (T-11), Toledo (T-12) and Crane Creek (T-27).  !

Gross beta analysis is performed on each of the weekly samples. Each quarter, the filters from each location are combined (composite) and analyzed for gamma emitting radionuclides, stron-tium-89 and strontium-90.

Beta emitting radionuclides were detected at both the indicator and control locations at average )

3 3 concentration of 0.021 pCi/m and 0.022 pCi/m , respectively. Beryllium-7 was the only gamma j emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites.

Beryllium-7'is a naturally occurring radionuclide produced in the upper atmosphere by cosmic radiation. No other gamma emitting radionuclides were detected above their respective LLDs.  ;

Strontium-89 (Sr-89) and Strontium-90 (SR-90) were not detected above their LLDs. These re- I sults show no adverse change in radioactivity in air samples due to operation of the Davis-Besse Nuclear Power Station in 1998. i 39 .

4

- Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Airborne Iodine-131 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, scaled in separate collection bags and sent to the laboratory for gamma spectral analysis, in all of the samples collected in 1998, there was no detectable iodine-131 3

above the LLD of 0.07 pCi/m .

1998 Airborne Particulate Gross Beta 0.05 ._

0.045 -

0.04 <

0.035-0.03 - A 0.025-0.02 -

A 0.015-N 0.01 <

0.005 =

0 January March May Juh September November I-+-indicator -e-Control l Figure 10: Concentration of beta emitting radionuclides in airborne particulates samples were essentially identical at indicator and control locations.

l 40

Divis-Besse Nucl:ar Pow:r Station 1998 ' Annual Radiological Environmental Operating Report Table 5: Air Monitoring Locations Sample Location Type of Number Location Location Description T-1 1 Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station T-4 I Site boundary,0.8 miles S of Station T-7 I Sand Beach, main entrance,0.9 miles NW of Station T-8 I Earl Moore Farm,2.7 miles WSW of Station T-9 C Oak Harbor Substation,6.8 miles SW of Station T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station I = Indicator C = Control 41 I

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Davis-Besse Nuclear Power Station 1998 /.nnual Radiological Environmental Operating Report Terrestrial Monitoring The collection and analysis of groundwater, milk, meat, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. Animal and wildlife feed samples provide additional information on radionuclides that may be present in the food chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere.

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

e 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 e beryllium-7, present as a result of the interaction of cosmic radiation with 6e upper atmosphere e cesium-137, a man-made radionuclide which has been deposited in the envi-ronment, (for example, in surface soils) as a result of fallout from nuclear weapons testing anti routine releases from nuclear facilities e potassium-40, a naturally occurring radionuclide normally found throughout the environment (including humans) e fallout radionuclides from nuclear weapons testing, including strontium-89, strontium-90, cesium-137, cerium-141, cerium-144, and ruthenium-106.

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

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

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

1 When milk is available, samples are collected at the indicator location and at the control location  !

once a month from November through April, and twice a month from May through October.

Sampling is increased in the summer when the herds are usually outside on pasture and not on 45

f.i

)

1

- Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report L stored feed. In December of 1993, the indicator location, T-8, was eliminated from the sampling

!' - program because the family there went out of the dairy business and sold the herd. The control location will continue to be sampled 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.

The 1998 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 1998. Strontium-89 was not detected above it's LLD. Strontium-90 was detected in all but one samples collected. The annual average concentration of strontium-90 was 0.9 pCi/1.

For all sample sites, the annual average concentration was similar to those measured in the previ-4 ous years.

Iodine-131 was not detected in any of the milk samples above the LLD of 0.5 pCi/l. The con-centrations of barium-140 and cesium-137 were below their respective LLDs in all samples col-lected.

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

.In order to detect the potential environmental accumulation of these radionuclides, the ratios of i

the strontium radioisotopes radioactivity (pCi/l) to the concentration of calcium (g/l), and cesium j radioisotopes radioactivity (pCi/l) to the concentration of potassium (g/l) were monitored in milk, i These ratios are compared to standard values to determine if build up is occurring. No statisti-

. cally significant 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 I i t  ;

46

r I

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report  !

I a

Groundwater Samples Soil acts as a filter and an ion exchange medium for most radionuclides. However, tritium and other radionuclides such as ruthenium-106 have a potential to seep through the soil and could reach groundwater. Although Davis-Besse does not discharge its liquid effluents directly to the {j ground, REMP personnel sample local wells on a quarterly basis to ensure the early detection of any adverse impact on the local groundwater supplies due to Station operation. The wells sam-pled include two indicator locations (T-7, T-54), and one control location (T-27). In addition, a quality control sample is collected at one of the wells each quarter. The groundwater samples are analyzed for beta emitting radionuclides, tritium, strontium-89, strontium-90 and gamma emit-ting radionuclides.

1 Beta emitting radionuclides average 5.7 pCi/l for indicator locations and 4.5 pCiM for control lo-cations. Tritium was not detected above the LLD of 330 pCia. Strontium-89 was not detected 1 above the LLD of 1.0 pCiM. Strontium-90 was not detected in indicator sample above the LLD of 0.7 pCiM. There were no gamma emitting radionuclides detected above their respective LLDs j in any of the samples collected. All sample analyses were within normal ranges and were similar i to results of previous years.

4 Gross Beta Ground water 1982-1998 i 8-

N hA N / V\ x _ P

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2-1-

0  :  :  :  :  :  :  :  :  :  :  :  :  :  :  : :

E 2 3 $ $ 58 8 8 E E 9 3 8 8 5 8 sE E E E E E E S E E E a2 ? E 2

--+-- Indicator

--o- Control Figure 14: Shown above are the annual averages for gross beta in groundwater from 1982 - 1998. This years results are well within the range of previous years.

47

Davis-Besse Nucliar Power Station' 1998 Annual Radiological Environmental Operating Report l Table 7: Groundwater Monitoring Locations Sample Location Type of Number Location Location Description l 1

T-7 I Sand Beach,0.9 miles NW of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station T-54 I Weis Farm,4.3 miles SW of Station i

T-141 QC Roving Site 1 I = indicator C = control QC = quality control Broad Leaf Vegetation and Fruit Samples i Fruits and broad leaf vegetation also represent a direct pathway to humans. Fruits and broad leaf  ;

vegetation may become contaminated by deposition of airborne radioactivity (nuclear weapons l fallout or airborne releases from nuclear facilities) or from irrigation water drawn from lake wa-ter receiving liquid effluents (from 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 broad leaf vegetation, such as kale and cabbage, and fruits,

)

such as apples and grapes, are collected from farms in the vicinity of Davis-Besse.

In 1998, broad leaf vegetation samples were collected at three indicator locations (T-17, T-36 and T-19) and one control location (T-37). Fruit samples were collected at two indicator locations (T-8 and T-25) and two control locations (T-37 and T-173). Broad leaf vegetation was collected j once a month during the growing season. Broad leaf vegetation collected consisted of cabbage, j and swiss chard. The fruits collected were apples, and grapes. All samples were analyzed for i gamma emitting radionuclides, strontium-89, strontium-90, and iodine-131, 1

Iodine-131 was not detected above the LLD of 0.024 pCi/g (wet) in any broad leaf vegetation nor l above the LLD of 0.022 pCi/g (wet) in fruit samples. The only gamma emitting radionuclide  !

detected in the fruit and broad leaf vegetation samples was potassium-40, which is naturally oc-l curring. In both fruit and broad leaf vegetation, strontium-89 was not detected above their LLDs of 0.003 pCi/g (wet) and 0.014 pCi/g (wet). In broadleaf vegetation, strontium-90 (Sr-90) was detected at average concentrations of 0.015 pCi/g (wet) for indicator locations and below LLD of 0.003 for control locations. In the fruit samples, Sr-90 at location T-8, T-25 (indicator) and T-37 and T-173 (control) was <0.001 pCi/g (wet). All results of analyses were similar to results ob-

,. served in previous years; this demonstrates that the operation of Davis-Besse had no adverse ef- i fect on the surrounding environment in 1998.

l 48 l

c Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report i

i

! Table 8: Broad Leaf Vegetation and Fruit Locations Sample Location Type of Number Location Location Description T-8 I Moore Farm,2.7 miles WSW of Station T-17 I J. Sobieralski ,1.8 miles SSE of Station T-19 I B. Skinner,1.0 mile W of Station T-25 I Witt Farm, T-36 I Allen's Get Away,2.3 miles NW of Station T-37 C Bench Farm,13.0 miles SW of Station T-173 C Firelands Winery, Sandusky,20.0 miles SE of station.

I = indicator C = control Animal / Wildlife Feed Samples As with broad leaf vegetation and fruit samples, samples of domestic animal feed, as well as vegetation consumed by wildlife, provide an indication of airborne radionuclides deposited in the vicinity of the Station. Analyses of animal / wildlife feed samples also provide data for determin-ing radionuclide concentration in the food chain. Domestic animals feed samples are collected at two domestic meat-sampling locations. Wildlife feed samples are collected from the Navarre Marsh onsite and from a local marsh within five miles of the Station. As in all terrestrial sam-ples, 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 location (T-197) and one control location (T-34). The feed collected was chicken feed. All samples were analyzed for gamma emit-ting 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 and smart weed. Samples were analyzed for gamma emitting radionuclides.

j In both the animal and wildlife feed, naturally occurring potassium-40 and beryllium-7 l was detected. All other radionuclides were below their respective LLDs. The operation i

of Davis-Besse had no adverse effect on the surrounding environment.

i 49 l

e r

Divis-Besse Nuclear Power Station 1998 Annual Radiologic:.1 Environmental Operating Report Table 9: Animal / Wildlife Feed Locations Sample Location Type of Number Location Location Description T-31 I Davis-Besse, onsite roving location T-32 C Metzer Marsh,10.0 miles WNW of the Station T-34 C Sager farm, Graytown 8.8 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 v/ild meat provides information on environmental radionuclide con-centrations that humans may be exposed to through an ingestion pathway. The principle path-ways for radionuclide contamination of meat animals include deposition of airborne radioactivity on 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 (chickens) and eggs on an annual ba-sis. Wild animals commonly consumed by residents in the vicinity of Davis-Besse include wa-terfowl, deer, rabbits and muskrats. Analyses from animals whose meat is eaten by humans provides general information on radionuclide concentration in the food chain. When evaluating the results from analyses performed on meat animals, it is important to consider the age, diet and mobility of the animal before drawing conclusions on radionuclides concentration in the local environment or in a species as a whole.

Domestic meat samples were sampled in 1998 as follows:

Domestic Meat: Chickens were collected at one indicator location (T-197)

L and one control location (T-34). The samples were analyzed for gamma emit-l ting nuclides.

Wild Meat: Muskrat samples were obtained from one location onsite (T-31).

.(only natural occurring radionuclides were detected in the edible portion of chickens and muskrat) 50

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report

• Eggs; Eggs were t.navailable at both locations at the time of collection.

T-197 and T-34 did not have any laying ch&ns.

Table 10: Wild and Domestic Meat Locations Sample Location Type of <

Number Location Location Description T-31 I Onsite roving location T-34 C Sager Farm, Graytown Rd,9.0 miles W of the Station T-197 I Lochotzki residence,4.0 miles W of the Station lemon Road

{

I = indicator C = control j i

Soil Samples i 1

Soil samples are generally collected twice a year at the sites that are also equipped with air sam- I plers. Only the top layer of soil is sampled in an effort to identify possible trends in the local en- I vironmental nuclide concentration caused by atmospheric deposition of fallout and station l released radionuclides. Generally, the sites are relatively undisturbed, so that the sample will be representative of the actual deposition in the area. Ideally, there should be little or no vegetation present, because the vegetation could affect the results of analyses. Approximately five pounds of soil are taken from the top two inches at each site. Many naturally occurring radionuclides such as beryllium-7 (Be-7) and potassium-40 (K-40) and fallout radionuclides from nuclear weapons testing are detected. Fallout radionuclides that are often detected include strontium-90 l (Sr-90), cesium-137 /Cs-137), cerium-141 (Ce-141) and ruthenium-106 (Ru-106).

During 1998, soil was collected at ten sites in April and October. The indicator locations in-cluded T-1, T-2, T-3, T-4, T-7, and T-8. The control locations were T-9, T-11, T-12, and T-27.

All soil samples were analyzed for gamma emitting radionuclides. The results show that the only gamma emitter detected in addition to naturally occurring Be-7 and K-40, was Cs-137. Cs-137 was found in both indicator and control locations at average concentrations of 0.26 pCi/g dry and l

0.24 pCi/g dry, respectively. The concentrations were similar to that observed in previous years 1 (Figurel5).

l 51

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Cs-137 in Soll from 1972 1998 1.2 -

1- - -

l.* kvicalor i + catre 0.s . - -

0.6 - -- - -

0.4 - - -

q ./-

0.2 - - - -

i 1

0 .........................

Figure 15: The concentration of cesium-137 in soil has remained fairly constant over the years REMP has been con-ducted. The peak seen in 1978 was due to fallout from nuclear weapons testing.

i 1

52 )

i

i Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report l

Table 11: Soil Locations q l

l Sample Location Type of '

Number Location Location Description T-1 I Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary 1.4 miles ESE of Station l

I T-4 I Site boundary 0.8 miles S of Station l l

T-7 I Sand Beach, main entrance,0.9 miles NW of Station l

T-8 I Moore Farm,2.7 miles WSW of Station T-9 C Oak Harbor Substation,6.8 miles SW of Station T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station I = indicator C = control t-53

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Aquatic Monitoring Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-off/ soil erosion, and releases of radioactive material in liquid effluents from hospitals or nu-

. clear facilities. These sources provide two forms of potential exposure to radiation,' external and

' internal. ' External exposure can occur from the surface of the water, shoreline sediments and from immersion (swimming) in the water. Internal exposure can occur from ingestion of radio-nuclides, either directly from drinking water, or as a result of the transfer of radionuclides through the aquatic food chain with eventual consumption of aquatic organisms, such as fish. To

. monitor these pathways, Davis-Besse samples treated surface water (drinking water), untreated surface water (lake or river water), fish, and shoreline sediments.

Treated Surface Water Treated surface water is water from Lake Erie which has been processed for human consumption.

Radiochemical analysis of this processed water provides a direct basis for assessing the dose to l humans from ingestion of drinking water.

Samples of treated surface water were collected from two indicators (T-28 and T-50) and two  ;

control locations (T-11 and T-12). These locations include the water treatment facilities for  !

Davis-Besse, Eric Industrial Park, Port Clinton and Toledo. Samples were collected weekly and j composited monthly. The monthly composites were analyzed for beta emitting radionuclides. l The samples were also composited in a quarterly sample and analyzed for strontium-89, stron- J tium-90, gamma emitting radionuclides, and tritium. One QC sample was collected from a rou- I tine location which was changed each month.

The annual average for beta emitting radionuclides for indicator and control locations were 2.5 pCi/l and 2.3 pCi/1, respectively. These results are similar to previous years as shown in Fig-ure 19. Tritium was detected above the LLD of 330 pCi/l at on location, T-28 during December.

The concentration of this sample was 667 pCi/l. Strontium-89 was not detected above the LLD 1.5 pCi/1. Strontium-90 activity was 1.3 pCi/l at indicator locations and 1.2 pCi/l at control sites.

These results are similar to those of previous years and indicate no adverse impact on the envi-ronment resulting form the operation of Davis-Besse in 1998.

1 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 2.4 pCi/l and 2.4 pCi/l at routine locations. Tritium and cesium-137 were below their respective LLDs. There was good agreement between the routine and QC locations.

l 57 l

l

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Gross Beta Treated Surface Water 19721998 5

4.5 - - --- -- --- - - - - --- - - --

4- -- -- - - - - - . - .

l t

i

' 3.5 - + -- - - - - - --- - - -- -

1 3- - - - -*-- - - -- - ---- - - -

2.5 - - -- - - - - - - -- - - - -

-+-Indcats A >

{

2- -- -- - - -

V% _- -

W-1.5 - - -- - -- - - - - - - -- - - - -

1 3 . .. . . . .. . .. .

0.5 - - + ,

o ,

1972 1974 1978 1978 1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 Figure 19: Since 1974, the annual concentrations of beta emitting radionuclides in treated surface water samples collected from indicator locations have been consistent with those from control locations. This shows that Davis-Besse has had no measurable radiologicalimpact on surface water used to make drinking water. ,

l I Table 12: Treated Surface Water Locations I

Sample Location Type of Number Location Location Description f

i 1

T-11 C Port Clinton Water Treatment Plant 9.5 miles l SE of Station i l

T_-12 C Toledo Water Treatment Plant 23.5 miles WNW of Station T-28 I Treated Water supply from Davis-Besse site -;

I l

T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE j of Station T-143 QC Quality Control Site I = indicator C = control QC = quality control l

I 58 i i

(

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environrnental Operating Report i.

L Untreated Surface Water l

l Sampling and analysis of untreated surface water provides a method of assessing the dose to hu- q mans from external exposure from the lake surface as well as immersion in the water. It also j provides information on the radionuclides present which may affect drinking water, fish, and ir- j rigated crops.

{

H Routine Program The routine program is the basic sampling program which is performed year round. Untreated water samples are collected in the areas of the station intake and discharge and at the water in-takes used by nearby water treatment plants. - Routine samples are collected at Port Clinton, Toledo, Davis-Besse, and Erie Industrial Park. A sample is also collected from Lake Erie at the

! ~ ' ' '

mouth of the Toussaint River. These samples are collected weekly and composite monthly. The monthly composite is analyzed for beta emitting radionuclides, tritium, and gamma emitting ra-dionuclides. The samples are further composite quarterly and analyzed for strontium-89 and

strontium-90. A QC sample is also collected weekly. It is at a different location each month.

Summer Program 1

The summer program is designed to supplement the routine untreated water samplmg program m order to provide a more comprehensive study during the months of high lake recreational activ- )

-ity, such as boating, fishing, and swimming. These samples are obtained in areas along the shoreline of Lake Erie.' The samples are collected monthly and analyzed for beta emitting radio-activity, tritium, strontium-89, strontium-90 and gamma emitting radionuclides.

For the routine samples composite weekly, the beta emitting radionuclides had an average con-centration of 2.8 pCih at indicator and 2.5 pCiM at control locations respectively. The average concentration of beta emitting radionuclides in all samples (include lake water) was 3.2 pCia at indication and 2.7 pCiM at control locations.

The tritium detected, ranged from a concentration of 359 pCia to 1221 pCia. The average con-centration of tritium detected above the LLD was 538 pCia at indication location and 706 pCia at controls. The maximum tritium concentration detected is only 0.12% of the effluent concen-tration limit of 1,000,000 pCiM for tritium in an unrestricted area, as provided by 10CFR20, Ap-pendix B, Table 2, column 2. The tritium detected at the control location is presumed to come from activities not associated with the operation of Davis-Besse.

Cesium-137 and strontium-89 were not detectable in samples of untreated water above their LLDs of 10 pCia and 1.3 pCiM, respectively. Strontium-90 activity at indicator and control loca-tions were 1.3 and 0.9 pCia respectively. The results of untreated water show that the operation of Davis-Besse had no adverse impact on nearby residents or on the environment.

l 59 u

Davis-Besse Nuclear Power Station 1998 Annuil Radiologicci Environmental Operating Report i

Gross Beta Concentration in Untreated Surface Water from 1977 1996 7

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-+-INDICATOR

-e- CONTROL l $- -

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Figure 20: The average concentration of beta emitting radionuclides in untreated water was similar between control l and indicator locations. This demonstrates that Davis-Desse had no radiological impact on the surrounding envi-ronment.

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 2.8 pCi/l and 2.8 pCi/l at routine locations. Tritium and cesium-137 were below their respective LLDs. There was good agreement between the routine and QC locations.

1 l

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Davis-B:sse Nuclear Power Sttion 1998 Annual Radiological Environmental Operating Report L Table 13: Untreated Surface Water Locations i

Sample Location Type of Number Location Location Description T-3 I Site boundary,1.4 miles ESE of Station T-11 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-28 I Davis-Besse Water Treatment Plant T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE of Station T-131 I Lake Erie,0.8 miles NE of Station T-132 I Lake Erie,1.0 miles E of Station T-133 I Lake Erie,0.8 miles N of Station T-134 I Lake Erie,1.4 miles NW of Station T-135 I Lake Erie,2.5 miles WNW of Station T-137 C Lake Erie,5.8 miles WNW of Station T-145 QC Roving Quality Control Site T-152 C Lake Erie,15.6 miles WNW of Station i T-158 C Lake Erie,10.0 miles WNW of Station 1

T-162 C Lake Erie,5.4 miles SE of Station l

T-167 C Lake Erie,11.5 miles E of Station I = indicator C = control

)

61 l

i

Davis-Besse Nuclear Power Stction 1998 Annual 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 fishermen and swimmers.

Samples of deposited sediments in water along the shore were collected at various times from three indicator sites (T-3, T-4, and T-132) and one control location (T-27). Shoreline sediment was collected with a shovel. All samples were analyzed for gamma emitting radionuclides.

Naturally occurring potassium-40 was detected at both controls and indicator locations. Cs-137 was detected at one location, T-4 at a concentration of 0.24 pCi/g. These results are similar to previous years.

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

1 62 l

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I Davis Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report j 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-137, and strontium-90. Depending upon the feeding habit of the species (e.g., bottom-feeder versus predator), results from sample analyses may vary.

With the aid of a local commercial fisherman, Davis-Besse routinely collects three species of fish 6 Jaileye, white perch or white bass and carp) twice a year from sampling locations near the Sta-tion's liquid discharge point and more than ten miles away from the Station where fish popula-tions would not be expected to be impacted by the Station operation. Walleye are collected because they are a popular sport fish, white perch or white bass because they are an important l commercial fish. Carp are collected because they are bottom feeders and thus would be more likely to be affected by radionuclides deposited in lake sediments. The edible portion of fish were analyzed for beta and gamma emitting radionuclides.

The average concentration of beta emitting radionuclides in fish muscle was similar for indicator and control locations (2.66Ci/g and 2.56/g wet weight, respectively). Cesium-137 was not de-tected above the LLD of <0.018 pCi/g for indicator and control locations. No other gamma emitter were detected above their respective LLDs.

Gross Beta Concentration in Fish 1972-1998 5

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l-e-Indicator -*-Control l Figure 21: Average concentrations of beta emitting radionuclides in fish samples were similar at indicator and con-trol locations and were within the range of results of previous years.

63 L

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 15: Fish Locations Sample Location Type of Number Location Location Description T-33 I ' Lake Erie, within 5 miles radius of Station i T-35 C Lake Erie, greater than 10 mile radius of Station I = indicator C= control I

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Davis-Besse Nuclear Power Sbtion 1998 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Thermoluminescent Dosimeters Radionuclides present in the air, and those deposited on the ground, may directly irradiate indi-viduals. Direct radiation levels at and around Davis-Besse are constantly monitored by thermo-luminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information.

The TLDs used at Davis-Besse contain a calcium sulfate: dysprosium (CaSO4:Dy) card with four main readout areas. Multiple readout areas are used to ensure the precision of the measurements.

Thermoluminescence is a process by which ionizing radiation interacts with phosphor which is the sensitive material in the TLD. Energy is 1.apped in the TLD material and can be stored for several months or years. This provides an excellent method to measure the dose received over 1 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 rezeros the TLD and prepares it for reuse.

