ML20217M538
| ML20217M538 | |
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| Site: | Davis Besse  |
| Issue date: | 12/31/1997 |
| From: | CENTERIOR ENERGY |
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| NUDOCS 9805050036 | |
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{{#Wiki_filter:l l a l ANNUAL RADIOLOGICAL- 1 ENVIRONMENTAL OPERATING REPORT for l Davis-Besse Nuclear Power Station l January 1,1997 through December 31,1997 Prepared by: Radiation Protection Section Davis-Besse Nuclear Power Station Toledo Edison Company Toledo, Ohio April 1998 1 ADO 46' , R PDR l J
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Repon TABLE OF CONTENTS Title P_ age List of Tables iv List of Figures vi Executive Summary viii INTRODUCTION Fundamentals 1 Radiation and Radioactivity 2 Interaction with Matter 3 Quantities and Units of Measurement 5 Sources ofRadiation 7 Health Effects ofRadiation 9 Health Risks 10 Benefits ofNuclear Power 11 i Nuclear Power Production 11 Station Systems 16 Reactor Safety and Summary 19 Radioactive Waste 19: Description of the Davis-Besse Site 22
~ References 24 RADIOLOGICAL ENVIRON' DENTAL 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
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l Davis-Besse Nuclear Power Stction 1997 Annual Radiological Environmental Operating Report Title RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) { 1997 Program Deviations l 38 Atmospheric Monitoring 39 Terrestrial Monitoring 45 Aquatic Monitoring 57 l Direct Radiation Monitoring 68 Conclusion { 79 References 80 RADIOACTIVE LFFLUENT RELEASE REPORT Protection Standards 83 ! Sources ofRadioactivity Released 83 Processing and Monitoring 84 t Exposure Pathways 85 i Dose Assessment 86 Results ] 87 ) Regulatory Limits 88 EfIluent Concentration Limits 89 . Average Energy 89 Measurements ofTotal Activity 89
' Batch Releases
_90 Sources ofInput Data ~ 91 Doses to Public Due to Activities Inside the Site Boundarf 91 Inoperable Radioactive Effluent Monitoring Equipment 92 Changes to The ODCM and PCP 92 i LAND USE CENSUS Program Design 110 Methodology 110 Results 111 s t ii
y- Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Title Page NON-RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring 116 4 Land and Wetlands Management 142 Water Treatment 144 Chemical Waste Management 149 Waste Minimization and Recycling 153
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APPENDICES Appendix A: Interlaboratory Comparison Program Results 154 Appendix B: Data Reporting Conventions 189 Appendix C: Effluent Concentration Limit of Radioactivity in Air and Water 192 Above Natural Background in Unrestricted Areas Appendix D: REMP Sampling Summary 194 iii
l Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report List of Tables Table Page Title Number Number
' Risk Factors: Estimated Decrease in Average Life Expectancy 1 10 Sample Codes and Collection Frequencies 2 30 Sample Collection Summary 3 31 Radiochemical Analyses Performed on REMP Samples 4 33 Air Monitoring Locations 5 41 Milk Monitoring Location 6 46 Groundwater Monitoring Locations 7 48 Broad Leaf Vegetation and Fruit Locations 8 49 Animal /Wddlife Feed Locations 9 50 Wild'and Domestic Meat Locations 10 51 Soil Locations 11 53 Treated Surface Water Locations 12 58
' Untreated Surface Water Locations 13 61 Shoreline and Bottom Sediment Locations 14 62 Fish Locations 15 64 Thermoluminescent Dosimeter Locations 16 70 Gaseous Effluents - Summation of All Releases 17 93 Gaseous Effluents - Ground Level Releases - Batch Mode 18 94 i Gaseous Effluents - Ground Level Releases - Continuous Mode 18 95 Gaseous Effluents - Mixed Mode Releases - Batch Mode 19 97 Gaseous Effluents - Mixed Mode Releases - Continuous Mode 19 98 Liquid Effluents - Summation of All Releases 20 100 Liquid Effluents - Nuclides Released - Batch Releases 21 101 Liquid Effluents - Nuclides Released - Continuous Releases 21 103 Solid Waste and Irradiated Fuel Shipments 22 105 Doses Due to Gaseous Releases for January through December 1997 23 107 Doses Due to Liquid Releases for January through December 1997 24 108 Annual Dose to The Most Exposed Member of The Public 25 109 Closest Exposure Pathways Present in 1997 26 113 Pathway Locations and Corresponfing Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters 27 115 7 iv
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table Page ,.y Title Number Number Summary of Meteorological Data Recovery for 1997 28 122 Summary of Meteorological Data Measured for 1997 ?" 123 Joint Frequency Distribution by Stability Class 30 137
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' Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report List of Figures Figure Page Description Number Number The Atom 1 .1 Principal Decay Scheme of the Uranium Series 2 3 Range and Shielding ofRadiation 3 4 Sources ofExposure to the Public 4 8 Fission Diagram 5 12 Fuel Rod, Fuel Assembly, Reactor Vessel 6 13 Schematics ofDBNPS 7 15 Dry Fuel Storage Module Arrangement 8 21 Map ofArea Surrounding Davis-Besse 9 22 Airborne Particulate: Gross Beta 10 40
. Airborne Sampling Locations on Davis-Besse Site 11 42 Airborne Sampling Locations within a Five Mile Radius 12 43 Airborne Sampling Locations within a Twenty-Five Mile Radius 13 44 Groundwater Samples: Gross Beta 14 47 Soil Samples: Cesium-137 15 52 Terrestrial Sampling Locations on Davis-Besse Site 16. 54 , Terrestrial Sampling Locations within a Five Mile Radius 17 55 Terrestrial Sampling Locations within a Twenty-Five Mile Radius 18 56 Treated Surface Water Samples: Gross Beta 19 58 Untreated Surface Water Samples: Gross Beta 20 60 Fish Samples: Gross Beta 21 63 Aquatic Sampling Locations on Davis-Besse Site 22 65 Aquatic Sampling Locations within a Five Mile Radius 23 66 Aquatic Sampling Locations within a Twenty-Five Mile Radius 24 67 TLD Dose Comparison 1973 - 1997 25 69 Comparison ofNRC and Davis-Besse TLDs 26 70 Direct Radiation Sampling Locations on Davis-Besse Site 27 76 Direct Radiation Sampling Locations within a Five Mile Radius 28 77 Direct Radiation Sampling Locations within a Twenty-Five Mile Radius 29 78 Exposure Pathways e 30 86 , Y
1 i Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l l Figure Page I Description Number Number i Land Use Census Map 31 112 Wind Rose Annual Average 100M 32 125 Wind Rose Annual Average 75M 33 126 I 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 I Water Treatment Plant Schematic 38 145 l l Y
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Emironmental Operating Repon Executive Summary The Annual Radiological Environmental Operating Report (AREOR) is a detailed report on the Environmental Monitoring Programs conducted at the Davis-Besse Nuclear Power Station from January 1 through December 31,1997. This report meets all of the requirements in Regulatory Guide 4.8, Davis-Besse Technical Specifications 6.9.1.10, and Davis-Besse Offsite Dose Calculation Manual (ODCM) Section 7.1. Reports included are the Radiological Environmental Monitoring Program, Land Use Census, and the Non-Radiological Environmental Programs, which consist of Meteorological Monitoring, Land and Wetland Management, Water Treatment, Chemical Waste Management, and Waste Minimization and Recycling. This report also includes the Radiological Effluent Release Report for the reporting period of January 1 through December 31,1997. Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is established to monitor the radiological condition of the environment around Davis-Besse. The REMP is conducted in accordance 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 ant . valuating 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 radiation and radioactivity normally present in the area as natural background. Davis-Besse has continued to monitor the environment by sampling air, groundwater, milk, edible meat, fruit and vegetables, animal feed, soil, drinking water, surface water, fish, shoreline sediment, and by measuring radiation directly. Samples are collected from indicator and control locations. Indicator locations are within approximately 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 locations are farther away from the Station and are expected to indicate the presence of only naturally occurring radioactivity. The results obtained from the samples collected from indicator locations are compared with the results from those collected from control locations and with the concentrations present in the environment before Davis-Besse became operational. This allows for the assessment of any impact the operation of Davis-Besse might have had on the surrounding environment. Over 1700 radiological environmental samples were collected and analyzed in 1997. 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 aHve background radiation or radioactivity is attributed to the operation of Davis-Besse, viii _ __ A
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report The sampling results are divided into four sections: atmospheric monitoring, terrestrial monitoring, aquatic monitoring and direct radiation monitoring.
- Air is continuously being filtered at 10 locations and the filters are collected to monitor the atmosphere. The 1997 results are similar to those observed in preoperational and previous operational programs. Only background and fallout radioactivity normally present in the environment was detected and only at concentrations normal to the area.
. Terrestrial monitoring includes analysis of milk, ground water, meat, fmits, vegetables, animal feed and soil samples. The results of the analyses of the terrestrial samples indicate concentrations of radioactivity similar to previous years and indicates no build-up of radiation due to the operation of Davis-Besse.
- Aquatic monitoring includes the collection and analysis of drinking water, untreated surface water, fish and shoreline sediments. The 1997 results of analysis for fish, untreated surface water, drinking water and shoreline sediment indicate normal background concentration of radionuclides and show no increase or build-up of radioactivity due to the operation of Davis-Besse.-
- Direct radiation averaged 13.512.7 mrem /91 days at indicator locations and 14.1 il.4 mrem /91 days at controllocations. This is similar to results of previous years.
- The operation of Davis-Besse in 1997 cac ;d no significant increase in the concentrations of radionuclides in the environment and no adverse effect on the quality of the environment.
Radioactivity 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 1997 was well below all applicable regulatory limits.
In order to estimate radiation dose to the public, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the REMP. During the census, Davis-Besse personnel travel every public l road within a five mile radius of the Station to locate the radiological exposure pathways (e.g., l residences, vegetable gardens, milk cows / goats, etc.). The one pathway of particular interest is ! the pathway that, for a specific radionuclide, provides the greatest dose to a sector of the population, and is called the critical pathway. The critical pathway for 1997 is a garden in the West sector,1640 meters from Davis-Besse. I i ix
=t Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Radiological Efiluent Release Report The Radiological Efiluent Release Report (RERR) is a detailed lieting of radioactivity released from the Davis-Besse Nuclear Power Station during the period, January 1,1997 through Decem-ber 31, .1997. The doses due to radioactivity released during this period were estimated to be: Liquid Effluents: Maximum Individual Whole Body Dose 5.00E-02 mrem (0.0500 mrem) Maximum Individual Significant Organ Dose 5.03E-02 mrem (0.0503 mrem)
- TotalIntegrated Population Dose 4.59E-01 person- rem (0.459 person-rem)
Average Dose to the Individual .2.1lE-04 mrem
-(0.000211 mrem)
Gaseous Emuents: Maximum Individual Whole Body Dose due to 8.31E-03 mrem I-131, H-3 and Particulates with half-lives (0.00831 mrem) ' greater than 8 days Maximum Significant Organ dose due to. I-131, 1.54E-02 mrem H-3 and Particulates with half-lives greater than . (0.0154 mrem) 8 days TotalIntegrated Population dose due to I-131, . 5.75d-03 person-rem H-3 and Particulates with half-lives greater than (0.00575 person-rem) 8 days - Average dose to an Individual in the population- 2.64E-06 mrem due to I-131, H-3 and Particulates with half-lives
- (0.00000264 mrem)
; greater than 8 days
- Maximum Individual Skin dose due to noble gases 2.36E-04 mrad (0.000236 mrad)
Maximum Individual Whole Body Dose due to 2.04E-04 mrad noble gases ~ (0.000204 mrad) Total Integrated Population dose due to noble gases 6.42E-05 person-rem (0.0000642 person-rem)
- Average dose to individualin population due to 2.95E-08 mrem noble gases (0.0000000295 mrem) 7 x
Davis-Besse Nuclear Power Station 1997 Anat i J.adiological Environmental Operating Report These doses represent an extremely small fraction of the limits set by the NRC or the limits set in the ODCM. l There was one abnormal gaseous release during this reporting period. ! There were no changes to the Process Control Program (PCP) during this reporting period. There was one change to the Offsite Dose Calculation Manual during this ; reporting period. Non-Radiological Environmental Programs - l l 4 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 Requirement was 97.7%.
+ Marsh Management Toledo Edison and the Cleveland Electric Illuminating Company co-own the Navarre Marsh which they lease to the U.S.-Fish and Wildlife Service,~who manage it as part of the Ottawa .
National Wildlife Refuge. - Davis-Besse personnel are responsible for inspecting the marsh and reporting on its status monthly. Special projects conducted in 1996 with the cooperation of Ohio Department of- Natural Resources included Canada goose banding, a Volunteer Eagle Watch Workshop, International Migratory Bird Day and a-Waterfowl Identification Seminar. During 1995,~ 10 acres of land outside the marsh has been planted with prairie grass and wild flowers. This will provide habitat for upland animals, improve water quality, and reduce soil crosion. Also, Davis-Besse pledge partnership 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 produce any young. i Water Treatment I Davis-Besse uses Lake Eric as a source of water for its Water Treatment Plant. The water is !
. treated onsite to provide domestic water and to produce high purity water for use in the Station's cooling systems.
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Davis-Besse Nuclear Power Statirn 1997 Annual Radiological Emironmental 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 Eric.
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 Eric.
+ Chemical Waste Management The Chemical Waste Management Program at Davis-Besse was developed to ensure that the offsite disposal of non-radioactive hazardous and nonhazardous chemical wastes is performed in accordance with all applicable state and federal regulations. Chemical waste disposal vendors contracted by Davis-Besse use advanced technology for offsite disposal of chemical wastes in order to protect human health and the environment.
In 1997, the Davis-Besse Nuclear Power Station maintained small quantity generator status, generating 5,150 pounds of hazardous waste. Davis-Besse personnel also continuously strive to identify alternate ways to reduce hazardous waste generation.There were 27,000 gallons of non-hazardous waste oil generated in 1997. Approximately 1,430 gallons of oil filters and solid oily debris were also generated. Additionally 45,300 gallons of water containing small amounts of diesel fuel oil from an on-site fuel oil leak and Main Transformer outage activities were generated in 1997. As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse reported hazardous products and chemicals to local fire departments and local and state planning comrnsions. As part o.f the program to remove PCB fluid from Davis-Besse, all electrical transformers have been retrofilled and reclassified as non-PCB transformers.
+ Waste Minimization and Recycling The Waste Minimization and Recycling Program at Davis-Besse began in 1991 with the collection and recycling of paper. This program was expanded and reinforced during 1993 to include the recycling of paper, aluminum cans, cardboard, and metal. Paper and cardboard recycling typically exceeds 50 tons annually. The scrap metal collected onsite was sold to scrap companies.
Appendices Appendix A contains results from the Interlaboratory Comparison Program required by Davis-Besse Technical Specifications. Samples with known concentrations of radioisotopes are prepared by the Environmental Protection Agency (EPA), and then sent (with information on sample type and date of collection only) to the laboratory contracted by the Davis-Besse to analyze its REMP samples. The results are then checked by the EPA to ensure consistency with the known values. The results from both the contracted laboratory and the EPA are provided in Appendix A. xii
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report
' Appendix B contains data reporting conversions used in the REMP at Davis-Besse. The
. appendix 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 deviations is also provided. Appendix C lists the effluent concentration limits for alpha and beta emitting radioisotopes and for certain other radioisotopes in air and water samples. These concentrations are taken directly from the Code of Federal Regulations Title 10, Part 20, and provide comparison values for actual REMP sampling results for 1997. Appendix D provides a REMP sampling summary from 1997. . The appendix provides a listing of the following for each sample type: e the number and types of analyses performed, e the lower limit of detection for each analysis, e the mean and range of results for control and indicator locations, e the mean, range, and location description for the location with the highest annual mean, e the number of non-routine results. For detailed studies, Appendix D provides more specific information than that listed in Chapter 2 of this report. The information presented in Appendices A through D was provided by Teledyne Isotopes Midwest Laboratories in their Final Progress Report to Toledo Edison (February 1998). l i xiii
1 Davis-Isesse Nuc.. tr Power Station 1997 Annual Radiological Environmental Operating Report Introduction- 1 Coal, oil, natural gas and hydropower are used to run this nation's electric generating stations; however, each method has its drawbacks. Coal-fired power can affect the environment through j 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- I tics, risk assessment, reactor operation and effluent control is provided in this section. 1 Fundamentals The Atom All matter consist of atoms. Simply de-scribed, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called pr _ protons, electrons, and neutrons, respec- .. ; tively (Figure 1). The relatively large pro- e ==g i tons and neutrons are packed tightly to- I 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
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charges of the electrons are balanced by the j [ kt , .um positive charges of the protons. Due to their dissimilar charges, the protons and electrons GE have a strong attraction for each other, % u ., won.,y,. which helps hold the atom together. Other attractive forces between the protons and g=gsg g gr
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- iy m =c.n.s. w -,,w. w w.ew neutrons keep the densely packed protons *- zxm e- w r e. . a . i from repelling each other, preventing the nu- '
cleus from breaking apart. - i 1 l
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Radiation and Radioactivity Isotopes and Radionuclides A group ofidentical atoms, containing the same number of protons, make up an element. In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms - with one proton are hydrogen atoms and all atoms with eight protons are oxygen atoms. How-ever, the number of neutrons in the nucleus of an element may vary. Atoms with the same num-ber of protons, but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties and many are stable or nonradioactive. An un-stable or radioactive isotope of an element is called a radioisotope, radioactive atom, or radio-nuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess-energy is usually due to a surplus or deficit in the number of neutrons in the nucleus. Radionu--
. clides can be naturally occurring such as uranium-238, beryllium-7 and potassium-40, or man-
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I made, such as iodine-131, cesium-137, and cobalt-60.
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' Radiation l
Radiation is simply the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. ' Ionizing radiation is another type of radiation and has similar properties to those of the examples listed above. Ion-izing radiation consists of both electromagnetic radiation and particulate radiation. Electro- l magnetic radiation is energy with no measurable mass' that travels with a wave-like motion { through space. Included in this category are gamma rays and X-rays. Particulate radiation con- ; sists of tiny, fast moving particles which,- if unhindered, travel in a straight line through space. The three types of particulate radiation of concern to us are alpha particles, made up of 2 pro-tons and 2 neutrons; beta particles, which are essentially free electrons'(electrons not attached to an atom); and neutrons. The properties of these types of radiation will be described more fully in the Range and Shielding section. : Radioactive Decay
; Radioactive atoms attempt to reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release'of energy from an atom through the emission J
ofionizing radiation. Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daughter products which eventually result in a stable atom. The loss of energy and/or matter through radioactive decay may transform the atom into a chemically different element. For example, when uranium-238 decays, it emits an alpha particle and, as a result, the atom loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom determines its chemical
' identity. Therefore, when the uranium-238 atom loses the 2 protons and 2 neutrons, it is trans-formed into an atom of thoriuni-234. Thorium-234 is one of the 14 successive daughter products .' uranium-238. Radon is another daughter product, and the series ends with stable lead-206.
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Davis.Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report ' This example is part of a known radioactive decay series, called the uranium series, which begins with uranium-238 and ends with lead-206 (Figure 2). 1
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Half-life Most radionuclides vary greatly in the frequency with which their atoms release radiation. Some radioactive materials, in which there are only infrequent emissions, tend to have a very long half-lives. Those radioactive materials that are very active, emitting radiation more frequently, tend to have comparably short half-lives. The length of time an atom remains radioactive is defmed in terms of half-lives. Half-life is the amount of time required for a radioactive substance to lose halfits activity through the process of radioactive decay. Half-lives vary from millionths of a sec-ond to millions ofyears. Interaction with Matter Ionization Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When these forms of radiation interact with any form of material, the energy they impart may cause atoms in that material to become ions, or charged particles. Normally, an atom has the same number of , protons as electrons. Thus, the number of positive and negative charges cancel, and the atom is electrically neutral. When one or more electrons are removed an ion is formed. Ionization is one of the processes which may result in damage to biological systems.
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Davis.Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Range and Shielding Particulate and electromagnetic radiation each travel through matter differently because of their different properties. Alpha particles contain 2 prcions and 2 neutrons, are relatively large, and carry an electrical charge of +2. Alpha partkies 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 ofits energy through collisions and other interactions with atoms. As a result, alpha particles can easily be stopped by a sheet ofpaper or a few centimeters of air (Figure 3). Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed oflight (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 alpha particles, so they can travel farther. Beta particles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood.
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ATE PAPER ALUftNUM LEAD CONCRETE. 1 Figure 3: As radiation travels, is collides and interacts with other atoms and loses energy. Alpha particles can be j stopped by a sheet of paper. and beta particles by a thin sheet of aluminum. Gamma radiation is shielded by highly ; dense snaterials such as lead. while hydrogenous materials Ghose containing hydrogen atoms), such as wa.cer and concrete. are used to stop neutrons. j l Gamma rays are pure energy and travel at the speed oflight. They have no measurable charge or ! mass, and generally travel much farther than alpha or beta particles before being absorbed. After j repeated interactions, the gamma ray finally loses all ofits energy and vanishes. The range of a j gamma ray in air varies, depending on the ray's energy and interactions. Very high energy gamma j 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 ofits density. : Several inches oflead or concrete may be needed to effectively shield gamma rays. I 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, s neutrons are not of environmental concern since the neutron source at nuclear power stations is sealed within the containment building. i 4 L
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report 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 called a thermal neu-j
- tron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons.
Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron I shielding materials commonly used to slow neutrons down are water or polyethylene. The shield is then completed with a material such as cadmium, to absorb the now thermal neutrons. At Davis-Besse, concrete is used to form an effective neutron shield because it contains water mole-cules and can be easily molded around odd shapes. Quantities and Units of Measurement There are several quantities and units of measurement used to describe radioactivity and its ef-fects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent. I 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 requirsd to produce one curie varies. For example, one gram (1/28 th of an ounce) of radium-226 is the equivalent of one curie of activity, but it.would take 9,170,000 grams (about 10 tons) of thorium-232 to equal one curie. Smaller units of the curie are often used, especially when discussing the low concentrations of ra-dioactivity detected in enviromnental samples. For instance, the microcurie (uCi) is equel to one millionth of a curie, while the picocurie (pCi) represents one trillionth of a curie. Absorbed Dose: Rad Absorbed dose is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation. The 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 (1 Rad = 100 erg /gm). The rate of absorbed dose is usually given in Rad /hr.
