ML20140D941
| ML20140D941 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/31/1996 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20140D936 | List: |
| References | |
| NUDOCS 9704250004 | |
| Download: ML20140D941 (218) | |
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{{#Wiki_filter:- . . ... . -- .- l ANNUAL RADIOLOGICAL ! ENVIRONMENTAL OPERATING , REPORT i 1 l i i i for a Davis-Besse Nuclear Power Station ! January 1,1996 through December 31,1996 I l Prepared by: { Radiation Protection Section
- Davis-Besse Nuclear Power Station Toledo Edison Company Toledo, Ohio April 1997 i
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I Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report l TABLE OF CONTENTS Tide faae List of Tables iv I
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List of Figures vi Executive Summary viii INTRODUCTION Fundamentals 1 Radiation and Radioactivity 2 I i Interaction with Matter 3 i Quantities and Units of Measurement 5 Sources of Radiation 7 Health Effects of Radiation 9 Health Risks 10 l l Benefits of Nuclear Power 11 ! Nuclear Power Production 11 Station Systems 16 Reactor Safety and Summary 19 Radioactive Waste 19 Description of the Davis-Besse Site 22 References 24 l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Introduction 26 Preoperational Surveillance Program - 26 Operational Surveillance Program Objectives 27 Quality Assurance 27 Program Description 28 Sample Analysis 32 Sample History Comparison 35 i
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Title Page RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) 1996 Program Deviations 37 Atmospheric Monitoring 39 Terrestrial Monitoring 45 Aquatic Monitoring 57 Direct Radiation Monitoring 68 Conclusion 79 References 80 RADIOACTIVE EFFLUENTitELEASE REPORT Protection Standards 83 Sources of Radioactivity Released 83 Processing and Monitoring 84 i Exposure Pathways 85 i Dose Assessment 86 Results 87 ! Regulatory Limits 88 Effluent Concentration Limits 89 s 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 ; Methodology 110 Results 111 I 1 ii i
Davis-Bt.sse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Title Page
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NON-RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring i16 Land and Wetlands Management 142 Water Treatment 144 I Chemical Waste Management 150 Waste Minimization and Recycling 154 l APPENDICES l Appendix A: Interlaboratory Comparison Program Results 155 l Appendix B: Data Reporting Conventions 191 l Appendix C: EfHuent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas 194 Appendix D: REMP Sampling Summary 196 i l 1 i 1 1
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Davis-Besse Nuclear Power Station 1996 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 droundwater 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 Bottem Sediment Locations 14 62 Fish Locationr 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 Lffluents - Mixed Mode Releases - Continuous Mode 19 98 Liquid Effluents - Summation of All Releases 20 100 l Liquid Effluents - Nuclides Released - Batch Releases 21 101 l 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 1996 23 107 Doses Due to Liquid Releases for January through December 1996 24 108 Annual Dose to The Most Exposed Member of The Public 25 109 j Closest Exposure Pathways Present in 1996 26 113 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters 27 115 iv
Davis-Basse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repn Table Page Title Number Number Summary of Meteorological Data Recovery for 1996 28 122 Summary of Meteorological Data Measured for 1996 29 123 Joint Frequency Distribution by Stability Class 30 137 V
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f Davis-Besse Nuclear Power Station 19% Annual Radiological Environmental Operating Repon List of Figures I l Figure Page ) Description Number Number i
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The Atom 1 1 Principal Decay Scheme of the Uranium Series 2 3
- Range and Shielding of Radiation 3 4 i
Sources of Exposure to the Public 4 8 ! Fission Diagram 5 12 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 j Airborne Sampling Locations on Davis-Besse Site 11 42
) Airbome 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 4 Soil Samples: Cesium-137 15 52 Terrestrial Sampling Locations on Davis-Besse Site 16 54 i Terrestrial Sampling Locations within a Five Mile Radius 17 55 j Terrestrial Sampling Locations within a Twenty-Five Mile Radius 18 56 l 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 1 Aquatic Sampling Locations within a Five Mile Radius 23 66 i Aquatic Sampling Locations within a Twenty-Five Mile Radius 24 67 l TLD Dose Comparison 1973 - 1996 25 69 I
- Comparison of NRC and Davis-Besse TLDs 26 70 Direct Radiation Sampling Locations on Davis-Besse Site 27 76 j 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 vi l
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environraental Operating 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 Wind Rose Monthly Average 100M 35 128 Wind Rose Monthly Average 75M 36 131 Wind Rose Monthly Average 10M 37 134 Water Tmatment Plant Schematic 38 146 r i e 5 eo-vii
Davis-Besse Nuctrar Power Station 19% Annual Radiological Environmental Operating Report Executive Summary r 4 i 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 January I through December 31,1996. This repon meets all of the requirements in Regulatory Guide 4.8, Davis-Besse Technical Specificttions 6.9.1.10, and Davis-Besse Offsite Dose Calcu-lation Manual (ODCM) Section 7.1. Reports included are the Radiological Environmental
- Monitoring Program, Land Use Census, and the Non-Radiological Environmental Programs, l
, which consist of Meteorological Monitoring, Land and Wetland Management, Water Treatment, ^ Chemical Waste Management, and Waste Minimization and Recycling. This report also includes the Radiological Effluent Release Report for the reporting period of January 1 through December 31,1996. i
- Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is established to monitor the ra-diological condition of the environment around Davis-Besse. The REMP is conducted in accor-1 i dance with Regulatory Guide 4.8, Davis-Besse Technical Specification 6.8.4.d and the Davis-Besse Offsite Dose Calculation Manual Section 6.0. This program includes the sampling and analysis of environmental samples and evaluating the effects of releases of radioactivity on the
! environment. Radiation levels and radioactivity have been monitored within a 25 mile radius around Davis-Besse since 1972. The REMP was established at Davis-Besse about five years before the Station
. became operational. This pre-operational sampling and analysis program provided data on ra- ;
! diation and radioactivity normally present in the area as natural background. Davis-Besse has continued to monitor the environment by sampling air, groundwater, milk, edible meat, egg, fruit and vegetables, animal feed, soil, drinking water, surface water, fish, bottom and shoreline sedi-ment, and by measuring radiMion directly. Samples are collected from indicator and control locations. Indicator locations are within ap-proximately 5 miles of the site and are expected to show naturally occurring radioactivity plus any increases of radioactivity that might occur due to the operation of Davis-Besse. Control lo-cations are fanher 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 tha assessment of any impact the operation of Davis-Besse might have had on the surround-ing environment. Approximately 1800 radiological environmental samples were collected and analyzed in 1996. 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 with applicable federal regulations. No measurable increase above background radiation or ra- , dioactivity is-attributed to the operation of Davis-Besse. viii
Davis-Besse Nuclear Power Station 1996
- nnual Radiological Environmental Operating Repon l
. l The sampling results are divided into four sections: atmospheric monitoring, terrestrial monitor-ing, aquatic monitoring and direct radiation monitoring. i e Air is continuously being filtered at 10 locations and the filters are collected to monitor the atmosphere. The 1996 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, I 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, e Aquatic monitoring includes the collection and analysis of drinking water, untreated surface water, fish and shoreline sediments. The 1996 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 13.3 i 2.6 mrem /91 days at indicator lo-cations and 14.2 2.2 mrem /91 days at controllocations. This is similar to results of previous years.
The operation of Davis-Besse in 1996 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 1996 ,
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was well below all applicable regulatory limits. In order to estimate radiation dose to the public, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is per-
- formed as part of the REMP. During the census, Davis-Besse personnel travel every public road within a five mile radius of the Station to locate the radiological exposure pathways (e.g., resi-dences, vegetable gardens, milk cows / goats, ete). The one pathway of particular interest is the pathway that, for a specific radionuclide, provides the greatest dose to a sector of the population, and is called the critical pathway. The critical pathway for 1996 is a Goat milk at 7010 meters west-southwest of the plant.
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Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon
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Radiological Effluent Release Report j
' The Radiological Emuent Release Report (RERR) is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period, January 1,1996 through Decem-ber 31,1996. The doses due to radioactivity released during this period were estimated to be:
Liquid Emuents: 1 Maximum Individual Whole Body Dose 9.60E-02 mrem 4 (0.096 mrem) Maximum Individual Significant Organ Dose 1.22E-01 mrem ' a (0.122 mrem) l TotalIntegrated Population Dose 1.84E+00 person- rem j (1.84 person-rem) ) Average Dose to the Individual 8.44E-04 mrem (0.000844 mrem) '
- Gaseous Emuents
1 Maximum Individual Whole Body Dose due to 4.79E-03 mrem { I-131, H-3 and Particulates with half-lives (0.0(M79 mrem) { greater than 8 days
- Maximum Significant Organ dose due to I-131, 3.05E-02 mrem H-3 and Particulates with half-lives greater than (0.0305 mrem)
, 8 days Total Integrated Population dose due to I-131, 1.09E-02 person-rem H-3 and Particulates with half-lives greater than (0.0109 person-rem) 8 days Average dose to an Individual in the population 4.49E-06 mrem due to I-131, H-3 and Particulates with half-lives (0.00000449 mrem) greater than 8 days Maximum Individual Skin dose due to noble gases 2.06E-02 mrad
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(0.0206 mrad) Maximum Individual Whole Body Dose due to 5.25E-03 mrad noble gases (0.00525 mrad) Total Integrated Population dose due to noble gases 1.22E-02 person-rem (0.0122 person-rem) Average dose to individual in population due to 5.60E-06 mrem noble gases _ (0.00000560 mrem) X
b Davis-Besse Nuclear Power Station 19% Annual Radiological Environmental Operating Repon These doses represent an extremely small fraction of the limits set by the NRC or the limits set in the ODCM. There were two abnormal liquid releases and one abnormal gaseous release during this reporting period. There were no changes to the Process Control Program (PCP) during this reporting pe-riod. There was one change initiated to the Offsite Dose Calculation Manual during this reporting period. Non-Radiological Environmental Programs
+ Meteorological Monitoring The Meteorological Monitoring Program at Davis-Besse is part of a program for evaluating the radiological effects of the routine operation of Davis-Besse on the surrounding environment.
Meteorological monitoring began in October,1968. Meteorological data recorded at Davis-Besse include wind speed, wind direction, sigma theta (standard deviation of wind direction), ambient temperature, differential temperature, dew point and precipitation. Two instrument-equipped meteorological towers are used to collect data. Data recovery for the six instruments required to be operational by Davis-Besse Technical Re-quirement was 98.6%.
+ Marsh Management Toledo Edison and the Cleveland Electric illuminating Company co-own the Navarre Marsh l
which they lease to the U.S. Fish and Wildlife Service, who manage it as pan of the Ottawa Na-tional Wildlife Refuge. Davis-Besse personnel are responsible for inspecting the marsh and re-poning on its status monthly. Special projects conducted in 1996 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 up-land animals, improve water quality, and reduce soil crosion. Also, Davis-Besse pledge panner-ship with Ducks Unlimited, the Ohio Division of Wildlife and Ottawa National Wildlife Refuge in restoring 908 acres of wetland in Metzers Marsh. A pair of American Bald Eagles used the nest platform that was built in 1996 but failed to pro-duce any young. The extreme cold and wet spring caused several nests in the Lake Erie region to fail as well.
+ Water Treatment 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.
l i Davis-Besse Nuclear Power Statia 1996 Annual Radiological Environmental Operating 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.
+ Chemical Waste Management l
The Chemical Waste Management Program at Davis-Besse was developed to ensure that the off-site disposal of non-radioactive hazardous and nonhazardous chemical wastes is performed in accordance with all applicable state and federal regulations. Chemical waste disposal vendors contracted by Davis-Besse use advanced technology for offsite disposal of chemical wastes in 1 order to protect human health and tin environment. In 1996, the Davis-Besse Nuclear Power Station generated 2750 pounds of hazardous wastes, which represents a 70% increase inm 1995. Reason for increase was due to 1996 being outage l year and it matches closer to the 1994 waste generated. There were 2800 gallons of non-hazardous waste oil generated in 1996, a 8% reduction from 1995. Approximately 1,650 gallons of oil filters and solid oily debris were also generated. Additionally,21,660 gallons of water l containing small amounts of diesel fuel oil from an on-site fuel oil leak were disposed of as non- ' hazardous regulated waste. As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse reported hazardous products and chemicals to local fire depanments and local and state planning commis-sions. As part of the program to remove PCB fluid from Davis-Besse, all electrical transfonners 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 1996, a total of 52 tons of paper were collected and recycled and 6 tons of cardboard were collected that would have otherwise been disposed ofin a landfill. The scrap metal collected onsite was sold to scrap com-panies.
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 laboratory contracted by the Davis-Besse Nuclear Power Station to analyze its REMP samples. The results are then checked by the EPA to ensure consistency with the known values. The results from both the contracted laboratory and the EPA are provided in Appendix A. xii
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. l Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report !
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I~ Appendix B contains data reporting conversions used in the REMP at Davis-Besse. The appen-dix provides an explanation of the format and computational methods used in reporting REMP data. Information on counting uncertainties and the calculations of averages and standard devia-tions is also provided. Appandix C lists the effluent concentration limits for alpha and beta emitting radioisotopes and J 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 1996. J Appendix D provides a REMP sampling summary from 1996. The appendix provides a listing of the following for each sample type: l
. the number and types of analyses performed,
+ 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 ; I 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 1996). e en xiii
1 e Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report l 1 Introduction Coal, oil, natural gas and hydropower are used to run this nation's electric generating stations; 1 however, each method has its drawbacks. Coal-fired power can affect the environment through mining, acid rain and air pollution. Oil and natural gas are in limited supply and are therefore costly, and hydropower is limited due to the environmental impact of damming our waterways and the scarcity of suitable sites in our country. Nuclear energy provides an alternate source of energy which is readily available. The operation of nuclear power stations has a very small impact on the environment. In fact, the Davis-Besse Nuclear Power Station is surrounded by hundreds of acres of marshland which make up part of the Ottawa National Wildlife Refuge, the only national refuge in Ohio. In order to more fully ! understand this unique source of energy, background information on basic radiation characteris-tics, risk assessment, reactor operation and effluent control is provided in this section. 1 Fundamentals l The Atom [ l o enerom
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All matter consist of atoms. Simply de- O st.ccTeen scribed, atoms are made up of positively and k J negatively charged particles, and particles _ which are neutral. These particles are called O picAons, electrons, and neutrons, respec- I tively (Figure 1). The relatively large pro-tons and neutrons are packed tightly to- _ gether in a cluster at the center of the atom called the nucleus. Orbiting around this nu-cleus are one or more smaller electrons. In an electrically neutral atom the negative [ O \. rswamcw cmu r charges of the electrons are balanced by the Q positive charges of the protons. Due to their ~ dissimilar charges, the protons and electrons have a strong attraction for each other, Fig m 1: An atom amsists of Iwo pans: a nucim containing pmhly charged pnxons and electncaHy which helEs hold the atom toEether. Other neutral neutrons and one or more negatively charged attractive forces between the protons and electrons orbiting the nucleus. Protons and neutrons neutrons keep the densely packed protons are nearly identical in size and weight, while each is from repelling each other, preventing the about 2000 times heavier than an electron. nucleus from breaking apart. I
Davis-BIsse Nuclear Power S'nion 1996 Annual Radiological Environmental Operating Repon
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Radiation and Radioactivity Isotopes and Radionuclides A group of identical atoms, containing the same number of protons, make up an element. In fact, the number of protons an atom contains determines its chemical identity. For instance, all { atoms with one proton are hydrogen atoms and all atoms with eight protons are oxygen atoms. However, the number of neutrons in the nucleus of an element may vary. Atoms with the same I number of protons, but different numbers of neutrons are called isotopes. Different isotopes of the same element have .the same chemical properties and many are stable or nonradioactive. An , unstable or radioactive isotope of an element is called a radioisotope, radioactive atom, or ra- i dionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The ex-cess energy is usually due to a surplus or deficit in the number of neutrons in the nucleus. Radionuclides can be naturally occurring such as uranium-238, beryllium-7 and potassium-40, or man-made, such as iodine-131, cesium-137, and cobalt-60. Radiation Radiation is simply the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation ^ is another type of radiation and has similar properties to those of the examples listed above. ; lonizing radiation consists of both electromagnetic radiation and particulate radiatlan. Elec- l tromagnetic radiation is energy with no measurable mass that travels with a wave-like motion through space. Included in this category are gamma rays and X-rays. Particulate radiation con- i 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; heta 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.
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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 emis- i sion of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go j through a series of decay stages, called a radioactive decay series, and produce several daugh- l ter products uhich 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
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2 neutrons. As discussed previously, the number of protons in the nucleus of an atom determines its chemical identity. Therefore, when the uranium-238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of thorium-234. Thorium 234 is one of the 14 successive daughter products of uranium 238. Radon is another daughter product, and the series ends with stable lead-206. 2 l l l l i
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1 Davis-B:sse Nuclear Power Station 1996 Annual Radiological Envirmmental Operating Report s I - j_ . ., This example is pan of a known radioactive decay series, called the uranium series, which begins t l with uranium-238 and ends with lead-206 (Figure 2). l l 22*u 1 22*u i I 4.s 'a so'y 8 5 * ' 22*ea 3- pt.2 min
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a iep, , Half-life 2 8.. mio 24 y i Most radionuclides vary greatly in the frequency with which their atoms release radiation. Some 1 radioactive materials, in which there are only infrequent emissions, tend to have a very long half- l lives. Those radioactive materials that are very active, emitting radiation more frequently, tend to have comparably short half lives. The length of time an atom remains radioactive is defined in terms of half lives. Half-life is the amount of time required for a radioactive substance to lose i half its activity through the process of radioactive decay. Half-lives vary from millionths of a i second to millions of years. l Interaction with Matter Ioni/.ation i Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When these forms of radiation interact with any form of material, the energy they impart may cause at- i oms in that maternal to become ions, or charged panicles. Normally, an atom has the same num- i ber 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. Ioniza-tion is one of the processes which may result in damage to biological systems.
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I Davis-Besse Nuclear Power Station 1996 Annual Radiological F.nvironmental Oprating Repon - Range and Shielding - I Particul..te and electromagnetic radiation each travel through matter differently because of their different properties. Alpha particles contain 2 protons and 2 neutrons. are relatively large, and carry an electrical charge of +2. Alpha particles are ejected from the nucleus of a radioactive ; atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its compara- ; tively large size, an alpha particle usually does not travel very far before it loses most of its en-ergy through collisions and other interactions with atoms. As a result alpha particles can easily i be stopped by a sheet of paper or a few centimeters of air (Figure 3). Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed j of light (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1. Because they are so small and have a low charge, they do not collide and interact as often as al- i pha particles, so they can travel fanher. Beta particles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood. i s .
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m RADioACTlvE PAPER I F1ATERIAL AwMINUM LEAD CONCRETE Figure 3: As radiation travels. it collides and interacts with other atoms and loses energy. Alpha parueles can be stopped by a sheet of paper, and beta particles by a thin sheet of aluminum. Ganuna radiation is shielJed by highly l dense materials such as lead. while hydrogenous material.s (those containing hydrogen atoms) such as water and ! concrete, are used to stop neutrons. Gamma rays are pure energy and travel at the speed of light. They have no measurable charge or mass, and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamina ray finally loses all of its energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high energy gamma radiation can travel a considerable distance, whereas low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of lead or concrete may be needed to effectively shield gamma rays. Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within operating nuclear power reactors. However, neutrons are not of environmental concern since the neutron source at nuclear power stations is sealed within the containment building. 4
Davis-Besse Nuclear Power Station 19% Annual Radiological Environm:ntal Operating Repon
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Because neutrons have no charge, they are able to pass very close to the nuclei of the material through which they are traveling. As a result, neutrons may be captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some ofits energy. After a series of these deflections, the neutron has lost most ofits energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is cal!ed a thermal neu-i 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. j Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron l 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 l Davis-Besse, concrete is used to form an effective neutron shield because it contains water mole-l cules and can be easily molded around odd shapes. l Quantities and Units of Measurement ' There are several quantities and units of measurement used to describe radioactivity and its ef-fects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent. Activity: Curie Activity is the number of atoms in a sample that disintegrate (decay) per unit of time. Each time an atom disintegrates, radiation is emitted. The curie (Ci)is the unit used to describe the activity ' of a material and indicates the rate at which the atoms of a radioactive substance are decaying. One curie indicates the disintegration of 37 billion atoms per second. A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. Fr>r example, one gram (1/28 th of an ounce) of radium-226 is the i equivalent of one curie of activity, but it would take 9,170,000 grams (about 10 tons) of ! thorium-232 to equal one curie. l Smaller units of the curie are often used, especially when discussing the low concentrations of radioactivity detected in environmental samples. For instance, the microcurie (uCi) is equal to one millionth of a curie, while the picocmic (pCi) represents one trillionth of a curie. Absorbed Dose: Rad Absorbed dose is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation. The rad (radiation absorbed dose)is the unit used to measure the absorbed dose. It is defined as the energy ofionizing radiation deposited per gram of absorbing material (I rad = 100 erg /gm). The rate of absorbed dose is usually given in rad /hr. 5 1
Davis-Besse Nuclear Power Station 1996 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 measumment 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 ioniza-tion 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 radia-tion. The dose equivalent is measured in rem (radiation equivalent man). An example of this conversion from absorbed dose to dose equivalent uses the quality factor for alpha 4adiation, which is 20. Thus, I rad of alpha radiation is approximately equal to 20 rem. Beta and gamma radiation each have a quality factor of 1, therefore one rad of either beta or gamma radiation is approximately equal to one rem. Neutrons have a quality factor ranging from 2 to 10. One tem 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) i Deep dose equivalent is the measurement of dose within the body, from sources of radiation that < are external to the body. It is what is measured and recorded thermoluminescent dosimeters (TLDs), film badges, or other dosimeters. For example, at Davis-Besse or at any hospital that I has x-ray equipment, you will see people wearing these devices. These instmments are worn to I measure deep dose equivalent (DDE). j Committed Effective Dose Equivalent (CEDE) J Committed effective dose equivalent is a measure of the dose received from any radioactive ma- j 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. l 6 h
Davis-Besse Nuclear Power St: tion 19% Annual Radiological Environmental Operating Report
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Total Effective Dose Equivalent (TEDE) Total effective dose equivalent means the sum of the deep dose equivalera (for dose from sources external to the body) and the committed effective dose equivalent (for internal dose). As these are both doses to the body, they are not tracked separately. The NRC limits occupational dose to a radiation worker to five rem (5000 mrem) TEDE per year. Sources of Radiation Background Radiation Radiation is not a new creation of the nuclear power industry; it is a natural occurrence on the earth. It is probably the most " natural" thing in nature. Mankind has always lived with radiation and always will. In fact, during every second oflife, over 7,000 atoms undergo radioactive decay
" naturally" in the body of the average adult. In addition, radioactive decay also occurs naturally in soil, water, air, and space. All these common sources of radiation contribute to the natural background radiation to which everyone is exposed.
l 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 evegone still receives about 20 to 50 mrem each year from this I source. The thinner air at higher altitudes provides less protection against cosmic radiation. So people living at higher altitudes or flying in an airplane are exposed to more cosmic radiation. Radionuclides commonly found in the atmosphere as a result of cosmic ray interactions include begllium-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-sults from the decay of radium-226, a member of the uranium-238 decay series. Since uranium ocents naturally in all soils and rocks, everyone is continuously exposed to radon and its daughter products. Radon would not be considered to pose a health hazard unless it is concentrated in a confined area, such as buildings, basements or underground mines. Radon-related health con-cerns stem from the exposure of the lungs to tfils radioactive gas. Raden emits alpha radiation when it decays, this could cause damage to internal tissues when inhaled. As a result, exposure to the lungs is of concern, as the only recognized health effect associated with exposure to radon is an increased risk oflung cancer. This effect has been seen when the radon is present at levels common in uranium mines. According to the National Council on Radiation Protection and Measurement (NCRP), over half of the radiation dose the average American receives is attributed to radon. 7
j Davis.llesse Nuclear Power Station IW6 Annual Radiological Environmental Op: rating Report -
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! Figure 4: The most signilicant annual dose received by an individual of the public is that recened from naturally ] occurring radon. A very small annual dose to the public results from producing electricity by nuclear power. e j Further information on radon, its measurement, and actions to reduce the radon concentration in j buildings can be obtained by contacting the state radon program office at the following address: 1 Radiological Health Program j Ohio Department of 1lealth i P.O. Box 118 i Columbus, Ohio 43266-0118 i (6141481-5800 (800) 523-4439 (in Ohio Only) l i The approximate average background radiation in this area (see Figure 4) is 300 mrem / year. I Man-Made Radiation - j In addition to naturally occurring cosmic radiation and radiation from naturally occurring radio-l activity, people are also exposed to man-made radiation. The largest sources of exposure include j medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer ! products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests ! is another source of man-made exposure. Fallout radionuclides include strontium-90, ) cesium-137, and tritium. Less than one percent of the annual dose a member of the public re-
! ceives is a result of having electricity generated by nuclear power.
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Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Health Effects of Radiation The effects ofionizing radiation on human health have been under study for more than 80 years. Scientists have obtained valuable knowledge through the study of laboratog animals that were exposed to radiation under extremely controlled conditions. However, it has been difficult to re- 4 late the biological effects of irradiated laboratoy 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 such groups are clock dial painters, who ingested large amounts of radium by " tipping" the paint brushes with their lips, and uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (uranium ore). The studies performed on these groups have increased our knowledge of the health effects from comparatively very large doses of radiation received over long periods of time. Continuous exposure to low levels of radiation may produce comatic changes over an extended period of time. For example, semeone may develop cancer from man-made radiation, back-ground radiation, or some other source not related to radiation. Because all illnesses caused by low level radiation can also be caused by other factors, it is virtually impossible to determine in-dividual health effects of low level radiation. Even though no effects have been observed at doses less than 50 rem, to be conservative, we assume the health effects resulting from low doses of radiation occur proportionally to those observed following large doses of radiation. Most ra-diation scientists agree that this assumption over-estimates the risks associated with a low level radiation exposure. The effects predicted in this manner have never been actually cbserved in any individuals exposed to low level radiation. Therefore, the most likely somatic effect of low level radiation is believed to be a small increased risk of cancer. Genetic effects could occur as a result of ionizing radiation interacting with the genes in the hu-man cells. Radiation (as well as common chemicals) can cause physical changes or mutations in the genes. Chromosome fibers can break and rearrange, causing interference with the normal cell division of the chromosome by affecting their number and structure. A cell is able to rejoin the ; ends of a broken chromosome, but if there are two breaks close enough together in space and time, the broken ends from one break could join incorrectly with those from another. This could cause translocations, inversions, rings, and other types of structural rearrangements. When this 9
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon
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happens, new mutated genes are created. Radiation is not the only mechanism by which such changes can occur. Spontaneous mutations and chemically induced mutations also have been observed. These mutated genes may be passed from parent to offspring. Viable mutations due to low level, low dose radiation have not been observed in humans. Health Risks While people may accept the risks inherent in their personal activities, such as smoking and driving to work each day, they are less inclined to accept the risk inherent in producing electric-ity. As with any industrial environment, it is not possible to guarantee a risk free environment. Thus, attention should be focused on taking steps to safeguard the public, on developing a realis-tic assessment of the risks, and on placing these risks in perspective. The perceptions of risk as-sociated with exposure to radiation has, perhaps, the greatest misunderstanding. Because people may not understand ionizing radiation and its associated risks, they may fear it. This fear is com-pounded by the fact that we cannot hear, smell, taste or feel ionizing radiation. However, we do not fear other potentially hazardous things for which we have the same lack of sensory perception, such as radio waves, carbon monoxide, and small concentrations of numer-ous cancer causing substances. These risks are larger and measurable compared to those pre-sumed to be associated with exposure to low level, low dose radiation. Most of these risks are with us throughout our lives, and can be added up over a lifetime to obtain a total effect. Table 1 shows a number of different factors that decrease the average life expectancy of individuals in the United States. Table 1: Risk Factors Estimated Decrease in Average Life Expectancy Overweight by 30% 3.6 years Cigarette smoking: 1 pack / day 7.0 years 2 packs / day 10.0 years Heart 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
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vis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon i Benefits of Nuclear Power I Nuclear power plays an important part in meeting today's electricity needs, and will continue to j serve as an important source of electric energy well into the future. Today more than twenty percent of the electricity produced in the United States is from nuclear powered electrical gener-
- ating stations.
Nuclear power offers several advantages over alternative sources of electric energy: e nuclear power has an excellent safety record dating back to 1957 when the first commercial nuclear power station began operating, 4 e
- uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States, 1
j 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. I The following sections provide information on the fundamentals of how Davis-Besse uses nu-1 clear fuel and the fission process to produce electricity. 4 Nuclear Power Production ! Electricity is produced in a nuclear power station in the same way as in a fossil-fueled station 3 l with the exception of the source of heat. Heat changes water to steam that turns a turbine. In a l fossil-fueled station, the fuel is burned in a furnace, which is also a boiler. Inside the boiler, wa-ter is turned into steam. In a nuclear' station, the furnace is replaced by a reactor containing a core of nuclear fuel, primarily uranium. Heat is produced when the atoms of uranium are split, or fissioned, inside the reactor.
- What is Fission?
1
- A special force called the binding force holds the protons and neutrons together in the nucleus of
, the atom. The strength of this binding force varies from atom to atom. If the bond is weak j enough, the nucleus can be split when bombarded by a free neutron (Figure 5). This causes the entire atom to split, producing smaller atoms, niore free neutrons, and heat. In a nuclear reactor, a chain reaction of fission events provides the heat necessary to boil the water to produce steam. i M l 11
Davis-Besse Nuclear Power Station 19% Annual Radiological Environmental Operating R: port . End O
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hen on ^ A 0111 Fission l fTtgment O)' l i 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 neighbonng atoms causing them to fission also. In the proper environment, j this process can continue indefinitely in a chain reaction. I Nuclear Fuel l J The fissioning of one uranium atom releases approximately 50 million times more energy than the combustion of a single carbon atom common to all fossil fuels. Since a single small reactor fuel pellet contains trillions of atoms, each pellet can release an extremely large amount of en- l ergy. The amount of electricity that can be generated from three small fuel pellets would require i about 3.5 tons of coal or 12 barrels of oil to generate. Nuclear fission occurs spontaneously in nature, but these natural occurrences cannot sustain themselves because the freed neutrons either are absorbed by non-fissionable atoms or quickly decay. In contrast, a nuclear reactor minimizes neutron losses, thus sustaining the fission proc-ess by several means:
. uung f uel that is free of impurities that might absorb the free neutrons, e ennchmg the concentration of the rarer fissionable isotope of uranium (U-235) relatne to the concentration ofS238, a more common isotope that does not fis-uon easil).
. 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 liefore it can be economically used in a reactor, it is enriched to three to five percent U-235. m contrast to nuclear material used in nuclear weapons which is enriched to over 97 percent. Ilecause of the low levels of U-235 in nuclear fuel, a nuclear power station cannot explode like a bomb. j 12
O Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmennil Operating Report After the uranium ore is separated from the earth and rock, it is concentrated by a milling proc- l ess. After milling the ore to a granular form and dissolving out the uranium with acid, the ura- j nium is converted to uranium hexalluoride (UF6). UF6 is a chemical fonn of uranium that exists as a gas at temperatures slightly above room temperature. The UF 6 is then highly purified j and shipped to an enrichment facility where gaseous diffusion converters increase the concen-tration of U-235. The enriched gaseous UF6 is then converted into powdered uranium dioxide (UO2), a highly stable ceramic material. The UO2Powder is put under high pressure to form fuel pellets, i 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. l l The Reactor Core 1 1 Two hundred eight fuel rods comprice a single fuct assembly. The reactor core at Davis-Besse ; contains 177 of these fuel assernblies, ean approximately 14 feet tall and 2,000 pounds in j weight. In addition to the fuel rods, the fuel assembly also contains 16 vacant holes for the in- - sertion of control rods, and one vacant hole for an incore monitoring probe. This probe l 4 monitors temperature and neutron levels in the fuel assembly. The Davis-Besse reactor vessel, 4 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. al O@ .i U. i
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. 4 Davis-Besse Nuclear Power Station 1996 Annual Radiologic:1 Environmental Operating Report
; Fission Control :
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i The fission rate inside the reactor core is controlled by raising or lowering control rod assem- I blies into the reactor core. Each assembly consist of " fingers" containing silver, indium, and l cadmium metals that absorb free neutrons, thus disrupting the fission chain reaction. When con-l
- trol rod assemblies are slowly withdrawn from the core, fissioning begins and heat is produced. '
i If the control rod assemblies are inserted rapidly into the reactor core, as during a plant " trip", the l chain reaction ceases. A slower acting (but more evenly distributed) method of fission control is J i achieved by the addition of a neutron poison to the reactor coolant water. At Davis-Besse, high I purity boric acid is concentrated or diluted in the coolant to achieve the desired level of fission. Boron-10 readily absorbs free neutrons, forming baron-11, removing the absorbed neutrons from the chain reaction. Reactor Types ; i l 1
- Virtually all of the commercial reactors in this country are either boiling water reactors )
(BWRs) or pressurized water reactors (PWRs). Both types are also called light water reac- I tors (LWRs) because their coolant, or medium to transfer heat, is ordinary water, which contains
- the light isotope of hydrogen. Some reactors use the heavy isotope of hydrogen (deuterium) in
. the reactor coolant. Such reactors are called heavy water reactors (HWRs). 1 In BWRs, water passes through the core and boils into steam. The steam passes through separa-tors which remove water droplets. The steam then travels to dryers before entering the turbine. After passing though the turbine the steam is condensed back into water and returns to the core to repeat the cycle. In PWRs, the reactor water or coolant is pressurized to prevent it from boiling. The reactor water is then pumped to a steam generator (heat exchanger) where its heat is transferred to a secon- j dary water supply. The secondary water inside the generator boils into steam which is then used ' to turn the turbine. This steam is then condensed back into water and returned to the steam gen- l erator. Davis-Besse uses a PWR design. - 1 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. De 14
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Station Systems Containment Building and Fission Product Release Barriers 1 The containment building houses the reactor vessel, the pressurizer, two steara generators, the reactor coolant pumps and reactor coolant system piping. The building is constructed of an inner 1 inch thick steel liner or containment vessel, and the shield building with steel reinforced con- j crete walls 2 feet thick. The shield building protects the containment vessel from a variety of l environmental factors and provides an area for a negative pressure boundary around the steel I containment vessel. In the event that the integrity of the containment vessel iWoSpromised (e.g., a crack develops), this negative pressure boundary ensures that any airborne radioactive contamination present in the containment vessel is prevented from leaking out into the environ-ment. This is accomplished by maintaining the pressure inside the shield building lower than that outdoors, thus forcing clean outside air to leak in, while making it irnpossible for the con- l taminated air between the containment vessel and the shield building to leak out. The free- . l standing containment vessel is the third in a series of barriers that prevent the release of fission i products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel cladding itself. The second barrier is the walls of the primary system, i.e. the r'eactor vessel, steam generator and associated piping. The Stearn Generators The steam generators perfonn the same function as a boiler at a fossil-fueled power station. l The steam generator uses the heat of the primary coolant inside the steam generator tubes to boil l the secondary side feedwater (secondary coolant). Fission heat from the reactor core is trans-ferred to the steam generator in order to provide the steam necessary to drive the turbine. How-ever, heat must also be removed from the core even after reactor shutdown in order to prevent ! damage to the fuel cladding. Therefore, pumps maintain a continuous flow of coolant through j the reactor and steam generator. Primary loop water (green in Figure 7) exits the reactor at ap- ; proximately 606 F, passes through the steam generator, transferring some of its heat energy to l the secondary loop water (blue in Figure 7) without actually coming in contact with it. Primary l coolant water exits the steam generator at approximately 558 F to be circulated back into the re-actor where it is again heated to 606 F as it passes up through the fuel assemblies. Under ordi-nary conditions, water inside the primary system would boil long before it reached such temperatures. However, it is kept under a pressure of approximately 2,200 pounds-per-square-inch (psi) at all times. This prevents the water from boiling and is the reason the reactor at Davis-Besse is called a Pressurized Water Reactor. Secondary loop water enters the base of the steam generator at approximately 450 F and under 1,100 psi pressure. At this pressure, the water can easily boil into steam as it passes over the tubes containing the primary coolant water. Both the primary and the secondary coolant water are considered closed loop systems. This 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 method of heat transfer that can occur between two fluid media. It is the same process by which radiatorrare used to heat homes. The water circulating inside the radiator is separated from the air (a " fluid" medium) by the metal piping. 16
D:vis-B:sse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon The Turbine - Generator The turbine, main generator, and the condenser are all hwsed in w. hat is commonly referred to as the Turbine Building. The purpose of the turbine 13 to convert the thermal energy of the steam produced in the steam generator (referred to as mao stear.. .cd in Figure 7) to rotational j energy of the turbine generator shaft. The turbine at Dans-Besse is actually composed of one six-stage high pressure turbine and two seven-stage Ics pusse turbines aligned on a common shaft. A turbine stage refers to a set of blades. Sicam enters at the center of each turbine and flows outward along the shaft in opposite directions through each successive stage of blading. As the steam passes over the turbine blades, it loses pressure. Thus, the blades must be propor-
- tionally larger in successive stages to extract enough energy from the steam to rotate the shaft at the correct speed.
1 The purpose of the main generator is to convert the rotational energy of the shaft to electrical energy for commercial usage and support of station systems. The main generator is composed of two parts, a stationary stator that contains coils of copper conductors, and a rotor that supplies a rotating magnetic field within the coils of the stator, Electrical current is generated in the stator ponion of the main generator. From this point, the electric current passes through a series of transformers for transmission and use throughout northem Ohio. The Condenser After the spent steam in the secondary loop (blue in Figure 7) passes through the high and low pressure turbines, it is collected in a cavernous condenser several stories tall and containing ; more than 70,000 small tubes. Circulating water (yellow in Figure 7) goes to the cooling tower j after passing through the tubes inside the condenser. As the steam from the low pressure turbines passes over these tubes, it is cooled and condensed. The condensed water is then purified and reheated before being circulated back into the steam generator again in a closed loop system. Circulating water forms the third (or tertiary) and final loop of cooling water used at the Davis-Besse Station. l Similar to the primary to secondary interface, the secondary to tertiary interface is based on a l closed loop design. The circulating water is able to cool the steam in the condenser, without ever ' actually coming in contact with it, by the process of convection. Even in the event of a primary to secondary leak, the water vapor exiting the Davis-Besse cooling tower would remain non-radioactive. Closed loops are an integral part of-the design of any nuclear facility. This design feature greatly reduces the chance of environmental impact from station operation. The Cooling Tower The cooling tower at Davis-Besse is easily the most noticeable feature of the plant. The tower stands 493 feet high and the diameter of the base is 411 feet. The two pipes circulating 480,000 gallons of water per minute to the tower are 9 feet in diameter. The purpose of the tower is to recycle water from the condenser by cooling it. 17
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon
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After passing through the condenser, the circulating water has warmed to approximately 100 F. In order to cool the water back down to around 70*F, the circulating water enters the cooling tower about 40 feet above the ground. The water is sprayed evenly over a series of baffles called fillsheets which are suspended vertically in the base of the tower. A natural draft of air blowing up through these baffles cools the water through the process of evaporation. The evaporated water exits the top of the cooling tower in the form of water vapor. As much as 10,000 gallons of water per minute are lost to the atmosphere via the cooling tower. Even so, approximately 98 percent of the water drawn from Lake Erie for station operation can be recycled through the cooling tower for reuse. A small portion of the circulating water is dis-charged back to Lake Erie at essentially the same temperature it was withdrawn earlier. The slightly warmer discharge water had no adverse environmental impact on the area of lake sur-rounding the discharge point. Miscellaneous Station Safety Systems The orange system in Figure 7 is part of the Emergency Core Cooling System (ECCS) housed in the Auxiliary Building of the station. The ECCS consists of three overlapping means of keeping the reactor core covered with water, in the unlikely event of a Loss Of Coolant Accident (LOCA), thereby protecting the fuel cladding barrier against high temperature failure. Depend-ing upon the severity of the loss of pressure inside the primary system, the ECCS will automati-cally channel borated water into the reactor by either high pressure injection pumps, a core flood tank, or low pressure injection pumps. Borated water can also be sprayed from the ceil-ing 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. Heat-ers inside the pressurizer turn water into steam. This steam takes up more space inside the pres-surizer, thus increasing the overall pressure inside the primary system. The pressurizer is equipped with spray heads that shower cool water over the steam in the unit. In this case, the steam condenses and the overall pressure inside the primary system drops. The quench tank pictured in Figure 8 is simply where excess steam is directed and condensed for storage. 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. Fol-lowing a reactor shutdown, the Auxiliary Feedwater System can supply water to the steam gen-erators from the Condensate Storage Tanks. The Auxiliary Feedwater System in housed in the Turbine Building along with the turbine, main generator, and the condenser. 18
, Davis-Bisse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Reactor Safety and Summary Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb because the concentration of fissionable material is far less than is n.ecessary for such a nuclear explosion. Also, many safety features are equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the local environment. Davis-Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features. If one system should fail, there are still back-up systems to assure the safe operation of the Station.
- During normal operation, the Reactor Control System regulates the power output by adjusting the position of the control rods. The reactor can be automatically shut down by a separate Reac-tor Protection System that causes all the control rod assemblies to be quickly and completely insened into the reactor core, stopping the chain reaction. To guard against the possibility of a Loss Of Coolant Accident, the Emergency Core Cooling System is designed to pump reserve water into the reactor automatically if the reactor coolant pressure drops below a predetermined level.