TLD Collection Davis-Besse has 75 TLD locations (64 indicator and i1 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 is a total of 186 TLDs in the environment surrounding Davis-Besse at any given time. By collecting TLDs on a quarterly and annual basis from a single site, each measurement serves as a quality control check on the other. Over 94% of the quarterly TLDs placed in the field and 87% of the annual TLDs placed in the field were retrieved and evaluated during the cur-rent reporting period.

In 1998, the average dose equivalent for quarterly TLDs at all indicator locations _ was l 13.8 mrem /91 days, and for all control locations was 15.0 mrem /91 days, The average dose equivalent for annual TLDs in 1998 was 56.9 mrem /365 days at indicator locations and 64.8 mrem /365 days for control locations.

Quality Control TLDs Duplicate TLDs have been placed at 18 sites. These TLDs were placed in the field at the same time and at the same location as some of the routine TLDs, but were assigned quality control site numbers. This allows us to take several measurements at the location without the laboratory be-ing aware that they are the same. A comparison of the quality control and routine results pro-vides a method to check the accuracy of the measurements. The average dose equivalent at the routine TLDs averaged _13.8 mrem /91 days while the quality control TLDs yielded an average dose equivalent of 13.3 mrem /91 days. All the quality control and routine sample results were similar, demonstrating the accuracy of both the TLDs and the laboratory's measurements.

68

Davis-Besse Nucicar Power Station 1998 Annual Radiological Environmental Operat.r g Report Gamma Dose for EnvironmentalTLDs 1973 1998 25 i t t

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l-+-indicator -e-control l Figure 25: The similarity between indicator and control results demonstrated that the operation of Davis-Be:2e has not caused any abnormal gamma dose.

l 69

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations Sample Location Type of Number Location Location Description T-1 I Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station T-4 I Site boundary,0.8 miles S of Station T-5 I Site boundary,0.5 miles W of Station T-6 I Site boundary,0.5 miles NNE of Station T-7 I Sand Beach, main entrance,0.9 miles NW of Station T-8 I Earl Moore Farm,2.7 miles WSW of Station T-9 C Oak Harbor Substation,6.8 miles SW of Str:on l

T-10 I Site boundary,0.5 miles SSW of station near l warehouse T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-24 C Sandusky,21.0 miles SE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station

-T-38 I Site boundary,0.6 miles ENE of Station T-39 i Site boundary 1.2 miles ENE of Station T-40 I Site boundary,0.7 miles SE of Station T-41 I Site boundary,0.6 miles SSE of Station

.T-42 I Site boundary,0.8 miles SW of Station 70

Davis-Besse Nuclear Pow:r Station 1998 Annual Radiological Environmental operating Report l

! Table 16: Thermoluminescent Dosimeter Locations (continued)

)

Sample Location Type of Number Location Location Descr.iption T-43 I Site boundary,0.5 miles SW of Station T-44 I Site boundary,0.5 miles WSW of Station T-45 I Site boundary,0.5 miles WNW of Station T-46 I Site boundary,0.5 miles NW of Station T-47 I Site boundary,0.5 miles N of Station T-48 I Site boundary,0.5 miles NE of Station T-49 I Site boundary,0.5 miles NE of Station T-50 I Erie Industrial Park, Port Clinton, 4.5 miles SE of Station I

T-51 C on Siren Pole,5.5 miles SSE of Station T-52 I Miller Farm,3.7 miles S of Station T-53 I Nixon Farm,4.5 miles S of Station T-54 I Weis Farm,4.8 miles SW of Station T-55 I King Farm,4.5 miles W of Station T-60 I Site boundary,0.3 miles S of Station T-62 I Site boundary,1.0 mile SE of Station T-63 I Site boundary,1.1 miles ESE of Station T-65 I Site boundary,0.3 miles E of Station T-66 I Site boundary,0.3 miles ENE of Station T-67 I Site boundary,0.3 miles NNW of Station i T-68 I Site boundary,0.5 miles WNW of Station T-69 I Site boundary,0.4 miles W of Station 71 r i

!i Dovis-Besse Nuclear Power Station 1998 Annual Radiological Environmental operating Report !

Table 16: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location Location Description ,

T-71 I Site boundary,0.1 mile NNW of Station T-73 I Site boundary,0.1 mile WSW of Station T-74 I Site boundary,0.1 mile SSW of Station T-75 I Site boundary,0.2 mile SSE of Station T-76 I Site boundary,0.1 mile SE of Station T-80 QC Quality Control Site T-81 QC Quality Control Site T-82 QC Quality Control Site T-83 QC Quality Control Site T-84 QC Quality Control Site T-85 QC Quality Control Site T-86 QC Quality Control Site i

T-88 QC Quality Control Site ,

l T-87 QC Quality Control currently located in lead pig, DBAB annex J

)

T-89 QC Quality Control Site T-91 I State Route 2 and Rankie Road,2.5 miles SSE of Station i

1 T-92 I Locust Point Road,2.7 miles WNW of Station l

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 72 m

r-Divis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Oper: ting Report Table 16: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location Location Description T-100 C Ottawa County Highway Garage, Oak Harbor, 6.0 miles S of Station T-111 C Toussaint North Road,8.3 miles WSW of Station T-112 I Thompson Road,1.5 miles SSW of Station T-113 QC Quality Control Site T-114 QC Quality Control Site T-115 QC Quality Control Site T-116 QC Quality Control Site I i

l T-117 QC Quality Control Site T-118 QC Quality Control Site l T-il9 QC Quality Control Site T-120 QC Quality Control Site T-121 I State Route 19,2.0 miles W of Station T-122 I Duff Washa and Humphrey Road,1.7 miles W of Station T-123 I Zetzer Road,1.6 miles WSW of Station T-124 C Church and Walnut Street, Oak Harbor,6.5 miles SSW of Station l T-125 I Behlman and Bier Roads,4.4 miles SSW of Station T-126 I Camp Perry Western and Toussaint South Road, 3.7 miles S of Station T-127 I Camp Perry Western and Rymers Road,4.0 miles SSE of Station l

73 l

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Opcrating Report Table 16: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location Location Description T-128 I Erie Industrial Park, Port Clinton Road, 4.0 miles SE of Station T-142 I Site Boundary,0.8 miles SSE of Station T-150 I Humphrey and Hollywood Road,2.1 miles NW of Station T-151 I State Route 2 and Humphrey Road,1.8 miles WNW of Station T-153 I Leutz Road,1.4 miles SSW of Station T-154 I State Route 2,0.7 miles SW of Station T-155 C Fourth and Madison Streets, Port Clinton,9.5 miles SE of Station l

4 T-200 QC Quality Control Site T-201 I Sand Beach,1.1 miles NNW of Station T-202 I Sand Beach 0.8 miles NNW of Station T-203 I Sand Beach,0.7 miles N of Station T-204 I Sand Beach,0.7 miles N of Station T-205 I Sand Beach,0.5 miles NNE of Station ,

T-206 I Site Boundary,0.6 miles NW of Station T-207 I Site Boundary,0.5 miles N of Station T-208 I Site Boundary,0.5 miles NNE of Station.

I = indicator . C = control QC = quality control 74

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Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report L 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-l tions measured at indicator locations were compared with concentrations measured at control lo- >

l cations, in previous operational studies and in the preoperational surveillance program. These comparisons indicate normal concentrations of radioactivity in all environmental samples col-( lected in 1998. Davis-Besse's operation in 1998 had no adverse impact on the residents and envi-ronment surrounding the station. The results of the sample analyses performed during the period 1 of January through December 1998 are summarized in Appendix D of this report.

i l

l l

l 78 l l

. Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report t

l 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).

l 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 Insta'-

! lations," DOE /EP-0023, Department of Energy, Washington, D.C. (July 1981).

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

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

7. " Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion 'As Low As Reasonably Achievable

• for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents," Code of Federal Regulations, Title 10 Energy, Part 50 " Domestic Licensing of Production and Utilization Facilities," Appendix I(1988).

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

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

I

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

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).

I1. Regulatory Guide 4.1," Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," US NRC (April 1975).

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

I I

L 79 l

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report

13. Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Nonnal 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. Regulatory Guide 0837, "NRC TLD Direct Radiation Monitoring Network," US NRC (1997).

~

i

16. " Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, l

- Part 20 (1993).

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

i 1

18. Teledyne Isotopes Midwest Laboratory, " Final Monthly Progress Report to Toledo Edison Company", (1991-1998).

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

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

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

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

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

24. Toledo Edison Company, " Radiological Environmental Monitoring Program," DP-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 Enhancement Sampling," DB-HP-10101.

80

y Davis-Besse Nuclear Power Stition 1998 Annual Radiological Environmental Operating Report i

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

I

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

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

)

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

i 1 l I 4

81

Davis Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31,1998 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 and Centerior Energy minimize health risk and environmental detriment and ensure that doses are maintained well be-low regulatory limits.

Sources of Radioactivity Released During the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in i the primary coolant water. The three types of radioactive material 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 airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologically and chemically nonreactive.

82

f' Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report l

L j l

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

l Iodine and Particulates Annual releases of radioisotopes of iodine, and those particulates with half-lives greater than 8 days, in gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing sys-

! tems, minimize their discharge. The predominant radiciodine released is iodine-131 with a half-life of approximately eight days. The main contribution of radioactive iodine to human dose is to the thyroid gland, where the body concentrates iodine.

The principal radioactive particulates released are fission products (e.g., cesium-134 and cesium-137) and activation products (e.g., cobalt-58 and cobalt-60). Radioactive cesium and cobalt con- I 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 ccatrolled to ensure radioactivity released to the environment is minimal and does not exceed regulatory 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 environmental 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 i

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report 1

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 l Monitoring Program coristantly sample the air in the surrounding environment. Frequent sam-pies of other environmental media, such as water and vegetation, are also taken to determine if I

buildup of deposited radioactive material has occurred in the area.

Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to ra-dioactive material. The major pathways of concern are those which could cause the highest cal-culated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the envi-ronment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An An-nual average on the water flow, wind speed , and wind direction are used to evaluate how the ia-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 internal exposure pathways considered are shown in Figure 30. The release of radioactive gaseous effluents involves pathways such as external whole body exposure, deposi-tion of radioactive material on plants, deposition on soil, inhalation by animals destined for hu-man consumption, and inhalation by humans. The release of radioactive material in liquid efflu-ents involves pathways such as drinking water, fish consumption, and direct exposure from the i lake at the shoreline and while swimming. l l

1 84

Davis-Basse Nuclear Pow r Station 1998 Annud Radiological Environmentd Operating Report DiMed By Atmo@ers Airborne hicases

%, L l Nh E'3""

.f.?!W i

.. h.yN. I i ,

?, '9 d e,,,,,,, p i my man ll, l(l 9P coessnes oeuded Sylahs Wy Anisists V .

Wegetaten By Man

~. RSH From seu

7

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Shorghne LAKE

h. >

Figure 30: The exposure pathways shown here, are monitored through the Radiological Environmental Monitoring Program (REMP), and are considered when calculating doses to the public.

Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure pathway which will provide, for a specific ra-dionuclide, 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 l specific organ. The organ receiving the greatest fraction of the dose is called the critical organ.

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

When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium collects in bone tissue.

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

85

l Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report 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-lated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the average weather conditions at the time of the release, the locations of expo-l 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- l tors). These calculations produce a conservative estimation of the dose, j Results ,

The Radioactive Efnuent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Station during the period from January 1,1998 through December 31, l 1998.

. Summation of the quantities of radioactive material released in gaseous and liquid effluents j

e Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites e A listing of all radioactive effluent monitoring instrumentation required by the Offsite Dose Calculation Manual, but which were inoperable for more than 30 days l During this reporting period, the estimated maximum individual offsite dose due to radioactivity released in effluent was:

Liquid Effluents:

e 1.30E-01 mrem, whole body e 1.68E-01 mrem, GI-LLI Gaseous Effluents:

Noble Gas:

e 3.54E-05 mrad, whole body e 1.19E-04 mrad, skin Iodine - 131, Tritium, and Particulates with Half-lives greater than 8 Days:

l e 8.23E-04 mrem, whole body l- e 1.16E-03 mrem, thyroid These doses are an extremely small fraction of the limits set by the NRC in the Davis-Besse ODCM.

86 l

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F .)

[ Davis Besse Nuclear Power Station 1998 Annual Radiological EnvironmIntal Operating Report .

L i Additional normal release pathways from the secondary system exist. For gaseous effluents, l i

l 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- I sins. Releases via these pathways are included in the normal release tables in this report. I l

i t i 1

Regulatory Limits- i Gaseous Effluents j 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 d following:

Noble gases:  !

' l

. 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.)

e 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:

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

In accordance with'10CFR50, Appendix I, Sec. IIB.1, air dose duc to radioactivity released in ~

_ gaseous effluents to areas at and beyond the site boundary shall be limited to the following. ,

l

• 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 I, Sec. IIC, dose to a member of the pub lic from Iodine- ,

131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gase- l 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.  ;

i Liquid Effluents In accordance with 10CFR50, Appendix I, Sec IIA, the dose or dose commitment to a member of l 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.

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Davis Bisse Nuclear Power staticri 1998 Annual Radiological Environmental Operating Report 1

Effluent Concentration Limits '

The Effluent Concentration Limits (ECs) for liquid and gaseous effluents at and beyond the site

, boundary are listed in 10CFR20, Appendix B, Table II, 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 in 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 (E) for gaseous effluents as described in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radio-activity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable.

Measurements of Total Activity Fission and Activation Gases:

These gases, excluding tritium, are collected in 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 counted by liquid scintillation.

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

Particulates  !

I 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 marinelli beaker and counted on a germanium detector. Quan-l 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 I

'a liquid scintillation counting system.

l l

l 88

p, L Davis-Besse Nucitar Power Station 1998 Annual Radiological Environmental Operating Report L Batch Releases L

Liquid from 1/1/98 through 12/31/98

1. Number of batch releases: 88

2. Total time period for the batch releases: 148.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />

3. Maximum time period for a batch release: 191 minutes

4. Minimum time period for a batch release: 62 minutes

5. Average time period for a batch release: 101 minutes Gaseous from 1/1/98 through 12/31/98

1. Number of batch releases: 13

2. Total time period for the batch releases: 156.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

3. Maximum time period for a batch release: 1810 minutes

4. Minimum time period for a batch release: 141 minutes

5. Average time period for batch release: 721 minutes Abnonnal Releases

1. Reactor trip on 6/24/98, entered Emergency Plan due to a tornado sighting. - Vented through Atmospheric Vent Valves (AVV) and ran Auxiliary Feed Pump (AFP) from 6/24/98 - 6/28/98 after a tornado hit the site. Total curies of Tritium released was 5.40E-03 during this time period.

2. Reactor trip on 10/14/98, which was initiated on a low Component Cooling Water

~ (CCW) surge tank alarm. Vented through AVV because of loss of CCW to the Reactor Coolant Pump (RCP). Also, one Main Steam Safety Valve (MSSV) stuck open. The total activity released was 8.90E-03 curies of Tritium.

3. Reactor trip on 11/13/98 due to ARTS testing. Steam was vented to atmosphere through the MSSV. Total activity released was 7.00E-4 curies of Tritium.

4. Auxiliary Steam 235 pound relieflifted for 5 seconds in May and 3 minutes in October. Total activity released was 2.30E-04 curies of Tritium.

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 1,1998 through December 31,1998.

PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1,1998 - December 31,1998 (Raseous)

Noble gases (gamma) 6.47E-05 mrad 10 mrad 6.47E-04 Noble gases (beta) 2.32E-04 mrad 20 mrad 1.16E-03 I-131. tritium and particulates 1.17E-03 mrem 15 mrem 7.80E-03 Report Period: January 1,1998 - December 31,1998 (liquid)

Total body 1.15E-01 mrem 3 mrem 3.83E+00 Organ 1.57E-01 mrem 10 mrem 1.57E+00 89

I.

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Sources ofInput Data e Water Usage: Survey of Water Treatment Plants (DSR-95-00347)

= 0-50 mile meat, milk, vegetable production, and population data: 1982 Annual En-vironmental Operating Report entitled, " Evaluation of Compliance with Appendix I to 10CFR50: Updated Population, Agricultural, Meat - Animal, and Milk Pro-duction Data Tables for 1982." This evaluation was based on the 1980 census; the Agricultural Ministry of Ontario 1980 report entitled " Agricultural Statistics and Livestock Marketing Account,1980"; the Agricultural Ministry of Ontario 1980 report entitled " Agricultural Statistics for Ontario - 1980 Publication 21,1980"; the {

Michigan Department of Agriculture, July,1981 report entitled " Michigan Agri-cultural Statistics,1981"; the Ohio Crop Reporting Service,1981 report entitled, l

" Ohio Agricultural Statistics,1981."

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

• Location of the nearest individuals and pathways by sector out to 5 miles, see Lanci 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 CFR190 standards.)

The Wellness Center located inside DBNPS controlled area is .co accessible to members of the public. Considering the frequency and duration of the visits, the resultant dose would be a small fraction of the calculated maximum site boundary dose. For purposes of assessing the dose to members of the public in accordance with ODCM Section 7.2, the following exposure assump-tions 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 /> (1 hr/ day,5 day / week, 50 wk/yr)

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

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

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

90

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report The equations in the ODCM may be used for calculating the potential dose to a member of the public for activities inside the site boundary. Based on these assumptions, this dose would be at least a factor of 35 less than the maximum site boundary air dose as calculated in the ODCM.

There are no areas onsite accessible to the public where exposure to liquid effluents could occur.

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

Inoperable Radioactive Effluent Monitoring Equipment I The following radioactive effluent monitoring equipment required to be operable by ODCM Section 2.1 and 3.1 was inoperable for more than 30 days during this reporting period.

• Total Dilution Flow, computer point F201, was inoperable during most of 1998 because of an ODCM Test requirement not being met. The ODCM required that a quarterly channel func-tional test and channel calibration every 18 months. The flow sensors FE2729, FE2799, and FE3611 are part of the equipment string and require the same testing. These flow elements have not been calibrated since the plant started operation. This problem has been documented on Potential Condition Adverse to Quality Report (PCAQR) 1998-1455. The flow elements have been successfully tested since this discovery.

Changes to the ODCM and PCP l There was one alteration to the OCDM, Revision 11.0 Change 1. The PCP had no changes.

l' l

L l

l 91

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report  !

Table 17 i Gaseous Effluents - Summation of All Releases 1 Type Unit 1st Qtr 2nd Qtr 3rd Qtr 4thQtr Est. Total 1998 1998 1998 1998  % Error Fission and Activation Gases Total Release Ci 4.51E-01 3.64E+00 3.36E-01 4.07E-03 2.5E+0!

Average Release Rate for Period' pCi/sec 5.72E-02 4.62E-01 4.26E-02 5.16E-04 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section l

Iodines

]'

Total lodines Ci 2.98E-07 2.29E-05 7.21E-06 5.27E-06 2.5 E+01 Average Release Rate for Period' Ci/sec 3.78E-08 2.90E-06 9.14E-07 6.68E-07 Percent of ODCM Limits See SupplementalInformation in ODCM Release LimitsSection I

Particulates  !

Particulates with half-lives greater Ci LLD 1.56E-05 LLD LLD 2.5E+01 than 8 days Average Release Rate for Period' pCi/sec LLD 1.98 E-M LLD LLD Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section l l

Tritium Total Release Ci 5.24E+00 1.41E+01 8.79E+00 7.32E+00 2.5E+01 Average Release Rate for Period' Ci/sec 6.64E-01 1.80E+00 1.12E+00 9.28E-01 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section

• The average release rate is taken over the entire quarter. It is NOT averaged over the time peri (x! of the releases.

92

!L Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 18 Gaseous Effluents - Ground Level Releases Batch Mode" ist Qtr 2ndQtr 3rdQtr 4th Qtr Nuclide Unit 1998 1998 1998 1998 l

Fission Gases Ci Kr-85 LLD' LLD6 LLDb LLD6 l Kr-85m LLD LLD LLD LLD }

Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xc-133 LLD LLD LLD LLD Xe-135 LLD LLD LLD LLD Xe-135m LLD LLD LLD LLD Xe-138 LLQ LLQ LLQ LLQ l

Total f( r Period: N/A N/A N/A N/A l Iodines Ci I-131 LLD LLD LLD LLD I-132 LLD LLD LLD LLD I-133 LLD LLD LLD LLD l-135 LLQ LLQ LLQ LLQ ,

II Total for Period: N/A N/A N/A N/A i I

l Particulates and Tritium Ci H-3 5.69E-03 7.50E-03 2.85E-03 1.44E-02 St-89 LLD LLD LLD LLD f Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD LLD LLD j Ba-140 LLD LLD LLD LLD i Co-58 LLD LLD LLD LLD Total for Period: 5.69E-03 7.50E-03 2.85E-03 1.44E-02 93

I l Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report  !

Table 18 (Continued) i Gaseous Effluents - Ground Level Releases Continuous Mode

• lst Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1998 1998 1998 1998 .

1 Fission Gases Ci i

Kr-85 LLD 6 M" RD 6 LLD 6 Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xc-135 LLD LLD LLD LLD Xe-135m LLD LLD LLD LLD Xe-138 RQ RQ QQ QQ Total for Period: N/A N/A N/A N/A lodines Ci 1-131 LLD LLD LLD LLD I133 LLD LLD LLD LLD 1 135 RQ RQ RQ QQ Total for Period: N/A N/A N/A N/A Particulates and Tritium Ci H-3 8.23E-02 1.67E-02 3.09E-02 5.41 E-02 Sr-89 LLD LLD LLD LLD Sr90 LLD LLD LLD LLD Cs 134 LLD LLD LLD LLD Cs-137 LLD LLD LLD LLD Ba140 RQ RQ QQ RQ Total tor Period: 8.23E-02 1.67E-02 3.09E-02 5.41 E-02 i

l 1

94

Divis Besso Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 18 (Continued)

Gaseous Effluents - Ground Level Releases Continuous and Batch Mode Ar 41: <2.2E-08 Ci/ml Kr 85: <6.2E-06 Ci/mi Kr-85m: <2.0E-08 Ci/mi Kr-87: <3.4E-08 Ci/ml Kr-88: <4.0E-08 Ci/ml Xe-131m: <9.0E-08 Ci/ml Xe-133: <4.6E-08 Ci/ml Xe-133m: < l .6E-07 pCi/ml Xe-135: < l .9E-08 pCi/mi Xe-135m: <4.0E-07 pCi/ml Xe-138: <2.5E-07 Ci/mi 1-131: < l.0E-07 Ci/ml I133: <2. l E-08 Ci/ml 1135: <2.lE-08 Ci/ml Mn-54 <2.0E-08 Ci/ml Fe 59: <4.0E-08 pCi/ml Co-58: <3.08 08 Ci/ml Co-60: <2.0E-08 Ci/mi Zn-65: <4.0E-08 pCi/ml Mo-99: <2.0E-07 Ci/ml Cs-134: <2.lE-08 Ci/ml .

