ML20107C286
| ML20107C286 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/31/1995 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20107C283 | List: |
| References | |
| NUDOCS 9604170301 | |
| Download: ML20107C286 (228) | |
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT for Davis-Besse Nuclear Power Station January 1,1995 through December 31,1995 Prepared by: Radiation Protection Section Davis-Besse Nuclear Power Station l Toledo Edison Company ! Toledo, Ohio April 1996
Davis-Besse Nuclear Power Station 1995 Annual Radiologict Environmental Operating Repon TABLE OF CONTENTS Title Page 1 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 liealth Effects of Radiation 9 l Health Risks 10 Benefits of Nuclear Power 11 Nuclear Power Production 11 Station Systems 16 Reactor Safety and Summary 19 Radioactive Waste 19 l Description of the Davis-Besse Site 22 References 24 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Introduction 26 Preoperational Surveillance Program 26 Operational Surveillance Program Objectives 27 Quality Assurance 27 Program Description 28 Sample Analysis 32 Sample IIistory Comparison 35 i
D:vis-Besse Nuclear Power Station 1995 Annual Radiologicd Environment-] Operating Report l Title 11ag RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) 1995 Program Deviations 37 Atmospheric Monitoring 39 Terrestrial Monitoring 45 Aquatic Monitoring 57 Direct Radiation Monitoring 68 Conclusion 79 References 80 RADIOACTIVE EFFLUENT RELEASE REPORT Protection Standards 83 Sources of Radioactivity Released 83 Processing and Monitoring 84 Exposure Pathways 85 Dose Assessment 86 Results 87 Regulatory Limits 88 Effluent Concentration Limits 89 Average Energy 89 Measurements of Total . Activity 89 Batch Releases 90 Sources ofInput Data 91 Doses to Public Due to Activities Inside the Site Boundary 91 Inoperable Radioactive Effluent Monitoring Equipment 92 Changes to The ODCM and PCP 92 Borated Water Storage Tank Radionuclide Concentration 92 ; LAND USE CENSUS Program Design 110 l Methodology 110 Results 111 ii
Davis-Besse Nuclear Power Station 1995 Annud Radiological Environmental Operating Report
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1 Title Page NON-RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring 116 Land and Wetlands Management 142 Water Treatment 145 Chemical Waste Management 150 Waste Minimization and Recycling 154 APPENDICES
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Appendix A: Interlaboratory Comparison Program Results 155 i q Appendix B: Data Reporting Conventions 190 4 i Appendix C: Emuent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas 193 l Appendix D: REMP Sampling Summary 195 j i 4 d i 4 I i
Davis-Besse Nuclear Power Station t995 Annual Radiological Environmental Operating Report List of Tables Table Page Title Number Number Risk Factors: Estimated Decrease in Average Life Expectancy 1 10 Sample Codes and Collection Frequencies 2 30 Sample Collection Summary 3 31 Radiochemical Analyses Performed on REMP Samples 4 33 Air Monitoring Locations 5 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 and Bottom Sediment Locations 14 62 Fish Locations 15 64 Thermoluminescent Dosimeter Locations 16 70 Gaseous Effluents - Summation of All Releases 17 93 Gaseous Effluents - Ground Level Releases - Batch Mode 18 94 Gaseous Effluents - Ground Level Releases - Continuous Mode 18 95 Gaseous Effluents - Mixed Mode Releases - Batch Mode 19 97 Gaseous Effluents - Mixed Mode Releases - Continuous Mode 19 98 Liquid Effluents - Summation of All Releases 20 100 Liquid Effluents - Nuclides Released - Batch Releases 21 101 Liquid Effluents - Nuclides Released - Continuous Releases 21 103 Solid Waste and Irradiated Fuel Shipments 22 105 Doses Due to Gaseous Releases for January through December 1995 23 107 Doses Due to Liquid Releases for January through December 1995 24 108 Annual Dose to The Most Exposed Member of The Public 25 109 Closest Exposure Pathways Present in 1995 26 113 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters 27 115 IV
Davis-Besse Nucicer Power Station 1995 Annuel Radiological Environmenti Ording Report Table Page Title Number Number Summary of Meteorological Data Recovery for 1995 28 122 Summary of Meteorological Data Measured for 1995 29 123 Joint Frequency Distribution by Stability Class 30 137 v
Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental 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 I Fuel Rod, Fuel Assembly, 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-Besse 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 Terrestrial Sampling Locations on Davis-Besse Site 16 54 Terrestrial Sampling Locations within a Five Mile Radius 17 55 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 Aquatic Sampling Locations within a Twenty-Five Mile Radius 24 67 I TLD Dose Comparison 1973 - 1995 25 69 Comparison of NRC and Davis-Besse TLDs 26 70 l Direct Radiation Sampling Locations on Davis-Besse Site 27 76 Direct Radiation Sampling Locations within a Five Mile Radius 28 77 ! Direct Radiation Sampling Locations within a Twenty-Five Mile Radius 29 78 Exposure Pathways 30 86 i vi
m-um Davis-Besse Nuclear Power Stat:n 1995 Annual Radiological Environmental Opening Report Figure Page Description Number Number Land Use Census Map 31 112 Wind Rose Annual Average 100M 32 125 ; Wind Rose Annual Average 75M 33 126 Wind Rose Annual Average 10M 34 127 J Wind Rose Monthly Average 100M 35 128 Wind Rose Monthly Average 75M 36 131 Wind Rose Monthly Average 10M 37 134 Water Treatment Plant Schematic 38 146
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l Davis-Besse Nuclear Power Station 1995 Annual Radiologicol Environmental Operating Report I l i Executive Summary The Annual Radiological Environmental Operating Report (AREOR) is a detailed report on the l Environmental Monitoring Programs conducted at the Davis-Besse Nuclear Power Station from i January 1 through December 31,1995. This report meets all of the requirements in Regulatory l 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 I l Monitoring Program, Land Use Census, and the Non-Radiological Environmental Programs, ! l which consist of Meteorological Monitoring, Marsh Management, Water Treatment, Chemical I Waste Management, and Waste Minimization and Recycling. This report also includes the Ra- ! diological Effluent Release Report for the reporting period of January 1 through December 31, i 1995. Radiological Environmental Monitoring Program l The Radiological Environmental Monitoring Program (REMP) is established to monitor the ra-l 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-i Besse Offsite Dose Calculation Manual Section 6.0. This program includes the sampling and I analysis of environmental samples and evaluating the effects of releases of radioactivity on the environment. i Radiation levels and radioactivity have been monitored within a 25 mile radius around Davis- ' l Besse since 1972. The REMP was established at Davis-Besse about five years before the Station l 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 l continued to monitor the environment by sampling air, groundwater, milk, edible meat,' egg, I fmit and vegetables, animal feed, soil, drinking water, surface water, fish, bottom and shoreline l sediment, and by measuring radiation directly. l Samples are collected from indicator and control locations. Indicator locations are within ap-proximately 5 miles of the site and are expected to show naturally occurring radioactivity plus any increases of radioactivity that might occur due to the operation of Davis-Besse. Control lo-l cations are farther away from the Station and are expected to indicate the presence of only natu-rally occurring radioactivity. The results obtained from the samples collected from indicator locations are compared with the results from those collected from control locations and with the concentrations present in the environment before Davis-Besse became operational. This allows for the assessment of any impact the operation of Davis-Besse might have had on the surround-j ing environment. Approximately 1700 radiological environmental samples were collected and analyzed in 1995. An explanation for the sample program deviations for this reporting period is provided on page 38. The results of the REMP indicate that Davis-Besse continues to be operated safely in accordance I with applicable federal regulations. No measurable increase above background radiation or ra-dioactivity is attributed to the operation of Davis-Besse. viii
1 Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report 1 The sampling results are divided into four sections: atmospheric monitoring, terrestrial monitor-ing, aquatic monitoring and direct radiation monitoring. j
. Air is continuously being filtered at 10 locations and the filters are collected to monitor the atmosphere. The 1995 results are similar to those observed in preoperational and previous operational pro-grams. Only background and fallout radioactivity normally present in the environment was detected and only at concentrations normal to the area.
Terrestrial monitoring includes analysis of milk, ground water, meat, fruits, vegetables, animal feed and soil samples. The results of the analyses of the terrestrial samples indicate concentrations of radioactivity similar to previous years and 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. The 1995 results of analysis for fish, untreated surface water, drinking water and shoreline sediment indicate normal background concen-tration of radionuclides and show no increase or build-up of radio-activity due to the operation of Davis-Besse. Direct radiation averaged 13.0 2.6 mrem /91 days at indicator lo-cations and 14.2 i2.2 mrem /91 days at control locations. This is similar to results of previous years. The operation of Davis-Besse in 1995 caused no significant increase in the concentrations of ra-dionuclides in the environment and no adverse effect on the quality of the environment. Radio-activity released in the Station's effluents was well below the applicable federal regulatory limits. The estimated radiation dose to the general public due to the operation of Davis-Besse in 1995 was well below all applicable regulatory limits. In order to estimate radiation dose to the public, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed 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 radiological exposure pathways (e.g., residences, 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 popu-lation, and is called the critical pathway. The critical pathway for 1995 is a garden located 880 meters north-northeast of the plant. ix
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Radiological Efiluent Release Report , The Radiological Emuent Release Report (RERR) is a detailed listing of radioactivity re-leased from the Davis-Besse Nuclear Power Station during the period, January 1,1995 through , December 31,1995. The doses due to radioactivity released during this period were estimated to be: j Liquid Emuents: i i Maximum Individual Whole Body Dose 1.03E-01 mrem (0.103 mrem) j Maximum Individual Significant Organ Dose 1.35E-01 mrem (0.135 mrem) TotalIntegrated Population Dose 3.63E+00 person- rem (3.36 person-rem) Average Dose to the Individual 1.66E-03 mrem , (0.00166 mrem) ! Gaseous Emuents: Maximum Individual Whole Body Dose due to 3.94E-03 mrem I-131, H-3 and Particulates with half-lives (0.00394 mrem) greater than 8 days Maximum Significant Organ dose due to I-131, 1.70E-02 mrem l H-3 and Particulates with half-lives greater than (0.017 mrem) l 8 days ! Total Integrated Population dose due to I-131, 5.06E-03 person-rem i H-3 and Particulates with half-lives greater than (0.00506 person-rem) ; 8 days l Average dose to an Individual in the population 2.32E-06 mrem due to I-131, H-3 and Particulates with half-lives (0.00000232 mrem) greater than 8 days Maximum Individual Skin dose due to noble gases 1.34E-02 mrad (0.0134 mrad) Maximum Individual Whole Body Dose due to 3.52E-03 mrad noble gases (0.00352 mrad) Total Integrated Population dose due to noble gases 8.24E-03 person-rem (0.00824 person-rem) Average dose to individual in population due to 3.77E-06 mrem noble gases (0.00000377 mrem) X
D:vis-Besse Nucle r Power Station 1995 Annual Radiological Enviromnental Operating Report These doses represent an extremely small fraction of the limits set by the NRC or the limits set in the ODCM. There were no abnormal liquid releases and no abnormal gaseous release during this re-porting period. There were no changes to the Process Control Program (PCP) during this reporting pe-riod. There were two changes to the Offsite Dose Calculation Manual during this report-ing period. Non-Radiological Environmental Programs
+ Meteorological Monitoring The Meteorological Monitoring Program at Davis-Besse is part of a program for evaluating the radiological effects of the routine operation of Davis-Besse on the surrounding environment.
Meteorological monitoring began in October,1968. Meteorological instruments are monitored by trained personnel. Meteorological data recorded at Davis-Besse include wind speed, wind direction, sigma theta (standard deviation of wind direction), ambient temperature, diffccential temperature, dew point and precipitation. Two instrument-equipped meteorological towers are used to collect data. Data recovery for the six instruments required to be operational by Davis-Besse Technical Specifications was 99.3%.
+ Marsh Management Toledo Edison and the Cleveland Electric Illuminating Company co-own the Navarre Marsh 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 1995 with the cooperation of Ohio Department of Natural Re-sources included Canada goose banding, a Volunteer Eagle Watch Workshop, International Mi-gratory Bird Day and a Waterfowl Identification Seminar. During 1995,10 acres of land outside the marsh has been planted with prairie grass and wild Howers. This will provide habitat for upland animals, improve water quality, and reduce soil erosion. Also, Davis-Besse pledge part-nership with Ducks Unlimited, the Ohio Division of Wildlife and Ottawa National Wildlife Ref-uge in restoring 908 acres of wetland in Metzers Marsh. For the first time in Davis-Besse history, a young eaglet was fledged in our marsh. The eaglet was one of 38 eaglets fledged in Ohio in 1995. l
+ Water Treatment I 1
Davis-Besse uses Lake Erie 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. 1 I l l xi l l
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmentcl Opercting Report Toledo Edison personnel collected and analyzed water samples from various locations on the station as part of the Zebra Mussel Control Program. Results show that the mussel population appears to be leveling off or declining slightly, mostly due to the increasing clarity of Lake Erie. 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. Two comminutors were purchased and installed to grind and shred incoming ma-terial and reduce clogging of the surge tank pumps.
+ Chemical Waste Management The Chemical Waste Management Program at Davis-Besse was developed to ensure that the offsite 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 1995, the Davis-Besse Nuclear Power Station generated 1,620 pounds of hazardous wastes, which represents a 74% reduction from 1994. There were 3,070 gallons of non-hazardous waste oil generated in 1995, a 32% reduction from 1994. Additionally, approximately 1,200 gallons of oil filters and solid oily debris were generated. 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 com-missions. As part of the program to remove PCB fluid from Davis-Besse, all electrical trans-formers have been retrofilled and reclassified as non-PCB transformers.
+ Waste Minimization and Recycling The Waste Minimization and Recycling Program at Davis-Besse began in 1991 with the collec-tion and recycling of paper. This program was expanded and reinforced during 1993 to include the recycling of paper, aluminum cans, cardboard, and metal. Throughout 1995, a total of 58 tons of paper were collected and recycled and 9 tons of cardboard were collected that would have otherwise been disposed ofin a landfill. The scrap metal collected onsite was sold to scrap companies.
Appendices Appendix A contains results from the Interlaboratory Comparison Program required by Davis-Besse Technical Specifications. Samples with known concentrations of radioisotopes are pre-pared by the Environmental Protection Agency (EPA), and then sent (with information on sam-ple type and date of collection only) to the labc,ratory 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 are provided in Appendix A. xii
Davis-Besse Nucleu Power Station 1995 Annual Radiological Environmental Operating Report ; Appendix B contains data reporting conversions used in the REMP at Davis-Besse. The ap-pendix provides an explanation of the format and computational methods used in reporting l REMP data. Information on counting uncertainties and the calculations of averages and standard deviations 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 1995. Appendix D provides a REMP sampling summary from 1995. The appendix provides a listing of the following for each sample type: e the number and types of analyses performed, 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 information presented in Appendices A through D was provided by Teledyne Isotopes Midwest Laboratories in their Final Progress Report to Toledo Edison (March 1995). I xiii
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l l Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Repon 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 envitonment. 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 characteris-tics, risk assessment, reactor operation and effluent control is provided in this section. Fundamentals The Atom F [ ' O PROTON All matter consist of atoms. Simply de- $ NEUTRON g,,,,,,,,, , scribed, atoms are made up of positively and negatively charged particles, and particles ( ) which are neutral. These particles are called '~~~ protons, electrons, and neutrons, respec-tively (Figure 1). The relatively large pro-o* "! g tons and neutrons are packed tightly to- [ \ gether in a cluster at the center of the atom " called the nucleus. Orbitirg around this nu-cleus are one or more smaller electrons. In f , an electncally neutral atom the negative f O + tacraos charges of the electrons are balanced by the ' positive charges of the protons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other, Figure 1: An atom consists of two parts: a nucleus contaming positively charged protons and electn-which helps hold the atom together. Other cally neutral neutrons and one or more negatively attractive forces between the protons and charged electrons orbiting the nucleus. Protons and neutrons keep the densely packed protons neutrons are nearly identical in size and weight, from repelling each other, preventing the while each is about 2000 times heavier than an elec-tiucleus from breaking apart. L' "- 1 1
l Davis-Besse Nucle:r Pow:r Station 1995 Annual Radiological Environmental 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, l the number of protons an atom contains determines its chemical identity. For instance, all atoms l with one proton are hydrogen atoms and all atoms with eight protons are oxygen atoms. How-ever, the number of neutrons in the nucleus of an element may vary. Atoms with the same num-ber of protons, but different numbers of neutrons are called isotopes. Different isotopes of the , same element have the same chemical properties and many are stable or nonradioactive. An un- l stable or radioactive isotope of an element is called a radioisotope, radioactive atom, or radi- l onuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess , energy is usually due to a surplus or deficit in the number of neutrons in the nucleus. Radionu- l clides can be naturally occurring such as uranium 238, beryllium-7 and potassium-40, or man- l made, such as iodine-131, cesium-137, and cobalt-60. ; Radiation l Radiation is simply the conveyance of energy through space. For instance, heat emanating from i a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation j is another type of radiation and has similar properties to those of the examples listed above. Ion-izing radiation consists of both electromagnetic radiation and particulate radiation. Electro-magnetic radiation is energy with no measurable mass that travels with a wave-like motion through space. Included in this category are gamma rays and X rays. Particulate radiation con-sists of tiny, fast moving particles which, if unhindered, travel in a straight line through space. The three types of particulate radiation of concern to us are alpha particles, made up of 2. pro-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 Range and Shielding section. Radioactive Decay Radioactive atoms attempt to reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of energy from an atom through the emission ofionizing 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 daughter products which eventually result in a stable atom. The loss of energy and/or matter through radioactive decay may transform the atom into a chemically different element. For example, when uranium-238 decays, it emits an alpha particle and, as a result, the atom loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom determines its chemical identity. Therefore, when the uranium-238 atom loses the 2 protons and 2 neutrons, it is trans-formed into an atom of thorium-234. Thorium-234 is one of the 14 successive daughter products of uranium-238. Radon is another daughter product, and the series ends with stable lead-206. 1 2 i
_w.. J w 4 a. 6 , - a-. - - - , -m,+., n - a . u- a w- a a Davis-Besse Nuclear Power Station t995 Annual Radiological Environmental Operating Report This example is part of a known radioactive decay series, called the uranium series, which begins l with uranium-238 and ends with lead-206 (Figure 2). 234U 234U 4.5 x 10'y ,2.5 x dy 234pg #.'
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24po 2 ioPb MPb 26.8 min 21 y statae 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 cf half-lives. Half-life is the amount of time required for a radioactive substance to lose halfits activity through the process of radioactive decay. Half-lives vary from millionths of a sec-ond to millions of years. Interaction with Matter Ionization Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When these forms of radiation interact with any form of material, the energy they impart may cause 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. Ionization is one of the processes which may result in damage to biological systems. l f 3
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environraental Operating Report Range and Shielding Paniculate and electromagnetic radiation each travel through matter differently because of their different properties. Alpha panicles 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 energy 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 panicles, traveling at speeds near the speed of light (186,000 miles per second). Beta panicles 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 alpha particles, so they can travel farther. Beta panicles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood.
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RADIOACTIVE F1ATERIAL PAPER ALUtilNU M LEAD CONCRETE Figure 3: As radiation travels, it collides and interacts with other atoms and loses energy. Alpha particles can be stopped by a sheet of paper, and beta particles by a thin sheet of aluminum. 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 oflight. 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 oflead or concrete may be needed to effectively shield gamma rays. Neutrons come from several sources, including the interactions of cosmic radiation with the carth's atmosphere and nuclear reactions within operating nuclear power reactors. Ilowever, neutrons are not of environmental concern since the neutron source at nuclear power stations is sealed within the containment building. 4
Davis-Besse Nuclear Power Station 1995 Annud Radiological Environmental Operating Report l Because neutrons have no charge, they are able to pass veiy close to the nuclei of the material through which they are traveling. As a result, neutrons raay 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 l these deflections, the neutron has lost most of its energy. At this point, the neutron moves about l as slowly as the atoms of the material through which it is traveling, and is called a thermal neu-l 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. l Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron shielding materials commonly used to slow neutrons down are water or polyethylene. The shield is then completed with a material such as cadmium, to absorb the now thermal neutrons. At Davis-Besse, concrete is used to form an effective neutron shield because it contains water mole-cules and can be easily molded around odd shapes. Quantities and Units of Measurement There are several quantities and units of measurement used to describe radioactivity and its ef- 1 , fects. Three terms of panicular usefulness are activity, absorbed dose, and dose equivalent. I i Activity: Curie l 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 ! l 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 l 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 ra-dioactivity 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 i Absorbed dose is a term used to describe the radiation energy absorbed by any material exposed j to ionizing radiation, and can be used for both particulate and electromagnetic radiation. The rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the en-crgy of ionizing radiation deposited per gram of absorbing material (I rad = 100 erg /gm). The rate of absorbed dose is usually given in rad /hr. l 5
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report 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, bio- . logical effects depend not only on the total energy deposited per gram of tissue, but on how this energy is distributed along its path. Experiments have shown that 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 ionization caused by these radiations. 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 radiation. The dose equivalent is measured in rem (radiation equivalent man). An example of this conversion from absorbed dose to dose equivalent uses the quality factor for alpha radiation, which is 20. Thus, I rad of alpha radiation is approximately equal to 20 rem. , Beta and gamma radiatior each have a quality factor of 1, therefore one rad of either beta or l 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 extemal 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 deep dose equivalent (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. 6
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Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Total Effective Dose Equivalent (TEDE) 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 liinits occupational dose to a radiation worker to five rem (5000 mrem) TEDE per year. Sources of Radiation l Background Radiation Radiation is not a new creation of the nuclear power industry; it is a natural occurrence on the 1 earth. It is probably tne most " natural" thing in nature. Mankind has always lived with radiation 1 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 back-ground 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 l 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 I i 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 cencems j stem from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it l 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 of lung cancer. This effect has been seen when the radon is present at levels com-mon in uranium mines. According to the National Council on Radiation Protection and Meas-urement (NCRP), over half of the radiation dose the average American receives is attributed to radon. I l l 7 _ . . _ - ._, , _ - - - _ . _ _ _ .s
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report SOURCES OF EXPOSURE TO THE PUBLIC tematsfl,L INTE RN L CCypafleu,L 1 4.......:. Lg.,
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1 TOTAL MANMADE I SOURCE - BEIR V j Figure 4: The most significant annual dose received by an individual of the public is that received from naturally occurTing 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 I buildings can be obtained by contacting the state radon program office at the following address: Radiological Health Program Ohio Department of Health P.O. Box 118 Columbus, Ohio 43266-0118 (614) 481-5800 ; (800) 523-4439 (in Ohio Only) The approximate average background radiation in this area (see Figure 4) is 300 mrem / year. Man-Made Radiation In addition to naturally occurring cosmic radiation and radiation from naturally occurring radioac-tivity, people are also exposed to man-made radiation. The largest sources of exposure include medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium-90, cesium-137, and tritium. Less than one percent of the annual dose a member of the public re-ceives is a result of having electricity generated by nuclear power. 8
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Health Effects of Radiation The effects of ionizing radiation on human health have been under study for more than 80 years. Scientists have obtained valuable knowledge through the study of laboratory animals that were exposed to radiation under extremely controlled conditions. However, it has been difficult to re-late the biological effects of irradiated laboratory animals to the potential health effects on hu-mans. The effects of radiation on humans can be divided 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 st.ch groups are clock dial painters, who ingested large amounts of radium by " tipping" the paint brushes with their lips, and uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (uranium ore). The studies performed on these groups have increased our knowledge of the health effects from comparatively very large doses of radiation received over long periods of time. Continuous exposure to low levels of radiation may produce somatic changes over an extended period of time. For example, someone may develop cancer from man-made radiation, background radiation, or some other source not related to radiation. Because all ilb :s caused by low level radiation can also be caused by other factors, it is virtually impossible to determine individual 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 radia-tion occur proportionally to those observed following large doses of radiation. Most radiation 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 indi-viduals exposed to low level radiation. Therefore, the most likely somatic effect of low level ra-diation is believed to be a small increased risk of cancer. Genetic effects could occur as a result of ionizing radiation interacting with the genes in the hu-man cells. Radiation (as well as common chemicals) can cause physical changes or mutations in the genes. Chromosome fibers can break and rearrange, causing interference with the normal cell division of the chromosome by affecting their number and structure. A cell is able to rejoin the ends of a broken chromosome, but if there are two breaks close enough together in space and time, the broken ends from one break could join incorrectly with those from another. This could cause translocations, inversions, rings, and other types of structural rearrangements. When this 9
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t ? l Davis-Besse Nuclear Power Station 1995 Annual Radiological Environrnental Operating Report happens, new mutated genes are created. Radiation is not the only mechanism by which such I changes can occur. Spontaneous mutations and chemically induced mutations also have been ob-l served. These mutated genes may be passed from parent to offspring. Viable mutations due to low level, low dose radiation have not been cbserved in humans. Health Risks l l While people mcy accept the risks inherent in their personal activities, such as smoking and driv-ing to work each day, they are less inclined to accept the risk inhemnt in producing electricity. As with any industrial environment, it is not possible to guarantee a risk free environment. Thus, at-l tention should be focused on taking steps to safeguard the public, on developing a realistic as-sessment of the risks, and on placing these risks in perspective. The perceptions of risk associated with exposure to radiation has, perhaps, the greatest misunderstanding. Because people may not l understand ionizing radiation and its associated risks, they may fear it. This fear is compounded by the fact that we cannot hear, smell, taste or feel ionizing radiation. 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 numerous cancer causing substances. These risks are larger and measurable compared to those presumed 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 j number of different factors that decrease the average life expectancy of individuals in the United l States. Table 1: Risk Factors Estimated Decrease in Average Life Expectancy Overweight by 30% 3.6 years 1 l Cigarette smoking: 1 pack / day 7.0 years 1 2 packs / day 10.0 years l Heart diseases 5.8 years Cancer 2.7 years City Living (not rural) 5.0 years All operating commercial nuclear less than 12 minutes power plants totaled 10
, Davis-Besse Nuclear Power Station 1995 Annuel Radiologicol Envinnmental Opmoting hport 1 Benefits of Nuclear Power i 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 f percent of the electricity produced in the United States is from nuclear powered electrical generat- l ing stations. ! i Nuclear power offers several advantages over alternative sources of electric energy: 1 e nuclear power has an excellent safety record dating back to 1957 when the first l commercial nuclear power station began operating, e uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is l 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. l The following sections provide information on the fundamentals of how Davis-Besse uses nuclear 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, water 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 fis-sioned, inside the reactor. What is Fission? l A special force called the binding force hc!ds 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, I a chain reaction of fission events provides the heat necessary to boil the water to produce steam. l 11
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DIvis-Besse Nucle:r Power St-tion 1995 Annual Radiologicc_1 Environment:.1 Operating R: port that 0 h [) e Bombarding / Neutton / Free 0i 70 N Neutron Atoni [ Fission Fragment Q i l 1 I I ! l l Figure 5: When a heavy atom, such as uranium-235 is split or fissioned, heat, free neutrons, and fission fragments result. The free neutrons can then strike neighboring atoms causing them to fission also. In the proper environ- I ment, this process can continue indefinitely in a chain reaction. I Nuclear Fuel The fissioning of one uranium atom releases approximately 50 million times more energy than the ) combustion of a single carbon atom common to all fossil fuels. Since a single small reactor fuel 1 pellet contains trillions of atoms, each pellet can release an extremely large amount of energy. 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. l 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 quicidy decay. In contrast, a nuclear reactor minimizes neutron losses, thus sustaining the fission process by several means:
. using fuel that is free ofimpurities that might absorb the free neutrons, e enriching the concentradon 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. 12
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operiting Report l l After the uranium ore is separated from the earth and rock, it is concentrated by a milling process. l After milling the ore to a granular form and dissolving out the uranium with acid, the uranium is ! converted to uranium hexafluoride (UFs). UF is 6 a chemical form of uranium that exists as a gas at temperatures slightly above room temperature. The UFe, is then highly purified and shipped to an enrichment facility where gaseous diffusion converters increase the concentration of l U-235. The enriched gaseous UF6 is then converted into powdered uranium dioxide (UO2), a l highly stable ceramic material. The UO2 powder is put under high pressure to form fuel pellets, l 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 i Two hundred eight fuel rods comprise a single fuel assembly. The reactor core at Davis-Besse l contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fuel rods, the fuel assembly also contains 16 vacant holes for the insertion of control rods, and one vacant hole for an incore monitoring probe. This probe monitors tem-perature 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. l
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Davis-Besse Nuclear Pawer Station 1995 Annual Radiological Environmental Operating Report Fission Control 1 1 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 metc.ls that absorb free neutrons, thus disrupting the fission chain reaction. When con- i trol rod assemblies are slowly withdrawn from the core, fissioning begins and heat is produced. If I 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. Boron-10 readily absorbs free neutrons, forming boron-11, n: moving the absorbed neutrons from , the chain reaction. l Reactor Types I 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 reactors (LWRs) because their coolant, or medium to transfer heat, is ordinary water, which contains the light isotope of hydrogen. Some reactors use the heavy isotope of hydrogen (deuterium) in the reactor coolant. Such reactors are called heavy water reactors (HWRs). In BWRs, water passes through the core and boils into steam. The steam passes through separa-tors which remove water droplets. The steam then travels to dryers before entering the turbine. After passing though the turbine the steam is condensed back into water and returns to the core to repeat the cycle. In PWRs, the reactor water or coolant is pressurized to prevent it from boiling. The reactor wa-ter is then pumped to a steam generator (heat exchanger) where its heat is transferred to a sec-ondary 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 generator, 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. I i 1 14 i
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Divis-Besse Nuclear Power Station 1995 Annu11 Radiological Environmental Operating Report Station Systems Containment Building and Fission Product Release Barriers ; The containment building houses the reactor vessel, the pressurizer, two steam generators, the reactor coolant pumps and reactor coolant system piping. The building is constmeted of an inner f' 1 inch thick steel liner or containment vessel, and the shield building with steel reinforced con- l crete walls 2 feet thick. The shield building protects the containment vessel from a variety of en- { vironmental factors and provides an area for a negative pmssure boundary around the steel ; containment vessel. In the event that the integrity of the containment vessel is compromised (e.g., l a crack develops), this negative pressure boundary ensures that any airborne radioactive contami-nation present in the containment vessel is prevented from leaking out into the environment. This is accomplished by maintaining the pressure inside the shield building lower than that outdoors, thus forcing clean outside air to leak in, while making it impossible for the contaminated air be- 1 tween 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 unhkely event of an accident. The first barrier to the release of fission products is the fuel cladding itself. The second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and associated piping. The Steam Generators The steam generators perform the same function as a boiler at a fossil-fueled power station. The steam generator uses the heat of the primary coolant inside the steam generator tubes to boil the secondary side feedwater (secondary coolant). Fission heat from the reactor core is transferred to the steam generator in order to provide the steam necessary to drive the turbine. However, 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 throtagh the reactor and steam generator. Primary loop water (green in Figure 7) exits the reactor at approximately 606 F, passes through the steam generator, transferring some ofits heat energy to the secondary loop water (blue in Figure 7) without actually coming in contact with it. Primary coolant water exits the steam generator at approximately 558 F to be circulated back into the reactor where it is again heated to 606 F as it passes up through the fuel assemblies. Under ordinary 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-pet-square-inch (psi) at all times. This prevents the water from boiling and is the reason the reactor at Davis-Besse is called a Pressur-ized Water Reactor. Secondary loop water enters the base of the steam generator at approxi- l mately 450 F and under 1,100 psi pressure. At this pressure, the water can easily boil into steam j as it passes over the tubes containing the primary coolant water. Both the primary and the secondary coolant water are considered closed loop systems. This means 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 !
i 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
Divis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report The Turbine - Generator l The turbine, main generator, and the condenser are all housed in what is commonly referred to as l 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
)
i 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 conunon shaft. A turbine stage refers to a set of blades. Steam enters at the center of each turbine and l flows outward along the shaft in opposite directions through each successive stage of blading. As I the steam passes over the turbine blades, it loses pressure. Thus, the blades must be proportion-ally larger in successive stages to extract enough energy from the steam to rotate the shaft at the l correct speed. ; I 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 i two pans, a stationary stator that contains coils of copper conductors, and a rotor that supplies a l rotatin); magnetic field within the coils of the stator. Electrical current is generated in the stator portior, of the main generator. From this point, the electric current passes through a series of trandormers for transmission and use throughout northern Ohio. The Condenser After the spent steam in the secondary loop (blue in Figure 7) passes through the high and low pressure turbines, it is collected in a cavernous condenser several stories tall and containing more than 70,000 small tubes. Circulating water (yellow in Figure 7) goes to the cooling tower after passing through the tubes inside the condenser. As the steam from the low pressure turbines l passes over these tubes, it is cooled and condensed. The condensed water is then purified and i reheated before being circulated back into the steam generator again in a closed loop system. Cir- ! culating water forms the third (or tertiary) and final loop of cooling water used at the Davis-Besse Station. Similar to the primary to secondary interface, the secondary to tertiary interface is based on a closed loop design. The circulating water is able to cool the steam in the condenser, without ever actually coming in contact with it, by the process of convection. Even in the event of a primary to secondary leak, the water vapor exiting the Davis-Besse cooling tower would remain non-radioactive. Closed loops are an integral part of the design of any nuclear facility. This design feature greatly reduces the chance of environmentalimpact from station operation. The Cooling Tower The cooling tower at Davis-Besse is easily the most noticeable feaiure 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 j recycle water from the condenser by cooling it. I 17 1 i
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Repon 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 venically 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 cin ulating 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 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. Depending upon the severity of the loss of pressure inside the primary system, the ECCS will automatically 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 ceiling of the containment vessel to cool and condense any steam that may escape from the primary system. 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. Heaters inside the pressurizer turn water into steam. This steam takes up more space inside the pressur-izer, 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 con-denses and the overall pressure inside the primary system drops. The quench tank pictured in Figure 8 is simply where excess steam is directed and condensed for storage. The scarlet system in Figure 7 is part of the Auxiliary Feedwater System, a key safety system in event the main feedwater supply (blue in Figure 7) to the steam generator is inadequate. Follow-ing a reactor shutdown, the Auxiliary Feedwater System can supply water to the steam generators from the Condensate Storage Tanks. The Auxiliary Feedwater System is housed in the Turbine Building along with the turbine, main generator, and the condenser. I8
Divis-Besse Nucle:r Power Station 1995 Annual Radiologicd Environmentil Operating Report Reactor Safety and Summary l Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. Also, many safety features are equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the local environment. Davis- , Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features. If one sys-tem should fail, there are still back-up systems to assure the safe operation of the Station. During normal operation, the Reactor Control System regulates the power output by adjusting the posi- , tion of the control rods. The reactor can be automatically shut down by a separate Reactor Pro-tection System 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. l The Davis-Besse Nuclear Power Station was designed, constructed, and operates to produce a reliable, safe, and environmentally sound source of electricity. Radioactive Waste Many of the activities we depend on in our everyday lives produce radioactive waste by-products. Nuclear energy, industrial processes, and medical treatments are some of these activities. These by-products are managed and disposed of under strict requirements set by the federal government. With the exception of used nuclear fuel assemblies, these by-products produced at commercial power plants are referred to as low level radioactive waste. Low Level Radioactive Waste i Low level radioactive waste consists mainly of ordinaq trash and other items that have become contaminated with radioactive materials. It includes plastic gloves and other protective clothing, machine parts and tools, medical and laboratory equipment, filters, resins, and general scrap. The radioactive material in low level radioactive waste emits the same types of radiation that natu-rally 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 dmunishes to stable materi-als in less than 300 years. In 1980, Congress passed the Low-Level Waste Policy Act. This law requires each state to de-velop an individual disposal site for waste, or to form " compacts" with other states to jointly dis-pose of their low-level waste. Approximately 10 regional compacts have been formed. 19
Davis-Besse Nuclear Power Station 1995 Annua 1 Radiological Environmental Operating Report Ohio is a member of the Midwest Compact, which includes Indiana, Iowa, Missouri, Minnesota, and Wisconsin. Since Ohio is the largest producer of low-level waste in the Compact, it has the responsibility to site the first disposal facility, which would receive waste from all Compact states l for 20 years. The responsibility then shifts to the Compact's next largest producer of waste, Min- ' nesota, which will host the repository for the second 20 years. Davis-Besse presently ships low level radioactive waste to a South Camlina disposal facility lo- ; l cated at Barnwell, South Carolina. This facility was closed to out of compact generators from l July 1,1994 to hly 1,1995. The facility was reopened by South Carolina to all generators on July 1,1995. 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 Level Radioactive Waste Storage Facility (LLRWSF) for several years in the event the Bamwell facility closes again. Low level waste will be shipped to a Midwest Compact facility when one becomes operational. High Level Nuclear Waste l I 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 per-cent of high-level waste from nuclear plants is used nuclear fuel. The fuel undergoes cenain 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 assemblies l reduce the efficiency of the chain reaction. Every 18 to 24 months, the oldest fuel assemblies are removed from the reactor and replaced with fresh fuel. High-level nuclear waste volumes are small. Davis-Besse produces about 30 tons of used fuel every 18 to 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 annually. l Also, nuclear waste slowly loses its radioactivity, but chemical waste remains hazardous indefi-nitely. l Davis-Besse presently stores its used fuel in a steel-lined concrete vault, filled with water, inside I the plant. The Department of Energy is charged with constmeting 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 as a possible site. Until the permanent DOE site is developed, nuclear plants will be responsible for l the continued safe storage of high-level waste. At Davis-Besse, the fuel pool reached its capacity l in 1995. At the end of 1995, Davis-Besse began the process of moving the older fuel assemblies that no longer require water cooling to air cooled concrete shielded canisters. These will remain stored onsite until the Department of Energy facilities are ready to receive them. Dry fuel storage ; is already used in many countries, including Canada, and in the U.S. at nuclear plants in Colorado, Maryland, Virginia, and South Carolina. Figure 8 illustrates the dry fuel storage module arrange-
- ment at Davis-Besse.
20
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Davis-Besse Nuclect Power Stction 1995 Annual Radiological Environmental Operating Report Description of the Davis-Besse Site The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the south-western shore of Lake Erie,just north of the Toussaint River. The site lies north and east of Ohio State Route 2, approximately 10 miles northwest of Port Clinton,7 miles north of Oak Harbor, and 25 miles cast of Toledo, Ohio (Figure 9). This section of Ohio is flat and marshy, with maximum elevations of only a few feet above the level of Lake Erie. The area originally consisted of swamp forest and marshland, rich in wildlife but unsuitable for settlement and farming. During the nineteenth century, the land was cleared and drained, and has been farmed successfully since. Today, the terrain consists of farmland with marshes extending in some places for up to two miles inland from the Sandusky Lake Shore Ridge. ,
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- P Figure 9: 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. 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. 22
_ . _ _ _ _ _ _ _ _ ~ . _ _ . _ _ . _ _ . . Davis-Besse Nuclear Power Stition 1995 Annual Radiological Environmental Operating Repon 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 7,1% .
- Oak Harbor - 7 miles south, population 2,637 e Rocky Ridge - 7 miles west southwest, population 425 e
Toledo (the nearest major city) - 25 miles west, population 322,943 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-lands. 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 of income in the area. The main industries within five miles of the site are lo-cated in Erie Industrial Park, about four miles southeast of the station. Most of the remaining marshes in the area have been maintained by private hunting clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife. The State of Ohio Department of Natural Resources operates many wildlife and recreational 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 allowing 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. 23
Davis-Besse Nuclear Power Staion 1995 Annual Radiological Environmental Operating Report References
- 1. " Basic Radiation Protection Criteria," Repon No. 39, National Council on Radiation Protec-tion and Measurement, Washington, D.C. (January 1971).
- 2. " Cesium-137 from the Environment to Man: Metabolism and Dose," Report No. 52, 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, Washington, D.C. (December 1987).
- 7. " Health Effects of Exposure to Low Levels ofIonizing 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, l 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, Washington, D.C. (September 1987).
i
- 13. " Natural Background Radiation in the United States," Report No. 45, National Council on Radiation Protection and Measurements, Washington, D.C. (November 1975).
24
Divis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operaing Report f
- 14. " Nuclear Energy Emerges from 1980's Poised for New Growth," U.S. Council for Energy Awareness, Washington, D.C. (1989). s
- 15. " Nuclear Power: Answers to Your Questions," Edison Electric Institute, Washington, D.C.
(1987).
- 16. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurement, Washington, D.C.
(December 1987).
- 17. " Radiation Protection Standards," Department of Environmental Sciences and Physiology and the Office of Continuing Education, Harvard School Of Public Health, Boston, MA. (July 1989).
- 18. Radiological Environmental Monitoring Report for Three Mile Island Station," GPU Nuclear Corporation, Middletown, PA. (1985). ;
- 19. " Sources, Effects and Risk of Ionizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation,1988 Repon 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 Fed- t eral Regulations, Washington, D.C. (1988).
- 22. " Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40, Part :
190, Code of Federal Regulations, Washington, D.C. (1988).
- 23. " Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1979).
- 24. Site Environmental Report, Fernald Environmental Management Project, U.S. Department of Energy (June 1993).
25
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Radiological Environmental Monitoring Program
l Divis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at Davis- 1 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 e.stablished to describe and quantify the radioactivity, and l 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 ra-dioactivity in the surrounding areas. A variety of environmental samples are collected as part of the REMP at Davis-Besse. The selec-tion of sample types is based on the established critical pathways for the transfer of radionuclides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population characteristics, and land usage in the area of interest. The selection of sampling frequencies for the various envi-ronmental media is based on the radionuclides of interest, their respective half-lives, and their be-havior in both the biological and physical environment. 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 monitor-ing prior to constmeting the facility. This preoperational surveillance program is aimed at collect-ing 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 facility op-eration 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 path-ways, should be sampled on at least an annual basis during the preoperational phase of the envi-ronmental surveillance program. 26
. . . . . _ -- __ -. . -- =
Divis-Besse Nuclear Power Station 1995 Annual Radiologic:.1 Environmentti Operating Repon The preoperational surveillance design, including nuclide/ media combinations, sampling frequen-cies and locations, collection techniques, and radioanalyses performed, should be carefully consid-ered and incorporated in the design of the operational surveillance program. In this manner, data can be compared in a variety of ways (for example: from year to year, location to location, 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 enviromnental 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 program at Davis-Besse will continue after the Station has reached the end of its economically useful life and decommissioning has begun. Operational Surveillance Program Objectives The operational phase of the environmental surveillance program at Davis-Besse was designed with the following objectives in mind:
- to fulfill the obligations of the radiological surveillance sections of the Station's Technical Specifications and offsite Dose Calculation Manual; e to determine whether any significant increase occurs in the concen-tration of radionuclides in critical pathways; e to identify and evaluate the buildup, if any, of radionuclides in the local environment, or any changes in normal background radiation levels; e to verify the adequacy of Station controls for the release of radio- l active materials.