The Davis-Besse Nuclear Power Station was designed, constructed, and operates to produce a reliable, safe, and environmentally sound source of electricity. Radioactive Waste Many of the activities we depend on in our everyday lives produce radioactive waste by-products. Nuclear energy, industrial processes, and medical treatments are some of these activities. These by-products are managed and dispowd of under strict requirements set by the federal govern-ment. With the exception of used nuclear fuel assemblies, these by-products produced at com-mercial power plants are referred to as low level radioactive waste. Low Level Radioactive Waste r Low level radioactive waste consists mainly of ordinary trash and other items that have become l 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 radioacti.ve waste emits the same types of radiation that naturally occurring radioactive materials tend to emit. Most low level radioactive waste " decays" to background levels of radioactivity in months or years. Nearly all of it diminishes to stable materials in less than 300 years. 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 1996 Annual 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 oflow-level waste in the Compact, it has the responsibility to site the first disposal facility, which would receh. waste from all Compact states for 20 years. The responsibility then shifts to the Compact's next largest producer of waste, Minnesota, which will host the repository for the second 20 years. Davis-Besse presently ships low level radioactive waste to a South Carolina disposal facility lo-cated at Barnwell, South Carolina. This facility was closed to out of compact generators from July 1,1994 to July 1,1996. The facility was reopened by South Carolina to all generators on July 1,1996. At this time, Davis-Besse resumed shipping of low level radioactive waste to the facility. Davis-Besse has the capacity to store low level waste it produced on site, in the Lcw 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 Like any industrial or scientific process, nuclear energy does produce waste. The most radioac-tive is defined as high-level" waste (because it has high levels of radioactivity). Ninety-nine percent of high-level waste from nuclear plants is used nuclear fuel. The fuel undergoes certain changes during fission. Most of the fragments of fission, pieces that are left over after the atom is split, are radioactive. After a period of time, the fission fragments trapped in the fuel assem-blies reduce the efficiency of the chain reaction. Every 18 to 24 months, the oldest fuel assem-blies are removed from the reactor and replaced with fresh fuel. High-level nuclear waste volumes are small. Davis-Besse produces about 30 tons of used fuel every 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 1 about five yards deep. All of America's nuclear plants combined produce only 3,000 tons of used fuel each year. By contrast, the U.S. produces about 300 million tons of chemical waste annu-ally. Also, nuclear waste slowly loses its radioactivity, but chemical waste remains hazardous I indefinitely. Davis-Besse presently stores its used fuel in a steel-lined concrete vault, filled with water, inside ! the plant. The Department of Energy is charged with constructing a permanent high-level waste ; repository for all of the nation's nuclear plants._By law, the Department of Energy must accept fuel from utilities by the end of 1998. Currently, Yucca Mountain, Nevada, is being considered as a possible site. Until the permanent DOE site is developed, nuclear plants will be responsible ; for the continued safe storage of high-level waste. At Davis-Besse, the fuel pool reached its ca- l pacity in 1996. At the end of 1996, Davis-Besse began the process of moving the older fuel as- 1 semblies that no longer require water cooling to air cooled concrete shielded canisters. These ' will remain stored onsite until the Department of Energy facilities are ready to receive them. Dry i 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 arrangement at Davis-Besse. 1 20
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Davis.Besse Nuclear PJwer Station 1996 Annual Radiological Environmental Operating Repon . , ! Description of the Davis-BeSse Site - The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the south-westem shore of Lake Erie,just nonh 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). i This section of Ohio is flat and marshy, with maximum elevations of only a few feet above the
- level of Lake Erie. The area originally consisted of swamp forest and marshland, rich in wildlife but unsuitable for settlement and farming. During the nineteenth century, the land was cleared 2
and drained, and has been farmed successfully since. Today, the terrain consists of farmland 3 with marshes extending it, m places for up to two miles inland from the Sandusky Lake Shore Ridge. g ' 15 j d ,
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i C~]Q 'G Figure 9. Dam lieue n near Oak Harbor. Pon Clinton, and the Ottawa National Wildlife Refuge. m l Davis-Desse site is mainly comprised of marshland with a small ponion consisting of farmland. l The marshes are pan of a valuable ecological resource, providing a breeding ground for a variety of wildlife, and a retuye 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, Depanment 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
Divis-Besse Nuclear Power Station 1996 Annual Radiologicd Environmental Operating Report The immediate area near Davis-Besse is sparsely populated; Ottawa County had a population of 40,029 in the 1990 census. The nearest incorporated communities are:
- Port Clinton - 10 miles southeast, population 7,106
- Oak Harbor - 7 miles south, population 2,637 e Rocky Ridge - 7 miles west southwest, population 425
. Toledo (the nearest major city) - 25 miles west, population 322,943 There are some residences aloag 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 ofincome in the area. The main industries within five miles of the site are lo-cated in Eric 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 Depanment of Natural Resources, Division of Wildlife. The State of Ohio Department of Natural Resources operates many wildlife and recrea-tional areas within 10 miles of the Station. These include Magee Marsh, Turtle Creek, Crane Creek State Park, and t' 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 southem 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 Station 1996 Annual Radiological Environmental Operating Repon References
- 1. " Basic Radiation Protection Criteria," Report No. 39, National Council on Radiation Protec-tion and Measurem:nt, 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 Prote.ction and Measurements, Washington, D.C. (December 1976).
t
- 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 Rrdiation: BEIR V," Committee on the Biological Effects of Ionizing Radiations, Board en RJiation 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 ofIndoor Radon,"
Seminars in Nuclear Medicine, Vol. XVIII, No.1, American Medical Association, Chicago, IL. (January 1987).
- 9. Hurley, P.,"Living with Nuclear Radiation," University of Michigan l'ress, Ann Arbor, MI.
(1982). 1
- 10. " Indoor Air Quality Environmental Information Handbook: Radon," prepared for the United States Department of Energy, Assistant Secretary for Environment, Safety and Health, by Mueller Associated, Inc., Baltimore, MD. (January 1986).
- 11. Introduction to Davis-Besse Nuclear Power Station Plant Technology, July 1992, Rev. 4, Pg.2-9.
- 12. ' Ionizing Radiation Exposure of the Population of the United States," Report No. 93, Na-tional Council on Radiation Protection and Measurements, Washington, D.C. (September 1987).
- 13. " Natural Background Radiation in the United States," Report No. 45, National Council on Radiation-Protection and Measurements, Washington, D.C. (November 1975).
i 24
Davis-B:sse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report l j 14. " Nuclear Energy Emerges from 1980's Poised for New Growth," U.S. Council for Energy Awareness, Washington, D.C, (1989). l
- 15. " Nuclear Power: Answers to Your Questions," Edison Electric Institute, Washington, D.C.
l (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 Nu-clear Corporation, Middletown, PA. (1985).
- 19. " Sources, Effects and Risk of Ionizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation,1988 Report to the General Assembly, United Nations, New York (1988).
- 20. " Standards for Protection Against Radiation," Title 10, Pan 20, Code of Federal Regulation, Washington, D.C. (1988).
- 21. " Domestic Licensing of Production and Utilization Facilities," Title 10 Part 50, Code of Federal Regulations, Washington, D.C. (1988).
- 22. " Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40, Part 190, Code of Federal Regulations, Washington, D.C. (1988).
- 23. " Tritium in the Environment," Repon 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). _
P
*e-25
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon
.l Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at Davis-Besse for several reasons: to provide a supplementary check on the adequacy of containment and effluent controls, to assess the radiological impact of the Station's operation on the surrounding area, and to determine compliance with applicable radiation protection guides and standards. The REMP was established in 1972, five years before the Station became operational. This preop-erational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of Davis-Besse. After Davis-Besse became op-erational in 1977, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas.
A variety of environmental samples are collected as part of the REMP at Davis-Besse. The se-lection of sample types is based on the established critical pathways for the transfer of radionu-clides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population char-acteristics, and land usage in the area of interest. The selection of sampling frequencies for the various environmental media is based on the radionuclides of interest, their respective half-lives, and their behavior 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 moni- , toring prior to constmeting the facility. This preoperational surveillance program is aimed at collecting the data needed to identify critical pathways, including selection of the radioisotope and sample media combinations to be included in the surveillance program conducted after facil-ity operation begins. Radiochemical analyses perfonned on the environmental samples should j 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 l 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 i 1 j
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report The preoperational surveillance design, including nuclide/ media combinations, sampling fre-quencies and locations, collection techniques, and radioanalyses performed, should be carefully considered and incorporated in the design of the operational surveillance program. In this man-ner, data can be compared in a variety of ways (for example: from year to year, location to loca-tion, etc.) in order to detect any radiological impact the facility has on the surrounding environment: Data collection during the preoperational phase should be planned to provide a comprehensive database for evaluating any future changes in the environment surrounding the , nuclear facility. Davis-Besse began its preoperational environmental surveillance program five years before the Station began producing power for commercial use in 1977. Data accumulated during those early years provide an extensive database from which Station personnel are able to identify trends in the radiological characteristics of the local environment. The environmental surveillance pro-gram at Davis-Besse will continue after the Station has reached the end of its economically use-fut life and decommissioning has begun. s Operational Surveillance Program Objectives 1 The operational phase of the environmental surveillance program at Davis-Besse was designed with the following objectives in mind: I e to fulfill the obligations of the radiological surveillance sections of , the Station's Technical Specifications and Offsite Dose Calculation { Manual; i 1 e to determine whether any significant increase occurs in the con-l centration 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-active materials.
Quality Assurance An important part of the environmental monitoring program at Davis-Besse is the Quality As- i 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;
~
e performing audits of contractor laboratories which analyze the en-vironmental samples; 27
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon 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-partment and the NRC. In addition, the NRC and the Ohio Department of Health (ODH) also perform independent environmental monitoring in the vicinity of Davis-Besse. The types of samples collected and the sampling locations used by the NRC and ODH were incorporated in Davis-Besse's REMP. Hence, the analytical results from the different programs can be com-pared. This practice of comparing results from identical samples, collected and analyzed by dif-ferent parties, 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 As-surance program into the REMP. Duplicate samples, called quality control samples, were col-lected at several locations. These duplicate samples were assigned different identification numbers than the numbers assigned to the routine samples. This ensured that the analytical labo-ratory would not know the samples were identical. The laboratory results from analysis of the quality control samples and the routine samples could then be compared for agreement. Quality control sampling has been integrated into the program and has become an important part of the REMP since 1987. Quality control sampling locations are changed frequently in order to dupli-cate as many sampling locations as possible, and to ensure the contractor laboratory has no way of correctly pairing a quality control sample with its routine sample counterpart. Program Description . 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 .rMvis-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
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon i . - e terrestrial - including samples of milk, groundwater, broad leaf vegetation, fruits animal / wildlife feed, soil, eggs, and wild and domes-4 , tic meat j- e aquatic - including samples of treated and untreated surface water, fish, and shoreline and bottom sediments
- e ' direct radiation -- measured by thermoluminescent dosimeters r
All environmental samples are labeled using a sampling code. Table 2 provides the sample codes and collection frequency for each sample type. REMP samples are collected onsite and offsite up to 25 miles away from the Station. Sampling locations may be divided into two general categories: indicator and control. Indicator locations are those which would be most likely to display the effects caused by the operation of Davis-Besse. Generally, they are located within five miles of the station. Control locations are those which should be unaffected by Station operations. Typically, these are more than five miles away from the Station. Data obtained from the indicator locations are compared with data from the control locations. This comparison allows REMP personnel to take into account naturally occurring background radiation or fallout from weapons testing in evaluating any radiological impact Davis-Besse has on the surrounding environment. Data from indicator and control loca-tions are also compared with preoperational data to determine whether significant variations or trends exist. Since 1987, the REMP has been reviewed and modified to develop a comprehensive sampling program adjusted to the current needs of the utility. Modifications have included additions of sampling locations above the minimum amount required in the ODCM and increasing the num-ber of analyses performed on each sample. Besides adding new locations, duplicate or Quality Control (QC) sample collection was initiated to verify the accuracy of the lab analyzing the envi-ronrnental samples. These additional samples are referred to as the REMP Enhancement Sam-ples. Over 1700 samples were collected and over 2350 analyses were performed during 1996. In addition,15% of the sampling locations were quality control sampling locations. Table 3 350 3 ne number of the sampling location and number collected for each type. a e f
. " i, i
29
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon , Table 2: Sample Codes and Collection Frequencies Sample Collection Sample Type Code Frequency Airborne Particulate AP Weekly Ahborne Iodine AI Weekly Thermoluminescent TLD Quarterly, Annually Dosimeter r Milk . MIL Monthly (semi-monthly during i grazing season) Groundwater WW Quarterly BLV Broad Leaf Vegetation Monthly (when available) - Surface Water- Treated SWT Weekly : Surface Water - SWU Weekly Untreated ( lake water , monthly ) Fish FIS Semiannually Shoreline / Bottom SED Semiannually Sediment Soil SOI Semiannually i Animal / Wildlife Feed DFE/WFE Annually , Meat-Domestic DME Annually Meet-Wild WME Annually Egg EGG Annually Fruits FRU Annually 4 l 30
. . ._. - = -. . . . _ _ - - - _. . .
Davis-Besse Nuclear Power Station 1996 Annud Radiologicel Enviro:unental Operating Repon ; Sample Analysis When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Davis-Besse REMP include: Gross beta analysis measures the total amount of beta emitting radioactive material present in a sample. Beta radiation may be released by many different radionuclides. Since beta decay gives a continuous energy spectmm rather than the discrete lines or " peaks" associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal concentra-tions of beta emitting radionuclides; it does not identify specific radionuclides. Gross beta analy-sis merely acts as a tool to identify samples that may require further analysis. Gamma spectral analysis provides more specific information than does gross beta analysis. Gamma spectral analysis identifies each gamma emitting radionuclide present in the sample, and
- the amount of each nuclide present. Each radionuclide has a very specific " fingerprint" that al-lows for swift and accurate identification. For example, gamma spectral analysis can be used to '
- identify the presence and amount of iodine-131 in a sample. Iodine-131 is a man-made radioac-tive isotope of iodine that may be present in the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power stations. a Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the amount present. As discussed in the Introduction Section, tritium is an isotope of hydrogen that emits low energy beta panicles.
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 l nuclear weapons testing. Strontium is usually incorporated into the calcium pool of the bio-sphere. In other words, strontium tends to replace calcium in living organisms and becomes in-corporated in bone tissue. The principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from airborne releases. ~ Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure. Table 6 provides a list of the analyses performed on environ- { mental samples collected for the Davis-Besse REMP. Often samples will contain little radioactivity, aqd may be below the lower limit of detection for F, 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 I level. When a measurement of radioactivity is reponed 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 1996 Annual Radiological Enriconmen.al Operating Report Table 3: Sample Collection Summary i Sample Collection Number of Number of Number of Type Type */ Locations Samples Samples (Remarks) Frequency ** Collected Missed Atmospheric Airborne Particulates 10 520 0 Airborne Radiciodine C/W 10 520 0 Terrestrial Milk (Jan.-Dec.) G/M i 12 0 Groundwater G/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 / Fruit G/M 7 17 0 Soil G/S 10 10 10 Animal / Wildlife Feed G/A 4 4 0 Aquatic Treated Comp /WM * *
- 2 30 0 Surface Water G/WM * *
- 4 42 0 Untreated G/WM * *
- 2 17 0 Surface Water G/M 10 60 0 Comp /WM"* 4 55 0 Fish (3 species) G/SA 2 3 3 Shoreline Sediments G/SA 4 8 0 Direct Radiation Thermolummewent C/Q * * * . 93 366 8 Dosimeters (TLD) C/A * *
- 93 89 5
- Type of Collection. C = Continuous; G = Grab; Comp = Composite
" Frequency of Collection: WM = Weekly composite Monthly; W = Weekly "* Includes qu.ility control locatson SM = Semimonthly; M = Monthly; Q = Quarterly; SA = Semiannually; A = Annually 31
l - > l Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report ! 1 Table 4: Radiochemical Analyses Performed on REMP Samples Sample Type Analyses Performed Atmospheric Monitoring l Airborne Particulate Gross Beta l Gamma Spectral l Strontium-89 Strontium-90 Airborne Radioiodine Iodine-131 l Terrestrial Monitoring Milk Gegruna Spectral Iodine-131 Strontium-89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectral Tritium ' Strontium-89 Strontium-90 Broad Leaf Vegetation Gamma Spectral I and Fruits Iodine-131 Strontium-89 Strontium-90 Animal / Wildlife Feed Gamma Spectral Soil Garnma Spectral Wild and Domestic Meat Gamma Spectral Egg Gamma Spectral 33
. _ , - _ -~ . - .. . - . .
Davis-Besse Nuclear Power Station 1996 Annual Radi:logicd Environmental Oper: ting Report Table 4: Radiochemical Analyses Performed on REMP Samples l (continued) i Sample Type Analyses Performed i 1 Aquatic monitoring l Untreated Surface Water Gross Beta ; Gamma Spectral , Tritium Strontium-89 Strontium-90 i Treated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Iodine-131 Fish Gross Beta Ganuna Spectral Shoreline Sediment Gamma Spectral i Direct Radiation Monitoring Thermoluminescent Dosimeters Gamma Dose l l l l 34
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THE TOLEDO EDISON COMPANY DOCUMENT REVIEW 4 CONTINUATION SHEET SHEET ! ED 6864-1-e 7 OF 7 l DOCUMENT TITLE DATE l Annual Radiological Environmental Operating Report 3/21/97 COMMENTS RESPONSE is contrary to the6hemobyl accident. Also, nuclear weapons testing was eliminated during the Carter Administration in the United States, therefore the 1981 report would be after the last US test.
- 7) Water Treatment - Treatment System (Page 144) - First l
paragraph states that the traveling screens remove large # particles. This should be removed because as implied in the text following, particles are small where as the screens k only removes debris greater than 1/2"in size.
- 8) Zebra Mussel Control- Page 145 - First paragraph l states that zebra mussels were introduced into North American Waters in 1988. They were actually introduced in 1986 according to all of the documentation found.
- 9) Zebra Mussel Control- Page 146 - Mussels have also I been found on the trash racks, and the intake ba[3 walls I prior to the traveling screens. These mussels are periodically cleaned off using high pressure water. Also no mention of the control methods used at Davis-Besse is gM(
rpparent in the document. We use continuous low level chlorination of the intake bays as a biocide which also controls the mussels in the plant. When the chorination system was down for an extended period of time in 1995, l zebra mussels did infiltrate the plant service water system. hb 4/3/?1 9 l amas
THE TOLEDO EDISON COMPANY FILE DOCUMENT REVIEW l ED 6864-14 DATE 3/20/97 SHEET 1 OF 2 REVIEW SUBMITTED TO REVIEW CONDUCTED BY ORGANIZATION INDIVIDUAL ORGANIZATION INDIVIDUAL SYME G. R. McIntyre SYME J.L. Lee A RESPONSE To EACH COMMENT is REouEsTED, PLEAsE
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O No RESPONSE REQUESTED @ RETURN THis FORM WITH YouR RESPONSE IN THE SPACE PRoVloED DOCUMENT WILE Annual Radiological Environmental Operating Report COMMENTS RESPONSE
- 1) Executive Summary - Chemical Waste Management (Page xii)- the section states that 2,750 pounds of n
hazardous waste was produced in 1996 amounting to a fu 70% increase over 1995. There needsto be a reason stated for this increase to be consistant, ib4v/d eypaged.
- 2) Station Systems - The Condenser (Page 17)- First par graph states " The condensed water is then purifieo 0V W
stnd reheated . ". This statement is not true as stated, only N4 a v ry small portion of the condensed water is purified.
- 3) Station Systems - The Cooling Tower (Page 18)- First paragraph states the circulation water is warmed to approximately 100 F and the cooling tower cools the water
[ down to around 70 F. This statement is true ONLY under very specific ambient conditions. Make this a generic stat: ment such as the cooling tower removes the heat pick d up in the water while passing through the condenser.
- 4) Miscellaneous Station Safety Systems - Page 18 - third paragraph implies the Auxiliary Feedwater System in used under normal conditions if the main feedwater supply is not sufficient and following a reactor shutdown. This is not true and should be clarified to state that it is an emergency 4p g O system use in the event NO main feedwater is available during an accident. This paragraph also states that the Auxiliary feedwater system is housed in the Turbine Building when it is actually part of the Auxili, ry Building with the entrance from the Turbine Building.
- 5) High-Level Nuclear Waste - Page 20 - second paragraph - This paragraph is very misleading because it contains out dated information and it compares high-level ~ , (()
weste to chemical waste inappropriately. It also makes a g( ( wrong claim that chemical waste remains hazardous b ind: finitely which is untrue except for elemental material that is classified as hazardous.
- 6) Sample History Comparison - Page 35 - General comment-justify why it is believed that nuclear weapons 1: sting fallout was the cause of elevated levels of iodine and c:sium. As it currently reads, terrestrial monitoring and 9 th M. pg4 cirborne monitoring contradict each other especially when pC compared to the 6.hernobfl accident. Increased levels uf white found in both atmospheric and terrestrial monitoring ) M I p rs for the Ehernobyl accident in a relatively short time after the cccident. For the years associated with weapons testing, th3 terrestrial monitoring appears to lag atmospheric which
Davis-Besse Nuclear Power Station 1996 Annual Radiologicd Environmental Operating Report i Sample History Comparison j 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 rea-l son 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 op-erational data. Additionally, the results of indicator and control locations are also compared. This allows REMP personnel to track and trend the radionuclides present in the environment, to ' assess whether a buildup of radionuclides is occurring and to determine the effects, if any, the operation of Davis-Besse is having on the environment. If any unusual activity is detected, it is investigated to determine whether it is attributable to the operation of Davis-Besse, or to some other source such as nuclear weapons testing. A summary of the REMP sample analyses per-formed from 1972 through the current reporting period is provided in the following section. Atmospheric Monitoring 4 e Airborne Particulates: No radioactive particulates have been detected as a result of Davis-Besse's operation. Only natural and fallout radioactivity from nuclear weapons testing and the 1986 nu-l clear accident at Chernobyl have been detected. Airborne Radiolodine: Radioactive iodine-131 fallout was de-tected in 1976,1977, and 1978 from nuclear weapons testing, and
; in 1986 (0.12 to 1.2 picoeuries per cubic meter) from the nuclear d
accident at Chernobyl. Terrestrial Monitoring:
- 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-l ries / liter respectively. In 1986, concentrations of 8.5 picocuries/
l liter were detected from the nuclear accident at Chernobyl. No io-l 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. e Broad Leaf Vegetation and Fruits: Only naturally occurring ra-dioactive material and material from nuclear weapons testing has been detected. 35
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Opercting 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 founh quarter sample in 1979 read 590 picoeuries per liter, and the first quarter sample in 1980 had a concentration of 960 pi-cocuries per liter. A follow up sample was collected in Lake Erie between T-7 and the Davis-Besse liquid discharge point. This sample contained tritium at a concentration of 2737 picocuries per liter. These concentrations could be attributed to the operation of Davis-Besse. Even so, these results at T-7 were more than 39 times lower than the annual average concentration allowed by the EPA National Interim Primary Drinking Water Regulations (40CFR141), and were only 0.032% of the Maximum Permissible Concentration (MPC of 3,000,000 picoeuries 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 concentration at T-7.
In 1991, the tritium concentration in the untreated surface water at T-130 was above normal background levels. T-130 is located in Lake Erie approximately 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 permis-sible 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-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/1. 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-
Deus-Besse Nuclear Porer Station 1996 Annual Radiological Environmental Operating Report s showed that the tritium had retumed to below the LLD of
. 330 pCi/1.
In the founh quarter of 1994, tritium was detected at 336 94 pCi/1, slightly above the lower limit of detection for tritium, at one of the treated water sampling locations. Tritium was also detected at sev-eral of the untreated water sampling locations at an average con-centration of 470 pCi/l during the 3rd and 4th quarters of 1994. Samples taken in January 1995 indicated that the tritium concen-tration in untreated water was less than the lower limit of detection for tritium in water. For comparison purposes, tritium concentra-tions in Lake Erie untreated surface water, determined during the preoperational sampling period of July 1972 through June 1974, ranged from 180 pCi/l to 590 pCi/l with an average concentration ofless than 300 pCi/1. In 1995, trace amounts of tritium was detected in six untreated water samples collected in May and one sample collected in Octo-ber. The tritium detected ranged between 330 to 1234 pCi/l with an average concentration of 681 pCi/1 This is only 0.12% of the Effluent Concentration Limit of 1,000,000 pCi/l for tritium in an unrestricted area, as stated in 10 CFR 20, Appendix B, Table 2. Subsequent samples taken showed the tritium activity to be <330 pCi/1, During 1996, tritium was detected ranged between 330 to 589 pCi/l with an average concentration of 340.3 pCi/lin 8 untreated surface water samples. The remainder of the untreated surface water sam-ples were <330 pCi/l.
- Fish: Only natural background radioactive material and material from nuclear testing has been detected.
- Shoreline Sediments: Only natural background, material from nuclear testing and from the 1986 nuclear accident at Chernobyl has been detected.
Direct Radiation Monitoring: -
. Thermoluminescent Dosimeters (TLDs): The annur.! average gamma dose rates for the current reponing period recorded by TLDs have ranged from 55.3 to 73.0 millirem per year at control locations and between 31.8 and 84.6 millirem per year at indicator locations. No increase above natural background radiation attrib-utable to the operation of Davis-Besse has been observed.
37 L
i: Davis-Besse Nuclear Power Station 1996 Annual Radi:: logical Environmental Operating Repon .; L 1996 Program Deviations . ! 4 Provided below is a description and explanation of 1996 environmental sample collection ! deviations. i j e Broad leaf vegetation samples during January, February, March, ; j April, May, June, November and December 1996 were unavailable for collection because of seasonal condition or insufficient quantity . j of desimd broad leaf vegetation, i i e T-3 untreated water samples were not collected due to ice on sur-r ! face for the following months : January, Feb, March. T-28 was ! l substituted for T-3 samples. i } e Various TLD's were lost in the field : T-7 location had I",3d ! j' quarter and annual missing. T-203 location had I" quarter and an- l 1 nual missing. Both T-155 and T-208 locations were missing 1",2"d i quarter and annual. T-204 location was missing 2"d quarter and an-( nual. i 4 -e T-12, surface water untreated was not a composite due to failure of ! Toledo Water department collecting sample for various times dur- i ing year. Grab samples taken for these times when composite not ! i available. !
- T-11,4-24-96 untreated surface water compositor found turned off, i Grab sample taken. Power v.. mstored and sampler returned to j 3 service, i
e T-1, air sampler was not reenergized after maintenance 10-1-96. l i - U j e T-28, surface water untreated compositor did not run the week of l j- 10-16-96 ( Tygon tube leaking ). Grab sample taken. The tubing j was replaced and the compositor was returned to service. ! e T-1,2,3 loss of power about 20 hours due to maintenance. Also T-1
- off week of 8-20-96 the breakers tripped unknown reasons. The i breakers were reset and power restored.
- T-7, well water site was changed as the original location put in j cistern . The new location is about one mile west of previous site. i e Added TLD location T-142 and deleted T-61 location due to eagle nesting interfering with collection.
t e In November 1996, the second fish collection of the year was not ; collected. The nets were removed from the indicator location early i in the month because oflow fish harvest. Weather conditions on : the lake also prevented collection prior to the nets being removed.'
. In December 1996, the wild meat (muskrat) sample was not col- !
- lected. Samples could not be purchased from trappers of this area i i
i 38 i
4 Davis-Besse Nuclear Power Station 1996 Annual Radiological Er evironmemal Operating Report because a permit to trap was not issued by the U.S. Fish and Wild-life Department . Atmospheric Monitoring : Air Samples Ewironmental air sampling is conducted to detect any increase in the concentration of airborne radicauclides that may be inhaled by humans or scrve as an external radiation source. Inhaled radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air sam-ples collected by the Davis-Besse REMP include both airborne particulates and airborne ra- , diciodine. Samples are collected weekly with low volume vacuum pumps which draw a continuous sample through a glass fiber filter and charcoal cartridge at a rate of approximately one cubic foot per
- minute. Airborne paniculate samples are collected on 47 mm diameter filters. Charcoal car-tridges are installed downstream of the particulate filters to sample for the airborne radiciodine.
The airborne samples are sent to an offsite contractor laboratory for analysis. At the laboratory, the airborne 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 shon half-life of io- , , ~ dine-131 (approximately eight days), the airbome radiciodine cartridges are analyzed upon re-ceipt by the contractor laboratory. Airborne Particulates : Davis-Besse continuously samples air for airborne radionuclides at ten locations. There are six indicator locations including four around the site boundary (T-1, T-2, T-3, and T-4), one at Sand Beach (T-7), and another at a local farm (T-8). There are four control locations, Oak Harbor (T-9), Pon Clinton (T-11), Toledo (T-12) and Crane Creek (T-27). Gross beta analysis is perfomied on each of the weekly samples. Each quarter, the filters from each location are combined (composite) and analyzed for gamma emitting radionuclides, stron-tium-89 and strontium-90. Beta emitting radionuclides were detected at both the indicator and control locations at average 3 3 concentration of 0.019 pCi/m and 0.020 pCi/m , respectively. Beryllium-7 was the only gamma i emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites. Beryllium-7 is a naturally occurring radionuclide produced in the upper atmosphere by cosmic radiation. No other gamma emitting radionuclides were detected above their respective LLDs.
^ ' Strontium-89 (Sr-89) was not detected above its LLD. Strontium-90 (Sr-90) was detected in one indicator location (T-3) during the first quarter (0.0003 +/- 0.0002 pCi/m3) and two control loca-tions; first quarter ,T-27, at 0.0003 +/- 0.0002 pCi/m3 and second quarter, T-9, at 0.0004 +/-
0.0003. These results show no adverse change in radioactivity in air samples due to operation of the Davis-Besse Nuclear Power Station in 1996. 39
Davis.Besse Nuclear Power Station 1996 Annui4 Radiologicc) Environmental Operating Repart Airborne Iodine-131 Airborne iodine.131 samples are collected at the same ten locations as the airborne particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly, scaled in separate collection bags and sent to the laboratory for gamma spectral analysis. In all of the samples collected in 1996, there was no detectable iodine.131 above the LLD of 0.07 pCi/m3. Gross Bote Air Particulate During 1996 043' ~ , 9 ,
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4
' Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report l r
Table 5: Air Monitoring Locations 1 i Sample Location Type of Number Location Location Description . T-1 I Site boundary,0.6 miles ENE of Station i i T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station i T-4 I Site boundary,0.8 miles S of Station 4
- 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 1 = 1r.dicator C = Control 41
6 DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AIR SAMPLES: SITE q .**TemeM&-----.----' *=,
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. i Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Terrestrial Monitoring The collection and analysis of groundwater, milk, meat, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. Animal and wildlife feed samples provide additional information on radionuclides that may be present in the food a chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere.
Many radionuclides are preser.t 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 e 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 the environment, (for example, in surface soils) as a result of fall-out from nuclear weapons testing and routine releases from nuclear facilities e potassium-40, a naturally occurring radionuclide normally found throughout the environment (including humans) j 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- r erational octa from previous years, control location data, and the types and amounts of radioac-tivity normally released from the Station in liquid and gaseous effluents. Milk Samples .- Milk sampling is a valuab!e 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 conunonly consumed soon after production. The milk pathway involves the deposition of radionuclides from atmospheric re-leases onto forage consumed by cows, The radionuclides present in the forage eating cow be-come incomorated into the milk which is then consumed by humans. 45
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i Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report i
- When milk is available, samples are collected at the indicator location and at the control location once a month from November through-April, and twice a month from May through October.
! Sampling is increased in the summer when the herds are usually outside on pasture and not on
- stored feed. In December of 1993, the indicator location, T-8, was elimir.ated from the sampling j program because the family there went out of the dairy business anc'. sold the herd. The' control j
- location will continue to be sampled monthly in order to gather adoitional baseline data. If any !
- dairy animals are discovered within five miles of the station, efforts will be made to include them ,
j .in the milk sampling program. j i { i The 1996 milk samples were analyzed for strontium-89, strontium 90, iodine-131 and other gunma emitting radionuclides, stable calcium and potassium. A total of 12 milk samples were co:lected in 1996. Strontium-89.was not detected above the U D of 1.2 pCi/l in any of the sam- 1
- ples. Strontium-90 was detected in all samples collected h annual average concentration 'of l 1 strontium-90 was 0.9 pCi/1. For all sample sites, the arraual average concentration was similar to l
l 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 con- ! centrations of barium-140 and cesium-137 were below their respective LLDs in all samples col-
- lected.
l ' Since the chemistries of calcium and strontium are similar, as are potassium and cesium, organ- I i isms tend to deposit cesium radioisotopes in muscle tissue and strontium radioisotopes in bones. i j In order to detect the potential environmental accumulation of these radionuclides, the ratios of , l 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/l) were monitored in milk. i
. These ratios are compared to standard values to determine if build up is occurring. No statisti- ;
cally significant variations in the ratios were observed. 1 J i ! ! )
- Table 6
- Milk Monitoring Location i
~
i , f ! Sample Location ' Type of . l Number Location Location Description 1 f T-24 C Toft Dairy, Sandusky,21.0 miles SE j of Station !
- J 9
j C = Control l I ! I I I i I $ f j 46 l l 3 l i
Davis-Beste Nuclear Power Station 1996 An::ual Radiological Environmental Operating Report Groundwater Samples Soil acts as a filter and an ion exchange medium for most radionuclides. However, tritium and i !. 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 . ground, REMP personnel sample local wells on a quarterly basis to ensum the early detection of any adverse impact on the local groundwater supplies due to Station operation. The wells sam- ! pled include two indicator locations (T-7, T-54), and one control location (T-27). In addition, a ; quality control sample is collected at one of the wells each quarter. The groundwater samples are ! analyzed for beta emitting radionuclides, tritium, strontium-89, strontium-90 and gamma emit- , ting radionuclides. Beta emitting radionuclides average 3.83 pCi/l for indicator locations and 2.75 pCi/l for control locations. Tritium was not detected above the LLD of 330 pCi/1. Strontium-89 was not detected above the LLD of 1.5 pCi/1. Strontium-90 was detected in indicator sample at an average con-centration of 0.48 pCi/1. There were no gamma emitting radionuclides detected above their re-snective LLDs in any of the samples collected. All sample analyses were within normal ranges and were similar to results of previous years. , t Grose Bets Ground water 1982-1996 ! 8 qpu g,
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t o E' E E I E E-I E E E E E E E E Figure 14: Shown above are the annual averages in cross beta in groundwater from 1982 - 1996. This years results are well within the re.gc of previous years. l l 47 i
i Davis-Besse Nuclear Power Station 1996 Annual Radiologic .1 Environmental Operating Report l l\
- 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 l
Station I .i l T-54 I Weis Farm,4.8 miles SW of Station I T-141 QC Roving Site ! I = indicator C = control QC = quality control i . i l l Broad Leaf Vegetation and Fruit Samples
- Fruits and broad leaf vegetation also repmsent a direct pathway to humans. Fruits and broad leaf l
vegetation may become contaminated by deposition of airbome radioactivity (nuclear weapons l fallout or airbome releases from nuclear facilities) or from irrigation water drawn from lake wa-ter receiving liquid effluents (from hospitals, nuclear facilities, etc.). Radionuclides from the soil
- may be absorbed by the roots of the plants and become incorporated into the edible portions.
- During the growing season, edible broad leaf vegetation, such as kale and cabbage, and fruits, such as apples and grapes, are collected from farms in the vicinity of Davis-Besse.
In 1996, 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
- 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, lettuce, and brussel sprout. The fmits collected were apples, pears, and grapes. All samples were ana-lyzed for gamma emitting radionuclides, strontium-89, strontium-90, and iodine-131.
Iodine-131 was not detected above the LLD of.0.026 pCi/g (wet) in any broad leaf vegetation no r above the LLD of 0.013 pCi/g (wet) in fruit samples. The only gamma emitting radionuclide detected in the fruit and broad leaf vegetation samples was potassium-40, which is naturally oc-curring . In both fmit and broad leaf vegetation, strontium-89 was not detected above their LLDs ' of 0.004 pCi/g (wet) and 0.014 pCi/g (wet). Strontium-90 (Sr-90) was detected at average con-centrations of 0.005 pCi/g (wet) for indicator locations and 0.0010 pCi/g (wet) for control loca-tions. In the fruit samples, Sr-90 at location T-8 (indicator) andT-173 (control) was <0.00lpCi/g 2 (wet). All results of analyses were similar to results observed in previous years; this demon-strates that the operation of Davis-Besse had no adverse effect on the surrounding environment. 48
. 1 Davis Besse Nuclear Power Station 1996 Annual Radiologicd Environmental Operating Report 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 R. Minier ,1.8 miles SSE of Station l T-19 I B. Skinner,1.0 mile W of Station T-37 C Bench Farm,13.0 miles SW of Station T-173 C Firelands Winery, Sandusky,20.0 l miles SE of station. I = indicator C = control ; Animal / Wildlife Feed Samples As with broad leaf vegetation and fruit samples, samples of domestic animal feed, as well as vegetation consumed by wildlife, provide an indication of airborne radionuclides deposited in the vicinity of the Station. Analyses of animal / wildlife feed samples also provide data for determin-ing radionuclide concentration in the food chain. Domestic 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 sam-ples, naturally occurring potassium-40, cosmic ray produced radionuclides such as beryllium-7, and fallout radionuclides from nuclear weapons testing may be present in the feed samples.
. 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.
j
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l 49 i
Davis-Besse Nucicar Power Station 1996 Annual Radiological Environmental Operating Repon 2
. 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 I the animal and wildlife feed, only naturally occurring potassium-40 l was detected. All other radionuclides were below their respective l LLDs. The operation of Davis-Besse had no adverse effect on the j surrounding environment. . Table 9: Animal / Wildlife Feed Locations l i Sample Location Type of i Number Location Location Description T-31 I Davis-Besse, onsite roving location i T-34 C Brooks farm, Graytown 8.8 miles W. of the $ Station 4
! T-197 I Lochotzki residence 4.0 miles W of the Station Lemon Road j T-198 I Toussaint Creek Wildlife Area 4.0 miles i WSW of the Station 4 1 = indicator C = control Wild and Domestic Meat Samples
- Sampling of domestic and wild meat provides information on environmental radionuclide con-centrations that humans may be exposed to through an ingestion pathway. The principle path-ways for radionuclide contamination of meat animals include deposition of airbome radioactivity
- on their fomi and drinking water and contamination of their drinking water from radionuclides released in liquid effluents. ,
The REMP generally collects wild meat and domestic meat (chickens) and eggs on an annual ba-
- sis. Wild animals commonly consumed by residents in the vicinity of Davis-Besse include wa-terfowl, deer, rabbits and muskrats. Analyses from animals whose meat is eaten by humans provides general information on radionuclide concentration in the food chain. When evaluating the results from analyses performed on meat animals, it is important to consider the age, diet and mobility of the animal before drawing conclusions on radionuclides concentration in the local environment or in a species as a whole.
50
. ~ . - - - .- . - - . ... .. - - - - - - - - . __. - _ . - - . - - -- .- .
Davis-BIsse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon Both wild and domestic meat samples and eggs were sampled in 1996 as follows: e Domestic Meat: Chickens were collected at one indicator location (T-197) and one control location (T-34). The samples were ana-lyzed for gamma emitting nuclides.
. Wild Meat: Muskrat samples were not obtained because a permit for trapper was not issued.
- e Eggs
- Egg:: were unavailable at both locations at the time of col-lection. T-197 and T-34 did not have any laying chickens.
N i Table 10: Wild and Domestic Meat Locations j Sample Location Type of Number Location Location Description
- T-31 I Onsite roving location ,
i T-34 C Brooks Farm. Graytown,8.8 miles W of
- j. the Station a
4
- T-197 I Lochotzki residence ,4.0 miles W of the Station I Lemon Road 1
I = indicator C = control , j- 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 representative of the actual deposition in the area. Ideally, there should be little or no vegetation i present, because the vegetation could affect the results of analyses. Approximately five pounds 1 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 , i
Davis-Besse Nuclear Power Station 1996 Annual Radiologict! Environmentzi Operating Report i During 1996, soil was collected at ten sites in April. The indicator locations included T-1, T-2, T-3, T-4, T-7, and T-8, The control locations were T-9, T-11, T-12,and T-27. All soil samples were analyzed for gamma emitting radionuclides. The results show that the only gamma emitter detected in addition to naturally occurring Be-7 and K-40, was Cs-137. Cs-137 was found in i both indicator and control locations at average concentrations of 0.21 and i 0.33 pCi/g dry, respectively. The concentrations were similar to that observed in previous years (Figure 15). l Grows Beta in Soll from 1972 to 1996 I i 1.2
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Davis-Besse Nucl:ar Pow:.r Station 1996 Annual Radiological Environmental Operating Repon l l Table 11: Soil Locations l Sample Location Type of ) Number Location Location Description j T-1 I Site boundary,0.6 miles ENE of Station . l T-2 I Site boundary,0.9 miles E of Station l T-3 I Site boundary 1.4 miles ESE of Station T-4 I Site boundary 0.8 miles S of Station 1 T-7 I Sand Beach, main entrance,0.9 miles NW of Station T-8 I Moore Farm,2.7 miles WSW of Station T-9 C Oak Harbor Substation,6.8 miles SW of Station T-11 C Port Clinton Water Treatment Plant,9.5 miles , SE of Station , 1 T-12 C Toledo Water Treatment Plant,23.5 miles l WNW of Station T-27 C Crane Creek State Park,5.3 miles WNW of ! Station ; 1 = indicator C = control l l l I 53
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t DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i TERRESTRIAL SAMPLES: SITE P .
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- i Davis-Besse Nucl ar Power Station 1996 Annual Radiological Environment:.1 Operating Report l Aquatic Monitoring l l
Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-off/ soil erosion, and releases of radioactive material in liquid effluents from hospitals or nu- ! clear facilities. These sources provide two forms of potential exposure to radiation, external and internal. External exposure can occur from the surface of the water, shoreline sediments and from immersion (swimming) in the water. Internal exposure can occur from ingestion of radi-onuclides, either directly from drinking water, or as a result of the transfer of radionuclides through the aquatic food chain with eventual consumption of aquatic organisms, such as fish. To I monitor these pathways, Davis-Besse samples treated surface water (drinking water), unt'eated r surface water (lake or river water), fish, and shoreline sediments. Treated Surface Water Treated surface water is water from Lake Erie which has been processed for human consumption. Radiochemical analysis of this processe<' vater 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 l 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 colle:ted 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-90, gamma emitting radionuclides, and tritium. One QC sample was collected from a rou-tine location which was changed each month. The annual average for beta emitting radionuclides for indicator and control locations were 2.1 and 1.8 pCi/l respectively. These results are similar to previous years as shown in Figure 19. One : quarterly tritium analysis results were slightly above LLD at 383pCi/l all others were less than the LLD of 330 pCi/1. All cesium-137 results were less than the LLD of 10.0 pCi/1. Strontiud39 was not detected in any sample abovo 1.6 pCi/1. Strontium 90 was detected at 0.6 pCi/l at indicator locations and 0.8 pCi/l at contro.' loca. ions. These results are similar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse. i 57
_ 4- - a Davis-Besse Wclear Power Station 1996 Annual Radiological Environmental Operating Report Groes Beta Treated Surface Water 19721996
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n . m Figure 19: Since 1974, the annual concentrations of beta emitting radionuclides in treated surface water samples collected from indicator locations have been consistent with those from control locations. This shows that Davis-Besse has had no measurable radiological impact on surface water used to make drinking water. Table 12: Treated Surface Water Locations 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 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 I = indicator C 9 control QC = quality control 58
Davis-B:sse Nuclear Power Station 19% Annuil Radiological Environmental Operating Repon { i 1 Untreated Surface Water 1 Sampling and analysis of untreated surface water provides a method of assessing the dose to hu- I mans from external exposure from the lake surface as well as immersion in the wat r. It also provides information on the radionuclides present which may affect drinking water, fhh. and ir-rigated crops. 1 Routine Program ' l The routine program is the basic sampling program which is performed year round. Untreated I water samples are collected in the areas of the station intake and discharge and at the water in-takes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo, Davis-Besse, and Erie Industrial Park. A sample is also collected from Lake Erie at the i mouth of the Toussaint River. These samples are collected weekly and composite monthly. The monthly composite is analyzed for beta emitting radionuclides, tritium, and gamma emitting ra-dionuclides. The samples are further composite quarterly and analyzed for strontium-89 and strontium-90. A QC sample is also collected weekly. It is at a different location each month. . Summer Program The summer program is designed to supplement the routine untreated water sampling program in order to provide a more comprehensive study during the months of high lake recreational activ-ity, such as boating, fishing, and swimming. These samples are obtained in areas along the shoreline of Lake Erie. The samples are collected monthly and analyzed for beta emitting radio- . activity, tritium, strontium-89, strontium-90 and gamma emitting radionuclides. l l For the routine samples composite weekly, the beta emitting radionuclides had an average con-centration of 2.6 pCi/l at indicator and 2.8 pCi/l at control locations respectively. The average concentration of beta emitting radionuclides in all samples (include lake water) was 2.85pCi/l at both indication and control locations. ' Of the 130 tritium analyses performed on untreated water,123 were less than the LLD of 330 pCi/l. The tritium detected, ranged from a concentration of 330 pCi/l to 2790 pCi/1. The average concentration of tritium detected above the LLD 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 0.12% of the effluent concentration limit of 1,000,000 pCi/i for tritium in an unrestricted area, as provided by 10CFR20, Appendix B, Table 2, column 2. The uitima detected at the control loca-tion is presumed to come from activities not associated with the operation of Davis-Besse. Cesium-137 and strontium-89 were not detectable in samples of untreated water above their LLDs of 10 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. 59
. -. . .. . . - . . . - . . - - - ~_ -, , . Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operiting Report orose seis ceneenereuen in untreeted surtece wowr from ten to teos . r yr.