Cs 137: <3.0E-08 Ci/ml Ce-141: <3.0E-08 pCi/ml Ce-144: < l .2E-07 Ci/ml Ba 140: <7.0E-08 Ci/ml La 140: <3.0E-08 Ci/mi Sr-89: <5.0E-08 Ci/ml Sr-90: <6.0E-09 Ci/ml a Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, and Auxiliary Boiler Outage Release i are listed as batch releases, 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

r q

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 19 Gaseous Effluents - Mixed Mode Releases e

7 -

Batch Mode Ist Qtr 2ndQtr 3rd Qtr 4th Qtr Nuclide Unit 1998 1998 1998 1998 Fission Gases Ar-41 Ci LLD" 9.17E-03 1.37E-02 LLD' Kr-85 Ci 3.04E-04 LLD b RD 6 RD Kr-85m Ci LLD 1.94E-04 3.15E-04 LLD Kr-87 Ci LLD LLD LLD LLD Kr-88 Ci LLD LLD LLD LLD Xe-133 Ci 2.21E-03 2.51E+00 3.06E-01 4.07E-03 Xe-133m Ci 1.42E-05 2.54E-02 1.97E-03 LLD Xe-135 Ci 4.25E-06 4.05E-02 1.37E-02 LLD Xc-135m Ci L1 D LLD LLD LLD Xe-138 Ci LLD LLD LLD LLD Xe-131m Ci LLD L.LQ LLD 2 49E-05 Total for Period: 2.56E-03 2.58E-+00 3.36E-01 4.07E-03

• Iodines I-131 Ci LLD LLD LLD LLD I-132 Ci LLD LLD LLD LLD I-133 Ci LLD LLD LLD LLD I-135 Ci LLD LLD LLD LLD Total for Period: Ci LLD LLD LLD LLD

• Particulates 113 Ci 3.CE 04 3.67E-02 1.29E-01 1.18E-03 Total for Perbd: Ci 3.89E-04 3.67E-02 1.29E-01 1.18E-03

• Release of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Station Vent) 96

Davis-Besse Nuclear Pow:r Station 1998 Annual Radiological Environmental Operating Report i

Table 19 (Continued)

Gaseous Effluents - Mixed Mode Releases Continuous Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1998 1998 1998 1998 Fission Gases Ar-41 Ci LLD' LLD' LLD' LLD' Kr-85 Ci LLD LLD LLD LLD Kr-85m Ci LLD LLD LLD LLD Kr-87 Ci LLD LLD LLD LLD e Kr-88 Ci LLD LLD LLD LLD Xe-133 Ci 4.49E-01 1.06E+00 LLD LLD Xe-133m Ci LLD LLD LLD LLD Xe-135 Ci LLD LLD LLD LLD Xc-135m Ci LLD LLD LLD LLD Xe-138 Ci RQ RQ RQ RQ Total for Period: 4.49E-01 1.06E+00 LLD LLD Iodines >

I-131 Ci 2.98E-07 2.29E-05 7.2 ] E-06 5.27E.06 1-133 Ci 4.27E-06 6.00E-06 4.04E-06 LLD I-135 Ci LLD LLD LLD LLD I-132 Ci RD 5.03E-05 RQ RQ Total for Period: 4.57E-06 7.92E-05 1.13E-05 5.27E-06 Particulates and Tritium H-3 . Ci 5.15E+00 1.41 E+01 8.63E+00 7.25E+00 Sr-896 Ci LLD LLD LLD LLD Sr-906

• Ci LLD LLD LLD LLD Cs-134 Ci LLD 1.49E-% LLD LLD Cs-137 Ci LLD 5.53E-06 LLD LLD Ba-140 Ci LLD LLD LLD LLD Co-58 Ci LLD 8.53E-06 LLD LLD La-140 Ci RQ RQ RQ RQ Total for Period: 5.15E+00 1.41 E+01 8.63E+00 7.25E+00 t

97

l. . .. . .

~

5:

1

j. Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report i

l Table 19 (Continued) l Gaseous Effluents - Mixed Mode Releases Continuous Mode". Batch Mode

• Ar-41 <2.9E-08 Ci/mi Kr-87 <4.5E-06 pCi/ml Kr-85 <3.3E-06 Kr-88. <6.6E-06 Ci/ml

. Kr-85m <l .3E-08,_ pCi/ml pCi/mi - Xe-135 <l .4E-05 Ci/ml Kr-87 <6.0E-08 Ci/ml - Xe-135m <2. l E-06 pCi/ml Kr-88 -. <6.0E-08 Ci/ml Xe-138 <2.8 E-05 pCi/ml Xe-131m . <4.4E-07 Ci/mi Ar-41 < l .8E-06 pCi/ml Xe-133m - <7.2E-08 Ci/ml Kr-85 <l .2E-06 pCi/ml Xe 135 <l.lE-08 ' Ci/mi Xe-133 - - <2.4E-06 pCi/ml Xe-135m . <5.9E-06 Ci/ml Xe-133m <1.0E-05 pCi/mi Xe-138 ' <2.0E-05 Ci/ml I135' <3.9E-10 Ci/mi Mn-54' <2.6E-14 Ci/ml Fe-59' <3.0E-14 Ci/ml Co-58*. <3.0E-14 pCi/mi Co-60' J <2.5E-14 pCi/mi Zn-65' <l.0E-13 ' pCi/mi Mo-99' <l .8E-14 pCi/ml Cs-134' <l.6E-14 pCi/ml Cs 137' <l.3E-14 pCi/mi Ce-141". . <l.2E-13 pCi/mi Ce-144' <l .2E pCi/ml

- Ba-140'

< 4.0E-14 Ci/ml ,

La-140' <l.0E 14 pCi/ml St-896 ' <9.3E-16 pCi/ml 6

Sr-90 # <3. l E-16 Ci/ml a These radionuclides were not identified in every quarter in concentrations above the

]

lower limit of detection (LLD). The largest LLD value is listed. '

b Quarterly composite sample for continuous mode, c Analysis not required for batch release.

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i Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report i

Table 21 Liquid Effluents - Nuclides Released Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1998 1998 1998 1998 Fission and Activation Products l Co-58 Ci 8.34E-06 8.92E-02 3.79E-03 1.65E-03 Co-60 Ci 8.15E-04 1.22E-02 3.24E-04 1.20E-03 Ag-110m Ci 3.63E-04 1.01E-02 2.30E-04 1.04E-03 l Sb-125 Ci 2.53E-03 5.47E-03 7.26E-03 2.31E-03 Cs-134 Ci LLD 4.32E-04 2.00E-05 2.33E-04 I Cs-137 Ci 1.36E-05 1.30E-03 1.24E-04 6.77E-04 I Sr-89a. b Ci LLD LLD LLD LLD Sr-90a. b Ci RD RD E @

Fe-55 Ci LLD 8.91E-02 2.67E-03 3.74E-03 Cr-51 Ci 2.79E-05 7.95E-03 1.02E-04 LLD ,

I-131 Ci 6.42E-06 5.72E-06 LLD 3.62E-06 I-132 Ci LLD 4.26E-04 LLD LLD I-133 Ci 2.99E-06 3.88E-06 LLD LLD Te-132 Ci LLD 3.76E-04 LLD LLD Tc-99m Ci 2.99E-07 8.08E-05 LLD LLD Sb-124 Ci LLD 1.96E-05 LLD LLD Sn-113 Ci LLD 1.81E-03 6.27E-05 1.79E-05 Ru-103 Ci LLD 6.17E-04 LLD LLD Mn-54 Ci 1.94E-06 2.24E-04 1.13E-06 2.28E-05 Np-239 Ci 2.21E-05 LLD 9.20E-05 LLD Co-57 Ci 1.14E-06 3.16E-04 2.60E-05 1.57E-05 Nb-95 Ci LLD 1.74E-03 LLD 4.22E-05 Zr-95 Ci LLD 1.16E-03 5.24E-06 3.91 E-05 Se-75 Ci LLD LLD LLD 9.02E-07 Fe Ci LLD 1.22E-02 4.39E-05 LLD Zn-65 Ci LLD 3.76E-06 LLD LLD.

Ce-144 Ci LLD 4.46E-05 LLD LLD Na-24 Ci LLD LLD LLD LLD Zr-97 Ci 9.86E-06 1.01E-04 6.48E-06 3.53E-05 Ce-141 Ci LLD 1.21E-04 LLD LLD Nb-97 Ci 2.83E-06 7.09E-06 2.95E-06 LLD La-140 Ci LLD 5.88E-04 LLD LLD Ba-140 Ci LLD 5.13E-05 LLD LLD Ru-106 Ci LLD LLD LLD 3.16E-05 Total for Period: Ci 3.81E-03 2.36E-01 1.48E-02 1.11E-02 100

r-i-Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Rcport .

Table 21 (continued)

Liquid Effluents - Nuclides Released Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4thQtr Nuclide Unit 1998 1998 1998 1998 Tritium Ci 5.39E+01 2.38E+02 7.95E+01 3.06E+02 Dissolved and Entrained Gases i

Kr-85m Ci LLD* LLD* LLD* LLD*

Kr-85 Ci LLD LLD LLD LLD Xe-131m Ci LLD LLD LLD LLD Xe-133 Ci 9.00E-05 1.14E-03 LLD 1.95E-04 Xe-135 Ci 6.08E-07 1.10E-06 LLD LLD Xe-133m Ci 5.75E-06 LLD LLD LLD Total for Period: Ci 9.64E-05 1.14E-03 LLD 1.95E-04 l

i I

1 1

( 1 l

l s

101

)

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - Nuclides Released l

Continuous Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1998 1998 1998 1998 Fission and Activation Products Cr-51 Ci LLD* LLD* LLD' LLD*

Fe-59 Ci LLD LLD LLD LLD Co-58 Ci LLD LLD LLD LLD Co-60 Ci LLD LLD LLD LLD Zn-65 Ci LLD LLD LLD LLD Sr-89a.b Ci LLD LLD LLD LLD Sr-90a.b Ci LLD LLD LLD LLD Nb-95 Ci LLD LLD LLD LLD Zr-95 Ci LLD LLD LLD LLD Mo-99 Ci LLD LLD LLD LLD Tc-99m Ci LLD LLD LLD LLD I-131 Ci LLD LLD LLD LLD Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci LLD LLD LLD LLD Ba-140/La-140 Ci LLD LLD LLD LLD l Ce-141 Ci LLD LLD LLD LLD i Total for Period: N/A N/A N/A N/A Tritium Ci 3.33E-01 LLD 3.71E-02 2.20E-01 Dissolved a::d Entrained Gases i Kr-85 Ci LLD LLD LLD LLD Xe-131m Ci LLD LLD LLD LLD Xe-133 Ci LLD LLD LLD LLD Xe-133m Ci LLD LLD LLD LLD Xe-135 Ci LLD LLD LLD LLD Total for Period: Ci N/A N/A N/A N/A '

l i

i 102 l l

1

[  !

l  ; Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report

!- J k

Table 21 (continued)

Liquid Effluents - Nuclides Released

• l l

Na-24 <2.0E-08 Ci/ml Sb-124 <l.0E-08 Ci/ml

! Cr-51 <l .7E-07 Ci/ml Sb-125 < l .7E-08 Ci/ml l Mn-54 <2.lE-08 Ci/mi Te-132 < l .8E-08 Ci/mi b

i Fe-55 <7,0E-07 Ci/ml Ce-141 <3.0E-08 Ci/ml L Fe-59 <4.2E-08 Ci/ml Ce-144 <l .7E-07 Ci/ml l

Co-57 < l .6E-08 Ci/ml Cs-134 <2.lE-08 Ci/ml j l Co-58 <l .9E-08 pCi/ml Ce-136 <2.8E-08 Ci/ml  !

Co-60 <2.5E-08 Ci/ml Cs-137 <2.7E-08 pCi/ml Zn-65 <5.2E-08 pCi/ml Ba-140 <7.0E-08 Ci/ml Se-75 <2.4E-08 Ci/ml La-140 <3.0E-08 Ci/ml b

Sr-89 <3.0E-08 Ci/ml Np-239 < l .2E-07 Ci/ml b

Sr-90 <8.0E-09 Ci/ml I-131 <2.5E-08 Ci/mi Zr-95 <4.0E-08 pCi/ml - I-132 <l.0E-08 Ci/ml Zr-97 <2.5E-08 Ci/ml I-133 <2. l E-08 Ci/ml Nb-95 <2. l E-08 Ci/ml I-135 < l .7E-07 Ci/ml l l Mo-99 < l .6E-07 Ci/ml Kr-85 <6.2E-06 Ci/ml I Tc-99m _ < l .8 E-08 Ci/ml Xe-131 <7.7E-07 Ci/ml Ru-103 <2.2E-08 pCi/ml Xe-133 <4.6E-08 Ci/ml Ag-l 10m <2.5E-08 Ci/ml Xe-133m < l .6E-07 Ci/ml l Sn-113 <2.8E-08 Ci/ml Xe-135 < l .9E-08 Ci/ml l'

• 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 i both batch and continuous modes due to identical sample and analysis methods.

l l b

l Quarterly composite sample l

l l

103

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 22 Solid Waste and Irradiated Fuel Shipments A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOS AL (Not irradiated fuel) 12-month Est. Total

1. Type of Waste Unit Period Error, %

a. Spent resins, filter sludges, m' 2.53E+01 2.5E+01 J

evaporator bottoms, etc. Ci 1.62E+00 2.5E+01 '

b. Dry compressible waste, m' l.68E+01 2.5E+01 contaminated equip., etc. Ci 2.81E+00 2.5E+01

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

d. Others: dewatered primary m 3.07E-01 2.5E+01 j system cartridge filters Ci 1.94E-01 2.5E+01 l

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

Est. Total Type Percent (%) Error. %

ss

a. Spent Resins Fe 1.00E+01 2.50E+01 Coss 2.61E+01 2.50E+01 Co* 1.07E+01 2.50E+01 Ni 63 2.69E+01 2.50E+01 i25 Sb 8.90E+00 2.50E+01 Cs'34 1.70E+00 2.50E+01 Cs'37 5.40E+00 2.50E+01 l 4

C 5.80E+00 2.50E+01

. b. Dry compressible waste, contaminated ss equipment, etc. Fe 1.46E+01 2.50E+01 Co* 9.20E+00 2.50E+01 I Ni 63 9.50E+00 2.50E+01  !

Cs'34 4.00E+00 2.50E+01 Cs'37 1.59E+01 2.50E+01 i 38 Co 3.96E+01 2.50E+01 Nb 95 4.70E+00 2.50E+01

c. None ,

ss

d. Cartridge filters Fe 1.28E+00 2.50E+01 ss Co 2.10E+01 2.50E+01 N 63 3.35E+01 2.50E+01 Cs'34 1.90E+00 2.50E+01 Cs'37 6.50E+00 2.50E+01 6

Co 1.28E+01 2.50E+01 C'4 7.00E+00 2.50E+01 125 Sb 1.50E+00 2.50E+01 104

Divis-Besse Nuclear Pow:r Station 1998. Annual Radiological Environmental Operating Report 1i Table 22 (continued)

Solid Waste and Irradiated Fuel Shipments

3. Solid Waste Disposition Number of Shipments: 2 Mode of Transportation: Truck Destination: Barnwell, SC 3

Type of Container (Container Volume): 2 resin / filter media HIC ( 5.72 m ) buried Number of Shipments: 3 Mode of Transportation: Truck Destination: GTS Duratek, Oak Ridge, TN for processing then disposal F Envirocare of Utah or Barnwell S.C.

Type of Container (Container Volume): Metal boxes 3

Volume shipped for processing 169.96m 3

Volume disposed 6.7m Number of Shipments: 2 )

Mode of Transportation: Truck Destination: ATG Inc. Richland Washington for processing then disposal at Envirocare of Utah Type of Container (Container Volume): Steel liner 3

Volume shipped for processing 27.39m 3

Volume disposed 14m Number of Shipments: 1 Mode of Transportation: Truck Destination: Frank W. Hake, Inc. Memphis Tenn. for processing then disposal at Envirocare of Utah Type of Container (Container Volume): Metal boxes 3

Volume shipped for processing 21.75m 3

Volume disposed *5.43m Number of Shipments: 1 Mode of Transportation: Truck Destination: Manufacturing Sciences Corp. Oak Ridge Tenn. for processing then disposal at Barnwell S.C. ,

Type of Container (Container Volume): Metal box  !

Volume shipped for processing 4.65m 3 I Volume disposed

• l.42m 3

• Volume estimated, as processing was not complete as of 12/31/98 B. IRRADIATED FUEL SHIPMENTS l There were no shipments of irradiated fuel.

105 l

Davis-Besse Nuclear Powcr Station 1998 Annual Radiological Environmental Operating Report i Table 23 Doses Due to Gaseous Releases j For January through December 1998 f

Maximum Individual Dose Due to I-131, H-3 and Particulates with Half Lives Greater than 8 days.

Whole Body Dose 8.30E-04 mrem Significant Organ Dose 1.17E-03 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 6.47E-05 mrad Skin Dose 2.32E-04 mrad Population Dose Due to I 131, H 3 and Particulates with Half-Lives Greater than 8 days.

l Total Integrated Population Dose 8.82E-03 person-rem l Average Dose to Individual in Population 4.05E-06 mrem

]

l Population Dose Due to Noble Gas Total Integrated Population Dose 1.25E-04 person-rem j Average Dose to Individual in Population 5.73E-08 mrem l

l l

106

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 24 Doses Due to Liquid Releases for January through December 1998 Maximum Individual Whole Body Dose 1.15E-01 mrem Maximum Individual Significant Organ Dose 1.57E-01 mrem Population Dose Total Integrated Population Dose 2.08E+00 person-rem Average Dose to Individual 9.52E-04 mrem I

l l

l 4

107

\ l

! Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 25 l Annual Dose to the Most Exposed Member of the Public 1998 ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem) (mrem) LIMIT Whole Body Dose l Noble Gas 6.47E-05 Iodine, Tritium, Particulates 8.30E-04 Liquid 1.15E-01 Total Whole Body Dose 1.16E-01 25 4.64E-01 Thyroid Dose l Iodine, Tritium, Particulates 1.17E-03 75 1.56E-03 1

l Skin Dose Noble Gas 2.32E-04 25 9.28E-04 Significant Organ Dose (Liver) 1.57E-01 25 6.28E-01 l

Meteorological Data Meteorological data on 3% inch microdisk for January through December 31,1998, has been l

submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, l Washington, D.C. 20555.

I 1

l 108 L-

Divis-Besse Nuclear Power Station 1998 Annual Radiological Envirormental Operating Report l

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 j Use Census Data. The Land Use Census identifies gaseous pathways by which radioactive mate- i rial may reach the general population around Davis-Besse. The information gathered during the l 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.  !

e Ground Exposure Pathway - External exposure from radionuclides deposited on the ground

. Plume Exposure Pathway - External exposure directly from a plume or cloud of l radioactive material. l e Vegetation Pathway - Internal exposure as a result of eating vegetables, fruit, etc. j which have a build up of deposited radioactive material or which have absorbed ra-  !

dionuclides through the soil.  !

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

l t

Methodology i i

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

The surveillance portion of the 1998 Land Use Census was performed during the month of July.  !

In order to gather as much information as possible, the locations of residences, dairy cows, dairy

! goats, as.d vegetable gardens were recorded. The residences, vegetable gardens, and milk ani- ,

, mais are used in the dose assessment program. The vegetable gardens must be at least 500 l

( square feet in size, with at least 20% of the vegetables being green leafy plants (such as lettuce, ]

cabbage, and kale).

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.

l 109 V

I b .

m

)

Davis-Besse Nuclear Power Station 1998 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 station vent at Davis-Besse.

Results

)

The following changes in the pathways were recorded in the 1998 census:

e- SW Sector - The garden at 5140 meters was replaced by a garden at 4920 meters.

• WSW Sector - The garden at 7010 meters was replaced with a garden at 4600 meters.

. NW - The garden at 2320 meters was removed.

The critical receptor identified by the 1998 Land Use Census is a garden in the W sector at 1640 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 infomiation on pathways, critical age group, atmospheric dispersion (X/Q) and deposition (D/Q) parameters for each sector. This information is used to update the Offsite i Dose Calculation Manual (ODCM). The ODCM describes the methodology and parameters used I 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, l

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n Davis-Bisse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report l

Table 26 Closest Exposure Pathways PreSent in 1998 l

Sector Distance from Station (meters) Closest Pathways N 880 Inhalation Ground Exposure Plume Exposure NNE 870 Inhalation i Ground Exposure Plume Exposure l NE 900 Inhalation Ground Exposure Plume Exposure ENE, E, ESE, SE N/A Located over Lake Erie SSE 2010 Inhalation Ground Exposure Plume Exposure SSE 2820 Vegetation S 1070 Inhalation Ground Exposure Plume Exposure 1

l S 3440 Vegetation SSW 980 Inhalation Ground Exposure Plume Exposure SSW 3450 Vegetation SW 1050 Inhalation Ground Exposure Plume Exposure

! SW*

• i 4920 Vegetation f ** Changes since 1997 l

l 112

r.

Davis Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report

- i j

i Table 26 (continued)

Closest Exposure Pathways Present in 1998 Sector Distance from Station (meters) Closest Pathways i WSW 1620 Inhalation l Ground Exposure i l'lume Exposure WSW*

• 4600 Vegetation W 980 Inhalation Ground Exposure Plume Exposure W 1640 Vegetation WNW 1730 Inhalation Ground Exposure Plume Exposure WNW 3650 Vegetation I NW 1450 Inhalation Ground Exposure Plume Exposure NNW 1210 inhalation Ground Exposure ,

Plume Exposure I

• • Changes since 1997 113

Divis-Besse Nuclear Power Station 198 Annual Radiological Environmental Operating Report Table 27 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q)

Parameters SECTOR METERS CRITICAL AGE X/Q D/Q PATHWAY GROUP (SEC/M') (M)

N 880 Inhalation Child 9.15E-07 8.40E-09 NNE 870 Inhalation Child 1.27E-06 1.47E-08 NE 900 Inhalation Child 1.26E-06 1.58E-08

- ENE* --- --- --- --- ---

E* --- --- --- --- ---

ESE* --- --- --- I- ---

SE* --- --- --- --- ---

SSE 2820 Vegetation Child 7.02E-08 8.36E-10 S 3440 Vegetation Child 4.39E-08 4.55E-10 SSW 3450 Vegetation Child 3.98E-08 5.llE-10 SW** 4920 Vegetation Child 4.04E-08 3.74E-10 WSW*

• 4600 Vegetation Child 5.32E-08 4.61 E-10 ,

1 W 1640 Vegetation Child 2.69E-07 4.21E-09 l WNW 3650 Vegetation Child 5.67E-08 4.28E-10 NW*

• 1450 Inhalation Child 1.52E-07 1.42E-09 NNW 1210 Inhalation Child 2.70E-07 1.92E-09

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

• • Changes since 1997 114

i Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report i Non-Radiological Environmental Programs  ;

i Meteorological Monitoring a The Meteorological Monitoring Program at Davis-Ber.se is required by the Nuclear Regulatory  ;

Commission (NRC) as part of the program for evaluating the effects of routine operation of nu- j

~

clear power stations on the surrounding environment. Both NRC regulations and Davis-Besse Technical Requirements Manual provide guidelines for the Meteorological Monitoring Program.

These guidelines ensure that Davis-Besse has the pioper equipment, in good working order, to support the many programs utilizing meteorological data.