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report If the biological effect ofradiation was directly proportional to the energy deposited by radiation j in an organism, the Rad would be a suitable measurement of the biological effect. However, bio- ' l logical effects depend not only on the total energy deposited per gram of tissue, but on how this l energy is distributed along its path. Experiments have shown that some types of radiation are j more damaging per unit path of travel than others. Thus, another unit is needed to quantify the j biological damage caused by ionizing radiation. Dose Equivalent: Rem
' Biological damage due to alpha, beta, gamma and neutron radiation may result from the ionization -
caused by these radiation's. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or X-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types ofionizing 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 ofionizing radiation. The dose equivalent is measured in rem (radiation equivalent man). An example of this conversion from absorbed' dose to dose equivalent uses the quality factor for I alpha radiation, which is 20. Thus,1 Rad of alpha radiation is approximately equal to 20 rem. ! Beta and gamma radiation each have a quality factor of 1, therefore one Rad of either beta or gamma radiation is approximately equal to one rem. Neutrons have a quality factor ranging from 2 to 10. One rem produces the same amount of biological damage, regardless of the source. In terms of radiation, the rem is a relatively large unit.' Therefore, a smaller unit, the millirem, is-often used. One millirem (mrem) is equal to 1/1000 of a rem. ' Deep Dose Equivalent (DDE) l Deep dose equivalent is the measurement of dose within the body, from sources of radiatiod that are external to the body. It is what is measured and recorded Thermoluminescent dosimeters L (TLDs), film badges, or other dosimeters. For example, at Davis-Besse or at any hospital that has x-ray equipment, you will see people wearing these devices. These instruments are worn to measure deep dose equivalent (DDE). Committed Effective Dose Equivalent (CEDE) , Committed effective dose equivalent is a measure of the dose received from any radioactive mate-rial taken into the body. It is calculated from the sum of the products of the committed dose equivalent to the organ or tissue multiplied by' the organ or tissue weighting factor. _ CEDE ac-counts for all of the dose delivered during the entire time the radioactive material is in the body.
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report
. Total Effective Dose Equivalent (TEDE)
Total effective dose equivalent means the sum of the deep dose equivalent (for dose from sources external to the body) and the committed effective dose equivalent (for internal dose). As these are both doses to the body, they are not tracked separately. The NRC 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 back-ground radiation to which everyone is exposed.
The earth is constantly showered by a steady stream of high energy. gamma rays and particulate. radiation that come from space, known as cosmic radiation. The atmosphere shields us from most of this radiation, but everyone still receives about 20 to 50 mrem each year from this source. The thinner air at higher altitudes provides less protection against cosmic radiation. ~ So people living at higher altitudes or flying in an airplane are exposed to more cosmic radiation. Radionuclides commonly found in the atmosphere -as a result 'of cosmic ray interactions include beryllium-7, carbon-14, tritium (H-3), and sodium-22. : Another common, naturally occurring radionuclide is potassium-40. About one-third of the ex-ternal and internal dose from naturally occurring background radiation is attributed to this rJidio-activeisotope ofpotassium. The major source of background radiation is radon, a colorless, odorless, radioactive gas that re-suits from the decay of radium-226, a member of the uranium-238 decay series. Since uranium occurs naturally in all soils and rocks, everyone is continuously exposed to radon and its daughter products. Radon would not be considered to pose a health hazard unless it is concentrated in a confmed area, such as buildings, basements or underground mines. Radon-related health concerns stem from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it 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 com-mon in uranium mines. According to the National Council on Radiation Protection and Meas-urement (NCRP), over half of the radiation dose the average American receives is attributed to radon.
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Reprt SOURCES OF EXPOSURE l TO THE PUBLIC
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occurring radon. A very small annual dose to the public results from producing electricity by nuclear power. Further information on radon, its measurement, and actions to reduce the radon concentration in buildings can be obtained by contacting the state radon program oflice at the following address: 1 Radiological Health Program Ohio Department ofHealth P.O. Box 118 l Columbus, Ohio 43266-0118 (614) 481-5800 (800) 523-4-439 (in Ohio Only) l The approximate average background radiation in this area (see Figure 4)is 300 mrem / year. , Man-Made Radiation In addition to naturally occurring cosmic radiation and radiation from naturally occurring radioac-tivity, people are also exposed to man-made radiation. The largest sources of exposure include medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium-90, cesium-137, and tritium. Less than one percent of the annual dose a member of the public re-ceives is a result of having electricity generated by nuclear power. 1 1 1 /
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l l l Davis-Besse Nuclear Power Station 1997 Annual Radi: logical Environmental Operating Report J Health Effects of Radiation 1 The effects ofionizing radiation on human health have been under study for more than 80 years. I Scientists have obtained valuable knowledge through the study oflaboratory animals that were exposed to radiation under extremely controlled conditions. However, it has been difficult to re- : late the biological effects ofirradiated laboratory animals to the potential health effects on hu- I 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 I 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 1 our knowledge' of the health effects from comparatively very large doses of radiation received overlong periods of time. Continuous exposure to low levels of radiation may produce somatic changes over an extended , period of time. For example, someone may develop cancer from man-made radiation, background radiation, or some other source not related to radiation. Because all illnesses caused by low level , radiation can also be caused by other factors, it is virtually impossible to determine indisdual health. effects oflow level radiation. Even though no effects have been observed at doses less than 50 rem, to be conservative, we assume the health effects resulting from low doses of radia-tion occur proportionally to those observed following large doses of radiation. Most radiation scientists agree that this assumption over-estimates the risks associated with a low level radiation exposure. The effects predicted in this manner have never been actually observed in any individu-als exposed to low level radiation. Therefore, the most likely somatic effect oflow level radiation is believed to be a smallincreased risk of cancer. Genetic effects could occur as a result ofionizing radiation interacting with the genes in th? hu-man cells. Radiation (as well as common chemicals) can cause physical changes or mutatic'.s in the genes. Chromosome fibers can break and rearrange, causing interference with the norral 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 translocatio'ns, inversions, rings, and other types of stmetural rearrangements. When this s 9 9
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Reprt 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 ob-served. 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. l l Health Risks While people may accept the risks inherent in their personal activities, such as smoking and driv-ing to work ~each day, they are less inclined to' accept the risk inherent in producing electricity. As
' with any industrial environment, it is not possible to guarantee a risk free environment. Thus, at-tention should be focused on taking steps to safeguard the public, on developing a realistic as- i sessment of the risks, and on placing these risks in perspective. The perceptions of risk associated I with exposure to radiation has, perhaps, the greatest misunderstanding. Because people may not j L understand ionizing radiation and its associated risks, they may fear it. This fear is compounded by the fact that we cannot hear, smell, taste or feel ionizing radiation. ' However, we do not fear other potentially hazardous things for which we have the same lack of sensory perception, such as radio waves, carbon monoxide, and small concentrations of numerous cancer causing substances. These risks are larger and measurable compared to those presumed to be associated with exposure to low level, low dose radiation. Most of these risks are with us throughout ou lives, and can be added up over a lifetime to obtain a total effect. Table I shows a ,
number of different factors that decrease the average life expectancy ofindividuals in the United ! States. 1 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 l Heart diseases : 5.8 years Cancer : 2.7 years I City Living (not rural) : 5.0 years
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' Divis-Bes'se Nuclear Power Station 1997_ Annual Radiological Envir::nmental Operating Report .
- Benefits ofNuclear Power' Nuclear power plays an'important part in meeting today's electricity needs, and will continue to :
- serve'as an'important source of electric' energy well into the future. Today more than twenty . percent of the electricity produced in the United States is from nuclear. powered electrical gener- ;
ating stations. , Nuclear power offers several advantages over alternative sources of electric energy: I e' nuclear power has an excellent safety record dating back_to 1957 when the first '- commercial nuclar power station began operating, e uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States,-
- nuclear power is the cleanest energy source for power stations that use steam to produce electricity. There are no " greenhouse" gases or acid gases produced when using nuclear fuel.
The following sections provide information on the fundamentals of how Davis-Besse uses nuclear fuel and the fission process to produce' electricity. Nuclear Power Production Electricity is produced in a nuclear power station in the same way as in a fossil-fueled station with the . exception of the source of heat. Heat changes water to steam that turns a turbine. In a fossil-
' fueled station, th'e fuel is burned in a furnace, which is also a boiler. Inside the boiler, water is turned into steam. In a nuclear station,'the furnace is replaced by a reactor containing a core of .. nuclear fuel, primarily uranium. Heat is produced when the atoms of uranium are split, or fis-sioned, inside the reactor.
What is Fission? A special force called the binding force holds the protons and neutrons together in the nucleus of ' the atom.' The' strength of this binding force varies from atom to atom If the bond is weak enough, the nucleus can be split when bombarded by a free neutron (Figure 5). This causes the-
- entire atom to split, producing smaller atoms, more free neutrons, and heat. In a nuclear reactor, a chain reaction of fission events provides the heat necessary to boil the water to produce steam.
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i Davis-Besse Nuclear Power Station 1997 Annual Radiological Environinental Operating Report I l 0 Bombardin s
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Neutron < rn. O lO Neutron Atom [ ' Fission Fragment Figure 5: When a heavy stom, such as uranium.235 is split or fissioned. heat. free neutrons, and fission fragments result. *The free neutrons can then strike neighboring atoms causing them to fission also. In the proper environment, this process can continue indefinitely in a chain reaction. Nuclear Fuel l The fissioning of one uranium atom releases approximately 50 million times more energy than the l combustion of a single carbon atom common to all fossil fuels. Since a single small reactor fuel j pellet contains trillions of atoms, each pellet can release an extremely large amount of energy. i The amount of electricity that can be generated from three small fuel pellets would ' require about l 3.5 tons of coal or 12 barrels of oil to generate. l l Nuclear fission occurs spontaneously in nature, but these natural occurrences cannot sustain I themselves because the freed neutrons either are absorbed by non-fissionable atoms or quickly l decay. In contrast, a nuclear reactor minimizes neutron losses, thus sustaining the fission process I by several means:
. using fuel that is free ofimpurities that might absorb the free neutrons, j
. enriching the concentration of the rarer fissionable isotope of uranium (U-235) l relative to the concentration of U-238, a more common isotope the.t does not fis- l sion easily, ,
, )
. slowing neutrons down by providing a " moderator" such as water to increase the probability of fission.
Natural uranium contains less than one percent U-235 compared to the more abundant U-238 when it's mined. Before it can be economically used in a reactor, it is enriched to three to five l
, percent U-235, in contrast to nuclear material used in nuclear weapons which is epriched to over 97 percent. Because of the low levels of U-235 in nuclear fuel, a nuclear power station cannot explode like a bomb.
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1 Davis-Besse Nuclear Power Station 1997 Annual Radiolc,gical Environmental Operating Report Aner the uraniam ore is separated from the earth and rock, it is concentrated by a milling process. After milling the ore to a granular form and dissolving out the uranium with acid, the uranium is converted to uranium hexafluoride (UF6). UF is 6 a chemical form of uranium that exists as a ! gas at temperatures slightly above room temperature. The UF6 is then highly purified and shipped to an enrichment facility where gaseous ditTusion converters increase the concentration of U-235. The enriched gaseous UF6 is then converted into powdered uranium dioxide (UO2), a highly stable ceramic material. The UO2 powder is put undei high pressure to form fuel pellets, each about 5/8 inch long and 3/8 inch in diameter . Approximately five pounds of these pellets are placed into a 12 foot long metal tube made of zirconium alloy. The tubes constitute the fuel cladding. The fuel cladding is highly resistant to heat, radiation, and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods.
. . The Reactor Core -
Two hundred eight fuel rods comprise a single fuel assembly. The reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fuel rods, the fuel assembly also contains 16 vacant holes for the insertion of contre! rods, and one vacant hole far an incare monitoring probe. This probe monitors tem-perature and neutron levels in the fuel assembly. The Davis-Besse reactor vessel, which contains all the fuel assemblies, weighs 838,000 pounds, has a diameter of 14 feet, is 39 feet high, and has 81/2 inch thick steel walls. I O GD 4Il ' h _
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Figure 6: The reactor core at Davis-Besse contains 177 fuel assemblies. Each assembly contains 208 fuel rods. s Each fuel rod is filled with approximately five pounds of fuel pellets, each pellet is approximately 3/8 inch in di l ameter and 5/8 inch long. 13
l Davis-Besse Nuclear Power Stelion 1997 Annual Radiological Environmental Operating Report l Fission Control 3 The fission rate inside the reactor core is controlled by raising or lowering control rod assem- j blies into the reactor core. Each assembly consist of "fmgers" containing silver, indium, and cad- ) mium metals that absorb free neutrons, thus disrupting the fission chain reaction. .When control ' rod assocblies are slowly withdrawn from the core, fissioning begins and heat is produced. If the control rod assemblies are inserted rapidly into the reactor core, as during a plant " trip", the chain reaction ceases. A slower acting (but more evenly distributed) method of fission control is achieved by the addition of a neutron poison to the reactor coolant water. At Davis-Besse, high purity boric acid is concentrated or diluted in the coolant to achieve the desired level of fission. , Borou-10 readily absorbs free neutrons, forming boron-11, removing the absorbed neutrons from ' the chain reaction. Reactor Types Virtually all of the commercial reactors in this country are either boiling water reactors (BWRs) or pressurized water reactors (PWRs). Both types are also called light water reactors (LWRs) because their coolant, or medium to transfer heat, is ordinary water, which contains the light isotope of hydrogen. Some reactors use the heavy isotope of hydrogen (deuterium) in the reachr coolant. Such reactors are called heavy water reactors (IIWRs). 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. l After passing though the turbine the steam is condensed back into water and returns to the core to l repeat the cycle. In PWRs, the reactor water or coolant is pressui.;ed to prevent it from boiling. The reactor wa-ter is then pumped to a steam generator (heat exchanger) where its heat is transferred to a,sec-ondary water supply. The secondary water inside the generator boils into steam which is then used to turn the turbine. This steam is then condensed back into water and returned to the steam generator. ' Davis-Besse uses a PWR design. The following paragraphs describe the various systems illustrated in Figure 7. Major systems in the Davis-Besse Station are assigned a different color in the figure. e 14
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l l Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report I 1 Station Systems Containment Building and Fission Product Release Barriers The containment building houses the reactor vessel, the pressurizer, two steam generators, the
. reactor coolant pumps and reactor coolant system piping. The building is constructed of an inner l 1 inch thick steel liner or containment vessel, and the shield building with steel reinforced con-crete walls 2 feet thick. The shield building protects the containment vessel from a variety of en-vironmental factors and provides an area for a negative pressure boundary around the steel . containment vessel. In the event that the integrity of the containment vessel is compromised (e.g.,
a crack develops), this negative pressure boundary ensures that any airborne radioactive contami- 1 nation present in the containment vessel is prevented from leaking out into the environment.- This { is accomplished by maintaining the pressure inside the shield building lower than that outdoors, j
' thus forcing clean outside ' air to leak in, while making it'im~p'ossible for the contaminated air be- l tween the containment vessel and the shield building to leak out. The free-standing containment i vessel is the third in a series of barriers that prevent the release of fission products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel cladding itself.
The second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and ) associated piping. The Steam Generators The steam generators perform the same function as a boiler at a fossil-fueled power station. The steam generator uses the heat of the primary coolant inside the steam generator tubes to boil the , ; secondary side feedwater'(secondary coolant). Fission heat from the reactor core is transfer' red ! to the steam generator in order to provide the steam necessary to drive the turbine. However,- heat must also be removed from the core even after reactor shutdown in order to prevent damage to the fuel cladding. Therefore, pumps maintain a continuous flow of coolant through the reactor
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and steam generator. Primary loop water (green in Figure 7) exits the reactor at approxinfately 606 F, passes through the steam generator, transferring some ofits heat energy to the secondary loop water (blue in Figure 7) without actually coming in contact with it. Primary coolant water exits the steam generator at approximately 558'F to be~ circulated back into the reactor where it is again heated to 606*F as it passes up through the fuel assemblies. Under ordinary conditions, ' water inside the primary system would boil long before it reached such temperatures. However, it , is kept under a pressure of approximately 2,200 pounds-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 Pressur-ized Water Reactor. Secondary loop water enters the base of the steam generator at approxi-mately 450 F and under 1,100 psi pressure. At this pressure, the water can easily boilinto steam as it passes over the tubes containing the primary coolant water.
Both the primary and the secondary coolant water are considered chosed loop systems. This mean:, 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 7- method of heat transfer that can occur between two fluid media. It is the same process by which radiators are used to heat homesj The water circulating inside the radiator is separated from the 7 air (a " fluid" medium) by the metal piping. 16
' Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l
The Turbine - Generator The turbine, main generator, and the condenser are all housed in what is commonly referred to as
.the Turbine Building. The purpose of the turbine is to' convert,the thermal energy of the l
- steam produced in the steam generator'(referred to as main steam, red in Figure 7) to rotational energy of the turbine generator shaft. The turbine'at Davis-Besse is actually composed of one' six-stage high pressure turb;ne and two seven-stage low pressure turbines aligned on a common
. shaft. A turbine stage refers to a set of blades. Steam enters at the center of each turbine and flows outward along the shaft in opposite directions through each successive stage of blading. As :
.the steam passes over the turbine blades, it loses pressure. . Thus, the blades must be proportion-
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ally larger in successive stages to extract enough energy from the steam to rotate the shaft at the
. correct speed '
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The purpo'se of the main generator is to' convert the ~r otational energy of the shaft to electrical energy for commercial usage and support of station systems. The main generator is composed of ' i two parts, a stationary stator that contains coils of copper conductors, and a rotor that supplies a rotating magnetic field within the coils of the stator. Electrical current is generated in the stator portion of the main generator. From this point, the electric current passes through' a series of transformers for transmission and use throughout northern Ohio. The Condenser After the spent steam in the secondary loop (blue in Figure 7) passes through the high and low pressure turbines, it is collected in a cavernous condenser several stories tall and containing more than 70,000 small tubes. Circulating water (yellow in Figure 7) goes to the cooling tower' after
. passing through the tubes inside the condenser. As the steam from the low pressure turbines passes over these tubes, it is cooled and condensed. The condensed water is then purified and
. reheated before being circulated back into the steam generator again in a closed loop system. .Cir- ! culating water forms the third (or tertiary) and final loop of cooling water used at the IIavis- I Besse Station. Similar to the primary to secondary interface, the secondary to tertiary interface is based on a closed loop design.- The circulating water is able to cool the steam in the condenser, without ever actually coming in contact with it, by the process ofconvection. 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. <
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report After passing through the condenser, the circulating water has warmed to approximately 100 F. l I In order to cool the water back down to around 70 F, the circulating water enters the cooling l tower about 40 feet above the ground. The water is sprayed evenly over a series of baffles called l fillsheets which are suspended vertically in the base of the tower. A natural draft of air blowing i up through these baffles cools the water through the process of evaporation. The evaporated l l water exits the top of the cooling tower in the form of water vapor. l l As much as 10,000 gallons of water per minute are lost to the atmosphere via the cooling tower. l Even so, approximately 98 percent of the water drawn from Lake Erie for station operation can j be recycled through the cooling tower for reuse. A small portion of the circulating water is dis- l 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 oflake sur-rounding the discharge point. Miscellaneous Station Safety Systems The orange system in Figure 7 is part of the Emergency Core Cooling System (ECCS) housed in the Auxiliary Building of the station. The ECCS consists of three overlapping means of keeping the reactor core covered with water, in the unlikely event of a Loss Of Coolant Accident (LOCA), thereby protecting the fuel cladding barrier against high temperature failure. Depending upon the severity of the loss of pressure inside the primary system, the ECCS will automatically channel borated water into the reactor by either high pressure injection pumps, a core flood tank, or low pressure injection pumps. Borated water can also be sprayed from the ceiling of the containment vessel to cool and condense any steam that may escape from the primary system. The violet system illustrated in Figure 7 is responsible for maintaining the primary coolant water in a liquid state. It accomplishes this by adjusting the pressure inside the priom y system. Heaters inside the pressurizer turn water into steam. This steam takes up more space inside the pressur-izer, thus increasing the overall pressure inside the primary system. The pressurizer ispequi ped with spray heads that shower cool water over the steam in the unit. In this case, the steam con-denses and the overall pressure inside the primary system drops. The quench tank pictured in
- Figure 8 is simply where excess steam is directed and condensed for storage.
The scarlet system in Figure 7 is part of the Auxiliary Feedwater System, a key safety system in event the main feedwater supply (blue in Figure 7) to the steam generator is lost. Following a re-actor shutdown, the Auxiliary Feedwater System can supply water to the steam generators from the Condensate Storage Tanks. The Auxiliary Feedwater System is housed in the Turbine Building along with the turbine, main generator, and the condenser.
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D:vis-Besso Nuclear Power Station 1997 A'nnual Radiological En-konmental Operating Report l Reactor Safety and Summary l Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear l' power plants cannot explode like a bomb because the concentration of fissionable material is far l less than is necessary for such a nuclear explosion. Also, many safety features are equipped with - l
.several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the tod environment. Davis-Besse, like all U.S. nuclear units, has many overlapping, or redundant safety fevures. If one sys-tem should fail, there are still back-up systems to assure the safe operation of the Ctation. During L- normal operation, the Reactor Control System regulates the power output by adjusting the posi-l tion of the control rods. The reactor can be automatically shut down by a separate Reactor Pro-l tection System that causes all the control rod assemblies to be quickly and completely inserted L into the reactor core, stopping the chain reaction. To guard against the possibility of a Loss Of
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Coolant Accident, the Emergency Core Cooling System is designed to ptimp ~ reserve water'into' the reactor automatically if the reactor coolant pressure drops below a predetermined level. L The Davis-Besse Nuclear Power Station was designed, constmeted, and operates to produce a reliable, safe, and environmentally sound source of electricity. I l i Radioactive Waste j 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 l by-products are managed and disposed ofunder strict requirements set by the federal government.
- With the exception of used nuclear fuel assemblies, these by-products produced at commercial power plants are referred to as low level radioactive waste.