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Figure 20: The average concentration of beta emitting radionuclides in untreated water was similar between control and indicator locations. This demonstrates, that Davis-Besse had no radiological impact on the surrounding envi- ' ronment. Each month, weekly quality control samples were collected at different locations. The results of the analyses from the quality control samples were consistent with the routine samples. The av-erage concentrations of beta emitting radionuclides detected at the QC location was 2.8 pCi/l and 2.6 pCi/l at routine locations. Tritium and cesium-137 were below their respective LLDs. There was good agreement between the routine and QC locations. > 1 i I l l
\
l I 60
D vis-Besse Nuclear Power Station 1996 Annual Radiological Environmentd Operating Report l
- 1 Table 13: Untreated Surface Water Locations Sample Location Type of Number Location Location Description T-3 I Site boundary,1.4 miles ESE of Station i
T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant, sample taken from intake crib,11.25 miles NW of Station ' T-28 I Davis-Besse Water Treatment Plant T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE of Station T-131 1 Lake Erie,0.8 miles NE of Station 1 T-132 1 Lake Erie,1.0 miles E of Station 4 T-133 1 Lake Erie,0.8 miles N of Station T-134 1 Lake Erie,1.4 miles NW of Station T-135 I Lake Erie,2.5 miles WNW of Station l 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 T-158 C Lake Erie,10.0 miles WNW of Station 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 1 l 1 1 61
_ _ . _ - -__ ._ -- _ _. _ .--_ _ .. .--- - - - - - _ _ .- -m -y
- l 4
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental operating Report i i
. I Shoreline and Bottom Sediment l!
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 inges- , 4 tion of fish, through resuspension into drinking water supplies, or as an extemal radiation source ' l from shoreline exposure to fishermen and swimmers. j l l Samples of deposited sediments in water along the shore were collected at various times from 1 three indicator sites (T-3, T-4, and T-132) and one control location (T-27). Shoreline sediment ! I was collected with a shovel, or a hand held dredge. All samples were analyzed for gamma emit- l } ting radionuclides. Naturally occurring potassium-40 was detected at both controls and indicator j locations. Cesium-137 was detected at location (T-4) of 0.033 pCi/g above the LLD of 0.048
- PCi/g.
1 i 1
- Atmospheric testing of nuclear weapons has been the principal source of cesium-137 in the envi-
! l 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- ,! i mately 30 years). No other gamma emitting radionuclides were detected in any of the samples 1 l above their LLD. The concentrations of those detected were consistent with normal concentra- i
- . tions for this area and were not attributed to plant operation.
Table 14: Shoreline and Bottom Sediment Locations j 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 I T-132 I Lake Erie,1.0 miles E of Station
~
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l = indicator C = control 1 l l l 62 l l 1
t Davis.Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report l
, Fish Sample Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondar-ily to serve as indicators of radioactivity in the aquatic ecosystem. The principal nuclides which may be detected in fish include naturally occurring potassium-40, as well as cesium-137, and strontium-90. Depending upon the feeding habit of the species (e.g., bottom-feeder versus predator), results from sample analyses may vary.
With the aid of a local commercial fisherman, Davis-Besse routinely collects three species of fish (walleye, white perch or white bass and carp) twice a year from sampling locations near the Station's liquid discharge point and more than ten miles away from the Station where fish popu-lations would not be expected to be impacted by the Station operation. Walleye are collected be-cause they are a popular sport fish, white perch or white bass be.uuse they are an important commercial fish. Carp are collected because they are bottom feeders and thus would be more likely to be affected by radior.uclides deposited in lake sediments. The edible portion of fish were analyzed for beta and gamma emitting radionuclide.s. The average concentration of beta emitting radionuclides in fish muscle was similar for indicator and control locations (2.93 pCi/g and 3.09 pCi/g wet weight, respectively). Cesium-137 was not detected above the LLD <0.021 for indicator and control locations. No other gamma emitter were detected above their respective LLDs. G ro s e B e ta C o n c e n tra tio n in F is h 1972 1998 4 3.5 d y + E =
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1 . y ; r,, 0 Figure 21: Average concentrations of beta emitting radionuclides in fish samples were similar at indicator and con. ' trol locations and were within the range of results of previous years. 63 ) 1
4 Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Opercting Report Table 15: Fish Locations Sample Location ' Type of Number Location Location Description T-33 I Lake Erie, within 5 miles radius of Station T-35 C Lake Erie, greater than 10 mile radius of Station . I = indicator C= control l I i i 64 j j
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Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon Direct Radiation Monitoring Thermoluminescent Dosimeters Radionuclides present in the air, and those deposited on the ground, may directly irradiate indi-viduals. Direct radiation levels at and around Davis-Besse are constantly monitored by thermo-luminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information. The TLDs used at Davis-Besse contain a calcium sulfate: dysprosium (CaSO4:Dy) card with four main readout areas. Multiple readout areas are used to ensure the precision of the measurements. Thermoluminescence is a process by which iorazing radiation interacts with phosphor which is the sensitive material in the TLD. Energy is ' rapped in the TLD material r.nd can be stored for several months or years. This provides an excellent method to measure the dose received over long periods of time. The energy that was s'ored in the TLD as a result of interaction with radia-tion is released and measured by a controll;d heating process in a calibrated reading system. As the TLD is heated, the phosphor releases tae stored energy in the fomi 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 quarterly and annual basis from a single site, each measurement serves as a quality control check on the other. Over 98 % of the quarterly TLDs placed in the field and 94 % of the annual TLDs placed in the field were retrieved and evaluated during the current reporting period. In 1996, the average dose equivalent for quanerly TLDs at all indicator locations was 12.6 mrem /91 days, and for all control locations was 14.2 mrem /91 days. The average dose 1 equivalent for annual TLDs in 1996 was 56.8 mrem /365 days at indicator locations and j 63.1 mrem /365 days for control locations. l l Quality Control TLDs : 1 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- j ing aware that they are the same. A comparison of the quality control and routine results pro- I vides a method to check the accuracy of the measurements. The average dose equivalent at the j routine TLDs averaged 13.1 mrem /91 days while the quality control TLDs yielded an average i dose equivalent of 12.2 mrem /91 days. All the quality control and routine sample results were similar, demonstrating the accuracy of both the TLDs and the laboratory's measurements. 68
i Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
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Figure 25: The similarity between indicator and control results demonstiated that the operation of Davis-Besse has not caused any abnormal gamma dose. NRC TLD Monitoring The NRC has 22 TLDs located around Davis-Besse as part of their Direct Monitoring Network Pregram. Davis-Besse maintains TLDs at all the NRC TLD monitoring sites. The NRC collects their TLDs on a quarterly basis, whereas Davis-Besse colle.:ts TLDs quarterly and annually at these locations. The NRC TLDs are collected and read independently of Davis-Besse's TLDs, thus providing a quality control check on both laboratories. t l The NRC uses Panasonic Model UD801 TLD, which has two elements of lithium borate: copper (Li 2B 40 7: 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 13.2i2.3 mrem /91 days for the Davis-Besse TLDs and 15.8i2.6 mrem /91 days for the NRC TLDs. As the confidence intervals overlap, there is no statistical difference between the meas-t urements. I t I 1 l l r er i t j 69
. i Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report NRC and Davis Besse TLD Results for 1988-1996 s
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! Sample Location Type of I i Number Location Location Description I
) T-1 1 Site boundary,0.6 miles ENE of Station
-T.2 1 Site boundary,0.9 miles E of Station T-3 i Site boundary,1.4 miles ESE of Station T-4 1 Site boundary,0.8 miles S of Station T-5 i S.its boundary,0.5 miles W of Station T6 1 Site boundary,0.5 miles NNE of Station T-7 1 Sand Beach, main entrance 0.9 miles NW of I Statiu T-8 1 Earl Moore Farm,2.7 miles WSW of Station ,
4 T.9 C Oak Harbor Substation,6.8 miles SW of i Station 70
i
- Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Table 16
- ThermolumineScent Dosimeter Locations (continued)
- - Sample Location Type of ;
Number Location Location Description , T-10 I Site boundary,0.5 miles SSW of station near i
- warehouse i
T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles ' l WNW of Station i , T-24 C Sandusky,21.0 miles SE of Station i T-27 C Crane Creek State Park,5.3 miles WNW of Station T-38 I Site boundary,0.6 miles ENE of Station T-39 I Site boundary 1.2 miles ENE of Station T-40 I Site boundary,0.7 miles SE of Station T-41 I Site boundary,0.6 miles SSE of Station T-42 i Site boundary,0.8 miles SW of Station e T-43 I Site boundary,0.5 miles SW of Station l T-44 i Site boundary,0.5 miles WSW of Station T-45 I Site boundary,0.5 miles WNW of Station J T-46 i Site boundary,0.5 miles NW of Station T-47 1 Site boundary,0.5 miles N of Station T-48 i Site boundary,0.5 miles NE of Station i l T-49 i Site boundary,0.5 miles NE of Station T 50 1 Erie Industrial Park, Port Clinton, 4.5 miles SE of Station T-5i C on Siren Pole,5.5 miles SSE of Station i 71 , I
-- _ . _ . - = . . . - , _ . - - - - - - ..
Davi: Lesse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon 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-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.! mile NNW of Station ! T-73 I Site boundary,0.1 mile WSW of Station T-74 I Site boundary,0.1 mile SSW of Station
. T-75 I Site boundary 0.2 mile SSE of Station T-76 I Site boundary. 0.1 mile SE of Station T-80 QC Qtrality Control Site j
T-81 QC Quality Control Site T-82 QC Quality Control Site l T-83 QC Quality Control Site T-84 QC Quality Control Site t i 72 l
D;vis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued) Sample Location Type of Number Location Locailon Description J T-85 QC Quality Control Site ! T-86 QC Quality Control Site J T-88 QC Quality Control Site s T-87 QC Quality Control currently located in lead pig, 4 DBAB annex T-89 QC Quality Control Site T-91 I State Route 2 and Rankie Road,2.5 miles SSE
- of Station
) T-92 I Locust Point Road,2.7 miles WNW of Station 3 T-93 I Twelfth Street, Sand Beach,0.6 miles NNE of * , Station 1 T-94 I State Route 2,1.8 miles WNW of Station 1 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 T-114 QC Quality Cont ol Site T-ll5 QC Quality Control Site ! ! T-i16 QC Quality Control Site T-117 QC Quality Control Site T-118 , ._ QC Quality Control Site
. T-119 QC ' Quality Control Site l
73
e Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report i Table 16: ThermolumineScent Dosimeter Locations (continued) ! Sample Location Type of Number Location Location Description T-120 QC Quality Control Site T-121 I State Route 19,2.0 miles W of Station T-122 I Duff Washa and Humphrey Road,1.7 miles W of Station T-123 I Zetzer Road,1.6 miles WSW of Station i T-124 C Church and Walnut Street, Oak Harbor,6.5 , miles SSW of Station T-125 I Behlman and Bier Roads,4.4 miles SSW of Station T-126 I Camp Perry Western and Toussaint South Road, 3.7 miles S of Station T-127 I Camp Perry Western and Rymers Road,4.0 miles SSE of Station T-128 I Erie Industrial Park, Port Clinton Road, 4.0 miles SE of Station T-142 I Site Boundary,0.8 miles SSE of Station T-150 I Humphrey and Hollywood Road,2.1 miles NW of Station T-151 I State Route 2 and Humphrey Road,1.8 miles WNW of Station T-153 I Leutz Road,1.4 miles SSW of Station T-154 I State Route 2,0.7 miles SW of Station ' T-155 C Fourth and Madison Streets, Port Clinton,9.5 miles SE of Station T-200 , . . . QC Quality Control Site T-201 I Sand Beach,1.1 miles NNW of Station i 74
-e Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)
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 j l T-205 I Sand Beach,0.5 miles NNE of Station i 1 T-206 I Site Boundary,0.6 miles NW of Station 1 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 l I I i l l l 75
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8 Dcvis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
) ! CODCluSiOD The Radiological Environmental Monitoring Program at Davis-Besse is conducted to determine the radiological impact of the Station's operation on the environment. Radionuclide concentra-tions measured at indicator locations were compared with concentrations measured at control lo-cations, in previous operational studies and in the preoperational surveillance program. These comparisons indicate normal concentrations of radioactivity in all environmental samples col-lected in 1996. Davis-Besse's operation in 1996 had no adverse impact on the residents and envi-ronment surrounding the station. The results of the sample analyses performed during the period of January through December 1996 are sununarized in Appendix D of this report.
e I 1 2 i 4 1 1 a m 79 , l
, ._ . - - . ~ - _ _ . - - . _ _ __~ _ _ _ _ .. _. . . s D;vis-Besse Nuclear Power Station 1996 Annualltadiological Environmental Operating Repon References
- l. " Cesium-137 from the Environment to Man: Metabolism and Dose," Report No.52, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1977).
- 2. " Environmental Radiation Measurements," Report No.50, National Council on Radiation Protection and Measurement, Washington, D.C. (December 1976).
- 3. " Exposure of the Population in the United States and Canada from Natural Background Ra-diation," Report No.94, National Council on Radiation Protection and Measurement, Wash-ington, D.C. (December 1987).
- 4. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy Instal-lations," DOE /EP-0023, Department of Energy, Washington, D.C. (July 1981).
- 5. "lonizing Radiation Exposure of the Population of the United States," Report No.93, Na-tional Council on Radiation Protection and Measurement, Washington, D.C. (September 1987).
- 6. " Natural Background Radiation in the United States," Report No.45, National Council on Radiation Protection and Measurement, Washington, D.C. (November 1975).
- 7. " Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion 'As Low As Reasonably Achievable' for Radioactive Materialin Light Water -
Cooled Nuclear Power Reactor Effluents," Code of Federal Regulations, Title 10 Energy, Part 50 " Domestic Licensing of Production and Utilization Facilities," Appendix I(1988).
- 8. " Performance. Testing and Procedural Specifications for Thermoluminescent Dosimetry,"
American National Standards Institute, Inc., ANSI-N45-1975, New York, New York (1975). ;
- 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).
- 10. " Radiological Assessment: Predicting the Transpon , Bioaccumulation and Uptake by Man of Radionuclides Releawd to the Environmenh" Report No.76, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1984). I
- 11. Regulatory Guide 4.1. " Programs for Monitoring Radioactivity in the Environs of Nuclear ,
Power Plants." US NRC (April 1975). i l
- 12. Regulatory Guide 4.13. " Performance, Testing, and Procedural Specifications for Thermolu-minescent Dosimetry: Environmental Applications," US NRC (July 1977).
l l l 80
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report .
- 13. Regulatory Guide 4.15," Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment," US NRC (February 1979).
- 14. Regulatory Guide 0475, " Radiological Environmental Monitoring by NRC Licensees for Routine Operuons of Nuclear Facilities," US NRC (September 1978).
- 15. Regulatory Guide 0837, "NRC TLD Direct Radiation Monitoring Network," US NRC :
(1996).
- 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).
j 18. Teledyne Isotopes Midwest Laboratory, " Final Monthly Progress Report to Toledo Edison
- Company", (1991-1996).
l
- 19. Teledyne Isotopes Midwest Laboratory, "Preoperational Environmental Radiological Moni-toring for the Davis-Besse Power St ition 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 l
l Effluent Technical Specifications," Volume 1, Appendix A to License No. NPF-3.
- 22. Toledo Edison Company," Final Environmental Statement -Related to the Construction of Davis-Besse Nuclear Power Station," Docket #50-346 (1987). *
- 23. Toledo Edison Company," Performance Specifications for Radiological Environmental Monitoring Program." S-72N.
l
- 24. Toledo Edison Company. " Radiological Environmental Monitoring Program," DP-HP-00015. _
- 25. Toledo Edimn Company, " Radiological Environmental Monitoring Quarterly, Semiannual, and Annual Sampling". DB-HP-03004.
- 26. Toledo Edimn Company," Radiological Monitoring Weekly, Semimonthly, and Monthly Sampling," DB HP-03005.
4
- 27. Toledo Edison Company,"REMP Enhancement Sampling," DB-HP-10101.
l i 81 l
i' l
- Davis-Besse Nuclear Power Station 1996 Annual Radiologict .onmental Operating Repon l
- 28. Toledo Edison Company, " Updated Safety Analysis for the Offsite Radiological Monitoring
. Program," USAR 11.6, Revision 14,(1992). ' ' l
- 29. Toledo Edison Company, " Annual Radiological Environmental Operating Report Preparation i
! and Submittal," DB HP-00014. , 30. Toledo Edison Company, Davis-Besse Nuclear Power Station, Offsite Dose Calculation i Manual 1 i i , 31. " Tritium in the Environment," Report No. 62, National Council on Radiation Protection and ;
- Measurements, Washington, D.C. (March 1979).
)
l l l i i 1 l i 1 i I l l l I 82
Davis-Besse Nuclear Pow:r Station 1996 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31,1996 __
- Protection Standards 3
Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ioniz- l
- ing radiation were recognized and efforts were made to establish radiation protection standards.
The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these 4 recommendations have been given legislative authority through publication in the Code of Fed-eral Regulations (CFR) by the Nuclear Regulatory Commission (NRC). The main objective in the control of radiation is to ensure that any dose is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA). The ALARA principle ap- ; plies to reducing radiation dose both to the individual working at Davis-Besse and to the general l 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 j minimize health risk and environmental detriment and ensure that doses are maintained well be-
- low regulatory limits. ;
1 Sources of Radioactivity Released l 1 I , During the normal operation of a nuclear power station, most of the fission products are retained within the fue' 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. l 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 ocIcur from valves, piping or equipment associated with the primary coolant system. These liquids are collected through a series of floor and equipment drains and sumps. All liquids of this nature are monitored and processed, if neces-sary, prior to release.
Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologically and chemically nonreactive. 83
Davis-B:.sse Nuclear Pow:r Station 1996 Annual Radiological Environmentil Operating Report They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an extemal source of radiation exposure to the body. Xenon-133 and xenon-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive no-ble gases released. They are readily dispersed in the atmosphere. Iodine and Particulates Annual releases of radioisotopes of iodine, and those particulates with half-lives greater than 8 days, in gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing sys-tems, minimize their discharge. The predominant radiciodine released is iodine-131 with a half-life of approximately eight days. The main contribution of radioactive iodine to human dose is to the thyroid gland, where the body concentrates iodine. The principal radioactive particulates released are fission products (e.g., cesium-134 and cesium-137) and activation products (e.g., cobalt-58 and cobalt-60). Radioactive cesium's and cobalt's contribute to intemal 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 fonn 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 dees not exceed regulatory limits. Efiluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance pro-grams for effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring. The radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gaseous wastes which contain radioactivity. For example, the Waste Gas Decay Tanks are holding tanks which allow radioactivity in gases to decay prior to release via the station vent. Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits. These instruments provide a continuous indication of the radioactivity present. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure the limits will not be exceeded. If a monitor alarms, a release from a tank is automati-cally stopped. ._ 84
Davis-Besse Nuclear Pow:r Station 1996 Annual Radiological Environmental Operating Report
'All wastes are sampled prior to release and analyzed in a laboratory to identify the specific concentrations of radionu-clides being released. Sampling and analysis provide a more sensitive and precise method of determining effluent composition than with monitoring instmments alone.
't A meteorological tower is located in the southwest sector of the Station. It is linked to computers which record the meteorological data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public. Beyond the plant, devices maintained in conjunction with the Radiological Environmental Monitoring Program con-stantly sample the air in the st:rrounding environment. Frequent samples of other environmental media, such as water and vegetation, are also taken to detennine 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 radioactive material. The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the environment. The environmental transport mechanism includes consideration of physi-cal factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An Annual aver-age on the water flow, wind speed , and wind direction are used to evaluate how the radionuclides will be distributed in an area for gaseous or liquid releases. An important factor in evaluating the expostre pathways is the use of the en-vironment. Many factors are considered such as dietary intake of residents, recreational use of the area, and the loca-tions 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 inwives pathways such as extemal whole body exposure, deposition of radioactive material on plants, depo-sition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radio-active material in liquid efGuents involves pathways such as drinking water, fish consumption, and direct exposure from the lake at the shoreline and while swimming. e 85
. . ..- ~ ~. . . . - ~ ~ - - . - . - - - - - . - ~ . - - - ~ - - -
2 j
. 1 1
' Davis.Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report i j Diluted By Atmosphere Airborne Releases 1 D l
~ Animals
* \ "
4 (Milk, Meat) *** y.3J@ 1
~ .," x k1.M m ,f
;l i ~
Consumed l'} i p'" By Man 4..% , Liquid Releases j Consumed Diluled By tske 1 By Animals
)
U Vegetation Consumed By Man M "A"s**d N - (@0 ~ FISH ; ro Soil MAN Drinking Water
]r 1M % Shoreline Exposure /
l f 3 ,
. e LAKE 1
p: .e , , I } Figure 30: The exposure pathways shown here, are monitored through the Radiological Environmental Monitoring I Program (REMP), and are considered when calculating doses to the public. l
, 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
- i. diet of the group, or other cultural factors. The dose may be delivered to the whole body or to a i specific organ. The organ receiving the greatest fraction of the dose is called the critical organ.
i-Dose Assessment j- 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. j 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-j dionuclides remain for very short times due to their rapid radioactive decay and/or elimination j
{ rate from the body, while other radionuclides may remain in the body for longer periods of time. j i i 4 3 86
.I
. _ _ _ _ . . . . . _ . _ _ . _ - _ - .. _m__..
l Davis-Bisse Nuclear Pont Station 1996 Annual Radiological Environmental Operating Report !
- i
- The dose to' the general public in the area surrounding Davis-Besse is calculated for each liquid l or gaseous release. The dose due to radioactive material released in gaseous effluents is calcu- f lated using factors such as the amount of radioactive material released, the concentration beyond l
the site boundary,' the average weather conditions at the time of the release, the locations of expo- ' sure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors , (inhalation, food consumption). The dose due to radioactive material released in liquid effluents ' is calculated using factors such as the total volume of liquid, the total ' volume of dilution water, : near field dilution, and usage factors (water and fish consumption, shoreline and swimming fac. .; tors). These calculations produce a conservative estimation of the dose. Results I t The Radioactive Effluent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Station during the period from January 1,1996 through December 31,- ; 19%. j e Summation of the quantities of radioactive material released in gaseous and liquid effluents i e Summation of the quantities of radioactive material contained in solid waste packaged and ; shipped for offsite disposal at federally approved sites > e ' A listing of all radioactive effluent monitoring instrumentation required by the Offsite Dose Calculation Manual, but which were inoperable for more than 30 days During this reporting period, the estimated maximum individual offsite dose due to radioactivity l released in effluent was: Liquid Effluents: e 9.60E-02 mrem, whole body
. 1.22E-01 mrem, liver Gaseous Effluents:
Noble Gas:
- 4.59E-03 mrad., whole body e 1.90E-02 mrad, skin Iodine - 131. Tritium, and Particulates with Half-lives greater than 8 Days:
c e 4.79E-03 mrem, whole body
- 3.05E-02 mrem, 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 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 87
Davis-Beste Nuclear PowGr Station ~ 1996 Annual Radiological Environmental Operating Report ' liquid effluents, the additional pathways include the Turbine Building drains via the settling ba-sins. Releases via ti.ese pathways are included in the normal release tables in this report. Regulatory Limits Gaseous Effluents ~ In accordance with Offsite Dose Calculation Manual, dose rates due to radioactivity released in . gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following: Noble gases:
- Released at a tag equal to or less than 500 mrem TEDE per year. (Note: the total d_qs due to these releases is also limited to 50 mrem in any calendar year.)
e Released at a Iam such that the total dose to the skin will be less than or equal to 3000 mrem in a year. Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
- Released at a rate such that the total dose to any organ will be less than or equal to 1500 mrem in a year.
In accordance with 10CFR50, Appendix I, Sec. IIB.1, air dose due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
- Iess 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. j e less than or equal to 10 mrad total for ganuna radiation and less than or equal to !
20 mrad total for beta radiation in any calendar year. l In accordance with 10CFR50, Appendix I, Sec. IIC, dose to a member of the public from Iodine- l 131, tritium, and all radionuclides in paniculate form with half-lives greater than 8 days in gase- . ous effluents released to areas at and beyond the site boundary shall be limited to the following: !
- Less than or equal to 7.5 mrem total to any organ in any calendar quarter. ;
e Less than or equal to 15 total mrem to any organ in any calendar year. I f I l l 88 l
),
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon ; i Liquid Effluents In accordance with 10CFR50, Appendix I, Sec IIA, the dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to accumulated doses of: l l
, e less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem !
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/mi of air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2. Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and activa-tion products to less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radio-activity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable. Measurements of Total Activity Fission and Activation Gases: These gases, excluding tritium, are collected in a marinelli beaker specially modified for gas sampling, steel flasks, or glass vials and are counted on a germanium detector for principal gamma emitters. Radionuclides that are detected are quantified via gamma spectroscopy.
~
Tritium gas is collected using a bubblier apparatus and counted by liquid scintillation. Iodine's lodine's are collected on a charcoal canridge filter and counted on a germanium detector. Spe-
'cific 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
D;vis-Besse Nuclear PowIr Station 1996 Annual Radiological Environmental Oper: ting Report 4 Liquid Effluents Liquid effluents are collected in a marinelli beaker and counted on a germanium detector. Quantification of each gamma-emitting radionuclide present in liquid samples is via gamma spectroscopy. 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 1/1/96 through 12/31/96
- 1. Number of batch releases: 84
- 2. Total time period for the batch releases: 148.5 hours
- 3. Maximum time period for a batch release: 250 minutes
- 4. Minimum time period for a batch release: 66 minutes
- 5. Average time period for a batch release: 106 minutes Gaseous from 1/1/96 through 12/31/96
- 1. Number of batch releases: 17
- 2. Total time period for the batch releases: 235.1 hours
- 3. Maximum time period for a batch release: 5260 minutes
- 4. Minimum time period for a batch release: 19 minutes
- 5. Average time period for batch release: 829.8 minutes Abnormal Releases
- 1. Auxiliary Boiler soot blow
- 2. Cooling Tower system valve CT-1 leaked to stonn sewer due to maintenance on the collection box.
- 3. 235 # relief valve lifted during startup.
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 1.1996 through December 31.1996. PERCENT OF SPECIFICATION ANNUAL DOSE . - LIMIT LIMIT R port Period: January 1,1996 - Decemher 31,1996 (gaseous) Noble gases (gamma) 5.25E-03 mrad 10 mrad 5.25E-02 Noble gases (beta) 2.06E-02 mrad 20 mrad 1.03E-02 1-131. tritium and particulates 3.05E-02 mrad 15 mrem 2.03E-01 R port Period: January 1,1996 December 31,1996 (liquid) Total body 9.60E-02 mrem 3 mrem 3.20E+00 Organ 1.22E-01 mrem 10 mrem 1.22E+00 90
Davis-B ,sse Nuclear Powir Station 1996 Annual Radiological Enviro'unental Operating Report l . I Sources ofInput Data l e Water Usage: Survey of Water Treatment Plants (DSR-95-00347) l l
- 0-50 mile meat, milk, vegetable production, and population data: 1982 Annual En-
' vironmental Operating Report entitled, " Evaluation of Compliance with Appendix l I to 10CFR50: Updated Population, Agricuhural, Meat - Animal, and Milk Pro- {
duction Data Tables for 1982." This evaluation was based on the 1980 census; the Agricultural Ministry of Ontario' 1980 report entitled " Agricultural Statistics and ) Livestock Marketing Account,1980"; the Agricultural Ministry of Ontario 1980 report entitled " Agricultural Statistics for Ontario - 1980 Publication 21,1980"; the Michigan Department of Agriculture, July,1981 repon entitled " Michigan Agri-cultural Statistics,1981"; the Ohio Crop Reporting Service,1981 report entitled,
" Ohio Agricultural Statistics,1981."
e Gaseous and liquid source terms: Tables 17 through 21 of this repon. i
. Location of the nearest individuals and pathways by sector out to 5 miles, see Land I Use Census Section of the report.
- Population of the 50-mile Radius of Davis-Besse (DSR-95-00398).
l 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- I sessment of radiation doses from radioactivity released in liquid and gaseous effluents to mem- i bers of the public due to activities inside the site boundary. l In special instances, members of the public are permitted access to the Radiologically Restricted Area within the Davis-Besse Station. Tours for the public are conducted with the assurance that l 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 maximally-exposed visitors is 250 hours (1 hr/ day,5 day / week, 50 wk/yr)
- Annual average meteorological dispersion (conservative, default use of maximum site boundary dispersion).
For direct " shine" from the Independent Spent Fuel Storage Installation (ISFSI),
, default use of the maximum dose rate for a comp leted (full) ISFSI, and a distance of 950 feet.
91
4 Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report to liquid (ffluents could occur. Therefore, the modeling of the oDCM conservatively estimates the maximum poten , tial dose to members of the public.
- Inoperable Radioactive Effluent Monitoring Equipment The following radioactive effluent monitoring equipment required to be operable by ODCM Section 2.1 and 3.1 was inoperable for more than 30 days during this reporting period.
o RE 8433 out of service on 10-07-96 Underground cable repair needed i o Total Dilution Flow, computer point F201, was unavailable from 12/15/96 to 12/31/96 when one of the input points, F886 Service Water Outflow, failed. Upon completion of maintenance activities, the computer point was returned to service. During the time F201 was inoperable, total dilution was estimated using other methods. Changes to the ODCM and PCP There were no changes to the PCP and one change to the ODCM (Revision 10 ). Borated Water Storage Tank Radionuclide Concentration
- The BWST was out of ODCM ( Section 2.2.4- sum of the fractions ) specification from 5/13/96 to 5/15/96. All addi-tions were suspended to the BWST and the demineralizer placed in service to lower the tank concentrations to within the limit. l l
4 4 1 92
r Table 17 i Gaseous Effluents - Summation of All Releases - E? r Est. Total y ' T.s pe ' Unit 1st Qtr 2nd Qtr 3rd Qtr- 4th Qtr' % Error y 1 K ! 1996 1996 1996~ 1996 Z Fission and Activation Gases g Total Release Ci 5.47E+01 4.26E+02 2.15E-01 LLD 2.5E+01 E- l c Average Release Rate for Period
- pCi/sec 6.96E+00 5.42E+01 4.27E-02 LLD y i Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section hf E^
lodines , Total lodines Ci 9.40E-05 2.41 E-03 7.78E-07 2.99E-05 2.5E+01 3! Average Release Rate for Period
- pCi/sec 1.20E-05 3.10E-04 9.90E-08 3.8E-06 [,
8 Percent of ODCM Limits' See Supplemental Information in ODCM Release Limits Section g; E, . ' .: o Particulates g ! Partic 'ates with half-lives greater than 8 days Ci LLD i.40E LLD LLD 2.5E+01 [ . Average Release Rate for Period
- pCi/sec LLD 1.78E-05 LLD LLD y[
Percent of ODCM Limits See Supplemental Information in OIX'M Release Limits Section [ 5 Tritium Total Release Ci 6.57E+00 1.11 E+01 8.91E+00 9.97E+00 2.5E+01 j Average Release Rate for Period
- Ci/sec 8.36E-01 1.41E+00 1.13E+00 1.27E+00 -
Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section y E,
- The average release rate is taken over the entire quarter. It is NOT averaged over the time period of the releases.
i I I
Davis-Besse Nuclear Power Station 1996 Annual Radiological Envircnmental Operating Rrport I J Table 18 Gaseous Effluents - Ground Level Releases Batch Mode
- 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr ,
Nuclide Unit 1996 1996 1996 1996 ' Fission Gases Ci 6 Kr-85 LLD LLD6 LLD6 LLD6 j , Kr-85m LLD LLD LLD LLD l Kr-87 LLD LLD LLD LLD l i i Kr-88 LLD LLD LLD LLD ; Xe-133 LLD LLD LLD LLD ! Xe-135 LLD LLD LLD LLD j Xc-135m LLD LLD LLD LLD I Xe-138 LLD LLD LLD LLD j r i Total for Period: N/A N/A N/A N/A lodines Ci 1-131 LLD LLD LLD LLD I-133 LLD LLD LLD LLD l-135 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A Particulates and Tritium C - H-3 1.93E-03 7.85E-G4 1.00E-02 2.46E-02 Sr-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD 1.61 E-05 1.12E-05 LLD Cs-137 LLD 1.20E-04 2.G1E-05 LLD Ba-140 LLD LLQ LIQ LLQ Total for Period: --- 1.93E-03 9.21 E G4 1.00E-02 2.46E-02 94
Davis-BIsse Nuclear Power Stttion 1996 Annual Radiological Environmental Operating Report l
~
Table 18 (Continued) Gaseous Effluents - Ground Level Releases ! Continuous Mode
- 1 1st Qtr 2nd Qtr 3rdQtr 4th Qtr Nuclide Unit 1996 1996 1996 1996 Fission Gases Ci Kr-85 LLD6 LLD6 LLD6 LLD*
Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD ! Xe-133 LLD LLD LLD LLD Xe-135 LLD LLD LLD LLD Xe-135m LLD LLD LLD LLD I Xe-138 LLD LLD LLD LLD Total for Period: 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 l Particulates and Tritium
]
Ci i H-3 5.56E-02 7.70E-03 4.68E-02 3.94E-01 Sr-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD I Cs-137 LLD LLD LLD LLD Ba-140 LLD LLD LLD LLD Total for Period: 5.56E-02 7.70E-03 4.68E-02 3.94E-01 i l 1 95
. f Davis-B:sse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report l l
Table 18 (Continued) .
)
1 Gaseous Effluents - Ground Level Releases j 1 Continuous and Batch Mode Ar-41: <2.2E-08 Ci/mi
)
Kr-85: <6.2E-06 pCi/mi ) Kr-85m: <2.0E-08 pCi/ml ! Kr-87: <3.4E-08 pCi/ml ) Kr-88: <4.0E-08 pCi/ml Xe-13Im: <9.0E-08 Ci/ml Xe-133: <4.6E-08 pCi/ml l Xe-133m: <1.6E-07 pCi/ml ! Xe-135: <l.9E-08 Ci/ml Xe-135m: <4.0E-07 Ci/ml j Xe-138: <2.5E-07 Ci/ml 1131: <l.0E-07 pCi/ml 1-133: <2. lE-08 Ci/ml 1135: <2. lE-08 Ci/ml Mn-54 <2.0E-08 pCi/ml Fe-59: <4.0E-08 Ci/ml Co-58: <3.0E-08 Ci/mi Co-60: <2.0E-08 Ci/ml Zn 65: <4.0E-08 Ci/mi Mo.99: <2.0E-07 pCi/mi Cs-134: <2. l E-08 Ci/ml l Cs-137: <3.0E-08 Ci/ml Cc 141: <3.0E-08 Ci/ml Cc.144: < l .2E-07 pCi/ml l Ba 140: <7.0E-08 pCi/ml ! La 140: <3.0E-08 pCi/ml l Sr-89: <5.0E-08 pCi/ml Sr90. <6.0E-09 pCi/ml !
.- j a Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, AVV Testing, and Auxiliary Boiler Outage Releaw are listed as batch releases.
b These tr-honuclides were not identified in concentrations above the lower limit of detection (LLD). i e Atnxnphene Vent Valve weepage and Steam Packing Exhaust are continuous releases. l l l 96
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Oper: ting Report Table 19 Gaseous Effluents - Mixed Mode Releases Batch Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1996 1996 1996 1996 Fission Gases Ar-41 Ci 1.06E 02 LLD LLD LLD Kr-85 Ci 3.00E+00 9.31E+00 2.15E-01 LLD Kr-85m Ci 1.09E-03 LtI LLD LLD Kr-87 Ci LLD" LLD6 LLD6 LLD* Kr-88 Ci LLD LLD LLD LLD Xe-133 Ci 1.98E+01 3.84E+01 LLD LLD Xe-133m Ci 6.30E-02 1.40E-01 LLD LLD Xe-135 Ci 2.81E-02 1.47E-02 LLD LLD Xe-135m Ci LLD LLD LLD LLD Xe-138 Ci LLD LLD JLD LLD Xc-131m Ci 7.17E-01 L41E+00 LLD. LLD Tctal for Period: 2.36E+01 4.93E+0! 2.15E-01 LLD
'Iodires *P:rticulates 113 Ci 6.06E-02 1.23E-01 4.47E-03 1.60E-03 Total for Period: Ci 6.06E-02 1.23E-01 4.47E-03 1.60E-03 t
l l Release of iodines and paniculates are quantified in Mixed Mode Releases, Continuous Mode (Unit Station Vent) I J 97
_ _ _ . . . ~ . _ . _ = _ ._ ,_ .. . _ .. O Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
- l Table 19 (Continued) - l 1
Gaseous Effluents - Mixed Mode Releases l Continuous Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1996 1996 1996 1996 Fission Gases Ar-41 Ci LLD' LLD' LLD* LLD' Kr-85 Ci LLD LLD LLD LLD Kr-85m Ci LLD LLD LLD LLD Kr-87 Ci LLD LLD LLD LLD Kr-88 Ci LLD LLD LLD LLD Xe-133 Ci 3.07E+01 3.61E+02 LLD LLD Xe-133m Ci LLD 3.42E+00 LLD LLD Xe-135 Ci 4.00E-01 1.18E+01 LLD LLD Xe-135m Ci LLD LLD LLD LLD Xe-138 Ci LLD LLD LLD LLD Total for Peded: 3.11 E+01 3.76E+02 LLD LLD Iodines I-131 Ci 6.34E-05 2.26E-03 7.78E-07 3.63E-06 I-133 Ci 3.07E-05 1.52E-04 LLD 2.63E-05 1-135 Ci LLD LLD LLD LLD ' Total for Period: 9.40E-05 2.41 E-03 7.78E-07 2.99E-05 Particulates and Tdtium i i 1 H-3 Ci 6.45E+00 1.10E+01 8.85E+00 9.58E+00 St-896 ' Ci LLD LLD LLD LLD Sr 90"' Ci - LLD LLD LLD LLD Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci LLD 3.78E-06 LLD LLD Ba-140 Ci LLD LLD LLD LLD La-140 Ci LLD LLD LLD LLD Total for Period: 6.45E+00 1.10E401 8.85E+00 9.5sE+00
)
I 98
_ ._ _ _. _ __ .- . _ ~ - _ _ . . - - _ _ - - --. __ ._ Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Opertting Report Table 19 (Continued) Gaseous Effluents - Mixed-Mode Releases Continuous Mode' Batch Mode' Ar-41 <2.9E-08 Ci/mi Kr-87 <4.5E-06 pCi/ml Kr-85 <3.3E-06 Ci/ml Kr-88 <6.6E-06 pCi/mi ! Kr.85m <1.3E-08 pCi/ml Xe-135 <l .4E-05 Ci/ml Kr-87 <6.0E-08 pCi/ml Xe-135m <2. lE-06 pCi/ml Kr-88 <6.0E-08 Ci/mi Xe-138 <2.8E-05 Ci/ml Xe-131m <4.4 E-07 Ci/ml , Xe-133m <7.2E-08 pCi/ml Xe-135 <l.lE-08 Ci/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 , Fe-59' <3.0E- 14 Ci/mi Co-58' <3.0E-14 pCi/ml Co-60' <2.5E- 14 Ci/ml Zn-65' <l.0E-13 pCi/ml Mo-99* < l .8E-14 pCi/ml Cs-134' <l .6E- 14 pCi/ml Cs-137' <l .3E-14 Ci/ml Cc-141' < l .2E-13 Ci/ml ! Cc-144' < l .2E- 14 pCi/mi Ba-140' <4.0E-14 Ci/ml La 140' <l.0E-14 pe"ml Sr-896 * <9.3E- 16 g - ml ! 6# Sr-90 <3. l E- 16 pCi/ml !
, a These radionuclides were not identified in every quarter in concentrations above the lower limit of de-tection (LLD). The largest LLD value is listed.
b Quarterly composite sample for continuous mode. c Analysis not required for batch release. l 99
l e Davis-B;sse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report j l l Table 20 - l Liquid Effluents - Summation of All Releases ! Est. Total Type Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr % Error 1996 1996 1996 1996 Fission and Activation Products l l Total Release (without Tritium, Gases, Alpha) Ci 2.69E-03 9.59E-03 2.80E-02 2.97E-02 2.0E+01 Average Diluted Concentration During Period
- pCi/ml 1.36E-08 5.67E-08 2.17E-07 2.60E-07 Percent of ODCM Limits % See Supplement information in ODCM Release Limits Section Percent of 10CFR20 Limit % 1.14E-02 2.30E-02 2.05E-02 1.38E-02 l Tritium Total Release Ci 3.3E+02 1.00E+02 3.22E+01 6.20E+01 2.0E+01 Average Diluted Concentration During Period' Ci/mi 1.67E-03 5.91 E-04 2.48E-04 5.43E-04 Percent of 10CFR20 Limit % 3.40E+00 1.30E+00 3.40E-01 7.50E-01
, Dissolved and Entrained Gases Total Release Ci 2.l lE+00 2.85E-01 LLD 1.87E-06 2.0E+01 Average Diluted Concentration During Period' Ci/ml 1.06E-05 1.68E-06 LLD 1.64E-11 Percent of 10CFR20 Limit % 1.75E-01 1.80E-02 LLD 1.13E-07 l Gross Alpha 1 Total Release Ci LLD LLD 6.95E-08 1.20E-07 2.0E+01 Volume cf Waste Released (prior to dilution) Batch liter 9.09E+05 1.01 E+06 5.03E+05 4.50E+05 2.0E+01 l Continuous liter 1.40E+07 1.39E+% 6.56E+06 4.50E+06 2.0E+01 Volume cf Dilution Water i i Batch liter 1.98E+08 1.69E+08 1.29E+08 1.14E+08 2.0E+0! Continuous liter 9.30E+09 7.'62E+09 8.04E+09 8.25E+09 2.0E+01 Totil Volume of Water Released liter 9.61 E+09 7.91 E+09 9.31 E+09 8.25E+09 1
- Tritium and alpha are found in both continuous and batch releases. Average diluted concentrations are based on total volume of water released during the quarter. Fission and Activation products and Dissolved and Entrained Gases are normally only detected in batch releases.
l l 100
. _ _ _ _ _ . _ .=. . - __ . . . - .