1 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- l tological studies which are used to determine whether Davis-Besse has had any impact upon the local climate. After extensive statistical comparative rerearch 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 I groups and programs: Radiological Environmental Monitoring Program, The Emergency Prepar-edness Program, The Chemistry Unit, and groups such as Plant Operations, Plant Security, Mate- l 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 i evacuations or station isolation during adverse weather. The Chemistry Unit uses meteorological data for chemical spill response activities, marsh management studies, and wastewater outfall j flow calculations. Plant Operations uses meteorological data for cooling tower efficiency calcu- j lations, forebay water level availability and plant work which needs certain environmental con- 1 ditions to be met before work begins. Plant Security utilizes weather data in their routine plan- j ning and activities. Materials Management plans certain plant shipments around adverse weather i conditions to avoid high winds and precipitation which would cause delays in material deliveries i 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 wo&. J Legal Affairs uses climatological data for their investigation into adverse weather accidents to the plant and personnel.

i i

j I15 ,

O Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report f On-site Meteorological Monitoring l System Description l At Davis-Besse'there are two meteorological systems, a primary and a backup. They are both housed in separate environmentally controlled buildiup wnn moependent power supplies. Both i primary and backup systems have been analyzed to be " statistically identical" to the other so if l 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 i 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 SolarInsolation Precipitation I i

MeteorologicalInstrumentation

The meteoielogical system consists of one monitoring site located at an elevation of 577 feet l above mean su icvel (IGLD 1955)*, a 100m free-standing tower located about 3,000 feet SSW  !

of the cooling tower, and an auxiliary 10m foot tower located 100 feet west of the 100 m tower, are used to gather the meteorological data. The 100m tower has primary and backup instruments for wind speed and wind direction at 100m and 75m. The 100m tower also measures differential temperature (delta Ts): 100-10m and 75-10m. The 10m tower has instruments for wind speed l and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the 10m tower.

According to the Davis-Besse Nuclear Power Station, Technical Requirements Manual, a mini-L mum of five instruments are required to be operable at the two lower levels (75m and 10m) to measure temperature, wind speed, and wind direction. During 1998, annual data recoveries for  ;

all required instruments were 97.8 percent. Minor losses'of data occurred during routine instru- I ment 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 an outside consulting firm. These instruments are wind tun-nel tested to assure compliance with applicable regulations and plant specifications.

l .. International Great Lakes Data - 1955 l'

116 L

L

g Davis-Besse Nucisar Power Station 1998 Annual Radiological Environmental Operating Report Meteorological Data Handling and Reduction Each meteorological system, primary and backup, have two Campbell Scientific Dataloggers (model 21XL) assigned to them. The primary system has a first datalogger to communicate 900 second averages to the control room via a Digital Alpha computer system. This is a dedicated line. 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 data base. All validated data is then documented and stored on hard copy and in digital format for a permanent record of meteorological conditions. ,

Joint Frequency Distributions and Wind Sector Graphics Summary statistics and Joint Frequency Distributions (JFDs) of wind and stability data are gen-erated and the results are reviewed for consistency in terms of known site characteristic and re-gional climate. The end result of the review process is a validated final database suitable for use by atmospheric dispersion models and for site meteorological characterizations. Wind Sector Graphics represent the frequency of wind direction by sector and the wind speed in MPH by

sector. This data is used by the NRC to better understand local wind patterns as they relate to l defined past climatological wind patterns as reported in Davis-Besse's " Updated Safety Analysis i Report".

Meteorological Data Summaries This section presents summaries of the meteorological data collected from the on-site monitoring program at Davis-Besse during 1998. Tables 28 through 30, discussed in this section, can be found on pages 120 through 139. i

, l L

Wind Speed and Wind Direction The maximum measured sustained wind speeds for 1998 were 50.58 mph for the 100m level on November 11,47.85 mph for the 75m level on November 11, and 36.96 mph for the 10m level on November 11. Figures 32-34 give an annual sector graphic of average wind speed and percent frequency by direction measured at the three monitoring levels. Each wind sector graphic has  ;

two radial bars, the t

117 j

l L j

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report darker bar represents the percent of time the wind blew from that direction. The hatched bar rep-

. resents the average speed of the wind from that direction. Wind direction sectors are classified using Pasquill Stabilities. Calms (less than or equal to 1.0 mph) are shown in percent in the mid-

. die of the wind sector graphic. ,

Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 1998 are given in Table 29.

These data are measured at the 10m level; with differential temperatures taken from 100m and 75m levels. The yearly average ambient temperature for 1998 was 53.53 F. The maximum temperature was 91.93 F on July 21 with the minimum temperature of 9.6 F on December 23.

Yearly average differential temperatures were -0.13 F (100m), and -0.05 F (75m). Maximum differential temperatures for.100m and 75m levels were 7.99 F on October 11 (100m), and 7.99 F on October 22 (75m). Minimum differential temperatures for 100m and 75m levels were

-3.74 F on October 22 (100m) and -3.56 F on May 5 (75m). Differential temperatures are a measurement of atmospheric stability and used to calculate radioactive plume dispersions based on the Gaussian Plume Models of continuous effluent releases.

Dew Point Temperatures and Relative Humidity Monthly average and extreme dew point and humidity temperatures for 1998 are provided in Table 29. These data are measured at the 10 meter level. The average dew point temperature

~

was 45.23 F with a maximum dew point temperature of 79.03 F on July 21. Please note that  !

dew point temperatures above 75 F are highly suspect and are possibly due to calm winds and I 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 4.18 F on March 15. Average rela-tive humidity is 75.00 percent for the year. The maximum relative humidity was _100.00 percent i on December 29. The minimum relative humidity was 37.2 percent on March 14. It is possible ]

to have relative humidity above 100 percent which is known as super saturation. 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. i Precipitation Monthly totals and extremes of precipitation at Davis-Besse for 1998 are given in Table 29. To-tal precipitation for the year was 33.98 inches. The maximum daily precipitation total was 1.80 inches in August. The minimum was 0.27 inches recorded in May. It is likely that precipitation totals recorded in colder months are somewhat less than actual due to snow / sleet blowing across

. the collection unit rather than accumulating in the gauge.

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

dispersion problems during an unlikely radioactive release. A lake breeze event occurs during the daytime, usually during the summer, where the land surface heats up faster than the water, and therefore reaches higher temperatures than the water. The warmer air above the land rises faster because it is less dense than the cooler air over the lake. This leads to rising air currents over the land with descending denser air over the lake. This starts a wind circulation, which 118

{7:

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report 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 large amounts of water needed to cool plant components. If water levels get too low the plant operators can take measures for the safe shut down of the plant. Since Lake Erie is the shallow-est lake in the Great Lakes, it is not uncommon for a plus or minus five foot lake level fluctuation to occur within an eight to ten hour period. High water levels also effect the plant due to emer-gency transportation and evacuation pathways.

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Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report i

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J l Davis.Besse Nuclear Power Station 1990 Annual Radiological Environmental Operating Report l

Land and Wetlands Management i

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 (units). The pools are separated from Lake Erie and each other by a series of dikes and revetments. Toledo Edison is

]

i responsible for the maintenance and repair of the dikes and controlling the water levels in each  !

pool. )

A revetment is a retaining structure designed to hold water back for the purpose of erosion con-trol and to encourage beach formation. Revetments are built with a gradual slope which causes j waves to dissipate their energy when they strike the revetment. This encourages beach formation through passive deposition of sediment. A dike is a retaining structure designed to hold back l water for the purpose of flood control and to aid in managing wetland habitat. When used as a marsh management tool, dikes aid in controlling water levels in order to obtain desired vegeta-tion and animal species. Manipulating water levels is one of the most important marsh manage-ment tools used in Navarre Marsh. Three major types of wetland communities exist in Navarre Marsh, the freshwater marsh, swamp forest, and wet meadow. Also, there exists a narrow dry beach ridge along the lake front with a sand bar 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. Including the Ottawa National Wildlife Refuge, the Ohio Department of Natural Re-sources (ODNR), and the Black Swamp Bird Observatory to preserve and enhance existing habitat, to gain knowledge through research, and to help educate the public about the importance of preserving wetlands.

With its location along two major migratory flyway, the Navarre Marsh serves as a refuge for a variety of birds in both the spring and the fall, where they rest and find nourishment before con-tinuing on their journey. The Black Swamp Bird Observatory captures, examines, bands, cata-logues, and releases songbirds in the marsh during these periods.

Navarre is also home to wildlife that is typical of much of the marshland in this area, including deer, fox, coyote, muskrats, rabbits, woodchucks, hawks, owls, ducks, geese, herons, snakes and turtles. For the first time in recent history, a pair of mature American Bald Eagles chose the Na-varre Marsh as their nesting site in late 1994, and fledged a healthy eaglet in July 1995. The young eagle was one of record 38 eaglets fledged in Ohio in 1996. The nest blew down in a storm in August of 1996, and State and Federal wildlife officials and Davis-Besse employees constructed an artificial nesting platform. This nest was the only one in Ottawa County to sur-vive the June 1998 severe weather.

Goose banding took place in June, and was conducted in cooperation with the ODNR and the f U.S. Fish and Wildlife Service. Over 100 Canada Geese were banded in about an hour.

1 140 l

p Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Ohio's fifth Federal Junior Duck Stamp Art Contest was hosted by Davis-Besse. Young Ohio artists in grades K-12 submitted nearly 800 entries in four separate age brackets. The Junior i 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 national contest with all other state best-of-show entries. The winner of this competition will be used to make this year's Junior 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 uses Lake Erie as a water source 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- l glomerate particles to mass together further. Finally, during sedimentation, large conglomerate j

_ particles settle to the bottom of the clarifier. These processes normally require large separate l tanks. However, the use of clarifiers saves both space and the manpower needed to operate the treatment plant.

141

r Davis Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report

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After the clarifier, the water goes through a flow-splitting box, which equally divides the water flow to the Automatic Valveless Gravity Filters (AVGF). These AVGFs consist of a 50:50 ratio of anthracite to filter sand. During this filtration process, suspended matter is removed from the water by the anthracite and sand media. This filtering reduces the turbidity of the water.

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 Since 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, has been 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 requirement 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 accidentally introduced into 142

n Davis-Besse Nuclear Power Station 1998 Anr.ual Radiological Environmental Operating Report i

North American waters in 1986 and was discovered in Lake Erie in 1989. Zebra mussels are i l

prolific breeders that rapidly colonize an area by secreting byssal threads that enable them to at-tach to solid surfaces and to each other. Because of their ability to attach in this manner, they I 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 yet 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 ca-nal).

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- i ing clarity of Lake Erie. As the food source for the zebra mussels decline, mussel population de-clines correspondingly.

Wastewater Treatment Plant Operation The WWTP operation is supervised by a state Certified Wastewater Operator. Wastewater gen- i erated _by site personnel is treated at an onsite extended aeration package treatment facility de-signed to accommodate a flow of 38,000 gallons per day (gpd). In the treatment process, waste-water from the various collection points around the site, called lift stations, enters the facility and is distributed to the surge tanks of the treatment plants The wastewater is then pumped into the aeration tanks. Here, sanitary waste is digested by mi-croorganisms which are provided with a source of oxygen. This is accomplished through the use of blowers. The mixture of organics, microorganisms, and decomposed wastes is called acti-vated sludge. The treated wastewater settles in a clarifier, and the clear liquid passes over a weir, leaving the plant by an effluent trough. The activated sludge contains the organisms necessary for continued treatment, and is pumped back to the front of the plant to digest more incoming wastewater. The effluent leaving the plant is disinfected with chlorine and is pumped to the wastewater treatment basin (NPDES Outfall 601) where further treatment takes place.

Summary of 1998 Wastewater Treatment Plant Operations Wastewater Treatant was interrupted briefly after the June tornado. Power was lost to the treatment facility fer two days. Portable diesel air compressors were hooked up to the aeration system in order to continue supplying the treatment organisms with sufficient oxygen for proper wastewater digest'.on. The north wall of the No. I Wastewater Treatment Plant was heavily damaged during ihe June storm and could not be repaired. For this reason the building was torn down and rer! aced with a larger, sturdier structure.

All other wastewater operations were normal during 1998.

143

I Davis-Desse Nuclear Power Station 1990 Annual Radiological Environmental Operating Report National Pollutant Discharge Elimination System (NPDES) Reporting l

The OEPA has established limits on the amount of pollutants that Davis-Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 2I800011

• FD. Parameters such as chlorine, suspended solids and pH are monitored under the NPDES permit. Toledo Edison personnel pre- ,

pare the NPDES Reports and submit them to the OEPA by the fifteenth day of each month. j Davis-Besse has six sampling points described in the NPDES permit. Five of these locations are ,

discharge points, or outfalls, and one is a temperature monitoring location. Descriptions of these i sampling points follow:

l Outfall 001 Collection Box: At a point representative of discharge to Lake Erie. i Source of Wastes: Low volume wastes (Outfalls 601 and 602), circulation system blowdown and service water.

Outfall 002 Area Runoff: Discharge to Toussaint River ,

I Source of Wastes: Storm water runoff, circulating pump house sumps.

Outfall 003 Screenwash Catch Basin: Outfall to Navarre Marsh. i Source Of Wastes: Wash debris from water intake screens.

Outfall 601 Wastewater Plant Tertiary Treatment Basin: Discharge from wastewater treatment system.

Sources Of Wastes: Wastewater Treatment Facility.

Outfall 602 Low volume wastes: Discharge from settling basins.

Sources of wastes: Water treatment residues, condensate polishing holdup tank decant, and condensate pit sumps.

Sampling Point 801 Intake Temperature: Intake water prior to cooling operation.

i 144

Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report  !

l 1998 NPDES Summary During 1996, the NPDES permit was renewed by the Ohio EPA. This permit will expire on  ;

October 31,2000. All outfalls remain the same. However, new parameters have been added, in-cluding hydrazine and dissolved oxygen during refueling and maintenance outages, total residual chlorine, copper, lead, and zinc. Many of these new parameters are a result of the Great Lakes Water Quality Initiative. The trend in the future permits will be further increased monitoring.

1 I

l l

i i

145 I

Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Chemical Waste Management The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes generated at the Davis-Besse. Nuclear Power Station was developed to ensure wastes are man-aged and disposed of in accordance with all applicable state and federal regulations.

Waste Management 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, semisolid, 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 kilograms / month (2200 lbs month ) or more. l e Small quantity Generators - A facility which generates less than 1000 kilograms / l month (2200 lbs/ month). j e Conditionally Exempt Small Quantity Generators - A facility which generates 100 kilo-grams / month- (220 lbs/ month).

In 1998, the Davis-Besse Nuclear Power Station maintained small quantity generator status, gen-erating 1,870 pounds of hazardous waste. Davis-Besse personnel also continuously strive to identify alternate ways to reduce hazardous waste generation.

Nonhazardous waste generated from standard cperating sources included 5,200 gallons of used l oils and 1,210 gallons of oil filters and solid oily debris. Other nonhazardous regulated waste generated included 315 gallons of other chemicals such as microfilm process chemicals and i polystyrenes resins. j RCRA also mandates other requirements such as the use of proper storage and shipping contain-

. ers, labels, manifests, reports, personnel training, spill control plan and an accident contingency

' plan ~, all of which are part of the Chemical Management Program at Davis-Besse. The following are completed as part of the hazardous waste management program to ensure compliance with -

the RCRA regulations.

146

Davis.Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Inspections

• Chemical Waste Accumulation Areas are designated throughout the site to ensure proper handling and disposal of chemical waste. These, along with the Chemical Waste Storage Area, are toutinely patrolled by security personnel and inspected weekly by Toledo Edison personnel. All areas used for storage or accumulation of hazardous waste are posted as such with warning signs, and drums are color-coded for easy identification of waste categories by Davis-Besse employees.

. Waste Inventory Forms Inventory forms are placed on waste accumulation drums or provided in the accumu-lation area to allow employees to record the waste type and amount as it is added to the drum. This ensures that incompatible wastes are not mixed and also identifies the dmm contents for proper disposal.

Emergency Response Planning Comprehensive Environmental Response, Compensation, and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, sometimes referred to as Superfund) established a federal authority and source of funding for re-sponding to spills and other releases of hazardous materials, pollutants, and contaminants into the environment. Superfund establishes " reportable quantities" for several hundred hazardous mate-rials, 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 ,

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 were made as to which products and chemicals were present in sufficient quantities to report.

-Annual SARA reports are submitted to local fire departments, and local and state planning com-missions by March I for the preceding calendar year. No additional chemical products were identified for calendar year 1998.

Spill Kits Spill control equipment is maintained throughout the Station at chemical storage areas and at ap-propriate hazardous chemical and oil use points. Equipment in the kits may include such items as chemical resistant coveralls, gloves, boots, decontamination agents, absorbent cloth, goggles, and warning signs.

147 L- .

U Divis-Besse Nucleir Power Station 1998 Annual Radiological Environmental Operating Report

.Other Regulating Acts 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 l

system, very similar to the hazardous waste management system established under RCRA. 1 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.

Retrofilling 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 retrofill process takes several years and will extract almost all of the PCB. In j all, Davis-Besse performed retrofill activities on eleven PCB transformers between 1987 and 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors. l These capacitors are being replaced and disposed of during scheduled maintenance activities. J Clean Air Act The Clean Air'Act identifies substances which are considered air pollutants. Davis-Besse holds an OEPA permit to operate an Air Contaminant Source for the station auxiliary boiler. This

' boiler is used to heat the station and provide steam to plant systems when the reactor is not oper-ating. A report detailing auxiliary boiler operation is submitted annually.

' Applications for Permits to Operate an Air Pollution Source were submitted to the Ohio EPA for our six emergency diesel engines, including the Station Blackout Diesel Generator, the 2 Emer-gency Diesel Generators, the Emergency Response Facility Diesel, the Miscellaneous Diesel, and the Fire Pump Diesel. These sources are operated infrequently to verify their teliability, and would only be used in the event of an emergency.

In response to recent " Clean Air Act Title V" legislation, an independent study identifying and i.

-quantifying all of the air pollution sources onsite was performed. Of particular significance is

! asbestos removal from renovation and demolition projects for which USEPA has outlined spe-cific regulations concerning handling, removal, environmental protection, and disposal. Also the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concern for. worker protection. Removal teams must meet medical surveillance, respirator fit tests, and training requirements prior to removing asbestos-containing material. Asbestos is not considered a hazardous waste by RCRA, but the EPA does require special handling and dis-  !

posal of this waste under the Clean Air Act. I 1

i 148 e j

E r

l Davis-Besse Nuclear Power Station 1993 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 State.s 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, j 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- j ating condition. l l

Other Programs 1 Underground Storage Tanks ]

l According to RCRA, facilities with Underground Storage Tanks (UST) are required to notify the j 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.

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

The State or Cbio 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 waste material where possible and recycling of other waste materials. This is frequently referred to as " Reduce, Reuse, and Recy-cle."

Davis-Besse has implemented and participated in company wide programs which emphasize the reduce, reuse, recycle approach to MSW management. Improved efficiency in collection and hauling, resulted in a two year reduction of approximately 71 percent for disposal cost MSW.

Additionally, joint partnership agreements with yard waste compositors have been developed for yard and lawn waste recycling.

j An Active Investment Recovery Program has greatly contributed to the reduction of both hazard-t ous 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, alumi-num cans, used tires, and metals recycling or recovery. Paper and cardboard recycling typically 149

Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report

exceeds 50 tons annually. This represents a large volume of recyclable resources which would have otherwise been placed in a landfill. Aluminum soft drink cans are collected on site for the Boy Scouts to recycle. Additionally, lead-acid batteries are recycled and tires are returned to the seller for proper disposal. Although scrap metal is not usually considered part of the MSW stream, Davis-Besse does collect and recycle scrap metals. The metals 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.  !

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r" Davis-Besse Nuclear Power Station 1998 Annual Radiologicci Environmental Operating Report i

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APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS i

1 I

l NOTE: Teledyne's Midwest Laboratory participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratoy, Las Vegas, Nevada. The results are reported in Appendix A. Also reported are results of International Intercomparison and Teledyne testing of TLD's, as well as, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January,1998 through December,1998 151 f'

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Davis-Besse Nuclear Power Station 1998 Annual Radiologicd Environmental Operating Report l

l l

ll AppendixA

_ interlaboratnrv enmnarison Procrram Resulte Teledyne.'Brown Engineering Environmental Services Midwest Laboratory (formerly Hazleton-Environmental Sciences) has y.cticipated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality cowd program in December 1971. These programs are operated by agencies I 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 the laboratory's analytical procedures and to alert it to any possible problems.-

Participant laboratories measure the concentration of specified radionuclides and report them to the I

1 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 4

~ controllimits indicate a need to check the instruments or procedures used. l

'Ihe 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 is conducted by the U.S. Environmental Protection Agency Office of Research and

. Developement National Exposure Research Laboratory Characterization Research Division-Las Vegas,

. Nevada.

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

Also Teledyne testing results are 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 l Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for " spiked" samples.

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

i i

152

h Davis-Besse Nuclear Power Station 1998 Annual Radiclogical Environmental Operating Report 12-31-98 ATTACHMENT A ACCEPTANCE CRITERIA POR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation ,

Analysis Level for single determinations Gamma Emitters 5 to100 pCi/ liter or kg 5.0 pCi/ liter

>100 pCi/ liter or kg 5% of known value 6

Strontium-89 5 to50pC1/ liter orkg 5.0 pCi/ liter

>50 pCi/ liter or kg 10% of known value 3 6

Strontium-90 2 to 30 pCi/ liter or kg 5.0 pCi/ liter

>30 pCi/ liter or kg 10% of known value ,

Potassium-40 >0.1 g/ liter or kg 5% of known value 1 1

Gross alpha $20 pCi/ liter 5.0 pCi/ liter I

>20 pCi/ liter 25% of known value Gross beta $100 pCi/ liter 5.0 pC1/ liter

>100 pC1/ liter 5% of known value Tritium s4,000 pCi/ liter is = (pCl/ liter) =

169.85 x (known)**

>4,000 pCi/ liter 10% of known value Radium-226,-228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value Iodine-131, s55 pCi/ liter 6.0 pCi/ liter Iodine-129 6 >55 pCi/ liter 10% of known value Uranium-238, 535 pCi/ liter 6.0 pCi/ liter -

Nickel-63 6 >35 pCi/ liter 15% of known value 6

Technetium-99 6 50 to 100 pCi/ liter 10 pCi/ liter iron-55 >100 pCi/ liter 10% of known value Others" -

20% of known value I~ ' From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year,1981-1982, EPA-600/4-81-004.

f

• Teledyne limit.