Low Level Radioactive Waste 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. l The radioactive material in low level radioactive waste emits the same types of radiation that natu-i rally occurring radioactive materials tend to emit. Most low level radioactive waste " decays" to , I background levels of radioactivity in months or years. Nearly all ofit diminishes to stable materi- l als in less than 300 years.- l In 1980, Congress passed the Low-Level Waste Policy Act. This law icquires each state to de-velop an individual disposal site for waste, or to form " compacts" with other states to jointly dis- j pose of their low-level waste. Approximately 10 regional compacts have been formed. j l l s e 19
Davis-Besse Nuclear Power Stati:n 1997 Annual Radiol:gical Emironmental Operating Report Davis-Besse presently ships low level radioactive waste to a South Carolina disposal facility 10-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 oflow level radioactive waste to the facility. Davis-Besse has the capacity to store low level waste it produced on site, in the Low Level Radioactive Waste Storage Facility (LLRWSF) for several years in the event the Barnwell facility closes again. ' 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 per-cent 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 leR over aRer the atom is
- split, are radioactive. After a period of time, the fission fragments trapped in the fuel assemblies -
reduce the efficiency of the chain reaction. Every 18 to 24 months, the eldest fuel assemblies are removed from the reactor and replaced with fresh fuel. High-level nuclear waste volumes are small. Davis-Besse produces about 30 tons of used fuel every 24 months. All the used fuel produced by all America's nuclear energy plants since the first plant started operating over 30 years ago would cover an area the size of a football field about five yards deep. All of America's nuclear plants combined produce only 3,000 tons of used fuel each year. By contrast, the U.S. produces about 300 million tons of chemical waste annually. Also, nuclear waste slowly loses its radioactivity, but some chemical waste remains hazardous in-definitely. 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 capacity in 1996. At the end of 1996, Davis-Besse began the process of moving the older fuel assemblies that no longer require water cooling to air cooled concrete shielded canisters. These will remain stored onsite until the Department of Energy facilities are ready to receive them. Dry fuel storage is already used in many_ countries, including Canada, and in the U.S. at nuclear plants in Colorado, Maryland, Virginia, and South Carolina. Figure 8 illustrates the dry fuel storage module arrange- . ment at Davis-Besse. 20 1
i I Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l - !il i
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I Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Description of the Davis-BesSe Site l The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the south-western shore of Lake Erie, just north of the Toussaint River. The site lies north and east of Ohio i State Route 2, approximately 10 miles northwest of Port Clinton, 7 miles north of Oak Harbor, and 25 miles east of Toledo, Ohio (Figure 9). l This section of Ohio is flat and marshy, with maximum elevations of only a few feet above the ' level of Lake Erie. The area originally consisted of swamp forest and marshland, rich in wildlife l but unsuitable for settlement and farming. During the nineteenth century, the land was cleared ! and drained, and has been farmed successfully since. Today, the terrain consists of farmland with marshes extending in some places for up to two miles inland from the Sandusky Lake Shore Ridge. 1
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ED 4 w /+ abrv r - r-Figure 9: Davis-Besse is near Oak Harbor, Port Clinton, and the Ottawa National Wildlife Refuge. Davis-Besse site is mainly comprised of marshland with a small portion consisting of farmland. The marshes are part of a valuable ecological resource, providing a breeding ground for a variety of wildlife, and a refuge for migratory birds. The site includes a tract known as Navarre Marsh, which was acquired from the U.S. Bureau of Sport Fisheries and Wildlife, Department of the Inte-rior. In 1971, Toledo Edison purchased the 188-acre Toussaint River Marsh. The Toussaint River Marsh is contiguous with the 610-acre Navarre Marsh section of the Ottawa National # Wildlife Refuge. ' 22
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report The immediate area near Davis-Besse is sparsely populated; Ottawa County had a population of 40,029 in the 1990 census. The nearest incorporated communities are: Port Clinton - 10 miles southeast, population 7,106 Oak Harbor - 7 miles south, population 2,637 Rocky Ridge - 7 miles west southwest, population 425 Toledo (the nearest major city) - 25 miles west, population 322,943 There are some residences along the lake shore used mainly as summer homes. However, the l ' 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 . crcps 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- l j cated in Erie Industrial Park, about four miles southeast of the station. 1 Most of the remaining marshes in the area have been maintained by private hunting clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife. The State of Ohio Department of Natural Resources operates many wildlife and recreational areas within 10 miles of the Station. These include Magee Marsh, Turtle Creek, Crane Creek State Park, and the Ottawa National Wildlife Refuge. Magee Marsh and Turtle Creek lie between three and six miles WNW of the Station. Magee Marsh is a wildlife preserve allowing public fishing, nature study, and controlled hunting season. Turtle Creek, a wooded area at the southern end of Magee Marsh, offers boating and fishing. Crane Creek State Park is adjacent to Magee Marsh and is a popular picnicking , swimming, and fishing area. The Ottawa National Wildlife Refuge lies four to nine miles WNW of the Site, immediately west ofMagee Marsh. 1 i [ ! s 23 i
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report References
- 1. " Basic Radiation Protection Criteria,"_ Report No. 39, National Council on Radiation Protec-
. tion and Measurement, Washington, D.C. (January 1971).
- 2.' " Cesium-137 from the Environment to Man:_ Metabolism and Dose," Report No. 52, 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). 1
~4. Eisenbud, M., " Environmental Radioactivity," Academic Press, Inc., Orlando, FL. (1987).
- 5. " Environmental Radiation Measurements," Report No. 50, National Council on Radiation
~
Protection and Measurements, Washihgton, D.C. (December 1976). L 6. " Exposure of the Population in the United States and Canada from Natural Background Ra-l diation," Report No. 94, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1987).
- 7. " Health Effects of Exposure to Low Levels ofIonizing Radiation: BEIR V," Committee on the Biological Effects ofIonizing Radiations, Board on Radiation Effects Research Commis-sion on Life Sciences, National Research Council, National Academy Press, Washington, D.C.
(1990).
- 8. Hendee, William R., and Doege, Theodore C., " Origin and Health Risks ofIndoo'r Radon,"
i Seminars in Nuclear Medicine, Vol. XVIII, No.1, American Medical Association, Chicago, IL. (January 1987). 9.' Hurley, P.,"Living with Nuclear Radiation," University ofMichigan Press, Ann Arbor, MI.
- l. (1982).
- 10. " Indoor Air Quality Environmental Information Handbook: Radon," prepared for the United States Department of Energy, Assistant Secretary for Environment, Safety and Health, by Mueller Associated, Inc., Baltimore, MD. (January 1986).
- 11. Introduction to Davis-Besse Nuclear Power Station Plant Technology, July 1992, Rev. 4, Pg.2-9. '
' 12. " Ionizing Radiation Exposure of the Population of the United States," Report No. 93, Na-tional Council on Radiation Protection and Measurements, Washington, D.C. (September 1987).-
- 13. " Natural Backgrotind, Radiation in the United States," Report No. 45, National Council on Radiation Protection and Measurements, Washington, D.C. (November 1975).
7 L m n 24 L
Davis-Besse Nuclear Power Station 1997 AnnualIbdiological Environmental Opecing Repon
- 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). j
- 16. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurement, Washington, D.C. (De-cember 1987).
- 17. " Radiation Protection Standards," Department of Environmental Sciences and Physiology and the Oflice of Continuing Education, Harvard School Of Public Health, Boston, MA. (July 1989).
L 18. Radiological Environmental Monitoring Report for Three Mile Island Station," . GPU Nuclear Corporation, Middletown, PA. (1985).'
- 19. " Sources, Effects and Risk ofIonizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation,1988 Report to the General Assembly, United Nations, New York (1988).
- 20." Standards for Protection Against Radiation," Title 10, Part 20, Code of Federal Regulation, Washington, D.C. (1988).
l
- 21. " Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50, Code of Fed-i eral Regulations, Washington, D.C. (1988).
- 22. " Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40,:Part 190, Code of Federal Regulations, Washington, D.C. (1988).
- 23. " Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1979). j i i
- 24. Site Environmental Report, Fernald Environmental Managaaent Project, U.S. Department of l
Energy (June 1993). l
- 25. " Exposure from the Uranium Series with Emphasis on Radon and it's daughters" Report No.
77, National Council on Radiation Protection and Measurements, Washington, D.C. (1984). l 26. " Evaluation of Occupational and Environmental Exposures to Radon and Radon daughter in l the United States, " Report No. 78, National Council on Radiation Protection and Measure-ments, Washington, D.C. (1984).
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Davis-Besse Nuclear Power Station 1997 Anmtal Radiological Environmental Operating Report I l Radiological Environmental Monitoring ; I l Program l l I 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 j efIluent controls, to assess the radiological impact of the Station's operation on the surrounding l 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 preopera-tional surveillance prog' ram was established to describe and quantify the radioactivity, and its v'riability, a in the area prior'to the operation of Davis-Besse. After Davis-Besse became opera- ! tionalin 1977, the operational surveillance program continued to measure radiation and radio-activity in the surrounding areas. A variety of environmental samples are collected as part of the REMP at Davis-Besse. The selec-tion of sample types is based on the established critical pathways for the transfer of radionuclides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population characteristics, and land usage in the area ofinterest. The selection of sampling frequencies for the various envi-ronmental media is based on the radionuclides ofinterest, their respective half-lives, and their be- l havior in both the biological and physical environment. A description of the REMP at Davis-Besse is provided in the following section. In addition, a brief history of analytical results for each sample type collected since 1972, and a more detailed summary of the analyses performed during this reporting period, is also provided. Preoperational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental moni- ] toring prior to constmeting the facility. This preoperational surveillance program is aimed at col- ! lecting the data needed to identify critical pathways, including selection of the radioisotope and ! I sample media combinations to be included in the surveillance program conducted after facility op-eration begins. Radiochemical analyses performed on the environmental samples should include ! not only those nuclides expected to be released during facility operation, but should also include typical fallout radionuclides and natural background radioactivity. All environmental media with a potential to be afrected 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- l ronmental surveillance program. , i
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report The preoperational surveillance design, including nuclide/ media combinations, sampling frequen-cies and locations, collection techniques, and radioanalyses performed, should be carefully consid-ered and incorporated in the design of the operational surveillance program. In this manner, data .j can be compared in a variety of ways (for example: from year to year, location to location, etc.) in - order to detect any radiological impact the facility has on the surrounding environment. Data - collection during the preoperational phase should be planned to provide a comprehensive database for evaluating any future changes in the environment surrounding the nuclear facility. Davis-Besse began its preoperational 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 program at Davis-Besse will continue after the Station has reached the end ofits economically useful life and decommissioning has begun. Operational Surveillance Program Objectives The operational phase of the environmental surveillance program at Davis-Besse was designed with the following objectives in mind:
. to fulfill the obligations of the radiological surveillance sections of the Station's Technical Specifications and Offsite Dose Calculation Manual; e to determine whether any significant increase occurs in the concen-tration of radionuclides in critical pathways;
. 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-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:
. performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keeping; e performing audits of contractor 1aboratories which analyze the envi-ronmental samples; 7 27
Davis-Besse Nuclear Power Station 1997 Annual Radi: logical Environmental Operating Report
- requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross-Check Pro-gram;
- requiring analytical contractor laboratodes-to split samples for separate analysis followed by a comparison ofresults; 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 sam-pies collected and the sampling locations used by the NRC'and ODH wer~e~ incorporated in Da~vis Besse's REMP. Hence, the analytical results from the different programs can be compared. This practice of comparing results from identical samples, collected and analyzed by different parties, provides a valuable tool to verify the quality of the laboratories analytical procedures and the data generated. l In 1987, environmental sampling personnel at Davis-Besse incorporated their own Quality Assur-l ance program into the REMP. Duplicate samples, called quality control samples, were collected l at several locations. These duplicate samples were assigned different identification numbers than l the numbers assigned to the routine samples. This ensured that the analytical laboratory.would L' not know the samples were identical. The laboratory results from analysis of the quality control i samples and the routine samples could then be compared for agreement. Quality control sampling has been integrated into the program and has become an important part of the REMP since 1987. Quality control sampling locations are changed frequently in order to duplicate as many sampling locations as possible, and to ensure the contractor laboratory has no way of correctly paidng a quality control sample with its routine sample counterpart. Program Description ) L Overview - The Radiological Environmental Monitoring Program (REMP) at Davis-Besse is conducted in
- accordance with Title 10, Code of Federal Regulations, Part 50; Regulatory Guide 4.8; the Davis-Besse Nuclear Power Station ~ Operating License, Appendix A (Technical Specifications); the Davis-Besse Offsite Dose Calculation Manual (ODCM) and Station Operating Procedures._ Sam-i pies are collected either weekly, monthly, quarterly, semiannually, or annually, depending upon the sample type and nature of the radionuclides ofinterest. Environmental samples collected by
- Davis-Besse personnel are divided into four general types:
l l= . atmospheric -including samples of airborne particulates and airborne ; radioiodine
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Davis-Besse Nuclear Power Station 1997 Ann tal Radiol gical Environmental Operating Report e terrestrial -- including samples of milk, groundwater, broad leaf vegetation, fmits animal / wildlife feed, soil, eggs, and wild and domestic meat e aquatic --including samples of treated and untreated surface water, fish, and shoreline sediments e direct radiation -- measured by thermoluminescent dosimeters 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. Inuicator 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 locations are also compared with preoperational data to deten tine whether significant variations or trends exist. Since 1987, the REMP has been reviewed and modified a develop a comprehensive sampling program adjusted to the current needs of the utility. Modi 9 cations have included additions of sampling locations above the minimum amount required ic % ? XM and increasing the number of analyses performed on each sample. Besides adding new acations, duplicate or Quality Control (QC) sample collection was initiated to verify the accuracy of the lab analyzing the environmental samples. These additional samples are referred to as the REMP Enhancement Samples. Over 1700 samples were collected and over 2350 analyses were performed during 1997. In addition,15% of the sampling locations were quality control sampling locations. Table 3 shows the number of the sampling location and number collected for each type. l l 1 i t l l I i 1 29
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report L Table 2: Sample Codes and Collection Frequencies Sample Collection Sample Type Code Frequency Airborne Particulate AP Weekly Airborne Iodine AI Weekly Thermoluminescent TLD Quarterly, Annually l Dosimeter i Milk MIL Monthly (semi-monthly during grazing season) . I Groundwater WW Quarterly I I l Broad Leaf Vegetation BLV Monthly (when available) l Surface Water - Treated SWT Weekly i Surface Water- SWU Weekly l Untreated (lake water , monthly) Fish FIS Semiannually Shoreline / Bottom SED Semiannually Sediment = Soil SOI Semiannually AnimalAVildlife Feed DFE/WFE Annually Meat-Domestic DME Annually Meat-Wild WME Annually L Egg EGG Annually Fruits FRU Annually S 30
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Davis-Besse Nuclear Power Stati:n 1997 Annual Radi: logical Environmental Operating Report Table 3: Sample Collection Summary Sample Collection Number of Number of Number of Type Type */ Locations Samples Samples (Remarks) Frequency *
- Collected Missed Atmospheric Airborne Particulates 10 520 0 Airborne Radiciodine C/W 10 520 0 Terrestrial Milk (Jan.-Dec.) G/M 1 12 0 Groundwater G/Q*** 4 16 0 Edible Meat wild G/A 1 0 1 domestic G/A 2 2 0 Eggs G/A 2 0 2 Broad Leaf Vegetation / Fruit G/M 7 15 0 Soil G/S 10 20 0 Animal / Wildlife Feed G/A 4 4 0 Aquatic
)
Treated Comp /WM*" 2 30 0 Surface Water G/WM * *
- 4 42 0 3 Untreated G/WM * *
- 2 17 0 Surface Water G/M 10 60 0 Comp /WM* *
- 4 55 0 q Fish (3 species) G/SA 2 6 0 l Shoreline Sedi.ments G/SA 4 8 0 I l
t Direct Radiation Thermoluminescent C/Q*** 93 360 12 Dosimeters (TLD) C/A"
- 93 83 10 l
- Type of Collection: C = Continuous; G = Grab; Comp = Composi;e i
*
- Frequency of Collection: WM = Weekly composite Monthly; W = Weekly
"* Includes quality control location SM = Semimonthly; M = Monthly; Q = Quarterly; SA = Semiannually; A = Annually 31
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental OI mting Report Sample Analysis. When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Davis-Besse REMP include: Gross beta ' analysis measures the total amount of beta emitting radioactive material present in a sample. Beta radiation may be released by many different' radionuclides. Since beta decay gives a I continuous energy spectrum rather than the discrete lines or " peaks" associated with gamma ra- j diation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross ; f beta analysis only_ indicates whether the sample contains normal or abnormal concentrations of beta emitting radionuclides; it does not identify specific radionuclides. Gross beta analysis merely acts as a tool to identify samples that may require further analysis. Gamma spectral analysis.provides more specific information than does gross beta analysis. Gamma spectral analysis 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 ofiodine-131 in a sample. Iodine-131 is a man-made radioac-tive isotope ofiodine that may be present in the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power stations. Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and'the - amount present. As discussed in the Introduction Section, tritium is an isotope of hydrogen that emits low energy beta panicles. Strontium _ analysis identifies the presence and am'ount of strontium-89 and strontium-90 in a sample. These man-made radionuclides are found in the environment as a result of fallout fr'o m 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 speciallaboratory procedure. Table 4 provides a list of the analyses performed on environmental samples collected for the Davis-Besse REMP.
' Often samples will contain little radioactivity, and may be below the lower limit of detection for the panicular type of analysis used. The lower limit of detection (LLD) is the smallest amount of
. sample activity which can be detected with a reasonable degree of confidence, at a predetermined level. When a measurement of radioactivity is reported as less than LLD (<LLD), it means that the radioactivity is so low that it cannot be accurately measured with any degree of confidence by that p' articular method for an individual analysis.
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples Sample Type Analyses Performed l Atmospheric Monitoring Airborne Particulate Gross Beta l Gamma Spectral l Strontium-89 Strontium-90 l Airborne Radiciodine Iodine-131 Terrestrial Monitoring . ., . . . . Milk Gamma Spectral Iodine-131 Strontium-89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Broad Leaf Vegetation Gamma Spectral and Fruits Iodine-131 , Strontium-89 Strontium-90 Animal / Wildlife Feed Gamma Spectral Soil Gat spectral Wild and Domestic Meat Gamma Spectral Egg Gamma Spectral
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Davis-Desse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report - I Table 4: Radiochemical Analyses Performed on REMP Samples (con-tinued) Sample Type Analyses Performed Aquatic monitoring Untreated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 l - -1' 1 Treated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Iodine-131 l Fish Gross Beta l Ganuna Spectral Shoreline Sediment Gamma Spectral l Direct Radiation Monitoring l 1 Thermoluminescent Dosimeters Gamma Dose l l l l
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I Davis-Desse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report I l Sample History Comparison ; The measurement of radioactive materials present in the environment will depend on factors such as weather or variations in sample collection techniques or sample analysis. This is one reason l why the results of sample analyses are compared with results from other locations and from earlier years. Generally, the results of sample analyses are compared with preoperational and operational data. Additionally, the results ofindicator and control locations are also compared. This allows l 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 performed from 1972 through the current reporting period is provided in the following section. Atmospheric Monitoring. .
. Airborne Particulates: No radioactive particulates have been de-tected as a result of Davis-Besse's operation. Only natural and fall-out radioactivity from nuclear weapons testing and the 1986 nuclear accident at Chernobyl have been detected.
- Airborne Radioiodine: Radioactive iodine-131 fallout was de-tected in 1976,1977, and 1978 from nuclear weapons testing, and in 1986 (0.12 to 1.2 picocuries per cubic meter) from the nuclear accident at Chernobyl.
Terrestrial Monitoring:
. Groundwater: Only naturally occurring radioactive material has been detected in groundwater.
- Milk: Iodine-131 from nuclear weapons testing fallout was de-tected in 1976 and 1977 at concentrations of 1.36 and 23.9 picocu-ries / liter respectively. In 1986, concentrations of 8.5 picocuries/
liter were detected from the nuclear accident at Chernobyl. No io-dine-131 detected has been attributable to the operation of Davis-Besse.
- Domestic and Wild Meat: Only naturally occurring potassium-40 and very low cesium-137 from fallout activity has taen detected in meat samples. Potassium-40 has ranged from 1.1 tc 4.6 picocu-ries / gram wet weight. Cesium-137 was detected in 1074, 1975, l and 1981 due to fallout from nuclear weapons testing.
. Broad Leaf Vegetation and Fruits: Only naturally occurring ra-l dioactive material and material from nuclear weapons testing has been detected. / /
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Davis-Besse Nuclear Power Station 1997 Annual Radiol:gical Environmental Operating Report o Soil: Only natural background and material from nuclear weapons testing and' the 1986 nuclear accident at Chernobyl has been detected.
- Animal / Wildlife Feed: Only natural background and material from weapons testing has been detected.
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- Eggs: Only natural background radioactive material has been detected.
Aquatic Monitoring e Surface Water (Treated and Untreated): In 1979 and 1980, the tritium concentrations at location T-7 were above normal background Location T-7 is a beach well fed directly by Lake Erie. The fourth quarter sample in 1979 read 590 picocuries per liter, and the first quarter sample in 1980 had a concentration of . , 960' picocurie's perliter. '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 picoeuries per i liter. These concentrations could be attributed to the operation of l Davis-Besse. Even so, these results at T-7 were more than 39 ' times lower than the annual average concentration allowed by the EPA National Interim Primary Drinking Water Regulations (40CFR141), and were only 0.032% of the Maximum Permissible ; Concentration (MPC of 3,000,000 picocuries per liter) for tritium in 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
' Toussaint 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 operation of Davis-Besse, it was only 0.029% of the maximum permissible 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 Toussaint River) showed trace amounts of activity which may be attributed to the normal operation of the station. The tritium concentration for the composite was 950 pCi/li This is only 0.032 percent of the maximum permissible concentration of 3,000,000 pCi/l for tritium in an unrestricted area, as stated in 10 CFR 20, Appendix B, Table 2. Subsequent samples collected during January 1 36
Davis Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report - showed that the tritium had returned to below the LLD of 330 pCi/1, In the fourth quarter of 1994, tritium was detected at 336+94 pCi/1, slightly above the lower limit of detection for tritium, at one of the treated water sampling locafons. Tritium was also detected at several of the untreated water sampling locations at an average concentration of 470 pCi/l during the 3rd and 4th quarters of 1994, Samples taken in January 1995 indicated that the tritium concentration in untreated water was less than the lower limit of detection for tritium in water. For comparison purposes, tritium concentrations in Lake Erie untreated surface water, determined during the preoperational sampling 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 w'as' detected in six bntreated water
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samples collected in May and one sample collected in October. The tritium detected ranged between 330 to 1234 pCi/l with an average concentration of 681 pCi/l. This is only 0.12% of the Efiluent Con-centration 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/l in 8 untreated surface water samples. The remainder of the untreated surface water samples were <330 pCi/l. During 1997, the tritium detected ranged between 340 to 575 pCill with an average concentration of 430 pCi/lin 4 untreated surface water samples. Even though these may be attributed to the operation of l Davis-Besse,- this average concentration is less than 0.06% of Maxi- ! mum Permissible Concentration for tritium in unrestricted areas e Fish: Only natural background radioactive material and material from nuclear testing has been detected, e Shoreline Sediments: Only natural background, material from nu-clear testing and from the 1986 nuclear accident at Chernobyl has been detected. Direct Radiation Monitoring:
- Thermoluminescent Dosimeters (TLDs): The annual average gamma dose rates for the current reporting period recorded by TLDs ranged from 45.0 to 72.2 millirem per year at control loca-tions and between 32.6 and 77.1 millirem per year at indicator lo-cations. No increase above natural background radiation attributable to the operation ofDavis-Besse has been observed.
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Davis Besse Nuclear Power Station 1997 Annual Radi: logical Emironmental Operating Report 1997 Program Deviations Provided below is a description and explanation of 1997 environmental sample collection deviations.
- Broad leaf vegetation samples during January, February, March, April, May, June, November and December 1997 were unavailable for collection because of seasonal condition or insufficient quantity of desired broad leaf vegetation.
. T-3 untreated water samples were not collected due to ice on i surface for the following months : January, Feb, March. T-28 was !
substituted for T-3 samples. d
.. Various TLDs were lost in the field : T-204 location had 2 and 3d l d quarter missing. T-7 location had 3 quarter and annual missing. 1 d
T-112 location had i",2 quarter and annual missing with evidence d c of maintenance work in area. T-38,203 3 quarter plus annual ~ l missing.T-1,48,49,200,2014* quarter and annual TLDs were I vandalized. This was documented in PCAQR 98-0071. Davis Besse l security and local law enforcement was informed. l e T-12, surface water untreated, was not a composite due to the failure of Toledo Water department in collecting samples for l l various times during year. Grab samples were taken for these times
- when composites were not available. On 10/27/97, an automatic compositor was put in place at the Low Pressure Pumping Station to assure this sample was collected.
. In November 1997, the second fish collection of the year was not l collected. The nets were removed from the indicator location early l in the month because oflow fish harvest. Weather conditions on j the lake also prevented collection prior to the nets being removed.
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- In October, the wild meat (muskrat) sample was not collected.
Samples could not be purchased from trappers of this area because a permit to trap was not issued by the U.S. Fish and Wildlife Department. Two unsuccessful attempts were made to trap L muskrat by site personnel.
- T-1 air sampler was not pumping properly due to pump pumping water instead of air during a hard rainstorm. Pump was changed out; no other problem noted. T-4 was used as Technical Specifications sample.