Quality Assurance An important part of the environmental monitoring program at Davis-Besse is the Quality As-surance (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 results of the REMP through: e performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keeping; performing audits of contractor laboratories which analyze the envi-ronmental samples; 27
D;vis-Besse Nuclear Power Station 1995 Annual Radiologicd Environment:1 Operning Report e requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross-Check Pro-gram; e requiring analytical contractor laboratories to split samples for separate analysis followed by a comparison of results; e splitting samples prior to analysis by independent laboratories, and then comparing the results for agreement, and, finally; e requiring analytical contractor laboratories to perform in-house spiked sample analyses. QA audits and inspections of the Davis-Besse REMP are performed by Davis-Besse's QA de- i partment and the NRC. In addition, the NRC and the Ohio Department of Health (ODH) also I perform independent environmental monitoring in the vicinity of Davis-Besse. The types of sam-plcs collected and the sampling locations used by the NRC and ODH were incorporated in Davis- { Besse's REMP. Hence, the analytical results from the different programs can be compared. This j practice of comparing results from identical samples, collected and analyzed by different parties, i provides a valuable tool to verify the quality of the laboratories analytical procedures and the data generated. In 1987, environmental sampling personnel at Davis-Besse incorporated their own Quality Assur-ance program into the REMP. Duplicate samples, called quality control samples, were collected at severallocations. These duplicate samples were assigned different identification numbers than the numbers assigned to the routine samples. This ensured that the analytical laboratory would not know the samples were identical. The laboratory results from analysis of the quality control samples and the routine samples could then be compared for agreement. Quality control sampling I has been integrated into the program and has become an important part of the REMP since 1987. Quality control sampling locations are changed frequently in order to duplicate as many sampling j locations as possible, and to ensure the contractor laboratory has no way of correctly pairing a quality control sample with its routine sample counterpart. Program Description l I 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. Sam-ples are collected either 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 radiciodine 28
I D;vis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report e terrestrial -- including samples of milk, groundwater, broad leaf vege-tation, fruits animal / wildlife feed, soil, eggs, and wild and domestic meat e aquatic --including samples of treated and untreated surface water, fish, and shoreline and bottom sediments e direct radiation - measured by thermoluminescent dosimeters l All environmental samples are labeled using a sampling code. Table 2 provides the sample codes l and collection frequency for each sample type. l 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- : 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 l 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 occur- l ring background radiation or fallout from weapons testing in evaluating any radiological impact Davis-Besse has on the surrounding environment. Data from indicator and control locations are ; also compared with preoperational data to determine whether significant variations or trends ex-ist. i 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 i sampling locations above the minimum amount required in the ODCM and increasing the number of analyses performed on each sample. Besides adding new locations, duplicate or Quality Con-trol (QC) sample collection was initiated to verify the accuracy of the lab analyzing the environ-mental samples. These additional samples are referred to as the REMP Enhancement Samples. Over 1700 samples were collected and over 2350 analyses were performed during 1995. In addi-tion,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. I l I 29
Divis-B .sse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 2: Sample Codes and Collection Frequencies Sample Collection Sample Type Code Frequency l l Airborne Particulate AP Weekly l Airbome Iodine AI Weekly l Thermoluminescent TLD Quarterly, Annually Dosimeter Milk MIL Monthly (semi-monthly during grazing season) Groundwater WW Quarterly Broad Leaf Vegetation BLV Monthly (when available) Surface Water - Treated SWT Weekly Surface Water - SWU Weekly Untreated Fish FIS Semiannually Shoreline / Bottom SED Semiannually Sediment Soil SOI Semiannually Animal / Wildlife Feed DFE/WFE Annually Meat-Domestic DME Annually Meat-Wild WME Annually Egg EGG Annually Fmits FRU Annually l 30 l l
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmentcl Opercting Report Table 3: Sample Collection Summary Sample Collection Numberof Numberof 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.) O/M 1 12 0 Groundwater O/Q"* 4 16 0 Edible Meat wild G/A 1 0 1 domestic G/A 2 2 0 Eggs G/A 2 0 2 Broad Leaf Vegetation / Fniit G/M 7 17 0 Soil G/S 10 20 0 Animal / Wildlife Feed G/A 4 4 0 Aquatic Treated Comp /WM* *
- 2 30 0 Surface Water G/WM* *
- 4 42 0 Ur/reated G/WM * *
- 2 17 0 Surface Water G/M 10 60 0 Comp /WM* *
- 4 55 0 Fish (3 species) G/SA 2 6 6 Shoreline Sediments G/SA 4 8 0 Direct Radiation Thermoluminescent C/Q * *
- 93 366 6 Dosimeters (TLD) C/A* *
- 93 89 4
- Type of Collection: C = Continuous; G = Grab; Comp = Composite
** Frequency of Collection: WM = Weekly composited Monthly; W = Weckly "* Includes quality control location SM = Semimonthly; M = Monthly; Q = Quarterly; SA = Semiannually; A = Annually 31
1 l Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmentcl Operating Report Sample Analysis When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Davis-Besse REMP include: Gross beta analysis measures the total iunount 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 spectmm rather than the discrete lines or " peaks" associated with gamma ra-diation, identification of specific beta emitting nuclides is much more difficult. Themfore, gross beta analysis only indicates whether the sample contains normal or abnormal concentrations of beta emitting radionuclides; it does not identify specific radionuclides. Gross beta analysis merely acts as a tool to identify samples that may require further analysis. Gamma spectral analysis provides more specific information than does gross beta analysis. Gamma spectral analysis identifics cach 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 I stations. l Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the l amount present. As discussed,in the Introduction Section, tritium is an isotope of hydrogen that emits low energy beta particles. l Strontium analysis identifies the presence and amount of strontium-89 and strontium-90 in a sample. These man-made radionuclides are found in the environment as a result of fallout from i nuclear weapons testing. Strontium is usually incorporated into the calcium pool of the bio- l sphere. In other words, strontium tends to replace calcium in living organisms and becomes in-corporated in bone tissue. The principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to depo.,ition from airborne releases. 1 Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a i special laboratory procedure. Table 6 provides a list of the analyses performed on environmental 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 that particular method for an individual analysis. 32
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples 1 Sample Type Analyses Performed i 1 Atmospheric Monitoring Airborne Particulate Gross Beta Gamma Spectral 1 Strontium-89 Strontium-90 Airbome Radioiodine Iodine-131 Terrestrial Monitoring Milk Gamma Spectral Iodine-131 Strontium-89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 l Broad Leaf Vegetation Gamma Spectral l and Fruits Iodine-131 l Strontium-89 l Strontium-90 Animal / Wildlife Feed Gamma Spectral Soil Gamma Spectral l Wild and Domestic Meat Gamma Spectral Egg Ganuna Spectral l 33
.l
Divis-Besse Nucliar Power Station 1995 Annut! Radiologict.1 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 l Strontium-90 ; 1 Treated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 l Strontium-90 l Iodine-131 Fish l Gross Beta ' Gamma Spectral l 1 Shoreline Sediment Gamma Spectral Direct Radiation Monitoring Thermoluminescent Dosimeters Gamma Dose l l l 34
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Opercting 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 earlier years. Generally, the results of sample analyses are compared with preoperational and operational 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 cf the REMP sample analyses performed from 1972 through the current reporting period is provided in the following section. Atmospheric Monitoring
. Airborne Particulates: No radioactive particulates have been de-tected as a result of Davis-Besse's operation. Only natural and fall--
out radioactivity from nuclear weapons testing and the 1986 nuclear accident at Chernobyl have been detected.
- Airborne Radioiodine: Radioactive iodine-131 fallout was de-tected in 1976,1977, and 1978 from nuclear weapons testing, and in 1986 (0.12 to 1.2 picocuries per cubic meter) from the nuclear accident at Chernobyl.
Terrestrial Monitoring: e Groundwater: Only naturally occurring radioactive material has been detected in groundwater.
- Milk: Iodine-131 from nuclear weapons testing fallout was de-tected in 1976 and 1977 at concentrations of 1.36 and 23.9 picocu-ries / liter respectively. In 1986, concentrations of 8.5 picocuries/
liter were detected from the nuclear accident at Chernobyl. No io-dine-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. Potassium-40 has ranged from 1.1 to 4.6 picocu-ries / gram wet weight. Cesium-137 was detected in 1974, 1975, and 1981 due to fallout from nuclear weapons testing.
Broad Leaf Vegetation and Fruits: Only naturally occurring ra-dioactive material and material from nuclear weapons testing has been detected. 35
Divis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report e Soil: Only natural background and material from nuclear weapons testing and the 1986 nuclear accident at Chernobyl has been de-tected.
- Animal / Wildlife Feed: Only natural background and material from weapons testing has been detected.
. Eggs: Only natural background radioactive material has been de-tected.
Aquatic Monitoring e Surface Water (Treated and Untreated): In 1979 and 1980, the tritium concentrations at location T-7 were above normal back-ground. Location T-7 is a beach well fed directly by Lake Erie. The fourth quarter sample in 1979 read 590 picoeuries per liter, and the first quarter sample in 1980 had a concentration of 960 picocu- ) ries per liter. A follow up sample was collected in Lake Erie be-tween T-7 and the Davis-Besse liquid discharge point. This sample j contained tritium at a concentration of 2737 picoeuries 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 I 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 I (MPC of 3,000,000 picocuries per liter) for tritium in unrestricted 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 concentra-tion 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 300 yards from the mouth of the Tous-saint River. The August composite was 884 picoeuries per liter. Follow up samples were less than the LLD of 330 picocuries per liter. Although this concentration may be attributed to the opera-tion of Davis-Besse, it was only 0.029% of the maximum permissi-ble concentration for tritium in an unrestricted area. -This did not have any significant adverse effect on the environment and the population near the station. The December 1992 composite for tritium at T-3 (mouth of Tous- I saint River) showed trace amounts of activity which may be attributed to the normal operation of the station. The tritium con-centration for the composite was 950 pCi/l. This is only 0.032 per-cent of the maximum permissible concentration of 3,000,000 pCi/l for tritium in an unrestricted area, as stated in 10 CFR 20, Appen-dix B, Table 2. Subsequent samples collected during January 1993 36
__.__..._.._m . _ _ . _ . . _ . _ . - . _ . _ . _ . . _ _ _ . _ _ . - _ . . . _ _ - . . _. i ~ , Divis-Besse Nuclear Power Station 1995 Annual Radiologie:1 Environmental Operating Repon i i showed that the tritium had returned to below the LLD of l 330 pCi/1. In the fourth quarter of 1994, tritium was detected at 336 94 pCi/1, slightly above the lower limit of detection for tritium, at one of the i treated water sampling locations. Tritium was also detected at sev- i eral of the untreated water sampling locations at an average concen- ; tration of 470 pCi/l during the 3rd and 4th quarters of 1994. l Samples taken in January 1995 indicated that the tritium concentra- l tion in untreated water was less than the lower limit of detection for tritium in water. For comparison purposes, tritium concentrations l in Lake Erie untreated surface water, determined during the preop- t erational sampling period of July 1972 through June 1974, ranged ! l from 180 pCi/l to 590 pCi/l with an average concentration of less ; than 300 pCi/l. During 1995, trace amounts of tritium was detected in six untreated ; l water samples collected in May and in one sample collected in Oc- !
- tober. The tritium detected ranged between 330 to 1234 pCi/l with l an average concentration of 681 pCi/1. This is only 0.12% of the i Ef0uent Concentration Limit of 1,000,000 pCi/l for tritium in an unrestricted area, as stated in 10 CFR 20, Appendix B, Table 2. j Subsequent samples taken showed the tritium activity to be {
<330 pCi/1. !
e Fish: Only natural background radioactive material and material ! from nuclear tesdng has been detected.
. Shoreline Sediments: Only natural background, material from I nuclear testing and frau ine 1986 nuclear accident at Chernobyl has been detected. ,
Direct Radiation Monitoring- ! t e Thermolumir escent Dosimeters (TLDs): The annual average l [ ganuna dose iEs for the current reporting period recorded by TLDs have ranged nom 47.1 to 74.7 millirem per year at contros i locations and between 35.7 and 77.1 millirem per year at indicator i locations. No increase above natural background radiation attribut-able to the operation of Davis-Besse has been observed. l 1995 Program Deviations 1 Provided below is a description and explanation of 1995 environmental sample collection i l deviations. Braad leaf vegetation samples during January, February, March, Aprit, May, June, November and December 1995 were unavailable for collection because of seasonal condition or insufficient quantity ; j of desired broad leaf vegetation. ' I i 37 i
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report i e The treated surface water sample from T-144 was deleted from the program in January 1995. On March 14,1995, the untreated surface water sample collected at T-28 may not have been a represented composite for that sampling { period. The line going to the compositor became plugged during the sampling period thus not compositing equal allotments of water. l A new line was installed and the compositor returned to service. l e The first quarter and annual TLDs were discovered missing from T-80 and T-92 at the time of TLD exchange. The reason is thought - to be random acts of vandalism. j l
- Due to bald eagle nesting activity in the vicinity of T-61 TLD, the l l !
l first quarter TLD was not removed until the end of the second l quarter. The dose on the TLD was reported so that equal partions was attributed to the first and second quarters. The second quarter and annual TLDs were discovered missing from T-66 and T-81 at the time of TLD exchange. The reason is thought to be random acts of vandalism. On July 11, 1995, three required continuous air monitors (T-1, T-2, and T-3) were out of service up to 4 hours due to maintenance activities.
. On July 25,1995, the compositor at T-28 untreated surface water location malfunctioned when the intake line broke. A grab sample was collected and the compositor was repaired and returned to service.
( e The third quarter and annual TLDs were discovered missing from l T-155 at the time of TLD exchange. The reason is thought to be a random act of vandalism. On October 24,' 1995 at T-4, the required LLD of <0.07 pCi/m' for I-131 could not be reached because of insufficient sample volume. Dae to a power outage cause by severe weather, a sufficient sample volume could not be collected during the sample period. The LLD reached for this sample was <0.08 pCi/m'.
- In October 1995, egg samples were unavailable for collection. The chickens at indicator location T-197 were not producing eggs yet.
The control location T-34 did not raise egg laying varieties of 1 chickens. I e In November 1995, the second fish collection of the year was not collected. The nets were removed from the indicator location early j in the month because of low fish harvest. Weather conditions on the lake also prevented collection prior to the nets being removed. ! I 38
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report I
- In December 1995, the wild meat (muskrat) sample was not col- ;
lected. The lower water levels in the onsite marsh reduced the muskrat population. Samples could not be purchased from trappers of this area because a permit to trap was not issued by the U.S. Fish and Wildlife Depanment. Also, effons by site personnel to trap , muskrats were unsuccessful. l
? The fourth quarter and annual TLDs were missing from T-112 at j the time of TLD exchange. The reason is thought to be random act ;
ofvandalism. i Atmospheric Monitoring Air Samples 4 Environmental air sampling is conducted to detect any increase in the concentration of airbome ! radionuclides that may be inhaled by humans or serve as an external radiation source. Inhaled ra- i dionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air samples collected by the Davis-Besse REMP include both airborne particulates and airborne radiolo-dine. Samples are collected weekly with low volume vacuum pumps which draw a continuous sample , through a glass fiber filter and charcoal cartridge at a rate of approximately one cubic foot per mi- ; nute. Airborne paniculate samples are collected on 47 mm diameter filters. Charcoal cartridges are installed downstream of the paniculate filters to sample for the airborne radioiodine. ! The airborne samples are sent to an offsite contractor laboratory for analysis. At the laboratory, 5 the airbome particulate filters are stored for 72 hours before they are analyzed to allow for the decay of naturally occurring short-lived radionuclides. However, due to the short half-life of io-dine-131 (approximately eight days), the airborne radioiodine cartridges are analyzed upon receipt 3 by the contractor laboratory. ! r Airborne Particulates Davis-Besse continuously samples air for airborne radionuclides at ten locations. There are six j indicator locations including fear 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 (composited) 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 concentration of 0.019 pCi/m'and 0.020 pCi/m', respectively. Beryllium-7 was the only gamma ; emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites. { Beryllium-7 is a natumlly occurring radionuclide produced in the upper atmosphere by cosmic ; radiation. No other gamma emitting radionuclides were detected above their respective LLDs. l Strontium-89 (Sr-89) was not detected above its LLD of 0.0011 pCi/m'. Strontium-90 (Sr-90) t 39 l
Divis-Besse Nucle:r Power Station 1995 Annual Radiological Environmentil Operating Report i was detected in one sample (T-2) during the second quarter at 0.002 0.0004 pCi/m'. For com-parison purposes, Sr-90 in air during the preop: rational period ranged from 0.0002 pCi/l to . 0.0026 pCi/l. These results show no adverse change in radioactivity in air samples due to opera-tion of the Davis-Besse Nuclear Power Station in 1995. l l Airborne Iodine-131 1 Airborne iodine-131 samples are collected at the same ten locations as the airbome particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly, sealed in separate t illection bags and sent to the laboratory for gamma l spectral analysis. In all of the samples collected in 1995, there was no detectable iodine-131 above l 3 the LLD of 0.07 pCi/m . On October 24,1995, at T-4, the required LLD for I-131 could not be s reached because ofinsufficient sample volume for that sampling period. The low volume was the result of a power outage caused by severe weather conditions. The LLD reached for this sample was <0.08 pCi/m'. i Gross Beta Concentration for Airbome Particulate During 1995 0.03 l l 0.028 - -- 0.026 -- -- u 0.024 - -
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40
Davis.Besse Nuclear Power Station 1995 Annual Radiological Environmental Opertting Report Table 5: Air Monitoring Locations Sample Location Type of Number Location Location Description T-1 I Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station T-4 I Site boundary 0.8 miles S of Station T-7 I Sand Beach, main entrance,0.9 miles NW of Station T-8 I Earl Moore Farm,2.7 miles WSW of Station T-9 C Oak Harbor Substation,6.8 miles SW of Station T-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 ! = Indicator C = Control 41
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Davis-Besse Nuclear Power Station 1995 Annu:1 Radiologicti Environmental Operating Repon Terrestrial Monitoring The collection and analysis of groundwater, milk, meat, fmits 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 I chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere. f i 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 upper atmosphere and as a result of routine release from ! nuclear facilities '
+ beryllium-7, present as a result of the interaction of cosmic radia-tion with the upper atmosphere e cesium-137, a man-made radionuclide which has been deposited in l the environment, (for example, in surface soils) as a result of fallout l from nuclear weapons testing and routine releases from nuclear ;
I facilitics ; e potassium-40, a naturally occuning 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 facilities The radionuclides listed above are expected to be present in many of the environmental samples collected in the vicinity of the Davis-Besse Station. The contribution of radionuclides from the operation of Davis-Besse is assessed by comparing sample results with preoperational data, op-erational data from previous years, control location data, and the types and amounts of radioac-tivity normally released from the Station ia liquid and gaseous effluents. l Milk Samples i 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 releases I onto forage consumed by cows. The radionuclides present in the forage catin.g cow become in-corporated into the milk which is then consumed by humans. 45
i Divis-Besse Nuclear Power Station 1995 Annuil Radiological Environmentti Operating Report , 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. i Sampling is increased in the summer when the herds are usually outside on pasture and not on i 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 dany business and sold the herd. The control location will continue to be sampled monthly in order to gather additional baseline data. If any , dairy ammals are discovered within five miles of the station, efforts will be made to include them ; in the milk sampling program. ' The 1995 milk samples were analyzed for strontium-89, strontium-90, iodine-131 and other ! gamma emitting radionuclides, stable calcium and potassium. A iotal of 12 milk samples were i collected in 1995. Strontium-89 was not detected above the LLD of 0.8 pCi/l in any of the sam-ples. Strontium-90 was detected in all samples collected. The annual average concentration of strontium-90 was 1.2 pCi/1. For all sample sites, the annual average concentration was similar to those measured in the previous years. Iodine-131 was not detected in any of the milk samples above the LLD of 0.5 pCi/l. The concen-trations of barium-140 and cesium-137 were below their respective LLDs in all samples collected. , 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 radiouuclides, the ratios of the strontium radioisotopes radioactivity (pCi/l) to the concentration of calcium (g/l), and cesium radioisotopes radioactivity (pCi/l) to the concentration of potassium (g/1) were monitored in milk. ; 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 i of Station , C = Control 46
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Rcport t 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 i 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 l analyzed for beta emitting radionuclides, tritium, strontium-89, strontium-90 and gamma emitting radionuclides. Beta emitting radionuclides average 3.56 pCi/l for indicator locations and 4.97 pCi/l for control locations. Tritium was not detected above the LLD of 330 pCi/1. Strontium-89 was not detected i above the LLD of 1.2 pCi/1. Strontium-90 was detected in indicator sample at an average concen-tration of 0.7 pCi/1. There were no gamma emitting radionuclides detected above their respective LLDs in any of the samples collected. All sample analyses were within normal ranges and were j similar to results of previous years. j Gross Beta Concentration in Groundwater from 1982 Through 1995 8 u 7 a .i\
& I.
56 j 3 --*- Indicator 5 . g ,. .
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"$ 3 2 S S S S S - 2 S S S S YEAR Figure 14: Shown above are the annual averages for gross beta in groundwater from 1982 - 1995. This years results are well within the range of previous years.
47
I i Divis-Besse Nuclear Power Station 1995 Annual Radiological Environmentil Operating Report Table 7: Groundwater Monitoring Locations Sample Location Type of Number Location Location Description 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,4.8 miles SW of Station
.T-141 QC Roving Site I = indicator C = control QC = quality control Broad Leaf Vegetation and Fruit Samples 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 fallout or airbome releases from nuclear facilities) or from irrigation water drawn from lake water receiving liquid effluents (from hospitals, nuclear facilities, etc.). Radionuclides from the soil may l 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 1995, broad leaf vegetation samples were collected at two indicator locations (T-17 and T-19) and one control location (T-37). Fruit samples were collected at two indicator locations (T-8 and 3 T-25) and two control locations (T-37 and T-173). Broad leaf vegetation was collected once a month during the growing season. Broad leaf vegetation collected consisted of cabbage, kale, beet
- greens, chinese cabbage and broccoli. The fruits collected were apples, pears, and grapes. All samples were analyzed for gamma emitting radionuclides, strontium-89, strontium-90, and iodine-131.
Iodine-131 was not detected above the LLD of 0.028 pCi/g (wet) in any broad leaf vegetation nor above the LLD of 0.021 pCi/g (wet) in fruit samples. The only gamma emitting radionuclide de-tected in the fruit and broad leaf vegetation samples was potassium-40, which is naturally occur-ring. In both fruit and broad leaf vegetation, strontium-89 was not detected above their LLDs of 0.0065 pCi/g (wet) and 0.0067 pCi/g (wet). Strontium-90 (Sr-90) was detected at average con-centrations of 0.002 pCi/g (wet) for indicator locations and 0.0014 pCi/g (wet) for control loca-tions. In the fruit samples, Sr-90 was detected at location T-8 (indicator) at 0.0005 pCi/g and l 48 l
1 Davis-Besse Nucl:ar Power Sttion 1995 Annual Radiological Environmental Operating Repon 1 T-173 (control) at 0.0036 pCi/gm Sr-90. All results of analyses were similar to results obsened l in previous years; this demonstrates that the operation of Davis-Besse had no adverse effect on the surrounding environment. 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 Centerior Energy propeny,0.68 mile SW of Station ! T-19 I Hemminger Farm,0.6 mile W of Station T-25 I Miller Farm,3.7 miles S 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. l l 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 airbome radionuclides deposited in the vicinity of the Station. Analyses of animal / wildlife feed samples also provide data for determining radionuclide concentration in the food chain. Domestic animal 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 samples, natu-rally occurring potassium-40, cosmic ray produced radionuclides such as beryllium-7, and fallout i radionuclides from nuclear weapons testing may be present in the feed samples. l
. Domestic animal feed was collected annually at chicken sampling locations. 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 emitting radionuclides.
49
Davis-Besse Nuclear Power Station 1995 Annual Radiological Enviroamental Operating Report
. Wildlife feed was collected annually at two locations (T-31 and T-198). The samples consisted of the edible portions of cattails.
Samples were analyzed for gamma emitting radionuclides. In both 1 the ammal and wildlife feed, only naturally occurring potassium-40 was detected. All other radionuclides were below their respective LLDs. The operation of Davis-Besse had no adverse effect on the surrounding environment. l l I Table 9: Animal / Wildlife Feed Locations l l Sample Location Type of Number Location Location Description l T-31 I Davis-Besse, onsite roving location T-34 C Brooks farm, Graytown 8.8 miles W. of the Station T-197 I Priesman Farm 1.7 miles W of the Station T-198 I Toussaint Creek Wildlife Area 4.0 miles WSW of the Station I = indicator C = control Wild and Domestic Meat Samples Sampling of domestic and wild meat provides information on environmental radionuclide concen-trations that humans may be exposed to through an ingestion pathway. The principle pathways 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 re-leasedin 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 water-fowl, deer, rabbits and muskrats. Analyses from animals whose meat is eaten by humans provides generalinformatica 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 ammal before drawing conclusions on radionuclides concentration in the local environment or in a species as a whole. 50
i l Davis-Besse Nuclear Power Station 1995 Annual Radiologicci Environmental Operating Report i Both wild and domestic meat samples and eggs were sampled in 1995 as follows: Domestic Meat: Chickens were collected at one indicator location l (T-197) and one control location (T-34). The samples were ana- I lyzed for gamma emitting nuclides.
. Wild Meat: Muskrat samples were not obtained because lower marsh levels onsite made collecting a sample impractical.
. Eggs: Eggs were unavailable at both locations at the time of col-lection. T-197 chickens were not laying eggs yet and T-34 did not
)
l have any laying chickens. l Table 10: Wild and Domestic Meat Locations Sample Location Type of Number Location Location Description T-31 I Onsite roving location T-34 C Brooks Farm, Graytown,8.8 miles W. of I the Station T-197 I Priesman Farm,1.7 miles W of the Station I = indicator C = control Soil Samples Soil samples are generally collected twice a year at the sites which are also equipped with air samplers. Only the top layer of soil is sampled in an effort to identify possible trends in the local environmental nuclide concentration caused by atmospheric deposition of fallout and station re-leased radionuclides. Generally, the sites are relatively undisturbed, so that the sample will be rep-resentative 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 which are often detected include strontium-90 (Sr-90), cesium-137 (Cs-137), cerium-141 (Ce-141) and ruthenium-106 (Ru-106). 51
, Davis-Besse Nuclear Power Station 1995 Annual Radiologiet! Environmentd Operating Report During 1995, soil was collected at ten sites in May and November. 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 i was found in both indicator and control locations at average concentrations of 0.57 and 0.40 pCi/g dry, respectively. The concentrations were similar to that observed in previous years t (Figurel5). Cs-137 Concentration in Soil from 1972 to 1995 , 1.2 1 m l 1 .-
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Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 11: Soil Locations Sample Location Type of Number Location Location Description T-1 I Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary 1.4 miles ESE of Station T-4 I Site boundary 0.8 miles S of Station T-7 I Sand Beach, main entrance,0.9 miles NW of Station ) T-8 1 Moore Farm,2.7 miles WSW of Station T-9 C Oak Harbor Substation,6.8 miles SW of' Station j T-11 C Pon Clinton Water Treatment Plant,9.5 miles j SE of Station ! T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station l T-27 C Crane Creek State Park,5.3 miles WNW of Station I = indicator C = control i 53
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Divis-Besse Nuclear Power Station 1995 Annual Radiological Environment:1 Operating Repon j Aquatic Monitoring
- Radionuclides may be present in Lake Erie from many sources including atmospheric deposition,
, mn-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 j immersion (swimming) in the water. Internal exposure can occur from ingestion of radionuclides, ! either directly from drinking water, or as a result of the transfer of radionuclides through the j 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 4 water (lake or river water), fish, and shoreline sediments.
i 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 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, Erie Industrial Park, Port Clinton and Toledo. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta emitting radionuclides. The samples were also composited in a quarterly sample and analyzed for strontium-89, stron-tium 00, gamma emitting radionuclides, and tritium. One QC sample was collected from a routine location which was changed each month. The annual average for beta emitting radionuclides for indicator and control locations were 2.0 and 2.1 pCi/l respectively. These results are similar to previous years as shown in Figure 19. All quarterly tritium analysis results were less than the LLD of 330 pCi/1. All cesium-137 results were less than the LLD of 10.0 pCi/1. Strontium-89 was not detected in any sample above 1.4 pCi/1. Strontium 90 was detected at 0.8 pCi/l at indicator locations and 0.7 pCi/l at control locations. These results are similar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Y _vis-Besse. t 57
DI.vis-Desse Nuclear Power Station 1995 Annual Radiological Environmentil Operating Report Gross Beta Concentration in Treated Surface Water from 1972 to 1995 3.3 ,, 3.1 - \" E
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E E $ $ $ $ $ $ YEAR Figure 19: Since 1974, the annual concentrations of beta emitting radionuclides in treated surface water samples l collected from indicator locations have been consistent with those from control locations. This shows that Davis-Besse has had no measurable radiological impact on surface water used to make drinking water. l Table 12: Treated Surface Water Locations l l l Sample Location Type of Number Location Location Description l T-11 C Pon Clinton Water Treatment Plant 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant 23.5 miles WNW of Station T-28 I Treated Water supply from Davis-Besse site T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE of Station T-143 QC Quality Control Site
! = indicator C = control QC = quality control i
l 58 i I
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Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmentd Operating Report Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to hu-mans from external exposure from the lake surface as well as immersion in the water. It also provides information on the radionuclides present which may affect drinking water, fish, and irri-gated crops. Routine Program The routine program is the basic sampling program which is performed year round. Untreated t water samples are collected in the areas of the station intake and discharge and at the water in-takes used by nearby water tmatment plants. Routine samples are collected at Port Clinton, Toledo, Davis-Besse, and Eric Industrial Park. A sample is also collected from Lake Erie at the mouth of the Toussaint River. 'Ihese samples are collected weekly and composited monthly. The , monthly composite is analyzed for beta emitting radionuclides, tritium, and ganuna emitting radi-onuclides. The samples are further composited 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 The summer program is designed to supplement the routine untreated water sampling program in order to provide a more comprehensive study during the months of high lake recreational activity, 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 radioactivity, tritium, strontium-89, strontium-90 and gamma emitting radionuclides. For the routine samples composited weekly, the beta emitting radionuclides had an average con-centration of 2.6 pCi/l at indicator and 2.3 pCi/l at control locations respectively. The average concentration of beta emitting radionuclides in all samples (include lake water) was 2.6 pCi/l at both indication and control locations. Of the 132 tritium analyses performed on untreated water,123 were less than the LLD of 330 pCi/1. The tritium detected, ranged from a concentration of 330 pCi/l to 1234 pCi/1. The av-erage concentration of tritium detected above the LLO was 681 pCi/l at indication location and 487 pCi/l at controls. It is presumed that the tritium detected at the indicator location may have been attributed to normal plant operation. The maximum tritium concentration detected is only O.12% of the effluent concentration limit of 1,000,000 pCi/l for tritium in an unrestricted area, as provided by 10CFR20, Appendix B, Table 2, column 2. The tritium detected at the control loca-tion is pmsumed 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 pCi/l and 1.3 pCi/1, respectively. Strontium-90 was detected at an average concen-tration of 0.63 pCi/l at indicator locations and 0.65 pCi/l at control locations. The results of un-treated water show that the operation of Davis-Besse had no adverse impact on nearby residents or on the environment, i 59
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Gross Beta Concentration in Untreated Surface Water 6.5 , from 1977 to 1995 6- --th-.
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R R E E E E E E E E S S S S S S S S S S l YEAR ' Figure 20: The average concentration of beta emitting radionuclides in untreated water was similar between con-trol and indicator locations. This demonstrates, that Davis-Besse had no radiologicalimpact on the surrounding environment. Each month, weeldy 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 aver-age concentrations of beta emitting radionuclides detected at the QC location was 2.5 pCi/l and l 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 l l l 60 l
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmentd Operating Report l Table 13: Untreated Surface Water Locations l 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 1 Erie Industrial Park, Port Clinton,4.5 miles SE of Station I 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 I 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 l T-158 C Lake Erie,10.0 miles WNW of Station i T-162 C Lake Erie,5.4 miles SE of Station T-167 C Lake Erie,11.5 miles E of Station I = indicator C = control 61
Divis-Besse Nucle:.r Power Strtion 1995 Annual Radiological Environmental Operating Report Shoreline and Bottom Sediment The sampling of shoreline and bottom sediments can provide an indication of the accumulation of undissolved 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, or a hand held dredge. All samples were analyzed for gamma emit-ting radionuclides. Naturally occurring potassium-40 was detected at both controls and indicator locations. Cesium-137 was not detected at any location above the LLD of 0.048 pCi/g. Atmospheric testing of nuclear weapons has been the principal source of cesium-137 in the envi-ronment to date. Although no atmospheric nuclear weapons tests have been reported since 1980, cesium-137 is still present in shoreline sediment samples because of its long half life (approxi-mately 30 years). No other gamma emitting radionuclides were detected in any of the samples above their LLD. The concentrations of those detected were consistent with normal concentra-tions for this area and were not attributed to plant operation. Table 14: Shoreline and Bottom 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 62
Davis Besse Nuclear Power St-lion 1995 Annual Radiologicci Environmental Operating Report Fish Sample l Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondarily l to serve as indicators of radioactivity in the aquatic ecosystem. The principal nuclides which may l be detected in fish include naturally occurring potassium-40, as well as cesium-137, and stron-tium-90. Depending upon the feeding habit of the species (e.g., bottom-feeder versus predator), i results from sample analyses may vary. 1 With the aid of a local commercial fisherman, Davis-Besse routinely collects three species of fish (walleye, white perch or white bass and carp) twice a year from sampling locations near the Sta-tion's liquid discharge point and rnore than ten miles away from the Station where fish populations l would not be expected to be impacted by the Station operation. Walleye are collected because l they are a popular sport fish, white perch or white bass because they are an important commercial i fish. Carp are collected because they are bottom feeders and thus would be more likely to be af- l fected by radionuclides deposited in lake sediments. The edible portion of fish were analyzed for j beta and ganuna emitting radionuclides. , 1 The average concentration of beta emitting radionuclides in fish muscle was similar for indicator and control locations (3.06 pCi/g and 3.34 pCi/g wet weight, respectively). Cesium-137 was not detected above the LLD <0.024 for indicator and control locations. No other gamma emitter , were detected above their respective LLDs. i i i I Gross Beta Concentration in Fish 1972 to 1995 l 4.5 4 s Q ,,
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. - . . _ . . - . - - . . - - . - ~ - - . - - - - , . . .-
Divis-Besse Nuclear Power Stition 1995 Annud Radiological Environmental Operating Report Table 15: Fish Locations l Sample Location Type of Number Location Location Description T-33 I Lake Erie, within 5 miles radius of Station l l l T-35 C Lake Erie, greater than 10 mile radius of Station I = indicator C= control 1 I l l b
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Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Opertting Report 1 Direct Radiation Monitoring I l Thermoluminescent Dosimeters i Radionuclides present in the air, and those deposited on the ground, may directly irradiate indi- I 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 1 l sensitive material in the TLD. Energy is trapped in the TLD material and can be stored for sev-eral months or years. This provides an excellent method to measure the dose received over long periods of time. The energy that was stored in the TLD as a result ofinteraction with radiation is l released and measured by a controlled heating process in a calibrated reading system. As the l 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 11 control) which are collected and replaced on a quarterly and annual basis. Eighteen QC TLDs are also collected on a quarterly and annual basis. There is a total of 186 TLDs in the environment surrounding Davis-Besse at any given time. By collecting TLDs on a quanerly and annual basis from a single site, each measurement serves as a quality control check on the other. Over 98.9% of the quarterly TLDs placed in the field and 95.7% of the annual TLDs placed in the field were retrieved and evaluated during the current reporting period. In 1995, the average dose equivalent for quarterly TLDs at all indicator locations was 13.0 mrem /91 days, and for all control locations was 14.2 mrem /91 days. The average dose equivalent for annual TLDs in 1995 was 54.5 mrem /365 days at indicator locations and ; 58.2 mrem /365 days for control locations. These results are similar to those observed in past ; years; in 1974,55-62 mrem in one year was reported as being the annual average dose equivalent. j 1 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 provides a method to check the accuracy of the measurements. The average dose equivalent at the routine j TLDs averaged 13.5 mrem /91 days while the quality control TLDs yielded an average dose
- equivalent of 13.0 mrem /91 days. All the quality control and routine sample results were similar, l demonstrating the accuracy of both the TLDs and the laboratory's measurements.
68
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._ _ _ - - _ _ _ _ _ . _ _ _ _ _ _ m . - _ . Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental Operating Report Gamma Dose for Environmental TLDs from 1973 to 1995 24 l l 22 8 - - - - 20 - I. E 18 - . -
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NRC TLD Monitoring The NRC has 22 TLDs located around Davis-Besse as part of their Direct Monitoring Network Program. Davis-Besse maintains TLDs at all the NRC TLD monitoring sites. The NRC collects their TLDs on a quarterly basis, whereas Davis-Besse collects TLDs quarterly and annually at I these locations. The NRC TLDs are collected and read independently of Davis-Besse's TLDs, thus providing a quality control check on both laboratories. The NRC uses Panasonic Model UD801 TLD, which has two elements oflithium borate: copper (Li 2B407: Cu) and two elements of calcium sulfate: thulium (CaSO4: Tm). The difference in TLD material used by the NRC and Davis-Besse will cause some minor variation in results. The results of TLD monitoring at these 22 locations show good consistency between the NRC TLDs and the Davis-Besse TLDs. The average dose equivalent of the quarterly results are 13.7i2.3 mrem /91 days for the Davis-Besse TLDs and 17.li2.6 mrem /91 days for the NRC TLDs. As the confidence intervals overlap, there is no statistical difference between the meas-urements. 1 69
Davis.Besse Nuclear Power Station 1995 Annual Radillogical Environmental Operaung Report Gamma Dose for NRC and Davis.Besse TLD for 1988 to 1995 20 19
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- Comparison of NRC and Davis-Besse TLDs Table 16: Thermoluminescent Dosimeter Locations l F:.mple 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 l T.5 I Site boundary,0.5 miles W of Station i T-6 I Site boundary,0.5 miles NNE of Station l l T-7 I Sand Beach, main entrance,0.9 miles NW of Station T-8 I Earl Moore Farm,2.7 miles WSW of Station T-9 C Oak Harbor Substation,6.8 miles SW of Station T-10 I Site boundary,0.5 miles SSW of Station near warehouse 1 70
_. _ __....._m.m . _ , _ . . . _ . _ _ _ . _ _ __. . _ _ _ _ _ . . _ _ . . . _ . _ _ . _ Davis.Besse Nuclear Power St: tion 1995 Annual Radiologicil Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued) Sample Location Type of Number Location Location Description 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 l T-23 C South Bass Island,14.3 miles ENE of Station, nearlighthouse 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 j 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 T-43 I Site boundary,0.5 miles SW of Station T-44 I Site boundary,0.5 miles WSW of Station i T-45 I Site boundary,0.5 miles WNW of Station l T-46 I Site boundary,0.5 miles NW of Station T-47 I Site boundary,0.5 miles N of Station T-48 I Site boundary,0.5 miles NE of Station T-49 I Site boundary,0.5 miles NE of Station T-50 I Erie Industrial Park, Port Clinton, 4.5 miles SE of Station T-51 C Daup Farm,5.5 miles SSE of Station 71
Divis-Besse Nuclear Power Station 1995 Annual Radiologiet! Environmentti Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued) Sample Location Type of Number Location Location Description 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-61 I Site boundary,0.6 miles SE 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 T-68 I Site boundary,0.5 miles WNW of Station T-69 I Site boundary,0.4 miles W of Station 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 boundarf,0.1 mile SE of Station T-80 QC Quality Control Site T-81 QC Quality Control Site T-82 QC Quality Contcol Si'e T-83 QC Quality Control Site T-84 QC Quality Control Site 72
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmentcl Opescling Report Table 16: Thermoluminescent Dosimeter Locations (continued) Sample Location Type of Number Location Location Description T-85 QC Quality Control Site T-86 QC Quality Control Site T-88 QC Quality Control Site T-89 QC Quality Control Site T-91 1 State Route 2 and Rankie Road,2.5 miles SSE of Station T-92 I Locust Point Road,2.7 miles WNW of Station T-93 I Twelfth Street, Sand Beach,0.6 miles NNE of Station T-94 1 State Route 2,1.8 miles WNW of Station T-95 C State Route 579,9.3 miles W of Station 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 , l T-114 QC Quality Control Site i T-115 QC Quality Control Site T-116 QC Quality Control Site T-117 QC Quality Control Site T-118 QC Quality Control Site T-119 ! QC Quality Control Site ! I 73
Davis-Besse Nuclear Power Station 1995 Annuil Radiological Environmental Operating Report I' i Table 16: Thermoluminescent Dosimeter Locations (continued) i ( Sample Location Type of Number Location Location Description l' l T-120 QC Quality Control Site l 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 i 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 l miles SSE of Station T-128 I Erie Industrial Park, Port Clinton Road, 4.0 miles SE 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 l T-200 QC Quality Control Site I T-201 I Sand Beach,1.1 m.iles NNW of Station T-202 i Sand Beach 0.8 miles NNW of Station 74 l >
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Opertting Report Table 16: Thermoluminescent Dosimeter Locations (continued) l Sample Location Type of Number Location Location Description T-203 I Sand Beach,0.7 miles N of Station T-204 I Sand Beach,0.7 miles N of Station i 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 l 1 l 75
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Davis-Besse Nuclear Power Station 1995 Annual Radiological Environment:.1 Operiting Report Conclusion The Radiological Envimnmer.io! Monitoring Program at Davis-Besse is conducted to determine the radiological impact of the Station's operation on the environment. Radionuclide concentra-tions measured at indicator locations were compared with concentrations measured at control lo-cations, in previous operational studies and in the preoperational surveillance program. These ) comparisons indicate normal concentrations of radioactivity in all environmental samples collected ! in 1995. Davis-Besse's operation in 1995 had no adverse impact on the residents and environment { surrounding the station. The results of the sample analyses performed during the period of 1 January through December 1995 are summarized in Appendix D of this report. 1 l I I l 1 79
l Davis-Besse Nucle:.r Power Station 1995 Annual Radiologicil Environmental Operating Report ! i References
- 1. " Cesium-137 from the Environment to Man: Metabolism and Dose," Report No.52, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1977).