}

153

flI Davis-Besse Nuclear Power Station 1998 Annuil Radiological Environment:1 Operating R! port -

l l Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's l j Midwest Laboratory results'.

l Concentration in pCi/L" l l

d 1.ab - Sample Date Teledyne Results EPA Result Control i Code Type Collected Analysis f2 Sigma' Is, N=1 Limits j STW-815 WATER - Jan,1998 Sr-89 6.0tl.0 8.0 i 5.0 2.2 - 13.8 STW-815 WATER Jan,1998 Sr-90 27.3 i 1.2 32.015.0 26.2 - 37.8 I STW-816 WATER Jan,1998 Gr. Alpha 31.212.3 30.5 i 7.6 21.7 - 39.3 STW-816 WATER Jan,1998 Gr. Beta 6.610.6 3.915.0 0.0 - 9.7 j STW-817 WATER Feb,1998 I-131 111.li0.9 104.9 i 10.5 86.7 - 123.1 STW-818 ' WATER Feb,1998 Ra-226 14.911.3 16.0 i 2.4 11.8 - 20.2 l STW-818 WATER Feb,1998 Ra-228 30.911.9 33.3 i 8.3 18.9 - 47.7

! STW-818 WATER Feb,1998 U 25.8 i t.1 32.013.0 26.8 - 37.2

! The presence of U-232 in the sample interfered with the recovery calculation. Result of recalculation; i l 28.211.2 pCi/L. ]

STW-823 WATER Mar,1998 H-3 2,151.0 i 75.2 2,155.0 1 348.0 1,551.2 - 2,758.8 STW-824 WATER Apr,1998 Gr. Alpha 48.3 i l.5 54.4 i 13.6 30.8 - 70.8 STW-824 WATER Apr,1998 Ra-226 15.3 i 0.9 15.012.3 11.0 - 19.0 )

STW-824 WATER Apr,1998 Ra-228 7.8tl.0 9.3i2.3 5.3 - 13.3 j STW-824 WATER Apr,1998 Uranium 5.1i0.1 5.0i 3.0 0.0 - 10.2 STW-825 WATER Apr,1998 Co-60 50.0i t.7 50.0 i 5.0 41.3 - 58.7 L STW-825 WATER Apr,1998 Cs-134 20.711.2 22.0 i 5.0 13.3 - 30.7 STW-825 WATER Apr,1998 Cs-137 9.0il.0 10.0 i 5.0 1.3 18.7 STW-825 WATER Apr,1998 Gr. Beta 92.1 i 3.2 94.7 i 10.0- 77.4 - 112.0 STW-825 WATER Apr,1998 St-89 5.3i1.5 6.0i 5.0 0.0 - 14.7 STW-825 WATER Apr,1998 Sr-90 17.3 i 1.5 18.0 i 5.0 9.3 26.7 STW 826 WATER Jun,1998 Ba-133 36.0 i 1.0 40.0 i 5.0 31.3 - 48.7 STW-826 WATER Jun,1998 Co-60 14.0il.0 12.0 5.0 3.3 - 20.7 STW-826 WATER Jun,1998 Cs-134 26.7 t l.2 31.015.0 22.3 - 39.7 STW-826 WATER Jun,1998 Cs-137 32.7 i 3.8 35.0 i 5.0 26.3 - 43.7 l STW 826 WATER Jun,1998 Zn-65 99.0111.8 104.0 1 10.0 86.7 - 121.3 STW-827 - WATER Jun,1998 Ra-226 4.7i 0.4 4.910.7 3.7 - 6.1  ;

STW-827 WATER . 'Jun,1998 Ra-228 2.6 i 0.7 2.1i0.5 1.2 - 3.0 STW-827 WATER Jun,1998 Uranium 3.010.1 3.0i 3.0 0.0 - 8.2 l STW-831 WATER - Jul,1998 Sr-89 19.0 i 3.0 21.0 i 5.0 12.3 - 29.7 STW-831 WATER , Jul,1998 Sr-90 7.0i0.0 7.0i 5.0 0.0 - 15.7 I STW-832 . WATER Jul,1998 Gr. Alpha 5.810.4 7.2i 5.0 0.0 - 15.9 STW-832 WATER Jul,1998 Gr. Beta 12.4 i 0.4 12.8 i 5.0 4.1 - 21.5 STW-833 WATER Aug,1998 - H-3 17,732.0 i 31.0 17,996.0 i 1,800.0 14,873.0 - 21,119.0 STW-840 WATER Sep,1998 I 131 5.9i0.1 6.1i2.0 2.69.6 STW-841 WATER Sep,1998 Ra-226 1.710.1 1.7i 0.3 1.2 - 2.2 STW-841 WATER Sep,1998 Ra 228 6.lio.6 5.7it.4 3.3 - 8.1 l^

154 L-

F Davis-B:sse Nuclear Power St:. tion 1998 Annual Radiologic .1 Environmental Opertting Report Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'.

i l Concentration in pCi/L6 l Lab Sample Date . Teledyne Results EPA Result' Control l Code Type Collected Analysis 12 Sigma' Is, N=1 Limits

[. 1 Sep,1998 Uranium STW-841 WATER 8.2i o.S 9.1 1 3.0 3.9 - 14.3 )

l

• Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a l l participant in the environmental sample crosscheck program operated by the Intercomparison and l Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.

Environmental Protection Agency (EPA), las Vegas, Nevada. .

• All results are in pC1/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter '

samples, which are in pCi/ Filter.

• Unless otherwise indicated, the TBEESML results are given as the meani 2 standard deviations for three determmations, d

USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) l and control limits as defined by the EPA.

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155

n 1 Davis-Besse Nuclear Power Station 1998 Annual Rr.diological Environment-J Operating Rrport I

p Table A-2. Crosscheck program results;'Ihermoluminescent Dosimeters. (TLDs).

i mR l'

Lab Teledyne Results Known Average i2 Sigma

' Code TLD Type Date Measurement i 2 Sigma ' Value (All Participants) lith InternmHanal Interenmnarlson 115-11A LIF-100 Chips Apr,1997 Field 13.2i l.0 19.0 17.8 i 8.4 l 115-11A LIF-100 Chips Apr,1997 Lab,Cs 32.1 i 2.0 . 58.1 55.2 i 9.9

[ "Ihe readings for LiF chips were low in both field and Lab Cs tests. No errors found in efficiency or test

! -calculations, however the reader setting is suspect. Interlaboratory test comparisons for LiF were-satisfactory.

lith Intern =Hanal Interenrnnarison 115-11B CaSO.: Dy Apr,1997 Field 19.111.4 19.1 18.9 i 8.7 Cards

! Lab,Cs~

115-11B CaSO.: Dy Apr,1997 55.714.1 58.3 55.2114.9 Cards l The Eleventh IntemationalIntercomparison of Environmental Dosimeters was conducted in 1997 and was

orgs.nized by the Department of Energy's Environmental Measurements Laboratory in collaboration with l- . Brookhaven National Laboratory and the National Institute of Standards and Tecimology.

l Tel.Avne TenHn- -

%1 Lab,1 '

LiF-100 Chips Mar,1996 15.9 i 0.3 15.4

%1 LIF-100 Chips Mar,1996 Lab,2 29.4 i 0.3 30.8 1 LIF-100 Chips Mar,1996 Lab,3 62.Sil.3 62.5

%1 - CaSO.: Dy Mar,1996 Reader 1, #1 14.410.1 15.4 ND l' Cards 96-1 CaSO.: Dy Mar,1996 Reader 1, #2 31.8 i 0.1 30.8 ND l Cards

%1 CaSO.: Dy Mar,1996 . Reader 1, #3 64.7 i 0.4 62.5 ND l Cards Taladvne Testina 96-2 CaSO.: Dy Mar,1996 Reader 2, #1 14.3 i 0.4 15.4 ND Cards I 96-2 CaSO.: Dy Mar,1996 Reader 2, #2 31.8 t 0.1 30.8 ND Cards

%2 CaSO.: Dy Mar,1996 Reader 2, #3 68.6 i 0.1 62.5 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne, Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1996.

l Teledvne Testinar I

97 1 LIF-100 Chips Mar,1997 Lab,1 13.4 i 1.4 15.0

97 LiF-100 Chips Mar,1997 Lab,2 29.810.6 30.1 97-1 LIF-100 Chips Mar,1997 Lab,3 63.410.9 60.2 156

Davis-Besse Nuclear Power Statica 1998 Annual Radiological Environmental Opertting Report l

l Table A-2. Crosscheck program results;'Ihermoluminescent Dosimeters. (TLDs),

mR Lab' Teledyne Results Known - Average 12 Sigma Code- TLD Type Date Measurement t 2 Sigma Value (All Participants) 97 1 CaSO.: Dy . Mar,1997 Reader 1, #1 15.5 i 0.1 15.0 ND Cards 97-1 CaSO.: Dy Mar,1997 Reader 1, #2 34.0 i 0.1 30.1 ND Cards 97-1 CaSO.: Dy Mar,1997 Reader 1, #3 68.3 i 2.1 60.2 ND Cards l Teledvne Testina 97-2 CaSO.: Dy Mar,1997 Reader 2, #1 16.8 i 0.3 15.0 ND Cards

.97-2 CaSO.: Dy Mar,1997 Reader 2, #2 36.2 i 0.2 30.1 ND Cards 97-2 CaSO.: Dy Mar,1997 Reader 2, #3 69.6 i 0.2 60.2 ND l

Cards ND = No Data;Teledyne Testing was only performed by Teledyne.

Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1997.

Teledvne Testing 98-1 LIF-100 Chips May,1998 Lab,1 15.511.3 16.7 l 98-1 LIF-100 Chips May,1998 Lab,2 23.9 i 0.9 32.4

! 98-1 LIF-100 Chips May,1998 Lab,3 59.8 i 1.9 60.2 98-1 CaSO.: Dy May,1998 Reader 1, #1 18.510.8 16.7 - ND Cards 98-1 CaSO.: Dy May,1998 Reader 1, #2 27.3i t.7 32.4 ND l Cards 98-1 CaSO.: Dy May,1998 Reader 1, #3 70.0 i 4.7 60.2 ND l Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in May,1998.

l 157 L

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Davis-B5sse Nucitar Power Station 1998 Annual Radiological Environmental Operating Rtport I

1^

Table A-3. In-house " spike" samples.

Concentration in pCi/I' Lab Sample Date - Teledyne Results Known Control' Code Type ~ Collected Analysis 2s, n=1' Activity Limits i-SPW.77 WATER Jan,1998 Cs-137 78.64 i 7.76 77.23 67.23 - 87.23 SPW-129 WATER Jan,1998 Am-241 16.96 i 1.24 20.64 12.38 - 28.90 SPW 130 WATER Jan,1998 Ra-226 9.3910.14 10.35 7.25 - 13.46 SPW-130 WATER Jan,1998 Ra-226 12.74 1 3.05 14.03 9.82 - 18.24 SPMI-498 MILK Jan,1998 CcH4 41.40 i 3.61 36.92 26.92 - 46.92

( SPMI-498 MILK Jan,1998 Cs-134 31.78 i 3.15 32.52 22.52 - 42.52 l' SPMI-498 MILK Jan,1998 Cs-137 37.03 i 4.57 38.56 28.56 - 48.56 l

SPW-499 WATER Jan,1998 Co-60 44.38 1 7.85 36.92 26.92 - 46.92 SPW-499 WATER Jan,1998 Cs-134 34.97t 7.78 32.52 22.52 - 42.52

' SPW-499 WATER Jan,1998 Cs-137 39.15 i 10.40 38.56 28.56 - 48.56 SPW 594 WATER Jan,1998 H-3 45125.00 i 568.00 45598.00 36478.40 - 54717.60 SPAP-5330 AIR FILTER Jan,1998 Cs-137 1.68 i 0.02 1.90 1.14 - 2.66

[

SPW-664 ' WATER Feb,1998 U-234 2.6310.40 3.00 1.80 - 4.20 SPW-664 WATER Feb,1998 U-238 3.26 i 0.49 3.00 0.00 - 15.00 SPCH-746 g g. AL Feb,1998 I-131(g) 1.73 i 0.06 2.03 1.22 - 2.84

- SPVE-750 VEGETATION Feb,1998 I 131(g) 6.16 i 0.14 5.43 0.00 - 15.43 .

SPW-790 WATER Feb,1998 I-131 136.35 1 1.33 137.03 109.62 - 164.44 l SPMI-791 MILK Feb,1998 I-131 132.63 i 1.63 137.03 109.62 - 164.44 l SPW-497 WATER Feb,1998 Gr. Alpha 43.73 1 7.61 41.27 20.64 - 61.91 SPW-497 WATER Feb,1998 Gr. Beta 59.45 i 2.90 61.70 51.70 - 71.70

! SPW-9854 - WATER Feb,1998 Gr. Alpha 62.60 t 5.10 53.88 26.94 - 80.82 l SPAP-748 AIR FILTER Feb,1998 Gr. Beta 1.72 i 0.02 1.66 0.00 - 11.66

{ SPW 1663 WATER Feb,1998 Ra-226 14.44 i 0.50' 13.80 9.66 - 17.94 l' WATER Feb,1998 Ra 228 18.79 1 1.58 18.29 12.80 - 23.78 SPW-1663 SPW-1665 WATER Mar,1998 Ra 226 14.16 1 0.29 13.80 9.66 - 17.94 SPW-1665 WATER Mar,1998 Ra-228 18.06i t.70 18.29 12.80 - 23.78 .

- SPW-1666 WATER Mar,1998 Sr-89 65.40 i 2.70 75.94 60.75 - 91.13

! SPW-1666 WATER Mar,1998 Sr-90 28.04 t l.22 32.65 26.12 - 39.18 i SPAP-1728 AIR FILTER Mar,1998 Gr. Beta 8.15 i 0.03 7.98 0.00 - 17.98 SPW 1998 WATER Apr,1998 Ra-226 13.70 i 0.33 13.80 9.66 - 17.94 SPW-1998 WATER Apr,1998 Ra-228 14.65 i 1.38 18.20 12.74 - 23.66 SPW-792 . WATER Apr,1998 Th-230 18.62 i 2.85 17.39 10.43 - 24.35

. SPW-2278 WATER Apr,1998 H-3 41641.00 1 552.00 43287.00 34629.60 - 51944.40 I

SPW 2284 WATER Apr,1998 Gr. Alpha 41.09 1 1.83 41.26 20.63 - 61.89 SPW-2284' WATER Apr,1998 Gr. Beta 32.01 1 1.10 30.72 20.72 - 40.72 SPMI-5451 MILK Apr,1998 Cs-137 80.78 i 6.60 76.68 66.68 - 86.68 SPW-5459 . WATER . Apr,1998 Co-60 48.50 i 3.74 44.65 34.65 - 54.65 SPW 5459 WATER Apr,1998 Cs-137 42.31 1 4.32 38.34 28.34 - 48.34 SPW-2977 WATER May,1998 Ra-226 11.91 1 0.27 13.80 9.66 - 17.94 L 158

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Divis-B ,sse Nucle r Power St: tion 1998 Annual Radiological Environmental Operating Report 1 j

l IL' L i 1

, Table A-3. - In-house " spike" samples.

( Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' l Code Type Collected Analysis 2s, n=1" Activity . Limits SPW-2977 WATER May,1998 Ra-228 16.26 i 1.67 18.00 12.60 - 23.40 l SPAP-3041 AIR FILTER May,1998 Cs-137 2.00 i 0.02 1.89 1.13 - 2.65

} SPW-3043 WATER May,1998 Gr. Alpha 40.49 i 2.57 41.25 20.63 - 61.88 SPW-3043 WATER May,1998 Gr. Beta 35.79 1 1.52 30.66 20.66 - 40.66 SPSO-3898 SOIL - May,1998 Cs 134 0.11 i 0.01 0.10 0.06 - 0.14 j SPSO-3898 SOIL May,1998 Cs-137 0.48 i 0.02 0.43 0.26 - 0.61 ]

SPP-3900 FISH May,1998 Cs-134 0.36 i 0.03 0.38 0.23 - 0.53 SPF-3900 FISH . May,1998 Cs-137 0.29 i 0.03 0.31 0.18 - 0.43 SPW-4162 - WATER Jun,1998 Ra-226 12.98 1 0.18 13.80 9.66 - 17.94 )

SPW-4162 WATER Jun,1998 Ra-228 16.73i t.62 17.80 12.46 - 23.14 SPW-5340 WATER Jun,1998 Gr. Alpha 41.38 t l.87 41.25 20.62 - 61.87 ,

SPW-5340 WATER Jun,1998 Gr. Beta 61.92il.51 64.92 54.92 - 74.92 l

)

l- SPW-4718 WATER Jul,1998 Ra-226 12.93 1 0.12 13.80 9.66 - 17.94 i SPW-4718 WATER Jul,1998 Ra-228 13.13il.59 17.67 12.37 - 22.97 j SPCH 5129 COAL Jul,1998 I-131(g) 0.61 i 0.05 0.57 0.34 - 0.80 R

l SPMI-5131 MILK Jul,1998 Cs-137 83.87 i 9.09 76.36 66.36 - 86.36 '

SPMI-5131. MILK Jul,1998 I-131 63.98 i 0.77 61.03 48.82 - 73.24 SPMI-5131 MILK Jul,1998 I-131(g) 62.05 i 11.00 61.03 36.62 - 71.03 SPMI-5131 MILK Jul,1998 Sr-89 52.66 i 2.13 62.05 49.64 - 74.46 SPMI-5131 MILK Jul,1998 Sr-90 29.78 t l.39 32.41 25.93 - 38.89 SPW 5134 WATER Jul,1998 H-3 20918.00 i 396.00 21666.00 17332.80 - 25999.20 SPW-5137 WATER Jul,1998 CM0 44.96 1 4.00 43.56 33.56 - 53.56 SPW-5137 WATER Jul,1998 Cs-137 72.05 i 5.84 76.36 66.36 - 86.36 SPW-5137 WATER Jul,1998 I-131 52.07 i 0.69 61.03 48.82 - 73.24 SPW 5137 WATER Jul,1998 1131(g) 58.78 i 7.69 61.03 36.62 - 71.03 SPW-5136 WATER Jul,1998 Gr. Alpha 50.02 i 2.28 41.24 20,62 - 61.86 SPW-5136 WATER Jul,1998 Gr. Beta 70.19 t l.88 64.80 54.80 - 74.80 SPAP-5611 AIR FILTER Jul,1998 Cs-137 1.6810.02 1.86 1.12 - 2.60 SPF-5453 FISH ' Jul,1998 Cs-137 0.33 i 0.03 0.31 0.18 - 0.43 ,

AIR FILTER Jul,1998 Cs-137 1.96 i 0.02 1.86 1.12 - 2.60 SPAP-5611 )

SPW-6091 WATER Aug,1998 Gr. Alpha 30.59 i 1.69 41.23. 20.62 - 61.85 )

SPW-6091 WATER Aug,1998 Gr. Beta 30.28i t.17 30.48 20.48 - 40.48 SPW-6092 WATER Aug,1998 Ra-226 6.2910.19 6.90 4.83 - 8.97 SPW-6092 WATER Aug,1998 Ra-228 7.85 i 1.28 8.72 6.10 - 11.34 SPW-7143 _ WATER Sep,1998 Ra 226 12.31 i 0.48 13.79 9.65 - 17.93 l l SPW-7143 ' WATER Sep,1998 Ra 228 15.70il.68 17.25 12.08 - 22.43

,. SPW-7144 WATER - Sep,1998 Gr. Alpha 35.48 il.65 33.97 16.99 - 50.%

SPW-7144 WATER Sep,1998 Gr. Beta 33.06il.11 30.41 20.41 - 40.41 159

h Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Opertting R: port l

- Table A-3. In-house " spike" samples.

l' Concentration in pCi/L' Lab Sample Date Teledyne Results - Known Control' Code ' Type Collected Analysis 2s, n=1' Activity Limits

- SPMI-7592 MILK Sep,1998 I-131 58.15 t 0.90 61.55 49.24 - 73.86 SPW-7594 - WATER Sep,1998 Co-60 46.15

• 8.78 42.34 32.34 - 52.34 SPW-7594 WATER Sep,1998 1131 77.97 0.81 82.07 65.66 -'98.48

. SPW-7594 WATER ' Sep,1998 I-131(g) 80.62

• 13.90 82.07 49.24 - 92.07

. SPVE-7596 VEGETATION Sep,1998 I-131(g) 2.61

• 0.08 2.46 1.48 - 3.44 SPCH-7615 AL S*P,1998 ~ I-131(g) 1.41

• 0.06 1.28 0.77 - 1.79 R

! SPF-1602 - _

FISH ~ Oct,1998 - Cs 137 0.56

• 0.04 0.61 0.37- 0.85 SPW-8178 - . WATER Oct,1998 Gr. Alpha 25.22

• 1.90 33.% 16.98 - 50.94

. SPW-8178 WATER Oct,1998 Gr. Beta 30.20 1.31 -30.36 20.36 - 40.36 SPW-8179 WATER - Oct,1998 Ra 226 11.12

• 0.16 13.80 9.66 - 17.94 SPW-8179 WATER Oct,1998 Ra 228 17.83

• 1.87 17.09 11.96 - 22.22 SPAP-8457 AIR FILTER Oct,1998 Cs-137 1.78

• 0.02 1.84 1.10 - 2.58 SPAP-8567 AIR FILTER Oct,1998 Gr. Beta 6.54

• 0.10 6.47 0.00 - 16.47 SPSO-9953 . SOlt Oct,1998 Cs 134 - 0.08

• 0.01 0.09 0.05 - 0.12 SPSO-9953 SOIL Oct,1998 Cs-137 0.45 0.01 0.43 0.26 - 0.60 SPW-9386 WATER Nov,1998. Ra-226 14.75 0.47 13.80 9.66 - 17.94 SPW-9386 _ WATER Nov,1998 Ra-228 15.67

• 1.59 16.95 11.87 - 22.04 SPW-9387 WATER Nov,1998 Gr. Alpha 27.49

• 2.38 33.97 16.99 - 50.96 SPW-9387 WATER Nov,1998 Gr. Beta 36.04 2.14 30.31 20.31 - 40.31 SPW-10347 WATER Nov,1998 Sr-90 4.30 1.10 3.20 0.00 - 13.20 SPW-10345 WATER Nov,1998 H-3 38980.00

• 548.00 38848.00 31078.40 - 46617.60

' SPW-10340 WATER Dec,1998 Ra 226 6.73 0.25 6.89 4.82 - 8.96 l

SPW-10340 WATER Dec,1998 Ra-228 7.44

• 1.77 8.40 5.88 - 10.92 l

SPW-10341 WATER Dec,1998 Gr. Alpha 49.30

• 3.35 33.97 16.99 - 50. %

l

' SPW-10341 WATER Dec,1998 Gr. Beta 33.63

• 1.70 30.25 20.25 - 40.25 SPW-10389 WATER Dec,1998 U 4.10

• 0.25 4.17 2.50 - 5.84 SPW 10390 - WATER Dec,1998 U 4.29

• 0.25 4.17 2.50 - 5.84

• All results are in pC1/L, except for elemental potassium (K) in milk, which are in mg/L; air filter samples, which are in pC1/ Filter; and food products, which are in mg/kg.

" All samples are the results of single deternunations.

• Controllimits are based or. Attachment A, page A2 of this report.

(  ! NOTE: For fish, Jello is used for the ' spike matrix. For vegetation, Sawdust is used for the spike matrix.

l-r.

160

F; Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table A-4. In-house " blank" samples.