- T-4 air sampler station had a power failure on 7/1/97 for an unknown reason. The fuse was replaced and no other problem noted.
e T-9 air sampler was hit by lighting on 8/19/97. The pump was ; changed out and station was operational again. ;
- T-1, T-2, and T-3 lost power on 11-15-97 for 10 hours due to ground fault in the transformer near the beach station. Repair of the transformer restored normal power supply.
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Emironmental Operating Report e Storm sewer Radiation Element was out of service from 8/2/97 to 11/20/97 due to pump failure. Samples were collected every {'
.8 hours.
RIM 1822A failed on 10/17/97 and repaired under MWO l-97-0714-00. Changed sample location of T-162 SWU to camp Perry beach area due to higher than normal lake water level; documented in DSR- 97-00217.- e F201 was out of service for longer than 30 days from 9/25 to 10/27 due to probe replacement under MWO 7-96-1376-01. Atmospheric Monitoring Air Samples ' Environment.al air sampling is conducted to detect any increase in the concentration of airborne - radionuclides that may be inhaled by humans or serve as an external radiation source. Inhaled l radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air samples collected by the Davis-Besse REMP include both airborne particulates and airborne radiciodine. Samples are collected weekly with low volume vacuum pumps which draw a continuous sample through a glass fiber filter and charcoal cantidge at a rate of approximately one cubic foot per minute. Airborne particulate samples are collected on 47 mm diameter filters. Charcoal cartridges are installed downstream of the particulate filters to sample for the airborne radioiodine. The airborne samples are sent to an offsite contractor laboratory for analysis. At the laboratory, the airborne particulate filters are stored for 72 hours before they are analyzed to allow for the decay'of naturally occurring short-lived radionuclides. However, due to the short half-life of ' iodine-131 (approximately eight days), the airborne radioiodine cartridges are analyzed upon receipt by the contractor laboratory. Airborne Particulates Davis-Besse continuously samples air for airborne radionuclides at ten locations. There are six indicator locations including four around the site boundary (T-1, T-2, T-3, and T-4), one at Sand Beach (T-7), and another at a local farm (T-8). There are four control locations, Oak Harbor (T-9), Port Clinton (T-11), Toledo (T-12) and Crane Creek (T-27). Gross beta analysis is performed on each of the weekly samples. Each quarter, the filters from each location are combined (composite) and analyzed for gamma emitting radionuclides, strontium-89 and strontium-90. Beta emitting radionuclides were detected at both the indicator and control locations at average concentration of 0.021 pCi/m' and 0.021 pCi/m', respectively. _ Beryllium-7 was the only gamma emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites. , Beryllium-7 is a naturally occurring radionuclide produced in the upper atmosphere by cosmic ! radiationi No other gamma emitting radionuclides were detected above their respective LLDs. j Strontium-89 (Sr-89) was not detected above its LLD. Strontium-90 (Sr-90) was detected in one I indicator location (T-7) during the first quarter (0.0005+/- 0.0003 pCi/m'). These results show l no adverse change in radioactivity in air samples due to operation of the Davis-Besse Nuclear l Power Station in 1997. I 39
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Airborne Iodine-131 Airborne iodine-131 samples are collected at the same ten locations as the airborne particulate samples. Charcoal canridges are placed downstream of the particulate filters. These cartridges are collected weekly, sealed in separate collection bags and sent to the laboratory for gamma spectral analysis. In all of the samples collected in 1997, there was no detectable iodine-131 above
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environm:ntal Operating Repon l 1
-Table 5: Air Monitoring Locations Sample Location ~ Type of Number Location _ Location Description T-1 I Site boundary,0.6 miles ENE of Station T-2~ I Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station
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' Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmenial Operating Report Terrestrial Monitoring The collection and analysis of groundwater, milk, meat, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. Animal and wildlife )
feed samples provide additional information on radionuclides that may be present in the food chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere, Many radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. Some of the radionuclides present are: tritium, present as a result of the interaction of cosmic radiation ' with the upper atmosphere and as a result of routine release from nuclear facilities 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 fallout from nuclear weapons testing and routine releases from nuclear fa-cilities e potassium-40, a naturally occurring radionuclide normally found-throughout the environment (including humans) e fallout radionuclides from nuclear weapons testing, including strontium-89, strontium-90, cesium-137, cerium-141, cerium-144, and ruthenium-106, These radionuclides may also be released in minute amounts from nuclear facilities f The radionuclides listed above are expected to be present in many of the environmental samples j collected in the vicinity of the Davis-Besse Station. The contribution of radionuclides from the l operation of Davis-Besse is assessed by comparing sample results with preoperational data, op- j erational data from previous years, control location data, and the types and amounts of radioac- J tivity normally released from the Station in liquid and gaseous effluents. ' Milk Samples Milk sampling is a valuable tool in environmental surveillance because it provides a direct basis for assessing the build up of radionuclides in the environment that may be ingested by humans. Milk is collected and analyzed because it is one of the few foods commonly consumed soon after production. The milk pathway involves the deposition of radionuclides from atmospheric releases onto forage consumed by cows. The radionuclides present in the forage eating cow become in-corporated into the milk which is then consumed by humans. I 45
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report When milk is available, samples are collected at the indicator location and at the control location I 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 eliminated from the sampling ) program because the family there went out of the dairy business and sold the herd. The control location will continue to be sampled monthly in order to gather additional baseline data. If any dairy animals are discovered within five miles of the station, effons will be made to include them in the milk sampling program. The 1997 milk samples were analyzed for strontium-89, strontium-90, iodine-131 and other gamma emitting radionuclides, stable calcium and potassium. A total of 12 milk samples were collected in 1997. Strontium-89 was not detected above the LLD of 1.1 pCi/l in any of the I samples. Strontium-90 was detected in all but one samples collected. The annual average ) concentration of strontium-90 was 1.09 pCi/1 For all sample sites, the annual average concentration was similar to those measured in the previous years. Iodine-131 was not detected in any of the milk samples above the LLD of 0.5 pCi/1. The concentrations of barium-140 and cesium-137 were below their respective LLDs in all samples collected. Since the chemistries of calcium and strontium are similar, as are potassium and cesium, organisms tend to deposit cesium radioisotopes in muscle tissue and strontium radioisotopes in bones In order to detect the potential environmental accumulation of these radionuclides, the ratios of the strontium radioisotopes radioactivity (pCi/l) to the concentration of calcium (g/l), md cesium radioisotopes radioactivity (pCi/l) to the concentration of potassium (g/l) were monitored in milk. These ratios are compared to standard values to determine if build up is occurring. No statistically significant variations in the ratios were observed. l l Table 6: Milk Monitoring Location Sample Location Type of Number Location Location Description T-24 C Toft Dairy, Sandusky,21.0 miles SE ofStation C = Control 46 (:
r Davis-Besse Nuclear Power Station 1997 Annual Radi:1 gical Environmental Operating Repon Groundwater Samples Soil acts as a filter and an ion exchange medium for most radionuclides. However, tritium and other radionuclides such as ruthenium-106 have a potential to seep through the soil and could reach groundwater. Although Davis-Besse does not discharge its liquid efiluents directly to the l ground, REMP personnel sample local wells on a quarterly basis to ensure the early detection of j any adverse impact on the local groundwater supplies due to Station operation. The wells sampled 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 emitting radionuclides. Beta emitting radionuclides average 6.8 pCi/l for indicator locations and 5.7 pCi/l for control locations. Tritium was detected on one sample above the LLD of 330 pCi/l, T-7 3d quarter was 355 pCi/l . Strontium-89 was not detected above the LLD of 1.4 pCi/1. Strontium-90 was not detected in indicator sample above the LLD of 0.6 pCi/1. There were no gamma emitting radionuchdes detected above their respective LLDs in any of the samples collected. All sample analyses were within normal ranges and were similar to results of previous years. Gross Beta Ground water 19821997 8 ~~ i
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 7: Groundwater Monitoring Locations Sample Location Type of Number Location Location Description T-7 I Sand Beach,0.9 miles NW of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station T-54 I Weis Farm,4.8 miles SW of Station T-141 QC Roving Site I = indicator C = control QC = quality control Broad Leaf Vegetation and Fruit Samples Fruits and broad leaf vegetation also represent a direct pathway to humans. Fruits and broad leaf vegetation may become contaminated by deposition of airborne radioactivity (nuclear weapons fallout or airborne releases from nuclear facilities) or from irrigation water drawn from lake water receiving liquid efIluents (from hospitals, nuclear facilities, etc.). Radionuclides from the soil raay be absorbed by the roots of the plants and become incorporated into the edible portions. During l 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. J
]
In 1997, broad leaf vegetation samples were collected at three indicator locations (T-17,T-36 and I T-19) and one control loca' ion (T-37). Fruit samples were collected at two indicator locations (T-8 and T-25) and one cou.;ol locations (T-37). Broad leaf vegetation was collected once a month during the growing season. Broad leaf vegetation collected consisted of cabbage, lettuce, and swiss chard. The fruits collected were apples. All samples were analyzed for gamma emitting radionuclides, strontium-89, strontium-90, and iodine-131. Iodine-131 was not detected above the LLD of 0.041 pCi/g (wet) in any broad leaf vegetation nor above the LLD of 0.015 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 occurring . In both fruit and broad leaf vegetation, strontium-89 was not detected above their l LLDs of 0.001 pCi/g (wet) and 0.008 pCi/g (wet). Strontium-90 (Sr-90) was detected at a concentration of 0.001 pCi/g (wet) for indicator locations and 0.010 pCi/g (wet) for control j locations. In the fruit samples, Sr-90 at location T-8,T-25 (indicator) and T-37 (control) was
<0.001 pCi/g (wet). All results of analyses were similar to results observed in previous years; this demonstrates that the operation of Davis-Besse had no adverse effect on the surrounding environment in 1997.
48
i' i Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Openting Report Table 8: Broad Leaf Vegetation and Fruit Locations Sample Location Type of Number Location Location Description , i T-8 I Moore Farm,2.7 miles WSW of Station I T-17 I J. Sobieralski,1.8 miles SSE of Station T-19 I B. Skinner,1,0 mile 'W of Station T-36 i Allen's Get Away,2.3 miles NW of Station T-37 C Bench Farm,13.0 miles SW of Station T-173 C Firelands Winery, Sandusky,20.0 miles SE of station. 1 = indicator C = control Animal / Wildlife Feed Samples I As with broad leaf vegetation and fmit samples, samples of domestic animal feed, as well as j 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 determining , radionuclide concentration in the food chain. Domestic animals feed samples are collected at two domestic meat-sampling locations. Wildlife feed samples are collected from the Navarre Marsh onsite and from a local marsh within five miles of the Station. As in all terrestrial samples, natu-rally occurring potassium-40, cosmic ray produced radionuclides such as ber/llium-7, and fallout radionuclides from nuclear weapons testing may be present in the feed samples.
. Domestic animal feed was collected annnlly 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.
I t
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49
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report
.. Wildlife feed was collected annually at two locations (T-31 and T-32). The samples consisted of the edible portions of cattails.
Samples were anal:wd for gamma emitting radionuclides. In both the animal and wildlife feed, naturally occurring potassium-40 was detected. Also Be-7 was detected at T-32 ( 2.0i 0.30 )All other radionuclides were below their respective LLDs. The operation of Davis-Besse had no adverse e&ct on the surroundlng environment. Table 9: Animal / Wildlife Feed Locations Sample . Location Type of Number Location Location Description T-31 I Davis-Besse, onsite roving location T-34 C Brooks farm, Graytown 8.8 miles W. of the Station T-197 1 Lochotzki residence 4.0 miles W of the Station Lemon Road T-32 I Toussaint Creek Wildlife Area 4.0 miles WSW of the Station I = indicator C = control Wild and Domestic Meat Samples l Sampling of domestic and wild meat provides information on environmental radionuclide concentrations that humans may be exposed to through an ingestion pathway. The principle pathways for radionuclide contamination of meat animals include deposition of airborne radioactivity on their food and drinking water and contamination of their drinking water from radionuclides released in liquid effluents. The REMP generally collects wild meat and domestic meat (chickens) and eggs on an annual basis. Wild animals cornmonly consumed by residents in the vicinity of Davis-Besse include . waterfowl, 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. l 50 l
1 Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Domestic meat samples were sampled in 1997 as follows: 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. j e Wild Meat: Muskrat samples were not obtained because a perndt for trapper was not issued. Two attempts to trap were unsuccessful.
. Eggs: Eggs were unavailable at both locations at the time of col-lection. T-197 and T-34 did not have any laying chickens.
Table 10: Wild and Domestic Meat Locations Sample Location Type of , Number Location Location Description j j T-31 I Onsite roving location f T-34 C Sager Farm, Graytown Rd, 9.0 miles W of ; the Station 1 T-197 I Lochotzki residence,4.0 miles W of the Station i Lemon Road I = indicator C = control Soil Samples : Soil samples are generally collected twice a year at the sites that are alo equipped with air sam-plers. Only the top layer of soil is sampled in an effort to identify possible trends in the local envi-romnental nuclide concentration caused by atmospheric deposition of fallout and station released 4 radionuclides. Generally, the sites are relatively undisturbed, so that the sample will be represen- ) tative of the actual deposition in the area. Ideally, there should be little or no vegetation present, I because the vegetation could affect the results of analyses. Approximately five pounds of soil are taken from the top two inches'at each site. Many naturally occurring radionuclides such as beryl-lium-7 (Be-7) and potassium-40 (K-40) and fallout radionuclides from nuclear weapons testing are detected. Fallout radionuclides that are often detected include strontium-90 (Sr-90), cesium-137 (Cs-137), cerium-141 (Ce-141) and ruthenium-106 (Ru-106). l 51
Davis-Besse Nuclear Power Stati:n 1997 Annual Radiological Emironmental Operating Report During 1997, 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 controllocations were T-9, T-11, T-12,and T-27. All soil samples were analyzed for gamma emitting radionuclides. The results show that the only gamma emitter detected in addition to naturally occurring Be-7 and K-40, was Cs-137. Cs-137 was found in both indicator and controllocations at average concentrations of 0.25 pCi/g dry and 0.35 pCi/g dry, respectively. The concentrations were similar to that observed in previous years (Figurel5). Cesium 137 in Soll from 1972 to 1997 i
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l Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l : l l i Table 11: Soil Locations ) l f 1
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Number Location Location Description l T-1 I Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station i T-3 1 Site boundary 1.4 miles ESE of Station T-4 I Site boundary 0.8 miles S of Station i l l T-7 I Sand Beach, main entrance,0.9 miles ! NW of Station Moore Farm,2.7 miles WSW of Station I T-8 1 ! 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 mile; WNW of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station I = indicator C = control 53
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I , 1 Davis-Besse Nuclear Power Statisn 1997 Annual Radiological Environmental Operating Report l Aquatic Monitoring Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-off/ soil erosion, and releases of radioactive material in liquid effluents from hospitals or . nuclear 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 radionuclides, either directly from drinking water, or as a result of the transfer of radionuclides through the aquatic food chain with eventual consumption of aquatic organisms, such as fish. To monitor these pathways, Davis-Besse samples treated surface water (drinking water), untreated surface water (lake or river water), fish, and shoreline sediments. l Treated Surface Water j Treated surface water is water from Lake Erie which has been processed for human consumption. Radiochemical analysis of this processed water provides a direct basis for assessing the dose to ; humans from ingestion of drinking water. I Samples of treated surface water were collected from two indicators (T-28 and T-50) and two control locations (T-11 and T-12). These locations include the water treatment facilities for Davis-Besse, Erie Industrial Park, Port Clinton and Toledo. Samples were collected weekly and . composited monthly. The monthly composites were analyzed for beta emitting radionuclides. l The samples were also composited in a quarterly sample and analyzed for strontium-89, l strontium-90, gamma emitting radionuclides, and tritium. One QC sample was collected from a { routine location which was changed each month. j y The annual average for beta emitting radionuclides for indicator and control locations were ; l 2.3 pCi/l and 2.1 pCi/l respectively. These results are similar to previous years as shown in { Figure 19. All tritium samples were less than the LLD of 330 pCi/1. l l l All cesium-137 results were less than the LLD of 10.0 pCi/1. Strontium-89 was not above the l l LLD of 1.2 pCi/1. Strontium 90 was detected up to 0.6 pCill at indicator locations and up to i 0.8 pCi/l.at controllocations. These results are similar to those ofprevious years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse in 1997, i l 1 i
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I 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 D Berse has had no measurable radiological impact on surface water used to make drinking water. Table 12: Treated Surface Water Locations Sample Location Type of I Number Location Location Description ) T-ll C Port Clinton Water Treatment Plant 9.5 miles SE of Station
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T-12 C Toledo Water Treatment Plant 23.5 miles WNW of Station T-28 I Treated Water supply from Davis-Besse site i T-50 1 Erie Industrial Park, Port Clinton,4.5 miles SE ofStation L T-143 QC Quality Control Site I = indicator C = contro! QC = quality control I l f 58
Davis-Besse Nuclear Power Station 1997 Annual Radi logical Emir:nmental Operating Report L Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to L. humans from external exposure from the lake surface as well as immersion in the water. It also L provides information on the radionuclides present which may affect drinking water, fish, and irrigated crops. I Routine Program The routine program is the basic sampling program which is performed year round. Untreated water samples are collected in the areas of the station intake and discharge and at the water intakes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo, Davis-Besse, and Erie Industrial Park. A sample is also collected from Lake Erie at the mouth of the Toussaint River. These samples are collected weekly and composited monthly. The l monthly composite is analyzed for beta emitting radionuclides, tritium, and gamma emitting radionuclides. The samples are further composited quarterly and analyzed for strontium-89 and strontium-90. A QC sample is also collected weekly. It is at a different location each month. I 1 Summer Program I i I l The summer program is designed to supplement the routine untreated water samphng program m ' order to provide a more comprehensive study during the months of high lake recreational activity, such as boating, fishing, and swimming. These samples are 'obtained in areas along the shoreline l of Lake Erie. The samples are collected monthly and analyzed for beta emitting radioactivity, tritium, strontium-89, strontium-90 and gamma emitting radionuclides. For the routine samples composite weekly, the beta emitting radionuclides had an average concentration of 2.8 pCi/l at indicator and 2.6 pCi/l at control locations respectively. The average concentration of beta emitting radionuclides in all samples (include lake water) was 2.96 pCill at both indication and control locations. Of the 130 tritium analyses performed on untreated water,126 were less than the LLD of
- 330 pCi/1. The tritium detected, ranged from a concentration of 340 pCi/l to 575 pCi/1. The l- concentration of tritium detected above the LLD was 575 pCi/l at indication location and 348 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 0.05%
l of the effluent concentration limit of 1,000,000 pCi/l for tritium in an unrestricted area, as provided by 10CFR20, Appendix B, Table 2, column 2. The tritium detected at the control location 'is presumed to come from activities not associated with the operation of Davis-Besse. Cesium-137 and strontium-89 were not detectable in samples of untreated water above their LLDs of 10 pCi/l and 2.4 pCi/l, respectively. Strontium-90 was detected at an average concentration of 0.62 pCi/l at indicator locations. The results of untreated water show that the operation of Davis-Besse had no adverse impact on nearby residents or on the environment. 59 t-
i- Davis-Besse Nuclear Power Station 1997 Annual Radi: logical Environmental Operating Report Gross Beta Concentration in Untreated Surface Water from 1977 to 1997 l 7
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o ' 1977 1978 1979 1980 1981 1982 1983 1984 196$ 1986 1967 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 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 emironment. 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 average concentrations of beta emitting radionuclides detected at the QC location was 3.23 pCi/l and 2.8 pCi/l at routine locations. Tritium and cesium-137 were below their respective LLDs. There was good agreement between the routine and QC locations. I I 60
l Divis-Besse Nuclear Power Station 1997 Annual Radiological Environniental Operating Report I i l Table 13: Untreated Surface Water Locations Sample Location Type of ! Number Location Location Description T-3 I Site boundary,1.4 miles ESE of Station T-11 C Port Clinton Water Treatment Plant,9.5 miles j I SE of Station T C Toledo Water Treatment Plant, sample taken 1 from intake crib,11.25 miles NW of Station i T-28 I Davis-Besse Water Treatment Plant l T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE l ofStation LT-131 I Lake Erie,0.8 miles NE of Station T-132 I- Lake Erie,1.0 miles E of Station T-133 I Lake Erie,0.8 miles N of Station l l T-134 I Lake Erie,1.4 miles NW of Station T-135 I Lake Erie,2.5 miles WNW of Station i T-137 C Lake Erie,5.8 miles WNW of Station l T-145 QC Roving Quality Control Site l , T-152 C Lake Erie,15.6 miles WNW of Station i ! 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 ! l = indicator C = control l
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61
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Shoreline and Bottom Sediment The sampling of shoreline and bottom sediments can provide an indication of the accumulation of undissolved radionuclides which may lead to internal exposure to humans through the ingestion of -fish, through resuspension into drinking. water supplies, or as an external radiation source from ' shoreline exposure to fishermen and swimmers. Samples of deposited sediments in water along the shore were collected at various times from three indicator sites (T-3, T-4, and T-132) and one control location (T-27). Shoreline sediment was collected with a shovel, or a hand held dredge. All samples were analyzed for gamma emit- - ting radionuclides. Naturally occurring potassium-40 was detected at both controls and indicator locations. Table 14: Shoreline and Bottom Sediment Locations
-1 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 j T-132 I Lake Erie,1.0 miles E of Station I = indicator C = control l
62
l I Davis-Besse Nuclear Power Station 1997 Annual Radi: logical Environmental Operating Report i Fish Sample Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondarily 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. j 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 populations would not be expected to be impacted by the Station operation. Walleye are collected because they are a popular sport fish, white perch or white bass because they are an important commercial fish. Carp are collected because they are bottorr. ,eeders and thus would be more likely to be affected by radionuclides deposited in lake sediments. The edible portion of fish were analyzed for beta and gamma emitting radionuclides. The average concentration of beta emitting radionuclides in fish muscle was similar for indicator and controllocations (2.80 pCi/g and 2.91 pCi/g wet weight, respectively). Cesium-137 was not detected above the LLD of 0.017 pCi/g for indicator location, and up to 0.027 pCi/g wet weight at control location. No other gamma emitter were detected above their respective LLDs. j
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l Davis-Besse Nuclear Power Station 1977 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Therrnoluminescent Dosirneters Radionuclides present in the air, and those deposited on the ground, may directly irradiate individuals. Direct radiation levels at and around Davis-Besse are constantly monitored by thermo-luminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information. The TLDs used at Davis-Besse contain a calcium sulfate: dysprosium (CaSO4:Dy) card with four main readout areas. Multiple readout areas are used to ensure the precision of the measurements. Thermoluminescence is a process by which ionizing radiation interacts with phosphor which is the sensitive material in the TLD. Energy is trapped in the TLD material and can be stored for I several months or years. This provides an excellent method to measure the dose received over long periods of time. The energy that was stored in the TLD as a result ofinteraction with radiation is released and measured by a controlled heating process in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy in the form of light. The amount oflight 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 96 % of the quarterly TLDs placed in the field and 89% of the annual TLDs placed in the field were retrieved and evaluated during the current reporting period. In 1997, the average dose equivalent for quarterly TLDs at all indicator locations was 13.5 mrem /91 days, and for all controllocations was 14.1 mrem /91 days. The average dose equivalent for annual TLDs in 1997 was 53.8 mrem /365 days at indicator locations and 59.0 mrem /365 days for control locations. Quahty Control TLDs Duplicate TLDs have been placed at 18 sites. These TLDs were placed in the feld 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 being aware that they are the same. A comparison of the quality control and routine results provides a method to check the accuracy of the measurements. The average dose equivalent at the routine TLDs averaged 13.9 mrem /91 days while the quality control TLDs yielded an average dose equivalent of 13.9 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
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#ffffffffffffffffffffffff Figure 25: The similarity between indicator and control results demonstrated that the operation of Davis-Besse has not caused any abnormal gamma dose.