- 2. " Environmental Radiation Measurements," Report No.50, National Council on Radiation Protection and Measurement, Washington, D.C. (December 1976).
- 3. " Exposure of the Population in the United States and Canada from Natural Background Ra-diation," Report No.94, National Council on Radiation Protection and Measurement, Wash-ington, D.C. (December 1987).
- 4. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy Installa-tions," 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 l Criterion 'As Low As Reasonably Achievable' for Radioactive Materialin Light Water l 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).
- 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.
(December 1987). l
- 10. " Radiological Assessment: Predicting the Transport , Bioaccumulation and Uptake by Man of Radionuclides Released to the Environment," Report No.76, National Council on Radiation i 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).
l 80
. . . _ . _ _ ..m__._._._._ .. - __ -. _ _ ...___. _. __ _ _ ..._ _ _ _ _ __ _ _
t Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Oper: ting Report
- 13. Regulatory Guide 4.15," Quality Assurance for Radiological Monitoring Programs (Normal Operations)- Effluent Streams and the Environment," US NRC (February 1979).
- 14. Regulatory Guide 0475, " Radiological Environmental Monitoring by NRC Licensees for
, Routine Operations of Nuclear Facilities," US NRC (September 1978).
- 15. Regulatory Guide 0837, "NRC TLD Direct Radiation Monitoring Network," US NRC (1995).
- 16. " Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, Part 20 (1993).
- 17. Teledyne Isotopes Midwest Laboratory, " Operational Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No.1, Oak Harbor, OH," Annual Report, Parts I and II (1977 through 1990).
- 18. Teledyne Isotopes Midwest Laboratory, " Final Monthly Progress Report to Toledo Edison Company", (1991-1995).
- 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 Ef-fluent 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.
81
Divis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report
- 28. Toledo Edison Company," Updated Safety Analysis for the Offsite Radiological Monitoring Program," USAR 11.6, Revision 14,(1992).
- 29. Toledo Edison Company, " Annual Radiological Environmental Operating Report Preparation and Submittal," DB-HP-00014.
- 30. Toledo Edison Company, Davis-Besse Nuclear Power Station, Offsite Dose Calculation Manual
- 31. " Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979).
82
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Davis-Besse Nuclear Power Stttion 1995 Annut! Radiological Environmentti Operating Report Radioactive Effluent Release Report January 1 through December 31,1995 Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ionizing radiation were acognized and efforts were made to establish radiation protection standards. The primary source of mcommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recom-mendations have been given legislative authority through publication in the Code of Federal 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 mducing 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 below regulatory limits. Sources of Radioactivity Released During the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in 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 equip-ment drains and sumps. All liquids of this nature are monitored and processed, if necessary, 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. 83
Davis-ihsse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an external source of radiation exposure to the body. Xenon-133 and xenon-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive noble gases released. They are readily dispersed in the atmosphere. Iodine and Particulates Annual releases of radioisotopes of iodine, and those paniculates with half-lives greater than 8 days, in gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing sys-tems, minimize their discharge. The predominant radioiodine released is iodine-131 with a half-life of approximately eight days. The main contribution of radioactive iodine to human dose is to the thyroid gland, where the body concentrates iodine. The principal radioactive particulates released are fission products (e.g., cesium-134 and cesium-137) and activation products (e.g., cobalt-58 and cobalt-60). Radioactive cesiums and cobalts contribute to internal radiation exposure of tissues such as the muscle, liver, and intestines. These particulates are also a source of external radiation exposure if deposited on the ground. Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in liquid effluents. It is also present in gaseous effluents. Tritium is produced in the reactor coolant as a result of neu-tron interaction with deuterium (also a hydrogen isotope) present in the water and with the boron in the primary coolant. When tritium, in the form of water or water vapor, is ingested or inhaled it is dispersed throughout the body until eliminated. Processing and Monitoring Effluents are strictly controlled to ensure radioactivity released to the environment is minimal and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance programs for efflu-ent and environmental programs, and procedures covering all aspects of effluent and environ-l mental monitoring. I 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 instmment 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 automatically stopped. 84
1 Dovis-Besse Nuclear Power Station 1995 Annual Radiologicol Environmental Operating Report i i 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 comput-ers which record the meteorological data. Coupled with the effluent release data, the meteoro-logical data are used to calculate the dose to the public. Beyond the plant, devices maintained in conjunction with the Radiological Environmental Moni-toring Program constantly sample the air in the surrounding environment. Frequent samples of other environmental media, such as water and vegetation, are also taken to determine if buildup of deposited radioactive material has occurred in the area. Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to ra-dioactive material. The major pathways of concern are those which could cause the highest calcu-lated radiation dose. These projected pathways are determined from the type and amount of ra-dioactive material released, the environmental transport mechanism, and the use of the environ-ment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. Information on the water flow, wind speed, and wind direction at the time of a gaseous or liquid release is used to i evaluate how the radionuclides will be distributed in an area. An important factor in evaluating the exposure pathways is the use of the environment. Many factors are considered such as dietary intake of residents, recreational use of the area, and the locations of homes and farms in the area. The external and internal exposure pathways considered are shown in Figure 30. The release of radioactive gaseous effluents involves pathways such as extemal whole body exposure, deposition of radioactive material on plants, deposition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents in-volves pathways such as drmking water, fish consumption, and direct exposure from the lake at the shoreline and while swimming. 85
. . - _ - - - - _ . _ - - -. ~ _- -- -- _--
Davis-Besse Nuclear Power St" tion 1995 Annual Radiologicol Environmentol Opecing Report Diluted By Atmosphere Airborne Releases O
/
Plume [' E** i eat) h g , "i.f
~
5 i fs $:a ::e.L l d M l
'Y "'"
Consume %.
!!.L%
Uquid Releases Consumed Diluted By Lake By Animals 4j S m M % E. Consumed Consumed t N g'. Vegetation By Man Act JJ h / FISH ro Soil MAN A - Drinking Water
- g. ' in < -4
- e.; - .
Shoreline / Exposure /
'e LAKE l
Q? * .&f.'& l.5 ,/ Figure 30: The exposure pathways shown here, are monitored through the Radiological Environmental Monitor-ing 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 radi-onuclide, 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 l diet of the group, or other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ. Dose Assessment 1 l 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. i 86
l Davis-Besse Nuclear Power St tion 1995 Annual Radiological Environmental Operating Report , l 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 calculated i 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 exposure 3 pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation, l 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 di- , lution, and usage factors (water and fish consumption, shoreline and swimming factors). These l calculations produce a conservative estimation of the dose. Results The Radioactive Effluent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Station during the period from January 1,1995 through December 31,1995.
. Summation of the quantities of radioactive material released in gaseous and liquid effluents e Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites
. A listing of all radioactive effluent monitoring instmmentation required by the Offsite Dose Calculation Manual, but which were inoperable for more than 30 days During this reporting period, the estimated maximum individual offsite dose due to radioactivity released in effluent was:
Liquid Effluents:
- 1.03E-01 mrem, whole body e 1.35E-01 mrem, liver Gaseous Effluents:
Noble Gas: e 3.52E-03 mrad, whole body e 1.34E-02 mrad, skin Iodine - 131, Tritium, and Particulates with Half-lives greater than 8 Days: e 3.94E-03 mrem, whole body
. 1.70E-02 nurm, thyroid These doses are an extremely small fraction of the limits set by the NRC in the Davis-Besse ODCM.
Additional normal release pathways from the secondary system exist. For gaseous effluents, these l 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 basins. Re-leases via these pathways are included in the nomial release tables in this report. l 87
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Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating There were no abnormal liquid releases and no abnormal gaseous releases d period. No changes to the Process Control Program (PCP) his occurred reporting during this time and 9 to the Offsite Dose Calculation Manual were written and approved during t period and accompanies this repon. Regulatory Limits Gaseous Effluents In accordance with Offsite Dose Calculation Manual, dose rates h due to radioa gaseous effluents from the site to areas at and beyond the site boundary sh following: Noble gases:
- Released at a a Late equal to or less than 500 mrem TEDE per year. (Note: the dose due to these releases is also limited to 50 mrem in any calendar year.)
. Released at a r4t_e such that the total dose to the skin will be less than or equa 3000 mrem in a year.
Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater 8 days:
. Released at a rate such that the total dose to any organ will be less than or equa 1500 mrem in a year.
In accordance with 10CFR50, Appendix I, Sec. IIB.1, air dose due to radioactivi gaseous effluents to areas at and beyond the site boundary shall be limited to
. I2ss than or equal to 5 mrad total for gamma radiation and less than or equal to 10 mrad total for beta radiation in any calendar quarter.
. Less than or equal to 10 mrad total for gamma radiation and less than or equal t 20 mrad total for beta radiation in any calendar year.
In accordance with 10CFR50, Appendix I, Sec. IIC, dose to a member of the publ 131, tritium, and all radionuclides in particulate form with half-lives greater than 8 da effluents released to areas at and beyond the site boundary shall be limited to the follo
. Less than or equal to 7.5 mrem total to any organ in any calendar quaner.
- Less than or equal to 15 total mrem to any organ in any calendar year.
88
Davis-Besse Nuclear Power Stition 1995 Annual Radiological Environmental Operating Report Liquid Effluents i In accordance with 10CFR50, Appendix I, Sec IIA, the dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to ac- ! cumulated doses of: 1 1
. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem l to any organ in any calendar quarter. ;
e 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. 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 lx10-5 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. l Average Energy The Davis-Besse oDCM limits the dose equivalent rates due to the release of fission and activa- l 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 Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Efflu-ents from Light-Water-Cooled Nuclear Power Plants" are not applicable. Measurements of Total Activity Fission and Activation Ga.ses: These gases, excluding tritium, are collected in a marinelli beaker specially modified for gas sam-pling, 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. Iodines Iodines are collected on a charcoal cartridge filter and counted on a germanium detector. Specific quantification of each iodine radionuclide is via gamma spectroscopy. Particulates Particulates are collected on filter paper and counted on a germanium detector. Specific quantifi-cation of each radionuclide present on the filter paper is via gamma spectroscopy. 89
Davis-Besse Nuclear Powrr Station 1995 Annual Radiologicil Enviromnental Operating Report Liquid Effluents Liquid effluents are collected in a marinelli beaker and counted on a germanium detector. Quan-tification of each ganuna-emitting radionuclide present in liquid samples is via gamma spectros-copy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system. Batch Releases Liquid from 1/1/95 through 12/31/95
- 1. Number of batch releases: 54
- 2. Total time period for the batch releases: 92.2 hours
- 3. Maximum time period for a batch release: 207 minutes
- 4. Minimum time period for a batch release: 73 minutes
- 5. Average time period for a batch release: 102 minutes Gaseous from 1/1/95 through 12/31/95
- 1. Number of batch releases: 12
- 2. Total time period for the batch releases: 153.8 hours
- 3. Maximum time period for a batch release: 1427 minutes
- 4. Minimum time period for a batch release: 49 minutes
- 5. Average time period for batch release: 769 minutes Abnormal Releases No abnormal releases occurred during this reporting period.
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 1,1995 through December 31,1995. l PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1,1995 - December 31,1995 (gaseous) Noble gases (gamma) 3.52E-03 mrad 10 mrad 3.52E-02 Noble gases (beta) 1.34E-03 mrad 20 mrad ,6.70E-02 I-131, tritium and particulates 1.70E-02 mrad 15 mrem i 1.13E-01 Report Period: January 1,1995 - Decemher 31,1995 (liquid) Total body 1.03E-01 mrem 3 mrem 3.43E+(O Organ 1.35E-01 mrem 10 mrem 1.35E+')0 90
l D2vis-Besse Nuclear Power St: tion 1995 Annual Radiological Environmental Operating Report Sources OfInput Data e Water Usage: Survey of Water Treatment Plants (DSR-95-00347) e 0-50 mile meat, milk, vegetable production, and population data: 1982 Annual En- ' vironmental Operating Report entitled, " Evaluation of Compliance with Appendix I l to 10CFR50: Updated Population, Agricultural, Meat - Animal, and Milk Produc-tion 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 Agricul-tural Statistics,1981"; the Ohio Crop Reporting Service,1981 report entitled, i
" Ohio Agricultural Statistics,1981." !
- Gaseous and liquid source terms: Tables 17 through 21 of this report. i
- Location of the nearest individuals and pathways by sector out to 5 miles, see Land Use Census Section of the report. I e 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 members of the public due to activities inside the site boundary. In special instances, members of the }'ublic 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 also 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 maximumally-exposed visitors is 250 hours (I hr/ day,5 day /
week,50 wk/yr) e Annual average meteorological dispersion (conservative, default use of maxunum site boundary dispersion). I e ' For direct " shine" from the Independent Spent Fue1 Storage Installaticn (ISFSI), default use of the maximum dose rate for a completed (full) ISFSI, and a distance I of 950 feet. 91
Davis-Besse Nuclear Power Station 1995 Ancaal Radiological Environmental Operating Repon The equamans in the ODCM may be used for calculating th ;.otential dose to a member of the public for .etivities 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 members of the public. Inoperable Radioactive Effluent Monitoring Equipment The following radioactive effluent monitoring equipment required to be operable by ODCM Sec-tion 2.1 and 3.1 was inoperable for more than 30 days during this reporting period.
- RE 4598BA was inoperable from 11/1/95 to 12/28/95 due to flow measuring system failure.
No replacement parts were available because the system is obsolete and no longer manufac-tt ed. A new flow system was ordered and installed. During this time a redundant system, RE 4598AA, was operable.
- Fr 5090 was inoperable from 3/21/95 to 5/26/95 due to erratic reading caused by a flow ele-ment failure. The problem was investigated, repaired, the instmment returned to service.
During this time a redundant system, FT5090A, was operable. I e FT 1821 A was inoperable from 10/30/95 to 2/28/96 when the lithium battery for the flow relay indicator failed. A replacement part was not available. After the part was received, the equipment was repaired and returned to service. While FT1821 A was inoperable, a redundant flow transmitter was operable.
- FQI 1700B was inoperable from 7/17/95 to 8/21/95 when a flow integrating indicator failed.
The equipment was repaired and returned to service. During the time this was inoperable, no releases wem made from this pathway. Also, a re,dundant system was available.
- Total Dilution Flow, computer point F201, was unavailable from 6/12/95 to 7/28/95 when one of the input points, F890 Service Water Outflow, failed. Upon completion of maintenance ac-tivities, the computer point was returned to service. During the time F201 was inoperable, to-tal dilution was estimated using other methods.
Changes to the ODCM and PCP There were no changes to the PCP and two revisions (8 and 9) to the oDCM. Borated Water Storage Tank Radionuclide Concentration 1 During this reporting period, the total activity did not exceed the activity limits listed in Davis-j Besse ODCM. i l 92
Table 17 , Gaseous Effluents - Summation of All Releases i. hr a Type Unit 1st Qtr 2nd Qtr 3nt Qtr 4th Qtr Est. Total h 1995 1995 1995 1995 % Error E Fission and Activation Gases S Total Release Ci 3.73E+01 1.44E+02 9.28E+1 2.72E+01 2.50E+01 2 , Average Release Rate for Period" pCi/sec 4.73E+00 1.83E+01 1.18E+01 3.45E+00 $ ! Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section ( 8 lodines G Total lodines Ci 7.38E-05 1.97E-04 2.36E-04 6.57E-05 2.50E+01 8 l 8 Average Releases Rate for Period
- Percent of 0DCM limits pCi/sec See Supplemental Information in ODCM Release Limits Section 9.36E-06 2.50E-05 2.99E-05 8.33E-06 {
E w 8. Particulates 5-Particulates with half-lives greater than 8 days Ci 8.17E-07 3.91E-07 1.26E-06 LLD 2.50E+01 d. Average Release Rate for Period
- pCi/sec 1.04E-07 4.96E-08 1.60E-07 N/A E Percent of ODCM Limits See Supplemental Information in ODCM Release Limit Section f, LLD Gross Alpha Activity Ci 3.65E-07 1.94E-07 2.99E-08 2.50E+01 l
E Tritium g Total Release Ci 7.14E+00 5.42E+00 3.99E+00 4.50E+00 2.50E+01 g Average Release Rate for Period" pCi/sec 9.06E-01 6.87E-01 5.06E-01 5.71E-01 [ Percent of ODCM Limits See Supplemental Information in ODCM Release Limit Section a The average release rate is taken over the entire quarter. It is NOT averaged over the time pericd of the releases.
l l I Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental Operating Report Table 18 Gaseous Effluents - Ground Level Releases ! Batch Mode" Nuclides Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 1995 1995 1995 1995 Fission Gases Ci b b Kr-85 LLD RD b LLD LLD b Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xel35 LLD LLD LLD LLD Xe-135m LLD LLD LLD LLD Xe-138 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A N/A Iodines Ci 1-131 LLD LLD LLD LLD I-133 LLD LLD LLD LLD I-135 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A Particulates and Tritium Ci ; H-3 2.98E-03 6.25E-03 3.52E-03 5.90E-03 Sr-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD LLD LLD Ba-140 LLD LLD LLD LLD Total for Period: 2.98E-03 6.25E-03 3.52E-03 5.90E-03 94
l i Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental Operating Report Table 18 (Continued) Gaseous Efiluents - Ground Level Releases l Continuous Mode l l Nuclides Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr j 1995 1995 1995 1995 Fission Gases Ci Kr-85 LLDb LLDb LLob LLDb Kr-85m LLD LLD LLD LLD l Kr-87 LLD LLD LLD LLD
- Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xe135 LLD LLD LLD LLD Xe-135m LLD LLD LLD LLD l Xe-138 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A i
Iodines Ci l I-131 LLD LLD LLD LLD I l I-133 LLD LLD LLD LLD I-135 LLD LLD LLD LLD l , l Total for Period: N/A N/A N/A N/A l Particulates and l Tritium Ci H-3 3.63E-02 6.18E-02 7.07E-02 8.03 E-02 l l Sr-89 LLD LLD LLD LLD l Sr-90 LLD LLD LLD LLD l Cs-134 LLD LLD .LLD LLD l Cs-137 LLD LLD LLD LLD Ba-140 LLD LLD LLD LLD Total for Period: 3.63E-02 6.18E-02 7.07E-02 8.03E-02 95
Davis-Besse Nuclear Power Station 1995 Annual Radiological Enytronmental Operating Report l Table 18 (Continued) l Gaseous Effluents - Ground Level Release ! Continuous and Batch Modes ! l Ar-41: <2.2E-08 pCi/ml Kr-85: <6.2E-06 pCi/ml Kr-85m: <2.0E-08 pCi/ml Kr-87: <3.4E-08 pCi/ml Kr-88: <4.0E-08 pCi/ml Xe-131m: <9.0E-07 pCi/ml Xe-133: <4.6E-08 pCi/ml Xe-133m: <l .6E-07 pCi/ml Xe-135: <l .9E-08 pCi/ml Xe-135m: <4.0E-07 pCi/ml Xe-138: <2.5E-07 pCi/ml I-131: <l.0E-06 pCi/ml I-133: <2. l E-08 pCi/ml , I-135: <2.lE-08 pCi/ml l Mn-54: <2.0E-08 pCi/ml Fe-59: <4.0E-08 pCi/ml Co-58: <3.0E-08 pCi/ml Co-60: <2.0E-08 pCi/ml Zn-65: <4.0E-08 pCi/ml Mo-99: <2.0E-07 pCi/ml Cs-134: <2. lE-08 pCi/ml Cs-137: <3.0E-08 pCi/ml Ce-141: <3.0E-08 pCi/ml Ce-144: <1.2E-07 pCi/ml Ba-140: <7.0E-08 pCi/ml La-140: <3.0E-08 pCi/ml ! Sr-89: <5.0E-08 pCi/ml Sr-90: <6.0E-09 pCi/ml a Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, AVV Testing, and Auxiliary Boiler Outage Release are listed as batch releases. l b These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed below: c Atmospheric Vent Valve weepage and Steam Packing Exhaust are continuous releases. 96
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 19 Gaseous Effluents - Mixed Mode Releases Batch Mode 1 Nuclides Unit 1st Qtr 1995 2nd Qtr 1995 3rd Qtr 1995 4th Qtr 1995 Fission Gases Ar-41 Ci 1.72E-02 4.78E-02 1.40E-02 2.23E-02 Kr-85 Ci 1.74E-01 1.14E+00 4.63E-01 1.12E+00 j Kr-85m Ci 1.04E-03 3.28E-03 1.09E-03 1.35E-03 j Kr-87 Ci LLob LLDb LLDb LLDb i Kr-88 Ci LLD LLD LLD LLD Xe-131m Ci 2.91E-01 9.96E-01 3.16E-01 2.92E-01 Xe-133 Ci 1.75E+01 8.02E+01 1.69E+01 1.28E+01 Xe-133m Ci 8.34E-02 3.95E-01 7.15E-02 6.59E-02 Xe-135 Ci 2.76E-02 9.8$E-02 3.05E-02 3.28E-02 Xe-135m Ci LLD LLD LLD LLD Xe-138 Ci LLD I,LD LLD LLD Total for Period: 1.81E+01 8.29E+01 1.78E+01 1.43E+01
- Iodines
*Particulates H-3 Ci 3.11E-02 1.10E-01 3.51E-02 4.94E-02 Total for Period: Ci 3.11E-02 1.10E-01 3.51E-02 4.94E-02 l l
- Release ofiodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Station Vent) 97
Divis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 19 (Continued) Gaseous Effluents - Mixed Mode Releases Continuous Mode Nuclide Unit 1st Qtr 1995 2nd Qtr 1995 3rd Qtr 1995 4th Qtr 1995 Mssion Gases , Ar-41 O LLDa LLDa LLoa LLDa Kr-85 0 LLD LLD LLD LLD ! Kr-85m Ci LLD 4.04E-01 LLD LLD Kr-87 Ci LLD LLD LLD LLD Kr-88 Ci LLD LLD LLD LLD i Xe-131m Ci LLD LLD LLD LLD Xe-133 Ci 1.90E+01 5.73E+01 7.24E+01 1.23E+01 Xe-133m Ci LLD LLD LLD LLD Xe-135 Ci LLD 3.48E+00 2.58E+00 5.92E-01 Xe-135m Ci LLD LLD LLD LLD Xe-138 Ci LLD LLD LL_D LLD Total for Peded: 1.90E+01 6.12E+01 7.50E+01 1.29E+01 Iodines I-l31 Ci 5.63E-05 1.61E-04 1.26E-04 4.56E-05 I-133 Ci 1.75E-05 3.57E-05 1.10E-04 2.00E-05 I-135 Ci LLD LLD LLD LLD Total for Peded 7.38E-05 1.96E-04 2.36E-04 6.57E-05 Particulates and Tritium H-3 Ci 7.07E+00 5.24E+00 3.88E+00 4.37E+00 b Sr-89 .c Ci LLD LLD LLD LLD b Sr-90 .c Ci LLD LLD LLD LLD Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci 8.17E-07 3.91E-07 1.26E-06 LLD Ba-140 Ci LLD LLD LLD LLD La-140 Ci LLD LLD LLD LLD Total for Period: 7.07E+00 5.24E+00 3.88E+00 4.37E+00 98
D vis-Besse Nuclear Power Station 1995 Annual Radiological Emiromnental Operating Report Table 19 (Continued) Gaseous Effluents - Mixed-Mode Releases Continuous Mode' Batch Mode
- Ar-41 <2.9E-08 pCi/ml Kr-87 <4.5E-06 pCi/ml Kr-85 <3.3E-06 pCi/ml Kr-88 <6.6E-06 pCi/ml Kr-85m <l.3E-08 pCi/ml Xe-135m <l.4E-05 pCi/ml Kr-87 <6.0E-08 pCi/ml Xe-135 <2.lE-06 pCi/ml l
Kr-88 <6.0E-08 pCi/ml Xe-138 <2.8E-05 Ci/ml Xe-131m <4.4E-07 pCi/ml l Xe-133m <7.2E-08 pCi/ml Xe-135 <l.lE-08 pCi/ml Xe-135m <5.9E-06 pCi/ml Xe-138 <2.0E-05 pCi/ml I-135* <3.9E-10 pCi/ml Mn-54* <2.6E-14 pCi/ml l Fe-59" <3.0E-14 pCi/ml Co-58* <1.6E-14 Ci/ml Co-60 <2.5E-14 pCi/ml Zn-65* <3.5E-14 Ci/ml Mo-99* <l.0E-13 pCi/ml Cs-134* <l.8E-14 pCi/ml Cs-137* <l.6E-14 pCi/ml l Cc-141* <l.3E-14 pCi/ml Ce-144*
<l.2E-13 pCi/ml Ba-140* <4.0E-14 pCi/ml 1 La-140* <l.0E-14 pCi/ml i Sr-89 b,e <9.3E-16 pCi/ml Sr-90 b,c <3.lE-16 pCi/ml a These radionuclides were not identified every quarter in concentrations above the lower limit of detection (I.LD) listed below. The largest LLD value is listed.
b Quarterly composite sample for continuous mode. c Analysis not required for batch release. I 99
La. A Table 20 Liquid Effluents - Summation of All Releases e Type Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total [ 1995 1995 1995 1995 % Error j z - Fission and Activation Products E Total Release (without Tritium. Gases, Alpha) Ci 5.59E-02 5.67E-03 5.21E-03 1.79E-03 2.00E+01 E Average Diluted Concentration during Period" Percent of ODCM Limit pCi/ml 6.34E-09 6.67E-10 5.21E-10 1.90E-10 See Supplement information in ODCM Release Limits Section { [ Percent of10CFR20 Limit % 9.05E-02 4.09E-02 2.57E-02 g, Tritium 8 Total Release Ci 2.56E+01 3.11 E401 7.42E+01 3.66E+01 2.00E+ 01 g 2.90E-06 3.66E-06 7.42E-06 3.88E-06 u Average Diluted Concentration During Period" pCi/ml P-~ ent of10CFR20 Limit % 2.90E-01 3.66E-01 7.42E-01 3.88E-01 i y D 4 cJ M and Entrained Gases $. i a Release Average Diluted Concentration During Period
- pCi/ml Ci 6.50E-05 7.38E-12 3.57E-04 4.20E-11 8.00E-03 8.00E-10 1.50E-03 1.59E-10 2.00E+01
{ p-Percent of 10CFR20 Limit % 3.69E-06 2.10E-05 4.00E-04 7.94E-05 $. ' Gross Alpha E Total Release Volume of Waste Released (prior to dilution) Ci 9.35E-06 LLD LLD 1.09E-03 2.00E+01 ( g Batch liter 3.31E+05 3.97E+05 5.27E+05 3.06E+05 2.00E+01 R Continuous liter 1.23E+08 1.05E+08 9.65E+07 1.74E+08 2.00E+01 [ Volume of Dilution Water g Batch liter 1.04E+08 1.49E+08 1.48E+08 8.10E+07 2.00E+01 g Continuous liter 8.58E+09 8.24E+09 9.75E+09 9.18E+09 2.00E+01 j i Total Volume ofWater Released liter 8.81E+09 8.50E+09 1.00E+10 9.44E+09 y
~8
- 2 a Tritium and alpha are found in both continuous and batch releases. Average diluted concentrations are based on total volume of water l released during the quarter. Fission and Activation products and Dissolved and Entrained Gases are normally only detected in batch releases.
f Divis-Besse Nuclear Power Station 1995 Annual Radi: logical Environmental Operating Report Table 21 Liquid Efiluents - Nuclides Released Batch Releases l Nuclides Unit 1st Qtr 1995 2nd Qtr 1995 3rd Qtr 95 4th Qtr 95 Fission and Activation Products Na-24 Ci LLD' LLD* LLD" 1.25E-06 l Cr-51 Ci 4.32E-04 LLD LLD LLD' Mn-54 Ci 1.09E-04 LLD 1.01E-06 LLD Fe-55 Ci 7.28E-03 4.37E-04 6.85E-04 3.68E-04 Fe-59 Ci LLD LLD LLD LLD Co-57 Ci 2.19E-04 1.34E-05 7.96E-06 9.91E-07 Co-58 Ci 2.86E-02 1.12E-03 4.21E-04 1.43E-04 Co-60 Ci 7.03E-03 4.40E-04 5.70E-04 1.94E-04 ; Zn-65 Ci LLD LLD LLD LLD Sr-89a,b Ci LLD L.LD LLD LLD Sr-90a,b Ci LLD LLD LLD LLD Nb-95 Ci 3.75E-04 LLD LLD 2.36E-06 Zr-95 Ci 3.42E-04 8.65E-06 L.LD LLD i Zr-97 Ci 3.75E-04 3.43E-06 LLD LLD l Mo-99 Ci LLD LLD LLD LLD Tc-99m Ci LLD LLD LLD LLD Ru-103 Ci 4.00E-05 LLD LLD LLD Ag-110m Ci 7.29E-03 3.29E-04 5.77E-04 1.07E-04 Sn-113 Ci 1.72E-04 4.49E-06 LLD LLD l Se-75 Ci 5.34E-06 LLD LLD LLD l Sb-125 Ci 8.46E-04 2.25E-04 6.84E-04 4.10E-04 I-131 Ci 1.42E-05 3.32E-05 2.47E-04 9.42E-05 l I-133 Ci LLD 1.73E-06 3.85E-05 4.46E-05 l I-135 Ci LLD LLD LLD 3.92E-06 ! Te-132 Ci LLD LLD LLD LLD Cs-134 Ci 8.57E-04 1.02E-03 5.68E-04 1.23E-04 Cs-137 Ci 1.76E-03 2.04E-03 1.35E-03 2.95E-04 Ce-144 Ci 2.05E-04 LLD LLD L'LD La-140 Ci LLD LLD LLD LLD 4 Ba-140 Ci LLD LLD LLD LLD Np-239 Ci LLD LLD LLD LLD C-14 Ci NA NA 6.00E-05 NA Total for Period: 5.59E-02 5.67E-03 5.21 E-03 1.79E-03 101
Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental Operating Repon Table 21 (continued) Liquid Effluents - Nuclides Released Batch Releases Nuclides Unit 1st Qtr 1995 2nd Qtr 1995 3rd Qtr 1995 4th Qtr 1995 Tritium Ci 2.55E+01 3.09E+01 7.40E+01 3.58E+01 Dissolved and Entrained Gases 8 Kr-85 Ci LLD* LLD 9.08E-04 LLD' Xe-131m Ci LLD LLD 4.01E-04 LLD Xe-133 Ci 6.50E-05 3.57E-04 6.69E-03 1.49E-03 Xe-135 Ci LLD LLD 2.71 E-06 7.20E-06 Total for Period: 6.50E-05 3.57E-04 8.00E-03 1.50E-03 102
1 i Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 21 (continued) i Liquid Effluents - Nuclides Released ! Continuous Releases i Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr i Nuclides Unit 1995 1995 1995 1995 l Hssion 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 l Zn-65 Ci LLD LLD LLD LLD I 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 L.LD 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 9.26E-06 Ba-140/La-140 Ci LLD LLD LLD LLD-Ce-141 Ci LLD LLQ LLD LLQ Total for Period: N/A N/A N/A 9.26E-06 Tritium Ci i15E-01 2.30E-01 1.58E-01 8.44E-01 Dissolved and Entrained Gases Kr-85 Ci LLD LLD LLD LLD Xe-131m Ci LLD LLD LLD LLD Xe-133 Ci LLD LLD LLD LLD ; Xel33m Ci LLD LLD LLD LLD I Xe-135 Ci LLQ LLQ LLD LLQ Total for Period N/A N/A N/A N/A l 103
Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental Operating Report , l l Table 21 (continued) Liquid Effluents - Nuclides Released" Na-24 <2.0E-08 pCi/ml Sn-113 <2.86-08 pCi/ml l Cr-51 <l.7E-07 pCi/ml Sb-125 <l.7E-08 pCi/ml l Mn-54 <2.lE-08 pCi/ml Te-132 <l.8E-08 pCi/mi b Fe-55 <7.0E-07 pCi/ml Ce-141 <3.0E-08 pCi/ml Fe-59 <4.2E-08 pCi/ml Ce-144 <l.7E-07 pCi/ml Co-57 <l.6E-08 pCi/ml Cs-134 <2.lE-08 pCi/ml Co-58 <l .9E-08 Ci/ml Ce-136 <2.8E-08 Ci/ml Co-60 <2.5E-08 pCi/ml Cs-137 <2.7E-08 pCi/ml Zn-65 <5.2E-08 pCi/ml Ba-140 <7.0E-08 pCi/ml Se-75 <2.4E-08 pCi/ml La-140 <3.0E-08 pCi/ml b l Sr-89 <3.0E-08 pCi/ml Np-239 <l.2E-07 pCi/ml b Sr-90 <8.0E-09 pCi/ml 1-131 <2.5E-08 pCi/ml Zr-95 <4.0E-08 pCi/ml 1-133 <2.1E-08 pCi/ml Zr-97 <2.5E-08 pCi/ml I-135 <l.7E-07 pCi/ml Nb-95 <2.lE-08 pCi/ml Kr-85 <6.2E-06 Ci/ml Mo-99 <l.6E-07 pCi/ml Xe-131m <7.7E-07 pCi/ml Tc-99m <1.8E-08 pCi/ml Xe-133 <4.6E-08 pCi/ml Ru-103 <2.2E-08 pCi/ml Xe-133m <l.6E-07 pCi/ml Ag-110m <2.5E-08 pCi/ml Xe-135 <l.9E-08 pCi/ml 1 i i a These radionuclides were not identified every quarter in concentrations above the lower limit of detection (LLD) listed below. The largest LLD value is used for each radionuclide. LLDs are applicable to both batch and continous modes due to identical sample and analysis methods. b Quarterly composite sample 104
Davis-Besse Nuclear Power Station 1995 Annual Radi: logical Emironmental Operating Report I Table 22 Solid Waste and Irradiated Fuel Shipments l l A. SOLID WASTE SillPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradis'.ed fuel) 6-month Est. Total l
- 1. Type of waste Unit Period Error, % 1 i
- a. Spent resins, filter sludges m 9.16E+00 2.5E+01 evaporator bottoms, etc. Ci 1.38E+01 2.5E+01 l
- b. Dry compressible waste, m' l.23E+00 2.5E+01 l contammated equip., etc. Ci 7.51E-01 2.5E+01 l i
- c. Irradiated components, m control rods, etc. Ci N/A N/A 3
- d. Others: dewatered primary m 1.76E+00 2.5E+01 system cartridge filters Ci 7.62E-01 2.5E+01
- 2. Estimate of major nuclide composition (by type of waste)
Est. Total True Percent (W Error. %
- a. Spent Resins Fe" 8.95E+00 2.50E+01 Co" 7.15E+00 2.50E401 l Co* 7.27E+00 2.50E+01 Ni'3 1.25E+01 2.50E+01 i C" 1.86E+00 2.50E401 Cs* 1.09E+01 2.50E+01 Cs"' 4.87E+01 2.50E+0!
- b. Dry compressible waste, contaminated Fe" 1.45E+01 2.50E+01 equipment, etc. Co* 3.17E+00 2.50E+01 Ni'3 1.61E+00 2.50E+01 Cs* 9.76E+00 2.50E+01 Cs"7 1.91E+01 2.50E+01 Ba/La'* 4.55E+01 2.50E+01 Sn"' 2.85E+00 2.50E+01 Cr" 1.81E+00 2.50E+01 i
- c. Nonc
- d. Cartridge filters Fe" 4.51E+01 2.50E+01 Ni" 1.76E+00 2.50E+01 Ni 3.16E+01 2.50Ei OI Cs* 9.86E+00 2.50E+01 Cs"' l.llE+01 2.50E+01 i
105
}
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 22 (continued) Solid Waste and Irradiated Fuel Shipments
- 3. Solid Waste Disposition Number of Shipments: 2 Mode ofTransportation: Tmck Destination: Barnwell - S.C.
Type of Container (Container Volume): 2 resin / filter HICs (7.18 m') buried Number of Shipments: 5 Mode ofTransportation: Truck Destination: Scientific Ecology Group - oak Ridge, TN Type of Container (Container Volume): a. Metal / Wood boxes of dry contaminated waste and metal (1.24 m') buried (1.02 m') estimated disposal volume after processing
- b. I resin / filter HIC (3.75 m') buried 3
- c. 7 steel resin liners (1.09 m ) estimated disposal volume after processing B. IRRADIATED FUEL SHIPMENTS There were no shipments ofirradiated fuel.
I 1 106
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 23 Doses Due to Gaseous Releases for January through December 1995 Maximum Individual doses due to I-131, H-3 and Particulates with HatT-Lives Greater than 8 Days. Whole Body Dose 3.94E-3 mrem Significant Organ Dose 1.70E-2 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 3.52E-3 mrad Skin Dose 1.34E-2 mrad . Population Doses due to I-131,11-3, and Particulates with IIalf-Lives Greater than 8 Days. TotalIntegrated Population Dose 5.06E-03 person-rem Average Dose to Individual in Population 2.32E-06 mrem Population Dose due to Noble Gas TotalIntegrated Population Dose 8.24E-03 person-rem Average Dose to Individual in Population 3.77E-06 mrem 107
. __ ._ __._ ... . - . _ . . . _ _ - _ _ . - . _ - - . ~ . Davis-Besse Nuclear Power Station 1995 Annual Radiol:gical Emironmental Oper: ting Report Table 24 Doses Due To Liquid Releases for January through December 1995 Maximum Individual Whole Body Dose 1.03E-01 mrem Maximum Individual Significant Organ Dose 1.35E-01 mrem Population Dose TotalIntegrated Population Dose 3.63E+00 person- rem Average Dose to Individual 1.66E-03 mrem 1 108
1 Davis-Besse Nuclear Pour Station 1995 Annual Radi: logical Emironmental Operating Report l Table 25 Annual Dose to the Most Exposed Member of the Public I ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem) (mrem) LIMIT Whole Body Dose Noble Gas 352E-03 Iodine, Tritium,Particulates 3.94E-03 Liquid 1.03E-01 Total Whole Body Dose 1.10E-01 25 4.42E-01 Thyroid Dose Iodine, Tritium,Particulates 1.70E-02 75 2.27E-02 Skin Dose Noble Gas 1.34E-02 25 5.36E-02 Significant Organ Dose (Liver) 1.35E-01 25 5.40E-01 l Meteorological Data Meteorological data on 31/2 inch microdisk for January I through December 31,1995, has been submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, D. C. 20555. . 109 1
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Davis-Besse Nuclear Power Station 1995 Anmial Radiol:gical Emironmental Operating Report Land Use Census Program Design , Each year a Land Use Census is conducted by Davis-Besse in order to update information neces- l sary to estimate radiation dose to the general public and to determine if any modifications are nec- ; essary to the Radiological Environmental Monitoring Program. The Land Use Census is required i by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis-Besse Nuclear l Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use Census Data. The Land Use Census identifies the various pathways by which radioactive material may 1 reach the general population around Davis-Besse. The information gathered during the Land Use Census for dose assessment and input into the REMP ensure these programs are as current as possible. The pathways of concern are listed below:
- Inhalation Pathway - Internal exposure as a result of breathing radionuclides carried in the air.
. Ground Exposure Pathway - External exposure from radionuclides deposited on the ground
. Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.
e Vegetation Pathway - Internal exposure as a result of eating vegetables, fruit, etc. which have a build up of deposited radioactive material or which have absorbed , radionuclides through the soil. l
- Milk Pathway - Internal exposure as a result of drinking milk which may contain radioactive material as a result of a cow or goat grazing on a pasture contaminated by radionuclides.
Methodology The Land Use Census consists of recording and mapping the locations of the closest residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) in each meteorological sector within a five mile radius of Davis-Besse. The surveillance portion of the 1995 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, and vegetable gardens were recorded. The residences, vegetable gardens, and milk animals are used in the dose assessment program. The vegetable gardens must be at least 500 square feet in size, with at least 20% of the vegetables being green leafy plants (such as lettuce, cabbage, and kale) yielding 2 kg/m2, Each residence is tabulated as being an inhalation pathway, as well as ground and plume exposure pathways. Each garden is tabulated as a vegetation pathway. I10
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 mi-nute series of the relevant quadrangles) which has been divided into 16 equal sectors correspond-ing to the 16 cardinal compass points (Figure 31). The closest residence, milk animal, and vege-table garden in each sector are determined by measuring the distance from each to the station vent at Davis-Besse. I 1 Results The following changes in the pathways were recorded in the 1995 census: NNE Sector - A garden at 880 meters was identified, this garden was not present during the 1994 census. SSE Sector - The garden at 2880 meters was replaced by a garden at 2820 meters. S Sector - The garden at 3280 meters was replaced by a garden at 1410 meters. SSW Sector - The garden at 1560 meters was replaced wit h a garden at 1220 meters i e SW Sector - The garden at '1050 meters was replaced with a garden at 960 me-ters.
. WSW Sector - A milk goat is present at 7010 meter which was not identified during the 1994 Census.
- W Sector - The garden at 1660 meters was replaced with a garden at 980 meters NNW Sector - The garden at 1370 meters was replaced with a garden at .1210 meters.