1 Concentration pCi/L*. l Teledyne Results Acceptance Lab ~ Sample Sample (4.66 Sigma) Criteria i )

Code Type - Date Analysis LLD Activity" (4.66 Sigma) '

RA-1 WATER Jan1998 Ra-226 <0.015 0.02 to.01 <1.00 RA-1 WATER Jan1998 Ra-228 <0.8745 0.66 i 0.49 <1.00 l SPW-333 WATER Jan1998 Am-241 <0.0934 0.01 i 0.07 <1.00 l SPW-495 WATER Jan1998 Gr. Alpha <0.3138 0.0010.21 <1.00 SPW-495 WATER Jan1998 Gr. Beta <0.8107 1.4710.61 < 3.20 SPW-495 WATER Jan1998 Sr-90 <0.8595 0.55 i 0.46 <1.00 1 SPMI-496 MILK Jan1998 Sr-89 <0.9576 0.60 i 0.86 < 5.00 l SPMI-496 MILK Jan1998 Sr-90 N/A 0.8110.30 <1.00 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-593 WATER . Jan 1998 H-3 <156.02 10.41 i 77.82 < 200.00 SPAP-5331 AIR FILTER Jan1998 Cs-137 <0.0009 0.00 i 0.00 < 10.00 SPW-1662 WATER Feb1998 Ra-226 <0.0134 0.04 i 0.01 <1.00 SPW-1662 WATER Feb1998 Ra 228 <0.889 0.3910.55 <1.00 SPW-793 WATER Feb1998 I-131 <0.3448 -0.35 i 0.14 < 0.50 SPMI-794 MILK Feb1998 I-131 <0.3849 -0.01 i 0.19 <0.50 SPAP 749 AIR FILTER Feb1998 Gr. Beta <0.6 0.11 i 0.38 < 3.20 SPW 1664 WATER Mar 1998 Ra-226 <0.0197 0.03 i 0.01 <1.00 SPAP-1729 AIR FILTER Mar 1998 Gr. Beta <0.0014 0.00 i 0.00 < 3.20 SPW-1997 WATER Apr1998 Ra-226 <0.0139 0.01 i 0.01 <1.00 SPW-2279. WATER Apr1998 H-3 <156.87 54.22 i 80.20 < 200.00 SPW-2285 WATER Apr1998 Gr. Alpha <0.3124 -0.0610.20 <1.00 SPW-2285 WATER Apr1998 Gr. Beta <0.8822 -0.36 i 0.57 < 3.20 SPMI 5450 MILK Apr1998 Cs-137 <5.27 0.53 i 2.64 < 10.00

' SPW-5458 WATER Apr1998 Co-60 <1.63 -1.93 15.90 < 10.00 SPW-5458 WATER Apr1998 Cs-137 <4.01 0.46 i 3.07 < 10.00 SPW-2976 WATER May1998 Ra-226 <0.0115 0.0110.01 <1.00 SPW-2976 WATER May1998 Ra-228 <0.865 0.15 i 0.42 <1.00 SPAP-3042 AIR FILTER May1998 Cs-137 <0.0010 0.00 i 0.00 < 10.00 SPW-3044 WATER May1998 Gr. Alpha <0.5036 -0.1810.25 <1.00 l l

SPW-3044 WATER May 1998 Gr. Beta <1.1494 0.1410.64 < 3.20 SPW-4161 WATER Jun1998 Ra 226 <0.0203 0.05 i 0.01 <1.00 SPW-4161 WATER Jun1998 Ra-228 <0.802 0.22 i 0.40 <1.00 SPW-5339 WATER Jun1998 Gr. Alpha <0.4785 0.1010.32 <1.00 SPW-5339 WATER Jun1998 Gr. Beta <1.0833 1.04 i 0.74 < 3.20 l

161

Fi Davis-Besse Nuclear Power Stction 1998 Annual Radiological Environment 51 Operating Report L

l Table A-4. . In-house " blank" samples.

l Concenuation pCi/L*.

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity * (4.66 Sigma)

SPW-4719 WATER Jul1998 Ra-226 <0.0117 0.05 i 0.01 <1.00 SPW-4719 WATER Jul1998 Ra-228 <0.435 0.39 i 0.25 <1.00 SPCH-5128 CHARCOAL Jul1998 I-131(g) <0.0088 -0.00 i 0.01 < 9.60 CANISTER SPMI-5130 MILK Jul1998 Co-60 <2.60 -1.09 i 25.30 < 10.00 SPMI-5130 MILK Jul1998 Cs-137 <4.43 -1.51 i 2.69 < 10.00 SPMI-5130 MILK Jul1998 I-131 <0.444 -0.14 i 0.24 <0.50 SPMI-5130 MILK Jul1998 I-131(g) <6.94 -1.71 i 7.03 < 20.00 SPMI-5130 MILK Jul1998 Sr-90 N/A 1.32 i 0.37 <1.00 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-5132 WATER Jul1998 H-3 <157 -81.70 i 74.15 < 200.00 SPW-5135 WATER Jul1998 I-131 <0.2796 -0.0610.15 <0.50 SPW-5135 WATER Ju11998 Co60 <1.90 3.26 i 3.92 < 10.00 SPW-5135 WATER . Jul1998 Cs-137 . <3.29 1.11 i 2.93 < 10.00 SPW-5135 WATER Jul1998 I-131(g) <8.41 2.66 t7.66 < 20.00 SPW-5135 WATER Jul1998 Gr. Alpha <0.3589 0.4910.27 <1.00 SPW 5135 WATER Jul1998 Gr. Beta <0.8127 0.79 i 0.55 < 3.20 SPW-6093 WATER Aug1998 Gr. Alpha <0.3766 .0.1010.32 <1.00 SPW-6093 WATER Aug1998 Gr. Beta <1.741 -0.34 i 0.84 < 3.20 SPW-6093 WATER Aug1998 Ra-226 <0.0166 0.05 i 0.01 <1.00 SPW-6093 WATER Aug1998 Ra-228 <0.670 -0.05 i 0.30 <1.00 SPW-7145 WATER Sep 1998 Gr. Alpha <0.2485 0.19 i 0.19 <1.00 SPW-7145 WATER Sep 1998 Gr. Beta <0.7483 0.3910.53 < 3.20 SPW-7145 WATER Sep1998 Ra-226 <0.0192 0.02 i 0.01 <1.00 SPW-7145 WATER Sep1998 Ra-228 <0.997 0.0310.56 <1.00 SPAP-7395 AIR PILTER Sep 1998 Gr. Beta (ss) <0.002 -0.00 i 0.00 <0.00 SPMI-7593 MILK Sep1998 Cs-137 <5.41 1.47 i 3.56 < 10.00

. SPMI-7593 MILK Sep1998 I-131 <0.4127 -0.26 i 0.22 < 0.50 SPMI-7593 MILK Sep1998 I-131(g) <9.60 4.12 1 24.90 < 20.00 SPW-7595 WATER Sep 1998 Co.60 . <4.60 2.32 ii.34 < 10.00 SPW-7595 WATER Sep1998 I-131 <0.2981 -0.22 i 0.15 <0.50 SPW-7595 WATER Sep1998 I-131(g) <8.71 2.82 i 6.66 < 20.00 SPVE-7597 VEGETATION Sep1998 I-131(5) <0.0166 -0.00 i 0.00 < 20.00 SPW-8180 WATER Oct1998 Ra-226 N/A 0.05 i 0.01 <1.00 SPW-8180 WATER Oct1998 Ra-226 < 0.0209 0.05 i 0.01 <1.00 162

Davis-B:sse Nuclear Power St:. tion 1998 Annu:1 Radiologicd Environmental Operating Report t

1

-)

I 1

, Table A-4. In-house " blank" samples.

Concentration pCi/L*,

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria I Code Type- Date Analysis LLD Activity" (4.66 Sigma)

SPW-8180 WATER Oct 1998 Ra-228 < 0.840 0.67 i 0.47 <1.00 SPW-9388 WATER Novi998 Gr. Alpha <0.74 0.2710.48 <1.00 l SPW-9388 WATER Nov 1998 Gr. Beta <1.99 1.04 i t.24 < 3.20

' SPW-9388 WATER Novl998 Ra-226 < 0.0203 0.04 i 0.01 <1.00

l. SPW-9388 WATER Nov1998 Ra-228 <0.932 0.32 i 0.56 <1.00 l _ SPW-10344 WATER Nov1998 H-3 <175 -8.13 i 86.41 < 200.00 f SPW-10339 WATER Dec1998 Gr. Alpha <0.95 -0.65 i 0.57 <1.00 SPW-10339 WATER Dec1998 Gr. Beta : <1.80 -0.28 i 1.18 < 3.20 SPW-10339 WATER Dec1998 Ra-226 <0.0261 0.02 i 0.01 <1.00

l. SPW-10339 WATER Dec1998 Ra-228 <0.83 0.24 i 0.42 <1.00 l

l

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

• The activity reported is the net activity result.

i

(

l L

1 l

I .

I 163 1

l __

p:--

- Davis-B:sse Nuclear Power Station 1998 Annual Radiological Environment:1 Opettting Report i

l' l

j Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second ~ Averaged -

l Codes * ' Date Analysis Result Result Result '

WW 10052,10053 Jan,1998 Gr. Beta . 1.1720

• 0.6030 2.1820 0.6630 1.6770

• 0.4481 CF-20,21 Jan,1998' Gr. Beta ' 17.5458 0.5866 17.6346 0.5614 17.5902 0.4060 CF-20,21 -Jan,1998 K-40 21.1870 0.6570 20.8610

• 0.7520 21.0240 0.4993

. CF-20,21 Jan,1998 Sr-90 0.0302

• 0.0085 0.0298 0.0071 0.0300

• 0.0055 WW-195,1% Jan,1998 Gr. Beta 2.9349 0.6584 2.9020 0.6291 2.9185 0.4553

- SW-298, 299 Jan,1998 ' H-3 144.2200

• 93.5400 92.1100 91.4500 118.1650

• 65.4080 l SW-349, 350 Jan,1998 Co-60 1.1100 9.1700 1.7900

• 2.4700 1.4500

• 4.7484 SW-349, 350 Jan,1998 Cs-137 -2.4900

• 3.2300 -0.6700 2 1.9400 -1.5800 i 1.8839 l CW-737,738 Jan,1998 H-3 559.2800

• 100.4400 524.8100

• 99.1900 542.0450

• 70.5812

l. PW-607,608 'Jan,1998 Co-60 0.3400 0.0340 0.7200

• 4.6200 0.5300

• 2.3101 L ' PW-607,608 Jan,1998 Cs-137 1.1700 1.8100 -0.0400

• 1.8700 0.5650 1.3012 SWU-531, 532 Jan,1998 Gr. Beta 3.4928 0.6902 3.9923 0.7129 3.7426

• 0.4 % 1 l

LW-653, 654 Jan,1998 Gr. Beta 2.3404

• 0.5778 1.6742

• 0.5968 2.0073 0.4153 SW-587, 588 ' Feb,1998 Gr. Beta 3.2097 0.7915 2.1021 0.7800 2.6559 0.5556 i WW-897, 898 Feb,1998 Co-60 0.2600

• 0.4800 0.4700

• 4.5900 0.3650 2.3075 -

WW-897, 898 - Feb,1998 Cs-137 0.2800

• 1.8700 0.3200 2.5200 0.3000 1.5690 NW-897, 898 Feb,1998 H-3 4,582.7400

• 197.9300 5,013.4400

• 205.6500 4,798.0900 142.7132 CW-920,921 Feb,1998 Gr. Beta 8.1600

• 1.3000 8.5200 1.3000 8.3400 2 0.9192 CW 920,921 Feb,1998 Gr. Beta 0.2500

• 1.2100 0.0000 1.2000 0.1250

• 0.8521 CW-1378,1379 Mar,1998 Gr. Beta 2.6100

• 1.3700 4.1400

• 1.5800 3.3750 1.0456 CW 1378,1379 Mar,1998 Gr. Beta -0.1000 1.1000 0.0000

• 1.2000 -0.0500

• 0.8139 MI-1552,1553 Mar,1998 K-40 1,392.5000 2 133.0000 1,280.8000

• 204.0000 1,336.6500

• 121.7631 i WW-1406,1407 Mar,1998 Gr. Beta 7.0991

• 0.8467 7.0712

• 0.5658 7.0852

• 0.5092 Mar,1998 Gr. Beta LW 1921,1922 2.9722 2 0.6466 2.5972

• 0.6466 2.7847 0.4572

( AP-2599,2600 Mar,1998 Co-60 -0.0003 0.0004 -0.0003 0.0002 -0.0003

• 0.0002 l AP-2599,2600 . Mar,1998 Cs-137 -0.0001

• 0.0004 0.0001

• 0.0005 0.0000

• 0.0003 SW-2040, 2041 . Mar,1998 H-3 6,004.3600 224.0000 6,322.4700

• 229.1400 6,163.4150 160.2195 SW - 2040,2041' h r,1998 -H3 6,322.4678

• 229.1356 6,004.3639

• 224.0020 6,163.4158

• 160.2186 l

AP-2620,2621 Mar,1998 Co-60 0.0005 0.dOO4 0.0009 0.0027 0.0007 0.0013

'AP-2620,2621 Mar,1998 Cs-137 - 0.0005

• 0.0005 -0.0000

• 0.0006 0.0002

• 0.0004

. LW-2253,2254 Mar,1998 Gr. Beta 1.9075

• 0.7042 2.1691

• 0.7478 2.0383

• 0.5136 l.

AP-2487; 2488 Mar,1998 Be-7 0.0569 0.0071 0.0601 t 0.0008 0.0585

• 0.0035 E-1966,1%7 - Apr,1998 Gr. Beta 1.1740

• 0.0530 1.1530

• 0.0530 1.1635

• 0.0375 E 1966,1%7 Apr,1998 - K-40 1.3900 0.1300 1.2422

• 0.1700 1.3161

• 0.1070 AP-2466,2467 Apr,1998 Be-7 0.0693 0.0158 0.0605

• 0.0113 0.0649

• 0.0097 WW-2012, 2013 Apr,1998 - Co-60 0.6300

• 0.6200 2.6700 2.3500 1.6500 1.2152 l

i L

164 l

1

Davis-Besse Nuclear Power Station 1998 Annu 1 Radiologic 11 Environrnenti Oper ting Report Table A-5. ' In-house " duplicate" samples.

Concentration in pCi/1' Lab Sample First Second Averaged Codes

• Date Analysis Result Result Result '

WW-2012, 2013 Apt,1998 Cs-137 0.5800

• 1.5600 1.2800 2.2800 0.9300 13813 WW-2012, 2013 Apr,1998 H-3 616.5800 100.3800 646.9400 101.4600 631.7600

• 71.3622

' MI-2112,2113 Apr,1998 I131 -0.0500

• 0.1600 -0.0500 0.1700 -0.0500 0.1167 ,

CW-2225,2226 Apr,1998 Gr. Beta 1.8900

• 1.4200 2.6400 1.4100 2.2650 1.0006 )

CW-2225,2226 Apr,1998' Gr. Beta -1.2600 1.0300 0.1500 1.2500 -0.5550

• 0.8098 I SWU-2302, 2303 Apr,1998 Gr. Beta 3.4606

• 0.6485 3.2027 0.6811 3 3317 2 0.4702 SWU-2302, 2303 Apr,1998 H-3 4353500

• 96.3410 .i933260

• 102.1870 514.3380

• 70.2207 CW-2325,2326 Apr,1998 Gr. Beta 16.1700 t 2.4300 14.3400 2.1600 15.2550

• 1.6256 )

CW-2325,2326 Apr,1998 Gr. Beta 5.0100 1.5900 5.9000

• 1.7300 5.4550 1.1748 j BS-2508, 2509 Apr,1998 Cs-137 0 3186

• 0.0538 0.2849

• 0.0601 0.3018

• 0.0403 BS-2508, 2509 Apr,1998 Gr. Alpha 15.5814

• 2.8742 15.4353

• 5.7607 15.5084 3.2190 BS-2508, 2509 Apr,1998 Gr. Beta 26.4292 2.2859 30.1462

• 4 3906 28.2877 2.4750 )

BS-2508, 2509 Apr,1998 K-40 18.6870 1.2400 17.6740 t 0.9500 18.1805

• 0.7810 BS-2508, 2509 Apr,1998 St-90 0.0490

• 0.0150 0.0280

• 0.0130 0.0385

• 0.0099 i G-2531,2532 Apr,1998 Cs-137 0.2387 0.0353 0.2089

• 0.0182 0.2238 0.0199 G-2531,2532 - ' Apr,1998 K-40 10.2470

• 0.5750 93951 03670 9.8211

• 0 3411 i)W-2790, 2791 'Apr,1998 Gr. Alpha 03001 0.2051 0.1634 0.2668 0.2318 0.1683 DW-2790,2791 Apr,1998 Gr. Beta 0.5947

• 0.2942 0.7350

• 0.3478 0.6649

• 0.2278 MI-2368,2369 Apr,1998 K-40 1,176.4000 162.0000 1,374.6000

• 108.0000 1,275.5000 973499 MI-2368,2369 Apr,1998 Sr-89 0.2160

• 1.0300 -03060 1.2300 -0.0450

• 0.8022 MI-2368,2369 Apr,1998 Sr-90 1.5430

• 0.4910 1.1744 0.4060 1.3587

• 0 3186 CW-2411,2412 Apr,1998 Gr. Beta 2.2800

• 1.0500 3.0100

• 1.5100 2.6450 0.9196 SWU-2067, 2068 Apr,1998 Gr. Beta 2.4865

• 0.7089 3 3197

• 0.6627 2.9031 0.4852 SS.2666, 2667 Apr,1998 Cs-137 0.0395 0.0194 0.0299 0.0133 0.0347

• 0.0118 SS-2666, 2667 Apr,1998 Gr. Beta 9.0977 2.0893 6.7058

• 1.9219 7.9018

• 1.4194 SS-2666, 2667 Apt,1998 K-40 5.3384 0.2820 5.9439

• 0.4020 5.6412 0.2455 WW-2701, 2702 Apr,1998 H-3 184.5500

• 86.5200 223.1700

• 88.1500 203.8600 61.7579 l

WW-2850, 2351 Apr,1998 CcHK) -0.1700

• 1.6000 -0 3400

• 6.3800 -0.2550 3.2888 WW-2850, 2851 Apr,1998 Cs-137 0.2900

• 2.4800 2.1600

• 2.0300 1.2250

• 1.6024 l

WW-2850, 2851 . Apr,1998 H-3 5,665.6200 217.4400 5,770.5600 t 219.2100 5,718.0900

• 154.3804 SS-3004,'3005' Apr,1998 Gr. Alpha 6.6840 t 4.0000 6.9820

• 4.4020 6.8330 2.9740 SS-3004, 3005 Apr,1998 Gr. Beta 19.9460

• 3.1700 20.7720

• 3.1970 20 3590 i 2.2511 I SS-3004, 3005 Apr,1998 K-40 15.1560

• 0.9910 13.9010

• 0.5860 14.5285 0.5756 BS-3240,3241 - Apr,1998 Gr. Beta 7.5126 1.9277 8.4047

• 1.9386 7.9587 1.3669 BS-3240, 3241 Apr,1998 K-40 10.2890

• 0.5380 10.1520 03430 10.2205 2 0.3190 MI-2941,2942 May,1998 K-40 1,2093000 2 152.0000 1,422.5000

• 193.0000 1,315.9000 122.8342 165 L' .

P f: D.vis-Bisse Nuclear Power Station 1998 Annual Radiological Environmental Operating Rtport l '

L Table A-5. In-house " duplicate" samples.

_ Concentration in pCi/I'-

t Lab Sample First Second Averaged I

. Codes

• Date Analysis Result Result Result '

l~ SO-2%2, 2963 May,1998 Cs 137 0.1835

• 0.0463 0.1531

• 0.0261 0.1683

• 0.0266 l

S 0 2962, 2963 - May,1998 Gr. Alpha 9.7590

• 3.4730 10.3360 3.5720 10.0475

• 2.4910

]

S O-2962, 2963 - May,1998 Gr. Beta 27.2230

• 2.8430 31.4690 3.0280 29.3460 2.0767 I SO 2962,2963 May,1998 ~ K-40 ' 23.0890

• 1.1600 21.6540

• 0.8142 22.3715 t 0.7086 -

SO 2962,2963 May,1998 ' Sr-90 0.0421 0.0117 0.0396

• 0.0146 0.0408

• 0.0094 LW-3048, 3049 May,1998 Gr. Beta 1.9020 i 0.6920 2.0920

• 0.7010 1.9970

• 0.4925 WW-3097, 3098 May,1998 Gr. Beta 4.6000 0.6640 4.4740 t 0.6600 4.5370 0.4681 WW - 3173,3174 May,1998 H-3 155.2485

• 83.4086 153.4076

• 83 3273 154.3280

• 58.9500

, F-3305,3306 May,1998 Gr. Beta 2.9966

• 0.1303 2.8744

• 0.1364 2.9355 0.0943 F-3305,3306 May,1998 K-40 2.5354

• 0.3690 2.5317

• 0.4260 2.5336

• 0.2818 SS-3463, 3464 May,1998 K-40 13.2060

• 0.6940 12.1740

• 0.5670 12.6900 0.4481 F - 3284,3285 May,1998 Co-60 0.0073 2 0.0286 -0.0054 0.0097 0.0009 2 0.0151 F - 3284,3285 May,1998 Cs-137 -0.0001

• 0.0047 0.0080 0.0095 0.0039 t 0.0053

- CW-3439,3440 May,1998 Gr. Beta 2.1268

• 1 3641 2.0093

• 1.1263 2.0681

• 0.8845 G-3546,3547 May,1998 Be-7 0.7130

• 0.2340 0.6940 0.1850 0.7035

• 0.1491 G-3546,3547. . May,1998 Gr. Beta - 10.7190 0.3340 10.9340 0.3370 10.8265 t 0.2372 J-3546,3547 May,1998 K-40 7.5468

• 0.5310 7.8713

• 0.6930 7.7091

• 0.4365 BS-3669, 3670 May,1998 Cs-137 0.2010

• 0.0535 0.2022

• 0.0215 0.2016

• 0.0288 BS-3669, 3670 May,1998 ' K-40 14.9080 0.4820 16.1580 1.0800 15.5330

• 0.5913 F-3694,3695 ' May,1998 K-40 1.7695

• 0.2850 1.6797 0.3440 1.7246

• 0.2234 PW - 3572,3573 May,1998 H-3 49.8073

• 97.6829 83.0122

• 98.9291 66.4098

• 69.5142 WW - 3763,3764 May,1998 Co-40 0.0478

• 0.0234 0.0551

• 0.0311 0.0515

• 0.0195 WW - 3790,3791 May,1998 Co-60 -0.0847 i 0.6250 0.5220 10.9000 0.2187 5.4590 l WW - 3790,3791 May,'1998 Cs 137 - 0.9210

• 1.9700 1.1200

• 1.5000 1.0205 1.2380 W W -3790,3791 May,1998 H-3 723.8914

• 114.0882 705.2824 113.4795 714.5869

• 80.4576

' F - 3715,3716 May,1998 Co40 0.0048

• 0.0567 0.0077

• 0.0214 0.0015

• 0.0303

)

F - 3715,3716 May,1998 Cs-137 0.0015

• 0.0090 0.0127

• 0.0137 0.0071

• 0.0082 BS - 3763,3764' May,1998 Cs-137 0.0884

• 0.0206 0.0754

• 0.0257 0.0819 0.0165

' SWU-3882, 3883 May,1998 Gr. Beta 2.9052 2 0.6786 3.7390 2 0.6595 33221 0.4731 SWU-3882, 3883 May,1998 H-3 43.3000

• 79.9590 34.1540

• 79.5400 38.7270 56.3916 CW - 4314,4315 May,1998 H-3 441.3905 %.6703 424.7922 * % .0349 433.0913 68.1319 .

F-3861,3862 May,1998 K-40 3.2973 0.5280 3.6404 03530 3.4689

• 0.3176

~ CW-4044,4045 May,1998 Gr. Beta 4.6775 1.6138 4.8186 1.6342 4.7481

• 1,1484 l-CW - 4044,4045 May,1998 Gr. Beta -0.7495 1.2072 -0.6833

• 1.0704 -0.7164

• 0.8067

- SW-4020, 4021 Jun,1998 K-40 (FP) 1.0380 1.0380 1.0380 AP-4111,4112 Jun,1998' _ Be-7 0.1860

• 0.0833 0.2650

• 0.1120 0.2255

• 0.0698 166 i

y Dwis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table A-5. In-house " duplicate" samples.