l NRC TLD Monitoring I l The NRC has 22 TLDs located around Davis-Besse as part of their Direct Monitoring Network Program. Davis-Besse maintains TLDs at all the NRC TLD monitoring sites. The NRC collects their TLDs on a quarterly basis, whereas Davis-Besse collects TLDs quarterly and annuafly 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. The NRC uses Panasonic Model UD801 TLD, which has two elements oflithium borate: copper l (Li2B407: 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 14.112.8 mrem /91 days for the Davis-Besse TLDs and 15.7 2.6 mrem /91 days for the NRC TLDs. As the confidence intervals overlap, there is no statistical difference between the meas-l urements. l l 69
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report NRC vs. Davis Besse Dose 20
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un sus iuo ini un ins un ins un un Date Figure 26: Comparison of NRC and Davis-Besse TLDs i Table 16: ThermolumineScent Dosimeter Locations Sample Location Type of Number Location Location Description T-1 I Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station T-4 1 Site boundary,0.8 miles S of Station T-5 I Site boundary,0.5 miles W of Station T-6 I Site boundary,0.5 miles NNE of Station i T-7 I Sand Beach, main entrance,0.9 miles NW of i 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 70
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table !6: Thermoluminescent Dosimeter Locations (continued)
- l. Sample Location Type of j Number Location Location Description l T-10 I Site boundary,0.5 miles SSW of station near warehouse l T-11 C Port Clinton Water Treatment Plant,9.5 miles j
SE of Station T C Toledo Water Treatment Phnt,23.5 miles WNW of Station T-24 C Sandusky,'21.0 miles SE of Station T-27 C Crane Creek State Park, 5.3 miles WNW of Station l 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 T-43 I Site boundary,0.5 miles SW of Station j 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 1 Site boundary,0.5 miles NW of Station l T-47 1 Site boundary,0.5 miles N of Station T-48 I Site boundary,0.5 miles NE of Station T-49 I Site boundary,0.5 miles NE of Station T-50 I Erie Industrial Park, Port Clinton, 4.5 miles SE of Station T-51 C on Siren Pole, 5.5 miles SSE of Station 71
I l Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report i i Table 16: Thermoluminescent Dosimeter Locations (continued) Sample Location Type of l Number Location Location Description l l 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 l T-60 I Site boundary,0.3 miles S of Station
'T-62 I Site boundary,1.0 mile SE of Station i
T-63 I Site boundary,1.1 miles ESE of Station l l i T-65 I Site boundary,0.3 miles E of Station l T-66 I Site boundary,0.3 miles ENE of Station I 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 l T-71 I Site boundary,0.1 mile NNW of Station - T-73 I Site boundary,0.1 mile WSW of Station T-74 I Site boundary,0.1 mile SSW of Station l T-75 I Site boundary,0.2 mile SSE of Station T-76 I Site boundary,0.1 mile SE of Station T-80 QC Quality Control Site T-81 QC Quality Control Site T-82 QC Quality Control Site T-83 QC Quality Control Site T-84 QC Quality Control Site 72 f l
Davis-Besse Nuclear Power Station 1997 Annual Radiological Enviromnental Operating Repon l l Table 16: Thermoluminescent Dosimeter Locations (continued) l Sample Location Type of
- Number Location Location Description l
T-85 QC Quality Control Site T-86 QC Quality Control Site ! T-88 QC Quality Control Site T-87 QC- Quality Control currently located in lead pig, DBAB annex T-89 QC Quality Control Site T-91 I State Route 2 and Rankie Road,2.5 miles SSE ofStation T-92 I Locust Point Road,2.7 miles WNW of Station T-93 I Twelfth Street, Sand Beach,0.6 miles NNE of Station T-94 I State Route 2,1.8 miles WNW of Station T-95 C- State Route 579,9.3 miles W of Station 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-il4 - QC Quality Control Site T-115 QC Quality Control Site T-116 QC Quality Control Site T-117 QC Quality Control Site T-118 QC Quality Control Site T-l19 QC Quality Control Site T-120 QC Quality Control Sit 73
Davis-Besse N.,acar Power Station 1997 Annual Radi: logical Environmental Operating Report Table 16: ThermolumineScent Dosimeter Locations (continued) Sample 1,0 cation Type of Number Location Location Description T-120 QC Quality Control Site i T-121 I State Route 19,2.0 miles W of Station i T-122 I Duff Washa and Humphrey Road,1.7 miles W ofStation ' T-123 I Zetzer Road,1.6 miles WSW of Station T-124 C Church and Walnut Street, Oak Harbor,6.5 miles SSW of Station T-125 I Behlman and Bier Roads,4.4 miles SSW of Station i T-126 I Camp Perry Western and Toussaint South Road, l 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 ofStation T-151 I State Route 2 and Humphrey Road,1.8 miles WNW of Station T-153 I Leutdoad,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 l T-201 I Sand Beach,1.1 miles NNW of Station T-202 I Sand Beach 0.8 miles NNW of Station 74
i
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Davis-Besse Nuclear Power Station 1997 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 T-205 I Sand Beach,0.5 miles NNE of Station T-206. I Site B mdary,0.6 miles NW of Station T-207 I Site Boundary,0.5 miles N of Station T-208 I Site Boundary,0.5 miles NNE of Station. I = indicator C = control QC = quality control I l
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Divis-Besse Nuclear Power Station t997 Annual Radiological Environmental Operating Report l Conclusion The Radiological Environmental Monitoring Program at Davis-Besse is conducted to determine ; the radiological impact.of the Station's operation on the environment. Radionuclide concentra-tions measured at indicator locations were compared with concentrations measured at control lo-ll cations, in previous operational studies and in the preoperational surveillance program. . These
- . comparisons indicate normal concentrations of radioactivity in all environmental samples collected in 1997, Davis-Besse's operation in 1997 had no adverse impact on the residents and environment
[ surrounding the station.~ The results of the sample analyses performed during the period of Janu-j- _ ary through December 1997 are summarized in Appendix D of this report. l l: l v
- . r i
1 u . I L t-l-
\
l l 79
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report 3 References
- 1. " Cesium-137 from the Environment to Man: Metabolism and Dose," Report No.52, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1977).
- 2. " Environmental Radiation Measurements," Report No.50, National Council on Radiation Protection and Measurement, Washington, D.C. (December 1976).
- 3. " Exposure of the Population in the United States and Canada from Natural Background Ra-diation," Report No.94, National Council on Radiation Protection and Measurement, Wash-ington, D.C. (December 1987). ,
s
- 4. "A Guide for Environmental Radiological Surveillance at U.S. Departmeat of Energy Installa-tions," DOE /EP-0023, Department ofEnergy, Washington, D.C. (July 1981).
- 5. " Ionizing Radiation Exposure of the Population of the United States," Report No.93, Na-tional Council on Radiation Protection and Measurement, Washington, D.C. (September 1987).
- 6. " Natural Background Radiation in the United States," Report No.45, National Council on Radiation Protection and Measurement, Washington, D.C. (November 1975).
- 7. " Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion 'As Low As Reasonably Achievable' for Radioactive 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. (De-cember 1987).
- 10. " Radiological Asxssment: Predicting the Transport , Bioaccumulation and Uptake by Man of Radionuclides Released to the Environment," Report No.76, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1984). [
l1. Regulatory Guide 4.1," Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," US NRC (April 1975).
- 12. Regulatory Guide 4.13, " Performance, Testing, and Procedural Specifications for Thermolu-minescent Dosimetry: Environmental Applications," US NRC (July 1977). }
,- / ;
j l l 1 80 l i
L Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Reprt
- 13. Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operations)- EfIluent Streams and the Environment," US NRC (February 1979). i
- 14. Regulatory Guide 0475, " Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities," US NRC (September 1978). ,
1 1
- 15. Regulatory Guide 0837,"NRC TLD Direct Radiation Monitoring Network," US NRC l (1997).
- 16. " Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, l Part 20 (1993).
- 17. Teledyne Isotopes Midwest Laboratory, " Operational Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No.1, Oak Harbor, OH," Annual Report, Parts I and II (1977 through 1990).
- 18. Teledyne Isotopes Midwest Laboratory," Final Monthly Progress Report to Toledo Edison Company", (1991-1997).
- 19. Teledyne isotopes Midwest Laboratory, "Preoperational Environmental Radiological Moni-toring for the Davis-Besse Power Station Unit No.1", Oak Harbor, OH (1972-1977).
l
- 20. Toledo Edison Company, " Davis-Besse: Nuclear Energy for Northern Ohio."
l ,
- 21. Toledo Edison Company, " Davis-Besse Nuclear Power Station, Unit No.1, Radiological Ef-fluent Technical Specifications," Volume 1, Appendix A to License No. NPF-3. ;
l 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 Enviromnental Monitoring Program," DP-HP-00015.
- 25. Toledo Edison Company, " Radiological Environmental Monitoring Quarterly, Semiannual, and Annual Sampling", DB-HP-03004.
l
- 26. Toledo Edison Company, " Radiological Monitoring Weekly, Semimonthly, and Monthly l Sampling," DB-HP-03005.
- 27. Toledo Edison Company,"REMP Enhancement Sampling," DB-HP-10101.
//
l 81
e-Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report
. 28. Toledo Edison Company," Updated Safety Analysis for the Offsite Radiological Monitoring Program," USAR 11.6, Revision 14,(1992).
- 29. Toledo Edison Company, " Annual Radiological Environmental Operating Report Preparation i and Submittal," DB-HP-00014,
- 30. Toledo Edison Company, Davis-Besse Nuclear Power Station, Offsite Dose Calculation Manual
- 31. *' Tritium in the Envirotunent," Report No. 62, Naticaal Council on Radiation Protection and
' Measurements, Washington,' D.C. (March 1979).
i 1 82
Davis-Besse Nuclear Powcr Station 1997 Annual Radiological Environmenta10perating Report 1 Radioactive Effluent Re_ ease Report January 1 through December 31,1997
- Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm. Roentgen, the potential hazards ofionizing radiation -
1were recognized and efforts were made to establish radiation protection standards. The prin Ary source of rec-ommendations for radiation protection standards within the United States is the National Council on Radiation -
' Protection and Measurement (NCRP). Many .of these recommendations have been given legislative authority - through publication in the Code of Federal Regulations (CFR) by the Nuclear Regulatory Commission (NRC).
The main objective in the control of radiation is to ensure that any dose is kept not only within regulatory limits, but As' Low As Reasonably Achievable (ALARA). The ALARA principle applies to reducing radiation dose both to the individual working at Davis-Besse and to the general public. '" Reasonably achievable" means that exposure reduction is based on sound economic decisions and operating practices. By practicing ALARA, Davis-Besse and Centerior Energy minimize health risk and environmental detriment and ensure that doses are maintained well below regulatory limits. Sources of Radioactivity Released 1
'During the normal operation of a nuclear power station, most of the fission products are retained within the fuel
- and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in the primary coolant svater. The three types of radioactive material released are noble gases, iodine and particulates, and tritium.
The noble gas fission products in the primary coolant are given off as a gas when the coolant is depressurized. Thise gases are then collected by a system designed for gas collection and stored for radioactive decay prior to release. Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primary coolant. system. These liquids are collected through a series of floor and equipment drains and sumps. All liq.
. uids of this nature are monitored and processed, if necessary, prior to release.
. Noble Gas -
Some of the fissio_n products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologically and chemically nonreactive.
/
l 83 L
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an external source of radiation exposure to the body. Xenon-133 and xenon-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive noble gases released. They are readily dis-persed in the atmosphere. l Iodine and Particulates Annual releases of radioisotopes of iodine, and those particulates with half-lives greater than 8 days, in gaseous and liquid emuents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high emciency of gaseous and liquid processing systems, minimize their discharge. The predominant radiciodine released is iodine-131 with a half-life of approximately eight days. The main con-tribution 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., antimony-125 and cesium-137) and activation products (e g., cobalt-58 and cobalt-60). Radioactive cesium and cobalt contribute to internal radia-l tion 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. l Tritium l Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in liquid emuents. It is also present in gaseous emuents. Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium l (also a hydrogen isotope) present in the water and with the boron in the primary coolant. When tritium, in the l form ofwater or water vapor, is ingested or inhaled it is dispersed throughout the body until eliminated. Processing and Menitoring i l Emuents are strictly controlled to ensure radioactivity released to the environment is minimal and does not ex-
)
L ceed regulatory limits. Emuent control includes the operation of monitoring systems, in-plant and environ- l i mental sampling and analyses programs, quality assurance programs for emuent and environmental programs, and procedures covering all aspects of emuent and environmental monitoring. The radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gase-L ous wastes which contain radioactivity. For example, the Waste Gas Decay Tanks are holding tanks which al-low radioactivity in gases to decay prior to release via the station vent. l Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits. These instru-ments 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 automatically stopped. l 84
Davis-Desse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report All wastes are sampled prior to release and analyzed in a laboratory to identify the specific concentrations of ra-dionuclides being released. Sampling and analysis provide a more sensitive and precise method of determining emuent composition t' . with monitoring instruments alone. A meteorological tower is located in the southwest sector of the Station. It is linked to computers which record the meteorological data. Coupled with the emuent release data, the meteorological data are used to calculate the dose to the public. Beyond the plant, devices maintained in conjunction with the Radiological Environmental Monitoring Program constantly sample the air in the surrounding environment. Frequent samples of other environmental media, such as water and vegetation, are also taken to determine if buildup of deposited radioactive material has occurred in the area. Exposure Pathways Radiological exposure pathways derme the methods by which people may become exposed to radioactive mate-rial. 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 environ-mental transport mechanism, and the use of the environment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An Annual average 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 exposure pathways is the use of the environment. Many factors are considered such as dietary intake of resi-dents, recreational use of the area, and the locations of homes and farms in the area. The external and internal exposure pathways considered are shown in Figure 30. The release of radioactive gaseous emuents involves pathways such as external whole body exposure, deposition of radioactive material on plants, deposition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radioactive material in liquid emuents involves pathways such as drinking water, fish consump-tion, and direct exposure from the lake at the shoreline and while swimming. 85
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report r DUuted By Mmosphere Airborne Releases M Animals Mume , IIP'5W8 ..,. g r: .... (Milt. Meat) I* _;ef q
.h.:
Consumed Ilj ' I By Man c.n _ ed By Animals
- u. . -. r Diluted ByLake D Consumed hpde " f 'A e) h RSH l m-v. ..
- gOrinklag Water e
w nr nyv A ;u a sue,,gia, \ l
" Exposure 2
$?; ff.9,w;-
Figure 30: The exposure patinvays shown here, are monitored through the Radiological Environmental Monitoring Program (REMP), and are considered when calcutating doses to the public. Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway _is the exposure pa*hway which will provide, for a specific radionuclide, the greatest dose to a population, or to a specific group of the population, called the critical group. The critical group may vary de-p:nding on the radionuclides involved, the age and diet of the group, or other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ. Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body exposure to radiation involves the exposure of all organs. Most background exposures are of this form. Both non-radioactive and radioactive elements can enter the body through inhalation or ingestion. When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium collects in bone tissue. The total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the amount of time that the radionuclide remains in the organc sonle radionuclides remain for very short times due to their rapid radioactive decay and/or elimination rate from the body, while other radionuclides may remain in the body for longer periods of time. 86
- Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report The dose to the general public in the area surrounding Davis-Besse is calculated for each liquid or gaseous re. I 'le:se. The dose due to radioactive material released in gaseous effluents is calculated using factors such as the ,
amount of radioactive material released, the concentration beyond the site boundary, the average weather con- l ditions at the time of the release, the locations of exposure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation, food consumption). The dose due to radioactive material re- ' leased in liquid effluents is calculated using factors such as the total volume of liquid, the total volume of dilu-tion water, near field dilution, and usage factors (water and fish consumption, shoreline and swimming factors). These calculations produce a conservative estimation of the dose. Results The Radioactive Efiluent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nu-clear Station during the period from January 1,1997 through December 31,-- 1997.
- o - Summation of the quantities of radioactive material released in gaseous and liquid effluents o 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 released in'ef- . fluent was:
Liquid Efiluents:-
. 5.00E-02 mrem, whole body e 5.03E-02 mrem, liver Gaseous Effluents:
Noble Gas: e 2.04E-04 mrad, whole body e' 2.36E-04 mrad, skin - Iodine - 131,133, Tritium, and Particulates with Half-lives greater than 8 Days: e 8.31E-03 mrem, whole body e 1.54E-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 efiluents, these pathways in- - clude the auxiliary feed pump turbine exhausts, the main steam safety valve system and the atmospheric vent valve system, steam packing exhaust and main feed water. For liquid effluents, the additional pathways include the Turbine Building drains via the settling basins. Releases via these pathways are included in the normal re-lease tables in this report. 87
Davis-Besse Nuclear Power Station 1997 Annual Radiologicel Environmental Operating Repon Regulatory Limits-Gaseous Effluents In accordance with Offsite Dose Calculation Manual, dose rates due to radioactivity released in gaseous efflu-L ents from the site to areas at'and beyond the site boundary shall be limited to the following:
- 1. ; Noble gases:
- Rekased at a talg equal to or less than 500 mrem TEDE per year. (Note: the 1qtal des due to these releases is also limited to 50 mrem in any calendar year.)
e Released at a Ialg such that the total dose to the skin will be less than or equal to 3000 mrem in a year. lodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 ' days: e ' Released at a rate such that the total dose to any organ will be less than or equal to 1500 mrem in l a year. In accordance with 10CFR50,' Appendix I, Sec. IIB.1, air dose due to radioactivity released in gaseous effluents !: to areas at and beyond the site boundary shall be limited to the following:
- Less than or equal to 5 mrad total for._ gamma ' radiation and less than or' equal to 10 mrad total for beta radiation in"any calendar quarter.
- Less than or equal to 10 mrad total for gamma radiation and less than or equal to 20 mrad total for beta radiation in any calendar year.
'In accordance with 10CFR50, Appendix I, Sec. IIC, dose to a member of the public from Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas -
at and beyond the site boundary shall be !imited to the following:
. Less than or equal to 7.5 mrem total to eny organ in any calendar quaner.
- Less than or equal to '15 total mrem to any organ in any calendar year.
l. L l i 1 88
1
' Davis-Besse Nuclear Power Station 1997 Annual Radiologic $1 Environmental Operating Report Liquid Efiluents In accordane with 10CFR50, Appendix I, Sec IIA, the dose or dose commitment to a member _of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to accumulated doses of:
- Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ in any calendar quarter.
~
- 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 emuents 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 j IE-05 uCi/ml of air (submersion dose) converted to an equivalent concentration in water as discussed in the In ' > ternational 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 activation 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
~
i skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive - Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable. Measurements of Total Activity Fission and Activation Gases: i These gases, excluding tritium, are collected in a marinelli beaker specially modified for gas sampling, steel j flasks, or glass vials and are counted on a germanium detector for principal gamma emitters. Radionuclides that l are detected are quantified via gamma spectroscopy. l i Tritium gas is collected using a bubbler apparatus and counted by liquid scintillation. Iodine Iodine is collected on a charcoal cartridge filter and counted on a germanium detector. Specific quantification i of each iodine radionuclide is via gamma spectroscopy. Particulates Particulates are collected on filter paper and counted on a germanium detector. Specific quantification of each radionuclide present on the filter paper is via gamma spectroscopy. l l 89 i
f Davis-Besse Nuclear Power Station 1997 Annual Radiological EnvironmentIl Operating Report Liquid Efiluents 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 1/1/97 through 12/31/97
- 1. Number of batch releases: 63 5 2. Total ti:ne period for the batch releases: 99.3 hours
- 3. Maximum time period for a batch release: 207 minutes
- 4. Minimum time period for a batch release: 67 minutes
- 5. Average time period for a batch release: 94 minutes Gaseous from 1/1/97 through 12/31/97 j
- 1. Number of batch releases: 9 I
- 2. Total time period for the batch releases: 137 hours i
- 3. Maximum time period for a batch release: 2530 minutes
- 4. Minimum time period for a batch rdease: 197 minutes
- 5. Average time period for batch release: 913 minutes Abnormal Releases
- 1. Reactor trip of 5-4-97. One OTSG relief valve did not reset.
- 2. Auxiliary steam 235 relief valve lifted twice for 4 seconds in June.
Percent of ODCM Release Limits < The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in per-cent oflimits, for January 1,1997 through December 31,1997. PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1,1997 - December 31,1997 (gaseous) Noble gases (gamma) 2.04E-04 mrad 10 mrad 2.04E-03 Noble gases (beta) 2.36E-04 mrad 20 mrad 1.18E-03 I-131, tritium and particulates 8.31E-03 mrem 15 mrem 5.54E-02 Report Period: January 1,1997 - December 31,1997 (liquid) Total body 5.00E-02 mrem 3 mrem 1.67E+00 Organ 5.03E-02 mrem 10 mrem 5.03E-01 90
'I l
i Davis-Besse Nuclear Power Station 1997. Annual Radiological Environmental Operating Report ) Sources ofInput Data Water Usage: Survey of Water Treatment Plants (DSR-95-00347)
= 0-50 mile meat, milk, vegetable production, and population data: '1982 Annual Environmental -
' Operating Report ' entitled, " Evaluation of Compliance with Appendix I to 10CFR50 Updated Population, Agricultural, Meat - Animal, and Milk Production Data Tables for 1982." This evaluation was based on the 1980 census; the Agricultural Ministry of Ontario 1980 report enti-
^
tied " Agricultural Statistics and Livestock Marketing Account,1980"; the' Agricultural Ministry L' 'of Ontario 1980 report entitled " Agricultural Statistics for' Ontario - 1980 Publication 21,1980"; i the Michigan Department of Agriculture, July,1981 report entitled " Michigan Agricultural Sta-
- j. tistics,1981"; the Ohio Crop Reporting Service,1981 report entitled, " Ohio Agricultural Statis-
!' tics,1981." r !~ . Gaseous and liquid source terms:. Tables 17 through 21 of this report. j e ' Location of the nearest individuals and pathways by sector out to 5 miles, see Land Use Census j Section of the report. J 1
. 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 Emuent Release Report includes an assessment of ra-diation doses from radioactivity released in liquid and gaseous emuents to members of the public due to activi-ties inside the site boundary. I l
In special instances, members of the public are permitted access to the Radiologically Restridted Area within the Davis-Besse Station.- Tours for the public are conducted with the assurance that no individual will receive any ' appreciable' dose due to radioactivity released in gaseous or liquid emuents (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 Consid-ering 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 L ODCM Section 7.2, the following exposure assumptions are used:
L
. Exposure time for maximally-exposed visitors is 250 hours (I hr/ day, 5 day / week, 50 wk/yr)
- Annual average meteorological dispersion (conservative, default use of maximum site boundary l
dispersion). _For direct " shine" from the Independent Spent Fuel Storage Installation (ISFSI), default use of the maximum dose rate for a completed (full) ISFSI, and a distance of 950 feet. j The' equations in the ODCM may be used for calculating the potential dose to a member of the public for activi- i ties inside the site boundary; Based on these assumptions, this dose would be at lea'st a factor of 35 less than ! th3 maximum site boundary air dose as calculated in the ODCM. There are no areas onsite accessible to the < j
; public where exposure to liquid emuents could occur. Therefore, the modeling of the ODCM conservatively i estimates the maximum potential dose to members of the public.
l-91
i i Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Inoperable Radioactive Effluent Monitoring Equipment l 1 - The following radioactive effluent monitoring equipment required to be operable by ODCM Section 2.1 and 3.1 f was inoperable for more than 30 days during this reporting period. 1 o RE 8433 was out of service from 0101-97 until 10-07-97. Underground cable repair was needed. j o Total Dilution Flow, computer point F201, was unavailable for most of 1997. This was due to problems with - dilution pump discharge actual flow vs. pump curve data and design of flow transmitter, During the time F201 was inoperable, total dilution was estimated using other methods. o RE 4686 (storm sewer) was out of service for five months due to various problems (clogged suction, pump and cable problems). Changes to the ODCM and PCP There were no changes to the PCP and one change to the ODCM (Revision 11.0). 92
i Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l'
- Table 17 l Gaseous Effluents - Summation of All Releases
! Est. Total l_ Type Unit 1st Qtr 2ndQtr 3rd Qtr 4th Qtr % Error 1997 1997 1997 1997 4 Fission and Activation Gases TotalRelease Ci LLD 4.48E+00 LLD 2.24E-02 2.5E+01 l . Average Release Rate for Period
- Ci/sec LLD 5.68E-01 LLD 2.82E-03
- Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section Iodines Totallodines Ci 1.4IE-06 1.89E-05 4.53E-07 6.49E-06 2.5E+01 l Average Release Rate for Period' Ci/sec 1.79E-07 2.40E-06 5.75E-08 8.23E-07 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section Particulates l Particulates with half-lives Ci LLD 1.22E-05 LLD LLD 2.5E+01 greater than 8 days Average Release Rate for Period' Ci/sec LLD 1.55E-06. LLD LLD Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section Tritium Total Release Ci 6.42E+00 8.29E+00 4.92E+00 5.42E+00 2.5E+01 -
' Average Release Rate for Period' Ci/sec 8.14E-01 1.05EH)0 6.24E-01 6.87E-01 ,
1 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section i
- The average release rate is taken over the entire quarter. It is NOT averaged over tie time period of the releases.