The critical receptor identified by the 1995 Land Use Census is a child for the vegetation pathway at 880 meters in the NNE sector. This is a change from the 1994 Land Use Census. The detailed list in Table 26 was used to update the database of the efIluent dispersion model used in dose calculations. Table 26 is divided by sectors and lists the distance (in meters) of the closest pathway in each meteorological sector. Table 27 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and deposition (D/Q) parameters for each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and in calculat-ing liquid and gaseous efIluent monitoring instrumentation alarm / trip setpoints. Ii1
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Davis-Besse Nuclear Power Stati:n 1995 Annual Radiological Environmental Operating Report Table 26 . Closest Exposure Pathways Present in 1995 Sector Distance from Station (meters) Closest Pathways N 880 Inhalation , Ground Exposure Plume Exposure NNE 870 Inhalation Ground Exposure ; Plume Exposure NNE*
- 880 Vegetation NE 900 Inhalation i Ground Exposure Plume Exposure l ENE, E, ESE, SE N/A Located over Lake Erie l
SSE 2010 Inhalation i Ground Exposure ] Plume Exposure l 3 SSE** 2820 Vegetation S 1070 Inhalation Ground Exposure Plume Exposure S** 1410 Vegetation SSW 980 Inhalation Ground Exposure Plume Exposure SSW" 1220 Vegetation SW*
- 960 Inhalation Ground Exposure l Plume Exposure Vegetation
- Changes since 1994 113
Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental Operating Report Table 26 (continued) Closest Exposure Pathways Present in 1995 Sector Distance from Station (meter 3) Closest Pathways WSW 1620 Inhalation Ground Exposure Plume Exposure WSW 4270 Vegetation WSW *
- 7010 Goat Milk
! W*
- 980 Inhalation Ground Exposure Plume Exposure Vegetation WNW 1730 Inhalation
- Ground Exposure l Plume Exposure WNW 1750 Vegetation i
NW l100 Inhalation Ground Exposure Plume Exposure , NW 2340 Vegetation l NNW *
- 1210 Inhalation l Ground Exposure
! Plume Exposure Vegetation 4
** Changes since 1994 l
l ( 114
Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental 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') (hf*) N 880 Inhalation Child 9.15E-07 8.40E-09 NNE*
- 880 Vegetation Child 1.24E-06 1.44E-08 NE 900 Inhalation Child 1.26E-06 1.58E-08 ENE* --- --- --- --- ---
E* --- --- --- -- --- ESE* --- --- --- --- --- SE* --- --- --- --- --- SSE** 2820 Vegetation Child 7.02E-08 8.36E-10 S** 1410 Vegetation Child 1.27E-07 2.57E-09 SSW*
- 1220 Vegetation Child 1.57E-07 3.46E-09 SW** 960 Vegetation Child 3.18E-07 5.78E-09 WSW 7010 Goat Milk Infant 3.60E-08 2.03E-10 W*
- 980 Vegetation Child 6.21E-07 9.58E-09 WNW 1750 Vegetation Child 1.46E-07 1.72E-09 NW 2340 Vegetation Child 6.84E-08 5.61E-10 NNW*
- 1210 Vegetation 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 1994.
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Davis-Besse Nuclear Power Stati!n 1995 Annual Radiological Environmental Operating Report l 1 Meteorological Monitoring l Introduction The Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory l Commission (NRC) as part of the program for evaluating the effects of routine operation of nu-clear power stations on the surrounding environment. Both NRC regulations and Davis-Besse Technical Specifications provide guidelines for the Meteorological Monitoring Program. These 7,uidelines ensure that Davis-Besse has the proper equipment, in good working order, to support l
'he many programs utilizing meteorological data.
1 i Meteorological observations at Dtvis-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 l local climate. After extensive statistical comparative research the meteorological personnel have foued no impact upon local climate or short term weather patterns. The Meteorological Monitoring Program also provides data that can be used by many other groups and programs: Radiological Environmental Monitoring Program, The Emergency Pre-paredness Program, The Environmental Activities Program, and groups such as Plant Opera-tions, Plant Security, Materials Management, Industrial Safety Program, Toledo and Cleveland Service Dispatch, Legal Affairs, plant personnel and members of the surrounding community. The Radiological Environmental Monitoring Program uses meteorological data to aid in evaluat-ing the radiological impact, if any, of radioactivity released in Station effluents. The meteoro- l logical data is used to evaluate radiological environmental monitoring sites to assure the program is as current as possible. The Emergency Preparedness Program uscs meteorological data to cal-culate emergency dose scenarios for emergency drills and exercises and uses weather data to plan evacuations or station isolation during adverse weather. The Environmental Activities Pro-gram uses meteorological data for chemical spill response activities, marsh management studies, and waste water outfall flow calculations. Plant Operations uses meteorological data for cooling tower efficiency calculations, forebay water level availability and plant work which needs cer-tain environmental conditions to be met before .vork begins, such as humidity percentages and j barometric pressures for sensitive plant components. Plant Security utilizes weather data in their
- routine planning and activities. Materials Management plans certain plant shipments around ad-verse weather conditions to avoid high winds and precipitation which would cause delays in material deliveries and safety concerns. Industrial Safety uses weather and climatological data to advise personnel of unsafe working conditions due to environmental conditions, providing a safer place to work. Service Dispatch in both Toledo and Cleveland utilize Davis-Besse weather i
satellite imagery for planning and scheduling maintenance crews to restore power to customers more efficiently. Legal Affairs uses climatological data for their investigation into adverse weather accidents to the plant and personnel; and company employees and members of the sur-rounding community rely on daily weather forecasts provided by meteorological personnel at Davis-Besse to better plan their daily and routine work activities. i 116
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report On-site Meteorological Monitoring 1
System Description
At Davis-Besse there are two meteorological systems, a primary and a backup. They are both housed in separate environmentally controlled buildings with independent power supplies. Both i primary and backup systems have been analyzed to be " statistically identical" to the other so if one system fails the other can take its place. The instrumentation of each system follows: PRIMARY BACKUP l 100 Meter Wind Speed 100 Meter Wm' d Speed 75 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 100 Meter Wind Direction 75 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 10 Meter Wind Direction ) 100 Meter Delta Temperature 100 Meter Delta Temperature I 75 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Ambient Temperature 10 Meter Dew Point 10 Meter Solar Insolation Precipitation Barometric Pressure MeteorologicalInstnunentation The meteorological system consists of one monitoring site located at an elevation of $77 feet above mean sea level (IGLD 1955)*, a 100 m free-standing tower located about 3,000 feet SSW of the cooling tower, and an auxiliary 10 m foot tower located 100 feet west of the 100 m tower, are used to gather the meteorological data. The 100 m tower has primary and backup instruments for wind speed and wind direction at 100 m and 75 m. The 100 m tower also measures differen-tial temperature (delta Ts): 100-10 m and 75-10 m. The 10 m tower has instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the 10 m tower. According to the Davis-Besse Nuclear Power Station Operating License, Appendix A, Technical Specification, a minimum of six instmments are required to be operable at the two lower levels (75 m and 10 m) to measure temperature, wind speed, and wind direction. During 1995, annual data recovery for all required instruments were 99.3 percent. The annual data recovery for all other measured parameters was 99.2 percent. Minor losses of data occurred during routine in-stnament maintenance, calibration, and data validation. International Great Lakes Data - 1955 117
Davis-Besse Nuclear Power Stati:n 1995 Annual Radiologmal Emironmental Operating Report Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly. Data is reviewed daily to ensure that all communication pathways, data availtbility and data reliability are working as required. Tower instrumentation maintenance and semiannual calibrations are per-formed by in-house facilities and sn outside consulting firm. These instruments are wind tunnel tested to assure compliance with applicable regulations and plant specifications. 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 11/84 and VAX computer system. This is a i dedicated line. If a failure occurs at any point between the primary meteorological system and the l control room the second data logger in the primary shelter can be utilized by the control room. l . Each datalogger has its own dedicated communication link with battery backup. The backup meteorological system 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 light-ning and surge protection, plus four independent communication lines and datalogger battery backup. l The data from the primary and backup meteorological systems are stored in a 30-day circular l
- storage module with permanent storage held by the Digital VAX computer. Data goes back to i 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 gener-ated 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 sec-tor. This data is used by the NRC to better understand local wind patterns as they relate to de- i fined past climatological wind patterns as reported in Davis-Besse's " Updated Safety Analysis Re-port". l I i 1 118 L _ _ - . - . _
l l l Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmentel Operating Report Meteorological Data Summaries This section presents summaries of the meteorological data collected from the on-site monitoring program at Davis-Besse during 1995. Tables 28 through 30, discussed in this section, can be found on pages 122 through 141. Wind Speed and Wind Direction The maximum wind speeds for 1995 were 46.17 mph for the 100m level on October 5, 42.52 mph for the 75m level on November 27, and 33.90 mph for the 10m level on October 5. 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 darker bar repre sents the percent of time the wind blew from that direction. The hatched bar represents the aver-age 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 middle of the wind sector graphic. l Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 1995 are given in Table 29. , These data are measured at the 10m level; with differential temperatures taken from 100m and l 75m levels. The yearly average ambient temperature for 1995 was 49.71 F. The maximum tem- r l perature was 96.77 F on July 14 with the minimum temperature of -0.14 F on February 12. Yearly average differential temperatures were -0.25 F(100m), and -0.16 F(75m). Maximum dif- ! ferential temperatures for 100m and 75m levels were 8.00 F on March 7 (100m), and 7.99 F on October 17 (75m). Minimum differential temperatures for 100m and 75m levels were -3.90 F on August 17 (100m) and -3.44 F on August 17 (75m). Differential temperatures are a measurement l of atmospheric stability and used to calculate radioactive plume dispersions based on the Gaussian l Plume Models of continuous effluent releases. Dew Point Temperatures and Relative Humidity Monthly average and extreme dew point and humidity temperatures for 1995 are provided in Ta-ble 29. These data are measured at the 10 meter level. The average dew point temperature was 41.89*F with a maximum dew point temperature of 80.70 F on July 15. Please note that dew point temperatures above 75*F are highly suspect and are possibly due to calm winds and high ! solar heating allowing the aspirated dew point processor to retain heat. The minimum dew point ; i (dew point under 32*F is frost point) temperature was -9.25 F on February 9. Average relative humidity is 76.14 for the year. The maximum relative humidity was 100.00 percent on ! December 29. The minimum relative humidity was 0.24 percent on April 11. It is possible to have relative humidity above 100 percent which is known as super saturation. Conditions for su-per saturation have been met a few times at Davis-Besse due to its close proximity to Lake Erie j and the evaporative pool of moisture available by such a large body of water. l i i I k { l19
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Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report i I l Precipitation l Monthly totals and extremes of precipitation at Davis-Besse for 1995 are given in Table 29. Total l precipitation for the year was 24.64 inches. The maximum monthly precipitation total was 3.42 i inches in May. The minimum was 0.66 inches recorded in February. It is likely that precipitation l 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 l Lake Breeze is monitored at Davis-Besse because ofits potential to cause major atmospheric / l 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 i l therefore reaches higher temperatures than the water. The warmer air above the land rises faster
- because it is less dense than the cooler air over the lake. This leads to rising air currents over the land with descending denser air over the lake. This starts a wind circulation which draws air from the water to the land during the daytime, creating a " lake breeze" effect. This event could be problematic if a release were to occur because diffusion would be slow thus creating an adverse atmosphere to the surrounding site.
1 Lake and forebay levels are monitored at Davis-Besse to observe, evaluate, predict and dissemi-nate high or low lake level infonnation. 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 shallowest ! 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 emergency l transportation and evacuation pathways. l i s 120
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Repn Satellite Imagery A state-of-the-art satellite weather system was installed in 1994. This system consists of a remote one-meter satellite dish, a host computer receiver which has four remote user connections, with a real-time weather access. The weather satellite is 22,000 miles out in space, with a geosyncro-nous orbit situated over North America. Data from the satellite is fed to WSI corporation for l base map interpretation and then sent to a communication satellite which then sends the com-pleted imagery to the receiving satellite dish at Toledo Edison. Data from this site can then be sent to all four remote users; two users in the Toledo area and two in Cleveland. This advanced weather station allows meteorological staff to forecast adverse weather conditions long before they arrive. This enables planners in Service Dispatch to keep needed crews available if adverse weather conditions dictate; or to send home unneeded crews if a projected storm tracks out of the customer service area. Load Dispatch utilizes the weather system to get an idea where the peak and low electricity loads will be either during very hot days or very cold ones. High winds, solar flares, freeze lines, wind chill, min-max temperatures and graphic imagery can all be obtained digitally through this weather satellite system, allowing better planning by staff and better service i to customers; saving time and money as well. I f A 6 ,
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Table 28 Summary of Meteorological Data Recovery For The Davis-Besse Nuclear Power Station E. January 1,1995 through December 31,1995 j' N Z JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1995 5. 100M Wind Speed 100 98.36 95.03 94.72 100 98.75 98.92 99.19 100 100 100 98.79 98.65 $ 100m Wind Direction 100 98.36 95.03 99.72 100 98.75 98.92 87.10 100 100 100 98.79 98.04 2' 75m Wind Speed 100 98.36 95.03 97.22 100 98.75 98.92 99.19 100 100 100 98.79 98.86 $ 75m Wind Direction 100 98.36 95.03 99.72 100 98.61 98.92 99.19 100 100 100 98.79 99.05 y 10m Wm' d Speed 100 100 100 99.72 100 98.75 98.92 99.29 100 100 100 98.79 99.61 [ 10m Wind Direction 100 100 100 99.72 100 95.83 98.92 99.19 100 100 100 98.79 98.37 - 10m Ambient AirTemp 100 100 100 99.72 100 98.75 98.92 99.19 100 100 100 99.46 99.67 $ 10m Dew Point Temp 100 100 100 97.78 99.46 96.39 98.92 96.77 100 100 97.08 99.46 98.82 g g Delta T (100m-10m) 100 100 100 99.72 100 98.75 98.92 99.19 100 100 100 99.46 99.67 a " E Delta T (75m-10m) 100 100 100 99.72 100 98.75 98.92 99.19 100 100 100 99.46 99.67 Joint 100m winds and b Delta T (100m-10m) 100 98.36 95.03 94.72 100 98.75 98.92 87.10 100 100 100 98.79 97.63 k' Joint 75m winds and I Delta T (100m-10m) 100 98.36 95.03 97.22 100 98.61 98.92 99.19 100 100 100 98.79 98.85 @ Joint 10m winds and 5. Delta T (75m-10) 100 100 100 99.72 100 95.83 98.92 99.19 100 100 100 98.79 99.37 5 R a E.
*all data for individual months expressed as percent of time instrument was operable during the month, divided by the maximum number of hours in that month that the instrument could be operable. Values for annual data recoveries equals {
the percent of time instrument was operable during the year, divided by the number of hours in tia year that the @, instrument was operable. 5 i2
Table 29 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station [ January 1,1995 through December 31,1995 s' 3 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1995 100M WIND $ Max Speed (mph) 36.06 37.12 39.20 42.41 43.52 27.63 27.67 25.47 27.22 46.17 44.68 38.53 46.17 2' Date ofMax Speed 31 04 20 27 14 07 06 31 27 05 27 19 10/05 $ Min Speed (mph) 1.08 4.34 0.74 1.52 1.80 1.87 1.57 1.13 1.16 2.47 0.38 1.32 0.38 y Date ofMin Speed 10 23 02 14 05 13 08 27 04 31 29 31 11/29 [ Ave Wind Speed 18.10 18.26 14.90 17.59 16.12 11.84 13.99 11.27 13.32 19.19 18.67 18.17 15.94 - 75M WIND $ Max Speed (mph) 33.43 35.34 36.08 40.82 41.52 26.74 33.32 23.81 25.01 41.76 42.52 35.03 42.52 g g Date ofMax Speed 31 04 20 27 14 07 13 31 22 05 27 09 11/27 g " Min Speed (mph) 1.22 3.06 0.74 2.77 1.81 1.66 1.60 1.34 1.54 2.54 0.71 1.77 0.71 g Date oFW Speed 10 23 03 01 05 12 08 29 02 31 29 31 11/29 e.. be Wind Speed 16.81 16.89 13.79 16.69 14.80 10.89 12.73 10.46 12.18 17.30 17.17 16.52 14.68 j 10M WIND g-Max Speed (mph) 25.85 26.94 23.68 31.42 31.88 21.02 28.14 17.46 20.99 33.90 33.72 32.06 33.90 y Date ofMax Speed 02 11 20 27 14 07 13 31 07 05 27 19 10/05 s. Min Speed (mph) 1.37 1.40 0.70 1.74 1.67 0.89 1.15 1.01 1.00 1.16 0.60 1.89 0.60 $ Date ofMin Speed 27 23 02 01 24 02 30 02 27 02 29 02 11/29 l Ave Wind Speed 11.71 11.57 8.98 12.03 10.02 7.08 7.54 6.59 7.50 9.94 10.87 11.36 9.59 E. O 1
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i Table 29 (continued) Summary of Meteorological Data Measured at , Davis-Besse Nuclear Power Station j. January 1,1995 through December 31,1995 j' 1 1 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1995 E. 10M AMBIENT TEMP O Max (F) 64.34 46.82 68.39 75.43 80.10 91.93 96.77 90.80 85.33 80.08 69.18 54.51 %.77 Date ofMax 14 23 13 18 23 19 14 13 06 13 02 03 07/14 {4 Min (F) 2.11 -0.14 16.74 17.79 44.67 52.41 54.89 61.15 37.56 35.30 21.61 1.92 -0.14 I? Date ofMin 05 12 02 05 06 08 08 23 23 17 05 09 02/12 [ Ave Temp 27.43 25.64 38.72 44.29 58.83 70.02 74.04 75.67 62.27 55.02 36.37 26.89 49.71 - 10M DEW POINT g
- TEMP E E Mean (F) 24.10 20.24 30.81 35.23 48.35 61.74 64.59 67.52 52.55 44.52 30.41 22.23 41.89 Max (F) 57.33 42.93 57.44 65.08 68.10 73.50 80.70 80.10 69.19 64.21 61.94 50.69 80.70 g.
Date ofMax 14 15 07 18 28 19 15 13 12 06 02 03 07/15 g Min (F) 0.54 -9.25 9.73 8.33 29.69 38.97 26.62 2.85 28.20 22.67 15.70 -1.42 -9.25 [ Date ofMin 05 05 02 04 21 13 04 13 22 04 15 09 02/05 gs k PRECIPITATION ~ g Total (inches) 2.14 0.66 1.32 2.64 3.42 1.48 3.21 2.20 0.82 3.66 2.40 0.69 24.64 g 2.36 E Max. in One Day .92 .40 1.01 .70 1.37 .74 .87 .83 .44 2.36 1.00 .38 g Date 19 27 7 8 29 26 15 17 20 5 10 13 10/5 'g x
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*** * *** DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT *** * **25-JAN-96 TIME OF DAY: 13:29:47 5.
PROGRAM:. JFD VERSION: F77-1.0 EE!
******** DAVJS-BESSE 75-10 DT, NO BACKUP ******** SITE IDENTIFIER: 95 E DATA PERIOD EXAMINED: 1/ 1/ 95 - 12/ 31/ 95 % N
*** ANNUAL *** Q g U g STABILITY CLASS A l
STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET % T WIND MEASURED AT: 35.0 FEET *1 WIND THRESHOLD AT: 1.00 MPH O h JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET M g 1 SPEED C m W NNW TOTAL (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW WNW NW CALM 0 O 3 1 01- 3.49 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 M 3.50- 7.49 7.50-12.49 2 1 2 0 0 0 0 0 2 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 2 4 13 4 1 0 14 18 y g 12." 18.49 0 0 0 0 0 0 0 0 0 0 0 0 0 2 2 0 4 to q
- 18. 44.49 0 0 0 0 0 0 0 0 0 0 0 0 0 3 4 0 7 Qp
>a. 49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >- g=
w C* 4 TOTAL 3 2 0 0 2 0 0 2 0 0 0 0 0 11 23 1 44 C O
- w. W STABILITY CLASS B O
U o STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET y It THRE HO A 0 M ' JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN MOURS AT 35.00 FEET M SPEED r+ W [ (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL T CALM
- 0 0 1.01- 3.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,
3.50- 7.49 6 3 0 0 0 0 0 0 0 0 0 0 2 2 3 0 16 g 7.50-12.49 8 1 0 0 0 1 0 0 0 4 0 1 0 4 6 8 33 e 12.50-18.49 0 0 1 2 0 0 0 0 0 0 0 0 0 1 2 3 2 4 2 7 2 2 0 20 11 C 8".- 18.50-24.49 0 0 0 3 0 0 0 0 0 0 0
>24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 w
TOTAL 14 4 1 5 0 1 0 0 0 4 0 4 7 12 18 10 80 . h I
I i
*** * *** D m
DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT *** *
**25-JAN-96 TIME OF DAY: 13:29:47
$. t PROGRAM: JFD VERSION: F77-1.0 ? [
135 ,
* * * * * * *
- DAVIS-BESSE 7 5-10 DT. NO BACKUP ******** SITE IDENTIFIER: 95 DATA PERIOD EXAMINED: 1/ 1/ 95 - 12/ 31/ 95 y
..* ANNUAL *** 2 O.
g STABILITY BASED ON: DELTA T BEWEEN 250.0 AND 35.0 FEET STABILITY CLASS C y { ; WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH
*t O [ !
O i JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET C SPEED G m [ (MPH) N NNE NE ENE E ESE SE SSE g S SSW SW WSW W WNW NW NNW 1VTAL U c. CALM 0 M o H g s 1.01- 3.49 0 0 0 t D b 0 0 0 0 0 0 0 0 0 0 0 1 0 3.50- 7.49 6 7 1 0 0 0 0 0 1 5 7.50-12.49 9 3 9 8 10 1 1 0 1 5 0 1 3 1 1 10 40 G 8'"' 3 9 14 4 4 6 20 102 12.50-18.49 3 3 6 1 1 0 0 0 0 1 3 6 11 7 16 3 61 [* g ;> 18.50-24.49 0 0 0 1 0 0 0 0 0 0 3 10 3 4 5 0 26 qO g
>24.49 0 0 0 0 0 0 0 0 0 0 0 2 3 0 0
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W 0 5 7A Oo TOTAL 18 13 15 10 11 1 1 1 6 9 15 33 24 16 29 33 235 C p, O ! [ g C. . STABILITY BASED ON: DELTA T STABILITY CLASS BEWEEN 250.0 AND 35.0 FEET D Q S l WIND MEASURED AT: 35.0 FERT 7C M WIND THRESHOLD AT: 1.00 MPR MQ i-CL, l JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E h U g l ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL d-CALN 1.01- 3.49 8 3 5 15 14 9 10 5 18 6 2 5 8 12 4 4 3 3 127 3.50- 7.49 7.50-12.49 44 73 54 100 155 72 117 114 92 54 62 51 94 94 52 31 20 30 30 1011 N" 2 259 206 64 49 40 57 149 195 220 118 71 12.50-18.49 39 59 104 66 63 1 3 10 16 82 162 286 120 61 92 76 68 56 1916 1204 Q k 18.50-24.49 1 9 43 34 4 0 0 2 4 8 84 118 16 22 30 20 395 '
>24.49 0 7 16 2 0 0 0 0 0 0 21 22 1 7 D3 00 3 1 80 m
TOTAL 165 232 395 493 401 166 116 119 146 339 564 710 290 185 234 178 4735 h oo i N a > t k s
.m.__= --_-______________-_1._ _ - . _ _ _ . - - . _ _ _ . _ _ _ _ - _ _ _ _ - -_. _.____ - _- ._m__ _ - _ _ . _ _ _ _ _ . . __-__m_-_ --.___m__.
I. U DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT *** *
" 2 5 -J AN- 9 6 $
TIME OF DAY: 13:29:47 ;;;- PROGRAM: JFD VERSION: F77-1.0 g n
******** DAVIS-BESSE 75-10 DT, NO BACKUP ******** SITE IDENTIFIER: 95
- DATA PERIOD EXAMINED: 1/ 1/ 95 - 12/ 31/ 95 % 5
*** ANNUAL *** O Z C
g STABILITY CLASS E k STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET q WIND MEASURED AT: WIND THRESHOLD AT: 35.0 FEET 1.00 MPH g h O JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN NOURS AT 35.00 FEET g SPEED g M (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL g O Wd o h um 2 qq D 1.01- 3.49 3 6 4 6 16 20 23 31 48 16 9 13 12 7 6 6 226 Q* 3.50- 7.49 7.50-12.49 20 6 24 15 20 17 49 40 89 41 112 25 90 24 98 49 165 54 186 130 77 150 63 139 59 87 27 44 18 38 11 34 1108 893 Cg La 12.50-18.49 2 2 1 15 5 2 2 4 12 53 46 37 28 20 26 3 258 MW > 18.50-24.49 1 0 0 8 0 0 0 0 2- 6 21 7 3 3 0 0 51 $Q
>24.49 0 1 2 0 1 0 0 0 0 0 1 3 1 2 0 0 11 yn f TOTAL 32 48 44 118 152 159 139 182 281 391 304 190 103 88 54 2549 262
- h. O O y O e 5.
STABILITY CLASS F U y* j 6 STABILITY BASED ON: DELTA T BJTWEEN 250.0 AND 35.0 FEET yg o WIND MEASURED AT: 35.0 FEET y g . WIND THRESMOLD AT: 1.00 MPH g g JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET Mv SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL M h CALM 0 O 1.01- 3.49 1 0 2 2 1 5 19 24 49 34 18 25 14 1 3 0 198 n 3.50- 7.49 1 3 6 8 13 19 28 44 81 134 85 28 40 6 1 0 497 M , 7.50-12.49 12.50-18.49 0 0 1 0 3 0 8 0 6 0 4 0 5 0 4 0 1 0 17 1 6 0 12 1 6 0 8 0 0 0 4 1 85 3 O g 18.50-24.49
>24.49 0
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 { m
,9 M
M E TOTAL 2 4 11 18 20 28 52 72 131 186 109 66 60 15 4 5 783 g. oo M o
**25-JAN-96 U
*** * *** DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT TIME OF DAY: 13:29:47 $
E* PROGRAM: JFD VERSION: F77-1.0 b5 SITE IDENTIFIER: 95 g
******** DAVIS-BESSE 75-10 UT. NO BACKUP ******** y g DATA PERIOD EXAMINED: 1/ 1/ 95 - 12/ 31/ 95
*** ANNUAL ***
O z h e+ N E' STABILITY CLASS C BE7 WEEN 250.0 AND 35.0 FEET y 4 STABILITY BASED ON: DELTA T g 'tf C WIND MEASURED AT: 35.0 TEET g WIND THRESMOLD AT: 1.00 MPH L.2 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRFCTION IN HOURS AT 35.00 FEET C M SPEED S SSW SW WSW W WNW NW NNW TOTAL O N NNE NE ENE E ESE SE SSE (MPH) ' 1 O CALM 18 15 8 8 0 6 4 95 M D3 - 1.01- 3.49 3.50- 7.49 3 1 1 1 1 2 5 9 1 12 1 9 3 10 11 11 1 10 36 0 44 1 12 0 6 0 4 0 1 0 0 0 0 0 158 25 m[ v *g 0 0 0 4 3 12 4 0 0 ta c W 7.50-12.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.50-18.49 0 0 0 0 0 0 0 18.50-24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 p. O 0 0 0 0 0 0 g* m A >24.49 0 a O 4 2 3 18 16 22 17 23 46 63 27 14 12 1 6 4 279 C O e+ 0 go,, TOTAL g c . . STABILITY CLASS ALL O STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET C' Q C 0 b WIND MEASURED AT: 35.0 FEET MQ WIND THRESHOLD AT: 1.00 MPH Q. U k t JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED SSW SW WSW W WNW NW NNW TOTAL h h (MPH) N NNE NE PNE E ESE SE SSE S 5 o' w*
- h. ,
CALM 32 35 55 72 125 74 50 58 38 12 19 13 648 O 1 1.01- 3.49 15 10 12 28 268 150 139 59 57 52 2844 100 183 230 232 182 217 338 463 M"+ i 3.50- 7.49 80 94 113 304 360 386 215 135 155 134 3072 107 83 94 7.50-12.49 12.50-18.49 97 44 120 64 184 112 319 84 266 69 3 5 14 28 137 211 331 162 94 127 41 65 20 1550 490 g E 0 0 2 6 14 108 137 24 34 18.50-24.49 2 9 43 46 4 27 5 9 3 1 96 p3 2 1 0 0 0 0 0 22 m
>24.49 0 8 18 402 285 8705 M .
TOTAL 238 305 469 662 602 377 325 399 610 992 1019 1089 583 343 { a
- =
k i
i ( O .
% l E
* **25-JAN-96 TIME OF DAY: 13:29:47 h
*** * *** DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT *** g PROGRAM: JFD VERSION: F77-1.0 SITE IDENTIFIER: 95 -. [
* * * * * * *
- DAVIS-BESSE 75-10 DT, NO BACKUP ******** m 2 ,
DATA PERIOD EXAMINED: 1/ 1/ 95 - 12/ 31/ 95 ... " D
... ANN m Nj 4 STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET f
>1 WIND MEASURED AT: 35.0 FEET O WIND THRESHOLD AT: 1.00 MPH .D k C ,
TOTAL NUMBER OF OBSERVATIONS: 8760 O TOTAL NUMBER OF VALID OBSERVATIONS: 8705 55 C O k". TOTAL NUMBER OF MISSING OBSERVATIONS: 99.4 % g i M PERCENT DATA RECOVERY FOR THIS PERIOD: MEAN WIND SPEED FOR THIS PERIOD: 9.6 MPH TOTAL NUMBER OF OBSERVATIONS WITH BACKUP DATA: 0 O O $ M i
?
m"* ? PERCENTAGE OCCURRENCE OF STABILITY CLASSES F
~ A B C D 29.28 E
8.99 G 3.21
.O r 0.92 2.70 54.39 o' m ,
b 0.51 C O E f C. OC Q DISTRIBUTION OF WIND DIRECTIONS VS STABILITY SW WSW W WNW NW NNW CALM g . . E ESE SE SSE SSW - NE ENE N NNE C' sC 0 MO ' A 3 2 0 0 2 0 0 2 0 0 0 4 0 0 0 4 0 7 11 12 23 18 10 1 0 M v. Q k 0 0 0 B 14 4 15 1 5 10 0 11 1 1 1 1 6 9 15 33 710 24 290 16 185 29 234 178 33 2 $ h C 18 13 493 401 166 116 119 146 339 564 262 190 103 88 54 2 ga D 165 232 395 139 182 281 391 304 5 0 >== 48 44 118 152 159 109 66 60 15 4 E 32 20 28 52 72 131 186 1 6 4 1 .9 18 12 F G 2 4 4 2 11 3 18 16 22 17 23 610 46 992 63 27 1019 14 1089 583 343 402 285 5 q" , 662 602 377 325 399 TOTAL 238 305 469 b b i m M & ? E
=
i N o t
D:vis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report l l Land and Wetlands Management Navarre Marsh The Naverre 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 Wildlife 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 l responsible for the maintenance and repair of the dikes and controlling the water levels in each l 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 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 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 vegetation l and animal species. Manipulating water levels is one of the most important marsh management 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 habi-tat, to gain knowledge through ongoing research, and to help educate the public about the impor-tance of native wetlands. With its location along a major migratory flyway, the Navarre Marsh serves as a refuge for a va-riety of birds in both the spring and the fall, where they rest and fmd nourishment before continu-ing on theirjourney. The Black Swamp Bird Observatory captures, examines, bands, catalogues, and releases songbirds in the marsh during these periods. Navarre is also home te 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 l turtles. For the first time in recent history, a pair of mature American Bald Eagles chose the Navarre Marsh as their nesting site in late 1994, and fledged a healthy eaglet in July,1995. The young eagle was one of a record 38 eaglets fledged in Ohio in 1995. , Goose banding took place in June, and was conducted in cooperation with the ODNR and the i U.S. Fish and Wildlife Service. Over 100 Canada Geese were banded in about an hour. l 142
]
Davis-Besse Nuclear Power Stati:n 1995 Annual Radiological Environmental Operating Report Davis-Besse opened the Navarre Marsh for public tour for the first time ever in observance ofIn-ternational Migratory Bird Day. About 350 members of the public took pan in shuttle van tours, which included a bluebird trail demonstration, a banded bird demonstration given by the Black Swamp Bird Obsevatory, and a look at Davis-Besse's American Bald Eagle pair. Back to the Wild, Inc., a licensed animal rehabilitator, joined the activities and brought several live animals as part of the program. Ohio's first Federal Junior Duck Stamp Art Contest was hosted by Davis-Besse. Young Ohio artists in grades K-12 submitted nearly 600 entries in four separate age brackets. The Junior Duck Stamp Art Contest was designed to teach conservation through the arts and give students a chance to experience the beauty and diversity of wildlife. A total of 101 ribbons were awarded to young Ohio artists, with the state Best of Show entry being sent to Washington, D. C. to compete with all state winners for best in the nation, which will be featured on the 1995-1996 Junior Duck Stamp. Davis-Besse also hosted a Volunteer Eagle Watchers Workshop and a Waterfowl Identification Seminar, both of which were sponsored by the Ohio Division of Wildlife. l Land Management - Habitat Improvement Prairie Planting i 1 In a cooperative effort with the local chapter of Pheasants Forever, a 10 acre section of land outside of the marsh was carefully prepared and planted with four species of prairie grass and seven species of wildflowers. The area had in the past, consisted of weeds and nuisance grasses which provided little or no wildlife habitat, and had to be mowed about twice a year. The cost of the prairie establishment was minimal, with Pheasants Forever providing the prai-rie grass seed and the use of a no till grain drill, and future costs of repeated turf grass and weed mowing will be eliminated. Aesthetically, the prairie will pay for itself as well. Not only are prairie grasses and forbs bet-ter to look at, they provide better habitat, improve water quality, and prevent soil erosion. Employees and neighboring landowners will be treated to ever-changing colors and shapes as the prairie evolves throughout the growing season. Other areas of Davis-Besse are being considered for prairie establishment in the coming years. Metzger Marsh Wetland Restoration Project Davis-Besse pledged pannership with Ducks Unlimited, the Ohio Division of Wildlife, and the Ottawa National Wildlife Refuge in the restoration of 908 acres of vital wetlands in the Metzger Marsh by donating electrical service to be supplied to the marsh pump, boring costs, overhead costs and the cost of a transformer for the pump that will be used to drain the marsh. 143
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report i 1 4 The $4.2 million project is the largest ever undertaken by Ducks Unlimited, and includes a i 7,700 feet oflakefront dike which allows for precise water level control which is essential for
- good marsh management.
l The restoration of former wetlands and the preservation of existing wetlands is good envi-ronmental stewardship, since Ohio wetlands have been reduced by over 90% since the 1800's. 1 5 , 1 l ) e i I 4 i ) i 1 i l I 144 i
Davis-Besse Nuclear Powcr Station 1995 Annual Radiolsgical Envimnmental Operating Report l Water Treatment l Water Treatment Plant Operation Description l l The Davis-Besse Nuclear Power Station uses Lake Erie as a water source for its water treatment i plant. The lake water is treated with chlorine, lime, and other chemicals to make the water clean I and safe for consumption. This water may also be further treated to produce high purity water which is used by many of the Station's cooling systems. Operation of the water treatment plant is monitored by the Ohio Environmental Protection Agency (OEPA) and the Ohio Department of Health. The operation of the facility is reviewed by a Public Water Supply certified operator. Activities at the water treatment plant are conducted in compliance with the Safe Drinking Water Act and the regulations for public water supply as set forth by the OEPA. Monthly operational reports, required by the OEPA, are completed by Toledo Edison personnel and submitted to the agency. These reports contain sample dates and analytical results, which are compared to standards established by the OEPA. Operational data are also reviewed for compli-ance with the limits set by the OEPA. As a further means of monitoring water quality, drinking water is sampled annually for pesticides, herbicides, heavy metals (such as chromium, arsenic, mercury, lead) and quarterly certain organic chernicals. The health and safety of the water treat-ment plant operators and other site personnelis ensured through weekly housekeeping inspections of the facility. 4 Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which remove debris and large particles. The water is then pumped to chlorine detention tanks. Next the water passes through one of two clarifiers. Davis-Besse uses upflow clarifiers, or precipita-tors, to remove sediment, organic debris, and dissolved agents from the raw water prior to filtra-tion. Clarifiers combine the conventional treatment steps of coagulation, flocculation,.and sedi-mentation into a single unit. Coagulation is the process by which a chemical, 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 conglomerate particles to mass together further. Finally, during sedimentation, large conglomerate particles settle to the bottom of the clarifier. These processes normally require large separate tanks. However, the use of clarifiers saves both space and the manpower needed to operate the treatment plant. l l 145
Davis-Besse Nuclear Power Station 1995 Annual Radi11ogical Emironmental Operating Report 5"lE" STR CTURE l
~ ~ FLOW ~
l SP WATER CHLORINE ##* 7 TREATMEin DETENTION CLA M ERS - - FEED PUMPS TANKS - CLEARWELL RTERS l TO DOMESTIC TO FIRE (DRWKitG) WATER WATER SWTEM SYSTEM TO DEMWERAttZED WATER SYSTEM Figure 38: At Davis-Besse, raw water is drawn into the water treatment plant and processed to make drinking water and water for plant systems. After the clarifier, the water goes through a flow-splitting box which equally divides the water flow to the Automatic Valveless Gravity Filters (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 and odor and im-prem the tasa of the water. After Sitration, the watt.: goes to a 32,000 gallon clearwell. The clearwell acts as a reservoir from o hich water can be drawn as needed for all systems, including fire water, demineralized water, and also drinking water. Zebra Mussel Control Introduction The plant receives all ofits water from an ir.take system from Lake Erie. Zebra mussels can se-verely impact the availability ofwater for plant processes. Dreissenapolymorpha, commonly known as the zebra mussel, is a native European bivalve that was accidentally introduced into North American waters in 1988 and was discovered in Lake Erie in 1989. Zebra mussels are prolific breeders which rapidly colonize an area by secreting byssal threads which enable them to attach to solid surfaces and to each other. Because of their ability to attach in this manner, they may form layers several inches deep. This poses a problem to facilities that rely on water intakes l from Lake Erie because mussels may attach to the intake structures and restrict water flow. Ze-bra 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 canal). 146
Davis-Besse Nuclear Power Stahon 1995 Annual Radmiogical Environmental Operating Report Monitoring The Zebra Mussel Monitoring Program has been in place since April,1990. The program in-volves the collection of several types of samples which are observed for the presence of adult ze-bra mussels or the free-swimming larval forms, veligers. The frequency of sampling is determined by lake water temperature. Samples are taken when the lake temperature is above 12 C since this is the temperature above which spawning may occur. At temperatures above 18 C, spawning conditions are most favorable, and more frequent samples are taken. Weather data and water temperatures are also recorded to determine their effects on veliger/ mussel population. i I Water samples are collected in the station's intake forebay. These samples are collected using a plankton net sampler: a net support system with a straining bucket used for plankton-size j (microscopic) organisms including veligers. One milliliter from each sample is observed under a microscope to check for the presence of veligers to determine the average number of veligers per liter. l l The mussel population appears to be leveling off or declining. This is likely due to the mcreasmg 4 clarity ofLake Erie. As the food source for the zebra mussels decline, mussel population dechnes ; correspondingly. I Wastewater Treatment Plant Operation The wastewater treatment plant (WWTP) operation is supervised by a state Certified Wastewater Operator. Wastewater generated by site personnel is treated at an onsite extended aeration pack- ! age treatment facility designed to accommodate a flow of 38,000 gallons per day (gpd). In the l treatment process, wastewater from the various collection points around the site, called lift sta-tions, enters the facility and is distributed to the surge tanks of the treatment plants. The wastewater is then pumped into the aeration tanks. Here, organic materials are digested by , microorganisms 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-l vated sludge. The treated wastewater settles in a clarifier, and the clear liquid passes over a weir, l leaving the plant by an eifluent 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.
Sununary of 1995 Wastewater Treatment Plant Operations Two comminutors were purchased and installed in March 1995. One comminutor was placed at the inlet to each wastewater treatment plant to grind / shred incoming materials, which prevents ! clogging of the surge tank pumps. This has greatly improved the facility's operability and re-j duced maintenance costs. l 147
Davis-Besse Nuclear Power Station 1995 Annual Radiological Emironmental Operating Report National Pollutant Discharge Elimination System (NPDES) Reporting The OEPA has established limits on the amount of pollutants that Davis-Besse may discharge to I the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 2IB00011
- ED. Parameters such as chlorine, sus-I pended solids and pH are monitored under the NPDES permit. Toledo Edison personnel prepare the NPDES Reports and submit them to the OEPA by the fifteenth day of each month.
1 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 sampling points follow: Outfall 001 Collection Box: At a point representative of discharge to Lake Erie. Source of Wastes: Low volume wastes (Outfalls 601 and 602), circulation system blowdown and service water. i Outfall 002 Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water mnoff, circulating pump house sumps. Outfall 003 1 Screenwash Catch Basin: Outfall to Navarre Marsh. Source Of Wastes: Wash debris from water intake screens. i i 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. 148
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Davis-Besse Nuclear Power Station 1995 Annual Radi: logical Emironmental Operating Report 1995 NPDES Summary 1 During 1995, there was one noncompliance event on March 16 and 17, when the pH at Outfall 001 reached 9.07 standard units (S.U.). This resulted due to high Lake Erie intake water pH values at or near the discharge limit of 9.00 S.U. l I 149
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Chemical Waste Management Introduction 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 ofin accordance with all applicable state and federal regulations. Waste Management Resource Conservation and Recovery Act The Resource Conseivation 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 is 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, e Small quantity Generators - A facility which generates less than 1000 kilograms /
month (2200 lbs/ month).
- Conditionally Exempt Small Quantity Generators - A facility which generates 100 kilo-grams / month (220 lbs/ month).