Concentration in pCl/L' Lab Sample . First Second Averaged Codes

• Date Analysis Result Result Result P-4183,4184 ' Jun,1998 H 22.7850 81.0520 44.7120 81.6170 33.7485 2 57.5125 CW - 4195,41% . Jun,1998 Gr. Beta 2.9189

• 1.4811 2.8922 t 1.4740 2.9055

• 1.0448 l . CW - 4195,41% ;Jun,1998 Gr. Beta ~ -0.4892 1.0638 -0.4909 1.1091- -0.4900 2 0.7684 W W 4410,4411 Jun,1998 Gr. Beta 4.9907 0.7658 5.7601

• 0.8338 5 3754

• 0.5661 WW-4410, 4411 Jun,1998  : H-3 -5.3910

• 77.2770 ' 66.4880

• 80 5500 30.5485 55.8123 MI- 4389,4390 Jun,1998 Co-60 0.1420

• 0.2080 1.4200

• 13.6000 . 0.7810

• 6.8008

-MI-4389,4390 - Jun,1998 Cs-137 0.1810

• 2.7600 0.6020 4.0700 0.3915

• 2.4588

. MI-4389,4390 Jun,1998 I131 -0.0469

• 0.2433' -0.1152

• 0.2559 -0.0811

• 0.1765

' AP-4664,4665 Jun,1998 Be-7 0.1539

• 0.0750 0.2627

• 0.1220 - 0.2083 0.0716 MI-4685,4686 < Jun,1998 I-131 -0.1010

• 0.1620 -0.0221 0.1728 -0.0616 0.1184 SW - 4901,4902 Jun,1998 H-3 2,541.2239

• 156.4571 2,510.5125 155.7462 2,525.8682

• 110.3808

- AP-5188,5189 ~Jun,1998 Be-7 0.0844 0.0163 0.0733

• 0.0117 0.0789

• 0.0100 SWU-4798, 4799 Jun,1998 Gr. Beta 1.9402 0.5398 1.8412

• 0.5411 1.8907

• 0.3822 LW-4993,4994 Jun,1998 Gr. Beta 3.1224

• 0.6129 2.0740

• 0.5328 2.5982

• 0.4061 LW-4993, 4994 Jun,1998 H-3 3,543.4600

• 184.5020 3,482.0770

• 183.2600 3,512.7685

• 130.0242 WW-4819, 4820 Jul,1998 Gr. Beta 1.2760

• 0.6431 0.7313

• 0.6161 1.0037

• 0.4453 iW-4819,4820 Jul,1998 K-40 0.8650

• 0.0865 0.9515

• 0.0950 0.9083

• 0.0642

- AP-5209,5210 . Jul,1998 Be-7 0.1079

• 0.0180 0.0901 0.0107 0.0990

• 0.0105 AP-5392,5393 - Jul,1998 Be-7 0.0782

• 0.0143 0.0885 0.0144 0.0833 0.0101 AP-5413,5414 " Jul,1998 Be-7 0.0625 0.0072 0.0718

• 0.0091 0.0671 0.0058 WW-4848, 4849 Jul,1998 Co-60 0.2220

• 0.1290# 0.5080 0.8150 0.3650

• 0.4126

- WW-4848, 4849 - Jul,1998 Cs 134 0.9310

• 2.0500 0.8130

• 0.8130 0.8720

• 1.1027 WW-4848,4849 ' Jul,1998 Cs-137 0.7040 1.8700 -0.1190

• 1.8300 0.2925

• 1.3082 WW-4848, 4849 Jul,1998 H-3 37.2000 t 89.2000 -13.0000 87.0000 12.1000

• 62.3010 l

CW-4947,4948 ' Jul,1998 Gr. Beta 5.2400

• 1.5700 5.1900

• 1.5700 5.2150

• 1.1102 SW 7804,7805 Jul,1998 Gr. Alpha 0.3147

• 0.6025 1.7030 0.5568 1.0089

• 0.4102

- SW-7804,7805 Jul,1998 Gr. Beta 2.0032

• 0.7183 2.5489

• 0.6474 2.2761

• 0.4835 W W-4880,4881 Jul,1998 Co-60 0.2540

• 0.6210 -0.4430

• 0.8250 -0.0945 0.5163 W W-4880,4881 Jul,1998 Cs-137 1.4600 1.2800 1.1400 2.0000 1.3000 1.1873 WW-4880, 4881 Jul,1998 H-3 308.5000

• 102.7000 328.9000 103.5000 318.7000

• 72.9033 G-5090,5091 Jul,1998 Be-7 1.5334

• 0.2310 1.5696

• 0.2550 1.5515

• 0.1720 G-5090,5091 . Jul,1998 K-40 6.2521

• 0.4900 6.0430 0.4800 6.1476

• 0.3430 l SW 5281,5282 Jul,1998 Gr. Alpha 5.7564 1.0355 5.4517 0.9702 5.6041 0.7095 SW-5281, 5282 Jul,1998 Gr. Beta 8.8798

• 0.7835 9.9157 0.8418 9 3978

• 0.5750 SW-5281,5282 Jul,1998 H-3 12.9950

• 87.9900 46.4090

• 89.3890 29.7020 62.7149

/E-5323,5324 Jul,1998 K-40 9.4179 t 0.7440 8.3494 0.4700 8.8837

• 0.4400 f

167

e l

Davis-B sse Nuclear Power St: tion' 1998 Annual Radiological Environment:1 Oper ting Report i

Table A-5. -In-house " duplicate" samples.

Concentration in pCi/L' Lab- . Sample First- Second - Averaged Codes

• Date Analysis Result Result Result '

SWU-5744, 5745 Jul,1998 Gr. Beta 2.0648

• 0.5650 2.4432 0.6352 2.2540 0.4251 VE-5302,5303 J41998 Gr. Alpha 0.1233 0.0458 0.0816 0.0381 0.1025 t 0.0298  ;

VE-5302,5303 Jul,1998 - Gr. Beta 3.8738

• 0.1201 3.4382

• 0.1081 3.6560

• 0.0808 VE-5302,5303 Jul,1998 K-40 3,845.0000 384.0000 3,561.0000 419.0000 3,703.0000 284.1729 l j G-5346,5347 Jul,1998 Be-7 1.0649 0.3460 1.1877

• 0.2220 1.1263 i 0.2055 G-5346,5347 J41998 Gr. Beta 5.5890

• 0.2200 5.4932

• 0.1571 55411 0.1352 ,

G-5346,5347 Jul,1998 K-40 5.8497 2 0.7760 6.4013

• 0.5600 6.1255 2 0.4785 AP-5371,5372 Jul,1998 Be 7 0.2899 t 0.0987 0.2565 t 0.0949 0.2732 0.0685 AP-5530,5531 J41998 Be-7 0.2559

• 0.0941 0.3365

• 0.0984 0.2 % 2 0.0681

S O-5556, 5557 J41998 Gr. Beta 17.8997

• 2.6057 15.8321

• 2.3577 16.8659

• 1.7570 CW4134,6135 Jul,1998 Gr. Beta 4.8400

• 1.2300 4.0700

• 1.0900 4.4550 0.8217 AP-5721,5722 Jul,1998 Be-7 0.2175

• 0.0616 0.2461

• 0.1180 0.2318

• 0.0666 SWU-5744,5745 - Jul,1998 H-3 - 223.9760

• 86.8830 209.4480 86.2730 216.7120 t 61.2203

)

- WW-5836, 5837 - Jul,1998 H-3 80.4980 t 80.6500 65.9720 79.9940 73.2350 56.7967

. WW-6176, 6177. Jul,1998 H-3 31.0590 x 81.2420 1.8270

• 79.9170 16.4430 56.9802 WW-6176, 6177 Jul,1998 Gr. Beta 0.6954

• 0.5544 1.3234

• 0.5462 1.0094 2 0.3891 W-5965,5966 Aug,1998 Gr. Beta 3.1093 0.6160 2.2762 t 0.6288 2.6928

• 0.4401 LW-5965,5966 Aug,1998 H-3 80.4580

• 82.3350 36.9020

• 80.3920 58.6800

• 57.5368 G-5986,5987 Aug,1998 Be-7 2.2321

• 0.3670 _ 1.9885

• 0.3010 2.1103

• 0.2373 G-5986,5987 Aug,1998 K-40 5.4909

• 0.6280 6.3514 2 0.7550 5.9212 0.4910 CW-6013,6014 Aug,1998 Gr. Beta 0.5400

• 1.2300 0.9900

• 1.2500 0.7650

• 0.8768 CW4134,6135 Aug,1998 Gr. Beta 3.2200 1.5200 4.1200 1.1600 3.6700

• 0.9560 P, - Aug,1998 Gr. Beta 2.1416 2 0.0774 1.9173 0.0791 2.0295

• 0.0553 P-6447,6448 Aug,1998 K-40 2.1309

• 0.2570 1.8657

• 0.1280 1.9983

• 0.1436 AP-6467,6468 . Aug,1998 Be-7 0.1612

• 0.0873 0.1293

• 0.1260 0.1453

• 0.0766 VE-6489,6490 Aug,1998 Cs-134 1.0300 2 1.8700 0.1500

• 0.1000 0.5900

• 0.9363 VE4489,6490 Aug,1998 Cs-137 0.9500 1.4300 0.6800 2.0400 0.8150 1.2456 AP-6722,6723 Aug,1998 Be 7 0.3063 0.1590 0.3100

• 0.0937 0.3082 2 0.0923 VE-6774,6775 - Aug,1998 Be-7 0.5894

• 0.2720 0.4208

• 0.1520 0.5051

• 0.1558 VE-6774,6775 Aug,1998 Gr. Beta 5.9406 0.1789 5.6841

• 0.1706 5.8124

• 0.1236 CW4800,6801 - Aug,1998 Gr. Beta 2.2300

• 1.4400 2.1300 1.3100 2.1800 0.9734 LW-7129,7130 Aug,1998 Gr. Alpha ' O.6433

• 0.3557 0.5551

• 0.3614 0.5992

• 0.2535 LW-7129,7130 - Aug,1998 Gr. Beta 2.4016 0.4281 2.3041 0.4447 2.3529 0.3086

- LW 7129,7130 l Aug,1998 H3 170.2100

• 87.3900 37.4100 81.5000 103.8100

• 59.7479 LW-7129,7130 Aug,1998 H-3 154.7950

• 94.8090 104.6950 92.7500 129.7450 66.3161 L 3 0-6943, 6944 Sep,1998 Co40' O.1466 0.0399 0.1452

• 0.0303 0.1459

• 0.0251 p

I8

Davis-B3sse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table A-5. In-house " duplicate" samples. ]

Concentration in pCi/L' Lab Sample First Second Averaged Codes

• Date - Analysis Result Result Result '

S O-6943, 6944' Sep,1998 Cs-137 - 15.1000 0.2000 15.7000 0.3000 15.4000 0.1803 q

- S O-6943, 6944 Sep,1998- K-40 16.5680 2 0.7660 17.3780

• 1.1000 16.9730

• 0.6702 CW-7043,7044 Sep,1998 Gr. Beta 4.5000 1.6000 - 4.9000

• 1.5000 4.7000 1.0966 VE-7250,7251 Sep,1998 Cs-134 0.0800 1.1800 0.4600

• 0.5100 0.2700

• 0.6427

. _VE-7250, 7251 Sep,1998 Cs-137 0.1300 2 0.7200 0.0100 0.3400 0.0700 0.3981 l VE-7064,7065 .Sep,1998 Cs 134 -0.1100

• 0.0800 0.1200 2 1.4900 0.0050

• 0.7461 l

VE-7064,7065 Sep,1998 Cs-137 -0.3600 0.7600 0.0200 0.8200 -0.1700 0.5590 VE-7171,7172 Sep,1998 Cs-134 0.0600

• 0.5200 -0.1300 13.1000 -0.0350

• 6.5552 VE-7171,7172 - Sep,1998 Cs-137 0.6300

• 0.5200 0.6800 2 0.8000 0.6550

• 0.4771 )

CW 7204,7205 Sep,1998 Gr. Beta 2.6900 1.4300 1.5600 1.3000 2.1250 0.9663 -)

SW-6363, 6364 - Sep,1998 Gr. Beta 4.3450

• 0.7618 4.1456

• 0.7464 4.2453

• 0.5333 SW-6363, 6364, Sep,1998 H-3 133.9370 82.9580 148.6820 83.6110 141.3095 58.8915 j VE-7279,7280 Sep,1998 K-40 2.1575

• 0.2580 2.3167

• 0.3420 2.2371 2 0.2142 )

SWU-7452, 7453 Sep,1998 Gr. Beta 4.1567 0.6600 4.1515

• 0.7395 4.1541

• 0.4956 )

F-7819,7820 Sep,1998 K-40 3.0166

• 0.3920 2.7430 0.5190 2.8798 0.3252 ]

CW 7375,7376 Sep,1998 Gr. Beta 1.7100

• 1.1500 2.2000

• 1.1900 1.9550

• 0.8274

]

iS-7598, 7599 Sep,1998 K-40 9.5919

• 0.7430 8.9290

• 0.4590 9.2605

• 0.4367 AP-7598,7599 Sep,1998 Be-7 0.0639 0.0188 0.0815

• 0.0156 0.0727 0.0122 VE-7397,7398 Sep,1998 Cs-134 0.1900 2 2.6800 0.6300 1.3500 0.4100 1.5004 VE-7397,7398 Sep,1998 Cs-137 -0.0900 i 0.9400 0.5200 0.9500 0.2150

• 0.6682 SWU-7452, 7453 - Sep,1998 H3 23.7170 2 81.6810 -19.3480

• 79.6820 2.1845

• 57.0548 SWT 7765,7766 Sep,1998 Gr. Beta 3.2443

• 0.6638 2.9078

• 0.6593 3.0761

• 0.4678

~ SW-7857,7858 Oct,1998 Gr. Beta 2.3410

• 0.7265 2.1443 0.7591 2.2427

• 0.5254 S O-7878, 7879 Oct,1998 Gr. Beta 19.3527

• 4.1969 23.2850

• 4.0731 21.3189

• 2.9242 S O-7878, 7879 Oct,1998 St-90 0.0034

• 0.0110 0.0080 2 0.0130 0.0057

• 0.0085 AP, Oct,1998 Be-7 0.0680

• 0.0527 0.0931

• 0.0702 0.0806 0.0439 WW-8073, 8074 Oct,1998 Gr. Beta 2.41 %

• 0.5973 3.1890

• 0.6509 2.8043 2 0.4417 WW-8073, 8074 Oct,1998 H-3 90.5270 84.1470 113.3172 2 85.1690 101.9221 59.8633 SS, Oct,1998 Cs-137 0.0509

• 0.0284 0.0222 0.0102 0.0365 0.0151 SS , Oct,1998 K-40 7.2289

• 0.6170 7.1271

• 0.4380 7.1780

• 0.3783 l,

l SS-8202, 8203 Oct,1998 Gr. Beta 4.5670 1.9890 '6.3930

• 2.0860 5.4800 1.4411 l: SS-8202, 8203 Oct,1998 K-40 6.9700 2 0.5400 7.1800 0.3800 - 7.0750

• 0.3302 l' WW, Oct,1998 Gr. Beta 1.0464

• 0.5347 1.4246

• 0.5276 1.2355 0.3756 WW, Oct,1998 H3 16.2610 81.9530 53.8530 83.6580 35.0670

• 58 5554 AP, Oct,1998 Be-7 0.1094

• 0.0878 0.1708 0.0934 0.1401

• 0.0641 sO-7878, 7879 Oct,1998 K-40 16.3430 0.9100 18.2150

• 1.1000 17.2790 0.7138

.169

Davis-B3sse Nuclear Power Stction 1998 Annual Radiological Environment 1 Operating Report Table A-5. In-house " dup!!cate" samples.

Concentration in pCl/1*

Lab Sample First Second Averaged Codes

• Date Analysis Result Result Result ' )

Sle8624,8625 Oct,1998 . K-40 2.0091

• 0.4260 1.9401 0.3310 1.9746

• 0.2697 SS-8689, 8690 Oct,1998 K-40 14.8820 0.8900 16.8160 t 1.2200 15.8490 0.7551 BS-8864, 8865 Oct,1998 Co-60 0.1424 0.0225 0.1313

• 0.0199 0.1368 2 0.0150 BS-8864, 8865 Oct,1998 Cs-137 0.0972

• 0.0204 0.1081

• 0.0207 0.1026

• 0.0145 BS-8864, 8865 Oct,1998 ' K 9.5076

• 0.4940 10.4040

• 0.5000 9.9558 0.3514 S O-10497, 10498 Oct,1998 K 19.0930

• 1.0800 19.7410

• 0.9100 19.4170 t 0.7061 S O-9098, 9099 Oct,1998 Cs-137 0.5240

• 0.0580 0.5300 0.0390 0.5270

• 0.0349 S O-9098, 9099 Oct,1998 K-40 17.7200

• 1.0700 18.4100

• 0.8000 18.0650 0.6680 BS-11122,11123 Oct,1998 De-7 0.4800 0.2700 0.3700

• 0.2200 0.4250 2 0.1741 BS-11122; 11123 Oct,1998 Co-60 0.0263

• 0.0084 0.0291

• 0.0090 0.0277 0.0062

- BS-11122,11123 Oct,1998 Cs-137 0.2714

• 0.0179 0.2747 0.0167 0.2730

• 0.0122 BS-11122,11123 - Oct,1998 K-40 9.0446

• 0.2600 8.9737

• 0.2760 9.0092 0.1896 VE-9182,9183 Oct,1998 Be-7 2.1684 0.4480 1.8643 0.4300 2.0164 2 0.3105 VE-9182,9183 Oct,1998 K-40 4.9628

• 0.6160 5.4867 0.6600 5.2248 0.4514 VE-9203,9204 Oct,1998 Be-7 1.9163

• 0.6090 1.9606 0.3870 1.9385

• 0.3608 VE-9203,9204 Oct,1998 Cs-137 0.2744 2 0.0568 0.2623

• 0.0361 0.2684

• 0.0337 JE-9203,9204 Oct,1998 K-40 3.9727

• 0.6770 4.0116 0.4430 3.9922

• 0.4045 S O-9119, 9120 Oct,1998 Cs 137 0.5500 2 0.0397 :0.5500

• 0.0480 0.5500 0.0311 S O-9119, 9120 Oct,1998 K-40 20.2600

• 1.0200 20.5090 t 0.8050 20.3845

• 0.6497 SO 9161,9162 Oct,1998 Cs-137 ' O.7715

• 0.0584 0.7532

• 0.0525 0.7624

• 0.0393 S O-9161, 9162 Oct,1998 K-40 18.1200

• 1.1200 20.0600

• 1.2000 19.0900

• 0.8207 I Oct,1998 Gr. Beta

.AP, 0.0246

• 0.0034 0.0262

• 0.0035 0.0254

• 0.0024 SWU, Oct,1998 H-3 161.5360 t 85.8760 157.8370

• 85.7160 159.6865 2 60.6670 SWU-9014,9015 Oct,1998 Gr. Beta 2.7210 0.6386 3.3308

• 0.6187 3.0259

• 0.4446

- MI-9035,9036 Oct,1998 K-40 1,531.4000

• 129.0000 1,426.0000 t 188.0000 1,478.7000

• 114.0011 LW-9479,9480 Oct,1998 Gr. Beta 2.0720 0.5550 1.9860

• 0.5500 2.0290 2 0.3907 BS-9349, 9350 Nov,1998 Cs-137 0.0239

• 0.0156 0.0277

• 0.0151 0.0258

• 0.0109

BS-9349, 9350 Nov,1998 Gr. Beta 8.4550 2.1970 6.4700 2.0840 7.4625

• 1.5141 BS-9349, 9350 Nov,1998 K-40 6.9294 t 0.4400 6.4650

• 0.4290 6.6972 : 0.3073 MI-9437,9438 Nov,1998 I131 -0.1516

• 0.2458 -0.0769

• 0.2776 -0.1143 0.1854 Mi-9437,9438 Nov,1998 K-40 681.2300

• 128.0000 714.6700

• 122.0000 697.9500 t 88.4138 VE-9667,9668 ' Nov,1998 Gr. Beta 4.4810 0.1970 4.3670 2 0.1940 4.4240

• 0.1382 VE-9667,9668 Nov,1998 K-40 4.2338

• 0.2840 3.7245 0.4880 3.9792

• 0.2823 SWT-10167,10168 Nov,1998 Gr. Beta 2.1779

• 0.5699 1.9517

• 0.5841 2.0648

• 0.4080 WW-9667, 9668 - Nov,1998 Gr. Beta 2.2847 0.6184 1.7189

• 0.5495 2.0018 0.4136

.iW-10069,20070 ' Nov,1998 Gr. Alpha 1.6469

• 0.5301 1.5758

• 0.5574 1.6114

• 0.3846 170 L e

s 1 Davis-Besse Nuclear Power Station 1998 Annual Radiologic 11 Environmentd Operating Rrport I

Table A-5. In-house " duplicate" samples.

Concentration in pCi/1*

Lab Sample First Second Averaged Codes

• Date Analysis Result Result Result '

SW-10069,10070 Nov,1998 Gr. Beta 3.4363 2 0.4683 3.5768 0.4928 3.5066 0.3399 MI-10146,10147 Dec,1998 K-40 1,403.6000 178.0000 1,372.9000 149.0000 1,388.2500 i 116.0657 S O-10573, 10574 Dec,1998 Cs-137 367.0300 80.5000 337.1100 32.8000 352.0700

• 43.4629 S O-10573, 10574 Dec,1998 K-40 17,459.0000

• 1,260.0000 16,004.0000 716.0000 16,731.5000

• 724.6130 MI-10686,10687 Dec,1998 ' K-40 1,320.3000

• 160.0000 1,350.3000

• 166.0000 1,335.3000 115.2779 j

! AP, Dec,1998 Gr. Beta 0.0180

• 0.0030 0.0158

• 0.0029 0.0169

• 0.0021 AP-9119,9120 Dec,1998 Be-7 0.1386 0.0876 0.1016 0.0396 0.1201 0.0481 AP-10948,10949 Dec,1998 Be-7 0.1379

• 0.0647 0.2164 0.0753 0.1772

• 0.0496 SWU-10920,10921 Dec,1998 H-3 364.3700 t 93.2290 364.3700 93.2290 364.3700

• 65.9229 AP-11079,11080 Dec,1998 Be-7 0.0680

• 0.0120 0.0680 t 0.0120 0.0680

• 0.0085 1

1 1

171

p a

, Davis-Btsse Nucl:ar Power Station 1998 - Annual!tadiolog.ical Environmental Operating Report .