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Table 21 Liquid Effluents - Nuclides Released Batch Releases 1st Qtr 1996 2nd Qtr 1996 3rd Qtr 1996 4th Qtr i Nuclide Unit 1996 Fission and Activation Products Co-58 Ci 5.23E-05 1.77E-03 3.04E-03 6.68E-04 Co-60 Ci 1.39E-04 7.08E-04 1.78E-03 1.31E-04 , Ag-110m Ci 1.31E-04 4.68E-04 2.02E-03 1.45E-04 i Sb-125 Ci 5.86E-04 3.52E-03 1.63E-02 2.72E-02 Cs-134 Ci 2.68E-04 2.24E-04 4.67E-05 1.llE-06 Cs-137 Ci 6.97E-04 8.14E-04 1.85E-04 4.84E 05 Sr-89* 6 Ci LLD* LLD' LLD' LLD* Sr-90* 6 Ci LLD LLD LLD LLD Fe-55 Ci 7.83E-04 1.69E-04 1.33E-03 LLD Cr-51 Ci 5.75E-06 5.43E-04 9.99E-04 6.01E-04 1-133 Ci 6.69E-06 1.07E-06 LLD LLD I-131 Ci 2.43E-05 1.38E-04 LLD LLD I-132 Ci LLD 1.74E-04 LLD LLD Te-132 Ci LLD 1.60E-04 LLD LLD Tc-99m Ci LLD 3.31E-06 2.32E-06 LLD Sb-124 Ci LLD 4.97E-04 8.48E-04 4.21E-04 ; Sn-113 Ci LLD 4.68E-05 1.29E-04 6.91E-06 Ru-103 Ci LLD 3.21 E-05 5.46E-05 2.25E-06 Mn-54 Ci LLD 1.70E-05 3.75E-05 1.88E-06 Np-239 Ci LLD 1.13E-05 2.36E-05 3.62E-04 Co-57 Ci LLD 5.37E-06 1.35E-05 9.19E-M Nb-95 Ci LLD 1.47E-(M 6.89E-04 LLD Zr-95 Ci LLD 9.02E 05 3.62E-04 LLD Se-75 Ci LLD 5.14E-06 3.89E-06 LLD Fe-59 Ci LLD 1.74 E-05 LLD LLD Zn-65 Ci LLD 4.00E-06 LLD LLD Cc-144 Ci LLD 2 46E-05 1.17E-(M LLD Na-24 Ci LLD LLD 6.50E-06 8.41 E-06 , Zr 97 Ci LLD LLD 7.68E-07 LLD l Cc-141 Ci ~ LLD LLD 2.74 E-06 LLD ) Tetal for Period: Ci 2.69E-03 9.59E-03 2.80E-02 2.97E-02 ( 101
- - - . .. ~ . - ._ . - . ~ . = . .= - -.
Davis-BIsse Nuclear Powir Station 1996 Annual Radiological Environmental Oper.-ting Report Table 21 (continued) . Liquid Effluents - Nuclides Released Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1996 1996 1996 1996 Tritimen Ci 3.30E+02 1.00E+02 3.21E+01 6.19E+01 Dissolved and Entrained Graes Kr-85m Ci 1.73E-06 LLD' LLD' LLD' Kr-85 Ci 2.35E-02 1.21E-02 LLD LLD Xe-131m Ci 3,71E-02 1.48E-02 LLD LLD l Xe-133 Ci 2.04E+00 2.58E-01 LLD LLD Xe-135 Ci 4.70E-04 LLD LLD 1.87E-06 Xe-133m Ci 7.75E-03 1.74E-04 LLD LLD Total for Period: Ci 2.11E+00 2.85E-01 LLD 1.87E-06 I i 1 l 102
- . . . . . . - - . - = _ - . . .---.---- -.. ~ ~ - - ..
Divis-Besse Nuclear Power Station 1996 Annut! Radiological Environmental Operating Report , 1 1 Table 21 (continued) l Liquid Effluents - Nuclides Released Continuous Releases l 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr i Nuclide Unit 1996 1996 1996 1996 d Fission and Activation Products i i ! 4
- Cr-51 Ci LLD' LLD' LLD' LLD' I
) Fe-59 Ci LLD LLD LLD LLD l Co-58 Ci LLD LLD LLD LLD I , Co-6G Ci LLD LLD LLD LLD l Zn-65 Ci LLD LLD LLD LLD i Sr-89b Ci LLD LLD LLD LLD Sr-90* 6 Ci LLD LLD LLD LLD j Nb-95 Ci LLD LLD LLD LLD j Zr-95 Ci LLD LLD LLD LLD l Mo-99 Ci LLD LLD LLD LLD l ' l Tc.99m Ci LLD LLD LLD LLD
- I-131 Ci LLD LLD LLD LLD Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci LLD LLD LLD LLD Ba 140/La-140 Ci LLD LLD LLD LLD Ce-141 Ci LLD LLD LLD LLQ Total for Period
- N/A N/A N/A N/A Tritium Ci 2.54E-01 3.49E-01 1.01 E-01 6.83E-02 Dissolved and Entrained Gases Kr 85 Ci LLD LLD LLD LLD i Xe 131m Ci LLD LLD LLD LLD l Xc 133 Ci LLD LLD f.LD
- LLD Xc-133m Ci LLD LLD LLD LLD Xe 135 Ci LLD LLD LLD LLD ;
Total for Period: Ci N/A NM NL6 N% ; 1 103
. _ _ . - . . _ . _ _ _ _ ._ . __ _ . _ . . _ ..._. _. ..___._.m.._
Davis-BIsse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Table 21 (continued) . l Liquid Effluents - Nuclides Released *
]
Na-24 <2.0E-08 Ci/mi Sb-124 <l.0E-08 Ci/ml 1 Cr-51 <l.7E-07 Ci/mi Sb-125 <l.7E-08 Ci/ml
. Mn-54 <2. lE-08 Ci/mi Te-132 <l .8E-08 pCi/ml j 6 '
Fe-55 <7.0E-07 pCi/mi Ce-141 <3.0E-08 Ci/ml . Fe-59 <4.2E-08 Cihnl Cc-144 < l .7E-07 Ci/ml l Co-57 <l.6E-08 pCi/ml Cs-134 <2.lE-08 pCi/mi i Co-58 <l .9E-08 Ci/mi Ce-136 <2.8E-08 pCi/ml i Co-60 <2.5E-08 Ci/ml Cs-137 <2.7E-08 pCi/mi j i Zn-65 <5.2E-08 pCi/ml Ba-140 <7.0E-08 Ci/ml l . Se-75 <2.4E-08 pCi/ml La-140 <3.0E-08 pCi/mi I 6 Sr-89 <3.0E-08 Ci/ml Np-239 <l.2E-07 pCi/ml 6 Sr-90 <8.0E-09 Ci/ml I-131 <2.5E-08 Ci/mi j ! Zr-95 <4.0E-08 Ci/mi I-132 <l .0E-08 Ci/mi l Zr-97 <2.5E-08 Ci/ml 1-133 <2. l E-08 Ci/ml i
- Nb-95 <2. lE-08 Ci/ml I-135 <l .7E-07 Ci/ml
{ Mo-99 <l.6E-07 pCi/mi Kr-85 <6.2E-% Ci/mi
- Tc-99m l
< l .8E-08 Ci/ml Xe-131 <7/m-07 pCi/mi -
t Ru-103 <2.2E-08 Ci/ml Xe-133 <4.6E-08 Ci/mi Ag-110m <2.5E-08 Ci/mi Xe-133m <l .6E-07 pCi/ml Sn-113 <2.8E-08 pCi/ml Xe-135 < l .9E-08 pCi/mi i 1 1 4 ! l i f These radionuclides were not identified every quarter in concentrations above the lower limit of detection (LLD). The largest LLD value is used for each radionuclide. LLDs are applicable to both batch and continuous modes due to identical sample and analysis methods. Quarterly composite sample i 4 w 4 -* A 4 104 i
..=_.m _ _ . . - - _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ . . . _ . _ . _ _ _ _ _ _ __ .
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
. Table 22 Solid Waste and Irradiated Fuel Shipments A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 12-month Est. Total
- 1. Type of Waste Unit Period Error, %
- a. Spent resins, filter sludges, m' l.44E+01 2.5E+01 evaporator bottoms, etc. Ci 7.27E+02 2.5E+01
, b. Dry compressible waste, m' 9.15E+00 2.5E+01 contaminated equip., etc. Ci 2.72E+00 2.5E+01
- c. Irradiated components, con- m' i trol rods, etc. Ci N/A N/A
- d. Others: dewatered primary m' 9.00E-01 2.5E+01 i system cartridge filters Ci 1.03E+01 l 2.5E+01
- 2. Estimate of major nuclide composition (by type of waste) e Est. Total Error.
3 Iyy.g Percent (H ,E
- a. Spent Resins Fe" 4.60E+00 2.50E+01 Co" 1.1OE+00 2.50E+01 Co* 7.46E+00 2.50E+01 4
' Ni'3 3.97E+01 2.50E+01 Sbus 5.30E-01 2.50E+01 Cs'" 1.29E+01 2.50E+01 l Cs"7 3.29E+01 2.50E+01 l j i i b. Dry compressible waste, contaminated equip-ment, etc. Fe" 6.49E+00 2.50E+01 Co' l.06E+01 2.50E+01 Ni'3 1.48E+01 2.50E+01 Cs'" 1.50E+01 2.50E+01
!' Cs* 3.74E+0! 2.50E+01 Sb"5 1.71E+00 2.50E+01 i Co" 1.04E+0! 2.50E+01 ! C" 1.93E+00 2.50E+01 j c. None
- d. Cartridge filters Fe" 4.77E+00 2.50E+01
. - Co" 5.76E+01 2.50E+01 Ni'3 6.58E+00 2.50E+01 Cs'" 1.35E+00 2.50E+01 Cs"7 2.80E+00 2.50E+01 Co*" 2.50E+00 2.50E+01 S r 2.07E+01 2.50E+01 i
4 105
_, .. . .. . .-. - - .- . ~ - - . - - - . - - - - - - -
--.-l j
. l D vis-Besse Nuclear Pow;r Station ~1996 Annud Radiological Environment:J Operating Report
_ 1 Table 22 (continued) - Solid Waste and Irradiated Fuel Shipments
- 3. Solid Waste Disposition Number of Shipments: 4 Mode of Transportation: Truck Destination: Barnwell, SC ;
Type of Container (Container Volume): 3 resin / filter media HICs (13.3 m') buried j 2 dry activated waste HICs (2.9 m') buried j Number of Shipments: 5 1 Mode of Transportation: Truck Destination: Scientific Ecology Group - Oak Ridge, TN Type of Container (Container Vo!ume): a. Metal / wood boxes of dry contaminated waste and metal (6.25 m') buried i
- b. I resin /lilter HIC (2.03 m') buried i
B. IRRADIATED FUEL SHIPMENTS There were no shipments ofirradiated fuel. eum 8 106 L
Davis-B:.sse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report 1
. Table 23 Doses Due to Gaseous Releases j for January through December 1996 ]
i Maximum Individual Dose Due to I 131, H 3 and Particulates with Half Lives Greater than 8 days. Whole Body Dose 4.79E-03 mrem l Significant Organ Dose 3.05E-02 mrem i Mr.ximum Individual Dose Dae to Noble Gas Whole Body Dose 5.25E-03 mrem , 1 Skin Dose 2.06E-02 mrem Popilation Dose Due to I 131, H 3 and Particulates with Half Lives Greater than 8 days.
- Total Integrated Population Dose 1.09E-02 person-rem
- Average Dose to Individual in Population 4.99E-06 mrem J Population Dose Due to Noble Gas j I l Total Integrated Population Dose 1.22E-02 person-rem l l
Average Dose to Individual in Population 5.60E-06 mrem
\
j s
~
1 l
- I k
107 i
a I Davis-Bssse Nuclear Power Station 1996 Annual RadiologicCl Environmental Opercting Report i Table 24 . Doses Due to Liquid Releases ; 1 for January through December 1996 l i I
- Maximum Individual Whole Body Dose 9.60E-02 mrem Maximum Individual Significant Organ Dose 1.22E-01 mrem Population Dose )
)
TotalIntegrated Population Dose 1.84E+00 person-rem l l Average Dose to Individual 8.44E-04 mrem j 1 i i I I i l em-108
Davis-Bisse Nuclear Power Station 1996 Annual Radiological Environmernal Operating Report
.- Table 25 Annual Dose to the Most Exposed Member of the Public ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem) (mrem) LIMIT Whole Body Dose Noble Gas 5.25E-03 lodine, Tritium, Particulates 4.79E-03 Liquid 9.60E-02 Total Whole Body Dose 1.06E-01 25 4.24E-01 Thyroid Dose Iodine Tritium, Paniculates 3.0$E-02 75 4.07E-02 Skin Dose Noble Gas 2.06E-02 25 8.24E-02 j
Significant Organ Dose (Liver) 1.22E-01 25 4.88E-01 Meteorological Data i Meteorological data on 3'/ 2inch microdisk for January through December 31,1996, has been submitted with this document to the U. S. Nu-l clear Regulatory Commission, Document Control Desk, Washington, D.C. 20555. O l l l I l
. - 1 l
l 109 i
_ - - . . . - _.,m _m... _ _ . . _ - __ ._,t- ., -. 41.6.mi, a. %_.- . m.. . .- , , -% Davis.Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Land Use Census Program Design l Each year a Land Use Census is conducted by Davis-Besse in order to update information neces-
- ~ sary to estimate radiation dose to the general public and to determine if any modifications are necessary to the Radiological Environmental Monitoring Program. The Land Use Census is re-
- quired by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis-Besse Nu-clear Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use Cen-l sus Data. The Land Use Census identifies gaseous pathways by which radioactive material mav i reach the general population around Davis-Besse. The information gathered during the Land L ,c Census for dose assessment and input into the REMP ensure these programs are as crrent as possible. The pathways of concern are listed below:
- Inhalation Pathway -Intemal exposure as a result of breathing radionudides car-j ried in the air.
Ground Exposure Pathway - External exposure from radionuclides deposited on l the ground
. Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.
- Vegetation Pathway - Internal exposure as a result of eating vegetables, fruit, etc.
which have a build up of deposited radioactive material or which have absorbed radionuclides through the soil. , e Milk Pathway - Internal exposure as a result of drinking milk which may contain i radioactive material as a result of a cow or goat grazing on a pasture contaminated j by radionuclides. Methodology 4 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 j meteorological sector within a five mile radius of Davis-Besse. I The surveillance portion of the 1996 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 ani-mais 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) . Each residence-is tabulated as being an inhalation pathway, as well as ground and plume expo-sure pathways. Each garden is tabulated as a vegetation pathway. I10
ll Davis-Besse Nuclear Pow:r Station 1990 Annual Radiological Environmental Operating Report f ; ! l
- . ]
All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 mi- j nute series of the relevant quadrangles) which has been divided into 16 equal sectors corre- , sponding to the 16 cardinal compass points (Figure 31). The closest residence, milk animal, and j vegetable garden in each sector are determined by measuring the distance from each to the station j vent at Davis.-Besse. j i Results The following changes in the pathways were recorded in the 1996 census:
. S Sector - The garden at 1410 meters was replaced by a garden at 3440 meters.
. SW Sector - The garden at 960 meters was replaced by a garden at 4130 meters e W Sector - The garden at 980 meters was replaced with a garden at 1640 meters e WNW Sector -The garden at 1750 meters was replaced by a garden at 2900 me-ters.
- NW - The garden at 2340 meters was replaced by a garden at 2320 meters.
The critical receptor identified by the 1996 Land Use Census is a infant for the goat milk path- , way at 7010 meters in the WSW sector. The detailed list in Table 26 was used to update the database of the effluent dispersion model used in dose calculations. Table 26 is divided by sectors and lists the distance (in meters) of the closest pathway in each meteorological sector. Table 27 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and deposition (D/Q) parameters for each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and in cal-culating liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. P
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Divis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report t- _. Table 26 Closest Exposure Pathways Present in 1996 Sector Distance from Station (meters) Closest Pathways L i N 880 Inhalation 4 i , Ground Exposure ; Plume Exposure NNE 870 Inhalation Ground Exposure Plume Exposure 1 1 1 NE 900 Inhalation 3 Ground Exposure Plume Exposure l ENE, E, ESE, SE N/A Located over Lake Erie ! SSE 2010 Inhalation ) Ground Exposure -1 Plume Exposure l SSE 2820 Vegetation i S 1070 Inhalation ! Ground Exposure Plume Exposure . i S" 3440 Vegetation ; SSW 980 Inhalation
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Ground Exposure Plume Exposure SSW 1220 Vegetation SW 1050 inhalation Ground Exposure -)' Plume Exposure SW'- 4130 Vegetation
** Changes since 1995 113 i a
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Table 26 (continued) Clo'sest Exposure Pathways Present in 1996 Sector Distance from Station (meters) Closest Pathways WSW 1620 Inhalation Ground Exposure Plume Exposure WSW 4270 Vegetation WSW 7010 Goat Milk W 980 Inhalation Ground Exposure Plume Exposure W** 1640 Vegetation WNW 1730 Inhalation , Ground Exposure Plume Exposure 1 WNW *
- 2900 Vegetation NW 1100 Inhalation Ground Exposure Plume Exposure ;
NW *
- 2320 Vegetation NNW 1210 Inhalation Ground Exposure Plume Exposure ,
** Changes since 1995 114
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Davis-Besse Nuclear Power station 1996 Annual Radiological Environmental operating Repon a Table 27 i
. Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q)
Parameters i , SECTOR METERS LdTICAL AGE X/Q D/Q PATHWAY GROUP (SEC/M') (M'*) N 880 Inhalation Child 9.15E-07 8.40E-09 NNE 87i) Inhalation Child 1.27E-06 1.47E-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** 3440 Vegetation Child 4.38E-08 4.55E-10 SSW 1220 Vegetation Child 1.57E-07 3.46E-09 SW *
- 4130 Vegetation Child 4.79E-08 5.17E-10 WSW 7010 Goat Milk Infant 3.60E-08 2.03E-10 W*
- 1640 Vegetation Child 2.69E-07 4.21E-09 WNW*
- 2900 Vegetation Child 7.19E-08 6.50E-10 NW *
- 2320 Vegetation Child 6.91E-08 5.70E-10 NNW 1210 Vegetation Child 2.70E-07 1.92E-09
- Since these sectors are located over rnarsh areas and Lake Erie, no ingestion pathways are present.
** Changes sitei1995.
I15
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Meteorological Monitoring Introduction The . Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nu-clear power stations on the surrounding environment. Both NRC regulations and Davis-Besse Technical Requirements provide guidelines for the Meteorological Monitoring Program. These guidelines ensure that Davis-Besse has the proper equipment, in good working order, to support the many programs utilizing meteorological data. Meteorological observations at Davis-Besse began in October 1968. The Meteorological Moni-toring Program at Davis-Besse has an extensive record of data with which to perform clima-tological studies which are used to determine whether Davis-Besse has had any impact upon the
- local climate. After extensive statistical comparative research the meteorological personnel have found no impact upon local climate or short term weather patterns.
The Meteorological Monitoring Program also provides data that can be used by many other groups and programs: Radiological Envirenmental Monitoring Program, The Emergency Prepar-edness Program, The Environmental Activities Program, and groups such as Plant Operations, 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 evalu-ating the radiological impact,if any, of radioactivity released in Station efnuents. The meteoro-logical data is used to evaluate radiological environmental monitoring sites to assure the program is as current as possible. The Emergency Preparedness Program uses meteorological data to cal-culate emergency dose scenarios for emergency drills and exercises and uses weather data to plan evacuations or station isolation during adverse weather. The Environmental Activities Program uses meteorological data for chemical spill response activities, marsh management studies, and waste water outfall Dow calculations. Plant Operations uses meteorological data for cooling tower efficiency calculations, forebay water level availability and plant work which needs certain environme.1tal conditions to be met before work begins, such as humidity percentages and baro-metric pressures for wnsitive 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 ma-terial deliveries and safety concems. 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 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. I16
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Davis Besse Nucitar Power Station 1996 Annual Radiological Environmental Operating Report On-site Meteorological Monitoring
System Description
At Davis-Besse there are two meteorological systems, a primary and a backup. They~are both l housed in separate environmentally controlled buildings with independent power supplies. Both ; primary and backup systems have been analyzed to be " statistically identical" to the other so if one system fails the other can take its place. The instrumentation of each system follows- i PRIMARY BACKUP l 100 Meter Wind Speed 100 Meter Wind Speed 75 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 100 Meter Wind Direction 75 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 10 Meter Wind Direction l 100 Meter Delta Temperature 100 Meter Delta Temperature 1 75 Meter Delta Temperature 75 Meter Delta Temperature
- 10 Meter Ambient Temperature 10 Meter Ambient Temperature
, 10 Meter Dew Point 10 Meter Solar Insolation I
Precipitation Barometric Pressure MeteorologicalInstrurnentation The meteorological system consists of one monitoring site located at an elevation of 577 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 t. ear the base of the 10 m tower. According to the Davis-Besse Nuclear Power Station Operating License, US AR, Technical Requirements, a minimum of six instruments are required to be operable at the two lower leuls (75 m and 10 m) to measure temperature, wind _ speed, and wind direction. During 1996, annual data recovery for all required instruments were 98.6 percent. The annual data recovery for ah' other measured parameters was 95.8 percent. Minor losses of data occurred during routir,e in-strument maintenance, calibration, and data validation. International Great Lakes Data - 1955 i 117
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Personnel at Davis Besse inspect the meteorological site and instrumentation regularly. Data is i
. reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required. Tower instrumentation maintenance and semiannual calibrations are performed by in-house facilities and an outside consulting firm. These instruments are wind tun . j nel 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 dedicated line. If a failure occurs at any point between the primary meteorological system and the control room the second data logger in the primary shelter can be utilized by the control 3 room. Each datalogger has its own dedicated communication link with battery backup. The backup meteorological system is desij;ned 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 l with lightning and surge protection, plus four independent communication lines and datalogger battery backup. e 1 The data from the primary and backup meteorological systems are stored in a 30-day circular storage module with permanent storage held by the Digital VAX computer. Data goes back to ; 1988 in this format and to 1968 in both digital and hardcopy formats. All data points are scruti- i 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. I 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 i 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 j format for a permanent record of meteorological conditions. j Joint Frequency Distributions and Wind Sector Graphics Summary statistics and Joint Frequency Distributions (JFDs) of wind and stability data are gen-erated and the results are reviewed for consistency in terms of known site characteristic and re-gional climate. The end result of the review process is a validated f' mal database suitable for use l 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 i sector. This data is used by the NRC to better understand local wind patterns as they relate to defined past climatological wind patterns as reported in Davis-Besse's " Updated Safety Analysis Report". 118
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- Meteorological Data Summaries
- This section presents summaries of the meteorological data collected from the on-site monitoring program at Davis-Besse during 1996. Tables 28 through 30, discussed in this section, can be found on pages 122 through 141. ,
Wind Speed and Wind Direction l" The maximum wind speeds for 1996 were 68.4 mph for the 100m level on December 14,50.7 mph for the 75m level on March 25, and 40.2 mph for the 10m level on January 27. Figures 32-l 34 give an annual sector graphic of average wind speed and percent frequency by direction meas-ured at the three monitoring levels. Each wind sector graphic has two isobars, the lighter bar rep-resents the percent of time the wind blew from that direction. The darker isobar represents the average speed of the wind from that direction. Wind direction sectors are classified using l Pasquill Stabilities. Calms (less than or equal to 1.0 mph) are shown in percent in the middle of , the wind sector graphic. Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 1996 are given in Table 29. These data are measured at the 10m level; with differential temperatures taken from 100m and 75m levels. The yearly average ambient temperature for 1996 was 48.7 F. The maximum tem-perature was 91.9 F on June 30 with the minimum temperature of-3.9 F on February 04. Yearly average differential temperatures were -0.39F(100m), and -0.25 F(75m). Maximum differential temperatures for 100m and 75m levels were 8.00 F on January 04 (100m), and 8.00 F on Janu-ary 04 (75m). Minimum differential temperatures for 100m and 75m levels were -4.00'F on July 15 (100m) and -3.99 F on July 15 (75m). Differential temperatures are a measurement of atmos-phe.ric stability and used to calculate radioactive plume dispersions based on the Gaussian Plume Models of continuous effluent releases. Dew Point Temperatures and Relative Humidity Monthly average and extreme dew point and humidity temperatures for 1996 are provided in Ta-ble 29. These data are measured at the 10 meter level. The average dew point temperature was 41.3 F with a maximum dew point temperature of 75.7 F on July 18. Please note that dew point temperatures above 75 F are highly suspect and are possibly due to calm winds and high solar
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heating allowing the aspirated dew point processor to retain heat. The minimum dew point (dew point under 32 F is frost point) temperature was -7.6 F on February 03. Average relative hu-midity is 75.4 for the year. The maximum relative humidity was 100.00 percent on August 29. The minimum relative humidity was 36.7 percent on April 04. It is possible to have relative humidity above 100 percent which is known as super saturation. Conditions for super saturation have been met a few times at Davis-Besse due to its close proximity to Lake Erie and the evaporative pool of moisture available by such a large body of water. I19
. Davis-Besse Nuclear Power Station 1996 Ann sal Radiological Environmental Operating Repon Precipitation Monthly. totals and extremes of precipitation at Davis-Besse for 1996 are given in Table 29. To-tal precipitation for the year was 20.25 inches. The maximum monthly precipitation total was . 3.73 inches in April. The minimum was 0.83 inches recorded in February. It is likely that pre-cipitation totals recorded in colder months are somewint less than actual due to snow / sleet blowing across the collection unit rather than accumulating in the gauge. :
Lake Breeze and Lake Level Monitoring Lake Breeze is monitored at Davis-Besse because of its potential to cause major atmospheric / dispersion problems during an unlikely radioactive release. A lake breeze event occurs during < the daytime, usually during the summer, where the land surface heats up faster than the water, and therefore reaches higher temperatures than the water. The warmer air above the land rises faster because it is less dense than the cooler air over the lake. This leads to rising air currents over the , land with descending denser air over the lake. This starts a wind circulation which draws air l 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 ad- ! verse atmosphere to the surrounding site. , I Lake and forebay levels are monitored at Davis-Besse to observe, evaluate, predict and dissemi . I 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 l operators can take measures for the safe shut down of the plant. Since Lake Erie is the shallow- i est lake in the Great Lakes, it is not uncommon for a plus or minus five foot lake level fluctuation to occur within an eight to ten hour period. High water levels also effect the plant due to emer- 3 gency transportation and evacuation pathways.
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1 l 120
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D:vis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Satellite Imagery ; A state-of-the-art satellite weather system was installed in 1994. This system consists of a re-mote 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 geo-syncronous orbit situated over North America. Data from the satellite is fed to WSI corporation for 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 to customers; saving time and money as well. 3
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i Table 28 Summary of Meteorological Data Recovery For The Davis-Besse Nuclear Power Station E. i January 1,1996 through December 31,1996 f [ JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1996 100 73.87 ( 100M Wind Speed 100 89.22 14.25 0.00 5.11 94.58 100 100 99.44 100 83.89 100 99.73 94.58 100 100 99.44 100 95.83 100 99.12 3' 100m Wind Direction 100 99.86 100 75m Wind Speed 100 84.63 100 100 99.73 94.58 100 100 99.44 100 94.31 100 97.72 $ 75m Wind Direction 100 99.86 100 100 99.73 94.58 100 100 99.44 100 95.83 100 99.12 j' 100 99.73 94.58 100 100 99.31 98.92 85.83 100 98.04 [ 10m Wind Speed 100 98.13 100 100 96.51 94.58 100 100 99.44 100 95.83 100 98.85 - 10m Wind Direction 100 99.86 100 $ 100 99.73 93.75 100 100 99.44 100 95.28 100 99.00 10m Ambient AirTemp 100 99.86 100 y 10m Dew Point Temp 100 86.35 99.06 100 92.88 85.14 100 95.16 92.92 100 85.56 100 94.75 100 99.73 92.50 100 100 99.44 100 95.56 100 98.92 [,
- 3 Delta T (100m-10m) 100 99.86 100 100 98.92 E
" 100 99.73 92.50 100 100 99.44 100 95.56 Delta T (75m-10m) 100 99.86 100 h Joint 100m winds and 5.11 92.50 100 100 99.44 100 83.61 100 73.67 g Delta T (100m-10m) 10() 89.22 14.25 0.00 [ Joint 75m winds and 100 100 99.73 92.50 100 100 99.44 100 94.03 100 97.52 g5 ' Delta T (100m-10m) 100 84.63 Joint 10m winds and 100 97.57 [7 100 100 96.51 92.50 100 100 99.31 98.92 85.56 i , Delta T (75m-10) 100 98.13 8 ' c
*all data for individual months expressed as percent of time instrument was operable during the month, divided by the 5,
maximum number of hours in that month that the instrument could be operable. Values for annual data recoveries equals 3' the percent of time instrument was operable during the year, divided by the number of hours in the year that the instrument was operable.
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Table 29 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station ?' January 1,1996 through December 31,1996 f 5 7 JAN Fell MAR APR htAY JUN 'JUL AUG SEP OCT NOV DEC 1996 100M WIND {l ' Max Speed (mph) 51.3 43.4 53.0 NA NA 28.7 30.0 25.1 31.6_ 51.2 28.6 68.4 68.4 m 07 30 26 14 12/14 I Date of Max Speed 27 24 25 NA NA 29 19 20 , 6.0 NA NA 1.7 1.0 1.4 1.2 2.0 2.1 0.0 0.0 a! ! Min Speed (mph) 1.2 1.7 E i NA NA 15 08 16 20 07 21 31 12/31 3 Date of Min Speed 04 06 05 NA NA 13.9 12.9 10.9 14.9 17.5 15.6 17.3 15.7 [ Ave Wind Speed 19.6 18.5 20.1 g 75M WIND Max Speed (mph) 49.7 39.9 50.7 41.8 39.8 27.3 38.2 24.1 29.2 48.0 31.2 39.6 50.7 g 20 10 29 29 20 07 30 07 01 3/25 g Date of Max Speed 27 24 25
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" Min Speed (mph) 1.7 2.6 2.4 1.9 0.8 2.1 1.1 1.2 1.3 1.9 2.2 0.0 0.0 g, 02 07 21 16 12/16 g.
Date of Min Speed 04 15 15 07 16 12 08 16 ; 14.6 12.6 12.0 10.1 13.8 15.8 14.4 16.2 14.9 @- ' Ave Wind Speed 18.0 16.5 17.0 17.8 E-10M WIND Max Speed (mph) 40.2 29.7 39.8 32.3 31.6 20.0 30.5 24 25 20 10 29 29 17.2 21.8 33.6 20.8 30.9 40.2 27 14 30 25 01 1/27 h'
- g. i Date of Max Speed 27 Min Speed (mph) 1.5 0.0 1.3 1.7 0.9 1.8 1.2 0.7 0.2 1.8 2.1 1.3 0.0 g!
02 18 30 26 21 26 2/23 y ; Date of Min Speed 03 23 12 07 04 11 I 9.3 10.5 9.9 E. 12.2 12.4 10.2 7.5 7.9 6.0 9.0 9.7 Ave Wind Speed 12.2 11.1 k' o G- i 3 i t
- _ . . ~ . _ __ ______ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Table 29 (continued) Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station l'g-
- January 1,1996 through December 31,1996 7s IOM AMBIENTTEMP JAN FEB MAR APR - MAY JUN JUL AUG SEP OCT NOV DEC 1996 ($"
Max (F) 62.5 63.4 61.8 74.1 88.0 91.9 89.4 89.9 82.2 77.23 63.3 58.8 91.9 2' Date of Max 18 27 M 12 19 30 07 07 11 01 07 01 6/30 $ Min (F) 0.6 -3.9 6.0 27.1 38.1 53.3 57.2 59.6 46.3 31.9 22.7 9.3 -3.9 Date of Min 31 04 08 09 13 05 31 01 25 31 27 19 2/04 y[ Ave Temp 24.5 26.7 30.3 45.3 56.4 70.5 70.9 72.6 64.5 53.6 35.7 32.8 48.7 - 10M DEW POINT g' T3 TEMP [ " 23.6 24.1 36.4 47.3 62.4 57.1 63.6 58.6 45.7 27.9 30.1 41.3 x Mean (F) 19.6 58.6 49.6 59.3 70.7 73.6 75.7 75.1 73.7 62.9 50.4 56 1 75.7 [. Max (F) 49.6 Date of Max 18 27 25 22 18 22 18 06 06 02 17 01 7/18 g Min (F) 1.6 -7.6 -0.5 4.5 22.3 42.0 3.1 51.6 41.9 21.3 16.3 4.7 -7.6 [ Date of Min 31 03 03 11 13 01 29 08 19 31 .14 19 2/3 (n k PRECIPITATION j' 1.08 2.70 1.97 0.26 2.03 0.78 1.68 - 0.92 20.25 = Total (inches) 1.64 0.83 2.63 3.73 Max. in One Day 0.15 0.25 0.30 0.37 0.18 0.24 0.34 0.03 0.10 0.16 0.92 0.81 o Date 23 27 19 12 10 18 24 20 10 30 04 13
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, Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Oper: ting Report
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e Davis.Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report ; 4 Figure 35 (continued) Wind Rose Monthly Average 100M 1m /100 M ' JUNE 1996 /100 M i
*E NNs CALM Ng CALM NE 2
N k ENE N gy
>%m NNw /.* , ww.
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D;vis-Besse Nuclear Power Station 1996 Annual Radi: logical Environmental Operating Report , 1 Figure 35 (continued) . j Wind Rose Monthly Average 100M i I SEPTEMBER 19961100 M WOSER 1996 /100 M NN6 NNE CALM I CALM NE N N " p n _)k i j , - *
/ p s -
, _ j_ \ " lI ww / Est 9 www wNw \ 88
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, Divis Besse Nuclear Power Station 1996 Annual Radi: logical Environmental Operating Report Figure 36 Wind Rose Monthly Average 75M FEBRUARY 1996175 M JANUARY 1996175 M NNE CALM ut N - EN.
" ENE NN. ! W%
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Davis-Besse Nuclear Power Station 1996 Annual Radi: logical Environmental Operating Report i Figure 36 (continued) . Wind Rose Monthly Average 75M 1 a MAY 1996 / 75 M JUNE 1996 / 75 M NP4
.NNE CALM NE CALM ~% NE N - N
.N.
==
[ * ""* ' e ww est ww Ft EsE W
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e Davis-Besse Nuclear Power Station 1996 Annual Radi logical Environmental Operating Report
- Figure 36 (continued)
Wind Rose Monthly Average 75M OCTo8ER 1996 / 75 M SEPTEMBER 1996 / 75 M NNE NNE NE CALM CALM tee
# EM 0"' ENE N ,
N %
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\ ' E NNW NNW / S Nw - ._/ ,
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Davis-Besse Nuclear P:wer St tion 1996 Annual Radiological Environmental Operating Report , l. Figure 37 - t Wind Rose Monthly Average 10M ARY 1M /10 M FEBRUARY 1996 /10 M NNE NE ' cAtu .- ng ENE N 1 ENE
\ \ #'~
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a Davis-Besse Nuclear Power Station 19% Annual Radiological Environmental Operating Report Figure 37 (continued) Wind Rose Monthly Average 10M MAY 1996110 M JUNE 1998 /10 M NNE Cuu % NE CALu "N gg b, ENE N
'N
\ ' b N
y
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Davis-Besse Nuclear Power Station 1996 Annual Radi: logical Environmental Operating Repost . Figure 37 (continued) - l Wind Rose Monthly Average 10M SEPTEMBER 1996 /10 M OCTOSER 1998 /10 M WNE NNE CALM NE CALM NE 4-JJ Ent
- ENE f .
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L
. * **28-JAN-97
* * * * * *
- DAVIS-BESSE EtNIRONMENTAL COMPLI ANCE UNIT * ' TIME OF DAY: 10:25:35 VERSION: F77-1.0
< PROGRAM: JFD ' S. SITE IDENTIFIER: 96 "
* * * * " *
- pAVIS-DESSE 75-10 DT, NO BACKUP ********
DATA PERIOD EXAMINED: 1/ 1/ 96 - 12/ 31t 96 *' *** ANNUAL { be a A O E, STABILITY CLASS STABILITY BASED ON: DELTA T BEnfEEN 250.0 AND 35.0 FEET 3* e
~%
- f. 1 WIND MEASURED AT: 35.0 FEET g 4 WIND THRESHOLD AT: 1.00 MPH y *1ll ;
O ^ JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET O SPEED ESE SE SSE S SN SW WSW W WNW NW NNW TOTAL 43 k m i (MPH) N NNE NE ENE E e 1 0 O CALM 0 0 0 0 0 0 0 0 0 0 0 0 1 3 3 [c. 0 1.01- 3.49 0 1 1 0 2 3 3 10 51 f3 0 0 0 0 0 0 0 1 M' 3.50- 7.49 21 10 1 2 3 10 3 29. 0 0 0 0 0 0 1 1 ~ 1.50-12.49 12.50-18.49 7 0 1 0 0 2 1 0 0 0 0 0 0 0 0 0 0 0 0 2 0 2 0 2 0 8 0 g , 0 0 0 0 0 0 0 0 m. 16.50-24.49 0 0 0
>24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 16 0
91
$q.y to D3 ko 0 0 0 1 2 4 8 15 , - TOTAL 28 12 2 -
I 2 1 0 0 7- c: w C O E.' 4 C' t,4 N STABILITY BASED ON: DELTA T STABILITY CLASS BETWEEN 250.0 AND 35.0 FEET B O U C) b' C-g WIND MEASURED AT: 35.0 FEET ' y WIND THRESHOLD AT: 1.00 MPH y g- '. JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FFE"" E. SPEED (MPH) N NNE NE. ENE E ESE SE SSE S SSW SW WSW- W NtM fM NNW TOTAL D3 m-{a - 0 7 g- - 1 a CALM 0 0 0 0 0 0 0 0 0 0 0 0 1 -* g , 1.01- 3.49 0 0 0 1 0 3 3 4 30 7* 0 0 0 1 1 " 3.50- 7.49 9 6 1 0 0 0 1 1 1 1 8 6 12 2 1 12 16 97 k
- 1.50-12.49 9 8 8 7 3 3 45 8 f 0 0 0 0 3 3. 6 3 5 9 1 b
12.50-18.49 18.50-24.49 5 0 0 3 0 4 2 1 1 0 0 0 0 0 0 3 9 0 0 0 2 0 0 0 0
~0 1E 0
Q
.- O i
0 0 0 0 0 0 0 0
>24.49 0 0 0 D3 g.
TOTAL 23 17 13 10 5 1 4 1 1 11 13 28 5 11 24 21 188 $ g s- - Ott
.M- n
- s t
- . - . . - . . . . - n - , - - . . , . - , no. - . , - - - < - . . , - - , . - -,n. , ,
t
* **28-JAN-97
*** * *** DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT ***
TIME OF DAYt 10:25:35 g m PROGRAM: JFD VERSION: F77-1.0 2.
******r* DAVIS-BESSE 75-10 DT. NO BACKUP ******** SITE IDENTIFIER: 96 '
DATA PERIOD EXAMINED: 1/ 1/ 96 - 12/ 31/ 96 *** e *** ANNUAL % I O
~*
'a:
STABILITY CLASS C g 8 M $~~ STABILITY DASED CN: DELTA T DETWEEN 250.0 AND 35.0 FEET 4 WIND MEASURED AT: 35.0 FEET g *O WIND THRESHOLD AT: 1.00 MPH m O O JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET .O SPEED FEW TOTAL C N NNE NE FNE E ESE SE SSE S SSW SW WSW W WNW NW * (MPH) O 0 U O q . CAU4 0 0 0 1 0 0 0 0 0 1 0 0 0 0 1 0 3 M p , 2.01- 3.49 10 4 2 6 5 82 y 3.50- 7.49 7 7 9 2 1 0 3 4 8 10 4 ~ 15 10 2 1 6 11 25 21 6 4 25 23 179 - 9 14 6 1 7.50-12.49 12.50-18.49 7 5 3 13 2 0 0 0 0 0 4 11 15 17 2 2 4 0 11 1 10 0 87 25
,O rA ej h
0 0 0 0 1 3 18.50-24.49
>24.49 1
0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 0 0 0 0 6 Qo g y TOTAL 24 27 18, 30 13 1 5 6 14 26 49 63 15 10 43 38 382 Q C O - g g STABILITY CLASS D 6j STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 , FEET U yg 3* g WIND MEASURED AT: 35.0 FEET y g g-WIND THRESHOLD AT: 1.00 MPH & JOINT FREQUENCY DISTRIBUTION OF WIND SPECD AND DIRECTION IN HOURS AT 35.00 FEET @ v, Q m
- SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL $
T F c;' , 1 w* C , CAI.M i . 4 's : *. I 4 to r. *i 6 6 R 6 7 2 6 6 6 ng O 8 I.to
/s si *4 v. t ."; r,4 54 42 5H (12 t,2 54 30 22 23 28 UJ7 k
[ i . ,o t.49 , 200 184 122 79 102 105 1776 7.50-12.49 50 76 141 194 96 176 37 37 8 47 6 44 3 83 11 136 88 181 189 75 59 66 113 1249 C b 12.50-18.49 el 108 38 128 34 10 0 2 0 0 0 18 60 102 31 11 18 16 368 >-* p 18.50-24.49
>24.49 28 21 10 8 0 0 0 0 0 1- 5 25 52 6 2 0 1 131 Mg g, m . .
210 270 366 399 352 117 94 95 159 337 534 588 266 179 215 269 4451 g. TOTAL De 12 2 i
- e
_. .m ..__ - . . . . _ ..__.m_.m___.__________ _ . _ . _ _ . _ _ _ -r - - - _ . - . .s _.. . _ _ .
e' e T
* " 2 8 -J AN- 97
*" * * *
- DAVIS-BESSE DNIRONMEffrAL COMPLI ANCE UNIT "
- TIME OF DAY: 10:25:35 0
PROGRAM: JFD VERSION: F77-1.0 I SITE IDENTIFIER: 96 y*
* * * " * * ** DAVIS-BESSE 7 5-10 DT, NO BACKUP * * ' * * "
DATA PERIOD EXAMINED: 1/ 1/ 96 - 12/ 31/ 96
"* ANNUAL "' g i E
Q g STABILITY CLASS U g DETWEC1 250.0 AND 35.0 FEET , STABIL11Y BASED ON: DELTA T g WIND MEASURED AT: 35.0 FEET Y WIND THRESHOLD AT: 1.00 M214 h 2 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 WSW FEET W WNW NW NNW TOTAL y SPEED SSE S SSW SW (MPH) N NNE NE E*,'E E ESE SE C Ch 5 g- i CALM 13 25 32 17 13 10 9 9 6 3 2 15 166 1146 3 O d { o 3 2 8 13 132 78 60 31 22 8 1.01- 3.49 1 8 15 45 97 112 96 100 131 205 115 105 89 39 35 24 852 M A7 3.50- 7.49 9 29 41 17 135 252 - 7.50-12.49 12.50-18.49 13 6 25 10 27 8 35 3 3 33 5 0 33 0 0 7 1 16 7 18 3 40 4 54 11 29 15 21 4 1 11 0 0 10 0 0 14 0 0 55 18 D$ Q* i 18.50-24.49 0 4 3 0 0 7 5 0 0 0 0 3
>24.49 0 3 2 87 70 55 2494 . O 246 397 329 241 184 148 196 E w TOTAL 29 53 57 8 94 145 158 C ^O F-S O y STABILITY CLASS F .",
Q U, [ BETWEEN 250.0 AND 35.0 FEET Q -- U ' 5-* i STABILITY BASED ON: DELTA T
- r WIND MEASURED AT: 35.0 FEET 7C O E
~
WIND THRESHOLD AT: 1.00 MPH O " JOIPTT FREQUENCY DISTRIBUTION OF WIND SFEED AND DIRECTION IN HOURS AT 35.00 WFEET b SPEED NE ENE E ESE SE SSE S SSW SW WSW WIM iM NNW TOTAL (/.) h m . (MPH) N NNE 4 A E o Om 4 8 16 47 48 39 21 17 7 4 2 3 0 222 435 T 4' 8 I 2 3 ~1 55 31 45 8 3 1.01- 3.49 0 3 5 17 19 29 49 66 102 4 13 4 0 0 61 N* g 3.50- 7.49 1 2 0 9 5 4 7 M :s 2 3 4 3 3 4 0 0 0 1 9 ' 7.50-12.49 0 0 1 2 12.50-18.49 0 0 0 1 0 0 0 0 0 0 0 1 0 0 0 0 0 1 n E 0 0 0 0 0 0 0 0 0 0 0 0 - 18.50-24.49 0 0 0 0 0 0 *
>24.49 0 0 0 0 0 0 N
- 16 5 4 732 09 119 146 86 56 65 = R r 11 24 30 45 105 TOTAL 1 6 9 g. .