93
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l Table 18 Gaseous Effluents - Ground Level Releases Batch Mode
- l 1st Qtr '
2nd Qtr- 3rd Qtr 4th Qtr l Nuclide Unit 1997 1997 1997 1997 Fissiin Gases - Ci 6
. Kr-85 LLD 6 LLD6 LLD LLD
Kr-85m LLD LLD LLD LLD I Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xe-135 LLD LLD LLD LLD Xc-135m LLD LLD LLD LLD
' Xe-138 LLD LLD LLD LLD Total for Period: N/A N/A < N/A N/A
-lodines Ci
'I-131 LLD LLD LLD LLD 1-132 LLD LLD LLD LLD l133 LLD LLD LLD LLD j 1-135 LLD LLD LLD LLD Totil for Period: N/A N/A N/A' N/A Pirticulates and Tritium Ci H-3 1.59E-02 1.54E-02 5.09E-03 9.73E-03 Sr-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD LLD LLD Ba-140 LLD LLD LLD LLD
. Co-58 LLD LLD LLD LLD l
Total for Period: 1.59E-02 1.54E-02 5.09E-03 9.73E-03,- l 94 l
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report 3 1 Table 18 (Continued) Gaseous Efiluents - Ground Level Releases j l Continuous Mode
- I 1
ist Qtr 2nd Qtr 3rd Qtr 4th Qtr l Nuclide Unit 1997 1997 1997 i997 i j Fission Gases Ci . Kr-85 LLD 6 LLD 6 LLD6 LLD' . Kr-85m LLD LLD LLD LLD
]
Kr-87 LLD LLD LLD LLD i Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xe-135 LLD LLD LLD LLD Xe-135m LLD LLD LLD LLD Xe-138 LLQ LLD LLD LLD Total for Period: N/A N/A N/A N/A lodines Ci 1-131 LLD LLD LLD LLD I133 LLD LLD LLD LLD l-135 LLD LLD LLD LLD j i Totti for Period: N/A N/A N/A N/A - Perticulates and Tritium Ci H-3 3.68E-01 1.llE-01 9.16E-02 2.04E-01 Sr-89 LLD LLD LLD LLD St-90 LLD LLD LLD LLD Cs-134 - LLD LLD LLD LLD Cs-137 LLD LLD LLD LD Ba-140 LL,Q LLD LLD LLD Tctal for Period: 3.68E-01 1.1lE-01 9.16E-02 2.04E-01
/ ,
95
1 i Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report
)
Table 18 (Continued) Gaseous Effluents - Ground Level Releases Continuous and Batch Mode l Ar-41: <2.2E-08 Ci/ml 1 Kr-85: <6.2E-06 Ci/ml Kr-85m: <2.0E-08 pCi/ml Kr-87; <3.4E-08 Ci/ml , Kr-88: <4.0E Ci/ml Xe-131m: <9.0E-08 Ci/ml Xe-133: <4.6E-08 Ci/ml i Xe-133m: <l.6E-07 Ci/ml - Xc-135: <l .9E-08 Ci/m! Xe-135m:- <4.0E-07 Ci/ml j Xe-138: <2.5E-07 Ci/ml i
'l-131: <l.0E-07 Ci/ml 1-133: <2. lE-08 Ci/ml 1-135: <2. lE-08 Ci/ml Mn-54 ' <2.0E-08 Ci/mi Fe-59: <4.0E-08 Ci/ml Co-58: <3.0E-08 Ci/ml Co-60: <2.0E-08 pCi/ml Zn-65: <4.0E-08 Ci/ml Mo-99: <2.0E-07 Ci/ml Cs-134: <2. lE-08 Ci/mi Cs-137: <3.0E-08 Ci/ml Ce-141: <3.0E-08 Ci/ml Ce-144: <l.2E-07 pCi/ml Ba-140: <7.0E-08 Ci/ml La-140: <3.0E-08 Ci/ml Sr-89: <5.0E-08 Ci/ml St-90: <6.0E-09 Ci/ml I. a Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, AVV Testing, and Auxiliary Boiler Outage Release are listed as batch releases.
- b. These radionuelides were not identified in concentrations above the lower limit of detection (LLD).
c ' Atmospheric Vent Valve weepage and Steam Packing Exhaust are continuous releases. i 96
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 19 Gaseous Efiluents - Mixed Mode Releases Batch Mode I l 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1997 1997 1997 1997 1 i Fission Gases Ar-41 Ci LLD b 2.17E-02 LLD b LLDb Kr-85 Ci LLD 2.45E+00 LLD LLD b Kr-85m Ci LLD LLD LLD 1.46E-04 Kr-87 Ci LLD LLD LLD 1.90E-05 Kr-88 Ci LLD LLD LLD 1.14E-04 Xe-133 . Ci LLD 1.91E+00 LLD 1.50E-02 l Xe 133m Ci LLD 1.68E-02 LLD 4.27E-04 Xc-135 Ci LLD LLD LLD 6.69E-03
. Xe-135m Ci LLD LLD LLD LLD Xe-138 Ci LLD LD LLD LLD Xe-131m Ci LLD LLD Totil for Period: LLD 4.40E+00 LLD 2.24E-02 *lodines I 131 Ci LLD LLD LLD LLD I-132 Ci LLD LLD LLD LLD I-133 Ci LLD LLD LLD LLD I-135 Ci LLD LLD LLD LLD Tot:1 for Period: Ci LLD LLD LLD LLD *P;rticulates H3 Ci LLD 6.42E-01 1.68E-03 1.59E-03 Totl for Period: Ci LLD 6.42E-01 1.68E-03 1.59E-03 l
f
- Release ofiodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Station Vent) i 97
Davis-Besse ' Nuclear Power Station 1997 Annual Radiological Environmental Operating Report [ Table 19 (Continued) Gaseous Efiluents - Mixed Mode Releases l Continuous Mode l l 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr i Nuclide Unit 1997 1997 1997 1997
- Fission Gases i
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 LLD LLD LLD LLD Xe-133m Ci LLD LLD LLD LLD l Xe-135 Ci LLD 8.39E-02 LLD LLD i Xe-135m Ci LLD LLD LLD LLD Xe-138 Ci LLD LLD LLD LLD l Total for Period: LLD 8.39E-02 LLD LLD lodines I-131 Ci 1.41E-06 7.48E-06 4.53E-07 6.49E-06 I-133 Ci LLD 1.14E-05 LLD LLD I-135 Ci LLD LLD LLD LLD Total for Period: 1.41E-06 1.89E-05 4.53E-07 6.49E-06 Particulates and Tritium H-3 Ci 5.39E+00 7.52E+00 4.82E+00 5.20E+00 6 Sr-89 # Ci LLD LLD LLD LLD 6 Sr-90 # Ci LLD LLD LLD LLD Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci LLD 2.24E-06 LLD LLD Ba-140 Ci LLD LLD LLD LLD l Co-58 Ci LLD 4.91E-06 LLD LLD l La-140 Ci LLD LLD LLD LLD Total for Period: 5.39E+00 7.52E+00 4.82E+00 5.20E+00 98
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Rcport i I Table 19 (Continued) l Gaseous Effluents - Mixed-Mode Releases Continuous Mode' Batch Mode' Ar-41 <2.9E-08 Ci/ml Kr-87 <4.5E-06 pCi/ml Kr-85 <3.3E-06 Ci/ml Kr-88 <6.6E-06 Ci/ml-Kr-85m < l .3 E-08 pCi/ml Xe-135 < l .4E-05 Ci/ml Kr-87 <6.0E-08 Ci/ml Xe-135m <2. l E-06 Ci/ml Kr-88 <6.0E-08 Ci/ml Xe-138 <2.8E-05 Ci/ml Xe-131m <4.4E-07 Ar-41 l Ci/ml < l .8E-06 Ci/ml Xe-133m <7.2E-08 pCi/ml Kr-85m < l .2E-06 { Ci/ml Xe-135 <l.lE-08 Ci/ml Xc-133 <2.4E-06 pCi/ml Xe-135m <5.9E-06 Ci/mi X: 33m <l.0E-05 pCi/ml Xe-138 <2.0E-05 Ci/mi I-135* <3.9E-10 Ci/ml Mn-54* <2.6E- 14 Ci/ml Fe-59* <3.0E-14 Ci/ml Co-58' <3.0E-14 Ci/ml Co-60* <2.5E-14 Ci/ml Zn-65* <l.0E-13 Ci/ml Mo-99* <1.8E-14 Ci/ml Cs-134' <l .6E-14 Ci/ml Cs-137* <l .3E-14 pCi/ml Ce-141* <l .2E-13 Ci/ml Ce-144' <l .2E-14 Ci/ml Ba-140* <4.0E-14 Ci/ml La-140* <l .0E-14 Ci/ml 6 Sr-89 '* <9.3 E-16 Ci/ml 6 Sr-90 <3. lE-16 Ci/ml a These radionuclides were not identified in every quarter in concentrations above the lower limit of detection (LLD). The largest LLD value is listed. b Quarterly composite sample for continuous mode, c Analysis not required for batch release. 99
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f l Davis-Besse Nuclear Powcr Station 1997 Annual Radiological Environmental Operating Report ! I Table 21 l l Liquid Effluents - Nuclides Released Batch Releases Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1997 1997 1997 1997 Fission and Activation Products Co-58 Ci 1.32E-04 1.93E-04 3.17E-05 1.42E-05 Co-60 Ci 5.62E-05 1.43E-04 1.01E-04 2.03E-04 Ag-110m Ci 6.46E-05 6.26E-05 5.88E-06 6.78E-05 Sb-125 Ci 3.42E-03 1.53E-03 7.67E-05 2.08E-04 Cs-134 Ci 4.83E-06 5.55E-06 2.01E-06 1.89E-06 Cs-137 Ci 4.82E-05 9.46E-05 3.12E-05 3.15E-05 S r-8 9 ' Ci LLD' LLD* LLD' LLD' Sr-90* 6 Ci LLD LLD LLD LLD Fe-55 Ci LLD 4.28E-04 LLD LLD Cr-51 Ci 6.32E-05 3.97E-06 LLD LLD ' I-133 Ci LLD LLD LLD LLD
'I-131 Ci LLD LLD LLD LLD l-132 Ci LLD LLD LLD LLD Te-132 Ci LLD LLD LLD LLD Tc-99m Ci LLD LLD LLD LLD Sb-124 Ci 7.51E-06 LLD LLD LLD Sn-113 Ci 1.23E-06 LLD 5.66E-07 LLD Ru-103 Ci LLD LLD LLD LLD Mn-54 Ci LLD 1.39E-06 LLD LLD Np-239 Ci LLD LLD LLD LLD Co Ci 4.91E-07 4.19E-06 1.21E-06 1.38E-06 Nb-95 Ci LLD LLD LLD LLD Zr-95 Ci LLD LLD LLD LLD Se-75 Ci LLD LLD LLD LLD Fe-59 Ci LLD LLD LLD LLD Zn-65 Ci LLD LLD LLD LLD Ce-144 Ci LLD LLD LLD LLD Na-24 Ci LLD LLD LLD LLD Zr-97 Ci LLD LLD LLD LLD Ce-141 Ci LLD LLD 1.53E-07 LLD
. Total for Period: Ci 3.80E-03 2.48E-03 2.52E-04 5.28E-04 l <" ,
101
Davis-Besse Nuclear Powtr Stttion 1997 Annual Radiological Environmental Operating Report Table 21 (continued) Liquid Effluents - Nuclides Released l Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1997 1997 1997 1997 Tritium Ci 7.68E+01 1.77E+02 3.66E+01 4.08E+01 Dissolved and Entrained Gases l l Kr-85m Ci LLD' LLD' LLD' LLD' Kr-85 Ci LLD LLD LLD LLD Xe-131m Ci LLD LLD LLD LLD Xe-133 Ci LLD 3.70E-04 2.22E-06 2.26E-06 Xe-135 Ci LLD LLD 2.04E-06 LLD Xe-133m Ci LLD LLD LLD LLD Total for Period: Ci 7.69E+01 1.77E+02 3.66E+01 4.40E+01 l j 1 I 102
I 1 Davis-Besse Nucley Power Station 1997 Annual Radiological Environmental Operating Report Table 21 (continued) Liquid Efiluents - Nuclides Released Continuous Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 1997 1997 1997 1997 Fission and Activation Products Cr-51 Ci LLD' LLD* LLD' LLD' Fe-59 Ci LLD LLD LLD LLD Co-58 Ci LLD LLD LLD LLD ; Co-60 Ci LLD LLD LLD LLD { Zn-65 Ci LLD LLD LLD LLD l Sr-89* 6 Ci LLD LLD Il D LLD l Sr-906 LLD Ci LLD LLD LLD Nb-95 Ci LLD LLD LLD LLD Zr-95 Ci LLD LLD LLD LLD l Mo-99 Ci LLD LLD LLD LLD Tc-99m Ci LLD LLD LLD LLD I-131 Ci LLD LLD LLD LLD Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci LLD LLD LLD LLD Ba-140/La-140 Ci LLD LLD LLD LLD Ce-141 Ci LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A Tritium Ci 7.93E-01 2.68E-01 1.57E-01 3.59E-01 Dissolved and Entrained Gases Kr-85 Ci LLD LLD LLD LLD Xe-131m Ci LLD LLD LLD LLD Xe-133 Ci LLD LLD LLD LLD Xe-133m Ci LLD LLD LLD LLD Xe-135 Ci LLD LLD LLD LLD Total for Period: Ci N16 N/A N/A N/A 103
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report i Table 21 (continued) l Liquid Effluents - Nuclides Released
- Na-24 <2.0E-08 Ci/mi Sb-124 <1.0E-08 Ci/ml Cr-51 <l.7E-07 Ci/ml. Sb-125 <l.7E-08 Ci/ml Mn-54 - <2. l E-08 Ci/ml Te-132 <l .8E-08 6 Ci/ml
- Fe-55 <7.0E-07 . Ci/ml Ce-141 <3.0E-08 Ci/ml Fe-59 <4.2E-08 Ci/mi Ce-144 <l .7E-07 Ci/ml Co <l .6E-08 Ci/ml Cs-134 <2.1 E-08 Ci/ml Co-58 <l .9E-08 Ci/ml Ce-136 <2.8E-08 Ci/ml Co-60 . <2.5E-08 Ci/ml Cs-137 <2.7E-08 Ci/ml Zn-65 <5.2E-08 Ci/ml Ba-140
<7.0E Ci/ml Se-75 <2.4E-08 Ci/ml La-140 <3.0E-08 6 Ci/ml Sr-89 <3.0E-08 Ci/ml Np-239 <l .2E-07 6 Ci/mi Sr-90 <8.0E-09 Ci/ml I-131 <2.5E-08 Ci/ml
. Zr-95 <4.0E-08 Ci/mi I-132 <l.0E-08 Ci/ml Zr-97 <2.5E-08 Ci/ml I-133 . <2.1E-08 Ci/ml Nb-95 <2.1E-08 Ci/ml I-135 < l .7E-07 Ci/ml Mo-99 <l .6E Ci/ml Kr-85 <6.2E-06 Ci/ml l Tc-99m <1.8E-08 Ci/mi Xe-131 <7.7E-07 Ci/ml Ru-103 <2.2E-08 Ci/ml Xe-133 <4.6E-08 ~ Ci/ml Ag-110m <2.5E-08 Ci/ml Xe-133m <l .6E-07 pCi/ml Sn-113 <2.8E-08 Ci/ml Xe-135 <l .9E-08 Ci/ml
- These radionuchdes 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.
6 Quarterly composite sample l 1 L l l i 104 I
I 1 \- l 1 i Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l l Table 22: Solid Waste and Irradiated Fuel Shipments j l l ! A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
\
- l. 12-month Est. Total
- 1. Type of Waste ]
Unit Period Error, % 3 {
- a. Spent resins, filter sludges, m 2.00E+01 2.5 E+01 I evaporator bottoms, etc. Ci 1.34E+00 2.5E+01 f 3
- b. Dry compressible waste, m 2.19E+01 2.5 E+01 )
contaminated equip., etc. Ci 5.80E-02 2.5E+01 i c. Irradiated components, control m' rods, etc. Ci N/A N/A j l
- d. Others: dewatered primary m' 1.50E-01 2.5E+01 system cartridge filters Ci 9.80E-02 2.5 E+01
{ l
- 2. Estimate of major nuclide composition (by type of waste) '
Est. Total Tvoe Percent (%) Error. %
- a. Spent Resins Fe" 2.07E+01 2.50E+01 {
Co" 7.76E+00 2.50E+01 ) Co' l.53E+01 2.50E+01 ! Ni'3 3.28E+01 2.50E+01 i25 Sb 2.12E+00 2.50E+01 Cs"* 2.75E+00 2.50E+01 Cs'" 8.54E+00 2.50E+01 C" 6.66E+00 2.50E+01
- b. Dry compressible waste, contaminated equipment, etc. Fe" 1.57E+01 2.50E+01 l Co' 9.91 E+00 2.50E+01 I Ni'3 7.10E+00 2.50E+01 Cs"* 4.40E+00 2.50E+01 Cs'" 1.72E+01 2.50E+01 Co" 4.00E+01 2.50E+01 C" 3.40E+00 2.50E+01
- c. None
- d. Cartridge filters Fe" 4.77E+00 2.50E+01 H' l.30E+00 2.50E+01 Co" 1.60E+01 2.50E+01 Ni 9.80E+00 2.50E+01 Cs"* 2.76E+01 2.50E+01 Cs'" 5.90E+00 2.50E+01 I
Co' l.10E+01 2.50E+01 C" 6.55E+00 2.50E+01 i25 l Sb 4.12E+00 2.5E+01 l Ag " '" 1.54E+00 2.5E+01 105
)
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Rgort l ,
- Table 22 (continued) j Solid Waste and Irradiated Fuel Shipments !
l
- 3. Solid Waste Disposition 1 Number of Shipments: 1 Mode of Transportation: Truck i Destination: Barnwell, SC ]
Type of Container (Container Volume): I resin / filter media HIC ( 5.72 m') buried I Number of Shipments: 2 Mode of Transportation: Truck l Destination: American Ecology - Oak Ridge, TN Type of Container (Container Volume): a. Metal box ofdry contaminated waste ( 21.9 m') @ Envirocare of Utah for burial i i Number of Shipments: 1 Mode cf Transportation: Truck Destination: Manufacturing Sciences Corp. - Oak Ridge, TN Type of Container (Container Volume): a. 3 Metal liners ( 14.46 m') of secondary resin for burial @ Envirocare of Utah B. IRRADIATED FUELSHIPMENTS There were no shipments ofirradiated fuel. 1 . 1 106
Davis-Besse Nuclear Power Station ' 1997 Annual Radiological Environmental Operating Report Table 23 Doses Due to Gaseous Releases For January through December 1997 i Maximum Individual Dose Due to I-131, II-3 and Particulates with IIalf-Lives Greater than 8 days. Whole Body Dose 8.31E-03 mrem Significant Organ Dose 1.54E-02 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 2.04E-04 mrem Skin Dose 2.36E-04 mrem Population Dose Due to I-131, II-3 and Particulates with IIalf-Lives Greater than 8 days. Total Integrated Population Dose' 5,75E-03 person-rem Average Dose to Individual in Population 2.64E-06 mrem Population Dose Due to Noble Gas TotalIntegrated Population Dose 6.42E-05 person-rem Average Dose to Individualin Population 2.95E-08 mrem w 107
Davis-Bessa Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 24 Doses Due to Liquid Releases for January through December 1997 Maximum Individual Whole Body Dose 5.00E-02 mrem Maximum Individual Significant Organ Dose 5.03E-02 mrem Population Dose Total Integrated Population Dose 4.59E-01 person-rem Average Dose to Individual 2.11E-04 mrem , 108
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report 1 Table 25 1 Annual Dose to the Most Exposed Member of the Public 1997 ANNUAL DOSE 40CFR190 LlhilT PERCENT OF (mrem) (mrem) Lih11T Whole Body Dose Noble Gas 2.04E-04 Iodine, Tritium, Particulates 8.31E-03 l Liquid 5.00E-02 1 TotalWhole Body Dose 5.85E-02 25 2.34E-01 Thyroid Dose Iodine, Tritium, Particulates 1.54E-02 75 2.05E-02 Skin Dose Noble Gas 2.36E-04 25 9.44E-04 l l Significant Organ Dose (Liver) 5.03E-02 25 2.01E-01 Meteorological Data Meteorological data on 3'/2 inch microdisk for January through December 31,1997, has been submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555.
~
109
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental' Operating Report Land.Use Census Program Design Each year a Land Use Census is conducted by Davis-Besse in order to update information neces-sary to estimate radiation dose to the general public and to determine if any modifications are nec-i essary to the Radiological Environmental Monitoring Program. The Land Use Census is required by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis-Besse Nuclear Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use Census Data. The Land Use Census identifies gaseous pathways by which radioactive material may reach the general population around Davis-Besse. The information gathered during the Land Use Cen-sus for dose assessment and input into the REMP ensure these programs are as current as possi-ble. The pathways of concern are listed below: Inhalation Pathway - Internal exposure as a result of breathing radionuclides car-ried in the air.