Table A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP),

comparison of MAPEP and Teledyne's Midwest Laboratory results for various sample media'. i Concentration *

. Lab Sample Date Teledyne Results MAPEP Result' Control J. ode Type . Collected Analysis iStandard Deviation

• 1s, N=1 Limits j J

SPSO-628 SOIL Jan,1998. Co-57 862.20 i 86.22 1,190.00 833.00 - 1,547.00

' SPSO-823 SOIL Jan,1998 Co-60 886.60 i 88.66 1,110.00 777.00 - 1,443.00 SPSO-828 SOIL Jan,1998 Cs-137 442.80 i 44.28 552.00 386.40 - 717.60 SPSO-828 SOIL Jan,1998 K-40 540.30 i 54.03 652.00 456.40 - 847.60  ;

SPSO-828 SOIL Jan,1998 Mn-54 867.40 t 86.74 1,090.00 763.00 - 1,417.00 q

SPSO-828 SOIL Jan,1998 . Ni-63 326.10 i 32.61 405.00 283.50 - 526.50 '

SPSO-828 SOIL Jan,1998 Pu-238 52.30 i 5.23 50.60 35.42 - 65.78 i SPSO-828 SOIL Jan,1998 Sr-90 587.60 i 58.76 624.00 436.80 - 811.20 SPSO-828 - SOIL Jan,1998 U-234/233 38.20 i 3.82 51.40 35.98 - 66.82 SPSO-828 SOIL Jan,1998 U-238 105.40 i 10.54 120.00 84.00 - 156.00 )

SPSO-828 SOIL Jan,1998 ' Zn-65 2,256.80 i 225.70 2,780.00 1,946.00 - 3,614.00 i STW-814 WATER Jan,1998 Am-241 2.05 i 0.21 2.13 1.49 - 2.77 STW-814 WATER Jan,1998 Co-57 253.00 i 25.30 277.50 194.25 - 360.75 3 STW-814 - WATER Jan,1998 Co 60 133.00

• 13.30 132.46 92.72 - 172.20 STW-814 WATER Jan,1998 Cs-137 218.00 i 2.18 213.12 149.18 - 277.06 STW-814 WATER Jan,1998 Fe-55 397.80 i 39.80 492.10 344.47 - 639.73 STW 814 - WATER Jan,1998 Mn-54 221.00 i 22.10 221.63 155.14 4288.12

- STW-814 WATER Jan,1998 N1-63 265.50

• 26.50 358.90 251.23 - 466.57 STW-814 WATER Jan,1998 Pu-238 1.27i 0.13 1.40 0.98 - 1.82 STW-814 WATER Jan,1998 Pu-239/240 3.16 i 0.32 ' 3.44 2.41 - 4.47 STW-814 WATER Jan,1998 Sr-90 33.40 i 3.34 32.12 22.48 - 41.76 STW-814 WATER Jan,1998 U-234/233 3.2410.32 3.60 2.52 - 4.68

STW-814 WATER Jan,1998 U-238 0.0910.01 0.00 0.00 - 0.10 STW-814 ' WATER Jan,1998 Zn-65 612.00 i 61.20 588.30 411.81 - 764.79 '

' Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program,'

Idaho Operations office, Idaho Falls, Idaho.

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

• Unless otherwise indicated, the TBEESML results are given as the mean i l standard deviations for three determinations.

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma 1 determination) and controllimits as defined by the MAPEP.

i 1

172

P 1 1

l

. Davis.Besse Nuclear Power St^ tion 1998 Annual Radiologicel Environmental Operating Report {

{

(

l L:

j l Table A'-7. Environmental Measurements Laboratory Quality Assessment Program (EML),-

L comparison of EML and Teledyne's Midwest Laboratory results for various sample media *.

Concentration in Bq/L'

-Lab Sample . Date Control d

' Code Type Collected Analysis Teledyne Result' EML Result Limits' STSO-834_ SOIL Sep,1998 K-40 296.20

• 39.90 314.00

• 13.00 0.73 - 1.67 STSO-834 . SOIL Sep,1998 Pb-212 53.60

• 1.50 52.80 3.70 0.50 - 1.50 STSO-834 SOIL Sep,1998 Pb-214 31.00

• 5.90 29.10

• 1.20 0.50 - 1.50 STSO-834 SOIL Sep,1998 Sr-90 37.40

• 1.90 39.63 0.00 0.46 - 2.84 STSO-834 SOIL Sep,1998 TI-208 20.10 3.10 18.30

• 1.10 0.50 - 1.50 STW-835 WATER Sep,1998 Co-60 49.30 2.80 49.40 1.20 0.92 - 1.18 STW-835 WATER Sep,1998 Cs-137 50.10

• 3.20 50.00 1.70 0.90 - 1.28  ;

. STW-835 WATER Sep,1998 Fe-55 140.60

• 9.20 139.00

• 2.00 0.31 - 1.54 STW-835 WATER - Sep,1998 Gr. Alpha 1,178.30

• 47.20 1,080.00 60.00 0.50 - 1.29 STW-835 WATER Sep,1998 Gr. Beta 1,613.60

• 171.80 1,420.00

• 60.00 0.60 - 1.64 )

STW-835 - WATER Sep,1998 H-3 102.20

• 4.50 76.20

• 2.90 0.65 - 1.91 j STW-835 WATER Sep,1998 Mn-54 35.90

• 3.40 32.40

• 1.40 0.87 - 1.22

' STW-835 WATER Sep,1998 Sr-90 3.00 0.90 2.11 0.18 0.72 - 1.66 STAF-837 AIR FILTER Sep,1998 Co-60 9.30 0.30 9.16

• 0.58 0.74 - 1.24

'5FAP-837 AIR FILTER Sep,1998 Cs-137 22.40

• 0.50 22.47

• 1.03 0.72 - 1.32 FTAF-837 AIR FILTER Sep,1998 Mn-54 5.30

• 0.30 4.92 0.40 0.75 - 1.27 STAF-837 AIR FILTER Sep,1998 Sb-125 10.00 2 0.80 8.89 0.55 0.60 - 1.39 STAF-838 AIR FILTER Sep,1998 Gr. Alpha 2.20 0.10 1.65 0.16 0.83 - 1.55 STAF-838 AIR FILTER Sep,1998 Gr. Beta 2.80 0.10 2.16

• 0.07 0.73 - 1.84 STAF-838 _ AIR FILTER Sep,1998 Sr-90 1.10

• 0.10 1.12

• 0.05 0.66 - 2.65 STVE-839 VEGETATION Sep,1998 Co-60 18.10 1.50 20.00

• 1.00 0.62 - 1.42 ]

STVE-839 VEGETATION Sep,1998 Cs-137 340.40

• 4.80 390.00 20.00 0.81 - 1.45 STVE-839 VEGETATION Sep,1998 K-40 417.50

• 28.20 460.00

• 20.00 0.79 - 1.50 STVE-839 VEGETATION Sep,1998 Sr-90 672.50

• 32.50 606.00 40.00 0.48 - 1.29

• %e Environmental Measurements Laboratory provides the following nuclear species : Air Filters, Soil, Tissue, Vegetation and Water. Teledyne does not participate in the Tissue program.

• Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/Filte(', Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg. The results of elemental Uranium are reported in ug/ filter', g, or ml.

• Teledyne results are reported as the mean of three determinations

• standard deviation.

' he EML result listed is the mean of replicate determinations for each nuclidetthe standard error of the mean.

• The control limits are reported by EML and are established from percentiles of historic data distributions (1982-1992). The evaluation of this historic data and the development of the control limits is presented in DOE report EML-564.

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s APPENDIX B '

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' DATA REPORTING CONVENTIONS '

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Davis-Besse Nuclear Power St: tion 1998 Annu:J Radiological Environmental Operiting R: port Data Reporting Conventions 1.0. All activities except gross alpha and gross beta are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows:

xis

,- where x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is found to be below the lower limit of detection L it is reported as

<L where L = the lower limit of detection based on 4.66a uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: x1 s1 x2 i s2 Reported result x s where x = (1/2)(x1 + x2) s = (1/2) k sf + s$

3.2. Individual results: <Li

<L2 Reported result: <L where L = lower of L1and L2 3.3. Individual results: x i s

<L Reported result: x i s if x L;

<L otherwise 175

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Davis Brsse Nuclear Power Station 1998 Annui! Radiological Environmentd Operating Report I

l 4.0 Computation of Averageaand Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2. . . xn are defined as follows:

Ic=hx

,, (x- x)2 n-1 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all of the 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 erroris reported.  ;

I 4.5 In rounding off, the following r.tles are followed:

4.5.1. If the figure following those to be retained is less than 5, the figure is drcpped, and the retained figures are kept unchanged. As an example,11.443 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.

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b Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report I

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l APPENDIX C Emuent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas I

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f l Davis-Besse Nucle:r Power Station 1998 Annual Radiological Environmentti Operating Report t, Table C-1 Emuent Concentration Limit of Radioactivity in Air and Water l Above Natural Background in Unrestricted Areas' Air Water

(

l Gross Alpha IE-03 pCi/m3 Strontium-89 8,000 pCi/l Gross Beta i pCi/m3 Strontium-90 500 pCi/l 6

Iodine-131 2.86E-01 pCi/m' Cesium-137 1,000 pCi/l l

l Barium-140 8,000 pCi/l l Iodine-131 1,000 pCi/l Potassium-40' 4,000 pCi/l Gross Alpha 2 pCi/l Gross Beta 100 pCi/l Tritium lx10' pCi/l Taken from Code of Federal Regulation Title 10, Part 20, Table II and appropriate footnotes. Concentrations may be averaged over a period not greater than one year.

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

I A natural radionuclide. 2 i

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r Davis-B:sse Nuclear Pow::t Station 1998 Annual Radiologic:.1 Environmental Operating Report l

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APPENDIX D REMP SAMPLING

SUMMARY

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D:vis-Besse Nuclear Pow:r Station 1998 Annual Radiologic:1 Environmental Opertting Report ,

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Table 4.5 RadiologicalEnvironmentalMonitoringProgramSummary.

Nameof Facility Davis-Besse Nuclear Power Station Docket No. 50-346 locationof Facility Ottawa, Ohio Reporting Period January December 1998 (County, State)

Indkator location with Highest Control Number Sample Type and locations Annual Mean tocations Non.

Type Number of LLob Mean (F)C Routine a

Mean (F)C Mean (F)c (Unsts) Analyses Ranaec locationd Range Results' Ranaec Airborne GB 520 0.004I 0.021 (309/312) T 27, Crane Creek 0.024 (52/52) 0.022 (208/208) O particulates (0.005-0.039) State Park. (0.005-0.043) (0.005-0.045)

(pCi/m3) 5.3 mi. WNW Sr-89 40 0.0014 <LLD - - <LLD 0 Sr-90 40 0.0009 <LLD - - <LLD 0 GS 40 Be-7 0.015 0.077 (24/24) T-27, Crane Creek 0.085 (4/4) 0.078 (16/16) 0 (0.054-0.109) State Park, (0.063-0.110) (0.059-0.110) 5.3 mL WNW K-40 0.056 <LLD - - <LLD 0 Nb-95 0.0020 <LLD - - <LLD 0

, Zr-95 0.0037 <LLD - - <LLD 0 Ru-103 0.0019 <LLD - - <LLD 0 Ru-106 0.012 <LLD - - <LLD 0 Cs-134 0.0018 <LLD - - <LLD 0 Cs-137 0.0012 <LLD - - <LLD 0 Ce-141 0.0035 <LLD - -

<LLD 0 Ce-144 0.0074 <LLD - - <LLD 0 Airborne lodine I-131 520 0.07I <LLD - - <LLD 0 (pC1/m3) 1LD(Quarterly) Camma 286 1.0 13.8 (243/243) T 67, Site Boundary 19.2 (4/4) 15.0 (43/43) 0 (mR/91 days) (7.9-20.9) 0.3 mi. NNW (17.2-20.9) (11.3-19.0)

TLD(Quarterly) Camma 4 1.0 5.5 (4/4) - - None 0 (mR/91 days) (5.2-5.7)

(Shield)

TLD (Annual) Camma 65 1.0 55.7 (55/55) T 45, Site Boundary 90.6 (1/1) 64.3 (10/10) 0 (mR/365 days) (33.8-90.6) 0.5 mL WNW (45.8-78.7)

TLD (Annual) Camma 1 1.0 23.9 (1/1) - - None 0 (ir.R/365 days) 1 (Shield)

I80

F Davis-Besse Nuclear Power St: lion 1998 Annual Radiological Environmental Operating Report

l. Table 4.5 Radiological Envimnmental Monitoring Pmgram Summary.

Name of Fadlity Devis-Besse Nuclear Power Station Docket No. 50-346 Location of Fadlity Ottawa, Ohio Reportmg Period January - December 1998 (County, State)

Ind6cator tocation with Hnghest Control Number Sample Type and locations Annual Mean Locations Non-Ty Number of LLob Mean (F)C Routine Mean (F)C Mean (F)c  ;

. (U ts) ,

Analysosa Ranaec locationd Ranaec Range Results' Milk (pCi/L) 1131 12 0.5 none - - <LLD 0 Sr-89 12 1.1 none - - <LLD 0 Sr-90 12 0.5 none T-24,Sandusky, 0.9 (12/12) 0.9 (12/12) 0 21.0 mi SE (0.6-1.1) (0.6-1.1)

CS 12 K-40 100 none T 24, Sandusky, 1375 (12/12) 1375 (12/12) 0 21.0 mi SE (1210 1470) (1210-1470)

Cs-137 10 none - - <LLD 0 Ba-La-140 10 none - - <LLD 0 (g/L) Ca 12 0.50 none T 24, Sandusky, 0.88 (12/12) 0.88 (12/12) 0 21.0 mi SE (0.824.%) (0.82-0.%)

(g/L) K(stable) 12 0.1 none T-24, Sandusky, 1.59 (12/12) 1.59 (12/12) 0 21.0 mise (1.40-170) (1.40-170)

(pCi/g) Sr-90/Ca 12 0.36 none T-24, Sandusky, 0.97 (12/12) 0.97 (12/12) 0 2LO mise (0.63 1.22) (0.63-1.22)

(pci/g) Cs-137/K 12 5.23 none - - <LLD 0 Ground Water CB (TR) 12 3.8 SJ (6/8) T-7, Sand Beac14 6.9 (3/4) 4.5 (3/4) 0 i (pCl/L) (4.0 8.3) 0.9 ml NW (4.5-8.3) (4.1-43)

H-3 12 330 <LLD - - <LLD 0 Sr-89 12 1.0 <LLD - - <LLD 0 Sr-90 12 0.7 <LLD - - <LLD 0 CS 12 Mn-54 15 <LLD - - <tLD 0 Fe-59 30 <LLD - - <LLD 0 Co-58 15 <LLD - - <LLD 0 Co40 15 <LLD - - <LLD 0 Zn 65 30 <LLD - - <LLD 0 Zr-95 15 <LLD - - <tLD 0 I

Ca-134 10 <LLD - - <LLD 0 l l

Cs-137 10 <LLD - - <LLD 0 Ba-La-140 15 <LLD - - <LLD 0 181

e Davis-Besse Nuclear Power Station 1998 Annual Radiological Environmental Operating Report Table 45 Radiological Environmental Monitoring Program Summary l Name of Paculty Devne.Besse Nuclear Power Station Docket No. 5M46 Incationof Pacility Ottawa, Ohio Reporting Period January - December 1998 l (County, State)

Ind6cator location with Highest Control Number Sample Type and locations Annual Mean locations Non-Typ Number of 11Db Mean (F)C Mean (F)C Mean (F)c Routine

- (Umts) Analysesa Rana,c locationd c Range Itasults' GS 16 Treated Surface Water (PCl/L)

(continua 0 Mn-54 15 <LLD - - <LLD 0 Fe-59 30 <LLD - - <LLD 0 Co-58 15 <LLD - - <LLD 0 Co-60 15 <LLD - - <LLD 0 Zn45 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 Untreated GB(TR) 130 1.0 3.2 (78/78) T-152, 4.0 (7/7) 2.7 (52/52) 0 Surface Water (1.5-5.4) Canal Entrance to (2.9-5.2) (1.6-4.5)

(pCi/L) Maumee Bay S.P.

15.6 mi. WNW H3 130 330 590 (15/78) T-28, Onsite 1221 (1/12) 706 (2/52) 0 (359-1221) (391-1021)

St-89 20 1.0 <ILD - - <LLD 0 St90 20 0.8 1 3 (1/12) T,3, Site Boundary 1.3 (1/4) 0.9 (1/8) 0 1.4 mL ESE -

QS 130 Mn-54 15 <11D - - <LLD 0

~

Fe-59 30 <11D - - <LLD 0 Co-58 15 <LLD - - <LLD 0 Co-60 15 ~ <LLD - - <LLD 0 Zw65 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 l

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g Davis-B:sse Nuclear Power Station 1998 Annual Radiological Environmentd Operating Report l

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l Table 4.5 Radiological Environmental Monitoring Program Summary.

Name of Facihty Davis-Besse Nuclear Power Station Docket No. 50-346 locationof Pacility Ottawa,Otuo Reportmg Period January December 1998 (County, State)

Indwator location with Highest Control Number i

Sample Type and locations Annual Mean Locations Non-Type Number of LLDb m,n (p)c m.,, (p)c Mean (F)c Routine (Uruts) Analysema Rangec locationd Rawc Range Results' Animal GS 5 Wildide Feed (pC1/g wet) Be-7 0.052 0.98 (3/4) T-32, Onsite 1.56 (1/1) <LLD 0 (0.65-1.56) Roving location K-40 0.1 4.49 (4/4) T-34, Offsite 7.00 (1/1) 7.00 (1/1) 0 (3.514.68) Rovinglocation Nb-95 0.021 <LLD - - <LLD 0 Zr-95 0.042 <LLD - - <LLD 0 Ru-103 0.032 <LLD - - <LLD 0 Ru-106 0.27 <LLD - - <LLD 0 Ca 137 0.018 <LLD - - <LLD 0 Ce-141 0.045 <LLD - - <LLD 0 Ce-144 0.18 <LLD - - <LLD 0 Soil GS 20 (pCi/g dry)

Be-7 0.50 3.88 (3/12) T-1, Site Boundary, 5.15 (2/2) 0.79 (1/8) 0 (0.86-9.43) 0.6 mL ENE (0.86-9.43)

K-40 1.0 11.47 (12/12) T 9, Oak Harbor, 24.56 (2/2)' 19.14 (8/t) 0 (2.71-21.87) 6.8 mL SW (23.43-25.69) (7.64-25.69)

Nb-95 0.062 <LLD - - <LLD 0 Zr-95 0.084 <LLD - - <LLD 0 Ru-103 0.071 <LLD - - <LLD 0 Ru-106 0.28 <LLD - - <LLD 0 .

I Co-137 0.034 0.26 (6/12) T 2, Site Boundary, 0.54 (1/2) 0.24 (5/8) 0 l (0.10 0.54) 0.9 mL E (0.20 0.29)

Ce-141 0.12 <LLD - - <LLD 0 ,

Ce-144 0.23 <LLD - - <LLD 0  !

l Treated CB (TR) 48 1.0 2.3 (24/24) T 11, Port Clinton 2.7 (12/12) 2.5 (24 /24) 0 .

Surface Water (1.4-3.2) Water Treatment (1.9-3.8) (1.5-3.8)  !

(pCl/L) Plant, 9.5 mi. SE H3 16 330 677 (1/8) T 28, Onsite 677 (1/4) <LLD 0 Sr-89 16 1.5 <LLD - - <LLD 0 ,

St-90 16 0.8 1.3 (3/8) T 50, Erie Ind. Park 1.6 (1/4) 1.2 (3/8) 0 l (0.9-1.6) 4.5 mi. SE (1.0-1.3) l 183

I Davis-Besse Nuclear Power Station 1993 Annual Radiological Environmental Operating Report Table 45 Radiological Environmental Monitoring Program Summary.

Nameof Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Ohio Reporting Period January - December 1998 (County, State)

Indicator location with Highest Control Number Sample Type and locations Annual Mean locations Non.

Type Number of LIM Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analp a Rang,c Locationd Rangec Range Results' l l

l Edible Meat GS 3 (pC1/g wet)

K-40 0.1 3.01 (2/2) T 197, Farm 3 34 (1/1) 1.82 (1/1) 0 1.7 ml. W Cs-137 0.018 <LLD - - <LLD 0 Fruits and Vegetables 3r-89 4 0.003 <LLD - - <LLD 0 l

(pCl/g wet) Sr-90 4 0.001 <LLD - -

<LLD 0 1-131 4 0.022 <LLD - -

<LLD 0 CS 4 K-40 0.50 1.06 (3/3) T-173, Firelands 2.97 (1/1) 2.97 (1/1) 0 (0.83-1.35) Winery,20.0 mL SE ,

1 Nb-95 0.013 <LLD - -

<LLD 0 l

l Zr 95 0.023 <LLD - - <LLD 0 1 Cs-137 0.010 <LLD - - <LLD 0 Ce 141 0.022 <LLD - - <LLD 0 Ce 144 0.087 <LLD - - <LLD 0 l l

l Broad Leaf Sr-89 9 0.014 <LLD - - <LLD 0 Vegetation (pCi/g wet) Sr-90 9 0.003 0.015 (1/6) T 36, Garden 0.015 (1/3) <LLD 0 l 23 mL NW I I-131 9 0.024 <LLD - - <LLD 0 CS 9 K40 0.50 2.% (6/6) T 19, Farm 4.58 (2/2) 2.42 (3/3) 0 (1.68-5.19) 0 68 mi. W (3.96-5.19) (2.00-2.96)

Nb-95 0.018 <LLD - - <LLD 0 Zr-95 0.030 <LLD - - <LLD 0 Ca-137 0.017 <LLD - - <LLD 0 Ce-141 0.028 <LLD - - <LLD 0 Ce-144 0.080 <LLD - - <LLD 0 184 i d

Davis-Besse Nuclear Power Station 199tf Annual Radiological Environmental Operating Report Table 4.5 RadiologkalEnvimnmentalMonitoringProgramSummary.

Name of Facility Davis-Besee Nuclear Power Station Docket No. 50-346 1mcation of Pacility Ottawa, Oldo Re% Period January December 1998 (County, State)

Indicator Location with Highest Control Number Sample Type and Iscations Annual Mean locations Non-T Number of LLDb Mean (F)C Mean (F)C Mean (F)c Routine (U ts) Analyses a pangec locationd Ranaec Range Results' Fish GB 6 0.1 2.66 (3/3) T 33, take Ede, 2.66 (3/3) 2.56 (3/3) 0

. (pC1/g wet) (2.33-2.94) 1.5 mL NE (2.33-2.94) (2.11-2.82)

@ 6 K-40 0.1 2.44 (3/3) T-35, take Erie, 2.83 (3/3) 2.83 (3/3) 0 (2.20-2.58) > 10 mi. radius (2.65-3.14) (2.65-3.14)

Mn-54 0.014 <LLD - - <LLD 0 Fe-59 0.059 <LLD - - <LLD 0 Co-58 0.021 <LLD - - <LLD 0 Co40 0.017 <LLD - - <LLD 0 Zn-65 0.038 <LLD - - <LLD 0 Co-134 0.018 <LLD - - <LLD 'O Co-137 0.018 <LLD - - (LLD 0 1

Shorehne 2 8 Sediments (pCi/g dry) K-40 0.1 0 13.88 (6/6) T-4, Site Boundary 14.98 (2/2) 12.77 (2/2)

(11.38-17.82) 0.8 mL S (12.13-17.82) (12.69-12.85)

Mn-54 0.029 <LLD - - <LLD 0 Co-58 0.035 <LLD

<LLD 0 Co40 0.035 <LLD - - <!LD 0 Cs 134 0.062 <LLD - -- - <LLD 0 Cs-137 0.026 <LLD T-4, Site Boundar) 0 24 (1 /2) <LLD 0 0.8 mi. S a CB = groes beta, CS = gamma scan,TR = total residue.

b LLD = nominal lower limit of detection based on 446 sigma counting error for background sample.

C Mean based upon detectable measunements only. Fraction of detectable measurements at specified locations is indicated in parentheses (r).

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

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

I One result for airborne lodine-131 (<0.28 pCi/m 3, Station T-7 for the week ending June 23,1998) exceeded the required LLD, I

due to low volume. The gross beta result for the same week and location (<0.080) was not included in the LLD calculation.

r 185 e m