OS 3l . t L i _. . . _ . . _ . _ _ .m._ _ - . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _m m____m _ _ _ _ _ . _ _ - . _ _ _ ,-we-
k
* **28-JAN-97
'" * '
- DAVIS-BESSE ENVIFONMENTAL COMPLI ANCE UNIT * *
- TIME OF DAY: 10:25:35 g PROGRAM:. JFD VERSION: F77-1.0
****"S* DAVIS-BESSE 75-10 DT. NO BACKUP ********
SITE IDENTIFIER: 96 f* ' DATA PERIOD EXAMINED: 1/ 1/ 96 - 12/ 31/ 96 ***
*** ANNUAL b4 I
STABILITY CLASS G D N STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET krj WIND MEASURED AT: 35.0 FEET M [
. WIND THRESHOLD AT: 1.00 MPH O (
JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 WSW FEETW WNW NW NNW TOTAL R SPEED ESE SE SSE S SSW SW N NNE NE ENE E 0 (MPH) 0 E J C-CALM 2 1 1 0 2 6 13 23 16 13 6 4 0 1 1 0 0 1 84 131 h y >gn" 8, 1.01- 3.49 0 0 12 33 17 6 0 4 8 14 13 15 0 0 0 0 14 7 3.50- 7.49 2 1 7.50-12.49 1 0 0 0 0 0 0 1 0 4 0 3 0 1 0 1 0 1 0 1 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 QO w. T E 12.50-18,49 0 0 0 0 0 0 0 0 0 0 0 0 MW 18.50-24.49
>24.49 0
0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 229 hO ym ko 2 2t 6 13 17 16 22 26 57 34 20 10 1 1 eo L, E o TOTAL 1 STABILITY CLASS ALI, g C. .- BETWEEN 250.0 AND 35.0 TEET Q 12. STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET 7C .M MO D' WIND THRESHOLD AT: 1.00 MPH gU Q. L JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEIT SPEED SSE S SSW SW WSW W WNW NW NNW TOTAL p E ESE SE (MPH) N NNE NE ENE 10 7 h 46 25 16 12 12 568 C S CALM 1.01- 3.49 4 12 8 14 30 27 50 92 84 275
- 83 432 53 277 175 145 70 60 63 2712 "'
m g, 3.50- 7.49 75 68 82 152 252 210 166 210 171 295 355 328 234 130 184 171 3008 M , 257 226 77 82 97 81 98 141 1650 E 7.50-12.49 12.50-18.49 88 99 126 126 185 145 115 45 8 13 19 29 136 23 251 78 243 143 101 31 13 19 16 464 O 18.50-24.49 29 42 37 10 14 0 0 0 2 0 1 0 7 0 3 1 5 32 63 7 2 0 1 155 7
>24.49 21 13 1046 998 549 312 373 404 8567 C#3 E TOTAL 316 387 467 552 553 324 312 425 565 974 s.
04 I T2 s
~
. i-
* **28-JAN-97 DAVIS-BESSE DNIRONMENTAL COMPLIANCE UNIT **
- TIME OF DAY: 10:25:35 PROGPAM: JFD VERSION: F77-1.0 0 SITE IDENTIFIER: 96 $
' * * " " DAVIS-BESSE 75-10 I7r. NO BACKUP * * * * * * "
12/ 31/. 96 y' DATh PERIOD EXAMINED: 1/ 1/ 96 - *** g
. *** ANNUAL 4 STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET y h WIND MEASURED AT: 35.0 FEET Q g WIND THRESHOLD AT: 1.00 MPH we U
TOTAL NUMBER OF OBSERVATIONS: 8783 TOTAL NUMBER OF VALID OBSEFVATIONS: 8567 216 Y I, TOTAL NUMBER OF MISSING OBSERVATIONS: Q FERCENT DATA PECOVERY FOR THIS PERIOD: 97.5 % g g MEAN WIND SPEED FOR THIS Prstog. 9,9 Men 4 0 g
- TOTAL PRIMDER OF OBSERVATIO;' w!TH DACFtJP DATA: O PERCENTAGE OCCURRENCE OF STABILITY CLASSES O d M SD 8 E F G A B C D 29.11 8.54 2.67 7 -
1 06 2.19 4.46 51.96
- w. O nu U. O a
DISTRIBUTION OF WIND DIRECTION VS STABILITY WSW W NNW NW NNW CALM 7A E
- I ENE SE SSE S SSW SW A N NNE NE E ESE C O E.
~
C. O D
- o 2 0 0 0 0 0 1 2 4 8 15 16 0 O r E.
A 28 12 2 1 1 11 13 28 5 11 24 21 0 g -- ;:3-B 23 17 13 10 5 1 4 1 49 63 15 10 43 38 0 0 - C 24 27 18 30 11 1 5
- 6 14 26 337 534 588 266 179 215 269 1 7C O D 210 270 366 399 352 117 94 95 159 184 87 70 55 5 MO E 29 53 57 94 145 158 148 196 246 397 146 329 86 241 56 65 16 5 4 '4 (r} C* {
6 9 11 24 30 45 105 119 F 1 26 57 34 20 10 1 1 1 0 c+ @- 2 2 6 13 17 16 22 W < G 1 312 425 565 974 1046 998 549 312 373 404 10 TOTAL 316 387 467 557 551 324 T x;*
=: 8 x
x g
=
O E Y- $., M E Ei' OQ a 12
Davis-B:sse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report e Land and Wetlands Management Navarre Marsh The Navarre Marsh, which is part of the Ottawa National Wildlife Refuge, makes up 733 acres of wetlands on the southwestern shore of Lake Erie and surrounds the Davis-Besse Nuclear Power Station. The marsh is owned by Toledo Edison and jointly managed by the U.S. Fish and Wild-life Service and Toledo Edison. Navarre Marsh is divided into three pools (units). The pools are separated from Lake Erie and each other by a series of dikes and revetments. Toledo Edison is responsible for the maintenance and repair of the dikes and controlling the water levels in each pool. A revetment is a retaining structure designed to hold water back for the purpose of erosion con-trol and to encourage beach formation. Revetments are built with a gradual slope which causes 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 vegeta-l tion and animal species. Manipulating water levels is one of the most important marsh manage-ment tools used in Navarre Marsh. Three major types of wetland communities exist in Navarre Marsh, the freshwater marsh, swamp forest, and wet meadow. Also, there exists a narrow dry beach ridge along the lake front with a sand bar extending out into Lake Erie. All these areas
)
i provide essential food, shelter, and nesting habitat as well as a resting area for migratory birds. Davis-Besse personnel combine their efforts with a number of conservation agencies and organi-zations. including the Ottawa National Wildlife Refuge, the Ohio Department of Natural Re-sources (ODNR). and the Black Swamp Bird Observatory to preserve and enhance existing habitat. to gain knowledge through ongoing research, and to help educate the public about the ' importance of natne wetlands. With its h> cation along a major migratory flyway, the Navarre Marsh se.ves as a refuge for a va-riety of birds in both the spring and the fall, where they rest and find nourishment before con-tinuing on their joumey, The Black Swamp Bird Observatory captures, examines, bands, cata-logues, and releases wngbirds in the marsh during these periods. Navarre is also home to wildlife that is typical of much of the marshland in this area, including deer, fox, coyote, muskrats, rabbits, woodchucks, hawks, owls, ducks, geese, herons, snakes and turtles. For the first time in recent history, a pair of mature American Bald Eagles chose the 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 1996. The nest blew down in a storm in August of 1996, and an artificial nesting platform was constructed by State and Federal wildlife officiah and Davis -Besse employees. The eagles used the nest during 1996 breeding season but failed to produce any young. The extreme cold and wet spring caused several nest in the Lake Eric region to fail. 142
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
- - Goose banding took place in June, and was conducted in cooperation with the ODNR and the U.S. Fish and Wildlife Service. Over 100 Canada Geese were banded in about an hour.
Davis-Besse opened the Navarre Marsh for public tour for the first time ever in observance of International Migratory Bird Day About 350 members of the public took part in shuttle van tours, which included a bluebird trail demonstration, a banded bird demonstration given by the Black Swamp Bird Observatory, 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 ani-mais as part of the program. Ohio's Second Federal Junior Duck Stamp Art Contest was hosted by Davis-Besse. Young Ohio artists in grades K-12 submitted nearly 1500 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 submitted by Adam Grimm of Elyria. His entry placed fourth in the nation as he competed with other state'Best of Show entries for a , chance to have his artwork used in the production of the 1996 Junior Duck Stamp. Davis-Besse also hosted a Volunteer Eagle Watchers Workshop, a Wetland Wildlife and Fisher-ies Workshop, and an informational meeting addressing the new State limit on Yellow Perch, all of which were sponsored by the Ohio Division of Wildlife. l em F 143 ! i e
Davis-Besse Nuctsar Power Station 1996 Annual Radiological Environmental Operating Report Water Treatment Water Treatment Plant Operation I Description i The Davis-Besse Nuclear Power Station uses Lake Erie as a water source for its water treatmem plant. The lake water is treated with chlorine, lime, and other chemicals to make the water clean 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 monitoreil by the Ohio Environmental Protection l Agency (OEPA) and the Ohio Department of Health. Tne operation of the facility is reviewed by a Public Water Supply certified operator. Activities r.c the water treatment plant are conducted in compliance with the Safe Drinking Water Act and th: regulations for public water supply as set l 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 chemicals. The health and safety of the water treat-l ment plant operators and other site personnel is ensured through weekly housekeeping inspec-tions of the facility. l l Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which i will remove debris greater than % " in size. The water is then pumped to chlorine detention tanks. Next the water passes through one of two clarificrs. Davis-Besse uses upflow clarifiers, or precipitators, to remove sediment, organic debris, and dissolved agents from the raw water prior to filtration. Clarifiers combine the conventional treatment steps of coagulation, floccula-tion, and sedimentation 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. How-ever, the use of clarifiers saves both space and the manpower needed to operate the treatment plant.
Davis-Bisse Nuclear Po:ct Station 1996 Annual Radiohgicd Erwironmental Operating Report AAW WATrA WTAKE STRUCTURE
- FLOW SPLrrTNG ~
sox weta estonWs 7 - ^m*7'c lg"gy,*Uu - i CLEARWELL ann y j l i }
<_. i _;
u . CLEARWELL l 1 TRANSFTR PUMPS
! l l TO DOMESTIC To nRE 40RWKWG) waqp WATER SYSTE.M SYST1,'v TO DEMWERALCED WATER SYSTDJ Figure 38: At Davis Besse, raw water is drawn into the water treatment plant and processed to make drinking water and water for plant systemt After the clarifier, the water goes through a flow-splitting box which equally divides the watei flow to the Automatic Valveless Gravity Filters (AVGF). These AVGFs consist of a 50:50 ratio of anthracite :o 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-proves the taste of the water.
After filtration, the water goes to a 32,000 gallon clearwell. The clearwell acts as a reservoir from which water can be drawn as needed for all systerus, including fire water, demineralized water, and also drinkmg water. Summary of 1996 Water Treatment Plant Operation An agreement has been reached for drinking water to be supplied by the Carroll Township Water District. This new water system is expected to be completed by mid-1997. New drinking water distribution system piping was installed at the end of 1996 in preparation for this new system. Zebra Mussel Control Introduction The plant receives all of es water from an intake system from Lake Erie. Zebra mussels can se-verely impact the availability of water for plant processes. Dreissena polymorpha, commonly known as the /ebra mussel is a native European bivalve that was accidentally introduced into Nonh Amenean waters in 1986 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. Be- Because of their ability to attach in this 145
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i D:vis Besse Nuclear Power Station 1996 Annua 0ediological Environmental Operating Report manner, they may form layers several inches deep. This noses a problem to facilities that rely on - l water intakes from Lake Erie because mussels may attach o the intake structures and restrict water flow. Zebra mussels have not yet caused any significana poblems 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 cana') ! . Monitoring l l ' The Zebra Mussel Monitoring Program has'been in place since April,' 1990. The program in-l . 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 deter- !
mined 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. ; 1 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 ( mi- I croscopic ) organisms including veligers. One milliliter from each sample is observed under a { microscope to check for the presence for veligers to determine the average number of veligers per l
- liter.
1 Mussels have also been found on the trash racks, and the intake bay #3 walls prior to the travel- l ing screens.'These mussels are' periodically cleaned using high pressure water. We use continu-ous low level chlorination of the intake bays as a biocide which also controls the mussel popula- , tion in the plant. ' The mussel population appears to be leveling off or declining. This is likely du~e to the increas-ing clarity of Lake Erie. As the food source for the zebra mussels decline, mussel population de-clines correspondingly. Wastewater Treatrnent Plant Operation The wastewater treatment plant (WWTP) operation is supervised by a state Cer:itied 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 ) 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 - l 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-vated sludge. The treated wastewater settles in a clarifier, and the clear liquid passes over a weir, leaving the plant by an effluent trough. The activated sludge contains the organisms necessary l: for continued treatment, and is pumped back to the front of the plant to digest more mcoming 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. 146
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i Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
' Summary of 1996 Wastewater Treatment Plant Operations Wastewater treatment plant (WWTP) number 1 is currently being renovated . The paint is being repainted, rewired and a new roof is being installed . This will greatly improved the facility's operability and appearance.
National Pollutant Discharge Elimination System (NPDES) Reporting The OEPA has established limits on the amount of pollutants that Davis-Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 21B000ll
- ED. Parameters such as chlorine, suspended solids and pH are monitored under the NPDES permit. Toledo Edison personnel pre-pare the NPDES Reports and submit them to the OEPA by the fifteenth day of each month.
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. Outfall 002 Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water runoff, circulating pump house sumps. Outfall 003 l Screenwash Catch Basin: Outfall to Navarre hTarsh. , Source Of Wastes: Wash debris from water intake screens. l Outfall 601 I Wastewater Plant Tertiary Treatment Basin: Discharge from wastewater treatment system. l Sources Of Wastes: Wastewater Treatment Facility. 1 147
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report 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 P6 int 801
- Intake Temperature: Intake water prior to cooling operation.
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- . ~. -. - . = - - . . = - . .. , . _ . ..
Davis-Bisse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
- 1996 NPDES Summary
' During 1996,the NPDES permit was renewed by the Ohio EPA . This permit will expire on Oc-tober 31,2000. All outfalls remain the same . However , new parameters have been added, in-cluding hydrazine and dissolved oxygen during refueling and maintenance outages , total resid-ual chlorine , copper, lead, and zinc. Many of these new parameters are a result of the Great Lakes Water Quality Initiative. The trend in the future permits will be further increased monitoring.
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Davis-Besse Nuclear Power Station 1996 Annual Radiologicci 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. 1 Waste Management
! Resource Conservation and Recovery Act The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid haz-ardous waste. Solid waste is defined as a solid, liquid, semisolid, or contained gaseous material.
The major goals of RCRA are to establish a hazardous waste regulatory program to protect hu-man health and the environment and to encourage the establishment of solid waste management, resource recovery, and resource conservation systems. The intent of the hazardous waste man-agement program is to control hazardous wastes from the time they are generated until they are ! properly disposed of, commonly referred to as " cradle to grave" management. Anyone who gen-erates, transports, stores, treats, or disposes of hazardous waste 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 !
i (2200 lbs month ) or more.
- 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 (220lbs/ month).
In 1996, the Davis-Besse Nuclear Power Station generated 1,620 pounds of hazardous wastes, l which represents a 74% reduction from 1994. There were 3,070 gallons of non-hazardous waste oil generated in 1996, a 32% reduction from 1994. Additionally, approximately 1,200 gallons of oil filters and solid oily debris were generated during 1996. Additionally,2,500 gallons of water
- containing small amounts of diesel fuel oil from a minor on-site diesel fuel oil leak were dis-posed as non-hazardous regulated 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. 150 i l
i e Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon ' Inspections e Chemical Waste Accumulation Areas are designated throughout the site to ensure l proper handling and disposal of chemical waste. These, along with the Chemical , Waste Storage Area, are routinely patrolled by security personnel and inspected I weekly by Toledo Edison personnel. All areas used for storage or acc6mulation of hazardous waste are posted as such with warning signs, and drums vm color-coded for easy identification of waste categories by Davis-Besse empicyees.
. Waste Inventory Forms Inventory forms are placed on waste accumulaticn drums or provided in the accumu- [
l lation area to allow employees to record the waste type and amount as it is added to j the drum. This ensures that incompatible wastes are not mixed and also identifies the drum contents for proper disposal. e' Testing of Waste Oil The majority of waste oil generated at Davis-Besse is not disposed of, but is removed f 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 nonhaz-7 l ardous waste. i s P l ! r t I L I s i 1 151 J l l l l ,
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Emergency Response Planning - Comprehensive Environmental Responc, Compensation, and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, sometimes referred to as Superfund) established a federal authority and source of funding for re-sponding to spills and other releases of hazardous materials, pollutants, and contaminants into the environment. Superfund establishes " reportable quantities" for several hundred hazardous mate-rials, and regulates the cleanup of abandoned hazardous waste disposal sites. Superfund Amendment and Reauthorization Act (SARA) Superfund was amended in October,1986, to establish new reporting programs dealing with emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enhanced by ensuring that the potential for release of hazardous substances is minimized and adequate a id timely responses are made to protect surrounding populations. Davis-Besse conducts site-wide inspections to identify and record all hazardous products and chemicals onsite as required by SARA. Determinations were made as to which products and chemicals were present in sufficient quantities to repon. 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 1996. Spill Kits Spill control equipment is maintained throughout the Station at chemical storage areas and at ap-propriate hazardous chemical and oil use points. Equipment in the kits may include such items as chemical resistant coveralis, gloves, boots, decontaimination agents, absorbent cloth, goggles, l and waming signs. l l Other Regulating Acts ! Toxic Substances Control Act (TSCA) _ l The Toxic Schstance 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-doced into the environment, and to regulate them where necessary. This law would have little impact on utihties except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management system, very sinular to the hazardous waste management system established under RCRA.
)
In 1992 Davis-Besse completed an aggressive program that eliminated PCB transformers onsite. l PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with l non-PCB liquid. 152
Davis-B:sse Nuclear Power Station 1996 Am4 Radiological Environmental Operating Report i l Retrofilling PCB transformers involves dushing the PCB fluid out of a transformer, refilling it I with PCB-leaching solvents and allowmg the solvent to circulate in the transformer during op- i cration. The entire retrofill process tales several years and will extract almost all of the PCB. In j all, Davis-Besse performed retrofill activities on eleven PCB transformers between 1987 and ' 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors. j These capacitors are being replaced and disposed Of during scheduled maintenance activities. I Approximately 15 kilograms of PCBs were disposed ot in 1996. Clean Air Act 1 The Clean Air Act identifies substances which are considered air pollutants. Davis-Besse holds an OEPA permit to operate an Air Contaminant Source for the station auxiliary boiler. This boiler is used to heat the station and provide steam to plant systems when the reactor is not oper-ating. A repon detailing auxiliary boiler operation is submitted annually. i 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- I 1 gency Diesel Generators, the Emergency Response Facility Diesel, the Miscellaneous Diesel, and j 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.
' In response to recent " Clean Air Act Title V" legislation, an independent study identifying and quantifying all of the air pollution sources onsite was performed.
Of particular significance is asbestos removal from renovation and dentolition projects for which USEPA has outlined specific regulations concerning handling, remoeal, environmental protec-tion, and disposal. Also the Occupational Safety and Health Protection Administration (OSHA) { strictly regulates asbestos with a <.oncem for worker protection. Removal teams must meet i medical surveillance, respirator fit c.sts, and training requirements prior to removing asbestos-containing material. Asbestos is not onsidered a hazardous waste by RCRA, but the EPA does 1 require special handling and dispc. sal of this waste under the Clean Air Act. l l Transportation Safety Act 4 The transportation of hazardous chemicals, including chemical waste, is regulated by the Trans-I ponation Safety Act of 1976. These regulations are enforced by the United States Department of l l Transponation (DOT) and. cover all aspects of transponing hazardous materials, including pack-
- ing, handling, labeling, marking, and placarding. Before any wastes are transported off site.
l Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations, including verification that the vehicle has appropriate placards and it is in good oper- [ ating condition. Other Programs ! i Underground Storage Tanks l According to RCRA, facilities with Underground Storage Tanks (UST) are required to notify the
} State. This regulation was implemented in order to profded protection from tank contents leaking and causing damage to the environment. Additional standards require leak detection systems and performance standards for new tanks. At Davis-Besse two 40,000 gallon and one 8,000 gallon diesel fuel storage tanks are registered USTs.
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Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Waste Minimization and Recycling Municipal Solid Waste (MSW) is everyday trash which is produced by individuals at home and by industries. In some communities MSW is burned in specially designed incinerators to pro-
! duce power or separated into waste types (such as aluminum, glass, and paper) ar.d recycled. But the vast majority of MSW is sent to landfills for disposal. As the population increases and older landfills reach their capacity and close, MSW disposal becomes an important economic, health, and resource issue.
The State of Ohio has addressed the issue with the State Solid Waste Managemer,t Plan, other-wise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing land-fills by reducing the amount of MSW produced, by reusing waste material where possible and recycling of other waste materials. This is frequently referred to as " Reduce, Reuse, and Recy-cle." Davis-Besse and Centerior Energy have implemented several programs wh'ch i emphasize the reduce, reuse, recycle approach to MSW management. Improved efficiency in collection and hauling, resulted in a two year reduction of approximately 71 % for disposal cost MSW. Addi-tionally, joint partnership agreements with yard waste compositors have been developed for yard and lawn waste recycling. An Active Investment Recovery Program has greatly contributed to the reduction of both hazard-ous and municipal waste generated by evaluating options for uses of surplus materials prior to the materials entering Davis-Besse's waste streams. Such programs include papct, cardboard , alu-minum cans, used tires, and metals recycling er recovery. Greatet than 52 tons of paper and greater than 6 tons of corrugated cardboard were recycled in 1996, which would have otherwise been placed in a landfill. Additionally, approximately 600 pounds of aluminum soft drink cans are collected on site for the Boy Scouts to recycle. Lead-acid batteries are recycled and tires are i returned to the seller for proper disposal, Although scrap metal is not usually considered part of j the MSW stream, Davis-Besse does collect and recycle scrap metals. Company-wide, the Cente- j rior Energy Company collected for reclamation over 312 tons of scrape metals and copper in i 1996.The metals are sold at current market price to a scrap dealer for resource recovery. These program are continuously being expanded and reinforced as other components of MSW stre m are targeted for reduction. - l l I
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- D:vis Besse Nuclear Power Station 1996 Annu 1 Radiological Enviror. mental Operating Rcport i 1
1 l J i J L 4 h 1 1 i i APPENDIX A j INTERLABORATORY COMPARISON PROGRAM RESULT 5 t 1 j: , !~ i e 4 I i
- i e
i NOTE: Teledyne's Midwest laboratory participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratorv. Las Vegas, Nevada. The results are reported in ; Appendis A. Also reported are results of In' itional Intercomparison and Teledyne testing of T1.D's, as well as, in house spikes, blanks, d '.+ ates and mixed analyte performance evaluation program. Appendia A is updated four times . ,. tr; 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,1996 through December,1996 -
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Davis-Best.: Nuclear Power Station 19% Annual Radiological Environmental Operating Repan . Anoendir A I Intr Wratov Comnarison Pmnam Results J Teledyne's Midwest Laboratory (formerly Mazleton Environmental Sciences) has participated in interlaboratoiy comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides know to the issuing agency but not to participant 4 2 laboratories. The purpose of such a program is to provide an independent check on the laboratory'r analytical procedures and to alert it to any possible problems. l Participant laboratories measure the concentration of specified radionuclides and report them to the j 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 j control limits indicate a need to check the instruments or procedures used. J a j 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.
'Ihis program is conducted by the U.S. Environmental Protection Agency Intercomparison and
] Calibration Section, Quality Assurance Branch, Envimnmental Monitoring and Support Laboratory, ! Las Wy,as, Nevada. The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), since 1976 via j various International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Tetedyne testing results are listed. j ) l 4 Table A-3 lists results of the analyses on in-house " spiked" samples for the past twelve months. ; All samples are prepared using NIST tracable sources. Data for previous years available upon ; request. 1 i 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 nouse " 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.
i The results in Table A-6 were obtained through participatica ~ in the mixed analyte performance
- evaluation program.
l The results in Table A-7 were obtained through participation in the Environmental Measurement ! ) Laboratory Quality Assessment Program.
)
I i ) Attachment A lists acceptance criteria for " spiked" samples. l 1 t Out-of-limit results are explained directfy ivlow the result.
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i .i 156 1
f l D:vis-Besse Nuclear Power Station 1996 Annual Radiologicil Environmental Operating Report l4 i l l i 12 % l ATTACIIMENT A ACCEPTANCE CRITERI A FOR " SPIKED" SA MPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES
- i One Standard Deviation ;
Analysis Level for single determinations l Camma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg. 5% of known value ;
l 6 l Strontium-89 5 to 50 pCi/ liter or kg 5.0 pCi/ liter ! ! >50 pCi/ liter or kg 10 of knownvalue j i 6 l Strontium-90 2 to 30 pCi/ liter or kg 5.0 pCi/ liter j
>30 pCi/ liter or kg 10% of known value l 1
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 s100 pCi/ liter 5.0 pCi/ liter l >100 pCi/ liter 5% of known value j Tritium st,000 pCi/ liter is = (pCi/ liter) = ,
169.85 x (known)*"" . , >4,000 pCi/ liter ' 10% of known value ! l Radium-226,-228 <0.1 pCi/ liter 15% of known value ! Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value l I i .. . l Iodine-131, s55 pCi/ liter 6.0 pCi/ liter i Iodine-129' >M PCi/ liter 10% of known value l l Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-64 6 >35 pCi/ liter ~ 15% of known value 6
, Technetium-99 50 to 100 pCi/ liter 10 pCi/ liter om55
>100 pCi/ liter layo of known value Others" -
20% of known value
- From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies s Program, Fiscal Year,1981-1982, EPA 400/4-81-004.
- Teledyne limi'.,
de l 157 l l
- / Davis-Besse Nuclear Power Station 1996 Annual Radirlogical Environmental Operating Report ,
Tcble A-1. US. Environmental Protection Agency's crosscheck progr:m, compirison of EPA and Teledyne's Midwest Laboritory results for various sample media *. * ) Concentration in pCi/L' 2 Sample Date Teledyne Results EPA Result' Control Lab Type . Collected Analysis 12 Sigma' Is, N=1 Limits Code Jan,1996 Gr. Alpha . 19.5 i 1.5 12.115.0 3.4 - 20.8 STW-752 WATER WATER Jan,1996 Cr. Deta 7.90.7 7.015.0 0.0 - 15.7 STW-752 Feb,1996 1131 70.711.5 67.017.0 54.9 - 79.1 STW-753- WATER Mar,1996 H-3 22,776.7 1 185.0 22,002.0 i 2,200.0 18,185.1 - 25,818.9 STW-761 WATER Results where indavertently not reported due to administrative error in laboratory. 63.812.4 74.8118.7 42.4 - 107.2 STW 762 WATER Apr,1996 Gr. Alpha 2.9i 0.1 3.010.5 2.1 - 3.9 STW-762 WATER Apr,1996 Ra-226 WATER Apr,1996 Ra 228 4.610.2 5.0i13 2.7-73 STW 762 57.910.5 58.4 i 5.8 48 3 - 68.5 STW-762 WATER Apr,1996 Uranium Apr,1996 Co-60 32.710.6 31.015.0 223 - 39.7 STW-763 WATER WATER Apr,1996 Cs-134 43.011.0 46.0 5.0 373 - 54.7 STW-763 Apr,1996 Cs 137 52312.1 50.015.0 413 - 58.7 STW-763 WATER Apr,1996 Gr. Beta 154.9 i 6.8 166.9 1 25.0 123.5 - 2103 i STW-763 WATER WATER Apr,1996 Sr-89 42.013.6 43.015.0 34 3 - 51.7 j STW-763 WATER Apr,1996 Sr-90 15312.9 16.015.0 7.3 24.7 ! STW 763 l Jun,1996 Ba-133 745.0 1 19.5 745.0 1 75.0 614.9 - 875.1 STW-764 WATER Jun,1996 Co-60 97.013.6 99.015.0 903 - 107.7 STW-764 WATER Jun,1996 Cs-134 72311.2 79.015.0 703 - 87.7 g STW-764. WATER Jun,1996 Cs 137 2013 12.3 197.0 1 10.0 179.7 - 214 3 STW-764 WATER , l Jun,19% Zn-65 298.016.2 300.0 1 30.0- 248.0 - 352.0 STW-764 WATER Jun,1996 Ra-226 4.810.1 4.910.7 3.7 - 6.1
' STW-765 WATER Jun,1996 Ra 228 8.710.5 9.0123 5.0 - 13.0 STW-765 WATER Jun,1996 Uranium 20.410.8 20.213.0 15.0 - 25.4 STW-765 WATER Jul,1996 Sr-89 24.012.0 25.015.0 163 - 33.7 STW 767 WATER Jul,1996_ Sr-90 11 3 i 1.2 12.015.0 3.3 - 20.7 STW-767 WATER Jul,1996 Cr. Alpha 20.112.0 24.4 i 6.1 13.8 - 35.0 STW 766 WATER WATER jul,1996 Gr. Deta 40.413.2 44.8 5.0 36.1 - 53.5 STW-768 13.610.4 14.012.1 10.4 - 17.6 STW-774 WATER Sep,1996 Ra.226 5.410.4 4.711.2 2.6 - 6.5 STW-774 WATER Sep,1996 Ra-228 10.010.2 10.113.0 4.9 - 15 3 STW-774 WATER Sep,1996 Uranium Oct,1996 l131 26.7123 27.016.0 16.6 - 37.4 STW-775 WATER ,,
Oct,1996 Gr. Alpha 10.212.1 10315.0 1.6 - 19.0 STW-778 WATER 32.0 1.6 34.615.0 25.9 - 433 STW-778 WATER Oct.1996 Gr. Deta
- ' 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 determinatioris.
- USEPA results are presented as the knnwn values and expected laboratory precision (1s,.1 determination)
' and controllimits as defined by the EPA. 158
Davis-Besse Nucle:r Power Station 1996 Annual Radiological Environmental Operating Report . Table A-2. Crosscheck program results;Thermolununescent Dosimeters. (TLDs). mR bb Teledyne Results Known Average i2 Sigma Code U.D Type Date Measurement i 2 Sigma Value t 2 Sigma ( All Participants) 2nd intemational Intercomnarison 115-2 CaF : Mn Bulb Apr,1976 Field 17.011.9 17.1 16.4 7.7 115-2 CaF : Mn Bulb Apr,1976 Lab 20.8 4.1 21.3 18.8 7.6 Second Intemational Intercomparison of Envirorunental 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 Intercomparison 115-3 CaF:: Mn Bulb Jun,1977 FieId 30.7i 3.2 34.9 4.8 31.5 i 3.0 115-3 CaF2 : Mr. Bulb Jun,1977 Lab 89.616.4 91.7114.6 86.2124.0 Third International Intercomp3rison 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 Intemational Intercomna rison 115-4 CaF : Mn Bulb Jun,1979 Field 14.111.1 14.111.4 16.019.0 115-4 CaF : Mn Bulb Jun,1979 12b, High 40.411.4 45.8 9.2 43.9113.2 115-4 CaF : Mn Bulb Jun,1979 Lab, low 9.811.3 12.212.4 12.017.4 Fourth Intemational Intercomparison of Environmental Dosimeters conducted in the smnmer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 5th infomational Intercomrarison 115-5A CaF : Mn Butb Oct,1980 FieId 31.411.8 30.016.0 30.2114.6 115-5A CaF2 : Mn Butb Oct,1980 Lab,End 96.615.8 88.4 i 8.8 90.7131.2 115-5A CaF:Mn Bulb Oct,1980 Lab, Start , 77.415.8 75.217.6 75.8 i 40.4 Fifth Intemational 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. I Sth Intemational Intercomnarison 115-5B LiF-100 Chips Oct,1980 Fie1d 30.3 4.8 30.016.0 30.2114.6 115-5B LIF-100 Chips Oct,1980 12b, End 85.4 i 11.7 88.4 i 8.8 90.7131.2 115-5B LiF-100 Chips Oct,1980 Lab, Start 81.1 7.4 75.217.6 75.8140.4 Fifth Intemational 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 Measurernents l2boratory, New York, New York, U.S. Department of Energy. 6th Intemational Intercomcarison 115-6 Teledyne did not participate in the Sixth International Intercomparison of Environmental Dosimeters. 7th Intemational Intercomnarison 115-7A LIF-100 Chips Jun,1964 Field 75.412.6 75.816.0 75.1129.8 115-7A LIF-100 Chips Jun,1984 Lab, Co-60 80.0 3.5 79.914.0 77.9127.6 115 7A LiF-100 Chips Jan,19M Lab, Cs-137 66.612.5 75.0 i 3.8 73.0 i 22.2 Oe 159
1 Davis.Besse Nuclear Power Station 1996 . Annual Radiological Environmental Operating Repon , l Tcble A-2. Crosscheck pmgram results;hermoluminescent Dosimeters. (FLDs). mR Lab Teledyne Results Krewn Average i 2 Sigma ! Code 'll.D Type Date Measurement i 2 Sigma Value 2 Sigma ( All Participants) , Seventh Intemational Intercomparison of Environmental Dosimeters conducted in the spring and summer of f 1984 at Ias Vegas, Nevada, and sponsored by the US. Department of Energy, De Nuclear Regulatory Commission, and the US. Environmental Protection Agency. 7th Intemational Intercomoa rison i 115-7B LiF-100 Chips Jun,1964 Field 71.5 2.6 75.816.0 75.1129.8 I LIF-100 Chips Jun,1964 Lab, Co40 84.816.4 79.9 i 4.0 77.9 i 27.6 115-7B LIF-100 Chips Jun,1961 Lab, Cs 137 78.8 1.6 75.013.8 73.0122.2 115 7B Seventh Intemational Intercomparison of Environmental Dosimeters conducted in the spring and summer of ; l 1984 at Las Vegas, Nevada, and sponsored by the US. Department of Energy, The Nuclear Regulatory Commission, and the US. Envimamental Protection Agency. 7th Intemational Intercomoarison 115-7C CaSO : Dy Jun,1984 Field 76.8 2.7 75.8 i 6.0 75.1129.8 i Cards l 115-7C CaSO.: Dy Jun,1984 12b, Co-60 82.513.7 79.9 i 4.0 77.9127.6 l Cards 115-7C CaSO.: Dy Jun,1964 Lab, Cs-137 79.013.2 75.013.8 73.0122.2 Cards Seventh Intemational Intercomparison 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 l i Commission, and the US. Environmental Protection Agency. 8th Intemational Intercomoarison LIF-100 Chips Jan,1986 Field, Site 1 29.Sil.4 29.711.5 28.9112.4 115-8A LIF-100 Chips Jan,1986 Field, Site 2 11.310.8 10.410.5 10.119.1 ( 115-8 A LIF-100 Chips Jan,1986 12b, Cs-137 13.710.9 17.210.9 16.216.8 115-8A Eighth International Intercomparison of Envimnmental Dosimeters conducted in the fall and winter of l l 1985-1986 at New York, New York, arv.1 sponsored by the US. Department of F argy. l Rth Intemational intermmnarison LiF-100 Chips Jan,1936 Field, Site 1 32.3 1.2 29.7 i 1.5 28.9 12.4 115-8B LiF-100 Chips Jan,1986 Field, Site 2 9.0 1.0 10.4 0.5 10.1 9.0 i 115-8B 115-8B LiF-100 Chips Jan,1986 Lab, Cs-137 1., . 0.9 17.2 0.9 16.2 i 6.8 Eighth International Intercomparison of EnvimnmentaLDosimeters conducted in the fall and winter of l 1985-1986 at New York, New York, and sponsored by the US. Department of Energy. 8th Intemational Intercomoarison CaSO.: Dy Jan,1986 Field, Site 1 32.210.7 29.711.5 28.9112.4 115-8C Cards Jan,1986 Field, Site 2 10.6 i 0.6 10.410.5 10.1 i 9.0 115-8C CaSO.: Dy Cards Jan,1986 Lab, Cs-137 18.110.8 17.210.9 16.2 i 6.8 115-8C CaSO.: Dy Cards m l
.. 1 l
l l 160 i
)
. 1
~ i Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Ogerating Report j Table A-2. Crosscheck program results; Ihermoluminescent Dosimeters. (TLDs).
rnR Ub Teledyne Results Known Average i 2 Sigma Code TLD Type Da te Measurement t 2 Sigma Value i 2 Sigma ( All Participants) Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponso ed by the US. Department of Energy. 9th Intemational Intercomparison 115 9 The Ninth Intemational Intercomparison of Environmental Dosi:neters was not available to Teledyne's Midwest Laboratory. 10th Intemational Intercomparic.on 115-10A LiF-100 Chips Aug,1993 Field 25.7 1.4 27.0 1.6 26.4110.2 115-10A LiF-100 Chips Aug,1993 Lab,1 22.7 t 1.6 25.9 13 25.019.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62.712.6 72.711.9 69.81203 The Tenth International 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 Intemational Intercomparison - 115-10B CaSO.: Dy Aug,1993 Field 26.0123 27.011.6 26.4110.2 Cards 115-10b CaSO.: Dy Aug,1993 Lab,1 24.111.7 25.9113 25.019.4 Cards 115-10B CaSO.: Dy Aug,1993 bb,2 69.213.0 72.711.9 69.81203 Cards The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho Stat University and sponsored by the US. Department.of Energy and the Idaho Stat University. Teledyne Testing . 89 1 LiF-100 Chips Sep,1989 Lab 21.0 0.4 22.4 ND 1 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 j
- 89-2 Teledyne Nov,1989 bb 20.9 1.0 203 ND l CaSo.
- Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. l Cards were irr"diated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990.
Teledyne Testi g 90-1 Teledyne Jun,1990 bb 20.6 i 1.4 19.6 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performM by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. 161
1 Davis-B:sse Nu' clear Power Station 1996 ' Annual Radiologicti Environmental Operating Report (
* ]
Table A 2. Crosscheck program results;lhermolurninescent Dosirneters. (TLDs). . mR - Teledyne Results Known Average i 2 Sigma j bb .. i 2 Sigma Value i 2 Sigma ( All Participants) _ Code TLD Type Date Measurement [ Teladyne Testing Jun,1990 Lab 100.8143 100.0 ND i 90-2 Teledyne l CaSo.: Dy Cards I ND = No Data;Teledyne Testing was only performed by Teledyne. . l ! Cards were irradiated by Dosimetry Asssociates, Inc., NorthvC!e, MI, in October,1990. l - Teledyne Testinc Oct,1990 Lab,1 33.412.0 32.0 ND l 91 1 Teledyne l' CaSo. Dy l Cards Teledyne Oct,1990 Lab,2 55.2 4.7 58.8 ND ! 91-1 j CaSo. Dy Cards Oct,1990 Lab,3 87.816.2 85.5 ND 91 Teledyne CaSo.: Dy Cards ND = No Data:Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in October,1991. Teladvne Testine 10.7 ND i 92 1 LiF 100 Chips Feb,1992 bb,1 11.1.1 0.2 LiF-100 Chips Feb,1992 bb,2 25.610.5 25.4- ND 92-1: , ND LiF-100 Chips Feb,1992 bb,3 46.4 i 0.5 463 i 92-1 ND = No Dati: Teledyne Testing was only performed by Teledyne. i Chips were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in February,1992. ! Teledyne Testinc Teledyne Apr,1992 Reader 1, #1 20.110.1 20.1 ND 92-2 CaSo.: Dy Cards Teledyne Apt,1992 Reader 1, #2 40.610.1 40.0 ND 92-2 CaSo.: Dy Cards Teledyne Apr,1992 Reader 1, #3 . - 60.0113 603 ND 92 2 CaSo.: Dy Cards Teledyne Apr,1992 Reader 2, #1 203 103 20.1 ND 92 2 CaSo.: Dy Cards Teledyne Apr,1992 Reader 2, #2 39.2103 40.0 ND 92-2 CaSo.: Dy Cards 162
1 Davis-Besse Nuclear Power Station 19% Annual Radiological Environmental Operating Report l Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average i 2 Sigma Code T1.D Tvpe Date Measurement i 2 Sigma Value i 2 Sigma ( All Participants) 92 2 Telodyne Apr,1992 Reader 2, #3 60.710.4 603 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 April,1992. Teledyne Testinc 93-1 Teledyne Mar,1993 Lab,1 10.011.0 10.2 ND 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 LiF-100 Chips ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1993. Due to a pc cential error of 10-12% when cards where irradiated, results of the testing on the cards will not be published. Data is available upon request. Teledyne Testine 94-1 Teledyne Nov,1994 Lab,1 15.610.4 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 Lab,3 59.2103 597 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 94-1 Teledyne Nov,1994 Reader 1, #3 58.9103 59.7 ND CaSo.: Dy Cards 94 1 Teledyne Nov,1994 Reader 2, #1 . -- 15.410.2 14.9 ND
- CaSo.: Dy Cards 94 1 Teledyne Nov,1994 Reader 2, #2 31.410.2 29.8 ND -
CaSo.: Dy Cards 94 1 Teledyne Nov,1994 Reader 2, #3 60.1 03 59.7 ND CaSo.: Dy l Cards , 1 l l 1 163
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report -
?
Table A-2. Crosscheck program results;1hermoluminescent resimeters. (TLDs). , 4 mR ' Known Average 2 Sigma Lab Teledyne Results Code TLD Type Date Measurement 2 Sigma Value 2 Sigma (All Participants) , ND = No Data; Teledyne Testing was only performed by Teledyne.
- Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in November.,1994.
l Ieledvne Testing , 9 95 LIF 100 Chips Mar,1995 ' Lab,1 16.110.2 15.7 95 1- LiF-100 Chips Mar,1995 bb,2 31.7 i 0.1 32 3 95-1 LIF-100 Chips Mar,1995 bb,3 59.7 i 0.6 60.8 95-1 Teledyne Mar,1995 Reader 1, #1 16.4 i 0.1 15.7 ND CaSo.: Dy Cards- ; 95-1 Teledyne Mar,1995 Reader 1, #2 34.9 i 0.1 323 ND CaSo.: Dy , Cards 95-1 Teledyne Mar,1995 Reader 1, #3 64.4 i 1.5 60.8 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1995. Telaivne Tating , 95-2 Teledyne Mar,1995 Reader 2, #1 16.410.2 15.7 ND CaSo.: Dy Cards 95-2 Teledyne Mar,1995 Reader 2, #2 33.9'10.4 32 3 . ND CaSo.: Dy ; Cards 95-2 Teledyne Mar,1995 Reader 2, #3 60.SiO3 60.8 ND CaSo.: Dy Cards i ND = No Data; Teledyne Testing was only perforrmd by Teledyne. Cards and Chips were irradiateu by Teledyne isotopes, Inc., Westwood, New Jersey, in March,1995. l Teledvne Testine j bb,1 15.9 i 0 3 15.4 ! 96 1 LIF-100 Chips Mar,1996 bb,2 29.4 i 0 3 30.8 l 96-1 LIF 100 Chips Mar,1996 - 96-1 LIF-100 Chips Mar,1996 bb,3 62.5 i 1 3 62.5 ] 96-1 Teledyne Mar,1996 Reader 1, #1 14.4 i 0.1 15.4 ND l CaSo.: Dy , Cards 'l' 96 Teledyne Mar,1996 Feader 1, #2 31.810.1 30.8 ND CaSo.: Dy Cards
.~
ep 164
. ._ . . ..- - - - - _ . . . - . . . ~ ~. .. ._ - . . . . . ._ .- . - . .