. Ground Exposure Pathway - External exposure from radionuclides deposited on the ground f
- Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.
Vegetation Pathway - Internal exposure as a result of eating vegetables, fmit, etc. which have a build up of deposited radioactive material or which have absorbed radionuclides through the soil. " Milk Pathway - Internal exposure as a result of drinking milk which may co,ntain radioactive material as a result of a cow or goat grazing on a pasture contaminated by radionuclides. Methodology The Land Use Census consists of recording and mapping the locations of the closest residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) in each , meteorological sector within a five mile radius of Davis-Besse. The surveillance portion of the 1997 Land Use Census was performed during the month of July.
. In order to gather as much information as possible, the locations of residences, dairy co' w s, dairy goats, and vegetable gardens were recorded. The residences, vegetable gardens, and milk animals are used in the dose assessment program. The vegetable gardens must be at least 500 square feet in size, with at least 20% of the vegetables being green leafy plants (such as lettuce, cabbage, and kale) .
/
Each residence is tabulated as being an inhalation pathway, as well as ground and plume exposure 7 pathways. Each garden is tabulated as a vegetation pathway. 110
Davir-Besse Nuclear Power Station 1997 Annual RadioGogical Environmental Operating Report All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 nun-ute series of the relevant quadrangles) which has been divided into 16 equal sectors corresponding ) to the 16 cardinal compass points (Figure 31). The closest residence, milk animal, and vegetable l garden in each sector are determined by measuring the distance from each to the station vent at Davis-Besse. Results l The following changes in the pathways were recorded in the 1997 census: j ( - SSW Sector - The garden at 1220 meters was replaced by a garden at 3450 me-ters. 4
. SW Sector- The garden at 4130 meters was replaced by a garden at 5140 meters, j e - WSW Sector - The garden at 4270 meters was replaced with a garden at 7010 meters.
. WSW Sector - The removal of the goat.
. WNW Sector -The garden at 2900 meters was replaced by a garden at 3650 me-ters.
. NW - The resident at 1100 meters was replaced by a resident at 1450 meters.
The critical receptor identified by the 1997 Land Use Census is a garden in the W sector at 1640 meters from Davis-Besse. The detailed list in Table 26 was used to update the database of the effluent dispersion model used in dose calculations. ' Table 26 is divided by sectors and lists the distance (in meters) of the clpsest pathway in each meteorological sector. Table 27 provided information on pathways, ' critical age group, atmospheric dispersion (X/Q) and deposition (D/Q) parametars for each' sector. This information is used to update the Offsite Dose Calculation ManuJ (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and in calcu-- lating liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. l 1
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Repon I Table 26 Closest Exposure Pathways PreSent in 1997 Sector Distance from Station (meters) Closest Pathways i N 880 Inhalation l Ground Exposure Plume Exposure L-NNE 870 Inhalation I Ground Exposure Plume Exposure NE 900 Inhalatica l Ground Exposure Plume Exposure ENE, E, ESE, SE N/A Located over Lake Erie SSE 2010 Inhalation Ground Exposure Plume Exposure SSE 2820 Vegetation S 1070 Inhalation . Ground Exposure Plume Exposure S 3440 Vegetation SSW 980 Inhalation Ground Exposure Plume Exposure SSW" 3450 Vegetation SW 1050 Inhalation Ground Exposure Plume Exposure 1 SW" ' I 5140 Vegetation f l
** Changes since 1996
- l 113 !
1 l Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Reprt Table 26 (continued) ! Closest Exposure Pathways Present in 1997- ] 1 Secto- Distance from Station (meters) Closest Pathways WSW 1620 Inhalation I Ground Exposure Plume Exposure I WSW*
- 7010 Vegetation ;
l W 980 Inhalation l Ground Exposure Plume Exposure 1 W 1640 Vegetation l WNW 1730 Inhalation Ground Exposure Plume Exposure l WNW *
- 3650 Vegetation NW *
- 1450 Inhalation Ground Exposure Plume Exposure NW 2320 Vegetation l
NNW 1210 Inhalation Ground Exposure Plume Exposure ! ** Changes since 1996 l s t I 114
)
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Repon l Table 27 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) l Parameters l SFCTOR METERS CRITICAL AGE X/Q D/Q PATIIWAY GROUP (SEC/M ) 3 (M-2) l
- N 880 Inhalation Child 9.15E-07 8.40E-09 l NNE 870 Inhalation Child 1.27E-06 1.47E-08 l NE 900 Inhalation Child 1.26E-06 1.58E-08 ENE* - --- -- -- --
E* --- --- --- --- --- 1 ESE* - - - -- - 1 SE* -- - --- - -- l SSE 2820 Vegetation Child 7.02E-08 8.36E-10 S 3440 Vegetation Child 4.39E-08 4'55E-10 SSW*
- 3450 Vegetation Child 3.98E-08 5.llE-10 SW*
- 5140 Vegetation Child 3.88E-08 3.45E-10 WSW*
- 7010 Vegetation Child 3.60E-08 2.03E-10 l
W 1640 Vegetation Child 2.69E-07 4.21E-09 WNW*
- 3650 Vegetation Child 5.67E-08 4.28E-10 NW 2320 Vegetation Child 6.91E-08 5.70E-10 NNW 1210 Inhalation Child 2.70E-07 1.92E-09 since these sectors are located over marsh areas and Lake Erie, no ingestion pathwaysyre present.
" Changes since 1996. WSW was changed to Vegetation from Goat.
t 115
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Oprating Report
. Meteorological Monitoring ll Introduction (
j The Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory j 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 Specifica'tions 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 ri 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. Aner extensive statistical comparative research the meteorological personnel have found no impact upon local climate or short term weather patterns. The Meteorological Monitoring Program also provides data that can be used by many other groups and programs: Radiological Environmental Monitoring Program, The Emergency Prepar-edness Program, The Environmental & Safety Unit , and groups such as Plant Operations, Plant , Security, Materials Management, Industrial Safety Program, Toledo and Cleveland Service Dis- : patch, Legal Affairs, plant personnel and members of the surrounding community. I l The Radiological Environmental Monitoring Program uses meteorological data to aid in evaluat-ing the radiological impact, if any, of radioactivity released in Station effluents. The meteorologi-cal data is used to evalcate radiological environmental monitoring sites to assure the program is as current as possible. The Emergency Preparedness Program uses meteorological data to calculate ] emergency dose scencrios for emergency drills and exercises and uses weather data to plan evacuations or station isolation during adverse weather. The Environmental & Safety Unit uses meteorological data for chemical spill response activities, marsh management studies, and waste water outfall flow calculations. Plant Operations uses meteorological data for cooling tower efli-ciency calculations, forebay water level availability and plant work which needs certain environ-mental conditions to be met before work begins. Plant Security utilizes weather data in their rou-tine planning and activities. Materials Management plans certain plant shipments around adverse weather conditions to avoid high winds and precipitation which would cause delays in material deliveries and safety concerns. Industrial Safety uses weather and climatological data to advise _ personnel of unsafe working conditions due to environmental conditions, providing a safer place to work. Legal Affairs uses climatological data for their investigation into adverse weather acci-dents to the plant and personnel.
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116
Davis-Besse Nuclear Power Station 1997 Annual Radiologicti Environmental Operating Repon On-site Meteorological Monitoring System Description ,
'I
- At Davis-Besse'there are two meteorological systems, a primary and a backup. They are both ,
housed in separate environmentally controlled buildings with independent power supplies. Both ! primary and backup systems have been analyzed to be " statistically identical" to the other so if one ..
- system fails the other can take its place. The instrumentation of each system follows:
PRIMARY BACKLP
.100 Meter Wind Speed 100 Meter Wind Speed 75 Meter Wind Speed 75 Meter Wind Speed )
10 Meter Wind Speed '10 Meter Wind Speed j 100 Meter Wm' d Direction 100 Meter Wind Direction ! 75 Meter Wind Direction , 75 Meter Wind Direction - , 10 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 100 Meter Delta Temperature ,
.75 Meter Delta Temperature 75 Meter Delta Temperature ' 'l
- 10 Meter Ambient Temperature 10 Meter Ambient Temperature l 10 Meter Dew Point 10 Meter Solar Insolation-Precipitation MeteorologicalInstrumentation 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 2,000 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 bimiacet:
for wind speed and wind direction at 100 m and 75 m. The 100 m tower also measures differen-tial temperature (delta Ts): 100-10 m and 75-10 m. The 10 m tower has instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the 10 m tower. According to the Davis-Besse Nuclear Power Station Operating License, Appendix A, Technical Specification, a minimum of six instmments are required to be operable at the two lower levels (75 m and 10 m) to measure temperature, wind speed, and wind direction. During 1997, annual data recovery for all required instmments were 97.7 percent. Minor losses of data occurred dur-ing routine instrument maintenance, calibration, and data validation. i
/
International Great Lakes Data - 1955 7 . l ( j
. Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Repon Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly. Data is reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required. Tower instrumentation maintenance and semiannual calibrations are per-
- formed by in-house facilities and an outside consulting firm. These instruments are wind tunnel
' tested to assure compliance with applicable regulations and plant specifications.
l Meteorological Data Handling and Reduction Each meteorological system, primary and backup, have two Campbell Scientific Dataloggers l
'(model 21XL) assigned to them. The primary system has a first datalogger to communicate 900 l second averages to the control room via a Digital 11/84 and VAX computer system. This is a j 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 utilize ~d by the control room. ! Each datalogger has its own dedicated communication link with battery backup. The backup l meteorological system is daigned the same as the primary; so to lose all meteorological data the ! primary and backup meteorological systems would have to lose all four dataloggers. However, this would be difficult since each is powered by a different power supply and equipped with light-
-ning and_ surge protection, plus four independent communication lines and datalogger battery .
backup. ) The data from the primary and backup meteorological systems are stored in a 30-day circular _i l storage module with permanent storage held by the Digital VAX computer. Data goes back to - i 1988 in this format and to 1968 in both' digital and hardcopy formats. All data points are scruti-
- nized every 900. seconds by meteorological statistics programs mnning continuously. These are then reviewed by meteorological personnel daily for validity based on actual weather conditions.
A monthly review is performed using 21 NRC computer codes which statistically analyze all data l points for their availability and validity If questionable data on the primary system can not be l 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 l l- format for a permanent record of meteorological conditions. i Joint Frequency Distributions and Wind Sector Graphics Summary statistics and Joint Frequency Distributions (JFDs) of wind and stability data are gener-y ated and the results are reviewed for consistency in terms of known site characteristic and re-L gional climate. The end result of the review process is a validated final database suitable for use by atmospheric dispersion models and for site meteorological characterizations. Wm' d Sector Graphics represent the frequency of wind direction by sector and the wind speed in MPH by sec-l tor. This data is used by the NRC to better understand local wind patterns as they relate to de-l fined past climatological wind patterns as reported in Davis-Besse's " Updated Safety Analysis Re-port".
/
9 118 E_
- Davis-Besse Nuclear Power Station - 1997 Annual Radi
- logical Environmental Operating Report Meteorological Data Summaries This section presents summaries of the' meteorological data collected from the on-site monitoring I program at Davis-Besse during 1996. Tables 28 through 30, discussed in this section, can be i found on pages 122 through 141.
. Wind Speed and Wind Direction The maximum wind speeds for 1997 were 55.65 mph for the 100m level on Febmary 27, 53.16 mph for the 75m level on February 27, and 41.62 mph for the 10m level on February 27. Figures 32-34 give an annual sector graphic of average wind speed and percent frequency by direction-measured at the three monitoring levels. Each wind sector graphic has two radial bars, the darker bar represents the percent of time the wind blew from that direction. The hatched bar represents the average speed of the wind from that direction. Wind direction sectors are classified using r
Pasquill Stabilities. Calms (less than or equal to 1.0 mph) are shown in percent in the middle of (- the wind sector graphic. l Ambient and Differential Temperatures , Monthly average, minimum and maximum ambient temperatures for 1997 are given in Table 29. I ~ These data are measured at the 10m level;'with differential temperatures taken from 100m and 75m levels.' The yearly average ambient temperature for 1997 was 49.30 F. The maximum tem-
']
perature was 91.33 F on June 25 with the minimum temperature of -2.41 F on January 04.- ' Yearly average differential temperatures were -0.48 F(100m), and -0.33 F(75m). Maximum dif-- ferential temperatures for 100m and 75m levels were 7.99 F on December 20 (100m), and 7.99 F on December 20 (75m). Minimum differential temperatures for 100m and 75m levels were - 3.46 F on April 28 (100m) and -2.86*F on October 20 (75m). Differential temperatures are a l measurement of atmospheric stability and used to calculate radioactive plume dispersions based ) on the Gaussian Plume Models of continuous effluent releases. Dew Point Temperatures and Relative Humidity i Monthly average and extreme dew point and humidity temperatures for 1997 are provided in Ta-ble 29. These data are measured at the 10 meter level. The average dew point temperature was 41.24 F 'with a maximum dew point temperature of 76.70 F on July 14. Please note that dew point temperatures above 75*F are highly suspect and are possibly due to calm winds and high j solar heating allowing the aspirated dew point processor to retain heat. The minimum dew point i (dew point under 32 F is frost point) temperature was -4.62 F on January 4. Average relative humidity was 76.39 percent for the year. The maximum relative humidity was 100.00 percent on December 26.. The minimum relative humidity was 4.11 percent on July 26. 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.
l I19 l t
i
' Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report ;
Precipitation l Monthly totals and extremes of precipitation at Davis-Besse for 1997 are given in Table 29. Total l precipitation for the year was 32.0 inches. The maximum monthly precipitation total was 5.76 j l inches in June. The minimum was 0.74 inches recorded in October. It is likely that precipitation j
- totals recorded in colder months are somewhat less than actual due to snow / sleet blowing across
j the collection unit rather than accumulating in the gauge. I Lake Breeze and Lake Level Monitoring
)
Lake Breeze is monitored at Davis-Besse because ofits potential to cause major atmospheric / ; dispersion problems during an unlikely radioactive release. A lake breeze event occurs during the j daytime, usually during the summer, where the land surface heats up faster than the water, and ) therefore reaches higher temperatures than the water. The warmer air above the land rises faster because it is less dense than the cooler air over the lake. This leads to rising air currents over the land with descending denser air over the lake. This starts a wind circulation, which draws air from the water to the land during the daytime, creating a " Lake Breeze" effect. This event could i l be problematic if a release were to occur because diffusion would be slow thus creating an ad-l verse atmosphere to the surrounding site. 1 Lake and forebay levels are monitored at Davis-Besse to observe, evaluate, predict and dissemi-nate high or low lake level information. This data is critical in the running of the plant due to the large amounts of water needed to cool plant components. If water levels get too low the plant operators can take measures for the safe shut down of the plant. Since Lake Erie is the shallowest lake in the Great Lakes, it is not uncommon for a plus or minus five foot lake level fluctuation to occur within an eight to ten hour period. High water levels also effect the plant due to emergency transportation and evacuation pathways. l l l I s 4 120
i i' Davis-Besse Nuclear Power Stati:n 1997 Annual Radi+. logical Envir:nmental Operating Report i 1 I l l This page intentionally left blank. ; i I I 121
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 30 Joint Frequency Distribution by Stability Class
"* * '" CAV13-It33t try!103Mg3?AL COMPLIANCS UNIT '88 e es)g. jag.gg PAgg 31 P1001AN: JTD ft1310s: 777-1,9 Tint of DAtt 09:57:25 """" nAvt3-st$st 15-10 at, s0 sACsUt *""*"
CATA lit!0D ttAMIItD: 1/ 1/ 97- 12/ ll/ 91 sit! :D!attritt: 91 us Aggggs us STABILITT CIA 33 A STA3ILiff 8AstD 08: DELTA T stivttX 250.9 AfD 15.0 ttt? VIIe ntA3UltD AT: 35,0 rttt FIED TX125I0LD AT: 1.00 API J0!NT37!!D fi!QUtXCT DISTRIBUTICE Of WIND sit!D AND DIntCTION II 20013 At 35.00 ftt? (MfM) N ##8 31 EEE t CSE $$ 351 3 33V SW W3W W WW EW NNW TOTAL CAla 1.01- 3.49 0 8 0 0 7 0 4 4 4 3.50- 7.43 0 0 0 0
$ 5 0 0 t 0 0 t t i 1 4 1 0 1 1.50-12.49 4 4 0 0 0 0 0 3 3 ( 21 4 1 6 0 12.50-10.45 0 1 1 2 0 1 2 0 3 4 19 2 31 0 0 8 9 11.50-24.49 0 0 0 1 1 0 0 0 2 0 19 1 35 0 0 6 6
>24.49 4 0 4 0 0 4 0 0 0 0 0 0 0 1 5 6 6 0 0 0 1 0 0 0 0 1 tofAL 13 4 1 0 0 1 0 0 1 1 2 8 5 17 42 14 100 STASIL!ff IA$tD CI: t!LTA T STA61 Lift class 3 IITVtrX 250.0 AND 35.0 ft!T VIED MtA3Ut3D AT: 35.0 ttt!
WIID TI12330LD AT: 1.00 APE J0!IT$1880FitGUINCf DISTRIBUTION Of WIfD SPIID AfD O!!!CTIC# IN 00U13 Af 35.04 tt!T (KFIl t NIE It 181 5 331 58 331 3 33W $W WSW W WEV NW BW TOTA!. CALM - 1.81- 3.49 0 0 0 0 0 t t i 1 0 0 0 3.50- 7.($ 3 7 0 0 0 0 0 2 0 0 t i 1 0 1 1 7.50-12 (! 5 0 ( 0 0 1 1 2 0 28 12.50-14.41 1 1 1 *4 s 1 3 i ( 5 3 3 1 8 20 ft 18.50-24.49 2 4 2 e t 4 4 1 2 5 0 0 4 1 4 4 4 0 0 5 2 7 2 98
>20.49 4 0 1 3 0 2 0 15 0 4 4 0 t t t t 0 0 4
1 0 0 0 0 1 total 11 8 14 0 4 2 0 1 2 5 11 13 14 4 15 34 150 137 I
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 30 (continued) Joint Frequency Distribution by Stability Class
"* * "* 0A7!$-3t335 Eff!10EMI3fAL COMPLIMCI n!? "* * "30-JM-f 8 FAGF 92
?!ME Of DAT: 09:57:25 F10GIM: JTD ?!!3105: F17-1.0
"""" uits-us3r 15-Is of, so utut """" stft IDerf!rtta: $1 DATA Fra!00 IIMINID: 1/ 1/ 17- 12/ 31/ 97 su ggAL ese 87181LIff class C STASILiff SA3tO 08: DELTA T $1TWIII 250.0 UD 35.0 Ttt?
W110 stA3nto AT: 15.0 tttt WIID TI18380LD Af: 1.00 MPE J0!If f!!QUtXCT DI$f11Hf!03 Of VIED 8 PEED MD 9t!!Cf!05 II lons 1r 35.00 FItt 87 TID (178) E fut 33 tst t tst sg sst 3 333 sv vsv v v3W sw 35v TOTAL CALM 1.01 3.41 0 t i 7 2 8 1 e 1 e t 0 0 0 0 e i 4 3.56- 7.49 11 12 3 2 3 4 4 2 7 6 2 1 2 0 6 11 76 7.50-12.49 11 ( 18 12 12 4 2 4 4 11 11 11 4 1 il 23 Ill 12.50-18.49 3 7 13 19 3 e e 0 0 0 4 14 13 9 14 18.50 24.41 5 104 e 2 4 2 2 0 0 I ', 4 4 3 2 8 6 6 1 lo
>24.4) 8 0 0 0 0 e e i e i 2 7 0 0 t i 3 70fAL li li 26 36 20 4 6 3 11 18 38 41 31 16 30 to 318 ff181L!ff CLA33 3 3718!LIff IAstD 04: DitfA f S!fVIII 250.8 UD 35.0 ftt?
VIND R!A3HtD Af t 35.0 ftt? VIND 7811130L0 AT: 1.00 RPI JOINT F1tQEMCf DI5ftllOf!05 of ViaD sitD AfD Dit3CTIoa 12 50R3 Af 35.40 titt JPIED (xFs) : us at Ett I t3s st sst s s3v sv vsv v av sv an TOTAL CALn 1.81- 3.49 3 1 M 3.56 7.41 5 5 8 8 8 4 5 4 it . ( 5 7 5 1 ill 45 54 (5 til 123 (4 54 il 52 15 36 7.50-12.49 51 55 23 29 32 1841 76 103 145 !!2 146 61 31 36 48 151 17( 215 139 78 71 17 1719 12.54-16.49 55 122 131 il 10 3 1 4 3 48 178 273 106 (1 13 74 1343 18.5f-24.49 5 22 22 38 18 0 t I i 13 95 135 35 li 18 6 417 114.49 9 9 2 3 4 0 8 8 0 1 46 43 1 1 e i 11 total 114 310 316 144 100 104 423 363 111 306 Set 131 3t1 193 204 216 4741 138 l
Davis-Besse Nucleaf Power Station 1997 Annual Radislogical Erwironmental Operating Report Table 30 (continued) Joint Frequency Distribution by Stability Class
'" * '" OAT!3-5C33! IST!!0WIITAL CONF!.IANCE UI!! en e ujg.ygg.gg pagg g)
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$Ptt0 (NFI) I IRC 53 III 1 ISI $t $$t 3 $3W $W V3V W W3W IW IW TOTAL CALn 7
' !.01- 3.49 4 5 18 1 11 25 18 29 41 25 17 18 12 9 1 3 241 3.50- 7.49 13 !! 11 41 56 44 12 70 69 135 115 45 72 29 20 13 994 1.5e-12.49 5 14 II (1 52 19 20 23 40 114 143 107 77 28 21 26 816 12.50 18.49 1 9 13 7 11 5 3 1 18 55 72 31 11 14 11 1 289 18.50-24.49 0 1 0 3 0 1 0 0 0 7 30 19 2 3 2 1 69 124.49 0 0 0 0 0 0 0 0 0 0 3 2 0 0 0 0 5 total 29 40 de 105 134 114 113 143 188 456 340 244 114 83 61 46 2410 STAIIL!ff CLk33 r STA81 Lift Bast 0 08: DELTA f StfWits 250.0 AND 35.0 titt VIID MEA 3vitD Af: 35.0 fttf VIED ft1!33010 at: 1.00 EPs JOINT fitQt!3CT DISTR 18Df!08 Of VIND Iftt0 AND O!AICf!0518 EQUIS Af 35.00 ftti SPCtB (MPfl 5 Ett It ist t (St St 338 ' .3 $$W $W W3V W WW W NW TOTAL CALM i 1.01- 3.49 1 -1 2 1 2 1 1 25 43 45 22 13 7 3 2 1 116 3.50 . 7.49 -0 1 4 9 16 13 15 36 53 $$ 11 40 22 5 4 1 1.50-12.49 1- 0 0 2 5 1 1 0 2 4 10 3 5 1 1 0 , 31136 12.50-18.41 0 0 0 1 0 0 0 0 0 0 1 1 1 1 1 0 8 18.50-24.49 0 0 0 0 0 0 0 0 0 0 2 2 0 0 0 0 4
>24.49 0 0 0 0 0 0 0' 4 0 0 0 0 0 0 0 0 0 TotAA 1 2 6 13 23 15 23 61 94 144 112 59 35 10 4 2 613 139
Davis-Besse Nuclear Power Stathn 1997 Annual Raditgical Environmental Operating Report Table 30 (continued) Joint Frequency Distribution by Stability Class
*" * "* OAV13-88338 fff!10fM1GTAL COMPLIANCE tut? "* * "30-JAM-16 FAGE $4 racotAn Jr0 Trastos: r77-1.0 ftxt er DAT: 09:51:15 """" carts-et3st ?$-10 of, s0 ACEvr """" sit! 10tattritti 31 81TA 781!00 t!AMINED: 1/ 1/ 91 = 12/ 31/ 91 su gat ase STASILITT CLASS 4 STASILITT BASED 081 DELTA T StTWtts 250.0 AND 35.0 rit?