In 1995, the Davis-Besse Nuclear Power Station generated 1,620 pounds of hazardous wastes, which represents a 74% reduction from 1994. There were 3,070 gallons of non-hazardous waste oil generated in 1995, a 32% reduction from 1994. Additionally, approximately 1,200 gallons of oil filters and solid oily debris were generated during 1995. Additionally,2,500 gallons of water containing small amounts of diesel fuel oil from a minor on-site diesel fuel oil leak were disposed as non-hazardous redated waste. 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. l 150
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~1 l i Davis-Besse Nuclear Power Station 1995 Annual Radiological Envuonmental Operating Report l
l Inspections i I e Chemical Waste Accumulation Areas are designated throughout the site to ensure j proper handling and disposal of chemical waste. These, along with the Chemical 1 l Waste Storage Area, are routinely patrolled by security personnel and inspected I
- 1. weekly by Toledo Edison personnel. All areas used for storage or accumulation of L hazardous waste am posted as such with warning signs, and drums are color-coded i l for easy identification of waste categories by Davis-Besse employees. l l
l e Waste Inventory Forms I Inventory forms are placed on waste accumulation drums or provided in the accumu-l 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 drum contents for proper disposal. e Testing of Waste Oil l The majority of waste oil generated at Davis-Besse is not disposed of, but is removed to a recycling facility for energy recovery. Before removal for recycling, the oil is tested to ensure that it is nonhazardous. Waste oil that contains less than 1,000 parts per million of halogens and has a flash point above 140 F is considered to be non-l hazardous waste. l Emergency Response Planning l Comprehensive Environmental Response, Compensation, and Liability Act 1 , The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, l 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- l 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 i emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enh-M by ensuring that the potential for release of hazardous substances is minimized and adequate and timely responsec 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. 151 C
Davis-Besse Nuclear Power Station 1995 Annual Radiolopcal Environmental Operating Report i 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 1995. l Spill Kits i 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, decontaimination agents, absorbent cloth, goggles, and warning signs. 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 sys-tem, very similar to the hazardous waste management system established under RCRA. In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers onsite. PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with non-PCB liquid. Retrofilling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with PCB-leaching solvents and allowing the so! vent to circulate in the transformer during opera-tion. The entire retrofill process takes several years and will extract almost all of the PCB. In all, Davis-Besse performed retrofill activities on ekven PCB transformers between 1987 and 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors. These capacitors are being replaced and disposed of during scheduled maintenance activities. Approxi-mately 15 kilograms of PCBs were disposed ofin 1995. Clean Air Act The Clean Air Act identifies substances which are considered air pollutants. Davis-Besse holds an OEPA permit to operate an Air Contaminar.t Source for the station auxiliary boiler. This boiler is used to heat the station and provide steam to plant systems when the reactor is not operating. A report detailing 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 very infrequently to verify their reliability, and would only be used in the event of an emergency. 152 J
Davis-Besse Nuclear Power Station 1995 Annual Radiol:gical Enviran -=*=1 Operating Report In response to recent " Clean Air Act Title V" legislation, an independent study identifying and quantifying all of the rir pollution sources onsite was performed. Of particular significance is asbestos removal from renovation and demolition projects for which USEPA has outlined specific 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 sur-veillance, 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 disposal of this waste under the Clean Air Act. Transportation Safety Act The transportation of hazardous chemicals, including chemical waste, is regulated by the Trans-portation Safety Act of 1976. These regulations are enforced by the United States Department of ; Transportation (DOT) and cover all aspects of transporting hazardous materials, including pack-ing, handling, labeling, marking, and placarding. Before any wastes are transported off site, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations, including verification that the vehicle has appropriate placards and it is in good op-erating condition. Other Programs Underground Storage Tanks According to RCRA, facilities with Underground Storage Tanks (UST) are required to notify the State. This regulation was implemented in order to provided protection from tank contents leak-ing 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 gal-lon diesel fuel storage tanks are registered USTs. i 153
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Waste Minimization and Recycling , l I Municipal Solid Waste (MSW) is everyday trash which is produced by individuals at home and by i industries. In some communities MSW is burned in specially designed incinerators to produce 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 l landfills reach their capacity and close, MSW disposal becomes an imponant economic, health, ) and resource issue. I The State of Ohio has addressed the issue with the State Solid Waste Management Plan, other-wise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing landfills by reducing the amount of MSW produced, by reusing waste material where possible and recy-cling of other waste materials. This is frequently referred to as " Reduce, Reuse, and Recycle." Davis-Besse and Centerior Energy have implemented several programs which emphasize the re-duce, reuse, recycle approach to MSW management. Improved efficiency in collection and haul- I ing, resulted in a two year reduction of approximately 71 % for disposal cost MSW. Additionally, joint partnership agreements with yard waste compositors have been developed for yard and lawn waste recycling. Other programs include paper, cardboard , aluminum cans, used tires, and metals recycling or re-covery. Greater than 58 tons of paper and greater than 9 tons of corrugated cardboard were re-cycled in 1995, which would have otherwise been placed in a landfill. Additionally, approximately 2500 pounds of aluminum soft drink cans are collected on site for the Boy Scouts to recycle. 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 re-cycle scrap metals. The metals are sold at current market price to a scrap dealer for resource re-covery. These program are continuously being expanded and reinforced as other components of MSW stream are targeted for reduction. 154 _J
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l l l l l l Appendices l l l 4 i i I 4 1 3 i a 1 i l 8 l
Divis-Bcsse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report l l APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESUL'IS NOTE: Teledyne's Midwest Laboratory participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. The results are reported in Appendix A. Also reported are results of InternationalIntercomparison and Teledyne testing of TLD's, as well as, in-house spikes, blanks and duplicates. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only. Please refer to March, June, September and December progress reports for information. January,1995 through December,1995 155 m
DIvis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Apoendix A Interlaboratory Comoarison Procram Results Teledyne's Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparipn (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) contaming concentrations of radionuclides know 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 issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request. This program is conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada. The results in Table A-2 were obtained for 'Ihermoluminescent Dosimeters (TLDs), since 1976 via various International Intercomparisons of Environmental Dosimeters under the sponsorships listed I in Table A-2. Also Teledyne testing results are listed. l J Table A-3 lists results of the analyses on in-house " spiked" samples for the past twelve months. 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. , Attachment A lists acceptance criteria for " spiked" samples. Out-of limit results are explained directly below the result. 156 e . ..
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report 12-31-95 A~ITACHMDir A ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg 5% of known value 6
Strontium-89 5 to 50 pCi/ liter or kg 5.0 pCi/ liter
>50 pCi/ liter or kg 10% of known value 6
Strontium-90 2 to 30 pCi/ liter or kg 5.0 pCi/ liter
>30 pCi/ liter or kg 10% of known value Potassium >0.1 g/ liter or kg 5% of known value Gross alpha s20 pCi/ liter 5.0 pCi/ liter
>20 pCi/ liter 25% of known value Gross beta $100 pCi/ liter 5.0 pCi/ liter
>100 pCi/ liter 5% of known value Tritium 54,000 pCi/ liter Is = (pCi/ liter) = l 169.85 x (known)"" l
>4,000 pCi/ liter 10% of known value !
I Radium-226,-228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value lodine-131, s55 pCi/ liter 6.0 pCi/ liter 6 lodine-129 >55 pCi/ liter 10% of known value Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-64 6 >35 pCi/ liter 15% of known value Technetium-99* Iron-55, 50 to 100 pCi/ liter 10 pCi/ liter *
>100 pCi/ liter 10% of known value Others* -
20% of known value
- From EPA publication," Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-000 Teledyne limit.
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., Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's
- Midwest Laboratory results for various sample media'.
Concentration in pCi/L" Lab Sample Date Teledyne Results EPA Result' Control Code Type Collected Analysis i2 Sigma
- 1s, N=1 Limits
, STW-723 WATER Jan,1995 Sr-89 17.711.5 20.015.0 11.3 - 28.7 STW-723 WATER Jan,1995 Sr-90 13.7 i 0.6 15.0 i 5.0 6.3 - 23.7 STW-724 WATER Jan,1995 Gr. Alpha 4.3i 0.6 5.015.0 0.0 - 13.7 STW-724 WATER Jan,1995 Gr. Beta 4.7i 0.6 5.015.0 0.0 - 13.7 STW-725 WATER Feb,1995 1-131 99.0 i 4.4 100.0 1 10.0 82.7 - 117.3
- STW-726 WATER Feb,1995 Ra-226 19.210.4 19.li 2.9 14.1 - 24.1
- STW-726 WATER Feb,1995 Ra-228 19.2 i 2.0 20.015.0 11.3 - 28.7
) STW-726 WATER Feb,1995 Uranium 24.9 i 0.2 25.513.0 20.3 - 30.7 STW-727 WATER Mar,1995 H-3 7,460.0 i 87.2 7,435.0 1 744.0 6,144.2 - 8,725.8 i STW-728 WATER Mar,1995 Pu-239 11.010.6 11.111.1 9.2 - 13.0 j STW-729 WATER Apr,1995 Gr. AIpha 41.7 i 0.6 47.5 i 11.9 26.9 - 68.1 STW-729 WATER Apr,1995 Ra-226 13.4 t 0.5 14.9 i 2.2 11.1 - 18.7 ~ STW-729 WATER Apr,1995 Ra-228 13.112.4 15.8 i 4.0 8.9 - 22.7 STW-729 WATER Apr,1995 Uranium 9.510.6 10.013.0 4.8 - 15.2 STW-730 WATER Apr,1995 Co-60 29.0 i 1.7 29.015.0 20.3 - 37.7 STW-730 WATER Apr,1995 Cs-134 17.311.2 20.015.0 11.3 - 28.7 STW-730 WATER Apr,1995 Cs-137 11.0 1.0 11.0 5.0 2.3 - 19.'7 STW-730 WATER Apr,1995 Gr. Beta 74.813.2 86.6110.0 69.3 - 103.9 STW-730 WATER Apr,1995 Sr-89 17.010.0 20.015.0 11.3 - 28.7 STW-730 WATER Apr,1995 Sr-90 12.7 1.2 15.015.0 6.3 - 23.7 STW-732 WATER Jun,1995 Ra 226 14.7 i 0.3 14.812.2 11.0 - 18.6 STW-732 WATER Jun,1995 Ra-228 11.9 i 0.6 15.013.8 8.4 - 21.6 STW-732 WATER Jun,1995 Uranium 13.9 i 0.3 15.2 3.0 10.0 - 20.4
- STW-735 WATER Jul,1995 Gr. Alpha 16.412.4 27.5 i 6.9 15.5 - 39.5
- STW-735 WATER Jul,1995 Gr. Beta 16.811.0 19.415.0 10.7 - 28.1 STW-736 WATER Aug,1995 H-3 4,773.7 1 49.9 4,872.0 t 487.0 4,027.1 - 5,716.9
- Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
Environmental Protection Agency (EPA), Las Vegas, Neveda.
- All results are in pCi/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 mean i 2 standard deviations for three determinations.
- USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and controllimit as defined by the EPA.
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Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report l Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Date Measurement 12 Sigma Value t 2 Sigma (All Participants) 2nd IntemationalIntercomparison 115-2 CaF,: Mn Bulb Apr,1976 Field 17.011.9 17.1 16.4 i 7.7 115-2 CaF,:MnBulb Apr,1976 Lab 20.8 i 4.1 21.3 18.di 7.6 Second InternationalIntercompanson of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (HASL), New York, new York, and the School of Public Health of the University of Texas, Houston, Texas. 3rd Intemational Intercomoarison 115-3 CaF,:Mn Bulb Jun,1977 Field 30.7 i 3.2 34.9 i 4.8 31.5 i 3.0 115-3 CaF,:Mn Bulb Jun,1977 Lab 89.6 i 6.4 91.7 i 14.6 86.2 i 24.0 Third International Intercomparison of Environmental Dosimeters conducted in the summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas. 4th International Intercomoarispn 115-4 CaF,: Mn Bulb Jun,1979 Field 14.111.1 14.1 i 1.4 16.0 i 9.0 115-4 CaF,:Mn Bulb Jun,1979 Lab, High 40.411.4 45.8 i 9.2 43.9 i 13.2 115-4 CaF,: Mn Bulb Jun,1979 Lab, Low 9.8i1.3 12.212.4 12.017.4 Fourth International Intercomparison of Environmental Dosimeters conducted in the summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 5th International Intercomoarison 115-5A CaF,: Mn Bulb Oct,1980 Field 31.4 i t .8 30.016.0 30.2 i 14.6 115-5A CaF,: Mn Bulb Oct,1980 Lab,End 96.6 i 5.8 88.4 i 8.8 90.7 i 31.2 115-5A CaF,: Mn Bulb Oct,1980 Lab, Start 77.4 i 5.8 75.217.6 75.8140.4 Fifth International Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 5th Intemational Intercomoarison 115-5B LiF-100 Chips Oct,1980 Field 30.3 i 4.8 30.016.0 30.2114.6 115-5B LiF-100 Chips Oct,1980 Lab,End 85.4111.7 88.4 i 8.8 90.7 i 31.2 115-5B LiF-100 Chips Oct,1980 Lab, Start 81.l i 7.4 75.217.6 75.8140.4 Fifth International Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 6th international Intercomparison 115-6 Teledyne did not participate in the Sixth Intemational Intercomparison of Environmental Dosimeters. 7th International Intercomparison 115-7A LiF-100 Chips Jun,1984 Field 75.412.6 75.8 6.0 75.1129.8 159 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . I
, _ - . .- __ - - = _ _- Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-2. Crosscheck program results;hermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average i 2 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) 115-7A LiF-100 Chips Jun,1964 Lab, Co-60 80.013.5 79.9 i 4.0 77.9127.6 115-7A LiF-100 Chips Jun,1964 Lab, Cs-137 66.6 2.5 75.013.8 73.0122.2 Seventh InternationalIntercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Ias Vegas, Nevada, ano sponsored by the US. Department of Energy, ne Nuclear Regulatory Commission, and the US. Environmental Protection Agency. 7th International Intercomoarison 115-7B LiF-100 Chips Jun,1984 Fie1d 71.512.6 75.8 i 6.0 75.1 i 29.8 l 115-7B LiF-100 Chips Jun,1984 Lab, Co-60 84.8 i 6.4 79.9 i 4.0 77.9 i 27.6 115-7B LiF-100 Chips Jun,1984 Lab, Cs-137 78.8 1.6 75.0 i 3.8 73.0122.2 Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of ! l 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Comnussion, and the US. Environmental Protection Agency. 7th International Intercomoarison 115-7C CaSO.: Dy Jun,1984 FieId 76.812.7 75.816.0 75.1 i 29.8 Cards 115-7C CaSO.: Dy Jun,1984 Lab, Co-60 82.513.7 79.9 i 4.0 77.9 i 27.6 Cards 115-7C CaSO.: Dy Jun,1984 Lab, Cs-137 79.0 3.2 75.0 i 3.8 73.0122.2 Cards Seventh International 1ntercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the US. Department of Energy, The Nuclear Regulatory Commission, and the US. Environmental Protection Agency. 8th International Intercomoarison. 115-8A LiF-100 Chips Jan,1986 Field, Site 1 29.511.4 29.711.5 28.9 i 12.4 115-8A LiF-100 Chips Jan,1986 Field, Site 2 11.310.8 10.410.5 10.119.1 ! 115-8A LiF-100 Chips Jan,1986 Lab, Cs-137 13.7 i 0.9 17.2 i 0.9 16.2 i 6.S ) Eighth International Intercompanson of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the US. Department of Energy. 8th International Intercomoarison 115-8B LiF-100 Chips Jan,1986 Field, Site 1 32.311.2 29.711.5 28.9 i 12.4 115-8B LiF-100 Chips Jan 1986 Field, Site 2 9.011.0 10.4 i 0.5 10.l i 9.0 115-8B LiF-100 Chips Jan,1986 Lab, Cs-137 15.8 0.9 17.2 i 0.9 16.216.8 Eighth IntemationalIntercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the US. Department of Energy. 8th International Intercomoarison 115-8C CaSO : Dy Jan,1986 Field, Site 1 32.2 0.7 29.7 t l .5 28.9 12.4 Cards l l 160
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report I Table A-2 Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). l l l mR l 1 Lab Teledyne Results Known Average i2 Sigma TLD Type l Code Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) l 115-8C CaSO.: Dy Jan,1986 Field, Site 2 10.610.6 10.410.5 10.119.0 I Cards I 115-8C CaSO4 : Dy Jan,1986 lab, Cs-137 18.110.8 17.2 i 0.9 16.2 i 6.8 ; Cards ' Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy. 9th International Intercomoarison 115-9 The Ninth International Intercomparison of Environmental Dosimeters was not available to Teledyne's Midwest Laboratory. 10th International Intercomoarison 115-10A LiF-100 Chips Aug,1993 Field 25.711.4 27.011.6 26.4110.2 115-10A LiF-100 Chips Aug,1993 Lab,1 22.7 i 1.6 25.9 i 1.3 25.0 i 9.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62.712.6 72.711.9 69.8 i 20.3 The Tenth Intemational Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State University and sponsored by the U.S. Department of Energy and the Idaho State University. 10th International Intercomoarison 115-10B CaSO.: Dy Aug,1993 FieId 26.012.3 27.0 i 1.6 26.4 10.2 Cards 115-10B CaSO.: Dy Aug,1993 Lab,1 24.1 1.7 25.911.3 25.019.4 Cards 115-10B CaSO.: Dy Aug,1993 Lab,2 69.2 3.0 72.7 i l.9 69.8 20.3 Cards The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho Stat University and sponsored by the U.S. Department of Energy and the Idaho Stat University. Tcledyne Testing 89-1 LiF-100 Chips Sep,1989 Lab 21.0 0.4 22.4 ND ND = No Data:Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in September,1989. Teledyne Testing 89-2 Teledyne Nov,1989 Lab 20.9 1.0 20.3 ND CaSo.: Dy Cards ND = No Data: Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. 161
, - - . ._. - _ ~ . - . . _ ..- - . - . _ .--
l 1 Davis-Besse Nuclear Power Station 1995 Annual Radiological Enviror. mental Operating Report Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type - Date Measurement 2 Sigma Value i 2 Sigma (All Participants) Teledvne Testing 90-1 Teledyne Jun,1990 Lab 20.611.4 19.6 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. Teledyne Testing 90 2 Teledyne Jun,1990 Lab 100.8 i 4.3 100.0 ND L CaSo.: Dy ' Cards ND - No Data; Teledyne Testing was only performed by Teledyne. Cards w ere irradiated by Dosimetry Asssociates, Inc., Northville, MI, in October,1990. Teledyne Testing 91-1 Teledyne Oct,1990 Lab,1 33.412.0 32.0 ND CaSo.: Dy ' Cards ' 91-1 Teledyne Oct,1990 Lab,2 55.2 i 4.7 58.8 ND CaSo.: Dy Cards 91-1 Teledyne Oct,1990 Lab,3 87.8 6.2 85.5 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne, Cards were irradiated by Tcledyne Isotopes, Inc., Westwood, New Jersey, in October,1991. Teledyne Testing 92-1 LiF-100 Chips Feb,1992 Lab,1 11.110.2 10.7 ND 92-1 LiF-100 Chips Feb,1992 Lab,2 25.6 0.5 25.4 ND 92-1 LiF-100 Chips Feb,1992 Lab,3 46.4 0.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in February,1992. Teledyne Testing 92-2 Teledyne Apr,1992 Reader 1, #1 20.110.1 20.1 ND CaSo.: Dy Cards 92-2 Teledyne Apr,1992 Reader 1, #2 40.6 0.1 40.0 ND CaSo.: Dy Cards 162
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) 92-2 Teledyne Apr,1992 Reader 1,#3 60.011.3 60.3 ND CaSo.: Dy Cards 92-2 Teledyne Apr,1992 Reader 2, #1 20.310.3 20.1 ND CaSo.: Dy Cards 92-2 Teledyne Apr,1992 Reader 2, #2 39.210.3 40.0 ND CaSo.: Dy Cards 92-2 Teledyne Apr,1992 Reader 2, #3 60.710.4 60.3 ND j CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in April,1992. l Teledyne Testing 93-1 Teledyne Mar,1993 Lab,1 10.011.0 10.2 ND i LiF-100 Chips ! 93-1 Teledyne Mar,1993 Lab,2 25.212.2 25.5 ND LiF-100 Chips 93-1 Teledyne Mar,1993 Lab,3 42.7 i 5.7 45.9 ND I LiF-100 Chips l ND = No Data;Teledyne Testing was only performed by Teledyne. l Chips were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in March,1993. Due to a potential . error of 10-12% when cards where irradiated, results of the testing on the cards will not be published. Data is I available upon request. Teledyne Testing 94-1 Teledyne Nov,1994 Lab,1 15.6 0.4 14.9 ND LiF-100 Chips 94-1 Teledyne Nov,1994 12b,2 30.210.4 29.8 ND LiF-100 Chips 94-1 Teledyne Nov,1994 12b,3 59.2 0.3 59.7 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Reader 1, #1 14.910.1 14.9 ND CaSo.: Dy Cards 94-1 Teledyne Nov,1994 Reader 1, #2 30.8 0.1 29.8 ND CaSo.: Dy Cards 163
1 l Davis-Besse Nuclect Power Station 1995 Annual Radiological Environmental Operating Report Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) 94-1~ Teledyne Nov,1994 Reader 1, #3 58.910.3 59.7 ND CaSo.: Dy Cards 94-1 Teledyne Nov,1994 Reader 2, #1 15.410.2 14.9 ND ; CaSo.: Dy i Cards 94-1 Teledyne Nov,1994 Reader 2, #2 31.4 i 0.2 29.8 ND l CaSo.: Dy j Cards 94-1 Teledyne Nov,1994 Reader 2, #3 60.110.3 59.7 ND CaSo.: Dy - Cards ND = No Data; Teledyne Testing was only performed by Teledyne. I Cards were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, m November,1994. l i
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164
l . _ _ . ._ .-..___ l 1 Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report l l 1 Table A 3. In-house " spike" samples. Concentration in pCi/I
- I Lab Sample Date Teledyne Results Known Control' i
Code Type Collected Analysis 2s, n=1* Activity Limits SPW-7569 WATER Jul,1995 H-3 25806.9 i 447.7 26669.0 21335.2 - 32002.8 SPAP-10967 AIR MLTER Nov,1995 Gr. Beta 7.3i 0.0 8.0 0.0 - 18.0 SPAP-2513 AIR MLTER Apr,1995 Gr. Beta 7.5i0.0 8.1 0.0 - 18.1 SPAP-2542 AIR MLTER Apr,1995 Cs-137 2.3i2.1 1.9 1.2 - 2.7 SPAP-284 AlR FILTER Jan,1995 Cs-137 2.2 1 0.0 1.9 1.2 - 2.7 SPAP-284 AIR FILTER Jan,1995 I-131(g) 2.210.0 1.9 1.2 - 2.7 SPAP-408 AIR FILTER Jan,1995 Gr. Beta 7.5 i 0.0 8.1 0.0 - 18.1 SPAP-7554 AIR FILTER Jul,1995 Gr. Beta 7.310.0 8.1 0.0 - 18.1 i SPAP-7557 AIR FILTER Jul,1995 Cs-137 2.3 1 0.0 1.9 1.2 - 2.7 j SPCH-11238 CHARCOAL Oct,1995 1-131(g) 0.8 1 0.0 0.8 0.5-1.1 l CANISTER SPCH-5964 CHARC L Jun,1995 I-131(g) 2.2 1 0.1 2.3 1.4-3.3 SPCH-717 gCgt Jan,1995 I-131(g) 2.9 1 0.1 2.5 1.5 - 3.4 , SPF-10921 FISH Oct,1995 Co-60 0.710.0 0.8 0.5-1.1 SPF-10921 FISH Oct,1995 Cs-134 0.5 i 0.0 0.6 0.3 - 0.8 SPF-10921 FISH Oct,1995 Cs-137 0.9 i 0.1 0.9 0.5 - 1.2 SPF-3708 FISH May,1995 Cs-134 0.1 1 0.0 0.1 0.1 - 0.2 SPF-3708 FISH May,1995 Cs-137 0.210.0 0.2 0.1 - 0.2 SPMI 205 MILK Jan,1995 Cs-137 51.2 7.5 49.4 39.4 - 59.4 SPMI-205 MILK Jari,1995 Sr-89 19.4 i 3.4 23.1 13.1 - 33.1 1 SPMI-205 MILK Jan,1995 Sr-90 26.2 1.3 28.1 18.1 - 38.1 SPM1-2988 MILK Apr,1995 Cs-134 37.0i l .8 40.7 30.7 - 50.7 SPMI-2988 MILK Apr,1995 Cs-137 62.413.1 54.5 44.5 - 64.5 SPMI-2988 M3LK Apr,1995 Sr-89 32.613.3 36.5 26.5 - 46.5 SPMI-2988 MILK Apr,1995 Sr-90 25.6 i 1.6 24.9 14.9 - 34.9 SPMI-6838 MILK Jun,1995 I-131 38.5 i 0.5 39.6 27.6 - 51.6 SPMI 707 MILK Jan,1995 I-131 80.311.4 86.0 68.8 - 103.2 SPMI-707 MILK Jan,1995 I-131(g) 84.8110.4 86.0 51.6 - %.0 SPMI-7525 MILK Jul,1995 Cs-134 31.512.5 34.4 24.4 - 44.4 l SPMI-7525 MILK Jul,1995 Cs-137 50.214.0 43.4 33.4 - 53.4 SPMI-7525 MILK Jul,1995 I-131(g) 44.715.4 45.6 27.4 - 55.6 SPMI-7525 MILK Jul,1995 Sr-90 28.0 i 1.4 27.9 17.9 - 37.9 SPSO-5130 501L May,1995 Cs-134 0.3i 0.0 0.3 0.2 - 0.4 SPSO-5130 Soll May,1995 Cs-137 0.510.0 0.5 0.3 - 0.7 165 l i
. . -. - - . - - . . - _ . . . - ~ -.- - . _ . . - - . _ . _ -
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analysis 2s, n=1' Activity Limits SPVE-6006 VEGETATION Jun,1995 I-131(g) 0.610.0 0.5 0.3 - 0.8 SPVE-7190 VEGETATION Jul,1995 I-131(g) 1.110.0 1.0 0.6 - 1.4 SPVE-729 VEGETATION Feb,1995 I131(g) 1.9i 0.1 1.9 1.1 - 2.6 SPW-1204 WATER Feb,1995 Ra 226 6.9i 0.1 6.9 4.8 - 9.0 SPW-12079 WATER Nov,1995 H-3 27963.4 i 445.5 29315.0 23452.0 - 35178.0 SPW-12084 WATER Nov,1995 Gr. Alpha 75313.2 82.8 41.4 - 124.2 SPW-12084 WATER Nov,1995 Gr. Beta 86.912.5 86 3 76.3 - % 3 SPW-1790 WATER Mar,1995 Sr-89 0.913.9 42.7 32.7 - 52.7 ne raw data was reviewed and found to be free of errors. The sample was repeated with similar results.An Investigation was conducted to determine the cause of this deviation. No apparent cause was found for this discrepancy. It was determined the " spike" was prepared improperly. Another " spike" t was prepared and analyzed (See SPW-6388). No further action is planned. i SPW-1790 WATER Mar,1995 Sr-90 31.411.8 39.1 313 - 46.9 ; ne raw data was reviewed and found to be free of errors. De sample was repeated with similar results.An Irwestigation was conducted to determine the cause of this deviation. No apparent ca ase was found for this discrepancy. It was determined the " spike" was prepared improperly Another " spike" was prepared and analyzed (See SPW-6388). No further action is planned. j SPW-2544 WATER Apr,1995 H-3 9656.2 1 291.8 9333.0 7466.4 - 11199.6 l SPW-2652 WATER Apr,1995 Co-60 23.812.4 24.8 14.8 - 34.8 SPW-2652 WATER Apr 1995 Cs-134 29312.3 30.8 20.8 - 40.8 ) SPW-2652 WATER Apr,1995 Cs-137 42313.9 40.9 30.9 - 50.9 WATER l SPW-286 Jan,1995 H3 40929.9 i 5594.5 40871.0 32696.8 - 49045.2 l SPW-289 WATER Jan,1995 Co-60 250.5 14.1 247.5 222.8 - 2723 SPW-289 WATER Jan,1995 Cs-134 290.5 14.4 321.3 289.2 - 353.4 SPW-289 WATER Jan,1995 Cs-137 387.7 1 21.2 394.3 354.9 - 433.7 ; SPW-3051 WATER Mar,1995 Gr. Alpha 88.5 i 3.7 82.9 41.5 - 124.4 SPW-3051 WATER Apr,1995 Gr. Alpha 88.013.8 82.9 41.5 - 124.4 SPW-3051 WATER Mar,1995 Gr. Beta 83.012.3 87.2 77.2 - 97.2 SPW-3051 WATER Apr,1995 Gr. Beta 79.6 i 2 3 87.2 77.2 - 97.2 SPW-3589 WATER May,1995 Fe-55 2033.7 i 500.2 2274.0 1819.2 - 2728.8 i SPW-5608 WATER Jun,1995 1-131 78.8123 85.5 68.4 - 102.6 SPW-6005 WATER Jun1995 I-131 48.211.9 46.8 34.8 - 58.8 SPW-6008 WATER May,1995 Gr. Alpha 17311.4 20.7 10.4 - 31.1 SPW-6008 WATER May,1995 Gr. Beta 21.2 i l.0 21.8 11.8 - 31.8 SPW-6388 WATER May,1995 Sr-89 18.712.4 21.2 11.2 - 31.2 SPW-6388 WATER May,1995 Sr-90 21.211.1 23.2 13.2 - 33.2 166 I L _.
Davis-B:sse Nucle:r Power Station 1995 Annual Radiological Environmental Operating Report 4 Table A-3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date Teledyne Results Known Controf Code Type Collected Analysis 2s, n=1' Activity Limits i SPW-6398 WATER May,1995 Sr-89 18.7 i 2.4 21.2 11.2 - 31.2 SPW-6398 WATER May,1995 Sr-90 21.2 i 1.1 23.2 13.2 - 33.2 SPW-6839 WATER Jun,1995 I-131 34.9t 0.5 39.5 27.5 - 51.5 SPW-8179 WATER Jul,1995 Fe-55 2.3i0.4 2.1 0.0 - 22.1 SPW-9981 WATER Sep,1995 Sr-89 34.614.9 39.0 29.0 - 49.0 SPW-9981 WATER Sep,1995 Sr-90 20.311.3 20.0 10.0 - 30.0
- All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L; air filter samples, which are in pCi/ Filter; and food products, which are in mg/kg.
" All samples are the results of single determinations.
- Controllimits are based on 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 167
l Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-4. In-house " blank" samples. l Concentration pCi/L'. Teledyne Results Acceptance Sample Sample (4.66 Sigma) Criteria l Lab Code Type Date Analysis LLD Activity" (4.66 Sigma) SPAP 10968 AIR FILTER Nov 1995 Gr. Beta <0.4 0.61 i 0.26 < 3.2 SPAP-2514 AIR FILTER Apr1995 Gr. Beta <0.3 0.03 i 0.25 < 3.2 SPAP-2543 AIR FILTER Apr1995 Co-60 <4.4 0.39 i 2.20 < 10.0 SPAP-2543 AIR FILTER Apr1995 Cs-134 < 1.9 0.0512.11 < 10.0 i SPAP-2543 AIR FILTER Apr1995 Cs-137 < 1.1 -1.2411.83 < 10 0 f l SPAP-283 AIR FILTER Jan1995 Co-60 <2.7 -0.36 i 1.40 < 10.0 I SPAP-283 AIR FILTER Jan1995 Cs-134 <1.5 -0.67 i 1.33 < 10.0 SPAP-283 AIR FILTER Jan 1995 Cs-137 <2.4 0.46 i 1.33 < 10.0 SPAP-409 AIR FILTER Jan 1995 Gr. Beta <0.5 0.02 i 0.28 < 3.2 SPAP-7556 AIR FILTER Jul1995 Gr. Beta <1.0 0.06 0.55 < 3.2 SPAP-7558 AIR FILTER Jul1995 Co-60 <4.2 0.39 i 3.06 < 10.0 SPAP-7558 AIR FILTER Jul1995 Co-60 <4.2 0.0413.07 < 10.0 ( SPAP-7558 AIR FILTER Jul1995 Cs-134 <3.0 -1.23 i 2.45 < 10.0 l SPAP-7558 AIR FILTER Jul1995 Cs-137 <3.5 1.1812.04 < 10.0 j SPCH-11238 CHARCOAL Oct 1995 1131(g) < 1.9 -0.00 i 0.01 < 9.6 CANISTER i SPCH-287 CHARCOAL Jan 1995 1-131(g) <2.3 -1.98 i 3.12 <9.6 CANISTER SPCH-5975 CHARCOAL Jun1995 1131(g) <3.0 -0.7112.68 <9.6 CANISTER SPF-10922 F1SH Oct 1995 Co-60 <5.4 5.74 i 4.70 < 10.0 SPF-10922 FISH Oct 1995 Cs-134 < 8.9 2.4715.44 < 10.0 SPF-10922 FISH Oct 1995 Cs-137 <5.4 -2.44 5.08 < 10.0 SPF-3709 FISH May 1995 Co-60 <8.4 2.2115.97 < 10.0 SPF-3709 F1SH May 1995 Cs-134 <1.3 6.79 i 8.55 < 10.0 SPF-3709 FISH May 1995 Cel37 <1.3 3.6117.81 < 10.0 SPM-204 MILK Jan1995 Co-60 <5.3 0.4113.48 < 10.0 SPM-204 M1LK Jan1995 Cs-134 <4.4 -0.07 i 2.05 < 10.0 MILK Jan 1995 Cs-137 <4.3 1.3212.53 <10.0 SPM-204 MILK Jan 1995 I-131 <0.5 -0.03 i 0.22 <0.5 SPM-204 SPM 204 MILK Jan1995 Sr-89 <0.8 0.1411.08 <5.0 < SPM-204 M1LK Jan 1995 Sr-90 N/A 1.4610.48 < 1.0 Low level of Sr-90 concentration in rnilk (15 pCi/L)is not unusual. SPMI 10920 MILK Oct 1995 Co-60 <3.8 -0.4515.05 < 10.0 M1LK Oct 1995 Cs-134 <3.5 -2.79 i 4.35 < 10.0 SPMI-10920 168
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-4. In-house " blank" samples. Concentration pCi/L*. Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity" (4.66 Sigma) SPMI-10920 MILK Oct1995 Cs-137 <6.0 1.5514.13 < 10.0 SPMI-2987 MILK Apr1995 Cs-134 <3.4 0.37 i l.89 < 10.0 SPMI-2987 MILK Apr1995 Cs-137 <3.3 1.29 i 1.75 < 10.0 SPMI-2987 MILK Apr1995 Sr-89 <0.4 0.0610.62 <5.0 SPMI-2987 MILK Apr1995 Sr-90 N/A 1.47 i 0.38 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPMI-7526 MILK Jul1995 Co-60 <5.8 1.1913.34 < 10.0 SPMI-7526 MILK Jul1995 Cs-134 <5.1 0.4812.76 < 10.0 SPMI-7526 MILK Jul1995 Cs-137 <3.7 0.98 2.39 < 10.0 SPMI-7526 MILK Jul1995 1131 <0.5 0.0010.23 <0.5 SPMI-7526 MILK Jul1995 Sr-89 <0.6 -0.19 i 0.82 <5.0 SPMI-7526 MILK Jul1995 Sr-90 N/A 1.35 i 0.36 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPSO-11225 SOIL Oct 1995 Cs.134 <0.034 0.0010.02 < 10.0 SPSO-11225 SOIL Oct 1995 Cs-137 <0.019 -0.0010.01 < 10.0 SPSO-5131 SOIL May1995 Cs-134 <0.034 0.0110.01 < 10.0 SPSO-5131 SOIL May 1995 Cs-137 <0.012 0.00 i 0.01 < 10.0 SPVE-6007 VEGETATION Jun1995 1-131(g) <0.009 0.00 i 0.01 < 20.0 SPVE-7191 VEGETATION Jul1995 1-131(g) <0.005 -0.0010.00 < 20.0 SPVE-728 VEGETATION Jan1995 1-131(g) <12.0 2.33 i 7.54 < 20.0 SPW-1106 WATER Feb 1995 Ni-63 <12.0 0.25 i 6.31 < 20.0 SPW-12080 WATER Nov 1995 H-3 <149 23.01 1 74.94 < 200.0 SPW-12082 WATER Nov 1995 Co-60 < 2.1 0.62 1.13 < 10.0 SPW-12082 WATER Nov l995 Cs-134 < 1.9 0.0211.28 < 10.0 SPW-12082 WATER Novl995 Cs-137 <2.4 1.5311.22 < 10.0 SPW-12082 WATER Novl995 Cr. Alpha <0.6 0.1910.43 < 1.0 SPW-12082 WATER Nov 1995 Gr. Beta < 1.7 - 0.0611.11 < 3.2 SPW-2545 WATER Apr1995 H-3 <169 97.76 i 88.37 < 200.0 SPW-2651 WATER Apr1995 Co-60 <3.17 -1.0812.45 < 10.0 SPW-2651 WATER Apr1995 Cs-134 <3.32 0.2912.57 < 10.0 SPW-2651 WATER Apr1995 Cs-137 <3.56 -0.9212.64 < 10.0 SPW-285 WATER Jan 1995 H3 <165.0 -48.53 i 84.76 < 200.0 SPW-288 WATER Jan 1995 Co-60 <2.3 -0.1112.02 < 10.0 SPW-288 WATER Jan 1995 Cs-134 <3.5 -0.19 2.61 < 10.0 169 a
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report l l Table A-4. In-house " blank" samples. ! 1 Concentration pCi/L'. Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria l Code Type Date Analysis LLD Activity
- b 56 Sigma) I SPW-288 WATER Jan1995 Cs-137 <4.7 0.98 i 2.54 < 10.0 l SPW-3052 WATER Mar 1995 Gr. Alpha <0.6 0.49 i 0.43 < 1.0 SPW-3051 WATER ' Apr1995 Gr. Alpha <0.7 0.23 i 0.47 < 1.0 SPW-3052 WATER Mar 1995 Gr. Beta <1.4 3.05 i 0.98 < 3.2 SPW-3052 - WATER Apr1995 Gr. Beta <1.7 -0.02 i l.09 <3.2 SPW-3590 WATER May 1995 Fe-55 <602.0 0.00 1 365.40 < 1000.0 SPW-6011 WATER Jun1995 I-131 <0.4 -0.03 i 0.19 < 0.5 SPW-7570 WATER Jul1995 H-3 <164 51.58 i 83.71 < 200.0 SPW-8180 WATER Jul1995 Fe-55 <0.4 0.00 i 0.27 < 1000.0 SPW-8931 WATER Aug1995 Ra-228 < 1.0 0.5810.61 < 1.0 SPW-957 WATER Feb 1995 Co-60 <3.7 -1.25 i 3.02 < 10.0 SPW 957 WATER Feb 1995 Cs-134 <5.2 0.7612.77 < 10.0 SPW-957 WATER Feb 1995 Cs-137 <3.6 -1.3812.65 < 10.0 SPW-9982 WATER Sep 1995 Sr-89 <0.8 0.5210.76 < 5.0 SPW-9982 WATER Sep 1995 Sr-90 <0.4 0.21 i 0.21 < 1.0 ,
- 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.
- 'Ihe activity reported is the net activity result.
l 170
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report 1 Table A-5. In-house " duplicate" samples. Concentration in pCi/L' ; 1 Lab Sample First Second Averaged Codes * ~ Date Analysis Result Result Result WW-62, 63 Jan,1995 Gr. Beta 1.4160 i 0.4220 1.2900 i 0.4000 1.3530 i 0.2907 WW-62, 63 Jan,1995 H-3 22.5635 i 80.8891 18.8029 i 80.7140 20.6832 i 57.1354 WW-41, 42 Jan,1995 Gr. Alpha 5.0970 1 2.5260 2.4790 1 2.1920 3.7880 i 1.6722 i WW-41, 42 Jan,1995 Gr. Beta 4.6720 i 0.8260 4.9650 i 0.8770 4.8185 1 0.6024 WW-41, 42 Jan,1995 H-3 30.0800 i 81.2250 -47.0000 i 77.7750 -8.4600 i 56.2282 WW-41, 42 Jan,1995 K-40 1.3840 i 0.2076 1.7300 0.2595 1.5570 1 0.1662 WW-41, 42 Jan,1995 St-89 -0 3474 i 0.5730 -0.0685 i 0.5382 -0.2079 i 0 3931 l WW-41, 42 Jan,1995 Sr-90 0.2017 i 0.2519 0.1389 i 0.2174 0.1703 i 0.1664 l
- CF-20, 21 Jan,1995 Be-7 0.4327 i 0.1200 0.4741 1 0.1250 0.4534 i 0.0866 5 2.9920 1 0.0920 2.9520 i 0.0654 CF-20, 21 Jan,1995 Gr. Beta 2.9120 i 0.0930 CF-20, 21 Jan,1995 K-40 4.0808 i 0.3060 3.7714 i 0 3050 3.9261 i 0.2160 i CF-20, 21 Jan,1995 Sr-89 0.0013 i 0.0043 0.0000 i 0.0058 0.0007 i 0.0036 CF-20, 21 Jan,1995 Sr-90 0.0017 i 0.0011 0.0026 1 0.0015 0.0021 i 0.0009
} f CW-105,1% Jan,1995 Gr. Beta 5.4370 1 0.9970 6.1900 i 1.0260 5.8135 i 0.7153 ! CW-105,106 Jan,1995 - Gr. Beta 0.0490 i 0.4360 0,0590 i 0.4360 0.0540 1 03083 MI-83,84 'Jan,1995 Co-60 -03330 1 2.5300 0.6530 1 2.1700 0.1600 i 1.6666 ; l Mi-83, 84 Jan,1995 Cs-137 -1.1400 1 2.2700 0.0761 1.8700 -0.5320 i 1.4705 1 l i M1-83, 84 Jan,1995 I-131(G) -1.9100 i 3.2000 1.4700 i 2.4700 -0.2200 i 2.0212 Mi-187,188 Jan,1995 1-131 0.1496 1 0.2574 0.2682 1 03828 0.2089 i 0.2306 Ml-187,188 Jan,1995 K-40 1,573.0000 i 138.0000 1,426.0000 i 177.0000 1,499.5000 i 112.2197 ! l SW-213, 214 Jan,1995 H-3 5,939.6340 1 241.2390 6,091.2412 232.8063 6,015.4376 i 167.6269 i WW-240, 241 Jan,1995 H-3 39.8030 1 80 3410 9.9510 78.9420 24.8770 i S6 3172 j WW-316, 317 Jan,1995 H3 17,618.0000 1 377.0000 17,390.0000 1 381.0000 17,504.0000 1 267.9972 ' MI-295,296 Jan,1995 Co-60 -1.0900 i 23700 0.2510 2.8000 -0.4195 1 1.8342 MI-295,296 Jan,1995 Cs-134 -0.6360 i 1.8100 0.7830 i 2.4400 0.0735 i 1.5190 MI-295,2% Jan,1995 Cs-137 0 3200 i 1.8200 1.2900 1 2.6800 0.9050 i 1.6198 MI-295,2% Jan,1995 I-131 0.1300 1 0.2600 0.2300 1 0 3400 0.1800 i 0.2140 MI-295,2% Jan,1995 1-131(g) -0 3970 1 2.3600 -0.0386 1 43000 -0.2178 1 2.4525 Mi-295,296 Jan,1995 K-40 1,449.1000 i 91.2000 1,311.8000 i 108.0000 1,380.4500 1 70.6779 MI-295,296 Jan,1995 La-140 0.6220 i 1.6900 1.1800 i 2.5000 -0.2790 i 1.5088 MI-295,296 Jan,1995 Sr-89 0.2267 i 0.7985 0.1552 1 0.9326 0.1909 i 0.6139 MI-295, 296 Jan,1995 Sr-90 138131 03839 1.6174 1 0.4296 1.4993 i 0.2881 LW-609, 610 Jan,1995 Gr. Beta 2.6380 i 0.7310 1.6940 0.6930 2.1660 1 0.5036 LW-344, 345 Jan,1995 Co-60 -0.1680 1 1.8700 1.5200 3.1100 0.6760 i 1.8145 LW-344, 345 Jan,1995 Cs-137 0 3820 1 1.9200 -0.1570 2.9500 0.1125 i 1.7599 LW-344, 345 Jan,1995 Gr. Beta 3.2810 1 0.9440 3.3500 1 0.9390 3 3155 1 0.6657 171 j
l Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report }
- Table A-5. In-house " duplicate" samples.