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Table A-2. Crosscheck program results Thermolununescent Dosirneters. (IT.Ds). 2 rnR L bb Teledyne Results . Known Average i 2 Sigma
- i Code T1 D Type Da te Measurement i 2 Sigma Value i 2 Sigma (All Participants) l
- l 96-1 Teledyne Mar,1996 Reader 1, #3 64.710.4 62.5 ND CaSo.: Dy l
'. i Cards 4
ND = No Data; Teledyne Testing was only performed by Teledyne. l ., Chips and Cards were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in March,1996. l Teledyne Testine ,i _ 96-2 Teledyne Mar,1996 Reader 2, #1 14.310.4 15.4 ND
- CaSo.
- Dy ,
i Cards i 96-2 Teledyne Mar,1996 Reader 2, #2 31.810.1 30.8 ND l
; CaSo.: Dy l Cards 3 96-2 Teledyne Mar,1996 Reader 2, #3 68.610.1 62.5 ND j
] CaSo.: Dy l Cards l ND = No Data: Teledyne Testing was only perforrrei by Teledyne.' l
- Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1996. '
a (l 3 l l i d-de 165
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Regun . Tab!c A-3. In house " spike" sarnples. . Concentration in pCi/L' _ Lab Sarnple Date Teledyne Results Known Control' Ccde Type Collected Analysis 2s, n=1" Activity Limits SPCH 407 cggt Feb,1996 I-131(g) 0310.0 03 0.2 0.4 SPAP-609 AIR FILTER Feb,1996 Cs-137 -2.210.0 1.9 1.12.7 SPAP 611 AIR FILTER Feb,1996 Cr. Beta 6.810.0 8.0 0.0 - 18.0 SPW-621 WATER Feb,1996 I131 86.210.7 95.9 76.7 - 115.1 SPW-621 WATER Feb,1996 1131(g) 96.214.7 95.9 57.5 105.9 SPW-622 WATER Feb,1996 Gr. Alpha 96.416.6 82.8 41.4 - 124.2 SPW-622 WATER Feb,1996 Gr. Beta 83.7133 85.7 75.7 - 95.7 SPW-623 WATER Feb,1996 H-3 18228.7 1 3913 17833.0 14266.4 - 21399.6 SPW-624 WATER Feb,1996 Co-60 231.0 1 14.5 239 3 215.4 - 263.2 SPW424 WATER Feb,1996 Cs-137 4283124.1 4283 385.5 471.1 SPM1425 MILK Feb,1996 Cs-137 63.113.2 53.5 43.5 63.5 SPM1425 MILK Feb,1996 1131 47.810.7 48.0 36.0 - 60.0 , SPMI-625 MILK Feb,1996 I131(g) 48.012.9 48.0 28.8 - 58.0 SPVE-106g VECETATION Feb,1996 I131(g) 0.810.0 0.8 0.5 - 1.1 SPMI-2217 MILK Apt,1996 Cs-134 35.412.5 37.1 27.1 - 47.1 SPMI-2217 MILK Apr,1996 Cs-137 n7.215.4 106.6 95.9 - 1173 SPW-2219 WATER Apr,1996 Co40 26.013.4 23.4 13.4 - 33.4 SPW 2219 WATER Apt,1996 Cs-134 36.112.9 37.1 27.1 47.1 SPW-2219 WATER Apr,1996 Cs-137 117.1 i 6.4 106.6 95.9 - 117 3 SPW-2221 WATER Apr,1996 Gr. Alpha 76.916.1 82.8 41.4 - 124.2 - SPW-2221 WATER Apr,1996 Gr. Beta 132 3 i 5.0 136.8 123.1 - 150.5 SPW-2223 WATER Apr,1996 H-3 17538.9 1 354.1 17937.0 14349.6 21524.4 SPW 2283 WATER Apr,1996 I-129 15.7 i l.4 14.9 2.9 26.9 SPW-2285 WATER Apr,1996 Fe-55 1.210.5 1.1 0.0 - 21.1 SPW-2287 WATER Apr,1996 Tc-99 70.517.9 66.0 46.2 85.8 SPW-2289 WATER Apr,1996 Am-241 77.410.4 82.8 49.7 - 115.9 SPW-2289 WATER Apt,1996 Cnv244 - 37.911.7 36.4 21.8 - 51.0 SPW-2291 WATER Apr,1996 Th 230 41.611.9 45.0 27.0 - 63.0 SPW-2292 WATER Apr,1996 U-238 46.2 i2.0 45.4 31.8 - 59.0 SPF-3420 FISH May,1996 Cs-137 0.1 i 0.0 0.1 0.1 - 0.1 SPW 3439 WATER May,1996 1-131 23.9 i 0.8 25 3 133-373 SPMI 3441 MILK May,1996 1-131 23.510.5 25 3 133-373 SPMI - 4054 MILK Jun,1996 Cs-134 28.112.6 313 213-413 SPM1 - 4054 MILK Jun,1996 Cs-137 47.013.7 42 5 32.5 - 52.5 SPMI - 4054 Mll K Jun,1996 I-131(g) 39.413.6 40.4 .24.2 - 50.4 166
. D:vis-Besse Nuclear Po.ter Station 1996 Annual Radiological Environrnental Operating Report
- Table A-3. In-house " spike" sarnples. ~
l Concentration in pCi/L' Da te Teledyne Results Known Control' i Lab Sarnple l Type Collected Analysis 25, n=1' Activity Limits Code MILK 28.112.6 31 3 213 413 , SPMI-4054 Jun.1996 Cs-134 MILK Jun,1996 Cs-137 47.013.7 42.5 32.5 52.5 SPMl-4054 MILK Jun,1996 I-131 35.710.6 40 3 28.3 - 523 SPMI-4054 i M1LK Jun,1996 l-131(g) 39.413.6 40.4 24.2 - 50.4 SPM1-4054 WATER Jun,1996 Gr. Alpha 70.013.6 82.7 41.4 - 124.1 SPW-4246 WATER Jun,1996 Gr. Beta 140.513.2 136.1 122.5 149.7 SPW-4246 AIR FILITR Jul,1996 Cs-137 2.210.0 1.9 1.1 - 2.7 SPAP-4750 105.7 1 15.4 112.6 1013 - 123,9 SPW-4936 WATER Jul,1996 Co-63 WATER Jut,1996 Cs-134 127.1 1 10.9 135.2 121.7 - 148.7 SPW-49'L6 WATER Jul,1996 Cs-137 2202 120.2 211.9 190.7 - 233.1 SPW-4936 MILK Jul,1996 Cs-134 130.4 1 11.4 135.2 121.7 - 148.7 SPMI-1938 MILK Jul,1996 Cs.137 229.2 21.6 211.9 190.7 - 233.1 SPMI-4938 WATER Jul,1996 Fe-55 2.0105 1.8 0.0 21.8 SPW-4942 FISH Jul,1996 Cs-137 0.110.0 0.1 0.0 - 0.1 SPP-4996 AIR FILTER Jul,1996 Cr. Beta 7.010.0 7.8 0.0 - 17.8 SPAP-5669 WATER Aug,1996 H-3 49589.0 589.5 51058.0 40846.4 - 61269.6 SPW-5700 MILK Oct,1%'4 1-131 35.010.9 39.9 27.9 - 51.9 SPMI-7384 MILK Oct,1996 Cs-134 19.5 i 2.4 21.4 11.4 - 31.4 SPMI-7385 MILK Oct,1996 Cs-137 26.013.9 24.1 14.1 - 34.1 SPMl-7385 MILK Oct,1996 I-131(g) 1173 16.4 114 '- 68.5 - 125.5 SPMI-7385 MILK Oct,1996 I-131 64.5 14.4 79.9 63.9 - 95.8 SPMI-7444 WATER Oct,1996 1-131(g) 82.2116.2 79.9 17.9 - 89.9 SPW-7444 MILK Oct,1996 1131 235.512.8 199.7 159.8 - 239.6 SPMI-7445 WATER Oct,1996 I131(g) 190.9 14.1 199.7 119.8 - 219.7 SPW-7445 MILK Oct,1996 I-131 103.6 1.5 114.1 M3 - IM.9 SPMI 7685 AIR ITLTER Oct,1996 Cr.Deta 6010.0 6.0 0.0 - 16.0 SPAP-2 0.1-0.2 SPSO-2478 SOfL Oct,1996 Cs-134 0.2i0.0 0.2 SOIL Oct,1996 Cs-137 O.5 i 0.0 0.4 03-0.6 SPSO-2478 c1 0.4 0.0 0.4 0.2-0.5 SPCH-7473 gt Oct,1996 1-131(g) ClIAR L Oct,1996 I-131(g) 0.510.0 0.5 03-0.7 SPCH-7474 AIR FILTER Oct,1996 Cs-137 2.1 0.0 1.9 1.1 - 2.7 SPAP-7476 WATER Nov,19% Co-60 42.417.2 43.0 33.0 - 53.0 SPW-8734 WATER Nov,1996 Cs-134 29.016.6 30.1 20.1 - 40.1 SPW-8734 WATER Nov,1996 Cs-137 35.119.5 31.5 21.5 - 41.5 SPW-8734 WATER Nov,1996 H-3 25383.5 1 433.5 25075.0 2,0060.0 - 30090.0 SPW-8740 167
. . . . . . - . ~ . - . . - . . .... .. - _ - . . _ - - - . - - - . . .. .- . . _ _ - _ _ - - _ =
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Reprt af Table A-3, in-house " spike" samples. . , Concentration in pCi/L' Sample Date Teledyne Results Known Control' ! Lab Type Collected Analysis 2s, n=1' Activity Limits r Ccde 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 sampics 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. ? De 4 l 168
Divis-Besse Nuclear Powzr Station 1996 Annual Radiological Environmental Operating Report l Table A.4. In-house " blank" samples. !. Concentration pCi/L'. , 4-Teledyne Results Acceptance (4.66 Sigrna) Criteria , Lab Sample ' Sample Activity' - (4.66 Sigma) j Type Date Analysis LLD ! Code } <0.02 0.0210.13 < 1.0 SPW-7 WATER Jan 1996 Ra 226 l <0.02 0.0110.02 < 1.0 WATER Feb l996 Ra-226 i SPW < 9.6 j i CHARCOAL Feb l996 I-131(g) <2.7 0.1011.63 ! j SPCH-608 CANISTER 3.46 1339 < 10.0 a <4.1 j: SPAP-610 AIR FILTER Febl996 Co40 < 10.0
<3.6 -0.25 12.94 SPAP410 AIR FILTER Febl996 Cs-134 - < 10.0
[ <2.4 -031 12.53 SPAP410 AIR FILTER Feb l996 Cs-137 < 5.2 i } < 0. 4 032 10.29 SPAP-612 AIR FILTER Feb 1996 Gr. Beta < 10.0 j
<3.0 1.7011.60 WATER Febl996 ' Co-60.
SPW-627
< 2.5 -036 1.66 < 10.0 )
WATER Febl996 Cs-134 SPW-627
<3.2 033 i t.60 < 10.0 )
SPW-627 WATER Febl996 Cs-137 j i < 1.0 0.2010.93 <1.0 WATER Febl996 Gr. Alpha ' I' SPW-627 2.2611.76 < 3.2 Feb 1996 Gr. Beta <3.2 SPW-627 WATER < 0.5
<0.4 -0.21 i O32 SPW-627 WATER Feb 1996 I-131
-1.3812.18 < 10.0 Feb1996 Co40 <2.6 SPW-628 WATER < 10.0
<3.1 0.9512.11 SPW-628 WATER Febl996 Cs-134 0.55 1231 < 10.0 Febl996 Cs-137 <3.8 SPW-628 WATER < 0.5
<0.5 -0.18 1035 SPW-628 WATER Feb 1996 I131
-12.47 1 97.17 < 200.0 Feb1996 H-3 <197 SPW-629 WATER < 10.0
<3.5 1.26 i 1.79-SPMI430 MILK. Feb1996 Co40
<2.5 -0.1211.53 <10.0 MILK ' Feb 1996 Cs 134 SPMI430 0.22 1.44 < 10.0 .
Febl996 Cs-137 <2.6 SPMI-630 MILK
-0.07 0.24 < 0.5 Feb l996 I131 <03 SPMI430 MILK
-0.20 i l.27 < 5.0 Febl996 Sr-89 <0.9 SPMI-630 MILK ' < 1.0 N/A 1.48 0.40 SPMI430 MILK Feb 1996 Sr-90 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
0.00 t o.01 < 20.0 VECETATION Febl996 I-131(g) - <0.012 SPVE-1069 -0.00 i 0.04 < 1.0 Mar 1996 Ra-226 <0.08 SPW-3 WATER < 1.0
<0.9 0.4710.75 SPW-3 WATER Mar 1996 Ra-228 0.09 i 0.04 < 1.0 Apr1996 Ra-226 <0.06 SPW-4 WATER < 10.0
<4.8 2.5212.62 SPM1-2218 MILK Apr1996 Cs-134 4.4213.00 < 10.0 Apr1996 Cs-137 <5.4 SPMI 2218 MILK < 10.0
<2.9 0.95 1.58 SPW-2220 WATER Apr1996 Co-60 1.47 i 1.64 < 10.0 Apr1996 Cs-134 <2.7 SPW-2220 -- WATER < 10.0
< 1.9 -1.28 i 1.72
- SPW-2220 WATER Apr1996 Cs-137
<0.2 -0.2110.97 . . < 1.0
- SPW-2222 - WATER Apr1996 Cr. Alpha 169
J D;vis-B .sse Nuclear Power Statio3 1996 Annual Radiological Endronmental Operating Repon . i Table A-4. In-house " blank" samples. . Concentration pCi/L'. Teledyne Results Acceptance (4.66 Sigma) Criteria I.ab Sample Sample Activity' (4.66 Sigma) Type Date Analysis LLD Code
<2.8 2.26 i 1.57 < 3.2 SPW-2222 WATER Apr 1996 Cr. Beta l
101.30 1 70.18 < 200.0 Apr1996 H 3 <151 SPW-2224 WATER < 1.5 l
< l .4 0.2210.64 SPW-2284 WATER Apr1996 I 129
-0.0710.43 < 1000.0 Apr1996 Fe-55 <0.7 SPW-2286 WATER <10.0
<4.2 0.5512.29 SPW-2288 WATER Apr1996 Tc-99
<0.010 0.00 i 0.01 < 10.0 SPF-3421 FISH May1996 Co40
<0.014 4.0010.01 < 10.0 FISH May1996 Cs-134 SPF-3421 < 10.0
<0.015 0.0110.01 FISH May1996 Cs-137 SPF 3421 < 0.5 May 1996 I 131 < 0.1 0.0410.20 SPW-3440 WATER < 0.5
< 0.1 -0.0710.20 SPM1-3442 MILK May1996 I-131
< 1.0 0.73 11.05 < 1.0 SPW 6 WATER Jun1996 Ra-228
< 10.0 l
<8.7 2.51 14.51 SPMI-4055 M1LK Jun1996 Co40 l
<6.1 1.87 3.37 < 10.0 SPMI-4055 MILK Jun1996 Cs-134
<5.3 1.82 1 11.80 < 10.0 l SPMI-4055 MILK Jun1996 Cs-137
<0.3 0.21 0.24 . < 0.5 SPMI-4055 M1LK Jun1996 1-131 0.57 1.83 < 5.0
<0.8 SPMI-4055 MILK Jun1996 St-89 1.4910.44 <1.0 MILK Jun1996 St-90 N/A
. SPMI-4055 law level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
-0.05 i 0.70 < 1.0
<0.8 SPW-7 WATER Jul1996 Ra-228 1.26 i 1,44 < 10.0
<2.7 SPAP-4751 AIR FILTER Jul1996 Co-60 < 10.0
<4.8 1.5011.80 SPAP-4751 AIR FILTER Jul1996 Cs-134 < 10.0
<2.4 0.63 i 1.49 l SPAP-4751 AIR FILTER Jul1996 Cs-137 < 10.0
< 4.5 -0.2513.27 SPW-4937 WATER Jul1996 Co40 0.3413.39 < 10.0
<5.5 SPW-4937 WATER Jul1996 Cs-134
< 10.0
<5.7 -0.35 i 3.43 ;
SPW.4937 WATER Jul1996 Cs-137
< 10.0
< 8.0 1.13 14.73 SPMI-4939 M!LK Jul1996 Co40 < 10.0
<7.2 1.8015.18 SPMI-4939 MILK Jul1996 Cs-134 ' < 10.0
<5.8 1.01 3.77 SPMI-4939 MILK Jul1996 Cs-137
<0.6 0.1810.35 < 1000.0 l SPW-4943 WATER Jut 1996 Fe-55
< 10.0
<0.006 0.0010.00 SPF-4997 FISH Jul1996 Co-60
<0.006 -0.0010.01 < 10.0 SPF-4997 FISH Jul1996 Cs-134
<0.009 0.0110.01 < 10.0 SPF-4997 FISH Jul1996 Cs-137
<0.4 0.8010.32 < 3.2 AIR FILTER Jul1996 Gr. Beta SPAP-5670 < 1.0
<0.04 0.1610.(D SPW-8 WATER Aug1996 Ra 226
<1.0 044 10.79 < 1.0 SPW 8 WATER Aug1996 Ra-228 l
<0.05 0.0110.03 - < 1.0 SPW-9 WATER Sep1996 Ra-226 l
170 l
. . . . . - - - . _ . - _ . , . ~ ~ - - . ~ . - ~ . . _ . - - . - - - _ . . . . - . - - . - .
Davis-Besse Nuclear Power Station 1996 Annual Radiological Enviromnental Operating Reimrt , Table A-4. . In-house " blank" samples. Concentration pCi/L'. , i Teledyne Results Acceptance (4.66 Sigma) Criteria , lab Sample Sample
. Type Date Analvsis LLD Activity" (4.66 Sigma)
Code W ATER ~ Sep 1996 Sr-89 < 1.8 -0.7311.10 < 5.0 SPW-7013
<0.5 -0.0510.21 < 1.0 SPW 7013 WATER Sep 1996 Sr-90
< 1.0 0.8010.57 < 1.0 SPW-10 ' W ATER Oct 1996 Ra-223
<3.1 -0.25 2.62 < 10.0 SPMI-7382 MILK Oct 1996 Cs 134
< 4.8 0.15 2.68 < 10.0 SPM1-7382 MILK Oct 1996 Cs 137 Oct 1996 1131(g) <3.7 -1.6113.28 < 20.0 ;
SPMI 7382 MILK
< 5.7 0.2813.68 < 10.0 [
SPMI-7383 MILK Oct 1996 Cs-134
< 4.1 -1.83 3.63 < 10.0 SPMI-7383 MILK Oct 1996 Cs-137 '
< 0.4 0.1810.23 <0.5 SPMI-7383 MILK Oct 1996 1-131 Oct 1996 1-131(g) < 6.8 1.19 i 4.08 < 20.0 SPMI-7383 MILK
<0.4 -0.0810.17 <0.5 SPM1-7443 MILK Oct 1996 1-131 ;
CHARCOAL Oct1996 I-131(g) < 2.8 -1.58 1 12.74 < 9.6 SPCH-7475 CANISTER
<2.2 0.0010.00 < 10.0 SPAP-7477 AIR FILTER Oct 1996 Cs-137
<0.011 0.0010.00 < 10.0 SPSO 7479 SOIL Oct1996 Cs-134
<0.007 0.0010.00 < 10.0 SPSO-7479 SOlt Oct 1996 Cs-137 ;
AIR FILTER Oct1996 Gr.Deta < 0.7 0.10 0.45 < 3.2 SPAP 7527 FISH Oct 1996 Co-60 <0.016 -0.00 0.01 < 10.0 SPF-7505
<0.017 -0.0110.04 < 10.0 SPF-7505 FISH Oct 1996 Cs-134 FISH Oct 1996 Cs-137 <0.016 -0.0010.01 . < 10.0 SPF-7505 l < 6.0 -0.1410.10 < 10.0 l i
SPW-8735 WATER Nov 1996 Co-60 WATER Nov l996 Cs-134 <4.7 -0.53 7.69 < 10.0 SPW 8735 8.2 2.09 i 4.63 < 10.0 SPW 8735 WATER Nov 1996 Cs 137 WATER Nov 1996 Gr. Alpha < 0.3 0.1510.21 < 1.0 - l SPW-8735 l WATER Nov 1996 Cr. Beta <0.8 -0.4110.52 < 3.2 SPW-8735
<158 104.99 82.93 < 200.0
! SPW-8739 , WATER Nov 1996 H 3 l
- Liquid sample results are reported in pCi/ Liter, air fdter sample results are in pCi/ filter, charcoal samp results are in pCi/ charcoal, and solid sample results are in pCi/ kilogram.
- The activity reported is the net activity result.
I i i , l l l 171
^- - - - - -- - . _ __ . . . _ _ ,
l Davis-Besse Nuclear Power Station 19% Annual Radiologicil Environmentti Operating Report l Table A 5 In house " duplicate" samples. ~ Concentration in pCi/L' First Second Averaged Lab Sarnple Result Date Analysis Result Result Codes' 7.1423 1 0.2477 6.88801 0.1339 7.0152 1 0.1408 l CF - 20,21 Jan,1996 Gr. Beta 3.6750 03680 3.6536 1 0.1270 3.6643 1 0.1946 l CF - 20,21 Jan,1996 K-40 '
-0.0115 i 0.0138 0.00 2 1 0.0097 -0.0037 i 0.0085 CF - 20,21 Jan,1996 Sr-89 0.0045 1 0.0021 0.0051 1 0.0020 CF - 20,21 jan,1996 Sr-90 0.0057 i 0.0034 2.7900 3 3500 0.5600 1 2.6550 l Mi 47,48 Jan,1996 Cs 137 -1.6700 1 4.1200 0.0763 1 0.2005 0.0637 1 0.1473 MI- 47,48 Jan,1996 1131 0.0511 1 0.2159 0.2690 i 1.6500 1.0900 1 22400 0.6795 i 1 3911 LW - 103, IN Jan,1996 Co-60 1.0100 1 2 3800 0.7425 i 1.4174 LW - 103,104 Jan,1996 Cs-134 0.4450 i 1.5400 0.2970 1 2.2200 0.4950 i 1 3624 LW - 103,104 Jan,1996 Cs-137 0.6930 i 1.5800 2.2050 1 0.5678 2.2245 i 0 3819 LW - 103,104 Jan,1996 Cr. Beta 2.2440 1 0 3110 0.0635 1 0.1893 l l-131 0.0550 1 0 2332 0.0721 1 0.2983 LW - 103,101 Jan,1996
-1.2650 1 6.7673 l Jan,1996 1131(g) -3.9100 i 6.2600 13800 i 12.0000 LW - 103,104 99 3760 1 48.5000 89.0105 1 29.9931 LW - 100,104 Jan,1996 K-40 78.6450 1 35 3000
-0.2699 i 1.1417 0.7172 i 0.8549 CW - 132,133 Jan,1996 Cr. Beta 1.7043 i 1 2727 3.8880 1 1.5639 4.6944 1 1.1480 CW - 132,133 Jan,1996 Gr. Beta 5.5009 t 1.6811 1.6800 1 4.0900 1.4600 1 2.9528 Mi -70,71 Jan,1996 Co40 1.2400 1 4.2600 23700n 3.4200 134551 23659 MI - 70,71 Jan,1996 Cs-137 03210 1 3.2700
-0.4590 1 3.2500 0.5555 1 2.0655 MI- 154,155 Jan,1996 Co-60 1.5700 1 2.5500
-23100 1 2.5900 -1.0990 1 1.6927 M1 - 154,155 Jan,1996 Cs-134 0.1120 1 2.1800 0.6920 1 2.8500 -0.0215 1 1.7437 MI- 154,155 Jan,1996 Cs-137 -0.7350 i 2.0100 0.0326 1 02410 0.0377 1 0.1744 MI- 154,155 Jan,1996 l131 0.0429 1 02521 0.0793 1 3.8500 0.6597 i 2.5682 MI - 154,155 Jan,1996 1131(g) 1.2400 1 3.4000 1,628.4000 i 122.0000 1,574.7500 1 75.5951 MI - 154,155 Jan,1996 K 40 1,521.1000 i 893000
-0.6568 1 0.8029 -0.5925 1 0.5724 MI- 154,155 jan,1996 Sr89 -0.5282 1 0.8162 0.9595 t 03294 0.8898 1 0.2348 MI- 154,155 jan,1996 Sr-90 0.8201 1 03348
-0.0631 1 0.2130 -0.0315 1 0.1440 WW - 180,181 Jan.199n I131 0.0000 1 0.1940 02322 0.2760 0.1709 1 0.1737 MI- 298,299 jan.19% l131 0.1096 1 0 2108 1,551.7000 1 168.0000 1,565 3500 1 122.0174 MI- 298,299 Jan,1996 K-40 1,579.0000 1 177.0000
-0 3493 1 0.9041 -0.1312 1 0.6590 CW - 355,356 )an.1996 Cr. Beta 0.0868 [0.9590 2.0620 1 1.2550 2.2218 1 0.8937 CW - 355,356 Jan,1996 Cr. Deta 23816 1 1.2727 0.6880 1 1.8700 0.4120 1 1.0822 SW - 436,437 Jan,1996 Co-60 0.1360 i 1.0900 1.6100 i 1.8700 0.8441 1 1.1110 SW - 436,437 Jan,1996 Cs-137 0.0782 i 1.2000 20,597.1409 1 414 3977 20,8163571 1 294.4906 WW - 500,501 Jan,1996 H-3 21,015.5732 1 418.5372 3.1179 1 0.5254 2.9857 i 03768 SWT - 554,555 Jan1996 Cr. Beta 2.8534 1 0 5402 118.9000 1 57.7000 91.9630 1 32.1332 SW - 841,842 Jan,1996 K-40 65.0260 1 283000 7.8142 1 1 3095 7.2665 1 0.8272 SW - 479,480 f%,19% Cr. Beta 6.7187 1 1.0111 ,,
0.0602 1 5.0000 -0.4949 i 2.9002 MI - 521,522 Feb,1996 Co-60 -1.0500 1 2.9400 172
~ Davis-Besse Nuclear Power Stnion 1996 Annual Radiological Environmental Operating Repon In-house " duplicate" samples.
Table A-5. Concentration in pCi/L' Second Averaged Sample First Result Lab Result Result Date Analysis Codes * -0.3920 1 3.4400 -0.5925 1 2.2209 Feb,1996 Cs-137 -0.7930 1 2.8100 MI - 521,522 0.2232 1 0.2998 0.1682 1 0.2203 Feb,1996 1131 0.1131 03229 MI- 521,522 0.4770 1 1.5527
-0.7660 1 2.7300 1.7200 1 1.4800 MI - 580,581 Feb,1996 Co-60 0.4440 1 1.2600 0.5110 1 13069 Feb,1996 Cs-137 0.5780 1 2.2900 MI - 580,581 0.2779 1 0.2603 0.0692 1 0 3694 0.4666 i 03667 LW - 709,710 Feb,1996 Cr. Alpha 1.9519 1 0.4187 1.8215 1 0.2952 Feb,1996 Gr. Deta 1.6911 1 0.4163 LW - 709,710 60.9171 1 53.2954 37.4444 1 74 3195 84 3897 i 76.4083 LW - 709,710 Feb,1996 H-3
-0.2433 0.2580 -0.5499 1 0.2440 Feb,1996 I-131 -0.8566 1 0.4141 Mi- 603,604 1,359.1000 1 104.7020 1,382.9000 1 115.0000 1,335 3000 1 175.0000 M1 - 603,604 Feb,1996 K 40
-0.0926 1 0.2831 -0.0776 1 0.1951 Feb,1996 I-131 -0.0626 1 0 2685 WW - 648,649 -0.4776 1 0.2807
-0.8334 1 0.4012 -0.1217 1 03926 MI- 674,675 Feb,1996 1-131 1,493.6000 1 166.0000 1,442.0000 1 120.2414 Feb,1996 K-40 1,390.4000 1 174.0000 M1 - 674,675 0.1056 1 0.1522 0.1291 1 0.2170 0.08201 0.2136 WW - 865,866 Feb,1996 I131 03780123900 0.4450 1 1.4082 Feb,1996 Co40 031201 1.4900 PW - 932,933 0 3999 1 1.7318 0.0738 1 1,6600 0.72601 3.0400 PW - 932,933 Feb,1996 Cs-137 1.0300 1 1.5400 -0 3 650 1 1.8254 Feb,1996 Co-60 -1.7600 1 3 3100 SW - 911,912 -0.5785 1 2.0014
-0.2630 1 3.6000 -0.8940 1.7500 SW - 911,912 Feb,1996 Cs-137 2.2467 1 0.5131 23953103659 Feb,1996 Gr. Beta 2.5439 1 0.5217 SWT - 953,954 2.9331 1 03725 t
2.7972 1 0.5293 3.0691 1 0.5242 LW - 1037,1038 Feb,1996 Cr. Beta 76.6430 1 68,1407 36.5277 i 94.7223 116.7583 i 97.9812 LW - 1037,1038 Feb,1996 H-3
-0.1223 1 1.0275 0.2983 i 0.7812 Mar,1996 Cr. Beta 0.7188 1 1.1771 CW - 977,978 3.5395 i 1.0807 3.9324 1 1.5560 3.1466 1.5001 CW - 977,978 Mar,1996 Gr. Beta 130 3215 81.1431 130 3215 i 57 3768 Mar,1996 H-3 1303215 1 81.1431 SW - 1467,1468 -0.5947 1 1 3767
-0.0970 1 1.9887 1.0924 1 1.9042 SW - 1467,1468 Mar,1996 Sr-89 0.89201 03422 0.7297 i 0.2426 Mar,1996 Sr 90 0.5674 1 0 3439 SW - 1467,1468
-0.0360 1 0.4053 -0.1728 1 0.2944 Mar,1996 l-131 -0 3095 1 0.4234 MI- 1058,1059 1,524.5000 i 110.6628 1,500.0000 i 157.0000 1,549.0000 1 156.0000 MI- 1058,1059 Mar,1996 K-40
-1.5144 1 1.2855 -0.47211 0.7 %7 Mar,1996 Sr-89 0.5701 14).9417 MI- 1058,1059 1.9525 1 03288 1.5357 1 0 3610 23692 1 0.5498
.M1- 1058,1059 Mar,1996 Sr-90 0.1991 1 0.5613 0 3235 1 0.4213 MI- 1152,1153 Mar,1996 I 131 0.447810l>285 1,358.8000 1 172.0000 1,441.5500 1 116.4399 Mar,1996 K 40 1,524 3000 1 157.0000 M! 1152,1153 151.8191 1 82.0762 156 3020 1 58.1750 P - 1175,1176 Mar,1996 H3 160.7848 i 82.4671 2.6667 1 0.6178 2.4823 1 0.4302 Mar,1996 Cr. Beta 2.2980 1 0.5989 LW - 1213,1214 l 29.4770 1 94.5700 60.9185 1 67.7890 1.W - 1213,1214 Mar,1996 H3 92 3600 1 97.1490 f 36.8938 i 94 3559 59.6230 673896 l
SW - 1282,1283 Mar,1996 H-3 823522 1 96.2415 4.1400 1 2.4800 3.5600 1 2.6571
' Mar,1996 Co40 2.9800 1 4.7000 ,,
LW -1309,1310 2.2000 1 4.4100 1.0130 1 2.8369 LW - 1309,1310 Mar,1996 Cs-134 -0.1740 1 3.5700 ,, l 173 l l l
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Repon - Table A-5. In-house duplicate" sarnples. - Concentration in pCi/L' 12b Sarnple First Second Averaged Codes
- Date Analysis Result Result Result LW - 1309,1310 Mar,1996 Cs-137 -4.7600 1 3.9000 -1.0800 1 4.2200 2.9200 1 2.8731 LW - 1309,1310 Mar,1996 Gr. Beta 2.5861 1 0.52 % 2.8938 1 0.5364 2.7400 1 03769 LW - 1309,1310 Mar,1996 l-131 0.44371 05347 0.1485 1 0.5179 0.29611 03722 LW - 1307,1310 Mar,1996 1-131(g) 0.9870 1 5.4900 -0.6760 1 53400 0.1555 1 3.8294 LW - 1309,1310 Mar,1906 K-40 104.7400 1 51.7000 85.6000 t 56.5000 95.1700 38.2921 LW - 1362,1363 Mar,1996 H-3 162.9285 i 99 3622 107.9647 i 97.6775 135.4466 i 69.8451 LW - 1362,1363 Mar,1996 Sr-89 1.0161 1 03768 0.2819 i 13918 -0 3 671 i 0.8225 '
LW - 1362,1363 Mar,IM6 Sr.90 0.72 % i 03269 0.0477 1 0.5074 03886 03018 F 1446,1447 Mar,1996 Co-60 0.0011 1 0.0096 -0.0021 1 0.0136 -0.0005 i 0.0083 F - 1446,1447 Mar,1996 Cs-134 0.00(D 10.0080 0.0026 1 0.0132 0.0015 1 0.0077 F - 1446,1447 Mar,1996 Cs-137 0.0193 1 0.0100 0.0114 1 0.0119 0.0154 1 0.0078 F - 1446,1447 Mar,1996 C r. Deta 1.9680 1 0.0709 1.8487 1 0.0640 1.9084 0.0478 F - 1446,1447 Mar,1996 1-131(g) -0.0619 i 03550 -0.6810 i 05450 -03715i 03252 F - 1446,1447 Mar,1996 K-40 1.9652 1 0 3080 2.C071103800 2.0012 1 0.2446 SW - 1537,1538 Mar,1996 H-3 141.6453 1 96.7270 175.2449 i 98.0905 158.4451 1 68.8801 LW - 1612,1613 Mar,1996 Co-60 3.5000 1 3.0800 0.6920 i 1.6200 2.0960 i 1.7400 1 LW - 1612,1613 Mar,1996 Cs-134 1.4000 1 2.6700 1.5800 1 1.9600 1.4900 i 1.6561 : LW - 1612,1613 Mar,1996 Cs 137 4.7100 1 3.0200 13100 1 2.4100 3.0100 i 1.9319 l LW - 1612,1613 Mar,1996 Cr. Beta 2.6122 1 05460 3.0068 1 0.5285 2.8095 i 0 3799 LW- 1612,1613 Mar,1996 I131 0.2556 i 0.1548 0.0982 1 0.1470 0.1769 i 0.1067 LW - 1612,1613 Mar,1996 1-131(g) 0.2750 1 3.7100 0.7110 1 2.8600 0.49301 23422 LW - 1612,1613 Mar,1996 K-40 613000 1 33.1000 983000 i 31.4000 79.7500 1 22.8121 CW - 1709,1710 Mar,1996 Cr. Deta 4.4929 1 1.6917 3.5791 1 1.6536 4.0360 i 1.1828 l CW - 1709,1710 Mar,1996 Cr. Beta 0.4362 1 1.4668 0.2828 i 1.4589 0 3595 i 1.0344 AP - 2140,2141 Mar,1996 Sr-89 0.0001 1 0.0007 -0.0002 1 0.0007 -0.0001 1 0.0005 AP - 2140,2141 Mar,1996 Sr-90 0.0000 i 0.0002 0.0001 0.0002 0.0001 1 0.0001 WW - 1659,1660 Mar,1996 Co-60 0.1960 1 3.2100 2.2100 1 2 5200 1.2030 1 2.0405 WW - 1659,1660 Mar,1996 Cs-137 -1.8700 1 32800 2.2600 1 2.4400 0.1950 i 2.0440 WW - 1659,1660 Mar,1996 H-3 995.7658 i 1175351 1,115 3290 1 121.1114 1,055.5474 i 84 3638 PW - 1757,1758 Mar,1996 H3 8855M i 119.6998 68.8749 1 119.0511 78.7141 1 84.4115 AP -2547,2548 Mar,1996 Co-60 0.0304 1 0.0006 -0.0002 0.0006 0.0001 1 0.0004 AP - 2547,2548 Mar,1996 Cs-137 0.0001 i 0.0006 0.0030 1 0.0006 -0.0000 i 0.0004 AP -2568,2569 Mar,19% Co-60 0.0005 1 0.0005 0.0000 1 0.0004 0.00(Di 0.00CD AP - 2568,2569 Mar,1996 Cs-137 -0.0004 1 0.0005 -0.0002 i 0.0004 -0.0003 1 0.0003 MI- 1778,1779 Apr,1996 I-131 0.1746 1 03116 0.0752 1 0.1924 0.1249 i 0.1430 K-40 1,390.4000 i 98.1000 1,426.0000 1 144.0000 1,408.2000 1 87.1200 MI- 1778,1779 Apr,1996 - MI- 1778,1779 Apr,1996 Sr-89 -3.0921 1 2.1421 -1.3987 i 1.% 24 -2.2454 i 1.4526 174
.. _ . . . _ . _ _ _ . _ _ - _ _ __. _ .,_. _ _ m . _ _ ._ _m .__.__m__
Davis.Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
-i,c Table A 5. In-house "duplicste" samples.
Concentration in pCi/L' Lab Sample' First Second Averaged Cud Date Analysis Result Result Result Mi- 1778,1779 Apr,1996 Sr-90 2.2153 1 0.5049 1.9830 1 0.4425 ,LO991103357 MI- 1799,1800 - Apr,1996 Co40 0.1740 1 2.6900 - 1.89001 4 5800 L'1320i 2.6558 MI- 1799,1800 ' Apr,1996 Cs-137 2.0500 1 2.4200 1.7500 1 3.1500 1.9000 t 1.9861 MI- 1799,1800 Apr,1996 1-131 0.1298 1 0.2421 0.1053 1 0.2114 0.1176 i b.M07 MI- 1843,1844 Apr,1996 I-131 0.0149 1 0.2136 0.0570 1 0.2205 0.0359 1 0.1535 MI- 1843,1844 - Apr,1996 K 40 1,429.1000 t 93.2000 1,630 3000 1 143.0000 1,529.7000 1 85 3452 LW- 1913,1914 Apr,1996 Co40 2.2100 1 0.7960 1.1500 1 3.2300 1.6800 1 1.6633 LW - 1913,1914 Apr,1996 Cs-134 0.4140 i 0.8110 -0.7650 i 3.0700 -0.1755 i 1.5877 LW- 1913,1914 Apr,1996 Cs-137 0.5290 1 0.8890 0.5070 1 3.0900 0.5180 i 1.6077 LW- 1913,1914 Apr,1996 Cr. Deta 3.0335 1 0 5464 2.6622 05491 2.8478 1 03873 > LW-1913,1914 Apr,1996 I-131 0.0606 1 0.2364 0.0603 1 0.2573 0.0605 1 0.1747 LW 1913,1914 Apr,1996 I-131(g) -0.2280 1 1.7100 1.6800 1 5 3900 -0.9540 1 2.8274 LW - 1913,1914 Apr,1996 K-40 39.4200 i 17.4000 86.9000 1 43.4000 63.1600 1 23 3791 S O - 1946,1947 Apr,1996 Cs-137 0.1859 1 0.0270 0.1768 1 0.0201 0.1813 1 0.0168 i S O - 1946, 1947 Apr,1996 K-40 10.4690 1 0.4820 10.4630 1 03570 10.4660 1 0.2999 CW - 1991,1992 Apr,1996 Gr. Beta 3.8508 1 1.6711 4.6034 1 1.7163 4.2271 1 1.1977 CW - 1991,1992 Apr,1996 C r. Beta -0.2825 i 1.4171 0.28201 1.4546 -0.0003 1 1.0154
- WW - 1890,1891 Apr,1996 Co40 1.6200 1 1.7500 0.1810 1 2.2000 0.9005 i 1.4056 WW - 1890,1891 Apt,1996 Cs 137 -0.5890 1 1.6900 0.13701 2.5100 -0.2260 1 1.5130 WW - 1890,1891 Apr,1996 H3 538.1625 1 97.1244 6013381 1 993811 569.7503 1 69.4798 WW - 2063,2064 Apr,1996 Cr. Beta 63139 1 0.7737 6.2909 1 0.8290 6 3 024 1 0.5670
. WW - 2063, 2064 Apr,1996 H-3 69.4957 i 78.1213 26.7729 i 76.2293 48.1343 1 54.5753 MI- 2089,2090 Apr 1996 1-131 0.1583 1 02546 0.1536 i 0.2311 0.1559 1 0.1719 MI- 2089,2090 Apr.1996 K 40 1,3383000 1 180.0000 1,456.5000 i 160.0000 1,397.4000 1 120.4159 LW - 23(D,23N Apr,1996 Co-60 1.9400 1 2.9500 1.4800 3.N00 1.7100 1 2.1180 LW - 2303,23N Apr,1996 Cs-137 0.8050 1 2.7200 0.% 101 3.0000 0.8830 1 2.0247 LW 2303,2304 Apr,1996 Cr. Beta 3.7252 1 12629 4.09211 1.3004 3.9087 i 0.9063 MI-2418,2419 Apr,1996 I131 0.1925 1 0.4.050 0.2006 1 0.2588 0.1966 i 0.2403 MI-2418,2419 Apr,1996 K-40 1,418.9000 i 120.0000 1,4773000 1 182.0000 1,448.1000 1 109.0000 SS - 2442, 2443 Apr,1996 Cr. Alpha 3.5711 1 3.9146 034591 2.7237 1.9585 1 2 3845 SS - 2442,2443 Apr,1996 Cr. Beta 5 5419 i 3.0734 8.6149 1 3.2661 7.0784 1 2.2424 SS - 2442,2443 Apr 1996 K-40 7.5398 1 0.2470 7.8097 1 0.2680 7.6748 1 0.1822
-SS - 2442,2443 Apr,1996 Sr-90 0.0110i OD097 0.0030 1 0.0042 0 0070 1 0.0053 SL- 2589,2590 Apr,1996 Cs-137 0.05271 0.0297 0.06261 0.0358 0.0577 1 0.0233 l
SL - 2589,2590 Apr,1996 K-40 4.11391 0.4900 3.2858 1 0.5080 3.6999103529 ~ WW - 2700, 2701 Apr,1996 H3 -13.8536 1 73.4156 -31.1707 1 72.5940 ,- -22.5122 1 51.623 SW - 2675,2676 Apr,1996 Co40 -1.9100 1 1.9100 -1.1500 2.8600 .. -1.5300 1 1.71 % l
- l. 175
Davis-Besse Nuclear Power St:. tion 1996 Annuil Radiological Environmental Operating Report . Table A-5. In house " duplicate" samples. . Concentration in pCi/L' Lat' Sample First Second Averaged Codes
- Da te Analysis Result Result Result SW - 2675,2676 Apr,1996 Cs-137 1.0100 1 2 2000 3.0100 1 2.5900 1.0000 1 1.6991 SW - 2503,2501 Apr,1996 K 40 95 3880 472000 71.N60 36.8000 83.4670 1 30.1624 LW - 2777,2778 Apr,1996 Co-60 3.1300 1 3.7000 1.8900 1 2.7700 2.5100 1 2 3110
. LW - 2777,2778 Apr,1996 Cs 134 -1.0500 1 2.5100 -1.4600 1 2.5400 -1.2550 1 1.7855 LW - 2777,2778 ' Apr,1996 Cs-137 03840132600 2.4900 1 3.1300 1.4370 1 2.2597 LW - 2777,2778 Apr,1996 Cr. Deta 2.7205 1 0.6414 2.2112 1 0.6169 2.4658 1 0.4449 LW - 2777,2778 Apr,1996 I-131 0.19731 0.2628 -0.1244 1 0.4231 0.0365 1 0.2490 LW - 2777,2778 Apr,1996 I-131(g) 2.08001 103000 -1.7600 1 11.5000 0.1600 1 7.7191 LW - 2777,2778 Apr,1996 K-40 91.0650 1 43 2000 59.7000 i 37.0000 75 3825 1 28.43 % F- 2612,2613 May,1996 Co-60 0.0020 1 0.0070 0.0031 1 0.0137 0.0026 1 0.0077 F - 2612,2613 May,1996 Cs-137 0.00N i 0.0059 0.0082 1 0.0128 0.0043 i 0.0071 BS - 2654,2655 May,1996 Gr. Beta 4.6997 1 1.7758 5.9663 1 1.8980 5 3330 i 1.2996 BS - 2654,2655 May,1996 K-40 6.44061 0.4180 6.6513 1 03510 6.5460 1 0.2729 BS - 2654,2655 May,1996 Sr-89 0.0115 i 0.0275 0.0076 i 0.0247 0.0096 i 0.0185 BS - 2654,2655 May,1996 Sr-90 0.0021 i 0.0058 0.0010 1 0.0053 0.0015 i 0.0039 F - 2633,2634 May,1996 Co-60 0.0077 1 0.0135 0.0041 1 0.0068 0.0059 i 0.0076 F - 2633,2634 May,1996 Cs-137 0.0075 1 0.0079 0.0025 1 0.0064 0.0050 1 0.0051 MI- 2742,2743 May,1996 Co-60 -1.6100 i 3 2100 0.2250 1 2.7200 -0.6925 1 2.1037 , MI- 2742,2743 May,1996 Cs-137 0.6880 1 2.6100 -0.5110 1 2.3400 0.0885 i 1.7527 MI-2742,2743 May,1996 I-131 -0.0263 i 0.2140 0 2399 i 0.2578 0.1068 i 0.1675 l MI-2841,2842 May,1996 Co-60 2.0600 i 3 3400 0.4630 1 3.6400 1.2615 1 2.4701 l MI- 2841,2842 May,1996 Cs-137 0.44601 2.7600 3 3300 1 3.4000 1.8880 1 2.18 % MI - 2841. 2842 May,1996 1-131 03926i02720 -0.0819 1 0.2320 0.1754 1 0.1788 WW - 2866, 2867 May,1996 Gr. Deta 6.8885 1 1 3446 6.92431 13471 6.9064 i 0.9517 WW - 2866, 2867 May,1996 H-3 1783372 1 87.5017 133.)529 1 85.5877 156.0450 1 61.2001 LW - 2981,2982 May,1996 Co-60 1.94001 2.4500 0.75401 1.9900 13470 1.5782 l LW - 2981,2982 May,1996 Cs-134 0.8 moi 23500 0.1660 1 1.9900 0.4850 i 1.5397 LW - 2981,2982 May,1996 Cs-137 2.24001 2.6900 -0.7880 1 2.1600 0.7260 1 1.7249 LW - 2981,2982 May,1996 Gr. Beta 3.7095 i 0.6063 2.5867 i 0.5678 3.1481 1 0.4153 LW - 2981,2982 May,1996 I-131 -0.0178 1 0.2116 0.0518 i 0.2280 0.0170 1 0.1555 LW - 2981,2982 May,1996 I131(g) 1.9100 i 8 3 900 -2.9600 i 7.2900 -0.5250 i 5.7484 LW - 2981,2982 May,1996 K-40 121.00001 38.6000 150.7000 1 23 3000 135.8500 i 22 5436 F - 2887,2888 May,1996 Co-60 0.0025 1 0.0074 -0.0067 i 0.0107 -0.0021 1 0.0065 F - 2887,2888 May,1996 Cs-137 -0.0003 1 0.0054 0.0092 1 0.0083 0.0045 1 0.0050 j W W -3032,3033 May,1996 Gr. Beta 3.5731 1 0 3840 2.5437 i 0 5356 3.05&t 10.5168 WW - 3032,3033 May,1996 H-3 32.0189 i 83 3864 133.6172 i 88.2476 - 82 3181 1 60.8781 i SS - 2931, 2932 May,1996 Cs-137 0.2016 1 0.0948 0.1473 1 0.0352 .- 0.1745 1 0.0506 l l 176
Davis-Besse Nuclear Powrr Station 1996 Annual Radiological Environmental Operating Report ,s
- Table A-5.
In-house " duplicate" sarnples. Concentration in pCi/L' Second Averaged Lab Sarnple First Result Result Date Analysis Result Codes
- 20.157511.0M4 21.4470 1 1.7600 18.86S0 1 0.9850 SS - 2931,2932 May,1996 K 40 3.6434 1.6186 3.1445 1.1270 CW 2955,2956 May,1996 Gr. Beta 2.6457 15687
-0.4374 I.1068 -03889 1 0.7859 May,1996 Gr. Beta -0 3404 1 1.1161 CW - 2955,2956
-0.5940 1.9757 -0.0103 1.2447 MI- 3053,3054 ' May,1996 Sr-89 0.5734 1.5144 1.9168 05433 1.6382 1 0.3396 May,1996 ' Sr-90 13596 1 0.4076
. MI-3053,3054 03250143100 03255 1 2.5376
- MI-3099,3100 May,1996 Co-60 03260 1 2.6800
-0.8250 1 3.6300 -0.690012J152 MI- 3099,3100 May,1996 Cs-137 -05550125400 0.1521 1 0.2367 0.0761 1 0.1852
. MI-3099,3100 May,1996 T131 0.0000 1 0.2849 2.7477 1 0.2620 2.6871 i 0.2283 F - 3251,3252 May,1996 K-40 2.6265 1 03740 0.6314 i 0.0479 0.6111 1 0.0317 BS -3230,3231 May,1996 Cs-137 0.5908 i 0.0415 21.8090 i 0.8310 22.1265 1 0.5865 BS -3230,3231 May,1996 K-40 22.4440 i 0.8280 0.1735 1 0.2762 0.1780 0.1777 MI- 3344,3345 May,1996 I-131 0.1825 1 0.2236 1,409.5000 1 157.0000 1,5103500 1 123.2366 May,1996 K-40 1,611.2000 t 190.0000 MI-3344,3345 0.4370 1 0.1764 0.4411 i 0.1235 VE -3381,3382 May,1996 Gr. Alpha 0.4453 i 0.1729 4.0142 0.2465 4.1363 1 0.1725 VE -3381,3382 May,1996 Gr. Beta 4.2583 0.2415 4.10931 03490 4 3385 1 0.2243 VE - 3381,3382 May,1996 K-40 4.5676 1 0 2820 3.11211 0.5527 2.8165 1 03814 SWU - 3404,3405 May,1996 Gr. Beta 2.5210 1 0.5256 1883624 1 88.0751 192.9792 1 62.4152
. SWU - 3404,3405 May,1996 H-3 197 5959 1 88.4614 0.1600 1.7800 0 3255 i 1.4940 SW - 3677,3678 May,1996 Co40 0.4910 1 2.4000 r
-0.6680 1 2.1900 0.2460 1 2.0221 SW - 3677,3678 May,1996 Cs-137 1.1600 1 3.4000 6.0224 1 1.2717 5.7057 1 0.9105 SW - 3677,3678 May,1996 Gr. Beta 53891113(03 1.8916 0.4948 2.3345 1 03647 DW - 3551,3552 May,1996 Cr. Beta 2.7774 1 0.5358 0.0000 03989 0.15471 0.2729 DW - 3551,3552 May,1996 I-131 03093 03725 131.5000 1 74.9000 1223200 1 44.4265 DW - 3551,3552 - May,1996 K-40 113.1400 1 47.8000
-32.1916 79.5882 14 5481 1 56.8566 WW - 3506,3507 May,1996 H-3 3.0953 812184
-0.4110 1 3.0700 0.2400 1 1.8914 .
PW - 3700,3701 May,1996 Co-60 0.8910 1 22100 0.2960 1 3.1700 -0.6770 1 2.0279 PW - 3700,3701 May,1996 Cs-137 -1.6500 i 2.5300
-1.2600 1 4.7500 -0.9200 1 3.4086 ,
' MI 3447,3448 Jun,1996 Co-60 -0.5800 4.8900 ' -
2.6200 1 3.9300 1.6875 1 2.6614 MI- 3447,3448 Jun,1996 Cs-137 0.7550 1 3.5900
-0.0708 i 0.2845 -0.0531 1 0.1590 MI- 3447,3448 Jun,1996 1-131 -0.0354 1 0.1423 4.9200 i 0.09 % 4.8357 1 0.0698
' G-3530,3531. Jun,1996 Gr. Beta 4.7514 1 0.0978 4.5401 1 0.4480 4.7445 1 03421 G-3530,3531 Jun,1996 K-40 4.9488 1 05170
-0.0006 1 0.0057 0.0017 1 0.0040 l
- . G-3530,3531 Jun,1996 Sr-89 0.0041 0.0056 0.0009 1 0.0014 0.0005 1 0.0009 C - 3530,3531 Jun,1996 Sr-90 0.0000 1 0.0013 1.6547 1 0.6666 2.1534 1 0.4902 WW - 3597,3598 Jun,1996 Gr. Beta 2.6521 1 0.7188 107.8722 1 80.5219 .. 111.4089 i 57.04' WW - 3597,3598 .Jun,1996 H-3 114.9457 i 80 3320 5.6649 1 0.2200 5.5920 1 0.1434 G -3621,3622 Jun,1996 K-40 5.5191 1 0.1840 .-
i I77
i Davis-Besse Nucletr Power Station 1996 Annual Radiologic:1 Environmeatal Operating Report ,f i Table A 5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Date Analysis Result Result Result Codes *
-0.2191 03434 0.2403 1 03137 0.0106 1 0.2326 Mi 3612,3643 Jun,1996 1-131 Jun,1996 Cs-137 0.0147 0.0058 0.0120 1 0.0047 0.0133 1 0.0037 F - 4452,4453 Jun,19% Cs-137 0.0147 1 0.0058 0.0120 1 0.0047 0.0133 1 0.0037 F 4452,4453 Jun,1996 Gr. Beta 2.1435 1 0.1120 2.1090 1 0.1050 2.1262 0.0767 F - 4452,4453 2.1435 0.1120 2.1090 0.1050 2.1262 1 0.0767 F - 4452,4453 Jun,1996 G r. Beta Jun,1996 K-40 1.9188 1 0.1070 2.0107 i 0.1060 1.9648 i 0.0753 F - 4452,4453 Jun,1996 K-40 1.9188 0.1070 2.0107 1 0.1060 1.9648 i 0.0753 F - 4452,4453 Jun,1996 I-131 0.0373 1 0.4959 0.1570 1 0.4625 0.0972 1 03391 MI - 3830,3831 K-40 1,544.7000 i 111.0000 1,447.1000 1 159.0000 1,495.9000 i %.9562 MI- 3830,3831 Jun,1996 Jun,1996 Co40 13400 1 2.9800 2.5300 i 3.1800 1.9350 1 2.1790 MI- 3773,3774 Cs-137 3.7800 1 2.6400 -0 3320 1 2.6000 1.7240 1 1.8527 MI- 3773,3774 Jun.1996 l-131 0.1664 1 0 3100 -0.1240 1 0.4621 0.0212 0.2782 MI-3773,3774 Jun,1996 Jun,1996 Sr-89 -2.1430 i 1.8964 -13467 1 1.9330 -1.7448 i 13540
- MI- 3874,3875 Sr-90 2 3113 1 0.5587 23694 1 0.5928 2 3403 i 0.4073 Mi-3874,3875 Jun,1996 Jun,1996 K-40 6.6922 1 0.2270 7.1444 0.2770 6.9183 0.1791 G -3918,3919 Jun,1996 K-40 4.7112 1 0.5300 5.1352 1 0 3330 4.92321 03130 G - 4045,4046 Cr. Beta 2 3788 i 0.6583 1.9279 1 0.6369 2.1533 i 0.4580 SWU - 4092,4093 Jun,1996 H3 208.0150 i 84.7681 223.9706 i 85.4329 215.9928 i 60.1756 SWU - 4092,4093 Jun,1996 Jun,1996 I131 -0.1101 1 0 5660 -0.1326 1 0.5298 -0.1214 1 03876 l Mi- 4071,4072 1,229 3000 i 142.0000 1,512.1000 i 143.0000 1,370.7000 1 100.7633 MI- 4071,4072 Jun,1996 K-40 0.2841 1 1.0223 -0.4201 i 1.2371 -0.0680 1 0.8024 MI-4071,4072 Jun,1996 Sr-89 Sr-90 0.9516 1 03157 1.2585 i 0 3851 1.1050 i 0.2490 MI- 4071,4072 Jun,1996 0.2762 i 0.5142 0.1770 1 03719 WW - 4113,4114 ' Jun,1996 I131 0.0777 i 0 5375 1339151 753848 6.2494 1 75.0457 9.8205 1 53.1853 SW - 4162,4163 Jun,1996 H-3 H-3 58.4305 i 80 2304 104.2785 1 79.1202 813545 56 5543 PW - 4215,4216 Jun 1996 215.2812 i 86.9327 205 5493 1 61.1699 LW - 4259,4260 Jun,1996 H-3 195.8174 i 86.1367
-0.4630 1 1.4000 -03690 i 1.5300 -0.4160 i 1.0369 PW - 4549,4550 Jun,1996 Co-60
-1.1200 1 1.7200 -0.6960 i 1.9900 -0.9080 i 13152
- j. PW - 4549,4550 Jun,1996 Cs 137
-0.9280 1 1.9500 -0.2850 1 2.6100 -0.6065 i 1.6290 SW - 4406,4407 Jun,1996 Co-60
-0 3900 1 2.4300 2.5700 1 2.9300 1.0900 i 1.9033 SW - 4406,4407 Jun,1996 Cs-137 1.0430 1 0.0595 1.1245 1 0.0648 1.0837 i 0.0440 E 4284,4285. Jul,1996 Gr. Beta 1.1372 1 0.1830 1.1588 1 0.1160 1.1480 1 0.1083 E - 4284,4285 Jul,1996 K-40 0.0019 1 0.0044 0.0016 i 0.0045 0.0017 1 0.0032 E - 4284,4285 Jul,1096 Sr-89
-0.0001 1 0.0011 0.0003 i 0.0010 0.0001 i 0.0007 E - 4284,4285 )ul,1996 Sr-90 1.1828 1 0 3499 1.2369 1 0 3447 1.2098 1 0.2456 WW - 4305,4306 Jul,1996 C r. Deta l -1.0600 1 3.4400 -0.6150 1 2.2756 MI- 4326,4327 JuL1996 Co-60 -0.1700 1 2.9800
-0.0644 1 2 4300 2.0100 i 2.9700 0.9728 i 1.9835 Mi- 4326,4327 Jul,1996 Cs-137 178 .
- Davis-Besse Nuclear Power Station 1996 Annu 1 Radiological Environmental Operating Report Table A.S. In-house " duplicate" samples.
Concentration in pCi/L' Second Averaged Sample First Lab Result Result Date Analysis Result Codes
- 67.8970 1 52.2108 H-3 24 S404 i 71.8799 110.9537 1 75.7439 P - 4431,4432 Jul,1996
-0.0022 i 0.0030 -0.0004 1 0.0021 AP - 4595,45% Jul,1996 Sr-89 0.0015 1 0.0029 0.0002 0.0007 0.000510.00th AP 4595,45% Jul,1996 Sr 90 0.0008 i 0.0006 1.1800 1 2.4300 1.2400 1.6157 WW - 4375,4376 Jul,1996 Co40 13000 1 2.1300 1.0200 2.8700 1.0650 i 1.82 %
WW - 4375,4376 Jul,1996 Cs-137 1.1100 1 2.2700 25.4322 i 77.1605 -28.0937 1 54.4741 WW - 4375, 4376 Jul,1996 H-3 -30.7552 1 76.9153 0.1693 1 0.2869 0.0652 0.2009 Mi- 45(D,4504 Jul,1996 1-131 -0.0390 1 0.2814 1,188 3000 1 136.0000 1,237.7000 1 1053767 Jul,1996 K-40 1,287.1000 1 161.0000 MI- 45CD,4504
-1.7702 i 1.2061 -1.6338 1 0.7709 MI - 45(0,4504 Jul,1996 Sr-89 -1.4974 1 0.9605 2.4509 i 0.5124 2.0084 1 0 3675 MI - 45(D,4504 Jul,1996 Sr-90 1.5658 i 0.5270
-1.2100 1 2.6300 0 5 750 i l.8281 Mi- 4527,4528 Jul,1996 Co-60 23600125400 1.9000 1 2.5500 1 3455 i 1.5930 MI- 4527,4528 Jul,1996 Cs-134 0.7910 1 1.9100 0.0613 i 2.2900 -0 3 139 i 1.5301 M!- 4527,4528 Jul,1996 Cs-137 -0.6890 1 2.0300 0.0901 1 0.4519 0.14061 03200 MI-4527,4528 Jul,1996 1-131 0.1910 1 0.4532 0.1290 1 3.5800 0.0360 1 2.2817 Mi- 4527,4528 Jul,1996 1-131(g) -0.0570 1 2 3300 1,408.6000 1 107.0000 1,413.8500 1 703290 Jul,1996 K 40 1,419.1000 i 913000 MI- 4527,4528
-1.4605 i 1.1500 -0.9162 0.769(
MI- 4527,4528 Jul,1996 Sr-89 -0 3720 1 1.0231 1 3388 1 0.2716 1.1956 i 0.1780 M1 - 4527,4528 Jul,1996 Sr-90 1.0524 1 02303
-12.9958 i 77.6342 21.8566 i 54.6088 WW - 4684,4685 Jul,1996 H-3 -30.7174i76E208 0.8849 1 1.2477 0.9416 1 0.8852 W W 4808,4809 Jul,1996 Gr. Beta 0.99831 12558
-30.4456 i 72.7801 -22.7473 i 54.% 77 WW - 4808,4809 Jul,1996 H-3 -15.0491 1 823946 7.2772 i 0.2280 7.1240 1 0.2055 G -4762,4763 Jul,1996 K-40 6.9707 1 0 3420 1.1600 1 1.8600 0.0000 i 1.2498 LW - 4832,4833 Jul,1996 Co-60 -1.1600 i 1.6700 1.6900 1 2.2400 13550 13851 LW - 4832,4833 Jul,1996 Cs-137 l_0200 1 1.6300 335451 0.6948 3.4074 i 0.4941 LW - 4832,4833 Jul,1996 Cr. Beta 3.4602 i 0.7027 335451 0.6948 3.4074 1 0.4941 LW - 4832,4833 Jul,1996 Cr.Deta 3.4602 1 0.7027 2.0288 0.6093 2.0197 0.4314 LW - 5014,5015 Jul,1996 Gr. Deta 2.0107 1 0.6109 0.0522 1 0.0182 0.0528 1 0.0125 Jul,1996 Cs-137 0.0534 1 0.0171 F - 5515,5516 2.4865 1 0.0643 251131 10911 2.4617 1 0.0908 F - 5515,5516 Jul,1996 G r. Beta 2.6688 i 0.3560 2 5 369 1 0.2286 F - 5515,5516 Jul,1996 K-40 2.4049 1 02870 3.9669 i 1.5535 3.0749 i 1.0630 CW 4956,4957 Jul,1996 Cr. Beta 2.1830 1 1.4513 0.2749 i 0.8554 0.4288 i 0.7422 CW - 4956,4957 Jul,19% Gr. Beta 0.5827 1 12131 0.1870 1 1.8700 -0.40651 13365 Jul,1996 Co40 -1.0000 1 1.9100 SW - 5248,5249
-0.5680 1 2.4400 0.0955 i 1.6697 SW - 5248,5249 Jul,1996- Cs-137 0.7590 i 2 2800 317.9144 i 96.0148 250.6632 i 66.1398 WW - 5215,5216 Jul,1996 H3 183.4121 1 90.9893
-1.7100 i 4.1800 .. -0.2600 1 2.5931 Ju!,1996 Co40 1.1900 1 3.0700 MI- 5081,5082
-2.8800 1 3 3400 -1.1940 1 2.1163 ,
MI - 5081,5082 Jul,1996 Cs-137 0.4920 i 2.6000 - 179
Davis-Besse Nuclear Power Station 1996 Annual Radi: logical Environmenut! Operating Report . Table A-5. In house " duplicate" samples. ' Concentration in pCi/L' First Second Averaged Lab Sample Result Result Result Codes
- Date Analysis 0.1808 i 05572 0 5417 i 0.6704 0 3613 1 0.4359 M1 - 5081,5082 Jul,1996 1-131 0.1808 i 0.5572 03699 1 0.6986 0.2754 1 0.4468 Mi- 5031,5082 Jul,1996 1131 4.1217 i 2.0543 5.5300 1 2.3022 4.8258 i 1.5427 SWU - 5125,5126 Jul,1996 Cr. Deta 125.7490 1 88.7348 151.0734 i 63.4460 SWU - 5125,5126 Jul,1996 H3 176 3979 i 90.7067 3.1394 1 0.1026 3.0940 1 0.0683 3.1167 1 0.0616 VE - 5146,5147 Jul,1996 Cr. Beta .
3 3818 i 0.1400 3.4692 1 0.1430 3.4255 i 0.1001 VE - 5146,5147 Jut,1996 K 6.4711 1 1 3831 5.9871 1 1.2673 6.2291 1 0.9379 DW - 5269,5270 Jul,1996 Gr. Beta 0.21261 03519 0.04041 03202 0.1265 1 0.2379 DW - 5269,5270 Jul,1996 1-131
-0.0474 i 0.4432 -0.6129 i 0.5327 -03302103465 MI-5168,5169 Aug,1996 1131 1,585.8000 i 123.0000 1,534.4000 1 162.0000 1,560.1000 1 101.7018 MI-5168,5169 Aug,1996 K-40
-0.0550 1 0 5085 -0.3445 1 0.5937 -0.1998 i 03909 MI-5289,5290 Aug,1996 I-131
-1.6400 i 2.7500 -0.1890 1 4.0300 -0.91451 2.4394 MI-5190,5191 Aug,1996 Co-60 0.1550 1 3.1400 0.6150 i 33900 03850123104 MI- $190,5191 Aug,1996 Cs-137 0.2155 1 0.4940 0.4414 1 0.4691 03285103406 M1-5190,5191 Aug,1996 I-131 0.0012 1 0.0107 0.0083 1 0.0085 0.0047 1 0.0068 SL - 5424,5425 Aug,1996 Co-60 0.0054 i 0.0084 0.0071 1 0.0063 SL - 5424,5425 Aug,1996 Cs-134 0.0089 i 0.0094 0.0365 1 0.0149 0.0347 1 0.0113 SL- 5424,5425 Aug,1996 Cs-137 0.0328 1 0.0171 0.0005 1 0.0304 -0.0166 1 0.0275 -0.0081 1 0.0205 SL- 5424,5425 Aug,1996 1131(g) 1.6391 1 0.2110 1.6034 1 0.1647 SL -5424,5425 Aug,1996 K-40 1 5677 i 0.2530
-3.4000 1 4.8300 -1 3015 1 2.8942 M1-5386,5387 Aug,1996 Co-60 0.7970 1 3.1900 1.7500 1 3.4900 1.4450 1 2.1880 MI-5386,5387 Aug,1996 Cs-137 1.1400 i 2.6400
-0.0211 i 0.2171 -0.0073 1 0.1472 MI- 5386,5387 Aug,1996 I-131 0.0065 1 0.1987
-0.0271 1 0.2797 -0.0103 1 0.1716 MI-5386,5387 Aug,1996 I-131 0.0065 1 0.1987 2.4356 1 0 5278 1.9586 1 0.4235 SWU - 5905,5906 Aug,1996 Gr. Beta 1.4815 1 0.6624 306.5672 i 86.2631 281.8715 i 60 3037 SWU - 5905,5906 Aug,1996 H-3 257.1759 i 84.2902
-0.0245 1 0.5563 0.1058 i 0 3984 MI-5582,5583 Aug,1996 1131 0.2361 1 0.5705 1,459.0000 i 152.0000 1,466 3000 i 117.7964 Mi- 5582,5583 Aug,1996 K-40 1,473.6000 1 180.0000
-0.8030 i 1 5400 -0.0350 1 1.1921 LW - 5606,5607 Aug,1996 Co-60 0.7330 1 1 3200
~
-0.8750 1 2.5900 -0.1890 1 1.6031 LW - 5606,5607 Aug,1996 Cs-137 0.4970 i 1.8900 5 3355 i 1.2524 5 3 795 1 0.8923 LW - 5606,5607 Aug,1996 Gr. Beta 5.4236 1 1.2712 0.0289 i 0.0152 0.0303 i 0.0103 SL-5667,5668 Aug,1996 Cs-137 0.R316i 0.0139 2.6982 1 0.2670 2.5714 1 0.1975 SL- 5667,5668 Aug,1996 K-40 2.4446 i 0.2910 4.5529 i 1.5367 4.1419 1 1.0646 CW -5759,5760 Aug,1996 Gr. Beta 3.7309 1 1.4739 0.6561 1.1136 0.6562 1 0.7876 CW -5759,5760 Aug,1996 Gr. Beta 0.6563 1 1.1139
-4 3400 1 4.6000 3.7100 1 4.8200 -03150133314 MI-5817,5818 Aug,1996 Co-60 0 3 575 1 2.7561 w
,Aug,1996 Cs-137 -0.6750 i 4.2000 139001 3.5700 -
Mi-5817,5818 0.0522 i 0.0769 0.0405 1 0.0531 MI- 5817,5818 Aug,1996 1-131 0.02871 0.0732 180
+ Davis-Bisse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report ,
Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Date Analysis Result Result Result l Codes
- l, SWT - 5884,5885 Aug,1996 Gr. Beta 2.7135 0.7709 2.8640 0.7248 2.7888 0.52M 3.5571 0.M76 3.797010.90M 3.6770 0.5547 SW - 5925,5926 Aug,1996 Gr. Beta Aug,1996 -0.1138 1 0.5079 03728 0.4119 0.1295 03270 MI- 5978,5979 1-131 1,468.4000 1 179.0000 1,560.8000 1 173.0000 1,514.6000 124.46S9 MI - 5978,5979 Aug,1996 K-40 Co-60 0.0006 0.0062 0.0028 0.0058 0.001710 ON3 VE - 5950,5951 Aug,1996 Cs-137 -0.0006 1 0.0048 0.0003 1 0.0047 0.0002 0.00M VE - 5950,5951 Aug,1996 2.9014 1 0.0919 2.7239 0.1833 2.8126 1 0.1025 VE - 6031,6032 Sep,1996 Gr. Beta K-40 3.2199 i 0.1950 33724 0.3060 3.2962 i 0.1814 2 VE - 6001,6032 Sep,1996 0.0018 i 0.0024 -0.0004 i 0.0021 0.0007 1 0.0016 VE - 6031,6032 Sep,1996 Sr-89 Sr-90 0.0002 0.0007 0.0009 0.0007 0.0006 0.0005 VE - 6031,6032 Sep,1996 Co-60 0.9250 i 1.0500 -0.5060 1 1.5400 0.2095 1 0.9319 LW - 6052,6053 Sep,1996 LW - 6052,6053 Cs-134 03430i 13200 0.8910 1 2 3000 0.6170 13259 Sep,1996 Cs-137 0.0211 1 12900 -0.1280 i 1.8600 -0.0535 i 1.1318 LW - 6052,6053 Sep,1996 2.1334 1 0.7031 3.0766 1 0.5583 2.6050 1 0.4489 l LW - 6052,6053 Sep,1996 Gr. Beta
-0.4089 1 03821 0.0180 1 03249 -0.195S 1 0.2508 l LW - 6052,6053 Sep,1996 I-131 1.2200 1 6.0300 1.7000 1 10.1000 1.4600 1 5.8816 i LW - 6052,6053 Sep,1996 1-131(g)
K-40 66.8250 30.1000 43.6000 1 27.1000 55.2125 20.251t LW - 6052,6053 Sep,1996 1.6248 1 0.6211 1.0281 1 0.6056 13264 1 0.4337 WW - 6181,6182 Sep,1996 G r. Deta H-3 5 3932 1 82.7475 62.9204 i 85.2105 34.1568 i 593885
- WW - 6181,6182 Sep,1996 I-131 0.0780 1 0 3076 0.0130 1 03110 0.0455 i 0.2187 MI- 6006,6007 Sep,1996 1,472.0000 1 166.0000 1,502.9000 i 110.0000 1,487.4500 1 99.5691 M1 - 6006,6007 Sep,1996 K-40 4.6340 i 1.6130 4.5894 i 1.6139 4.6117 1 1.1409 CW - 6128,6129 Sep,1996 C r. Beta 4.6340 1.6130 4.5894 1.6139 4.6117 i 1.1409 CW - 6128,6129 Sep,1996 Gr.Deta 0.2285 1 1.1265 0 3197 1 1.1117 0.2741 1 0.7913 4
CW - 6128,6129 Sep,1996 Gr.Deta H-3 113.2802 85 3 728 61.4098 i 83.1710 87 3450 1 59.5943 SW - 6204,6205 Sep,1996 Co-60 1.9300 ! 2 3500 -0.5880 2.5900 0.6710 1.9255 Mi- 6225,6225 Sep,1996 2.7700 i 2.7200 -0.2550 i 2.4700 1.2575 1 1.8371 Mi- 6225,6226 Sep,1996 Cs-137 MI- 6225,6226 I131 -0.2584 0.4450 0.2718 1 03680 0.0067 0.2887 Sep,1996 K-40 2.2202 02730 2.0725 1 0.2780 2.1464 i 0.?948
~
VE - 6270,6271 Sep,1996 16,801.2285 i 999.6339 17,111.8829 i 1,006.N94 16,956.5557 i 709.1198 WW - 6331,6332 Sep,1996 H-3 4.7742 1 1.1613 3.9486 i 1.6377 4 3614 i 1.0038 CW - 6294,6295 Sep,1996 G r. Deta 1.0482 i 1.2275 -0.3383 i 1.0818 03550 1 0.8181 CW - 6294,6295 Sep,1996 Cr. Beta K-40 1.7000 1 0.2860 1.8440 1 0.1800 1.7720 1 0.1690 VE - 6379,6380 Sep,1996 St-89 -0.0018 0.0018 -0.0009 0.0014 0.0013 0.0012 4 VE - 6379,6380 Sep,1996 Sr-90 0 0012 0.0006 0.0005 i 0.0005 0.000810.00N VE - 6379,6380 Sep,1996 3.1975 1 1.54 % 3.2345 1 1.4740 3.2160 1 1.0694 CW - 6432, M33 Sep,'1996 Gr. Beta ,. 2.8412 0.0780 2.8390 1 0.0736 2.8401 1 0.0536 VE - 6481,6482 Sep,1996 Cr. Beta ,, 181
Davis.Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report , Table A-5. In-house " duplicate" samples. , Concentration in pCi/' ' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result hE M81,6482 Sep,1996 K-40 3 3857 i 0.2370 3.5694 0.1540 3.4776 i 0.1413 SW - 6524,6525 Sep,1996 H-3 223.5203 i 90.7888 151.2226 87.8631 1873714 1 63.1715 SWT - 6545,6546 Sep,1996 Cr. Beta 2.7317 1 0.5235 2.1160 i 0.4971 2.4238 03610 j AP 7220,7221 Sep,1996 Co-60 0.0006 1 0.0007 0.0001 i 0.0011 0.0003 1 0.0006 AP - 7220,7221 Sep,1996 Cs-134 -0.0001 1 0.0006 0.0001 1 0.0007 -0.000010.00N l AP - 7220,7221 Sep,1996 Cs-137 -0.0002 1 0.0006 0.0009 1 0.0008 0.00N i 0.0005 I AP- 7220,7221 Sep,1996 1131(g) 0.0013 1 0.0041 0.0004 1 0.0063 0.000810.0CB8 AP- 7220,7221 Sep,1996 K-40 0.0193 1 0.0100 0.0297 i 0.0160 0.0245 1 0.0094 DW - 6572,6573 Sep,1996 Cr. Alpha 1.0283 1 0.6412 0.2799 1 03100 0.6541 1 03561 DW - 6572,6573 Sep,1996 Cr.Deta 2.8779 i 0 3307 2.4510 1 0.2702 2.6645 1 0.4368 SW - 6593,6594 Sep,1996 H3 58.2259 80.0303 89.9855 i 81.4187 74.1057 i 57.0830 CW - 6616,6617 Sep,1996 Gr. Deta 3.1242 1 1 4295 4.9871 1 1.7193 4.0556 i 1.1844 CW - 6616,6617 Sep,1996 C r. Deta 0.2660 i 1.0617 -0.2956 i 1.0299 -0.0148 1 0.73 %
PW - 6675,6676 Sep,1996 H-3 21.6674 i 80.1010 88.4752 i 83.0584 55.0713 1 57.6950 AP - 7537,7538 Sep,1996 Co-60 0.00C010.0005 -0.0000 1 0.0007 0.0001 0.0005 AP- 7537,7538 Sep,1996 Cs-137 0.000210.00N 0.0002 1 0.0007 0.000210.00N VE - 6654,6655 Sep,1996 Co40 -0.0057 1 0.0156 0.0022 1 0.0147 -0.0018 1 0.0107 VE - 6654,6655 Sep,1996 Cs 137 0.0128 1 0.0133 0.0131 1 0.0110 0.0130 1 0.0086 CW - 6719,6720 Sep,1996 Cr. Beta 2.991011.4M4 2.1008 1 1.5104 2.5459 1 1.0312 CW - 6719,6720 Sep,1996 Cr. Beta -0 3107 1 1.0842 1.1119 1 1.1700 0.4006 i 0.7976 AP- 7558,7559 Sep,1996 Co 60 0.0003 1 0 0004 0.0008 1 0.0007 0.0006 1 0.0004 AP - 7558,7559 Sep,1996 Co-60 0.0003 i 0.00N 0.0008 1 0.0007 0.0006i 0.00N AP - 7558,7559 Sep,1996 Cs-137 -0.0001 1 0.0004 0.0002 1 0.0007 0.000110.00N AP - 7558,7559 Sep,1996 Cs 137 -0.000110.00N 0.0002 1 0.0007 0.000110.00N WW - 6696,6697 Sep,1996 H3 313.7207 i 98.9677 302.7129 i 98.5588 308.2168 i 69.8363 LW - 7118,7119 Sep,1996 Cr. Alpha 0.N4810.4053 -0.1825 1 03885 -0.0688 1 0.2807 LW - 7118,7119 Sep,1996 Cr. Beta 2.0623 1 0.4378 1.5831 1 0.5835 1.8227 03647 LW - 7118,7119 Sep,1996 H-3 89.2546 i 81.1237 92.8011 i 81.2786 91.0279 i 57.4179 ; E - 6783,6,51 Oct,1996 Gr. Beta 0.9337 1 0.0331 0.9578 1 0.0317 0.9457 1 0.0229 E - 6783,6784 Oct.1996 K-40 0.8969 1 0.1320 1.1090 1 0.1530 1.0029 1 0.1010 E 6783,6784 Oct,1996 Sr-89 -0.0002 1 0.0032 -0.0009 i 0.0029 -0.0006 1 0.0022 E - 6783,6784 Oct,1996 Sr 90 0.0005 1 0.0013 0.0005 1 0.0012 0.0005 1 0.0009 SW - 6877,6878 Oct.1996 H3 1,223.4684 1 1195914 1,320.2432 i 122.4059 1,271.8558 i 85.5647 AP - 7199,7200 Oct,1996 Sr-89 -0.0006 i 0.0015 0.0005 1 0.0020 -0.0001 i 0.0013 AP -7199,7200 Oct 1996 St-90 0.00N i 0D006 0.0006 1 0.0008 0.0005 1 0.0005 Mi - 6746,6747 Oct,1996 1131 -0.092510.2M0 0.1078 1 0.2514 ,. 0.0077 i 0.1823 M1 6746,6747 Oct,1996 K-40 1,427.9000 1 180.0000 1,425 3000 1 208.0000 1,426.6000 i 137 5354 182
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Table A-5. In-house duplicate" samples. Concentration in pCi/L' First Second Averaged lab Sample Result Result Date Analysis Result Civtos' 0.0164 1 0.0108 0.0030 t 0.0057 0.0097 1 0.0061 F - 6824,6825 Oct,1996 Co-60 0.0087 1 0.0073 0.0039 1 0.0051 0.0063 0.0M4 F - 6824,6825 Oct,1996 Cs-137 0.8880 i 1 3900 -0.4140 2.7800 0.2370 1 1.5541 WW - 6926,6927 Oct,1996 Co-60 1.2900 1 1.5000 1.8300 3.2300 1.5600 1.7807 WW - 6926,6927 Oct,1996 Cs 137 3.5430 1 77.7859 1.7715 1 55.1738 WW - 6926,6927 Oct,1996 H-3 7.0861 1 78.2685 0.0N610.0099 0.0059 1 0.0133 C - 7001,7002 Oct,1996 Co-60 0.0072 1 0.0247 0.0N310.0099 0.0072 1 0.0106 C - 7001,7002 Oct,1996 Cs-134 0.0101 1 0.0188
-0.0068 1 0.0204 -0.0042 1 0.0093 -0.0055 0.0112 C -7001,7002 Oct,1996 Cs 137 5.2080 0.2600 5.1980 0.2600 5.2030 0.1838 G - 7001,7002 Oct,1996 Gr. Beta 0.0141 1 0.0183 0.0002 1 0.0207 G - 7001,7002 Oct,1996 I-131(g) -0.0137 i 0.0372 5.5229 1 0.4170 5.8589 1 0.4147 G - 7001,7002 Oct,1996 K-40 6.1948 i 0.7170 0.0248 0.0125 0.0195 i 0.0091 SS - 7024,7025 Oct,1996 Cs-137 0.0141 1 0.0132 6.4672 1 1.8437 7.0597 i 1 3708 SS - 7024,7025 Oct,1996 Gr. Beta 7.6523 1 2.0292 6.9053 1 0.4040 7.0417 i 03416 SS - 7024,7025 Oct,1996 K-40 7.1780 1 0 5510
-0.7530 1 2.9100 0.4335 1 2.1296 LW - 7045,7046 Oct,1996 Co-60 1.6200 1 3.1100
-1.9300 1 3.0500 -0.9773 1 2.1531 LW - 7045,7N6 Oct,1996 Cs-134 -0.0246 1 3.0400 1.9300 1 2.9700 0.4735 1 2.0581 LW - 7045,7046 Oct,1996 Cs-137 -0.9830 1 2.8500 2 8922 0.534 ' 2.8571 1 0.4580 LW - 7N5,7M6 Oct,1996 C r. Deta 2.8219 1 0.7438
-0.2043 1 0.4541 0.0184 1 0.2926 LW - 7045,7046 Oct,1996 I-131 0.2410 1 0.5690 5.8000 1 27.7000 032501 203795 l LW- 7045,7046 Oct,1996 I131(g) -5.1500 1 29.9000 34.5000 1 33.8000 42.9000 1 25 3912 LW -7045,7046 Oct,1996 K-40 513000 1 37.9000 2.7243 0.1020 2.7585 1 0.0978 F- 6952,6953 Oct,1996 K-40 2.7927 1 0.1670 1.8000 2.8100 0.5195 1 2.7767 MI-6853,6854 Oct,1996 Co40 -0.76101 4.7900
-0.8890 1 2.4000 0 3305 1 2.1592 MI- 6853,6854 Oct,1996 Cs 137 1.5500 1 3.5900 0.2027 i 0.2586 0.0490 1 0.1886 MI- 6853,6854 Oct,1996 I-131 -0.1N710.2745 0.4510 4.9000 1.1255 i 2.8243 Oct,1996 Co40 1.8000 1 2.8100 MI- 6854,6855 0.4510 4.9000 1.1255 1 2.8243 Oct,1996 Co-60 1.8000 1 2.8100 MI- 6854,6855 0 3505 1 2.0281
-0.8890 1 2.4000 1.5900 1 3.2700 MI- 6854,6855 &t,1996 Cs-137 1.5900 1 3.2700 0 3505 1 2.0281 MI- 6854,6855 Oct,1996 Cs-137 -0.8890 1 1 4000
-0.1840 1 0.2910 -0.0675 1 0.1734 Oct.1996 I-131 0.0490 1 0.1886 MI- 6854,6855 0.0082 1 0.1949 0.2000 1 0.2600 -0.183710.29N MI- 6854,6855 Oct,1996 I-131
-0.1840 1 0.2910 0.0094 1 0.1946 Oct,1996 I-131 0.2027 1 0.2586 MI- 6854,6855 8.7497 i 1.6993 9.5648 i 2.4583 7.93451 23466 BS - 7138,7139 Oct.1996 Gr.Deta 7.2N8i 03301 7.2366i 0.4030 7.1729 1 0.5230 BS-7138,7139 Oct,1996 K-40 0.224310.N37 0.2309 1 0.0252 Oct,1996 Cs-137 0.2375 1 0.0250 S O - 7306,7307 9.472010.433<
9.4591 1 0.4680 9.4848 1 0.7300 S O - 7306,7307 .Oct,1996 K-40 " 1.45421 03070 1.5681 1 0.2215 Oct,1996 Gr. Beta 1.6819 1 03193 BO - 7747,7748 183
Divis-Besse Nuclear Power Station 19% Annual Radiological Environmental Operating Report e ,
\
i Table A-5. in-house " duplicate" samples. Concentration in pCi/L' 1 First Second Averaged Lab Sample Result Result Result Codes
- Date Analysis Oct,1996 K 40 0.7271 i 0.1770 0.5964 1 0.1430 0.6617 1 0.1138 BO 7747,7748 '
CEt,1996 2.0975 1 0.4500 1.7161 1 0 3850 1.9068 i 0.2961 F - 7328,7329 K 40
-0.1241 1 02405 -0.0565 i 0.2463 -0.0903 1 0.1721 MI 7285,7286 Oct,1996 1-131 2.2278 i 0.9950 2.6814 1 0.7230 CW - 7176,7177 Oct,1996 Cr. Beta 3.1350 i 1.0492
-0.4959 1 1 3277 -2.6954 i 1.1984 1 5956 1 0.8943 Mi - 7351,7352 Oct,19% Sr 89 1.6216 1 0.4003 1.5659 i 0 3840 1.5938 1 0.2774 MI - 7351,7352 Oct,1996 Sr 90 1.92031 02360 1.7284 1 0.2700 1.8244 1 0.1793 VE -7425,7426 Oct,1996 K-40 Oct,1996 2.1800 1 5.1000 5.8600 1 53900 4.0200 1 3.7102
- Mi- 7514,7515 Co.60 Oct,1996 Co-60 2.1800 1 5.1000 5.8600 i 53900 4.0200 1 3.7102 Mi-7514,7515 Oct,1996 0.2630 1 3.4000 13400143000 0.8015 1 2.7409 Mi-7514,7515 Cs.137 Oct,1996 0.2630 1 3.4000 13400143000 0.8015 1 2.7409 MI-7514,7515 Cs-137 Oct,1996 -0.0367 1 0.2747 0.0170 1 0.2780 -0.0098 i 0.1954 MI-7514,7515 1-131 Oct,1996 Co.60 0.0051 1 0.0115 0.0050 1 0.0119 0.0051 1 0.0083 F -7584,7585 Oct,1996 Cs-137 0.0018 1 0.0087 0.0006 i 0.0094 0.0027 i 0.0064 F -7584,7585 Oct,1996 Co-60 0.5440 i 1.7200 -3.0500 1 2.8000 -1.2530 i 1.6430 WW - 7653,7654 0.5440 1 1.7200 -3.0500 i 2.8000 -1.2530 1 1.6430 WW - 7653,7654 Oct.1996 Co-60 Oct,1996 -0 3090 1 1.9800 -13700 1 3.5700 -0.8395 1 2.0412 WW - 7653,7654 Cs-137 Oct,1996 -0 3 090 i 1.9800 1.3700 1 3.5700 -0.8395 1 2.0412 WW - 7653,7654 Cs-137 Oct,1996 H-3 -20.6120 1 753854 27.0900 1 78.0749 3.2390 i 54.4387 WW - 7653,7654 Oct,1996 K-40 2220901 03210 23.4780 1 0.8550 22 3435 i 0.5927 SS -8040,8041 Oct,1996 Gr. No 2.7320 05059 2.1353 1 0.5134 2.4337 i 0 3604 SWT- 7972,7973 Oct,1996 Cr. Beta 1.2200 1 1.7000 23526 1 1.7822 1.7863 1 1.2315 CW - 7794,7795 Oct,1996 Cr. Beta 1.6467 1 0.4826 1.8357 1 0.4589 1.7412 1 03330 ;
DW - 7994,7995 Oct,1996 H-3 64.0848 i 81.6689 29.6241 1 80.1237 46 3545 i 57.2049 DW - 7994,7995 Nov,1996 Cr.Deta 5.2418 1 0.7885 4.8908 1 0.7351 5.0663 1 0 5390 WW - 8121,8122 Nov,1996 H-3 49.1914 1 783272 25.7955 1 77.2446 37.4935155.0(M2 WW - 8121,8122 Nov,1996 Gr. Beta 2.0590 1 1.7640 -0.0624 1 1.6065 0.9983 1 1.1930 CW - 8089,8090 Nov,1996 Cr. Beta -03253115458 0.0296 i 1.5731 -0.1479 1 1.1027 CW - 8089,8090 I Nov,1996 C r. Beta 2.5755 1 05930 1.9537 1 0.5962 2.2646 1 0.4204 SWU - 8213,8214 SWU - 8213,8214 Nov,1996 H-3 257S646i86I697 234.9041 1 85.7288 246 3843 i 60.9530 l l Nov,1996 K-40 1092500 1 412000 97.1440 i 52.0000 1C0.1970133.1717 SWU - 8213,8214 Nov,1996 Cr. Beta 0.9444 i 1.4135 2.1017 1 1.4184 1.5230 1 1.0012 CW - 8302,83(B Nov,1996 I-131 -0.C286i 0.2146 0.0724 1 0.2406 0.0219 i 0.1612 Mi- 8337,8338 Nov,1996 K-40 1,454.6000191I>000 1,365.5000 i 193.0000 1,410.0500 1 106.8171 MI- 8337,8338 Nov,1996 H-3 4,719.0000 1 197.0000 4,718.8773 1 197.2068 4,718.9387 i 1393732 WW - 8561,8562 Nov,1996 Gr. Beta 3.1780 1 0.6522 2.4547 1 0.6458 2.8164 1 0.4589 SW - 8581,8582 ,_ WW - 8681,8682 Nov,1996 Cr. Alpha 0.1083 1 1.7623 -1.6686 1 1.5384 -0.7802 i 1.1697 184 i 1
" Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Reivart
~'
Table A-5. In-house " duplicate" sarnples. Concentration in pCi/l ' L.ab Sample First Second Averaged Date Analysis Result Result Result Codes
- WW - 8681,8682 Nov,1996 Cr. Beta 2.7636 i 1.6718 1.2914 1.6711 2.0275 1 1.1819 CW - 8612,8613 Nov,1996 C r. Deta 2.5959 1 1.4986 1.9085 1.4277 2.2522 1 1.0349 CW 8612,8613 Nov,1996 Cr. Deta 0.0730 1.0631 -0.7679 i 1.0588 -03474 0.7502 CW - 9219,9220 Nov,1996 Co-60 0.4990 1 1.9100 -0.2780 !.6600 0.1105 1.2653 CW - 9219,9220 Nov,1996 Cs-137 13800 1 2.0100 0.1520 2 1.6300 0.7660 i 1.2939 2,206.2783 i 149.9008 2,148.9684 1 105.0076 CW - 9219,9220 Nov, IW6 H3 2,091.6585 i 147.0922 Nov,19% Gr. Alpha 0.1864 1 0 3044 0.41301 03037 0.2997 1 0.2150 CW - 8830,8831 Nov,1996 Cr. Beta 11.077310/A82 10 2141 1 0.5784 10.6457 i 0.4344
- CW - 8830,8831 Nov,1996 H-3 2,053.4722 i 144.0356 2,112.1937 1 145.4793 2,082.8329 i 102 3603 4 CW - 8830,8831 CW - 8830,8831 Nov,1996 Sr-89 -0.2648 1 0.5335 -0.2665 1 0.6325 -0.2656 0.4137 Nov,1996 Sr-90 0.2880 1 0 3295 0.29801 03905 0.2930 1 0.2555 CW -8830,8831 D w,1996 Cr. Deta 2.4968i 0.8(D7 3.0769 1 0.7797 2.7869 1 0.5599 SW - 8635,8636 l SW - 8635,6636 Dec,1996 K-40 90.1230 1 52.8003 90.4480 1 51.9000 90.2855 1 37.0184 DW - 8660,8661 Dec,1996 Gr. Beta 2.1325 1 0.5706 1.8680 1 0.5881 2.00(D i 0.4097 DW - 8660,8661 Dec,1996 H-3 110.0746i 83I>820 1173323 i 83.9962 113.7035 1 59.2833 4 MI- 8704,8705 Dec,1996 I131 -0.2720 1 0.2656 -0.2978 1 0.2604 -0.2849 1 0.1860 Dec,1996 K-40 1,301.2000 1 141.0000 1,342.9000 i !50.0000 1,322.0500 1 102.9' j MI- 87N,8705 D w,1996 Co-60 0.4980 1 2.7500 0.4080 1 4.4400 0.4530 1 2.6113 MI - 8725,8726
) 1 - MI-8725,8726 Dw,1996 Cs-134 1.2300 i 2 3300 -0.6450 3.8000 0.2925 1 2.2287 D w,1996 Cs 137 1.7600 1 2.5400 1.11001 33900 1.4350 i 2.1180
- MI-8725,8726 Da,1996 1131 0.1756 1 0.18 % -0.1739 0.2108 -0.1747 i 0.1418 MI- 8725,8726 Mi- 8725,8726 Dec.1996 I-131(g) -0.9720 i 3.4000 4 5100 1 4.8700 1.76n0 2.997 Dw,1996 K-40 1,402.2000 i 111.0000 1,297.5000 1 150.0000 1,349.8500 93 3019 M1 - 8725,8726 MI 8725,8726 D w,1996 Sr-89 -1.0624 1 1.0291 -1.N6311.0N4 -1.0543 1 0.7190 Dw 19% Sr 90 13308103709 1.12321 03625 1.2270 1 0.2593 Mi - 8725,8726 SO 8802,8MD liv 19% Cs-137 0.467010.M19 0.4514 0.0374 0.4592 1 0.0281 SO - 8802, IWD Ik,19% Gr. Alpha 14.0253 1 4 2670 13.8M0 4.0228 13.9447 i 2.9322 SO - 8802,8&D Ik,19% C r. Beta 21.4173 1 3.1354 21.4610 1 2.8794 21.4391 2.1285 SO - 8802,88(D K-40 11.089010.6M0 10.8030 0.6130 10.9460 1 0.4518 Dec.1996 Dec, * - % C r. Beta 7.5204 1 03776 5.9562 0.8260 6.7383 1 0.6026 SWU - 9540,9541 SWU - 9540,9541 Dec,1996 H4 90.1991 1 86.7053 86 5424 i 86.5510 88 3707 i 61.2554 F - 9040,9041 D x,1996 Co 60 -0.0006 i 0.0144 -0.0002 1 0.0150 -0.0004 i 0.0104 F - 9040,9041 1%<, IM6 C4-134 -0.001510.01(B 0.0005 1 0.0120 -0.0005 i 0.0079 L k ,1996 Cs 137 0.0371 1 0.0163 0.N28 0.0186 0.0400 1 0.0124 F - 9040,9041 Dec,1996 Cr. Beta 3.5649 1 0.0939 3.5230 0.0939 3 5440 1 0.0664 F-9MO,9N1 F-9MO,9N1 D w,1996 1-131(g) 0.0008 i 0.0151 -0.00N i 0.0153 ,_
0.0002 1 0.010' F - 9040,9N1 K-40 3.2987 1 0.4720 3.0073 1 0.4330 3.1530 1 03203 Dec.19% , , , 185 i
. . . _ ._ __ . . . . ~ _ .. . . __ _.