Concentration in pCi/l
- j 1ab First Sarnple Second Averaged
. Codes
- Date Analysis Result Result Result MI 374,375 Jan,1995 I-131 -0.0572 0.2162 -0.0743 i 0.2780 -0.0658 i 0.1761
] ! MI-374,375 Jan,1995 K-40 1,250.0000 i 150.0000 1,286.5000 1 141.0000 1,268.2500 i 102.9332 SW-463, 464 Jdr1,1995 Gr. Beta 1.8970 i 0.5970 1.9470 i 0.6020 1.9220 i 0.4239 SW-463, 464 Jan,1995 H-3 35.5580 i 803070 7.4860 i 78.9880 - 21.5220 i S6.3212 WWU-860, 861 Jan,1995 Gr. Alpha 0 3000 i 0.6000 0.2000 i 0.3000 0.2500 i 0.3354 i WWU-860, 861 Jan,1995 Gr. Beta 0.8450 i 13200 1.7600 1 1.3500 1.3025 i 0.9440 l WWU-860, 861 Jan,1995 K-40 61.8050 1 32.9000 70.9860 1 36.2000 663 955 i 24.4584 SW-586, 587 Jan,1995 Co-60 -2.1600 i 2.2900 1.9400 i 2.7500 -0.1100 1 1.7893 SW-586, 587 Jan,1995 Cs-137 0.5590 1 2.3400 1.5000 i 2.8800 1.0295 i 1.8554 l' WW-547, 548 Jan,1995 H-3 602.5630 1 102.9290 619.5980 i 103.5540 611.0805 i 73.0031 l
- SWT-715, 716 Jan,1995 Gr. Beta 2 3000 i 0.6000 2 3 000 1 0.5000 2 3000 i 0.3905
< SW-694, 695 Feb,1995 Gr. Beta 3.9100 1 0.7450 4.1790 1 0.7550 4.0445 i 0.5303 WW-736, 737 Feb,1995 H-3 9,951.8722 1 284.2655 10,200.7626 i 287.5238 10,0763174i202.1613 > { l WW-763, 764 Feb,1995 H3 584.4290 i 101.0550 707.1020 i 105.5380 645.7655 i 73.0589 I MI-881,882 Feb,1995 1-131 0.1760 1 0.2567 0.1552 i 0.2852 0.1656 i 0.1919 ! M1-881,882 Feb,1995 K-40 1,340.4000 i 164.0000 1,492.0000 i 101.0000 1,416.2000i 96.302r ! MI-838,839 Feb,1995 Co-60 0.9670 i 2.6500 -0.4760 3.8100 0.2455 i 2.3205 l MI-838,839 Feb,1995 Cs-134 -0.0557 i 2.2800 -1.4200 3.0900 -0.7379 i 1.9201 l MI-838,839 Feb,1995 Cs-137 -0.4380 i 2.5500 -0.4370 i 3.0900 -0.4375 i 2.0032 l MI-838,839 Feb,1995 1-131 0.1283 i 0.1951 0.0880 i 0.1984 0.1081 i 0.1391 i MI-838,839 Feb,1995 I131(g) -0.2560 1 2.5800 -0.5630 1 3.1800 -0.4095 i 2.0475 MI-838, 839 Feb,1995 K-40 1,298.6000 i 99.4000 1,232.5000 1 125.0000 1,265.5500 i 79.8520 { i Mi-838,839 Feb,1995 St-89 0.5302 1 0.5774 0.5000 1 0.6000 0.5151 1 0.4164 f MI-838,839 Feb,1995 Sr-90 0.8186 i 0.2809 0.8000 1 0 3000 0.8093 i 0.2055 1 MI-937,938 Feb,1995 I-131 -0.0083 1 0.1800 -0.0270 1 0.1800 -0.0177 i 0.1273 M1-937,938 Feb,1995 K-40 1,451.8000 i 69.6000 1,456.6000 1 141.0000 1,454.2000 i 78.6212 l SW-904, 905 Feb,1995 H-3 640 3425 i 104.5679 597.4040 1 103.0233 618.8733 i 73.3966 l
; MI 1216,1217 Feb,1995 1-131 0.2640 1 0.2740 0.1160 i 0.2600 0.1900 1 0.1889 3
Mi-1216,1217 Feb.1995 K-40 1,583.0000 i 131.0000 1,493.6000 1 174.0000 1,538 3000 i 108.9002
- SW-1237,1238 Feb,1995 H-3 553942 i 973964 4.8591 i 95 3581 30.1267 i 68.1528 i SW-1264,1265 Feb,1995 H-3 67.0910 i 81.1760 109.2630 1 83.1440 88.1770 i 58.1001' G-1343,1344 Feb,1995 Be-7 11.4490 1 0.2850 11.8800 i 0.2560 11.6645 1 0.1915
; G-1343,1344 Feb,1995 K 40 2.9844 1 0.2420 3.0269 1 0.2250 3.0057 1 0.1652
{ SW-1494,1495 Feb,1995 Co-60 -2.1900 i 4.1200 0.0565 i 3.4400 -1.0668 i 2.6837 i, SW-1494,1495 Feb,1995 Cs-137 3.4500 1 3.6600 0.2430 3.5700 1.8465 1 2.5564 l SW-1367,1368 Feb,1995 H-3 560 3183 i 103.1109 606.1104 i 104.7919 583.2144 i 73.5072 1 E j 172 4
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-5. In-house duplicate" samples. Concentration in pCi/L' I 1 Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result l
- WW-1394,1395 Feb,1995 H-3 47.8810t 80.1790 -24.8930 i 76.6250 11.4940 i 55.4528 SWT-1515,1516 Feb,1995 Gr. Beta 2.4460 t 0.5250 1.6920 1 0.5000 2.0690 i 0.3625 WW-1536,1537 Feb,1995 H-3 2,874.3025 i 167.5000 2,924.0574 i 168.6330 2,899.1800 i 118.8416 4
j WW-1563,1564 Mar,1995 H-3 33.5160 i 82.6640 39.5490 i 82.9570 36.5325 1 58.5560 l WW-1618,1619 Mar,1995 Co-60 2.8000 i 1.5000 2.2000 i 4.6000 2.5000 i 2.4192 WW-1618,1619 Mar,1995 Cs-137 -0.9000 i 1.7000 -2.5000 i 3.2000 -1.7000 1 1.8118 WW-1618,1619 - Mar,1995 H-3 4,333.0000 1 204.0000 4,457.0000 1 206.0000 4,395.0000 i 144.9586 ! MI-1663,1664 Mar,1995 Co-60 1.9500 1 3.2400 -1.5300 i 2.7200 0.2100 i 2.1152 l MI-1663,1664 Mar,1995 Cs-134 0.1690 i 2.7700 -1.1300 i 2.0500 -0.4805 i 1.7230 [ MI-1663,1664 Mar,1995 Cs-137 -0.0737 i 2.7400 0.9210 1 2.4100 0.4237 1 1.8245 Mi 1663,1664 Mar,1995 1-131 0.1226 i 0.2720 0.2261 1 0.3010 0.1744 i 0.2028 I MI-1663,1664 Mar,1995 I-131(g) -0.4090 i 3.7100 0.1220 1 3.4200 -0.1435 i 2.5229 M1-1663,1664 Mar,1995 K-40 1,592.1000 1 124.0000 1,555.6000 i 118.0000 1,573.8500 i 85.5862 MI-1663,1664 Mar,1995 La-140 -1.6500 1 3.1000 -0.2240 1 2.6800 -0.9370 1 2.0489
~
MI-1663,1664 Mar,1995 Sr-89 0.5984 1 0.6672 0.5889 1 0.7467 0.59371 0.5007 MI-1663,1664 Mar,1995 Sr-90 1.3624 1 0.3718 1.5034 0.4517 1.4329 i 0.2925 ) WW-1684,1685 Mar,1995 Gr. Beta 4.9280 1 0.7420 5.0100 1 0.7400 4.9690 1 0.5240 WW-1684,1685 Mar,1995 H-3 81.7160 1 84.9140 85.7340 1 85.1040 83.7250 i 60.1105 l i LW 1707,1708 Mar,1995 Co-58 0.4070 3.0300 0.0486 i 2.8500 0.2278 i 2.0799 LW-1707,1708 Mar,1995 Co-60 1 0600 1 2.8900 1.5000 i 2.7000 1.2800 i 1.9775 LW-1707,1708 Mar,1995 Cs"-134 -1.8600 1 3.0500 -1.5400 1 2.8300 -1.7000 i 2.0003 LW-1707,1708 Mar,1995 Cs-137 2.5900 1 2.9600 -1.3700 1 2.5100 0.6100 i 1.9405 LW-1707,1708 Mar,1995 Fe-59 5.5200 6.1500 -6.6900 1 6.1500 -0.5850 1 4.3487 LW-1707,1708 Mar,1995 Gr. Beta 1.9570 i 0.4850 2.1270 1 0.4760 2.0420 1 0.3398 LW-1707,1708 Mar,1995 1131 0.2350 1 0 2925 -0.0500 1 0.2859 0.0925 1 0.2045 LW-1707,1708 Mar,1995 I-131(g) -0.6900 1 6.6800 -0.6210 1 6.2000 -0.6555 i 4 5569 LW-1707,1708 Mar,1995 K-40 79.3000 i 42.8000 75.3000 i 39.2000 77.3000 1 29.0193 LW-1707,1708 Mar,1995 La 140 -3.5900 i 5.0900 1.2800 i 4.5800 -1.1550 i 3.4236 LW-1707,1708 Mar,1995 Mn-54 -1.9300 i 3 1200 0.7640 i 2.5200 -0.5830 1 2.0053 LW-1707,1708 Mar,1995 Ru-103 -0.1320 1 3.3400 -0.7770 1 2.9700 -0.4545 i 2.2348 LW-1707,1708 Mar,1995 Zn-65 2.6700 1 6.4700 -1.7400 i 5.7700 -2.2050 i 4.3346 LW-1707,1708 Mar,1995 Zr-Nb-95 -0.2680 1 3.0600 -3.2400 1 2.7200 -1.7540 1 2.0471 SW-1762,1763 Mar,1995 H-3 104.4150 1 89.3960 92.2110 i 88.8390 98 3130 i 63.0159 5 0-1861, 1862 Mar,1995 Cs-137 0.2587 0.0414 0.2481 1 0.0248 0.2534 i 0.0241 5 0-1861, 1862 Mar,1995 K.40 11.7290 0.5530 11.2500 0.4990 11.4895 i 0.3724 S 0-1861, 1862 Mar,1995 Ra.226 1.6890 0.3970 1.5274 1 0.2730 1.6082 1 0.2409 173
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Samplc First Second Averaged Codes
- Date Analysis Result Result Result SW-1919,1920 Mar,1995 H .' -9.1230i E5.2000 66.6680 i 88.8670 28.7725 i 61.5556 SW-1919,1920 Mar,1995 H-3 -9.1230 i 85.2005 66.6679 i 88.8672 28.7725 i 61.5559 WWU-2031, 2032 Mar,1995 Gr. Alpha 1.9830 1 2.2510 3.0330 i 2.4400 2.5080 1.6599 WWU-2031, 2032 Mar,1995 Gr. Beta 1.2540 i 1.9270 2.1120 1 1.9680 1.6830 i 1.3772 CW-1997,1998 Mar,1995 Gr. Beta 2.6670 i 0.9880 2 3100 i 1.3570 2.4885 i 0.8393 CW 1997,1998 Mar,1995 Gr. Beta -0.5301 i 0.9521 0.5351 i 1.1355 0.0525 i 0.7409 AP-2784,2785 Mar,1995 C&50 -0.0004 1 0.0006 -0.0003 i 0.0005 -0.0003 i 0.0004 AP-2784,2785 Mar,1995 Cs-137 -0.0003 i 0.0006 0.0001 1 0.0004 -0.0001 i 0.0004 M1-2083,2084 Mar,1995 1-131 0.0210 1 0.1920 0.0150 i 0.1850 0.0180 1 0.1333 M1-2083,2084 Mar,1995 K-40 1,2.73.9000 i 69.7000 1,328.9000 i 59.8000 1,301.4000 1 45.9188 M1-2083,2084 Mar,1995 St-90 1.5850 1 0.4530 1.4D4010.5520 1.6945 i 0.3570 SW-2104, 2105 Mar,1995 Gr. Beta 1.6690 i 0.5320 1.7090 i 0.5640 1.6890 i 0.3877 SW-2200, 2201 Mar,1995 H-3 33.7710 i 85.6270 54.0340 1 86.5810 43.9025 i 60.8857 SW-2355,2356 Mar,1995 Co-60 0.6430 i 1.5100 0.8670 i 1.5800 0.7550 i 1.0928 SW-2355, 2356 Mar,1995 Cs-137 2.2000 2 1.5400 0.0533 1 1.8500 1.1267 i 1.2035 AP-2453,2454 Mar,1995 Sr-89 0.0002 1 0.0006 -0.0001 i 0.0006 0.0000 1 0.0004 AP-2453,2454 Mar,1995 Sr-90 0.0000 1 0.0002 0.0001 1 0.0003 0.0001 i 0.0002 AP-2805,2806 Mar,1995 Co-60 -0.0001 i 0.0004 0.0002 1 0.0003 0.0000 1 0.0002 AP-2805,2806 Mar,1995 Cs-137 0.0002 0.0004 0.0000 0.0004 0.0001 1 0.0003 SW-2221, 2222 Mar,1995 K-40 149.6900 i 74.4000 119 3800 1 46.7000 134.5350 i 43.9211 PW-2248, 2249 Mar,1995 H-3 154.6240 1 91.% 10 164.7520 1 91.5110 159.6880 1 64.5491 PW-2271, 2272 Mar,1995 Co-60 -0.4760 i 1.9800 -1.2100 1 2.8900 -0.8430 t 1.7516 PW-2271, 2272 Mar,1995 Cs-137 0.9590 i 2.0500 0.8750 1 3.4600 0.9170 1 2.0109 MI 2149,2150 Apr,1995 Co60 -1.2100 1 2.2200 0.6560 1 2.6900 -0.2770 i 1.7439 M1-2149,2150 Apr,1995 Cs-137 0.1650 1 2.0400 2.3100 1 2.2200 1.2375 i 1.5075 M1-2149,2150 Apr,1995 I 131(G) 0.0888 i 2.2200 0.3000 1 2.5100 0.1944 i 1.6754 WW-2313, 2314 Apr,1995 Gr. Beta 0.5850 1 0.4990 0.9810 1 0.5230 0.7830 1 0 3614 CW-2401, 2402 Apr,1995 Gr. Beta 1.7069 i 1 2973 3.4661 i 1.4515 2.5865 i 0.9734 CW-2401, 2402 Apr,1995 Gr. Beta 0.0096 i 1.1238 0.4760 i 1.1031 0.2428 i 0.7874 Sle2567,2568 Apr,1995 K-40 1.4123 1 0.4360 1.7225 t 0.3760 1.5674 i 0.2879 WW-2432, 2433 Apr,1995 H-3 -21.5803 1 82.7489 2.6975 1 83.9276 -9.4414 1 58.9305 WW-2659, 2660 Apr,1995 Gr. Beta 0.5450 1 0.6040 0.3970 1 0.4440 0.47101 03748 WW-2659, 2660 Apr,1995 H-3 38 3900 1 87.4520 1333540 1 91.7350 85.8720 1 633703 MI.2713,2714 Apr,1995 1-131 03870 1 0.5277 0.1686 1 0.2430 0.2778 i 0.2905 t M1-2713,2714 Apr,1995 K-40 1,420.9000 1 137.0000 1,420.0000 1 137.0000 1,420.4500 1 96.8736 CW 2739,2740 Apr,1995 Gr. Beta 13.7987 1 2.0770 14.3132 1 2.1038 14.0560 1 1.4782 174
Davis-Besse Nuclear Power Station 1995 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 CW-2739,2740 Apr,1995 Gr. Beta 5.0526 1 1.5206 2.2742 1 1.3431 3.6634t l.0144 SW-2686,2687 Apr,1995 H-3 52.6753 i 86.% 75 2.0260 1 84.5748 27.3506 i 60.6552 WW-3447, 3448 Apr,1995 Gr. Alpha -0.2920i t.6860 -1.4650 i 1.6480 -0.8785 t l.1788 WW-3447,3448 Apr,1995 Gr. Beta 1.2340 i 1.7000 3.1840 i 1.8140 2.2090 1 1.2430 CW-2835,2836 Apr,1995 Gr. Beta 1.9571 t l.4080 2.7378t l.4641 2.3474i t.0157 CW-2835,2836 Apr,1995 Gr. Beta 0.1817 1 1.1916 0.8185 i 1.2403 0.5001 1 0.8600 CW-2918,2919 Apr,1995 Gr. Deta 5.3065 i 1.6254 4.2821 i 1.5611 4.7943 i 1.1268 CW-2918, 2919 Apr,1995 Gr. Beta 2.0988 i 1.2349 0.7752 i 1.2404 1.a37010.9111 F-3552,3553 Apr,1995 K-40 3.1142 1 0.4410 2.8860 1 0.2410 3.0001 i 0.2513 F-3552,3553 Apr,1995 Sr-89 -0.0061 i 0.0064 0.0011 1 0.0080 -0.0025 i 0.0051 F-3552,3553 Apr,1995 Sr-90 0.0023 i 0.0029 0.0005 1 0.0036 0.0014 i 0.0023 SWT-3343,3344 Apr,1995 Gr. Beta 2.3310 i 0.5190 2.9830 1 0.4800 2.6570 1 0.3535 G-3133,3134 Apr,1995 K-40 6.5000 i 0.1740 6.0532 1 0.3120 6.2766 i 0.1786 SW-3403, 3404 Apr,1995 H-3 159.5512 i 90.5914 72.7069 i 86.6327 116.1290 i 62.6738 WW-3424, 3425 Apr,1995 H-3 442.5093 1 116.7309 430.4409 1 116.3142 436.4751 1 82.3940 LW-3682,3683 Apr,1995 Gr. Beta 2.0500 0.5760 1.5240 1 0.5500 1.7870 i 0.3982 LW-3682, 3683 Apr,1995 Gr. Beta 2.0501 1 0.6760 1.5244 1 0.5500 1.7872 1 0.4358 LW-3682, 3683 Apr,1995 H-3 139.9350 i 91.1490 75.0380 88.2140 107.4865 i 63.4229 LW-3682,3683 Apr,1995 H-3 75.0378 88.2143 139.9353 1 91.1494 107.4865 i 63.4231 S O-3531, 3532 May,1995 Cs-137 0.1624 1 0.0246 0.1418 1 0.0306 0.1521 1 0.01 %
S O-3531, 3532 May,1995 Gr. Alpha 6.8662 3.5751 9.2164 i 3.8687 8.0413 i 2.6338 S O-3531, 3532 May,1995 Gr. Beta 17.0973 3.0829 18.8034 i 3.1329 17.9503 i 2.1977 S O-3531, 3532 May,1995 K-40 25.0380 1 0.7710 23.8180 1 0.6600 24.4280 t 0.5075 SOUS.M, 3532 May,1995 Sr-89 -0.0129 i 0.0215 0.0014 i 0.0202 -0.0057 1 0.0147 SO 3531,3532 May,1995 Sr-90 0.0261 1 0.0109 0.0122 i 0.0093 0.0191 1 0.0072 WW-3577, 3578 May,1995 Co-60 -0.2530 i 2.2200 0.5410 1 2.5800 0.1440 i 1.7018 WW-3577, 3578 May,1995 Cs-137 1.1500 1 2.2000 -1.6400 1 2.9200 -0.2450 1 1.8280 WW-3577, 3578 May,1995 H-3 33.5750 90.9827 58.7563 i 92.0487 46.1657 i 64.7125 MI-3598,3599 May,1995 1 131 0.2288 i 0.3515 0.2122 i 0.3043 0.2205 i 0.2324 MI-3598,3599 May,1995 K-40 1,349.0000 i 112.0000 1,297.4000 i 151.0000 1,323.2000 i 94.0013 j M1-3809,3810 May,1995 Co.60 -0.3700. 2.9600 0.1820 1 2.9600 -0.0940 1 2.0930 M1-3809,3810 May,1995 Cs-137 0.9060 2.5000 0.1380 i 2.3600 0.5220 i 1.7190 M1-3809,3810 May,1995 I-131 0.1445 1 0.1573 0.1738 1 0.2057 0.1592 i 0.1295 ) CW-3838, 3839 May,1995 Gr. Beta 1.9922 1.3549 3.4291 1 1.4650 2.7106 0.9977 l CW 3838,3839 May,1995 Gr. Beta -0.7347 1.2274 -1.0782 1.2004 -0.9064 0.85S4 F-4309, 4310 May,1995 Co-60 -0.0017 0.0093 0.0032 1 0.0166 -0.0024 0.0095 175 j
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sarnple First Second Averaged Codes
- Date Analysis Result Result Result F-4309,4310 May,1995 Cs-137 0.0028 i 0.0089 0.0012 i 0.0133 0.0020 i 0.0080 F-4288,4289 May,1995 Co-60 0.0038 i 0.0097 0.0012 i 0.0088 0.0025 i 0.0065 F-4288,4289 Nay,1995 Cs-137 0.0002 1 0.0067 0.0022 i 0.0062 0.0012 i 0.0045 F-4330,4331 May,1995 Co-60 0.0018 i 0.0046 0.0031 i 0.0050 0.0024 i 0.0034 F-4330,4331 May,1995 Cs-137 0.0001 1 0.0042 -0.0007 i 0.0038 -0.0003 i 0.0028 M1-4377,4378 May,1995 Co-60 0.9480 i 1.7400 2.2200 i 2.6600 1.5840 i 1.5893 MI-4377,4378 May,1995 Cs-134 0.7830 i l.4900 -0.2080 i 2.3000 0.2875 i 13702 MI-4377,4378 May,1995 Cs-137 0.8740 1 1.3800 0.6430 1 2.1400 0.7585 i 1.2732 M14377,4378 May,1995 I-131 -0.0785 1 0.1490 -0.0420 i 0.1498 -0.0602 1 0.1056 MI-4377,4378 May,1995 1-131(g) 0.1700 1 1.3000 -1.1200 1 2.6200 -0.4750 1 1.4624 M14377,4378 May,1995 K-40 1,385.1000 i 63.2000 1,344.3000 1 92.5000 1,364.7000 1 56.0145 MI-4377,4378 May,1995 Sr-89 -0.0069 i 0.7313 0.0069 1 1.1490 0.0000 1 0.6810 MI-4377,4378 May,1995 Sr-90 1.2729 1 0.4414 1 3 229 i 0.6414 1.2979 i 0.3893 MI-4544,4545 May,1995 I131 0.0524 1 0.2867 0.0574 1 0.2367 0.0549 i 0.1859 MI-4544,4545 May,1995 K-40 1,410.0000 1 723000 1,359.0000 1 65.7000 1,384.5000 i 48.8461 MI-4544,4545 May,1995 Sr-90 2.1444 1 0.5153 1.2741 i 0.4112 1.7093 1 0 3296 G-4604,4605 May,1995 Be-7 1.9338 1 0.3520 1.7467 i O 3580 1.8403 i 0.2510 j G-4604,4605 May,1995 Co-60 -0.0112 1 0.0217 -0.0175 1 0.0189 -0.0144 1 0.0144 G-4604,4605 May,1995 Cs-134 0.0076 1 0.0165 0.0079 i 0.0163 0.0078 i 0.0116 G4604,4605 May,1995 Cs-137 0.1303 1 0.0332 0.1283 i 0.0420 0.1293 i 0.0268 G4604,4605 May,1995 Gr.- Beta 3.9523 1 0.1425 3.9500 1 0.1562 3.9512 i 0.1057 )
G-4604,4605 May,1995 1-131(g) 0.0101 i 0.0227 0.0055 0.0263 0.0078 1 0.0174 l G-4601,4605 May,1995 K-40 5.1487 1 0.6580 5.1002 0.6970 5.1245 1 0.4793 CW-4575, 4576 May,1995 Gr. Beta 1.9783 1 1.1888 2.8278 1.2558 2.4030 1 0.8646 CW-4575, 4576 May,1995 Gr. Beta -0.2059 i 1.0000 -0.5589 i 0.9721 -0.3824 1 0.6973 MI-4695,4696 May,1995 1-131 0.1049 i 0.1737 0.0942 i 0.1607 0.0995 i 0.1183 MI-4695,4696 May,1995 K-40 1,568.8000 1 114.0000 1,573.1000 i 50.1000 1,570.9500 i 62.2616 MI4716,4717 May,1995 Sr-89 -0.2701 i 0.7584 -0.0499 i 0.8752 -0.1600 1 0.5790 MI-4716,4717 May,1995 Sr-90 1.1720 1 0.4391 1.6280 1 0.4432 1.4000 1 03119 4 G4814,4815 May,1995 Be-7 0.6081 1 0.2520 0.5837 1 0.1750 0.5959 i 0.1534 G-4814,4815 May,1995 K-40 5.8319 1 0.6100 5.1295 1 0.5050 5.4807 i 0 3960 WW-4784, 4785 May,1995 H-3 18,665 3086 1 390.2155 18,274.9314 1 3863294 18,470.1200 2745535 ! SW-4759, 4760 May,1995 H3 3,679.8217 1 213.9409 3,817.7847 217.0401 3,748.8032 1523787l S 0-5178, 5179 May,1995 Cs-137 0.8481 1 0.% 91 0.8110 0.0710 0.8296 1 0.0495 ' S O-5178, 5179 May,1995 K-40 19.9200 1 1.0800 22.0860 1.1800 21.0030 0.7998 i SWU-5663, 5664 May,1995 Gr. Beta 2.4654 1 0.6199 2.5106 0.6258 2.4880 1 0.4404 l 176
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-5. in-house " duplicate" samples. Concentration in pCi/I
- Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result SWU-5663, 5664 May,1995 H-3 867.2182 i 104.9067 865.5032 i 104.8506 8663607 i 74.1604 BS '- 6983,6984 May,1995 Gr. Beta 7.3555 1 1.2333 8.0347 1 1.4183 7.6951 i 0.9397 BS - 6983,6984 May,1995 Gr. Beta 7 3555 i l.2333 8.0347 1 1.4183 7.6951 i 0.9397 BS - 6983,6984 May,1995 K-40 83490* 03090 8.5309 i 0.0683 8.4400 i 0.1582 BS - 6983,6984 May,1995 K-40 83490i 03090 8.5309 i 0.0683 8.4400 i 0.1582 BS-6983, 6984 May,1995 Cs-137 0.0074 i 0.0008 0.0094 0.0024 0.0084 i 0.0013 BS-6983, 6984 May,1995 Gr. Beta 7.3555 i 1.2333 8.0347 i 1.4183 7.6951 i 0.9397 BS-6983, 6984 May,1995 K-40 83490i 03090 8.5309 i 0.0683 8.4400 i 0.1582 BS - 5494,5495 May,1995 Cs-137 0.5929 i 0.0319 0.5876 0.0378 0.5903 i 0.0247 BS - 5494,5495 May,1995 Cs-137 0.5929 i 0.0319 0.5876 0.0378 0.5903 i 0.0247 BS - 5494,5495 May,1995 K-40 21.0920 1 0.6570 21 3050 1 0.7070 21.1985 i 0.4826 BS - 5494,5495 May,1995 K-40 21.0920 i 0.6570 21.3050 0.7070 21.1985 1 0.4826 BS-5494, 5495 May,1995 Cs-137 0.5929 i 0.0319 0.5876 1 0.0378 0 5903 i 0.0247 BS-5494, 5495 May,1995 K-40 21.0920 1 0 6570 213050 1 0.7070 21.1985 i 0.4826 F-5025, SC26 May,1995 Co-60 0.0024 i 0.?)64 0.0028 0.0077 0.0026 1 0.0050 F-5023,5026 May,1995 Cs-137 -0.0006 i 0.1 50 -0.0038 0.0063 -0.0022 1 0.0040 F-5385,5386 May,1995 K-40 2.5044 i 0.3450 2.5992 1 0 3 830 2.5518 i 0.2577 F-5046,5047 May,1995 Co-60 0.0012 i 0.0067 -0.0021 0.0073 -0.0004 t o.0049 F-5046, 5047 May,1995 Cs-137 0.0018 1 0.0053 0.0003 0.0046 Om07i0.0035 WW-5244, 5245 May,1995 H-3 6083574 1 963200 463.5639 91.1176 535.9606 1 65.2947 SW-6013, 6014 May,1995 Co-60 0.8080 2.2000 1.5300 3.0300 1.1690 1 1.8722 SW-6013, 6014 May,1995 Cs-137 -0.6750 2.3000 0.4560 2.3200 -0.1095 1 1.6334 M1-5620,5621 May,1995 1-131 0.1589 0.1736 0.0147 0.1644 0.0868 i 0.11 %
M1-5620,5621 May,1995 K-40 1,526.2000 119.0000 1,449 3000 162.0000 1,487.7500 i 100.5050 WW - 5642,5643 May,1995 Gr. Alpha 231201 23250 23120 i 2.3250 23120 1 1.6440 WW - 5642,5643 May,1995 Gr. Beta 23120 1 3.2540 23120t 3.2540 231201 23009 WW - 5642,5643 May,1995 K-40 94.3550 i 19.8000 58.9910 1 29.5000 76.6730 i 17.7644 3.0383 1 0.8411 l DW-5738, 5739 May,1995 Gr. Beta 2.5151 1 1.1685 3.5614 1 1.2103 DW-5738, 5739 May,1995 1-131 -0.0458 i 0.1650 -0.0284 i 0.1486 -0.0371 1 0.1110 LW-6327, 6328 May,1995 Gr. Beta 6.4501 i 1.0293 6.6100 i 1.0327 6.5300 1 0.7290 W-6398, 6399 May,1995 Sr-89 15.1044 1 3.8169 18.1475 2.7239 16.62591 23446 W-6398, 6399 May,1995 Sr-90 25.0828 1 1.8532 24.4207 1 13058 24.7518 i 1.1335 WW-6184, 6185 Jun,1995 Gr. Beta 6.0148 i l.1147 7.4613 13560 6.7380 1 0.8777 WW-6184, 6185 Jun,1995 H3 86.1439 i 78 3469 106.9572 i 79.2631 96.5505 1 55.7245 MI.5684,5685 Jun,1995 Co-60 0.0976 2.9600 0.4260 4.6300 0.2618 2.7477 , M1-5684,5685 Jun,1995 Cs-137 1.8400 2.6500 -0.9210 3.2400 0.4595 1 2.0929 i l l 177 : J
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' l Lab Sample First Second Averaged ! Codes
- Date Analysis Result Result Result MI-5684,5685 Jun,1995 I-131 0.0829 1 0.1477 -0.0025 1 0.1466 0.0402 i 0.1041 :
CW-5713, 5714 Jun,1995 Gr. Beta 3.1068 i 1.4397 3.2557 i 1.4487 3.1812 1 1.0212 CW-5713,5714 Jun,1995 Gr. Beta 0.0491 i 1.4849 0.3925 i 1.5076 0 2208 i 1.0580 4 SL-5832,5833 Jun,1995 Co-60 0.0410 1 0.0114 0.0585 i 0.0182 0.0498 1 0.0107 SL-5832, 5833 Jun,1995 Cs-137 0.0550 1 0.0124 0.0499 i 0.0215 0.0525 i 0.0124 ! Sle5832,5833 Jun,1995 Gr. Beta 4.6800 i 0.4800 4.6800 1 0.4800 4.6800 i 0.3394 j Sle5832,5833 Jun,1995 K-40 2.9035 i 0.2750 2.4429 1 03290 2.6732 1 0.2144 i Sle5832,5833 Jun,1995 St-89 0.0106 1 0.0261 0.0048 0.0336 0.0077 1 0.0213 SL-5832, 5833 Jun,1995 Sr-90 0.0102 i 0.0114 0.0164 1 0.0148 0.0133 1 0.0093 l WW-5992, 5993 Jun,1995 Co-60 03950 1 1.2200 0.9060 1 2.6500 0.6505 i 1.4587 WW-5992, 5993 Jun,1995 Cs-137 -1.4000 i 1.3800 -1.4400 1 3.0300 -1.4200 i 1.6647 WW-5992, 5993 Jun,1995 H-3 67.0084 i 76.1576 94.0370 i 773473 80.5227 i 54.2738 Sle6205,6206 Jun,1995 Co.60 0.0029 i 0.0088 0.0111 i 0.0120 0.0070 i 0.0074 j SI 6205, 6206 Jun,1995 Cs-134 0.0033 1 0.0070 0.0002 1 0.0096 0.0018 1 0.0059 i SL-6205,6206 Jun,1995 Cs-137 0.0138 i 0.0091 0.0174 1 0.0104 0.0156 i 0.0069 j Sle6205,6206 Jun,1995 Gr. Beta 3 3400 1 0.1000 3.3400 1 0.1000 3.3400 i 0.0707 SL-6205, 6206 Jun,1995 1-131(g) -0.0060 1 0.0135 -0.0003 1 0.0197 -0.0031 1 0.0119 SL-6205, 6206 Jun,1995 K-40 33386i 03100 33294 03780 3 3340 i 0.2444 SW-6256, 6257 Jun,1995 H-3 423.9034 i 92.0134 585.0329 i 97.8935 504.4682 i 67.1744 M1-6277, 6278 Jun,1995 1-131 0.0926 1 0.1619 0.0532 0.2284 0.0729 i 0.1400 M1-6277, 6278 Jun,1995 K-40 1,285.5000 1 152.0000 1,355.2000 i 114.0000 1,320 3500 i 95.0000 SW-6232, 6233 Jun,1995 H-3 68.3732 i 79.4680 136.7465 i 82.4296 102.5599 i 57.2490 VE-6348, 6349 Jun,1995 Gr. Alpha 03230 1 0.0990 0.1780 0.0520 0.2505 1 0.0559 VE-6348, 6349 Jun,1995 Gr. Beta 3.2970 i 0.1410 3.4170 0.0920 3 3570 1 0.0842 VE-6348, 6349 Jun,1995 K-40 3.1425 1 0 3310 2.9775 1 0 3350 3.0600 i 0.2355 l MI-6419,6420 Jun1995 1131 0.1154 1 0.1633 0.1197 1 0.1806 0.1175 i 0.1217 MI-6419,6420 Jun1995 K-40 1,457.2000 1 175.0000 1,339.3000 1 150.0000 1,398.2500 1 115.2443) MI-6521,6522 Jun,1995 1-131 0.0534 1 0.1511 0.0344 1 0.1784 0.0439 i 0.1169 M1-6521,6522 Jun1995 K-40 1,^75.40001123.0000 1,274.6000 1 160.0000 1,375.0000 i 100.9071i Sle6500,6501 Jun,1995 K-40 1.8001 1 0.4550 2.1667 1 0.5460 1.9834 1 03554 , MI-6446, 6447 Jun,1995 Co-60 0.1640f 4.8700 0.4440 1 2.8200 0.3040 1 2.8138 Mi-6446, 6447 Jun,1995 Cs-137 130001 33600 0.0563 i 2.1800 0.6782 1 2.0026 Ml-6446, 6447 Jun,1995 1-131 -0.043310.7J77 0.0000 1 0.2377 -0.0217 i 0.1578 CW-6474, 6475 Jun,1995 Gr. Beta 2.8423 i 1.4039 3.1674 1.4145 3.0049 1 0.9965 CW-6474, 6475 Jun.1995 Gr. Beta 0.0000 1.1519 0.0909 1.1588 0.M5510.8170 Mi-6564, 6565 Jun1995 1131 0.24603 0.2607 0.0948 0.2353 0.1704 i 0.1756 178
Davis-Besse Nuclear Powcr Station 1995 Annual Radiological Environmental Operating Report f Table A-5. In-house " duplicate" samples. l Concentration in pCi/I' Lab Sample First Second Averaged l Codes? Date Analysis Result Result Result BS-6960, 696 Jun,1995 Cs-137 0.0752 1 0.0292 0.0475 i 0.0274 0.0613 i 0.0200 l BS4960,6961 Jun,1995 K-40 17.6680 i 0.8700 17.0190 i 1.0600 173435 i 0.6857 WW-6861, 6862 Jun,1995 H-3 1,422.4460 i 128.0232 1,505.1361 i 130.2761 1,463.7910 i 91.3261 MI-6840,6841 Jun,1995 I-131 0.1583 i 0.2131 0.0509 i 0.1801 0.1046 1 0.1395 LW-6889,6890 Jun,1995 Co-60 -2.4000 1 3.4100 1.4300 i 1.7400 -0.4850 i 1.9141 LW-6889, 6890 Jun,1995 Cs-137 -0.5210 i 3.0300 0.1410 i 2.1900 -0.1900 i 1.8693 LW-6889, 6890 Jun,1995 Gr. Beta 3.0131 i 0.8315 3.0285 1 0.8358 ~;.0208i03895 SW-7053, 7054 Jun,1995 H-3 73.2226 i 75.6858 126.8001 78.1734 100.0114 i 54.4046 SW-7011, 7012 Jun,1995 H-3 203.5633 i 81.5943 226.7766 82.6041 215.1699 i 58.0540 MI-7032,7033 Jun,1995 I-131 0.2720 1 0.2879 -0.0925 1 0.2629 0.0897 i 0.1949 MI-7032,7033 Jun,1995 K-40 1,577.6000 i 127.0000 1,522.8000 i 164.0000 1,550.2000 i 103.7123 SWU-7101, 7102 Jun,1995 Gr. Beta 1.9679 i 0.4592 2.1339 i 0.5061 2.0509 i 03417 SWU-7101, 7102 Jun,1995 H3 118.5873 1 85.7967 92.6463 1 84.6688 105.6168 1 60.2700 SWU - 7828,7829 Jun,1995 Sr-89 0.5896 i 0.7987 0.0977 i 0.6691 03436i 05210 SWU - 7828,7829 Jun,1995 Sr-90 0.2398 i 0.3028 0.1937 i 0.2742 0.2168 1 0.2042 SWU - 7828,7829 Jun,1995 Sr-90 0.2398 i 03028 0.1937 1 0.2742 0.2168 i 0.2042 SWU-7828, 7829 Jun,1995 Sr-89 0.5896 1 0.7987 0.0977 1 0.6691 03436 i 0.5210 SWU-7828, 7829 Jun,1995 Sr-89 0.5896 i 0.7987 0.0977 1 0.6691 0 3436 i 0.5210 SWU-7828, 7829 Jun,1995 Sr-89 0 5896 1 0.7987 0.0977 1 0.6691 03436i 03210 SWU-7828, 7829 Jun,1995 Sr-89 0.5896 i 0.7987 0.0977 1 0.6691 0 3436 i 0.5210 SWU-7828, 7829 Jun,1995 Sr-90 01398 03028 0.1937 0.2742 0.2168 i 0.2042 l SWU-7828, 7829 Jun,1995 Sr-90 0.2398 i O3028 0.1937 i 0.2742 0.2168 1 0.2042 SWU-7828, 7829 Jun,1995 Sr-90 0.2398 1 03028 0.1937 0.2742 0.2168 1 0.2042 SWU-7828, 7829 Jun,1995 Sr-90 0.2398 i 03028 0.1937 1 0.2742 0.2168 1 0.2042 AP-8111,8112 Jun,1995 Co-60 -0.0002 i 0.0007 0.0004 1 0.0007 0.0001 i 0.0005 AP-8111,8112 Jun,1995 Cs-137 -0.0002 i 0.0007 0.0004 i 0.0005 ').0001 1 0.0004 SW-7080, 7081 Jun,1995 Gr. Beta 23011 1 0.5921 2.6708 1 0.6113 2.4860 1 0.4255 SW-7080, 7081 Jun,1995 K-40 61.2620
- 28 3000 95.4390 i 26.0000 78.3505 i 19.2152 WWT-7122, 7123 Jun,1995 H3 3.8386 i 81.4299 -13.4353 i 80.6115 -4.7983 i 57.2910 LW-7239, 7240 Jun,1995 Gr. Beta 2.5177 i 0.0580 2.4081 i 0.6061 2.4629 i 0.3044 WW-7143, 7144 Jun,1995 H-3 539.1386 i 1033228 436.4159 i 99.5398 487.7772 i 71.7352 PW-7)74, 7175 Jun,1995 H-3 144.0732 1 81.2861 121.4242 83.2655 132.7487t S92395 i
SW-7216, 7217 Jun,1995 H-3 203728 i 81.4069 62.9704 i 83 3227 41.6716 i 58.2446 l WW-7281, 7282 Jun,1995 Gr. Beta 1.8051 i 0 3271 2.1056 1 0.5796 1.9553 i 0 3328 L WW-7281, 7282 Jun1995 H3 -243250 1 75.1716 103381 76.8357 -6.9934 1 53.7459 SW-7387, 7388 Jul,1995 Co-60 1.0200 1 1.9000 0.1530 1.6700 0.5865 1.2648 179
. . - _ - . - _ _ . . . _ - - . - - . - - - -. . __ _~. .. Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmeatal Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result SW-7387, 7388 Jul,1995 Cs-137 0.5600 i 23400 -0.8650 i 2.0400 -0.1525 t l.5522 :
AP-8133,8134 Jul,1995 Co-60 -0.0000 1 0.0005 0.0003 i 0.0006 0.0001 i 0.0004 AP-8133,8134 J41995 Cs-137 -0.0001 1 0.0004 0.0000 1 0.0005 -0.0001 i 0.0003 AP-7600,7601 Jul,1995 Sr-89 0.0008 1 0.0008 0.0010 i 0.0008 0.0009 i 0.0005 AP-7600,7601 J41995 Sr-90 -0.0001 i 0.0003 0.0005 i 0.0003 0.0002 i 0.0002 MI-7260,7261 Jul,1995 Co-60 0 3390 1 2.9100 0.5630 i 5.2400 0.4510 1 2.9969 MI-7260,7261 Jul,1995 Cs-137 L660012.5900 -1.4600 i 3.3700 0 1000 1 2.1251 MI-7260,7261 Jul,1995 1-131 0.1745 i 0.1944 0.1004 i 0.1792 0.1374 i 0.1322 WW-7454, 7455 Jul,1995 11-3 7,142.7529 i 243.6211 6,985.4236 1 241.2186 7,064.0882 171.4188 LW - 7487,7488 J41995 K-40 48.0000 1 14.4000 95.7520 i 39.9000 71.8760 1 21.2095 LW - 7487,7488 J41995 K-40 48.0000 1 14.4000 95.7520 1 39.9000 71.8760 1 21.2095 LW-7487, 7488 Jul,1995 CM0 0.4460 1 1.0700 0.3830 i 3.0000 0.4145 i 1 5926 LW-7487, 7488 Jul,1995 Cs-134 0.1230 i 1.0600 -2.3900 i 3.0100 -1.1335 i 1.5956 LW-7487, 7488 J4 1995 Cs-137 0.4920 1 1.1000 -2.2200 1 2.8400 -0.8640 1 1.5228 ; LW-7487, 7488 Jul,1995 Gr. Beta 2.1095 i 0.4725 1.8520 1 0.4810 1.9807* 03371 LW-7487, 7488 Jul,1995 I-131 0.2323 1 0.2677 -0.0343 1 0.2508 0.0990 i 0.1834 LW-7487, 7488 Jul,1995 l-131(g) 0 3390 i 2.4400 0.9230 i 10.5000 0.6310 i 5 3899 LW-7487, 7488 Jul,1995 K-40 48.0000 1 14.4000 95.7520 i 39.9000 71.8760 i 21.2095 LW-7487, 7488 Jul,1995 K-40 48.0000 1 14.4000 95.7520 1 39.9000 71.8760 i 21 3095 LW-7487,7488 Jul,1995 K-40 48.0000 i 14.4000 95.7520 1 39.9000 71.8760 i 212095 LW-7487, 7488 Jul,1995 K'-40 48.0000 1 14.4000 95.7520 39.9000 71.8760 1 21.2095 SW-7323, 7324 Jul,1995 Gr. Deta 23 224 1 0.7511 2.5774 i 0.7631 2.4499 i 0.5354 SW-7323, 7324 Jul,1995 H-3 77.8879 1 83.9931 48.4345 1 82.6045 63.1612 1 58.9032 F-7366,7367 Jul,1995 Co-60 0.0092 i 0.0141 0.0061 1 0.0119 0.0076 i 0.0092 F-7366,7367 Jul,1995 Cs-137 0.0115 i 0.0108 0.0019 0.0111 0.0067 i 0.0077 MI7510,7511 J A 1995 1131 034431 03987 0.1361 1 0.3508 0.2402 1 0.2655 ) F-7344,7345 Jul,1995 Co-60 0.0037 1 0.0077 -0.0071 1 0.0119 -0.0017 1 0.0071 F-7344,7345 Jul,1995 Cs-137 0.0023 1 0.0057 0.0024 i 0.0097 0.0023 i 0.0056 MI-7429,7430 Jul,1995 1131 -0.1525 i 03171 0.1594 1 0.2283 0.0035 i 0.1953 F-8154,8155 J41995 Gr. Beta 23081 1 0.0743 2.2522 1 0.0730 2.2802 1 0.0521 F-8154,8155 J4 1995 K-40 2.2313 i 0.2640 2.1161 i 0.4420 2.1737 i 0.2574 MI 7575,7576 J4 1995 Co-60 -1.0000 i 2.8600 1.6000 1 3.1700 0 3000 1 2.1347 Ml-7575,7576 Jul,1995 Cs-134 1.7300 1 2.4200 -0.6220 i 2.3600 0.5540 i 1.6901 MI-7575,7576 Jul 1995 Cs.137 -0.7550 2.5100 1.2800 1 2 3800 0.2625 1.7295 M!-7575,7576 Jul,1995 I-131 0.1795 1 0.2309 0.0704 i 0.2260 0.1250 1 0.1616 M1-7575,7576 Jul,1995 I-131(g) 0.8570 2.2400 0.8540 2.4400 0.8555 1.6561 1 180 l
Davis-Besse Nuclear Power Stition 1995 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 MI-7575,7576 J4 1995 K-40 1,481.9000 i 111.0000 1,398.8000 i 106.0000 1,440.3500 i 76.7414 MI-7575,7576 J41995 Sr-89 0.6192 i 0.9862 -0.5435 0.9244 0.0378 1 0.6758 MI-7575,7576 Jul,1995 Sr-90 1.2363 1 0.4155 1.7902 i 0.4124 1.5133 i 0.2927 WWT-7621,7622 Jul,1995 I-131 0.0940 i 0.2062 0.0628 i 0.2223 0.0784 i 0.1516 MI-7739,7740 Jul,'1995 Co-60 0.8900 i 4.9100 -0.5720 i 4.5800 0.1590 t 3.3572 MI-7739,7740 Jul,1995 Cs-137 0.8600 i 3.7300 -0.4130 i 3.1400 0.2235 i 2.4379 MI-7739,7740 Jul,1995 I-131 0.1928 i 0.2674 -0.0475 0.2351 0.0727 i 0.1780 G-7805,7806 Jul,1995 Co-60 -0.0049 i 0.0159 0.0015 0.0156 -0.0017 i 0.0111 G-7805,7806 Jul,1995 Cs-134 -0.0076 1 0.0157 0.0025 i 0.0094 -0.0025 i 0.0091 G-7805,7806 Jul,1995 Cs-137 0.0045 1 0.0140 0.0006 1 0.0118 0.0026 i 0.0092 G-7805,7806 Jul, I')95 Gr. Beta 5.0973 i 0.1994 5.1127 i 0.2103 5.1050 i 0.1449 G-7805,7806 Jul,1995 I-131(g) -0.0048 i 0.0205 -0.0183 1 0.0205 -0.0115 i 0.0145 G-7805,7806 J4 1995 K-40 6.0481 1 0.5610 5.8484 0.5100 5.9483 i 0.3791 CW-7648, 7649 Jul,1995 Gr. Beta 6.6883 1 1.7265 6.7478 i 1.7419 6.7181 i 1.2263 CW-7648,7649 Jul,1995 Gr. Beta 0.7444i1.2623 0.2325 1 1.2230 0.4885 i 0.8788 CW-7648, 7649 Jul,1995 H-3 -64.4182 i 97.4643 -70.1870 97.2364 -67.3026 1 68.8371 WW-7673, 7674 Jul,1995 Gr. Beta 14.1451 1 2.2254 ' 14.2212 2.2315 14.1831 i 1.5757 WW-7673, 7674 Jul,1995 H-3 15.3145 i 81.7571 36.3720 82.7373 25.8432 i 58.1586 MI-78%,7897 Jul,1995 Sr-89 0.3508 0.9697 0.1856 i 0.8702 0.2682 i 0.6514 MI-7896 7897 J4 1995 Sr-90 1.7110 0.4271 1.2961 i 0.3929 1.5036 i 0.2902 WW-7967, 7968 Jul,1995 H-3 109.4679 i 84.6270 70.8322 1 82.8444 90.1500 t 59.2134 MI-7922,7923 J41995 Co-60 0.5680 3.1300 -1.0500 4.4600 -0.2410 1 2.7244 Mi-7922,7923 J41995 Cs-137 1.2100 2.8600 -0.5040 3.4200 0.3530 1 2.2291 MI 7922,7923 J41995 1-131 0.0502 1 0.1932 0.0416 0.2336 0.0459 i 0.1516 LW-7944, 7945 Jul,1995 Co-60 0.0830 1 2.2000 1.3000 i 1.8900 0.6915 i 1.4502 LW-7944, 7945 Jul,1995 Cs-137 0.6400 1 2.2200 -1.3800 1.8200 -0.3700 i 1.4353 LW-7944, 7945 Jul,1995 Gr. Beta 4.1332 1 0.9251 3.9971 i 0.9393 4.0652 1 0.6592 SW-8704, 8705 J41995 CMC 0.1830 1 2.4900 0.9840 i 1.7900 0.5835 i 1.5333 SW-8704, 8705 J41995 Cs-137 0.2640 i 3.4500 -0.6630 1.9100 -0.1995 i 1.9717 WW-8196, 8197 Jul,1995 H3 51.4226 i 87.9172 176.0234 i 93.3551 113.7230 i 64.1183 SWU-8318, 8319 J4 1995 Cr. Beta 1.9584 1 0.4714 1.9228 0.4731 '
1.9406 1 0.3340 SWU-8318, 8319 Jul,1995 H-3 102.7030 103.6806 35.5141 101.1620 69.1086 i 72.4283 SWU-8318, 8319 Jul,1995 K-40 93.2530 39.7000 99.7420 49.1000 96.4975 31.5710 SP-8540, 8541 Jul,1995 Gr. Alpha 5.1903 1.3072 3.8567 1.0701 4.5235 1 0.8447 SP-8540, 8541 Jul,1995 Sr-89 1,443.0886 1 42.0809 1,419.4750 35.3491 1,431.2818 1 27.4789 SP-8540, 8541 Jul,1995 Sr-90 15.7496 1 3.7553 19.4328 4.1309 17.5912 2.7914 181 _ ________ a
l Davis-B:sse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' 2 Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result VE-8090,8091 Jul,1995 Gr. Beta 2.3819 i 0.0781 2.3059 i 0.0779 2.3439 i 0.0552 !
VE-8090,8091 Jul,1995 K-40 2.8208 i 0.1170 2.7639 i 0.1330 2.7924 i 0.0886
]
SW-8175,8176 Jul,1995 Gr. Alpha 0.5000 i 0.6000 0.6583 i 0.8198 0.5791 i 0.5080 l 4 SW-8175, 8176 Jul,1995 Gr. Beta 0.8100 i l.1000 0.8265 i l.0847 0.8182t 0.7724 SW-8175,8176 Jul,1995 K-40 89.8150 i 23.8000 67.3590 1 39.3000 78.5870 i 22.9724 SW-8251, 8252 Ju!,1995 H-3 86.7952 i 78.8856 43.9921 1 76.9259 65.3937 i 55.0921 SW-8606, 8607 Jul,1995 Co-60 0.1320 1 1.7100 -0.2180 1 2.6000 -0.0430 i 1.5560 SW 8606,8607 Jul,1995 Cs-137 -1.0400 i 2.0400 -0.6580 1 2.2400 -0.8490 i 1.5149 G - 8272,8273 Aug,1995 K-40 6.7487 1 0.6490 6.6636 i 0.9730 6.7062 i 0.5848 G - 8272,8273 Aug,1995 Sr-89 0.0014 i 0.0091 -0.0007 i 0.0029 0.0004 i 0.0048 G - 8272,8273 Aug,1995 Sr-90 0.0053 i 0.0029 0.0016 i 0.0012 0.0034 i 0.0016 G-8272,8273 Aug,1995 Gr. Beta 6.2167 1 0.2594 5.9667 1 0.2551 6.0917 i 0.1819 MI-8293,8294 Aug,1995 I-131 -0.1058 i 0.1908 0.0093 1 0.2009 -0.0483 i 0.1385 Mi-8389,8390 Aug,1995 I-131 -0.0127 1 0.1267 0.1153 1 0.1318 0.0513 i 0.0914 MI-8389,8390 Aug,1995 K-40 1,543.8000 i 120.0000 1,369.6000 1 162.0000 1,456.7000 1 100.8018 M1-8413,8414 Aug,1995 Co-60 0.2940 1 3.1400 -2.3500 i 5.2200 -1.0280 1 3.0458 MI-8413,8414 Aug,1995 Cs-137 -0.7370 2.8900 -1.3600 3.3100 -1.0485 1 2.1971 Mi-8413,8414 Aug,1995 I-131 0.1142 1 0.2124 0.0598 0.2344 0.0870 1 0.1581 LW-8440, 8441 Aug,1995 Co-60 0.1030 2.3800 1.0300 1 1.8100 0.5665 1 1.4950 LW-8440, 8441 Aug,1995 Cs-137 0.7760 1.9900 -0.3890 1 2.0500 0.1935 1 1.4285 LW-8440, 8441 Aug,1995 Gr.' Beta 3.3064 i 1.1388 4.6623 i 1.2154 3.9844 i 0.8327 WW-8518, 8519 Aug,1995 Co-60 1.4700 3.1400 -1.8100 i 2.9800 -0.1700 i 2.1645 WW-8518, 8519 Aug,1995 Cs-137 1.7100 1 2.8700 0.4430 2.7700 1.0765 1 1.9944 WW-8518, 8519 Aug,1995 H-3 10.6795 1 74.0469 -19.5791 72.5777 -4.4498 1 51.8422 VE-8564,8565 Aug,1995 Co.60 0.0053 1 0.0122 0.0054 1 0.0128 0.0053 1 0.0088 VE-8564,8565 Aug,1995 Cs-137 0.0038 1 0.0093 -0.0003 1 0.0082 0.0018 i 0.0062 MI-8585,8586 Aug,1995 Co-60 -0.4810 1 4.0600 1.8800 1 2.5900 0.6995 1 2.4079 MI-8585,8586 Aug,1995 Cs-134 0.1220 1 3.5000 0.9370 1 2.2700 0.5295 t 2.0858 MI-8585,8566 Aug,1995 Cs-137 1.7700 1 3.6400 0.2160 i 2.0700 0.9930 1 2 0937 MI-8585,8586 Aug,1995 I-131 -0.2002 1 0.2079 0.0732 i 0.1900 -0.0635 i 0.1408 MI-8585,8586 Aug,1995 I-131(g) 0.1360 1 9.0300 2.4300 i 6.8100 1.2830 1 5.6550 MI-8585,8586 Aug,1995 K-40 1,454.6000 1 150.0000 1,478.2000 1 104.0000 1,466.4000 1 91.2634 MI-8585,8586 Aug,1995 Sr-89 0.1158 1 1.1111 -0.0833 0.9491 0.0162 i 0.7306 Mi-8585,8586 Aug,1995 Sr-90 1.9078 1 0.4296 1.6029 1 0.3807 1.7553 1 0.2870 , M1-8674,8675 Aug,1995 Co-60 -0.7910 1 3.2300 0.4890 1 3.3400 -0.1510 1 2.3232 ; MI.8674,8675 Aug,1995 Cs-137 0.7690 2.4300 0.4160 2.4000 0.5925 1 1.7077 182
=__ _ ._ ._ _ . . - _ . . _ _ _ _ . _ _ _ _ _ _ _ _ . . . _ _ . _ _ _ . _ _ _ . _ _ _ _ Davis-Besse Nuclear Power Station 1995 - Annual Radiological Environmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' l Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result MI-8674,8675 Aug,1995 I-131 0.1471 i 0.2525 -0.0869 i 0.2167 0.0301 i 0.1664 SW-8648,8649 Aug,1995 H-3 35.5546 i 75.1429 '
21 3328 i 74.4670 28.4437
- 52.8956 F-8754,8755 Aug,1995 Co-60 0.0009 i 0.0110 0.0031 i 0.0106 0.0020 i 0.0076 P-8754,8755 Aug,1995 Cs-134 -0.0026 i 0.0090 -0.0022 i 0.0087 -0.0024 i 0.0063 F-8754,8755 Aug,1995 Cs-137 0.0528 i 0.0207 0.0563 i 0.0171 0.0546 i 0.0134 F-8754,8755 Aug,1995 Gr. Beta 13.1178 i 03041 12.6488 i 0.2780 12.8833 i 0.2060 F-8754,8755 Aug,1995 1-131(g) 0.0026 i 0.0139 0.0013 i 0.012) 0.0019 i 0.0092 F-8754,8755 Aug,1995 K-40 2.8119 i 0 3670 3.2605 i 0.3670 3.0362 i 0.2595 VE-8946,8947 Aug,1995 Gr. Alpha 0.2000 1 0.0800 0.2018 i 0.0786 0.2009 i 0.0561 -
VE-8946,8947 . Aug,1995 Gr. Beta 43000 0.1500 4.3179 i 0.1511 43089 1 0.1065 VE-8946,8947 Aug,1995 K-40 3.9615 i 0.2670 4.0418 i 0 3300 4.0017 i 0.2122
' VE - 8802,8803 Aug,1995 Sr-89 -0.0001 1 0.0018 -0.0004 1 0.0022 -0.0002 i 0.0014 VE - 8802,8803 Aug,1995 Sr-90 0.0011 i 0.0006 0.0013 1 0.0007 0.0012 i 0.0005 VE-8802,8803 Aug,1995 K-40 23052 i 0.2360 2.3039 i 0.3070 23046 i 0.1936 MI-8845,8846 Aug,1995 I131 0.0098 i 0.1785 0.0835 i 0.1740 0.0467 i 0.1246 CW-8873, 8874 Aug,1995 Gr. Beta 1.8586 i 1.3992 4.2592 i 1.5511 3.0589 i l.0445 CW-8873, 8874 Aug,1995 Gr. Beta -0.6043 1.1348 -0.0465 i 1.1799 -0 3254 1 0.8185 MI-8902,8903 Aug,1995 I131 -0.0387 0.2325 0.1320 i 0.3198 0.0466 i 0.1977 VE-9035,9036 Aug,1995 K-40 2.1934 i 0.2790 2.3847 i 03380 2.2891 1 0.2191 SW-9056, 9057 Aug,1995 H3 140.7425 i 79.5937 55.2281 i 75.6687 97.9853 i 54.9111 M1-9113,9114 Aug,1995 1-l'31 0.2205 03289 0.2711 1 0.2835 0.2458 i 0.2171 LW-9079,9080 Aug,1995 Co-60 0.84101 2.8400 0.1630 i 2.9900 0.5020 1 2.0619 LW-9079,9080 Aug,1995 Cs-137 0.7700 2.7700 -0.5330 1 2.6700 0.1185 1 1.9237 LW-9079, 9080 Aug,1995 Gr. Beta 2.7566 0.8607 2.6 % 1 i 0.8549 2.7264 1 0.6065 SW-9183, 9184 Aug,1995 Co-60 -03280 i 3.0000 2.2200 i 4.0400 0.9460 i 2.5160 SW-9183, 9184 Aug,1995 Cs-137 0.8200 1 3.4400 l 0.2580 i 4 3700 0.5390 1 2.7808 SWU-9162, 9163 Aug,1995 Gr. Beta 2.5000 1 0.5000 2.5094 i 0.5480 2.5047 1 03709 SWU-9162,9163 Aug,1995 H-3 152.0000 i 88.0000 157.4341 i 83.7394 154.7170 i 60.7377 !
WW-9276, 9277 Aug,1995 H3 1,636.0299 i 130.9904 1,680.8118 i 132.2095 1,658.4209 i 93.0562 l VE-9210,9211 Aug,1995 Gr. Beta 4.1000 1 0.2000 4.0920 i 0.1675 4.0960 1 0.1304 VE-9210,9211 Aug,1995 K-40 4.6449 i 0.1090 4.6203 1 0.1150 4.6326 i 0.0792 l DW-9371, 9372 Aug,1995 Gr. Beta 4.9900 1 1.1960 4.5327 i 1.1679 4.7613 i 0.8358 : DW-9371, 9372 Aug,1995 I-131 .0.1312 0.2093 0.1381 1 0.1 % 1 0.1346 i 0.1434 l MI-9297,9298 Aug,1995 I131 0.0434 i 0.1996 0.0510 i 0.2134 0.0472 i 0.1461 M1-9297,9298 Aug,1995 K-40 1,727.8000 180.0000 1,602.7000 1 172.0000 1,665.2500 1 124.4829 i WW-9252, 9253 Sep,1995 H3 530.8948 98.~085 538.0449 98.9671 534.4698 i 69.8889 l 183
1 Davis.Besse Nuclear Power Station 1995 Annual Radiolc,gical Environm. ental Operating Report Table A-5. In-house duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result SW-7387, 7388 Jul1995 Cs-137 0.5600 1 23400 -0.8650 i 2.0400 -0.1525 1 1.5522 AP-8133,8134 Jul,1995 Co-60 -0.0000 i 0.0005 0.0003 i 0.0006 0.0001 i 0.0004 AP-8133,8134 J4 1995 Cs-137 -0.0001 i 0.0004 0.0000 1 0.0005 -0.0001 i 0.0003 AP-7600,7601 Jul1995 Sr-89 0.0008 i 0.0008 0.0010 i 0.0008 0.0009 i 0.0005 AP-7600,7601 Jul,1995 Sr-90 -0.0001 1 0.0003 0.0005 i 0.0003 0.0002 i 0.0002 MI-7260,7261 Jul,1995 Co-60 0.3390 1 2.9100 0.5630 1 5.2400 0.4510 i 2.9969 MI-7260,7261 Jul1995 Cs-137 1.6600 i 2.5900 -1.4600 i 3 3700 0.1000 i 2.1251 MI-7260,7261 Jul,1995 I-131 0.1745 i 0.1944 0.1004 i 0.1792 0.1374 i 0.1322 l
WW-7454, 7455 Jul,1995 H-3 7,142.7529 i 243.6211 6,985.4236 i 241.2186 7;064.0882 i l71.4188 ' LW - 7487,7488 Jul,1995 K-40 48.0000 i 14.4000 95.7520 39.9000 71.8760i2L2095 LW - 7487,7488 Jul,1995 K-40 48.0000 i 14.4000 95.7520 1 39.9000 71.8760 i 21 2095 LW-7487,7488 Jul,1995 CM0 0.4460 i 1.0700 0 3830 i 3.0000 0.4145i t.5926 LW-7487, 7488 Jut 1995 Cs-134 0.1230 i l.0600 -2.3900 1 3.0100 -1.1335 t l.5956 LW-7487, 7488 Jul,1995 Cs-137 0.4920 1 1.1000 -2.2200 1 2.8400 -0.86401 1.5228 LW-7487, 7488 Jul,1995 Gr. Beta 2.1095 i 0.4725 1.8520 i 0.4810 1.9807 i 0 3371 LW-7487, 7488 Jul,1995 1-131 0.2323 1 0.2677 -0.0343 i 0.2508 0.0990 1 0.1834 LW-7487, 7488 Jul,1995 I-131(g) 033901 2.4400 0.9230 1 10.5000 0.6310 i 5 3899 LW-7487, 7188 Jul1995 K-40 48.0000 i 14.4000 95.7520 39.9000 71.8760 i 21.2095 LW-7487, 7488 Jul,1995 K-40 48.0000 1 14.4000 95.7520 1 39.9000 71.8760 i 21.2095 LW-7487, 7488 Jul,1995 K-40 48.0000 i 14.4000 95.7520 39.9000 71.8760 i 21.2095 LW-7487, 7488 Jul,1995 K'-4 0 48.0000 i 14.4000 95.7520 39.9000 71.8760 i 21.2095 SW-7323, 7324 Jul,1995 Gr. Beta 2.3224 i 0.7511 2.5774 0.7631 2.4499 i 0.5354 SW-7323, 7324 Jul,1995 H-3 77.8879 83.9931 48.4345 1 82.6045 63.1612 1 58.9032 F-7366, 7367 J4 1995 CM0 0.0092 1 0.0141 0.0061 1 0.0119 0.0076 i 0.0092 F-7366, 7367 Jul,1995 Cs-137 0.0115 i 0.0108 0.0019 i 0.0111 0.0067 i 0.0077 MI-7510,7511 Jul1995 1-131 0.3443 i 0 3987 0.1361 i 0 3508 0.2402 i 0.2655 F-7344, 7345 Jul,1995 Co-60 0.0037 i 0.0077 -0.0071 i 0.0119 -0.0017 i 0.0071 F-7344,7345 Jul,1995 Cs-137 0.0023 i 0.0057 0.0024 i 0.0097 0.0023 i 0.0056 MI-7429,7430 JuL1995 I-131 -0.1525 i 0 3171 0.1594 i 0.2283 0.0035 i 0.1953 j F-8154,8155 Jul,1995 Gr. Beta 23081 1 0.0743 2.2522 1 0.0730 2.2802 1 0.0521 F-8154,8155 Jul,1995 K-40 2.2313 1 0.2640 2.1161 1 0.4420 2.1737 i 0.2574 , MI-7575,7576 Jut 1995 Co-60 -1.0000 i 2.8600 1.6000 i 3.1700 03000 1 2.1347 M1-7575,7576 Jul,1995 Cs-134 1.7300 1 2.4200 -0.6220 2.3600 0.5540 i 1.6901 Ml-7575,7576 Jul,1995 Cs-137 -0.7550 1 2.5100 1.2800 1 2.3800 0.2625 1.7295 Ml-7575,7576 Jul,1995 I-131 0.1795 i 0.2309 0.0704 i 0.2260 0.1250 1 0.1616 MI-7575,7576 Jul,1995 1131(g) 0.8570 2.2400 0.8540 1 2.4400 0.8555 1 1.6561 180 l
_ _ - _ _ - _ _ _ _ . . __ _ _ _ - _ _ _ _ . __ _ . _ . _ _ = _ _ _ _ _ - _ _- - - ___-_ - _ _ _ Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report 1 Table A-5. In-house " duplicate" samples. Conc ?ntration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result MI-7575,7576 Jul,1995 K-40 1,481.9000 i 111.0000 1,398.8000 i 106.0000 1,440.3500 i 76.7414 MI-7575,7576 Jul,1995 St-89 0.6192 1 0.9862 -0.5435 i 0.9244 0.0378 1 0.6758 MI-7575,7576 Jul,1995 St-90 1.2363 i 0.4155 1.7902 1 0.4124 1.5133 1 0.2927 WWT-7621,7622 Jul,1995 I-131 0.0940 i 0.2062 0.0628 1 0.2223 0.0784 i 0.1516 MI-7739,7740 Jul,~1995 CW 0.8900 i 4.9100 -0.5720 i 4.5800 0.1590 i 3.3572 MI-7739,7740 Jul,1995 Cs-137 0.8600 i 3.7300 -0.4130 t 3.1400 0.2235 i 2.4379 M1-7739,7740 Jul,1995 1-131 0.1928 i 0.2674 -0.0475 i 0.2351 0.0727 i 0.1780 G-7805,7806 Jul,1995 Co-60 -0.0049 i 0.0159 0.0015 0.0156 -0.0017 i 0.0111 G-7805,7806 Jul,1995 Cs-134 -0.0076 i 0.0157 0.0025 i 0.0094 -0.0025 i 0.0091 G-7805,7806 Jul,1995 Cs-137 0.0045 1 0.0140 0.0006 0.0118 0.0026 i 0.0092 G-7805,7806 Jul,1995 Gr. Beta 5.0973 i 0.1994 5.1127 0.2103 5.1050 1 0.1449 G-7805,7806 Jul,1995 I-131(g) -0.0048 i 0.0205 -0.0183 i 0.0205 -0.0115 i 0.0145 G-7805,7806 Jul,1995 K-40 6.0481 i 0.5610 5.8484 0.5100 5.9483 i 0.3791 CW-7648, 7649 Jul,1995 Gr. Beta 6.6883 i 1.7265 6.7478 1 1.7419 6.7181 1 1.2263 CW-7648,7649 Jul,1995 Gr. Beta 0.7444 i 1.2623 0.2325 i 1.2230 0.4885 i 0.8788 CW-7648, 7649 Jul,1995 H-3 -64.4182 i 97.4643 -70.1870 i 97.2364 -67.3026 i 68.8371 WW-7673, 7674 Jul,1995 Gr. Beta 14.1451 i 2.2254 14.2212 2.2315 14.1831 i 1.5757 WW-7673, 7674 Jul,1995 H-3 15.3145 i 81.7571 36.3720 i 82.7373 25.8432 i 58.1586 -
MI-78%,7897 Jul,1995 Sr-89 0.3508 i 0.9697 0.1856 1 0.8702 0.2682 i 0.6514 MI-78%,7897 Jul,1995 St-90 1.7110 0.4271 1.2961 0.3929 1.5036 i 0.2902 WW-7967, 7968 Jul,1995 H-3 109.4679 1 84.6270 70.8322 1 82.8444 90.1500 1 59.2134 MI-7922,7923 Jul,1995 Co-60 0.5680 1 3.1300 -1.0500 4.4600 -0.2410 2.7244 MI-7922,7923 Jul,1995 Cs-137 1.2100 2.8600 -0.5040 3.4200 0.3530 1 2.2291 M1-7922,7923 Jul,1995 I131 0.0502 1 0.1932 0.0416 i 0.2336 0.0459 i 0.1516 LW-7944, 7945 Jul,1995 CW 0.0830 i 2.2000 1.3000 i 1.8900 0.6915 i 1.4502 LW-7944, 7945 Jul,1995 Cs 137 0.6400 1 2.2200 -1.3800 1.8200 -0.3700 i 1.4353 LW-7944,7945 Jul,1995 Gr. Beta 4.1332 i 0.9251 3.9971 1 0.9393 4.0652 i 0.6592 SW 8704, 8705 Jul,1995 Co.60 0.1830 i 2.4900 0.9840 1.7900 0.5835 i 1.5333 SW-8704, 8705 Jul,1995 Cs-137 0.2640 1 3/ 500 -0.6630 1 1.9100 -0.1995 i 1.9717 WW-8196, 8197 Jul,1995 H-3 51.4226 i 87.9172 176.0234 i 93.3551 113.7230 i 64.1183 SWU-8318, 8319 Jul,1995 Cr. Beta 1.9584 1 0.4714 1.9228 1 0.4731 1.9406 1 0.3340 SWU-8318, 8319 Jul,1995 H3 102.7030 1 103.6806 35.5141 101.1620 69.1086 72.4283 SWU-E318, 8319 Jul,1995 K 40 93.2530 39.7000 99.7420 49.1000 96.4975 31.5710 SP-8540 8541 Jul,1995 Gr. Alpha 5.1903 1 1.3072 3.8567 1.0701 4.5235 1 0.8447 SP-8540, 8541 Jul,1995 St-89 1,443.0886 1 42.0809 1,419.4750 35.3491 1,431.2818 1 27.4789 SP-8540, 8541 Jul,1995 Sr 90 15.74 % i 3.7553 19.4328 t.'309 17.5912 i 2.7914 181
~ ~. ~ . . - - - - - - ~ - - - - - . . . . . . - - - . - . - . - - . _ . - - - . - . _ . - -
Davis-Besse Nuclear Power Station 1995 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 VE-8090,8091 Jul,1995 Gr. Beta 2.3819 i 0.0781 2.3059 i 0.0779 2.3439 i 0.0552 VE-8090,8091 Jul,1995 K-40 2.8208 i 0.1170 2.7639 i 0.1330 2.7924 i 0.0886 SW-8175,8176 Jul,1995 Gr. Alpha 0.5000i0.6000 0.6583 i 0.8198 0.5791
- 0.5080 1 SW-8175,8176 Jul,1995 Gr. Beta 0.8100 i 1.1000 0.8265 i 1.0847 0.8182 i 0.7724 SW-8175,8176 Jul,1995 K-40 89.8150 1 23.8000 67.3590 1 39.3000 78.5870 i 22.9724 ;
SW-8251, 8252 Jul,1995 H-3 86.7952 i 78.8856 43.9921 i 76.9259 65.3937 i 55.0921 SW-8606, 9607 Jul,1995 Co-60 0.1320 i 1.7100 -0.2180 2.6000 -0.0430 i 1.5560 , SW 8606,8607 Jul,1995 Cs-137 -1.0400 i 2.0400 -0.6580 1 2.2400 -0.8490 i 1.5149 G - 8272,8273 Aug,1995 K-40 6.7487 i 0.6490 6.6636 0.9730 6.7062 i 0.5848 G - 8272,8273 Aug,1995 Sr-89 0.0014 1 0.0091 -0.0007 i 0.0029 0.0004 i 0.0048 G - 8272,8273 Aug,1995 Sr-90 0.0053 i 0.0029 0.0016 1 0.0012 0.0034 i 0.0016 , G-8272,8273 Aug,1995 Gr. Beta 6.2167 i 0.2594 5.9667 1 0.2551 6.0917 i 0.1819 MI-8293,8294 Aug,1995 1-131 -0.1058 i 0.1908 0.0093 i 0.24)09 -0.0483 1 0.1385 : MI-8389,8390 Aug,1995 I131 -0.0127 i 0.1267 0.1153 1 0.1318 0.0513 1 0.0914 , MI-8389,8390 Aug,1995 K-40 1,543.8000 i 120.0000 1,369.6000 i 162.0000 1,456.7000 1 100.8018 M1-8413,8414 Co-60 Aug,1995 0.2940 1 3.1400 -2.3500 1 5.2200 -1.0280 i 3.0458 MI-8413,8414 Aug,1995 Cs-137 -0.7370 2.8900 -1.3600 3.3100 -1.0485 1 2.1971 l Mi-8413,8414 Aug,1995 I-131 0.1142 1 0.2124 0.0598 0.2344 0.0870 1 0.1581 l LW-8440, 8441 Aug,1995 Co-60 0.1030 i 2.3800 1.0300 1 1.8100 0.5665 i 1.4950 LW-8440, 8441 Aug,1995 Cs-137 0.7760 1 1.9900 -0.3850 i 2.0500 0.1935 t l.4285 LW-8440, 8441 Aug,1995 Gr.' Beta 3.3064 i 1.1388 4.6/,23 i 1.2154 3.9844 i 0.8327 WW-8518, 8519 Aug,1995 Co-60 1.4700 3.1400 -1 8100 2.9800 -0.1700 1 2.1645 WW-8518, 8519 Aug,1995 Cs-137 1.7100 1 2.8700 0.4430 2.7700 1.0765 f l.9944 WW-8518, 8519 Aug,1995 H-3 10.6795 1 74.0469 -19.5791 1 72.5777 -4.4498 1 51.8422 VE-8564, 8565 Aug,1995 Co-60 0.0053 1 0.0122 0.0054 1 0.0128 0.0053 1 0.0088 VE-8564,8565 Aug,1995 Cs-137 0.0038 i 0.0093 -0.0003 1 0.0082 0.0018 i 0.0062 MI-8585,8586 Aug,1995 Co-60 -0.4810 1 4.0600 1.8800 1 2.5900 0.6995 1 2.4079 MI-8585,8586 Aug,1995 Cs-134 0.1220 1 3.5000 0.9370 1 2.2700 0.5295 1 2.0858 MI-8585,8586 Aug,1995 Cs-137 1.7700 i 3.6400 0.2160 1 2.0700 0.9930 1 2.0937 MI-8585,8586 Aug,1995 1-131 -0.2002 i 0.2079 0.0732 i 0.1900 -0.0635 i 0.1408 ; M1-8585,8586 Aug,1995 I-131(g) 0.1360 i 9.0300 2.4300 i 6.8100 1.2830 i 5.6550
]
Mi-8585,8586 Aug,1995 K-40 1,454.6000 1 150.0000 1,478.2000 104.0000 1,466.4000 1 91.2634 I MI 8585,8586 Aug,1995 Sr-89 0.1158 i 1.1111 -0.0833 0.9491 0.0162 1 0.7306 Mi-8585,8586 Aug,1995 Sr-90 1.9078 1 0.4296 1.6029 0.3807 1.7553 1 0.2870 M18674,8675 Aug,1995 Co-60 -0.7910 3.2300 0.4890 3.3400 -0.1510 1 2.3232 l Mi 8674,8675 Aug,1995 Cs 137 0.7690 1 2.4300 0.4160 2.4000 0.5925 1 1.7077 182
Davis-Bisse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report l l Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sarnpie First Second Averaged Codes
- Date Analysis Result Result Result MI-8674,8675 Aug,1995 I-131 0.1471 i 0.2525 -0.0869 1 0.2167 0.0301 i 0.1664 SW-8648, 8649 Aug,1995 H-3 35.5546 i 75.1429 21.3328 74.4670 28.4437 1 52.8956 F-8754,8755 l Aug,1995 Co-60 0.0009 i 0.0110 0.0031 1 0.0106 l 0.0020 1 0.0076 F-8754,8755 Aug,1995 CS-134 -0.0026 i 0.0090 -0.0022 i 0.0087 -0.0024 i 0.0063 F-8754,8755 Aug,1995 Cs-137 0.0528 1 0.0207 0.0563 i 0.0171 0.0546 1 0.0134 F-8754,8755 Aug,1995 Gr. Beta 13.1178 i 0.3041 12.6488 0.2780 12.8833 i 0.2060 l F-8754,8755 Aug,1995 I-131(g) 0.0026 0.0139 0.0013 1 0.0121 0.0019 i 0.0092 F-8754,8755 Aug,1995 K-40 2.8119 i 0.3670 3.2605 1 0.3670 3.0362 i 0.2595 I VE-8946, 8947 Aug,1995 Gr. AIpha 0.2000 1 0.0800 0.2018 0.0786 0.2009 i 0.0561 !