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report
- Table A-5. In. house " duplicate" samples. -
Concentration in pCi/L' 12b Sample First S&ond Averaged Codes
- Date Analysis Result Result Result D e,1996 Cr. Beta CW - 9109,9110 4.1495 1.2265 1.9601 1 1.5457 3.0548 1 0.9866 CW - 9109,9110 D e,1996 Cr. Beta -0.8681 1 13230 -1.1056 i 1 3024 -0.9869 0.9282 Mi- 9197,9198 Dec,1996 l131 0.0738 t 03589 -0.1464 1 03804 -0.0363 1 0.2615 Mi 9197,9198 Dec,1996 K-40 1,462.6000 1 143.0000 1,381.2000 1 149.0000 1,421.9000 103.2594 WW 9269,9270 Dec,1996 .40 -1.1100 1 2 3300 -0.2890 1 2.6000 -0.6995 i 1.7456
' Dec,1996 0.2210 1 2.5500 -0.4945 i 1.6872 WW - 9269,9270 C3-137 -1.2100 1 2.2100 WW - 9269,9270 D e,1996 H-3 1,051.0538 1 116.7594 1,126.1290i119 G359 1,088.5914 i 83 3701 I LW - 9291,9292 Dec,1996 Co-60 -0.2250 2.0000 1.24001 23400 0.5075 1.5391 LW - 9291,9292 Dec,1996 Cs.137 4.0400 i 2.1800 0.1930 1 2.8300 2.1165 i 1.7861 LW - 9291,9292 Dec,1996 Cr. Beta 4.8680 i 1 3409 7 3432 i 1.4448 6.1056 1 0.9856 SW - 9743,9744 Dec,1996 H-3 1.2426 1 89.7614 51.5686 i 91.8276 26.4056 i 64.2056 SW - 9414,9415 Dec,1996 Gr. Beta 3.9527 1 0.6945 4.6396 1 0.7606 4.2961 1 0.5150 DW - 9RU,9521 Dec,1996 Cr. Beta 6.1588 i 1 3500 5.6935 1.2445 5.9261 0.9180 DW - 9520,9521 Dec,1996 1-131 0 3470 1 0.4182 0.2339 1 0.4184 0.2905 1 0.2958 CW -9383,9384 Dec,1996 Cr. Beta 4.7813 i 1.7392 4.5942 1 1.5609 4.6877 1 1.1685 CW - 9383,9384 Dec,1996 Gr. Beta 0.6113 i 1.4866 0.4335i 1.4715 0.5224 i 1.0459 SW 9433,9434 Dec,1996 H-3 309.2956 i 91.1018 247.0810 1 88.6107 278.1883 1 63.5545 SW - 9497,9498 Dec,1996 H-3 241.0070 i 91.8990 126.5590 i 87.2570 183.7830 1 63 3625 DW - 9564,9565 Dec,1996 C r. Beta 2.0290 1 0.5925 2.1508 i 0.5749 2.0899 i 0.4128 DW - 9564,9565 Dec,1996 H3 120.7999 i 83 3742 94.1528 i 82.2309 107.4763 i 58.5516
- All concentrations are reported in pCi/ liter, except solid samples, which are reported in pCi/ gram.
- 12b codes are cornprised of the sample media and the sample numbers. Client codes have been eliminated to protect client anonymity.
e i e We 186
. - .- - . -. - - - -- - ~ . .- - - . _ . - - - .
- Davis.Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report l
Table A.6. Department of Energy's Mixed Analyte Performan media'. Concentration in Bq/kg* MAPEP Result' Control Teledyne Results Limits Sample Date is, N=1 Lab Collected Analysis iStandard Deviation' Code Type 28.712.8 20.9 - 37.3 27.0 SOIL 9p,1996 Am-241 STSO-776 Standard deviation for three determinations not reported in Mixed Analy Summary Report. 568.4 - 1,055.6 879.0 812.0 1 83.5 SOIL Sep,1996 Coq 50 STSO-776 Standard deviation for three determinations not reported in Mixed Analyte Summary Report. 1,531.0 193.4 1,071.7 - 1,990.3 1,716.0 SOIL Sep,1996 Cs-137 ' STSO-776 Standard deviation for three determinations not reported in Mixed Analyte Summary Report. 15.9 i 1.8 11.1 - 20.7 13.0 SOIL Sep,1996 Pu.238 STSO-776 Standard deviation far three determinations not reported in Mixed Analyte Summary Report. 19.7 i 2.0 13.8 - 25.6 18.0 i SOIL Sep,1996 Pu.239/240 STSO-776 Standard deviation for three determinations not reported in Mixed Analyte P Summary Report. S36.0157.1 375.2 - 6 % .8 441.0 SOIL Sep,1996 Sr-90 STSO-776 ' Standard deviation for three determinations not reported in Mixed Analyte T Summary Report. M.9 i 7.3 44.7 - 83.1 59.0 SO!L Sep,1996 U-234/233 S15 0-776 Standard deviation for three determinations not reported in Mixed Analyte Pe Summary Report. 64.016.4 44.8 - 83.2 60.0 SOIL Sep,1996 U-238 S750-776 Standard deviation for three determinations not reported in Mixed Analyte Pe Summary Report.
- Results obtained by Teledyne Brown Engineering Environmental Services Midwest La participant in the Department of Energy's Mixed Analyte Performance Evaluatio Idaho Operations office, Idaho Falls, Idaho.
- All results are in Becquerels per kilogram as requested by the Department i of Energy.
f three
- Unless otherwise indicated, the TBEESML results are given as the mean i 1 standard
- determinations.
M APEP results are presented as the known values and expected laboratory p and control limits as defined by the M APEP. . I i 6-187 i
Davis-Besse Nuclear Power Station 1996 Annual Radiologicd Environmental Operating Report Tab!: A 7. Environmental Measurements laboratory Quality Assessment Program (EML), i comparison of EML and Teledyne's Midwest laboratory results for various sample , media'. l Concentration in Bq/L* l Lab Sample Date Control i d Code Type Collected Analysis Teledyne Result' EML Result Limits * { WATER Mar,1996 Am-241 0.810.1 0.810.0 0.7 - 1.6 i STW-755 WATER Mar,1996 Co-60 33.6 1.0 32.810.6 0.9 - 1.2 STW-755 STW-755 WATER Mar,1996 Cs-137 42.811.3 38310.9 0.9-13 l STW-755 WATER Mar,1996 Fe-55 109.0 1 21.7 83.013.4 03-1.6 WATER Mar,1996 H-3 434.0 1 34.1 251.0 11.4 0.7 - 1.9 STW 755 WATER Mar,1996 Mn-54 41.9 i 1.4 38.411.2 0.9 - 1.2 STW-755 STW-755 WATER Mar,1996 Pn-238 0.9i0.1 1.010.1 0.7-13 WATER Mar,1996 Pu 239 0.710.1 0.810.1 0.6 - 1.4 STW-755 STW-755 WATER Mar,1996 Sr-90 2.210.7 1.510.0 0.7 - 1.7 WATER Mar,1996 Cr. Alpha 2,180.0 1 53.5 1,850.0 i 185.0 0.6-13 S1W-756 S1W-756 WATER Mar,1996 Gr. Beta 872.0 1 27.0 744.0 1 74.0 0.8 - 1.7 STSO-757 SOIL Mar,1996 Am-241 6.212.9 3.710.5 0.5 - 2.4 ST50-757 SOIL Mar,1996 Cs-137 404.0 0.2 359.0 1 10.0 0.7 - 1.4 l STSO-757 SOIL Mar,1996 K-40 525.0 23 3 465.0 1 30.0 0.7-1.6 ST50-757 SOIL Mar,1996 Pu-238 42 3 i 1.6 43.012.4 0.2-2.0 STSO-757 SOIL Mar,1996 Pu-239 9.010.7 9.2103 0.6 - 2.0 STSO-757 SOIL Mar,1996 Sr-90 1,200.0 323 1,340.0 i 113.0 0.6 - 3.0 STSO-757 SOIL Mar,1996 Uranium 68.212.4 71.7 i 4.2 0.3-1.5 SWE-758 VEGETATION Mar,1996 Am-241 6.1113 5.610.2 0.6 - 2.9 VEGETATION Mar,1996 Cm-244 6.011.2 4.410.2 0.4 - 1.9 STVE-758 STVE-758 VEGETATION Mar,1996 Co-60 65.614.0 59.711.0 0.6 - 1.5 STVE-758 VEGETATION Mar,1996 Cs-137 1,100.0 1 12.6 944.0 i 16.2 0.8-1.5 , VEGETATION Mar,1996 K-40 1,190.0 i 61.6 1,030.0 1 33.0 0.5 - 1.5 STVE-758 STVE-758 VEGETATION Mar,1996 Pu-239 9.2 13 9.8 1.2 0.6 - 2.0 STVE-758 VEGETATION Mar,1996 Sr-90 1,210.0 1 32.2 1,300.0i S2.4 0.5-1.4 STAF-759 AIR FILTER Mar,1996 Am-241 03i0.0 0.2 0.0 0.6 - 1.9 STAF-759 AIR FILTER Mar,1996 Ce-144 23.2 1.0 333133 0.6-13 STAF-759 AIR FILTER Mar,1996 Co-57 6.1 0.1 8.9 0.9 0.6-13 STAF-759 AIR FILTER Mar,1996 Co-60 26.510.4 29.512.9 0.7-13 AIR FILTER Mar,1996 Cs 134 12.9 03 14.711.5 0.7 - 1.2 STAF-759 , STAF-759 AIR FILTER Mar,1996 Cs 137 6.210.9 6.6i0.7 0.7-13 STAF-759 AIR FILTER Mar,1996 Mn-54 3310.4 3.41.0.4 0.8-13 AIR FILTER Mar,1996 Pu.238 0.110.0 0.110.0 0.6 - 1.6 STAF-759 AIR FILTER Mar,1996 Pu 239 0.1 0.0 0.110.0 0.7 - 1.6 l STAF-759 AIR FILTER Mar,1996 Ru 106 10.2 i 1.9 11.6 i 1.4 0.5 - 1.6 l STAF-759 AIR FILTER Mar,19>6 Sb-125 10.1 0.8 9.811.0 0.4 - 1.4 l STAF-759 AIR FILTI!R Mar,1996 Sr.90 1.1 0.2 1.110.0 0.6-23 f STAF-759 AIR FILTER Mar,1996 Uranium 0.1 0.0 0.110.0 0.8-2.9 STAF-759 I88
~~ . Davis-Desse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report Environmental Measurements Laborstory Qualitymple Assessment Program (EML)
Table A-7. comparison of EML and Teledyne's Midwest Laboratory results for various sa media'. Concentration in Bq/L* Control Date EML Result' Limits' Lab Sample Analysis Teledyne Resuit' Type Collected 0.8 - 1.6 Code 2.2 0.1 1.610.2 AIR FILTER Mar,1996 Gr. Alpha 1.8 0.2 0.8-1.9 STAF-760 2.0 0.0 0.6 - 1.7 AIR FILTER Mar,1996 Gr. Beta 13 0.2 1.1 1 0.0 STAF-760 0.9 - 1.2 WATER Sep,1996 Am-241 61.110.7 STW-770 (5.0 2.2 0.9-13 WATER Sep,1996 Co-60 89.5 i 1.4 STW-770 95.113.0 0.5-13 WATER Sep,1996 Cs-137 1,210.0 t 121.0 STW-770 993.') 12.2 0.6 - 1.6 i WATER Sep,1996 Gr. Alpha 540.0 1 54.0 STW 770 57c.018.1 0.7 - 1.9 WATER Sep,1996 Cr. Deta 587.0 1 58.0 S1W 770 *88.0134.6 WATER Sep,1996 H-3 60.5 i 0.6 0.9-1.2 S1W-770 65.0 3.0 0.7-13 WATER Sep,1996 Mn-54 1.9 i 0.1 STW-770 13103 He analysis was WATER Sep,1996 Pu-238 STW-770 An investigation was conducted. No errors/LinNocalculations or transcription further action is planned. repeated in duplicate under 0.710.2 the observation 0.810.0 0.81.4 of the Techn 0.7 - 1.7 WATER Se- :996 Pu-239 2.710.2 STW-770 3.610.7 WATER
, 996 Sr-90 0.510.0 0.8 - 1.5 STW-770 0.510.2 WATER L- 16 U-234 0.510.4 0.8 - 1.4 S~lW-770 0.4 0.1 0.5 - 2.7 WATER Sep, J 6 U-238 13.5 i 0 5 STW-770 15.613.8 0.5-15 SOIL Sep,1996 Am-241 2.910.2 STSO-771 4.012.5 SOIL Sep,1996 Co-60 1,550.0 22.2 0.8-13 STSO-771 1,750.0 24.4 SOIL Sep,1996 Cs-137 300.0 1 25.0 0.7-1.7 STSO-771 369.0 1 59.5 Sep,1996 K-40 1.1i0.2 0.4 - 1.9 STSO-771 SO!L 0.810.4 Sep,1996 Pu-238 21.8 i 1.1 0.7 - 1.9 STSO-771 SOIL 24.011.9 Sep,1996 Pu-239 69.9 i 5.1 0.5 - 2.8 ST50-771 SOIL 63.6 4.0 SOIL Sep,1996 Sr-90 39.212.4 0.4-13 STSO-771 37.2 3.8 0.4 - 1.6 SOIL Sep,1996 U-234 41.610.6 ST50-771 40.8 4.0 0.7-2.8 SO!L Sep,1996 U-238 1.2 0.4 STSO-771 1.5 0.9 0.5 - 1.7 VEGETATION Sep,1996 Am-241 0.810.1 STVE-772 0.6 0.5 0.6 - 1.4 VEGETATION Sep,1996 Cm-244 10.910.7 STVE-772 14.014.4 VEGETATION Sep,1996 Co-60 190.016.7 0.8 - 1.5 STVE-772 219.0110.1 0.8 - 1.5 VEGETATION Sep,1996 Cs-137 992.0 i 29.0 STVE-772 , 1,160.0 i 99.4 VEGETATION Sep,1996 K-40 1,390.0 1 12.0 0.5-13 STVE 772 1,420.0 1 35.1 VEGETATION Sep,1996 Sr-90 14.810.8 0.6 - 1.2 STVE-772 11.8103 0.7 - 1.2 AIR FILTER Sep,1996 Co-57 8.610.4 STAP-773 9.210.4 AIR FILTER Sep,1996 Co-60 10.810.4 0.7 - 1.2 STAP-773 9.610.4 0,7-13 AIR FILTER Sep,1996 Cs 134 8.5 0.4 STAF-773 8.7 0.4 0.8 - 1.6 AIR FILTER Sep,1996 Cs-137 1.210.1 STAP-773 0.710.0 discovered. The AIR FILTER Sep,1996 Gr. Alpha STAP-773 An investigation was conducted and a transcription d error while calculating the 1.1510.01Bq/ filter. No further action is planne .
recalculated value is 189 l I
Davis-Besse Nuc13ar Power Stotion 1996 Annual Radiological Environmental Operating Report t Table A-7. Environrnental Measurements bboratory Quality Assessment Program (EML), , comparison of EML and Teledyne's Midwest I.aboratory results for various sample media'. Concentration in Bq /L* Lab Sample Date Control Code Type Collected Analysis Teledyne Result' EML Result' Limits' STAP-773 AIR FILTER Sep,1996 Gr. Beta 0.50.0 0.5 0.1 0.7 - 1.8 STAP-773 AIR FILTER Sep,1996 Mn-54 7.1 0.5 6.4103 0.8-13 STAP-773 A1R FILTER Sep,1996 Ru-106 11.5 3.2 10.8 1.1 0.6 - 1.3 STAP-773 AIR FILTER Sep,1996 Sb-125 12.4 1.0 10.810.5 0.6 - 1.4
- The Environmental Measurements bbomtory provides the following nuclear species : Air Filters, Soll, Tissue, Vegetation and Water. Teledyne does not participate in the Tissue program.
~
- Results are reported in Bq/L ' with the following exceptions: Air Filter results are reported in Bq/ Filter', Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg. The results of elemental Uranium are
~
reported in ug/ filter ', g, or ml.
- Teledyne results are reported as the mean of three determinationsistandard deviation.
' 'Ihe EML result listed is the mean of replicate determinations for each nuclideithe standard error of the mean.
- The control limits are reported by EML and are established from percentiles of historic data distributions (19821992). 'Ihe evaluation of this historie data and the development of the control limits is presented in DOE report EML-564.
1 l l l l a ee e. 190
. - - . . . . _ = _ . ~ . . = .. __ .__.
l V Davis-Besse Nuclear Power SttI n 1996 Annual Radiolo& ca! i Enuironmental Operating Report l l i s APPENDIX B DATA REPORTING CONVENTIONS E o de 191
- . . . ~ . . ... . . - . - - . = , . - - . . . .-_ . . . . .
Divis-Besse Nuclear Power Station 1996 Annual Radiologicd Environmental Operating R port e Data Renortina Conventinns 1.0. All activities except gross alpha and gross beta are decay corrected to collection time or the end of the collection period. 2.0. Sincie Measurements Each single measurement is reported as follows: x s where x = value of the measurement; 5 = 2s counting uncertainty (corresponding to the 95% confidence level). In cases where the activity is found to be below the lower limit of detection L it is reported as
<L .
where L = the lower limit of detection based on 4.66s uncertainty for a background sample. 3.0. Duplicate analyses 3.1 Individu11 results. x11 st x11s2 Recorted rtsult - xis where x = (1/2) (x11 x2) 2 2 s = (1/2) s+s3 2
- 32. Individual results <L1 l l
<L2 l
Reoorted result: <L where 1. kus er of L1 and L2
' ~
- 33. Individual results: xis
<L Reporttd rt-ult x s if x 2 L:
<L otherwise 1
4.0. Computation of Averaces and Standard Deviations l 192
Davis-Besse Nuclear Power Station 1996 Annuil Radiological Environmental Operating Report 4 s f l 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. 'Ihe average x and standard deviation (s)of a set of n numbers x1, x2 . xn are defined as follows: 1 x =- Ex E(xx)2 5* 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 f associated two sigma error is reported. 4.5 In rounding off, the following rules are followed: 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example,11.443 is rounded off to 11.44. ; ,- 4.5.2. If the figure following tho$ to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example,11.445 is ' rounded off to 11.45.
*w-
- .1 I
193
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report i l APPENDIX C J
- Effluent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ;
f J d 4 4 a l b O# 194 4
).
, Davis-Besse Nucicar Power Station 1996 Annu 1 Radiologicd Environmental Operating Report l
Table C-1 Effluent Concentration Limit of Radioactivity in Air and Water l Above Natural Background in Unrestricted Areas' 1 l l Air Water ! l Gross Alpha lE-03 pCi/m' Strontium-89 8,000 pCi/l ! Gross Beta 1 pCi/m' Strontium-90 500 pCi/l l Iodine-131' 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 pCill
)
Gross Beta 100 pCi/l Tntium lx10' pCi/l a- Taken from Code of Fedeeral Regulation Title 10. Part 20, Table Il and appropriate footnotes. Conan: rations nuy 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 e the an grass <ow<hild pathway, c A natural radionuclide. i o ' 195 i
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report j o l l l I l APPENDIX D REMP Sampling Sun:rnary l l A O4 196
~ . . _ _ _- _ _ _ _ . _ - . . _ _ _ _ _ _ _ _ . . _ . _ . _ . . _ _ _ . . . _ _ - . . _ .__.m_ .
t
- . L - Divis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report A
j: Table 4.5 Radiological Environmental Monitoring Program Summary. Name of Facility Davis Besse Nuclear Power Station Docket No. 50-346 locationof Facility otrawa, Ohio Reporting Period January - December 1996 , (County, State) : indtcator Location with Eghest Control ' Sample . Type and Number locations Quarterly Mean locations Type. Number of Non-LLDb Mean (F)C Routine (Units) Analyses a Mean (F)C Mean (F)e Rangec Locationd Rang c Range Results' Airborne CB 520 0.005 - 0.019 (311/312) T-11, Port Clinton, particulates 0.021 (52/52) 0.019 (207/208) O (0.006-0.044) 9.5 mi SE (0.010 4.036) (pCi/m3) (0.008 4.038) e Sr-89 40 0.0033 (LLD - -
<LLD 0 St-90 40 0.0011 <LLD - -
<LLD 0 CS 40 Be-7 0.015 0.079 (24/24) T-11, Port Clinton, 0.090 (4/4) 0.080 (16/16) 0 (0.050-0.10) 9.5 mi. SE (0.069-0.10) (0 X7-0.10)
K-40 0.042 <LLD - -
<LLD 0 Nb-95 0.0016 <LLD l
<LLD 0 i
j Zr-95 .0.0028 <LLD - -
<LLD 0 l Ru-103 0.0012 <LLD t
(LLD 0 [ Ru-106 0.011 <LLD I
<LLD 0 i i
Cs-134 0.0015 <LLD l i
<LLD 0- ;
l Cs-137 0.0013 (LLD --
<LLD 0 Ce-141 0.0024 <LLD - -
<LLD 0 l Ce-144 0.0054 <LLD -
i
<LLD 0 Airbomelodine I-131 520 0.07I <LLD - -
<LLD 0 (pCi/m3) l ILD (Quarterly) Camma 292 1.0 12.8 (248/24s) T-8, Farm, 18.7 (4/4) 14.1 (46/46) 0 (mR/91 days) (3.2 20.4) 2.7 mi WSW (17.6-20 4) (10.2 17.3)
' ' ~ TLD(Quarterly) Camma 4 1.0 5.3 (4/4) - None (mR/91 days) 0 (3.7-6 4) (Shield) i TLD (Annual) Camma 70 1.0 56 8 (60/60) T-8, Farm, 77.1 (1/1) 0 (mR/365 days) 63.0 (10/10) (318-846) . 2.7 mi WSW (41 5-73.5) l ' TLD (Annual) Camma 1 1.0 23.2 (1/1) - - None 0 (mR/365 days) , (Shield) 4 i 197 l
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report l
,o s
Table 4.5 Radiological Environmental Monitoring Program Summary. Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 location of Facility Ottawa, Ohio Reporting Period January - December 1996 (County, State) i Indicator Location with Highest Control Number Sample Type and locations Quarterly Mean Locations Non. Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analyses a Range c Locationd Rangec Range Results' Milk (pCi/L) 1-131 12 0.5 none - -
<LLD 0 Sr-6v 12 1.2 none - - <LLD 0 Sr-90 12 0.5 none T-24, Sandusky, 0.9 (12/12) 0.9 (12/12) 0 21.0 mi SE (0.71.1) (0.7-1.1)
CS 12 K-40 100 none T 24, Sandusky, 1420 (12/12) 1420 (12/12) 0 21.0 mise (1350-1510) (1350 1510) Cs-137 10 none - - <LLD 0 Ba-La 140 10 none - - <LLD 0 (g/L) Ca 12 0.50 none T-24, Sandusky, 0 87 (12/12) 0.87 (12/12) 0 21.0 mi SE (0.80-0_94) (0.80-0.94) (g/L) K (stable) 12 0.1 none T 24. Sandusky, 1.65 (12/12) 1.65 (12/12) 0 l 21.0 mise (136-1.74) (1.56-1.74) (pCi/g) St-90/Ca 12 0.36 none T-24, Sandusky, 1.07 (12/12) 1.07 (12/12) 0 2L0 mise (0.84 1.29) (0.84-1.29) 1 (pCl/g) Cs 137/K 12 6.40 none - - <LLD 0 l l l Ground Water CD (TR) 12 2.6 4.8 (5/8) T-7, Sand Deach, 6.8 (2/4) 4.2 (1/4) 0 l (pCi/L) (3.1-7.0) 0.9mi NW (6.5-7.0) l H-3 12 330 <LLD - - <LLD 0 Sr89 12 1.5 (LLD - - < LLD 0 Sr-90 12 06 07(1/8) T 7, Sand Beach. 0.7 (1/4) <LLD 0 0.9mi NW CS 12 Mn 54 15 <LLD - - <tLD 0 1 1 Fe-59 30 <LLD - - <LLD 0 j Co-58 15 <LLD - - <LLD 0 Co-60 15 <LLD - - <tLD 0 Zn 65 30 <LLD - - <LLD 0 Zr 95 15 <LLD - - <LLD 0 Cs-134 10 <LLD - <LLD 0 10 <LLD - - <LLD 0
. C,s;137 Ba La 140 19 <LLD - - <LLD 0 198
v Davis-Besse Nuclear Power Station 199(s Annual Radiologicci Environmental Operating Report b 1 Table 4.5 Radiological Environmental Monitoring Program Summary. Nameof Facility _Dgvis-Besse Nuclear Power Station Docket No. 50-346 locationof Facility Ottawa, Ohio Reporting Period January - December 1996 (County, State) , Indicator Location with Rghest Control Number Sample Type and Locations Quarterly Mean Locations Non. Type Number of LLDb Routine Mean (F)C Mean (F)C Mean (F)e (Units) Analysesa Rancec Locationd Rangec Range Results? Edible Meat . CS 2 (pCi/g wet) K-40 01 2.83 (1/1) T-34, Onsite Roving 2.% (1/1) 2.96 (1/1) 0 Location Cs-137 0.007 <LLD - -
<LLD 0 Sr-89 3 0.004 <LLD - -
dLD 0 Vegetables (pCi/g wet) Sr-90 3 0.002 <LLD - - <LLD 0 1-131 3 0.013 <LLD - -
<LLD 0 CS 3 l
K-40 0.50 1.04 (1/1) T 173, Firelands , 2.50 (1/1) 1.73 (2/2) 0 20.0 mi. SE (0.95-2.50) i Nb-95 0.010 (LLD - -
<LLD 0
)
Zr-95 0.010 <LLD - -
<LLD 0 Cs 137 0.008 <LLD - -
<LLD 0 1
Ce-141 0.016 <LLD - - <LLD 0 ! Ce 144 0.063 <LLD - -
<LLD 0 Broad Leaf Sr89 12 0.014 <LLD - -
<LLD 0 Vegetation (pCi/g wet) Sr-90 12 0.004 0.006 (3/8) T 37, Farm, 0.010 (2/4) 0.010 (2/4) 0 (0.005-0 008) 13 0 mi. SW (0.008-0.011) (0.003-0.011) 1-131 12 0.026 <LLD - -
< LL.D 0 GS 12 - "*
K-40 0.1 2,54 (8/8) T 19, Hemminger 3.19 (4/4) 2.61 (4/4) 0 (L74-4 69) Farm,0.68 mi. W (1.77-4.69) (2.53-2.73) Nb-95 0.021 (LLD - - <LLD 0 Zr-95 0.038 <LLD - - <LLD 0 Cs-137 0.024 <LLD - - <LLD 0 Ce-141 0.026 <LLD - -
<LLD 0 Ce-144 0.17 <LLD - - (LLD 0 199
Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report ,, 4 Table 45 Radiological Environmenta.1 Monitoring Program Sunenary. Nameof Facility Davis-Besse Nuclear Power Station Dock.et No. 50-346 location of Facility Ottawa, Ohio Reporting Period January - December 1996 (County, State) Indicator Location with Highest Control Number Sample Type and Locations Quarterly Mean Locations Non. T Number of LLDb Mean (F)C Routine Mean (F)C Mean (F)c j (Un ts) Analyses a Rangec locationd Raneec Range Results'
]
Animal CS 5 Wildlife Feed (pCi/g wet) Be-7 0.33 0.40 (1/4) T-31, Onsite 0.40 (1/1) <LLD 0 l Roving location K-40 0.1 5.45(4/4) T-197, Farm 7.04 (1/1) 6.75 (1/1) 0 (4.00-7.04) 1.7 mi. W ' Nb-95 0.034 <LLD - - <.LLD 0 Zr 95 0.033 (LLD - -
<tLD 0 Ru-103 0.024 <LLD - -
<LLD 0 Ru-106 0.21 <LLD - -
<LLD 0 Cs-137 0.022 <LLD - -
<LLD 0 Ce-141 , 0.061 <LLD - -
<LLD 0 l Ce-144 0.19 <LLD - -
<LLD 0 ;
I Soil CS 10 (pCl/g dry) i De-7 0.81 <LLD <LLD 0 i K-40 1.0 20.21 (6/6) T-27, Crane Creek , 33.62 (1/1) 2525(4/4) 0 (12.85-32.51) 5.3 mi WNW (20.31 33.62) Nb-95 O a70 <LLD - -
<LLD 0 Zr-95 l . ~3 <LLD - -
<LLD 0 Ru-103 0.075 <LLD - -
<LLD 0 1
Ru-106 0.59 <LLD - -
<LLD 0 j i
Cs.137 0 034 0.21 (5/6) T-2, Site Boundary, 0 52 (1/1) 0 34 (3/4) 0 ! (0.082-0.52) 0.9 mi. E (0.23-0.41) Ce-141 0.14 <LLD - -
<LLD 0 i e
l Ce 144 0.47 <LLD - - cl.LD 0 Treated GB (TR) 48 1.0 2.1 (24/24) T 11, Port Clinton, 2.4 (12/12) 2.1 (24/24) 0 Surface Water (1.5 2.6) 93 mi. SE (2.2 2.8) (1.5 2.8) (pCi/L) H-3 16 330 <LLD T-11, Port Clinton, 383 (1/I) 383 (1/1) 0 93 mi. SE Sr-89 16 1.6 <LLD - -
<LLD 0 Sr* 90_ 16 06 0.7 (1/8) T 12. Toledo Water 0.8 (1/4) 0.8 (1/4) 0 Treatment Plant, 11.3 mi WNW ,
200
I p Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report 4 l i
- \
Table 4.5 Radiological Environmental Monitoring Program Summary. Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 location of Facility Ottawa, Ohio Reporting Period January - December 1996 (County, State) Indicator Location with Highest Sample Type and Control Number locations & irterly Mean Type Locations Non-Nurnber of LLDb Mean (F)C Mean (F)C Routine (Units) Analyses' Mean (F)c Rangec Locata Rangec Range
, Results' CS 16 !
Treated Surface Water (pCi/L) hvnlinued) Mn 54 15 <LLD -
<LLD 0 Fe-59 30 <LLD - -
(LLD 0 l Co-58 15 <LLD - 1
<LLD 0 Co-60 15 <LLD - -
<LLD 0 Zn-65 30 <LLD - -
<LLD 0 Zr-95 15 (LLD - -
<LLD 0 Cs 134 !
10 <tLD - -
<LLD 0 Cs-137 10 <LLD - -
<LLD 0 i
Ba-La-140 15 (LLD '
<LLD 0 l
Untreated GB (TR) 111 1.0 2.9 (59/59) T 152, Surface Water 4.7 (7/7) 2.8 (52/52) 0 I (1.9-6.7) Canal Entrance to (2.7-6.7) (1.4-7.4) (pCi/L) Maumee Bay S.P. 15.6 mi. WNW H-3 til 00 405 (6/59) T 137, take Erie. 539 (1/12) 589 (1/52) 0 ! (348-562) 7.0 mi WNW ! Sr 89 20 2.5 <tLD - -
<LLD 0 4 90 20 09 (LLD - -
<LLD 0 CS 111 Mn.54 15 <LLD -
<LLD 0 Fe-59 30 <LLD . - -
<LLD 0 Co 58 15 <LLD 1
<LLD 0 l Co-60 15 <LLD - .
<LLD 0 Zn-65 30 <LLD -
<LLD 0 Zr-95 15 <LLD - -
<tLD 0 1
Cs 134 10 <tLD - -
<LLD 0 Cs-137 10 <LLD - -
<LLD 0 Ba-La-140 15 <LLD -
<LLD 0 201
1 Davis-Besse Nuclear Power Station 1996 Annual Radiological Environmental Operating Report 9 g i Table 4.5 Radiological Environmental Monitoring Program Summary. Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 location of Facihty Ottawa, Ohio Reporting Period January - December 1996 (County, State) indicator Location with Eghest Control Number Sample Type and locations Quarterly Mean Locations Non- ; 3 Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c Routine ] (Units) Analysesa Range c locationd Range e Range Results' Fish CD 6 0.1 2.94 (3/3) T-35, Lake Erie, 3.09 (3/3) 3.09 (3/3) 0 1 (pCi/g wet) (2.59-3.26) > 10 mi. radius (2.91-3.28) (2.91-3.28) l CS 6 K-40 0.1 2.83 (3/3) T-33, Lake Erie, 2.83 (3/3) 2.77 (3/3) 0 (2.61 3.02) 1.5 ml. NE (2.61-3.02) (2.58-3.05) Mn-54 0.013 <LLD - - <LLD 0 Fe-59 0.027 <LLD - - <LLD 0 Co-58 0.016 <LLD - - <LLD 0 ; 1 Co40 0.016 <LLD - - <LLD 0 Zn 65 0.030 <LLD - - <LLD 0 q l Cs.131 0.015 <LLD - - (LLD 0 C*- t r 0 021 <LLD - - <LLD 0 Shorehne G 10 Sediments 0 (pCi/g dry) K 40 01 17.96 (8/8) T-4 Site Boundary, 22.20 (2/2) 12.41 (2/2) (12.45-23.48) 0.8 mi. S (22.05-22.34) (11.49-13.33)
<LLD 0 Mn-58 0 038 (LLD - -
C"'5" - *
<LLD 0 0(48 <LLD Co m O M4 <LLD - - <LLD 0 C %.11 u tr/4 <LLD - - <LLD 0 T-4P, Site <LLD 0 C 1r 0025 0.10 (2/2) 0.17 (1/1)
(0.033-0.17) Doundary, 0.8 mi. S
- CB = grow teta GS . pmma w an. TR = total residue.
b LLD = normnal hower hmit of drention based on 4.66 sigma counting error for background sample. c Mean bawd upi n d 1ntable measurements only. Fraction of detectable measurements at specified locations is indicated in parenthews (F) d locatusns are spentmd tiv staine mde (Table 4.1) and distance (miles) and direction relative to reactor site.
' Non routme resuhw are itsw which exceed ten times the control station value.
I One result ( 012 pCumb 54atam T 1 for the week ending August 20,1996) exceeded the required LLD. The LLD was not reactwd due to low uilunw 202}}