VE-8946,8947 Aug,1995 Gr. Beta 4.3000 0.1500 4.3179 i 0.1511 4.3089 i 0.1065 VE-8946,8947 Aug,1995 K-40 3.9615 1 0.2670 4.0418 0.3300 4.0017 1 0.2122 VE - 8802,8803 Aug,1995 Sr-89 -0.0001 i 0.0018 -0.0004 i 0.0022 -0.0002 1 0.0014 VE - 8802,8803 Aug,1995 Sr-90 0.0011 1 0.0006 0.0013 i 0.0007 0.0012 i 0.0005 VE-8802,8803 Aug,1995 K-40 2.3052 i 0.2360 2.3039 i 0.3070 2.3046 1 0.1936 MI-8845,8846 Aug,1995 I-131 0.0098 i 0.1785 0.0835 i 0.1740 0.0467 i 0.1246 l CW-8873, 8874 Aug,1995 Gr. Deta 1.8586 1 1.3992 4.2592 1 1.5511 3.0589 1 1.0445 CW-8873, 8874 Aug,1995 Gr. Beta -0.6043 i 1.1348 -0.0465 i 1.1799 -0.3254 i 0.8185 MI-8902,8903 Aug,1995 I-131 -0.0387 0.2325 0.1320 0.3198 0.0466 1 0.1977 VE-9035,9036 Aug,1995 K-40 2.1934 0.2790 2.38471 0.3380 2.2891 1 0.2191 SW-9056, 9057 Aug,1995 H-3 140.7425 79.5937 55.2281 75.6687 97.9853 54.9111 M1-9113,9114 Aug,1995 1-131 0.2205 0.3289 0.2711 0.2835 0.2458 0.2171 LW-9079, 9080 Aug,1995 Co-60 0.8410 2.8400 0.1630 1 2.9900 0.5020 1 2.0619 LW-9079,9080 Aug,1995 Cs-137 0.7700 i 2.7700 -0.5330 2.6700 0.1185 i 1.9237 LW-9079,9080 Aug,1995 Gr. Beta 2.7566 1 0.8607 2.6961 0.8549 2.7264 1 0.6065 SW-9183, 9184 Aug,1995 Co-60 -0.3280 i 3.0000 2.2200 i 4.0400 0.9460 1 2.5160 SW-9183, 9184 Aug,1995 Cs-137 0.8200 3.4400 0.25801 4.3700 0.5390 1 2.7808 SWU-9162,9163 Aug,1995 Gr. Beta 2.5000 1 0.5000 2.5094 1 0.5480 2.5047 1 0.3709 SWU-9162,9163 Aug,1995 H-3 152.0000 i 88.0000 157.4341 i 83.7394 154.7170 i 60.7377 WW-9276, 9277 Aug,1995 H3 1,636.0299 1 130.9904 1,680.8118 i 132.2095 1,658.4209 i 93.0562 VE-9210,9211 Aug,1995 Cr. Beta 4.1000 0.2000 4.0920 1 0.1675 4.0960 1 0.1304 VE-9210,9211 Aug,1995 K-40 4.6449 1 0.1090 4.6203 i 0.1150 4.6326 1 0.0792 DW-9371, 9372 Aug,1995 Gr. Beta 4.9900 1 1.1960 4.5327 i 1.1679 4.7613 i 0.8358 DW-9371, 9372 Aug,1995 I-131 0.1312 0.2093 0.1381 0.1961 0.1346 0.1434 MI-9297,9298 Aug,1995 1131 0.0434 i 0.1996 0.0510 1 0.2134 0.04 72 0.1461 M1 9297,9298 Aug,1995 K-40 1,727.8000 180.0000 1,602.7000 172.0000 1,665.2500i l24A829 WW-9252, 9253 Sep,1995 H-3 530 8948 98.7085 538.0449 98.9671 534.4698 69.8889 183
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environrnental Operating Report Table A-5. In-house " duplicate" samples. l Concentration in pCi/L' l l Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result i MI-9327,9328 Sep,1995 I 131 0.1442 i 0.1680 0.0972 i 0.1575 0.1207 i 0.1151 WW-9396, 9397 Sep,1995 Co-60 2.0600
- 2.4700 0.687012.950C, 1.3735 i 1.9238 WW-9396,9397 Sep,1995 Cs 137 2.6700 i 2.7300 0.7790 1 2.5900 1.7245 i 1.8816 ;
WW-9396, 9397 Sep,1995 Gr. Beta 0.6947 i 1 3597 1.7640 i 1.3095 1.2293
- 0.9439 I
WW-9396, 9397, Sep,1995 H-3 14.9063 i 76.6085 48.8927 i 78.1795 31.8995 i 54.7287 SW - 10075,10076 Sep,1995 H-3 262.0954 i 87.9940 265.6857 i 88.1404 '!63.8905 i 62.2730 SW - 10075,10076 Sep,1995 Sr-89 -1.1140 0.9865 0.7627 i 0.9505 -0.1756 1 0.6849 SW - 10075,10076 Sep,1995 Sr-90 0.6409 i 0.2633 0.3425 i 0.2113 0.4917 1 0.1687 MI-9350,9351 Sep,1995 I-131 -0 0990 1 0.1565 0.0745 0.1636 -0.0123 i 0.1133 MI-9350,9351 Sep,1995 K-40 1,3353000 i 163.0000 1,521.4000 i 179.0000 1,428.3500 i 121.0475 , MI- 9463,9464 Sep,1995 I-131 0.1059 i 0.1889 0.0550 i 0.1695 0.0804 i 0.1269 , MI-9463,9464 Sep,1995 K-40 1,814.9000 i 139.0000 1,743.1000 i 180.0000 1,779.0000 1 113.7113 BS - 9710,9711 Sep,1995 K-40 834151 03890 8.7853 i 0.3190 8.5634 1 0.2515 CW - 9486,9487 Sep,1995 Gr. Beta 0 3695 i 1.1728 -0.8827 1 1.4122 -0.2566 1 0.9179 CW-9486,9487 Sep,1995 Gr. Beta 3.1540 1 1.5156 3.4306 1 1.5908 3.2923 i l.0986 S O - 9562,9563- Sep,1995 Cs-137 0.4189 i 0.0216 0.4786 i 0.0443 0.4488 i 0.0246 S O - 9562,9563 Sep,1995 K-40 14.9730 1 0.4070 15.6780 1 0.6540 15.3255 i 0 3852 VE-9515,9516 Sep,1995 Co-60 -0.0018 i 0.0107 -0.0046 1 0.0074 -0.0032 i 0.0065 VE-9515,9516 Sep,1995 Cs-137 -0.0003 1 0.0080 -0.0017 i 0.0071 -0.0010 i 0.0054 ; MI-%11, %12 Sep,1995 1131 0.1395 1 0.2011 0.0905 i 0.2020 0.1150 i 0.1425 MI-%11, %12 Sep,1995 K-40 1,463.6000 1 163.0000 1,381.6000 i 117.0000 1,422.6000 i 1003220 SW-9583, 9584 Sep,1995 H-3 191.7867 i 84 3836 59.5611 1 78.5845 125.6739 i 57.6544 l LW - 9632,9633 Sep,1995 Gr. Beta 4.9397 1 0.8738 4.1679 1 0.7956 4.5538 i 0.5909 LW-9632, 9633 Sep,1995 Co40 0.2420 1 2.5400 0.6900 i 1.8800 0.4660 i 1.5800 LW-9632, 9633 Sep,1995 Cs-134 -0.9850 i 2.5000 0.2670 i 23000 -0 3590 i 1.6985 LW-9632,9633 Sep,1995 Cs-137 0.7330 1 2.7300 1.9600 1 2.0000 1 3465 i 1.6921 LW-9632,9633 Sep,1995 I-131 -0.0233 1 0.1923 0.1754 i 0.2465 0.0761 i 0.1563 LW-9632, 9633 Sep,1995 1-131(g) -1.2000 1 7.8600 -1.7800 i 6.9200 -1.4900 t 5.2361 LW-9632, 9633 Sep,1995 K-40 73.2000 1 35.1000 84.4840 1 38.9000 78.8420 1 26.1974 MI-%77, %78 Sep,1995 1-131 0.1492 i 0.1575 -0.0782 1 0.2124 0.0355 i 0.1322 MI-%77, %78 Sep,1995 K-40 1,579.6000 i 149.0000 1,387.5000 i 150.0000 1,483.5500 i 105.7131 CW 9654,9655 Sep,1995 Gr. Beta 3.8956 1.4702 4.0324 1 1.4561 3.9640 1 1.0346 i CW.9654, 9655 Sep,1995 Gr. Beta -0.4258 1 1.0721 0.16371 1.0778 -0.1311 i 0.7601 l Ml-9758,9759 Sep,1995 Co40 0.0531 1 23000 -1.0600 i 5.6200 -0.5035 1 3.0362 M1-9758,9759 Sep,1995 Cs-137 0.1530 2.1000 3.3300 1 4.1300 1.7415 23166 MI 9758,9759 Sep,1995 1131 0.0357 i 0.1262 0.1303 1 0.1374 0.0830 1 0.0933 l 184
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table A-5. in-house " duplicate" samples. Concentration in pCi/L' Lab Sarnple First Second Averaged Codes
- Date Analysis Result Result Result VE-9781,9782 Sep,1995 K-40 3.6858 i 0 3040 3.8621 i 03830 3.7740 i 0.2445 WW - 991,7,9918 Sep,1995 Gr. Alpha 1.0000 i l.2000 0.1895 i 13470 0.5948 i 0.9020 WW - 9917,9918 Sep,1995 Gr. Beta 2.0000 1 1.6000 1.4626 i 1.5372 1.7313i t.1094 WW - 9917,9918 Sep,1995 K-40 61.5990 i 27.2000 55.4580 i 30.1000 58.5285
- 20.2845 SWU-10054,10055 Sep,1995 Gr. Beta 2.8699 i 0.6506 2.9815 1 0.6273 2.9257 1 0.4519 SWU - 10054,10055 Sep,1995 H-3 272.2258 i 86.5578 186.8216 i 82.9725 229.5237 i 59.9514 CW-9848, 9849 Sep,1995 Gr. Beta 10.0958 i 2.0529 10.6091 1 2.0035 10.3525 i 1.4343 CW-9848, 9849 Sep,1995 Gr. Beta 0.6483tl.1139 0.0874 i l.0548 0.3678 i 0.7670 CW-9848, 9849 Sep,1995 H-3 2 3592 i 75.6414 -2.9490 i 75.3926 -0.2949 i 533987 i M1-9873,9874 Sep,1995 I-131 0.1317 i 0.1666 0.2502 t 0.2503 0.1909 i 0.1503 SW - 10174,10175 Sep,1995 Co-60 -0.2100 i 1.9300 0.0995 i 3.2500 -0.0553 i 1.8899 SW - 10174,10175 Sep,1995 Cs-137 -0.0756 2.9100 -0.1070 i 2.8500 -0.0913 i 2.0366 WW-9988, 9989 Sep,1995 H-3 126.1391 1 81.1795 18.2725 i 76 3358 72.2058 1 55.7164 SWT- 10033,10034 Sep,1995 Gr. Beta 1.7710 i 0.4680 1.9280 i 0.4610 1.8495 i O 3285 P-10216,10217 Sep,1995 H-3 76.4356 i 78.6697 74.6580 1 78.5893 75.5468 i 55.5994 SW-10261,10262 Sep,1995 H-3 279.1447 i 88.4376 300.6173 i 893023 289.8810 i 62.8413 l VE - 10012,10013 Sep,1995 Gr. Beta 5.6577 i 0.3023 5.0000 i 0.4415 5.3288 i 0.2675 MI-10120,10121 Sep,1995 1-131 0.1055 i 0.1292 0.0027 i 0.1196 0.0541 1 0.0880 MI-10120,10121 Sep,1995 K-40 1,446.6000 i 163.0000 1,300.9000 i 145.0000 1,373.7500 t 109.0802 SW-10195,10196 Sep,1995 H-3 -19.5632 i 74.6957 103.1512 i 803270 41.7940 i 54.8450 CW - 10240,10241 Sep,1995 Gr. Deta 2.7919 i l.4430 3.6514 i l.5144 3.2216 1 1.0459 CW - 10240,10241 Sep,1995 Gr. Beta 0.5909 i 1.1545 2.4180 1 13151 1.5045 1 0.8750 SW-10150,10151 Sep,1995 H-3 119.1208 1 81.0078 129.7884 i 81.4747 124.4546 i 57.4465 4 SW - 10282,10283 Oct,1995 Gr. Beta 2.1771 0.4791 1.8939 1 0.4661 2.0355 i 0 3342 WW - 10349,10350 Oct,1995 H-3 64.9002 i 80.1767 4735 % i 79.4055 56.1299 i 56.4215 WW-10349,10350 Oct,1995 Co-60 0.0850 1 1.2400 1.4900 i 2.0900 0.7875 i 1.2151 WW-10349,10350 Oct,1995 Cs-137 0.7540 1 1.1500 0.0703 1 2.2400 0.4122 1 1.2590 VE-10370,10371 Oct,1995 K-40 33443 1 0.4620 3.2897 1 0.4770 3.3170 i 03320 F-10491,10492 Oct,1995 Co-60 -0.0087 i 0.0120 0.0051
- 0.0078 -0.0018 i 0.0072 F-10491,10492 Oct,1995 Cs-137 -0.0053 i 0.0105 -0.0009 i 0.0056 -0.0031 1 0.0059 AP - 10752,10753 Oct,1995 Co-60 -0.0006 i 0.0006 -0.0007 1 0.0005 -0.0007 i 0.0004 AP - 10752,10753 Oct,1995 Cs-134 0.0007 1 0.0004 0.0003 1 0.0007 0.0005 1 0.0004
- AP - 10752,10753 Oct,1995 Cs-137 -0.0004 0.0005 0.0000 1 0.0005 -0.0002 1 0.0003 AP - 10752,10753 Oct,1995 I-131(g) 0.0016 1 0.0034 -0.0005 1 0.0047 0.0005 0.0029 AP - 10752.10753 Oct,1995 K-40 0.0344 0.0103 0.0436 1 0.0113 0.0390 1 0.0076 AP - 11141,11142 Oct,1995 Co-60 0.000110.00CM 0.0002 1 0.0002 0.0001 i 0.0002 185
Davis-B:sse Nuclear Power Station 1995 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 AP- 11141,11142 Oct,1995 Cs-137 0.0000 1 0.0003 0.0003 i 0.0004 0.0002 i 0.0002 MI- 10324,10325 Oct,1995 Co-60 03420 1 2.2000 -1.0200 1 3.2000 -0.3390 i 1.9416 MI-10324,10325 Oct,1995 Cs-134 1.4400 i 1.9300 -1.0300 1 2.5800 0.2050 i 1.6110 MI- 10324,10325 Oct,1995 Cs-137 0 3320 i 2.0800 0.9930 1 2.5600 0.6625 i 1.6492 MI-10324,10325 Oct,1995 I-131 0.1255 i 0.1379 0.0629 i 0.2061 0.0942 i 0.1240 MI- 10324,10325 Oct,1995 I-131(g) -0.8920 i 2.6900 1.1700 1 3.2900 0.1390 i 2.1249 MI- 10324,10325 Oct,1995 K-40 1,440.7000 i 88.9000 1,432.5000 i 120.0000 1,436.6000 1 74.6713 MI- 10324,10325 Oct,1995 Sr-89 -0.4912 i 0.9456 -132t.8i 0.8823 -0.9090 1 0.6466 ,
MI- 10324,10325 Oct,1995 Sr-90 1.6952 i 03864 1.7252 1 0.3803 1.7102 1 0.2711 WWU-10392,10393 Oct,1995 I-131 0.0442 1 0.1674 0.0223 1 0.1698 0.0333 i 0.1192 F-10470,10471 Oct,1995 Co-60 0.0049 A 0.0063 0.0037 i 0.0052 0.0043 i 0.0041 F-10470,10471 Oct,1995 Cs-137 0.0003 i 0.0050 0.0020 1 0.0037 0.0011 i 0.0031 SW - 10413,10414 Oct,1995 H3 41.1376 i 773 777 62.2941 78 3358 51.7159 i 55.0541 WW-10437,10438 Oct,1995 H-3 81.6446 1 78.1486 -10.6493 1 73.8374 35.4977 i 53.7568 M1- 10512,10513 Oct,1995 I-131 0.0662 i 0.1335 0.0996 1 0.1517 0.0829 i 0.1010 S O - 10577,10578 Oct,1995 Co-60 0.0033 i 0.0117 0.0032 1 0.0142 0.0033 1 0.0092 S O - 10577,10578 Oct,1995 Cs-134 0.0204 i 0.0110 0.0277 i 0.0128 0.0241 i 0.0084 S O - 10577,10578 Oct,1995 Cs-137 0.1528 i 0.0249 0.1687 0.0241 0.1608 i 0.0173 , S O - 10577,10578 Oct, i995 Gr. Beta 18.4120 1 3.0080 20.0560 i 3.0020 19.2340 i 2.1249 S O - 10577,10578 Oct,1995 K-40 19.0300 1 0.5920 18.4690 1 0.6160 18.7495 1 0.4272 M1 10598,10599 Oct,1995 I-131 0.0233 1 0.1528 -0.1143 0.1290 -0.0455 i 0.1000 F - 10666,10667 Oct,1995 Co-60 -0.0011 0.0149 0.0022 0.0134 0.0005 1 0.0100 F - 10666,10667 Oct,1995 Cs-137 0.0062 1 0.0109 0.0088 1 0.0102 0.0075 1 0.0075 WW - 11206,11207 Oct,1995 H-3 144.1480 82.0522 298.7082 106.1128 221.4281 1 67.0681 F - 10687,10688 Oct,1995 Co-60 -0.0056 1 0.0092 0.0052 1 0.0111 -0.0002 1 0.0072 F - 10687,10688 Oct,1995 Cs-137 0.0051 1 0.0081 -0.0007 1 0.0102 0.0022 i 0.0065 MI- 10710,10711 Oct,1995 I131 -0.0702 1 0.1760 0.0060 i 0.1746 -0.0321 i 0.1240 WW - 10797,10798 Oct,1995 H3 255.7388 i 88.0244 190.9283 i 85.4061 223 3336 i 61.3239 F - 10882,10883 Oct,1995 K-40 2.4355 1 0.2770 23158 1 0.4530 23757 i 0.2655 CW - 10826,10827 Oct,1995 Gr. Beta 1.9841 i 13273 1.1082 i 1.2551 1.5461 1 0.9134 SWU - 10923,10924 Oct,1995 Gr. Beta 2.3790 1 0.5752 2.7204 i 0.5897 2.5497 1 0.4119 SWU - 10923,10924 Oct,1995 H-3 908.5097 i 108.7289 878 3050 1 107.7372 893.4074 1 76.5331 F - 10969,10970 Oct,1995 Cs-137 0.0391 0.0173 0.0589 i 0.0281 0.0490 1 0.0165 F - 10969,10970 Oct,1995 Gr. Beta 2 3088 i 0.0750 2.1970 1 0.0758 2.2529 i 0.0533 F - 10969,10970 Oct,1995 K-40 2.1279 i 03500 1.8750 0.4010 2.0015 0.2661 CW - 10773,10774 Oct,1995 Cr. Beta 8.4208 i 1.8580 9.9060 1 2.0352 9.1634 i 1 3 779 186 i i
i Davis-Besse Nuclect Power Station 1995 Annual Radiological Environmental Operating Report l Table A-5. In-house " duplicate" samples. Concentration in pCi/L' , l Lab Sample First Second Averaged j Codes
- Date Analysis Result Result Result 1 CW- 10773,10774 Oct,1995 Gr. Beta -0.2668 i 1.0986 0.8745 i 1.1142 03039 i 0.7824 CW- 10773,10774 Oct,1995 H-3 51.6603 i 77.7745 67.5106 1 78.4831 59.5854 i 55.2481 CW- 10858,10859 Oct,1995 Gr. Beta 3.8461 i 1.5209 5.5313 1.684,6 4.6887 i 1.1163
! CW- 10858,10859 Oct,1995 Gr. Beta 0.1646 i 1.1055 -0.2698 i 1.0572 -0.0526 i 0.7648 i l BS - 11056,11057 Oct,1995 Cs-137 0.3037 i 0.0214 0.3183 i 0.0167 03110 i 0.0136 BS - 11056,11057 Oct,1995 K-40 18.5050 1 0.4060 18.2890 0.3850 183970 i 0.2798 ; F - 11078,11079 Oct,1995 K-40 2.6694 1 0.1700 2.7062 1 0.1140 2.6878 i 0.1023 ! CW - 11261,11262 Oct,1995 Gr. Beta 3.4182 i 1.5101 3.8050 i 1.4573 3.6116 i 1.0493 l CW - 11261,11262 Oct,1995 Gr. Beta -0.9607 i 0.9909 -0.1199 1 1.1241 -0.5403 1 0.7492 MI- 11162,11163 Oct,1995 I-131 0.2163 0.2174 0.0872 0.2019 0.1517 1 0.1483 LW - 11185,11186 Oct,1995 Co-60 0.2560 i 2.0000 0.0639 3.9000 0.1600 1 2.1915 LW - 11185,11186 Oct,1995 Cs-137 0.9690 i 1.9600 1.3800 i 3.2600 1.1745 i 1.9019 LW - 11185,11186 Oct,1995 Gr. Beta 7.9276 i 1 3579 6.7150 i 1.2839 7.3213 i 0.9344 MI- 11284, l'1285 Oct,1995 I-131 0.1805 i 0.2626 0.1868 0.2352 0.1837 i 0.1763 MI- 11284,11285 Oct,1995 K-40 1,759.4000 i 182.0000 1,581.9000 i 164.0000 1,670.6500 i 122.4949 DW - 11565,11566 Oct,1995 Gr. Beta 2 3856 i 0.4715 2.6159 0.5003 2.5008 i 03437 DW - 11565,11566 Oct,1995 1-131 -0.1047i 03170 0.1835 1 0.2833 0.0394 i 0.2126 SW - 11309,11310 Oct,1995 Gr. Alpha 0.5829 1 0.5262 1.1580 0.6097 0.8705 i 0.4027 SW - 11309,11310 Oct,1995 Gr. Beta 3.1323 1 0.6596 2.5628 1 0.6351 2.8475 i 0.4579 MI- 11351,11352 Oct,1995 I-131 0.0319 1 0.2455 0.0097 0.2195 0.0208 1 0.1647 MI- 11351,11352 Oct,1995 K-40 1,492.6000 i 166.0000 1,431.8000 i 160.0000 1,462.2000 i 115.2779 SW - 11330,11331 Oct,1995 H-3 83.4709 i 77.8239 1063960 i 78.8560 94.9335 i 55 3959 MI- 11407,11408 Oct,1995 I-131 -0.1272 0.1871 0.1059 i 0.1876 -0.0106 i 0.1325 MI-11433,11434 Nov,1995 I-131 -0.0607 0.1789 0.1317 i 0.1462 0.0355 1 0.1155 MI- 11433,11434 Nov,1995 K-40 1,446.0000 i 167.0000 1,450.8000 i 119.0000 1,448.4000 i 102.5305 MI- 11433,11434 Nov,1995 Sr-89 -0.0542 1 1.2560 -0.0961 1.1700 -0.0752 1 0.8583 MI- 11433,11434 Nov,1995 Sr-90 1.9383 1 0.4889 1.8933 1 0.4555 1.9158 i 0 3341 BS - 11453,11454 Nov,1995 Gr. Beta 8 3022 1 1.4598 7.0981 i 1 3 963 7.7002 i 1.0100 BS - 11453,11454 Nov,1995 K-40 13.4130 1 0.6950 14.3840 1 1.0200 13.8985 1 0.6171 MI- 11476,11477 Nov,1995 1131 -0.0379 i 0.1804 0.0878 i 0.2013 0.0250 1 0.1352 MI- 11476,11477 Nov,1995 K-40 1,425.6000 1 155.0000 1,379.5000 1 93.1000 1,402.5500 i 90.4055 MI - 11476,11477 Nov,1995 St-89 0.1529 1 1.5801 0.6656 i 1.1518 0.4092 0.9777 MI - 11476,11477 Nov,1995 Sr-90 LS84510.6297 0.7492 1 0.4308 1.1668 i 0 3815 WW - 11657,11658 Nov,1995 Gr. Beta 0 3756 1 0.4690 0.4697 0.5060 0.4226 i 0.3450 WW - 11657,11658 Nov,1995 H-3 110.2042 1 79.0344 172.1940 81.6909 141.1991 1 56.8327 SW - 11519,11520 Nov,1995 H3 86.0705 1 77.9529 10.3285 1 74.5326 48.1995 53.9253 187
Divis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report 4 Table A-5. In-house duplicate" samples. Concentration in pCi/L' Lab Sarnple First Second Averaged Codes" Date Analysis Result Result Result WW - 11837,11838 Nov,1995 Co-60 0.6630 i 1.5100 0.09 % i 3.2500 0.3813 i 1.7918
- WW - 11837,11838 Nov,1995 Cs-137 0.0882 i 1.6800 -0.5360 i 2.9800 -0.2239 i 1.7105 MI-11588,11589 Nov,1995 K-40 1,282.9000 i 161.0000 1,390.4000 i 145.0000 1,336.6500 1 108.3351 MI-11611,11612 Nov,1995 1131 0.0368 i 0.2007 0.1136 i 0.2056 0.0752 1 0.1437 MI-11611,11612 Nov,1995 K-40 1,368.1000 i 112.0000 1,291.1000 i 158.0000 1,329.6000 1 96.8349 CW - 11678,11679 Nov,1995 Gr. Beta 2.6565 i 1.5123 2.0599 i 1.3520 2.3582 i 1.0143 M1-11786,11787 Nov,1995 I-131 0.0519 i 0.1914 -0.0830 1 0.1791 -0.0156 i 0.1311 M1- 11786,11787 Nov,1995 K-40 1,493.0000 i 100.0000 1,459.1000 i 170.0000 1,476.0500 i 98.6154 CW - 11865,11866 Nov,1995 Gr. Beta 1.9803 i 1.4093 1.1128 i 1.3439 1.5466 i 0.9737 LW - 11926,11927 Nov,1995 Co-60 -0.6990 1 2.1700 -1.3700 1 3.3200 -1.0345 i 1.9831 LW - 11926,11927 Nov,1995 Cs-137 1.3600 1 2.0100 1.6800 2.6800 1.5200 i 1.6750 LW - 11926,11927 Nov,1995 Cr. Beta 3.5794 i 0.9059 4.2705 1 0.9513 3.9250 1 0.6568 PW - 12451,12452 Nov,1995 Co-60 0.1370 1 1.6200 1.5900 2.0000 0.8635 i 1.2869 )
PW - 12451,12452 Nov,1995 Cs-137 -1.0900 1.7200 0.8750 1 2.5000 -0.1075 i 1 5173 WW - 12659,12660 Nov,1995 H-3 10,454.1364 283.5019 10,315.0095 i 281.7458 10,384.5729 1 199.8462 3 G - 12184,12185 Nov,1995 K-40 7.1257 1 0.4820 7.2496 i 0.5540 7.1877 i 0.3672
- DW - 12229,12230 Nov,1995 Gr. Beta 1.4868 i 0.4353 1.5192 i 0.4562 1.5030 i 0.3153 DW - 12229,12230 Nov,1995 H-3 48.3898 i 76.5630 70.8565 77.5707 59.6232 i 54.4957 S O - 12430,12431 Dec,1995 Cs-137 0.2060 1 0.0696 0.1746 i 0.0629 0.1903 1 0.0469 5 0 - 12430,12431 Dec,1995 Gr. Alpha 15.7026 1 4.4545 10.9075 i 4.1010 13.3051 1 3.0274 5 0 - 12430,12431 Dec,1995 Cr.' Beta 22.3778 1 2.8536 23.0769 1 2.9630 22.7273 1 2.0568 S O - 12430,12431 Dec,1995 K-40 16.6990 1.3000 17.6620 1 1.3500 17.1805 i 0.9371 LW - 12152,12153 Dec,1995 Co-60 1.4300 1 3.3200 3.3800 2.1000 2.4050 1.9642 LW - 12152,12153 Dec,1995 Cs-137 -0.1400 1 3.1900 0.3640 1 2.8500 0.1120 1 2.1388 l LW - 12152,12153 Dec,1995 Gr. Beta 5.1509 1 1.3079 4.8804 i 1.1924 5.0157 i 0.8849 MI- 12250,12251 Dec,1995 I-131 0.1190 1 0.1943 0.1981 1 0.2178 0.1586 1 0.1460 l MI-12250,12251 Dec,1995 K-40 1,470.3000 i 163.0000 1,386.6000 i 126.0000 1,428.4500 i 103.0109 WW - 12298,12299 Dec,1995 Co-60 0.4210 2.3800 0.1770 i 4.0900 0.2990 i 2.3660 WW - 12298,12299 Dec,1995 Cs-137 0.1580 1 2.0500 1.5200 i 2.7700 0.8390 i 1.7230 WW - 12298,12299 Dec,1995 H-3 42.7622 1 77.9643 99.7786 i 80.5282 71.2704 1 56.0429 LW - 12380,12381 Dec,1995 Co-60 1.2700 1 2.4400 2.2300 i 2.2300 1.7500 i 1.6528 LW - 12380,12381 Dec,1995 Cs-134 0.5120 2.1300 1.9500 1 2.2200 1.2310 1 1.5383 LW - 12380,12381 Dec,1995 Cs-137 0.8060 2.5100 1.2200 2.4400 1.0130 1 1.7503 LW - 12380,12381 Dec,1995 1-131 0.0861 i 0.1243 0.1222 1 0.2055 0.1041 1 0.1201 LW - 12380,12381 Dec,1995 1131(g) -7.3600 1 13.8000 4.7100 1 13.4000 -1.3250 9.6177 LW - 12380,12381 Dec,1995 K-40 129.0000 i 41.2000 133.0000 1 34.7000 131.0000 26.9329 188
Davis-Besse Nuclear Power Station 1995 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 MI- 12325,12326 Dec,1995 I-131 -0.1263 1 0.2456 0.1598 i 0.2 % 3 0.0167 1 0.1604 MI- 12325,12326 Dec,1995 K-40 1,409.0000 i 172.0000 1,438.6000 i 169.0000 1,423.8000 1 120.5664 WW - 12347,12348 Dec,1995 H-3 77.2534 1 78.8630 87.6308 i 79.3168 82.4421 i 55.9252 F - 12688,12689 Dec,1995 Co-60 0.0009 i 0.0117 0.0011 i 0.0141 0.0010 1 0.0092 F - 12688,12689 Dec,1995 Cs-134 0.0044 i 0.0094 -0.0069 0.0138 -0.0013 i 0.0084 F- 12688,12689 Dec,1995 Cs-137 0.0366 i 0.0179 0.0266 1 0.0149 0.0316 i 0.0116 F - 12688,12689 Dec,1995 I-131(g) -0.0050 1 0.0244 0.0254 i 0.0422 0.0102 1 0.0244 F- 12688,12689 Dec,1995 K-40 2.4139 1 0.3400 2.5180 0.3700 2.4660 i 0.2512 '
PW - 12945,12946 Dec,1995 Co-60 0.2950 2.7700 1.4000 1 1.9600 0.8475 i 1.6 % 7 PW - 12945,12946 Dec,1995 Cs-137 1.4900 2.5600 0.1240 1 2.1900 0.8070 1 1.6845
- All concentrations are reported in pCi/ liter, except solid samples, which are reported in pCi/ gram.
- Lab codes are comprised of the sample media and the sample numbers. Client codes have been eliminated to protect client anonymity.
1 I l 189
Divis-Besse Nucl :r Power Station 1995 Annual Radiological Environmental Operating Report l l l 1 i APPENDIX B DATA REPORTING CONVENTIONS l l 1 l \ ( l l f 190 i
Davis-Besse Nuclear Power Stition 1995 Annual Radiological Environmental Operating Report Data Reoortine Conventions I
\
1.0 All activities except gross alpha and gross beta are decay corrected to colledion time or the end of the collection period. ! l 2.0 Single Measurements l l Each single measurement is reported as follows: xis where x = value of the measurement; s=20 counting uncertainty (corresponding to the 95% confidence level). l' In cases where the activity is found to be below the lower limit of detection L it is reported as
<L 1
l where L = the lower limit of detection based on 4.660 uncertainty for a background sample. ; 3.0 Duplicate analyses 1 3.1 Individual results: xlist xliS2 Reported result: xis where x = (1/2)(x1 i x2) 2 2 s = (1/2) s) + s2 3.2 Individual results: <L1
<L2 Reoorted result: <L l where L = lower of L1 and L2 3.3 Individual results: xis
<L Reoorted result: x i s if x 2 L;
<L otherwise 1
191 l l l
Dzvis-B sse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report 4.0. Comoutation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average I and standard deviation (s) of a set of n numbers x1, x2 x n are defined as follows: i=f Ex s= 'I(R - xi )* , 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 error is reported. , 4.5 In rounding off, the following rules are followed: l 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example,11.443 is rounded off to 11.44. 4.5.2. If the figure following those to be retained is greater than or equal to 5, the figure is dropped and the last retained figure is raised by 1 As an example, 11.446 is rounded off to 11.45. 192
Davis-Besse Nuclear Power Station 1995 Annual Radiological Entrironraental Operating Report APPENDIX C Effluent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas 193
I Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table C-1 Effluent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas
- Air Water Gross Alpha IE-03 pCi/m' Strontium-89 8,000 pCi/l Gross Beta 1 pCi/m' Strontium-90 500 pCi/l lodine-131 6
2.86E-01 pCi/m' Cesium-137 1,000 pCi/l Barium-140 8,000 pCi/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 a Taken from Code of Fedceral Regulation Title 10, Pan 20, Table H and appropriate footnotes. Concentrations may be averaged over a period not greater than one year. b From 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting from the air-grass <ow-child pathway. c A natural radionuclide. 194
Davis-Bisse Nuclear Power Stition 1995 Annual Radiological Environmental Operating Report APPENDIX D REMP Sampling Summary l 195
Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary. Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 i location of Facility Ottawa, Ohio Reporting Period January- December 1995 (County, State) Indacator Location with $ghest Control Number Sample Type and locations Quarterly Mean Locations Non-Type Numberof LLob Mean (P)C Routine Mean (F)C Mean (F)c (Uruts) Analysesa W Immtiond Range P-da=8 Airborne CB 520 0.005 0.020 (310/312) T-1,2 0.021 (104/104) O 0.020 (208/208) particulates (0.008 4.045) Both locations had (0.006-0.045) 3 (0.006-0.046) (pCi/m ) identical means St-89 40 0.0011 <LLD - -
<LLD 0 Sr-90 40 0.0006 <LLD T-2, Site Boundary, 0.0024 (1/4) 0 0.0024 (1/16) 0.9 mi E CS 40 Be-7 0.015 0.000 (24/24) T-1, Site Boundary, 0.090 (4/4) 0 0.084 (16/16)
(0.052-0.109) 0.6 mi ENE (0.073 0.108) (0.055-0.099) K-40 0.048 <LLD - -
<LLD 0 j NW 0.0019 <LLD - - <LLD 0 l Zr-95 0.0037 <LLD - - <LLD 0 Ru 103 0.0021 <LLD - - <LLD 0 Ru-1% 0.015 <LLD - -
<LLD 0 Cs-134 0.0013 <LLD - -
<LLD 0 Cs-137 0.0015 <LLD - -
<tLD 0 Ce-141 0.0030 <LLD - -
<LLD 0 Ce-144 0.0070 <LLD - -
<LLD 0 Airborne Iodine I-131 520 0.07I <LLD - -
<LLD 0 (pCi/m3) 11.D (Quarterly) Gamma 296 1.0 13.0 (253/253) T 8, Farm, 19.1 (4/4) 14.2 (43/43) 0 (mR/91 days) (7.4-20.2) 2.7 mi WSW (17.3 20.2) (8.9-20.4)
TLD(Quarterly) Camma 4 1.0 5.0 (4/4) - - None 0 (mR/91 days) (4.4-53) (Shield) TLD (Annual) Camma 72 1.0 56.2 (62/62) T-8, Farm, 77.1 (1/1) 62.4 (10/10) 0 (mR/365 dsys) (35.7-77.1) 2.7 mi WSW (47.1 74.7) T1.D (Annual) Camma 1 1.0 23.0 (1/1) - - None 0 (mR/365 days) (Shield) 196
1 Davis-Besse Nuclear Power St0 tion 1995 Annual Radiological Environraental Operating Report i Table 4.5 Radiological Environmental Monitoring Program Summary. l Name of Facihty Davis-Besse Nuclear Power Station Docket No. 50-346 ! location of Facility Ottawa, Ohio Reportmg Period January- December 1995 (County, State) Intiacator Location with Haghast Control Number Sample Type and Ic.ations Quarterly Mean lomtions Non-l Type Number of LLDb Mann (F)C Mean (P)C Mean (F)c Rautane l (Umts) Analyses
- W tocadond W Range Results*
Milk (pCi/L) 1-131 12 0.5 none - - <LLD 0 Sr-89 12 0.8 none - -
<tLD 0 Sr40 12 0.5 none T-24, Sandusky, 1 2 (12/12) 1.2 (12/12) 0 21.0 mise (0.7-2.8) (0.7-2.8)
CS 12 i K-40 100 none T-24, Sandusky, 1450 (12/12) 1450 (12/12) 0 21.0 mise (1370-1610) (1370-1610) Cs-137 10 pone - -
<LLD 0
Ba-La-140 1D none - -
<LLD 0 (g/L) Ca 12 0 50 none T-24,Sandusky, 0.89 (12/12) 0 0.89 (12/12) 21.0 mise (0.78-1.04) (0.78-1.04)
(g/L) K(stable) 12 0.1 none T-24, Sanduwy, 1.68 (12/12) 0 1.68 (12/12) i i 21.0 mise (1.58-1.86) (1.58-1.86) ! (pCi/g) Sr-90/Ca 12 036 none T 24, Sandusky, 137(12/12) 0 1.37 (12/12)
' 21.0 mise (0.75-3.29) (0.75-3 29)
(pCi/g) Cs-137/K 12 631 none - -
<LLD 0 Ground Water CB (TR) 12 2.0 3.6 (8/8) T-27, Crane Creek, 6.8 (2/4) 0 53 (2/4)
(pCl/L) (2.9-5.6) 5.3miWNW (4.6-8.9) (4.6-6.0) H3 12 330 <LLD - -
<LLD 0 Sr89 12 1.2 <LLD - -
<LLD 0 Sr-90 12 0.8 <LLD - -
<LLD 0 l
l CS 12 1 Mn-54 15 <LLD - -
<LLD 0 l 4 59 30 <LLD - -
<LLD 0 i Co.58 15 <LLD - -
<LLD 0 Co40 15 <LLD - -
<LLD 0 2945 30 <LLD - - <LLD 0 Zr 95 15 (LLD - -
<LLD 0 Cs-134 10 <LLD - . <LLD 0 Cs-137 10 <LLD - - <LLD 0 0
a Ba-La-140 15 <LLD - - <LLD 4 J l 197
. - . . _ . - . - . - . ~ . . . - . - . -- -_ - - . . . . . . . . - - Davis-Besse Nuclear Power Station 1995 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary. Name of Facility Davis-Besee Nuclear Power Station Docket No. 50-346 Location of Fadhty Ottawa, Ohio Reportmg Feriod January - December 1995 (County, State) indicator location with Highest Control Number Sample Type and locatons Quarteriy Mean locations Non-Typ Number of LLDb Mean (F)C hiean (F)C Mean (F)c Routine (Umts) Analymusa W Lamtiond W Rasulm' , Edible Meet GS 2 (pCi/g wet) K-40 0.1 2.77 (1/1) T-34, Onsite Roving 2.81 (1/1) 2.81 (1/1) 0 location Cs-137 0.017 <LLD - - <LLD 0 St89 4 0.0065 <LLD - -
<LLD 0 ,
vegetables (pCi/g wet) Sr-90 4 0.0007 <LLD T 173, Firelands , 0.0036 (1/1) 0.0036 (1/2) 0 20.0 mL SE i 1-131 4 0.021 <LLD - -
<LLD 0 CS 4 K-40 0.50 1.10(2/2) T 173, Firelands , 3.04 (1/1) 2.12 (2/2) 0 (1.09-1.11) 20.0 mL SE (1.20-3.04)
Nb-95 0.013 <LLD - -
<LLD 0 Zr-95 0.023 <LLD - -
<LLD 0 Cs-137 0.012 <LLD - -
<tLD 0 Ce-141 0.027 <LLD - -
<LLD 0 Ce-144 0.072 <LLD - -
<LLD 0 BroadLeaf Sr-89 13 0.0067 <LLD - -
<LLD 0 Vegetation (pCi/g wet) Sr-90 13 0.0030 0.0043 (3/9) T 19, Hemminger 0.0043 (3/5) <LLD 0 (0.0033-0 0056) Farm,0.68 mi. W (0.0033-0.0056) 1-131 13 0.021 <LLD - - <LLD 0 i CS 13 K-40 0.1 3.17(9/9) T-19, Hemmmger 3.60 (5/5) 2.14 (4/4) 0 (1.78-5.72) Farm,0.68 mi. W (2.30-5.72) (1.90-2.49)
NtWS 0.014 <LLD - -
<LLD 0 Zr45 0.(D3 <LLD - - <LLD 0 Co-137 (L015 <LLD - -
<LLD 0 Ce141 0.022 <LLD - -
<LLD 0 Ce-144 0.12 <LLD - -
<LLD 0 I
198 i
Davis-Besse Nuclear Power Station 1995 Annual Radiologicd Environmental Operating Report i I l Table 4.5 Radiological Environmental Monitonng Program Summary. Name of Fadlity Davis-Besse Nuclear Power Station Docket No. 50-346 i taxation of Facility Ottawa, Ohio Reportmg Period January - December 1995 ! (County, State) indgator Locaten with Highest Control Number Sample Type and incations Quarterly Mean locations Non-Type Number of Id Mean (F)C Mean (F)C Mean (F)c Routine (Unies) Analysasa Rannec Locationd W W W l Anunal GS 4 Wildide Feed (pCl/g wet) Be-7 0.072 0.54 (2/2) T-198, Toussaint 0.62 (1/1) <LLD 0 (0.47 0.62) Creek 4.0 mL WSW K-40 0.1 2.52 (3/3) T-34, Offsite Roving 5.34 (1/1) 5.34 (1/1) 0 (01.35-4.68) location, >10 mL Nb-95 0.017 <LLD - -
<LLD 0 !
Zr-95 0.051 <LLD - -
<LLD 0 Ru-103 0.021 (LLD - - <LLD 0 Ru-106 0.18 <LLD - -
<LLD 0 Cs-137 0.024 <LLD - -
<LLD 0 Ce-141 0.057 <LLD - - <LLD 0 Ce-144 0.13 <LLD - -
<LLD 0 l
i l Soil GS 20 l (pCi/g dry) l Be-7 0.95 <LLD <LLD 0 K-40 1.0 15.90 (12/12) T-4, Site Boundary, 24.90 (2/2) 21.67 (8/8) 0 (1.56-29.20) 0.8 mi S (20.61-29.20) (19.08-24.92) Nb-95 0.21 <LLD - - <LLD 0 l Zr-95 0.18 <LLD - -
<LLD 0 l Ru 103 0.12 <LLD - -
<LLD 0 I Ru-106 0.48 <LLD - - (LLD 0 Cs 137 0.064 0.57 (9/12) T-8, Farm 1.09 (2/2) 0.40 (8/8) 0 (0.052 1.35) 2.7 mL WSW (0.83135) (0.11-0.86)
Ce-141 0.28 <LLD - - <LLD 0 Ce-144 0.45 <LLD - - (LLD 0 Treated CB (IR) 48 1.0 2.0 (24/24) T 11, Port Cimton 2.4 (12/12) 2.1 (24/24) 0 Surface Water (1.5-2.7) Water Treatment (1.9-2.9) (13 2.9) (pCi/L) Plant,9.5 mi. SE H-3 ' 16 11 0 <LLD - - <LLD 0 Sr-89 16 1.4 <LLD - -
<LLD 0 St90 16 0.6 10(3/8) ,T-50 Ene Ind. Park 1.0 (3/4) 08(3/8) 0 (0716) 4.5 mi SE (0.71.6) (0.7-0.8) 5
.i 199
Davis-Besse Nucl:ar Power Station 1995 Annual Radiological Environmental Operating Report Table 4.5 Radiological Envimnmental Monitoring Program Summary. Name of Facility Davis-Besee Nuclear Power Station Docket No. 50-346 Locationof Facility _ Ottawa, Ohio Reporting Period January- December 1995 (County, State) Indicator Location with Nghest Control Number Sample Type and locations Quarterly Mean locations Non-T Number of LLob Maan (F)C Routine Mean (F)C Mean (F)c l (U 88) Analysema Rannec locationd bd % Rasults' , CS 16 I Treated I Surface Water l (pCl/L) j (confinami) Mn-54 15 <LLD - - <LLD 0 l Fe-59 30 <LLD - -
<LLD 0 ,
Co-58 15 <LLD - - <LLD 0 Co-60 15 <LLD - - <LLD 0 Zn-65 30 <LLD - - <LLD 0 l Zr-95 15 <LLD - - <LLD 0 - Ce134 10 (LLD - - <LLD 0 l Cs 137 10 <LLD - - (LLD 0 , Ba-La-140 15 <LLD - -
<LLD 0 )
Untreated CB (TR) 120 1.0 2.6 (72/72) T-152, 3.7 (6/6) 2.4 (48/48) O Surface Water (1.7 5.4) Canal Entrance to (2.3-5.4) (1.6-5.3) ! (pCi/L) Maumee Bay S.P. l 15.6 mi. WNW ' l H3 120 130 681 (7/72) T-131, lake Erie, 1064 (2/6) 486 (2/48) 0 (330-1234) 0.8 mi NE (893-1234) (345-628) St-89 20 <LLD I 1.3 - -
<LLD 0 Sr-90 20 0.9 <tLD - -
<LLD 0 j
G 120
]
Mn 54 15 <LLD - - <LLD 0 Fe 59 30 <LLD - - <LLD 0 Co-58 15 <LLD - - <!.t.D 0 Co40 15 <LLD - - <LLD 0 Zn45 30 (Lt.D - - <LLD 0 Zr-95 15 <LLD - - <LLD 0 Cs 134 10 <LLD - - <LLD 0 Cs-137 10 <LLD - - <LLD 0 j Ba-La.140 15 <LLD - - <LLD 0 4 200
i Davis-Besse Nuclear Power Station 1995 Annual Radiological Environrnental Operating Report ) j Table 45 Radiological Environmental Monitoring Program Summary. l Name of Facility MBesae Nuclear Power Station Docket No. 50-346 location of Facility Ottawa, Ohio Reporting Period January - December 1995 (County, State) ! Indicator tocation with Eghest Control Number Sample Type and locations Quarterly Mean locations Non- 3 Type Number of LLob Mean (F)C Routine Mean (F)C Mean (F)c I (Urdts) Analysesa Rantec locationd Range Results' Rantec Fish CB 6 0.1 3.06 (3/3) T-35, take Erie, 3.34 (3/3) 0 3.34 (3/3) (pCi/g wet) (2.59-3.55) > 10 mi. radius (2.75-3.69) (2.75-3.69) G 6 K-40 0.1 3.01 (3/3) T-35, Lake Erie, 3.09 (3/3) 3.09 (3/3) 0 (2.59-3.23) > 10 mi. radius. (2.83-3.37) (2.83-3.37) , Mn-54 0.019 <LLD - -
<LLD 0 I Fe-59 0.078 <LLD - -
<LLD 0 Co-58 0.018 <LLD - -
(LLD 0 Co-60 0.021 <LLD - -
<LLD 0 Zn-65 0.048 <LLD - -
(LLD 0 Cs-134 0.022 <LLD - -
<LLD 0 Cs-137 0.024 <LLD - -
<LLD 0 j Shoreline G 10 l i
Sediments (pCi/g dry) K-40 0.1 16.62 (8/8) T-4P, Site 24.75 (2/2) 0 13.70 (2/2) l (12.18-27.09) (22.41-27.09) Boundary,0.8 mi. S (13.22-14.18) Mn 54 0.029 <LLD - -
<LLD 0 Co-58 0.080 <LLD
~ ~
0
<LLD Co 60 0.049 <LLD - -
<LLD 0 I
Cs-134 0.11 <LLD - -
<LLD 0 l
Cs 137 0.048 <LLD - -
<LLD 0 l
I a CB = gross beta, GS = gamma scan TR = total resuiue. b LLD = nonunal lower hmat of detection based on 4.66 sigma counting error for background sample. C Mean based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). d Locations are specified by staten code (Table 4 I) and distance (miles) and direction relative to reactor site.
' Non-routme results are those which exceed ten times the control staten value.
I One result (<0.08 pCi/m )3 exceeded the required LLD. The LLD was not reached due to low volume. 201 l
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DAVIS-BESSE NUCLEAR POWER STATION ; RADIATION PROTECTION SECTION 5501 NORTH STATE ROUTE 2 OAK HARBOR, OHIO 43449 I (419) 321-7310 4 GNFsRION "" musacy EDISON}}