W1uD K1A30 TID AT: 35.0 fttf WIND TER!sICL3 Aft 1.00 MPE JOINTSPttD TREQUENCT 813fRI57T!05 0F W!#D $P!!D AND 011tCTION IN E0V13 AT 35.00 f tt? (NPS) # 333 at  8 Est $3 ist 8 $3W SW W3W W WW 4 Ant atW TOTAL CALA 1.01- 3.49 0 0 0 0 0 2 1 2 21 22 i 21 13 2 0 450 7.43 0 0 0 2 5 4 6 9 21 53 42 6 4 1 0 05 0 0 0 149 1.50 12.49 8 0 0 0 0 4 0 0 0 0 0 1 0 0 0 0 5 12.50-14.49 0 0 0 6 4 0 0 4 0 0 6 4 0 4 9 8 9 10.50-24.49 0 4 0 0 0 0 8 0 0 0 0 0 0 0 0 0 0 224.49 0 0 0 0 0 0 0 0 0 0 0 0 8 0 0 0 0 total 0 4 0 2 5 le 1 11 43 75 43 20 i 1 0 0 240 STASILITT CLASS ALL STASILITT SA18D Oui OtLTA Y 8tTVttu 250.0 Asp 35.0 f t!T WIID MEA 3VatD AT: 35.0 fttT WIND TEtt$50LD AT: 1.00 378 J013TSPEED T1200tICT D!$fR18UT!05 0F W13D 87859 AND DISECT!05 IN ECUA3 AT 35.00 rttT (MPE) N NME $$ III 138 $$ E 333 3 $$W 3W WSW W WWW NW ENW TOTAL CALM 1.01- 3.45 8 17 25 14 21 36 7 34 85 111 too 10 44 26 26 15 11 621 3.50- 1.49 81- 90 45 ' 181 203 113 145 188 234 435 1.50-12.49 102 123 324 191 158 61 64 11 2684 179 240 211 100 it . 45 35 345 362 12.56-18.45 60 140 351 237 123 128 170 2905 141 119 94 0 4 11 11 let 154 131 130 102 135 L1 till 18.50-24.49 5 25 28 42 le 0 1 0 t 20 130 183 to 21 Il 13 530
>24.49 0 0 2 3 4 0 0 0 8 1 53 54 1 1 0 0 111 TOTAL 264 7 444 541 7 ' 314 243 lif 461 Tili T 1130 604 324 360 344 T
)
140
Davis-Besse Nuclear Power Station 1997 Annual Radi: logical Environmental operating Report Table 30 (continued) Joint Frequency Distribution by Stability Class
"* * "* DAfts-St338 tyt!80sME8tAL ContLIANCt is!T "*
* "38-JAN-98 PAGE 95 F1048AM: JfD TIMt Of CAf t 09:51:25 VitS208: f77-1.1 .
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$1TC 10tE11Fitti 91 BATA Pt1Ic0 EIAXI8tD 1/ 1/ 97 - 12/ 31/ 11 8 ese gyggAL en STA8!LITT 51520 05: 9tLTA f StfVits 250.1 AND 35.9 ftti VINS REA39tto AT: 33.0 fttf VIND TEAT 3E0LD Att 1.00 375 Total HNatt Of 04318?ATIOE3 4160 TOTAL 39N8tt of TALIf,088ttfAf!0851 8616 TOTAL 80M8t1 of N1881MO 088ttTAf!0ES: 144 f t1CEff DATA 1tC0ftt! FOR 7513 7811001 98.4 %
MtA5 VIND SFtto FOR ft?S 781100: 16.0 NFE TOTAL DM8tt of 08311TAf!0ES V!ft BACIVP CATA: 0 ItaCttfAGE OCC91At#CE of STA81LITY CLA5313 A 8 C D ! f G 1.25 1.14 4.39 54.6) 24.09 1.11 2,19 DI57118UT108 of VIED 011tCT!08 T3 87A8111TT 5 EMt El Ett t ($1 5t $58 8 $$V SV V3V V VNV EV BNV CALM A 13 6 2 8 e 1 9 e 1 1 2 4 5 11 42 16 4 5 11 8 14 4 4 2 0 1 2 5 11 13 14 4 15 34 4 C 25 il 26 36 20 8 6 3 11 11 38 41 31 16 30 40 0 D 184 318 314 423 363 144 100 les 114 366 549 731 341 193 244 216 1 3 29 40 60 185 134 134 113 143 Ill 458 300 266 114 43 61 46 8 7 2 2 6 13 23 15 23 61 94 144 112 59 35 to 8 2 4 e e e t 2 5 le 1 11 43 15 63 to 4 1 0 0 1 TOTAL 264 395 484 541 553 118 til 321 til 1945 till 1134 600 321 360 348 1 141
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report t l Land and. Wetlands Management l Navaire 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 Wildlife Service and Toledo Edison. Navarre Marsh is divided into three pools (units). The pools are separated from Lake Erie and each other by a series of dikes and revetments. Toledo Edison is 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 i control and to encourage beach formation. Revetments are built with a gradual slope which ! cau: s '.vaves to dissipate their energy when they strike the revetment. This encourages beach j fon n x through passive deposition of sediment. A dike is a retaining structure designed to hold j baci wrts for the purpose of flood control and to aid in managing wetland habitat. When used I as a marsh management tool, dikes aid in controlling water levels in order to obtain desired j vegetation and animal species. Manipulating water levels is one of the most important marsh management tools used in Navarre Marsh. Three major types of wetland communities exist in Navarre Marsh, the freshwater marsh, swamp forest, and wet meadow. Also, there exists a narrow dry beach ridge along the lake front with a sand bar extending out into Lake Erie. All these areas provide essential food, shelter, and nesting habitat as well as a resting area for j migratory birds. Davis-Besse personnel combine their efforts with a number of conservation agencies and , organizations. Including the Ottawa National Wildlife Refuge, the Ohio Department of Natural l Resources (ODNR), and the Black Swamp Bird Observatory to preserve and enhance existing habitat, to gain knowledge through research, and to help educate the public about the importance ! of preserving wetlands. 1 With its location along two major migratory flyway, the Navarre Marsh serves as a refuge for a variety of birds in both the spring and the fall, where they rest and find nourishment before continuing on theirjourney. The Black Swamp Bird Observatory captures, examines, bands, catalogues, and releases songbirds in the marsh during these periods. Navarre is also home to wildlife that is typical of much of the marshland in this area, including deer, fox, coyote, muskrats, rabbits, woodchucks, hawks, owls, ducks, geese, herons, snakes and turtles. For the first time in recent history, a pair of mature American Bald Eagles chose the Navarre Marsh as their nesting site in late 1994, and fledged a healthy eaglet in July,1995. The young eagle was one of record 38 eaglets fledged in Ohio in 1996. The nest blew down in a storm in August of 1996, and State and Federal wildlife oflicials and Davis-Besse employees constructed an artificial nesting platform. The eagles used the nest during 1996 and 1997 breeding season but failed to produce any young. 142
- Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report 1
Goose banding took place in June, and was conducted in cooperation with the ODNR and the l 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 in 1996 and again in 1997 in observance ofInternational Migratory Bird Day. Hundreds of members of the public took part in shuttle van l 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. Bach w l the Wild, Inc., a licensed animal rehabilitatorjoined the activities and brought several live admals as part of the program. A twenty-year anniversary celebration at Davis-Besse also featured shuttle van tours through the marsh for about 400 people in August of 1997. l Ohio's third Federal Junior Duck Stamp Art Contest was hosted by Davis-Besse. Young Ohio artists in grades K-12 submitted nearly 800 entries in four separate age brackets. The Junior Duck Stamp Art Contest - designed to teach conservation through the arts and give students a chance to experience the beauty and diversity of wildlife. A total of 101 ribbons were awarded to young Ohio artists, with the state Best of Show entry submitted to Washington, D.C. to compete in the national contest with all other state best-of-show entries. The winner of this competition will be used to make this year's Junior Duck Stamp. Davis-Besse also hosted a Volunteer Eagle Watchers Worksnop. Training was given to over 80 l volunteers who will be observing Ohio's expanding eagle population during the current breeding I and nesting season. l 1 l s. 143
l Davis-Besse Nuclear Power Station 1997 Annual Radiological Emironmental Operating Report i 1 Water Treatment Water Treatment Plant Operation Description The Davis-Besse Nuclear Power Station uses Lake Erie as a water source for its water treatment plant. The lake water is treated with chlorine, lime, and other chemicals to 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. The Ohio Environmental Protection Agency (OEPA) and the Ohio Department of Health monitor operation of the water treatment plant. The operation of the facility is reviewed by a Public Water Supply certified operator. Activities at the water treatment plant are conducted in compliance with the Safe Drinking Water Act and the regulations for public water supply as set forth by the OEPA. Monthly operational reports, required by the OEPA, are completed by Toledo Edison personnel and submitted to the agency. These reports contain sample dates and analytical results, which are compared to standards established by the OEPA. Operational data are also reviewed for compli-ance with the limits set by the OEPA. As a further means of monitoring water quality, drinking water is sampled annually for pesticides, herbicides, heavy metals (such as chromium, arsenic, mercury, lead) and quarterly certain organic chemicals. The health and safety of the water treat-ment plant operators and other site personnel is ensured through weekly housekeeping inspections of the facility. Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which will remove debris greater than one-halfinch in size. The water is then pumped to chlorine de-tention tanks. Next the water passes through one of two clarifiers. Davis-Besse uses upflow i clarifiers, or precipitators, to remove sediment, organic debris, and dissolved agents from the raw j water prior to filtration. Clarifiers combine the conventional treatment steps of coagulation, floc- i culation, 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 conglom-erate particles to mass together further. Finally, during sedimentation, large conglomerate parti-cles settle to the bottom of the clarifier. These processes normally require large separate tanks. However, the use of clarifiers saves both space and the manpower needed to operate the treat- i ment plant. 144
1 Davis Besse Nuclear Power Station 1997 Annual lladiological Environmental Operating Report fuW WATEA l sO C v -h _
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3Y5 ttu W l Figure 38: At Davis-Besse, raw water is drawn into the water treatment plant and processed to make drinking water and water for plant systems. After the clarifier, the water goes through a flow-splitting box, which equally divides the water flow to the Automatic Valveless Gravity Filters (AVGF). These AVGFs consist of a 50:50 ratio l of anthracite to filter sand. During this filtration process, suspended matter is removed from the water by the anthracite and sand media. This filtering reduces the turbidity and odor and im-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 systems, including firewater, demineralized wa-ter, and also drinking water. - Summary of 1997 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 l The plant receives all ofits water from an intake system from Lake Erie. Zebra mussels can se-verely impact the availability of water for plant processes. Dreissenapolymorpha, commonly known as the zebra mussel, is a native European bivalve that was accidentally introduced into North American waters in 1986 and was discovered in Lake Erie in i989. Zebra mussels are pro-lific breeders that rapidly colonize an area by secreting byssal threads that enable them to attach to soli 4 surfaces and to each other. Because of their ability to attach in this inanner,,they may form layers several inches deep. This poses a problem to facilities that rely on water intakea from Lake ~ Erie because mussels may attach to the intake stmetures and restrict water flow. 145
I Davis-Besse Nuclear Power Station 1997 Annual Radi:1:gical Environmental Operating Report Zebra mussels have not yet caused any significant problems at Davis-Besse, but mussds 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 j canal). j i Mussels have also been found on the trash racks, and the intake bay' #3 walls prior to the I traveling screens. These mussels are periodically cleaned using high pressure water. Davis-Besse uses continuous low level chlorination of the intake bays to control the mussels. The mussel population appears to be leveling off or declining. This is likely due to the increasing clarityof Lake Erie. As the food source for the zebra mussels decline, mussel population declines correspondingly. Wastewater Treatment Plant Operation The wastewater treatment plant (WWTP) operation is supervised by a state Certified Wastewater Operator. Wastewater generated by site personnel is treated at an onsite extended aeration package 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 stations, enters the facility and is distributed to the surge tanks of the treatment plants I I The wastewater is then pumped into the aeration tanks. Here, organic materials are digested by microorganisms which are provided with a source of oxygen. This is accomplished through the j use of blowers. The mixture of organics, microorganisms, and decomposed wastes is called ; activated sludge. The treated wastewater settles in a clarifier, and the clear liquid passes over a i weir, leaving the plant by an effluent trough. The activated sludge contains the organisms necessary for continued treatment, and is pumped back to the front of the plant to digest more incoming wastewater. The effluent leaving the plant is disinfected with chlorine and is pumped to thewastewater treatment basin (NPDES Outfall 601) where further treatment takes place. Summary of 1997 Wastewater Treatment Plant Operations Wastewater treatment plant (WWTP) number 1 is currently being renovated. The paint is being reapplied, wiring replaced and a new roofinstalled. This will greatly improved the facility's operability and appearance. 146
Davis-Besse Nuc1 car Power Stati:n 1997 Annual Radiological Environmental Optrating Report 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 l Elimination System (NPDES) permit, number 2IB00011
- FD. Parameters such as chlorine, 1 i
suspended solids and pH are monitored under the NPDES permit. Toledo Edison personnel I l prepare 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: l Outfall 001 Collection Box: At a point representative of discharge to Lake Erie. Source of Wastes: Low volume wastes (Outfalls 601 and 602), circulation water system blowdown and service water.
)
l Outfall 002 l l Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water mnoff, circulating water pump house sumps. , l Outfall 003 Screenwash Catch Basin: Outfall to Navarre Marsh. Source Of Wastes: Wash debris from water intake screens. I Outfall 601 Wastewater Plant Tertiary Treatment Basin: Discharge from wastewater treatment l system. Sources Of Wastes: Wastewater Treatment Facility.
- Outfall 602 Low volume wastes: Discharge from settling basins.
Sources of wastes: Water treatment residues, condensate polishing holdup tank decant, and
- condenser pit sumps.
Sampling Point 801 Intake Temperature: Intake water prior to cooling operation. 147
- Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report 1997 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 residual
, chlorine, copper, lead, and zinc. Many of these new parameters are a result of the Great Lakes Water Quality Initiative. The trend in the future permits will be further increased monitoring.
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l I Divis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Chemical Waste Management Introduction l 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 managed and disposed ofin accordance with all applicable state and federal regulations. Waste Management Resource Conservation and Recovery Act t The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid hazardous 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 human 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 management 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 generates, transports, stores, treats, or disposes of hazardous waste is subject to regulation under RCRA. Under RCRA, there are essentially three categories of waste generators:
- Large quantity Generators - A facility which generates 1000 kilograms / month
{ (2200 lbs month ) or more. i l e Small quantity Generators - A facility which generates less than 1000 kilograms / ) month (2200 lbs/ month). !
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- Conditionally Exempt Small Quantity Generators - A facility which generates less than l 100 kilograms / month (220 lbs/ month).
In 1997, the Davis-Besse Nuclear Power Station maintained small quantity generator status, generating 5,150 pounds of hazardous waste. Davis-Besse personnel also continuously strive to identify alternate ways to reduce hazardous waste generation. Nonhazardous waste generated from standard operating sources included 27,000 gallons of used oils and 1,430 gallons of oil filters and solid oily debris. Other nonhazardous regulated waste generated which were one time use generated (ie. not generated from standard operations) included 45,300 gallons of water containing small amounts of diesel fuel oil from an on site fuel oilleak and main transformer outage activities. RCRA also mandates other requirements such as the use of proper storage and shipping containers, 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. I 149
Davis-Besse Nuclear Power Station : 1997 Annual Radiological Environmental Operating Report 1 4 Inspections
. ( . Chemical Waste' Accumulation Areas are designated throughout th'e site to ensure
. proper handling and disposal of chemical waste. These, along 'with the Chemical Waste Storage Area, are routinely patrolled by security personnel and inspected weekly by Toledo Edison personnel. All areas used for storage or accumulation of hazardous waste are posted as such with warning signs, and dmms are color-coded for easy identification of waste categories by Davis-Besse employees.
. Waste Inventory Forms Inventory forms are placed on waste accumulation drums or provided in the accumu-lation area to allow employees to record the waste type and amount as it is added to
- the drum This ensures that incompatible wastes are not mixed and also identifies the drum contents for proper disposal.
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. Testing of Waste Oil The majority of waste oil generated at Davis-Besse is not disposed of, but is removed to a recycling facility for energy recovery. Before removal for recycling, the oil is tested to ensure that it is nonhazardous. Waste oil that contains less than 1,000 parts ;
l - per million of halogens and has a flash point above 140 F is considered to be nonhaz-ardous waste. i i
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l Emergency Response Planning
' Comprehensive Enviromnental Response, Compensation, and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, sometimes referred to as Superfund) established a federal authority and source of funding for re-sponding to spi Is and other releases of hazardous materials, pollutants, and contaminants into the environment. . Superfund establishes " reportable quantities" for several hundred hazardous materi-l als, and regulates the c!eanup of abandoned hazardous waste disposal sit'es.
- Superfund Amendment and Reauthorization Act (SARA) l L Superfund was amended in October,1986, to establish new reporting programs dealing with l l emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enhanced by ensuring that the potential for release of hazardous substances is minimized and adequate and timely responses are made to protect surrounding populations.
L i Davis-Besse conducts site-wide inspections to identify and record all hazardous products and i chemical onsite as required by SARA. Determinations were made as to which products and l chemicals were present in sufficient quantities to report. i l Annual SARA reports are submitted to local fire departments, and local and state planning com-L missions by March I for the preceding calendar year. No additional chemical products were L identified for calendar year 1997. 1 Spill Kits l 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 iteins as chemical resistant coveralls, gloves, boots, decontamination agents, absorbent cloth, goggles, and warning signs.
' Other Regulating Acts Toxic Substances Control Act (TSCA)
- The Toxic Substance Control Act (TSCA) was enacted to provide the USEPA with the authority l ~ to require testing of new chemical substances for potential health effects before they are intro-duced into the environment, and to regulate them where necessary. This law would have little
-impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls l
(PCBs),' has been singled out by TSCA. This has resulted in an extensive PCB management sys-tem, very similar to the hazardous waste management system established under RCRA. In 1992, Davis-Besse completed an aggressive progra/m that eliminated PCB transformers onsite.s PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with
- j non-PCB liquid.
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Davis-Besse Nuclear Power Stati:n 1997 ~ Annual Radiological Environmental Operating Report Retrof!!!ing PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with PCB-leaching solvents and allowing the solvent to circulate in the transformer during operation. The entire retrofill process takes several years and will extract almost all of the PCB. In 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. These capacitors are being replaced and disposed of during scheduled maintenance activities No PCB activities were performed in 1997, therefore, no waste PCBs were generated or disposed of in 1997. Clean Air Act The Clean Air Act identifies substances which are considered air pollutants.- Davis-Besse holds an Ohio EPA permit to operate an Air Contaminant Source for the station auxiliary boiler. This boiler is used to heat the stanon and provide steam to plant systems when the reactor is not operating. A report detailing auxiliary boiler operation is submitted annually. Applications for Permitt, 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 Emergency Diesel Generators, the Emergency Response Facility Diesel, the Miscellaneous Diesel, and the Fire Pump Diesel. These sources are operated very infrequently to verify their reliability, - and would only be used in the event of an emergency. 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 ubestos removal from renovation and demolition projects for which USEPA has outlined specific regulations concerning handling, removal, environmental protection, and disposal. Also the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concern for worker protection. Removal teams must meet medical surveillance, respirator fit tests, and training requirements prior to removing asbestos-containing material. Asbestos is not considered a hazardous waste by RCRA, but the EPA does require special handling and disposal of this waste under the Clean Air Act. Transportation Safety Act ; The transportation of hazardous chemicals, including chemical waste, is regulated by the Transportation Safety Act of 1976. These regulations are enforced by the United States ; Department of Transportation (DOT) and cover all aspects of transporting hazardous materials, including packing, handling, labeling, marking, and placarding. Before any wastes are transported orisite, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regtstions, including verification that the vehicle has appropriate placards and it is in good operating condition. Other Programs Underground Storage Tanks According to RCRA, facilities with Underground Storage Tanks (UST) are required to notify the ' State. This regulation was implemented in order to provided protection from tank contents 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. 152
Davis-Besse Nuclear Power SNi:n 1997 Annut! 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 produce power or separated into waste types (such as aluminum, glass, and paper) and recycled. But the vast majority of MSW is sent to landfills for disposal. As the population increases and older 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 Management Plan, othenvise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing landfills by reducing the amount of MSW produced, by reusing waste material where possible and recycling of other waste materials. This is frequently referred to as " Reduce, Reuse, and Recycle." Davis-Besse and Centerior Energy have implemented several programs which emphasize the reduce, reuse, recycle approach to MSW management. Improved efliciency in collection and hauling, resulted in a two year reduction of approximately 71 % for disposal cost MSW. Additionally, joint partnership agreements with yard waste compositors have been developed for yard and lawn waste recycling. An Active Investment Recovery Program has greatly contributed to the reduction of both hazardous and municipal waste generated by evaluating options for uses of surplus materials prior to the materials entering Davis-Besse's waste streams. Such programs include paper, cardboard, aluminum cans, used tires, and metals recycling or recovery. Greater than 50 tons of paper and cormgated cardboard were recycled in 1997, which would have otherwise been placed in a landfill. Additionally, aluminum soft drink cens are collected on site for the Boy Scouts to recycle. Lead-acid batteries are recycled and tires are returned to the seller for proper disposal. Although scrap metal is not usually considered part of the MSW stream, Davis-Besse does collect and recycle scrap metals. 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 ofMSW stream are targeted for reduction. 153
Davis-Besse Nuclear Power Station .1997 Annual Radiological Environmental Operating Report APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESUL'I5 1 3 i f NOTE: Telodyne's Midwest Laboratory participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. The results are reported in Appendix A. Also reported are results of InternationalIntercomparison and Teledyne testing of TLD's, as well as, in-house spikes, blanks, duplicates and mixed analyte performance evaluation progrr..n results. Appendix A is updated four times a year; the complete Appendix b included in March, June, September and December monthly progress reports only. T-January,1997 through December,1997 l ' 154 L - . . .
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Aooendix A Interlaboratory Comoarison Procram Results Teledyne Brown Engineering Environmental Services Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.
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Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the { r.ontrol limits indicate a need to check the instruments or procedures used.' l The results in Table A-1 were obtained through participation in the environmental sample crosscheck l program for milk, water and air filters during the past twelve months. Data for previous years is available upon request. l This program is conducted by the U.S. Environmental Protection Agency Office of Research and l Developement National Exposure Research Laboratory Characterization Research Division Las Vegas, l Nevada. ; The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2. { Also Teledyne testing results are listed. l Table A-3 lists results of the analyses on in-house " spiked" samples for the past twelve months., All samples are prepared using NIST traceable sources. Data for previous years availabic upon request. 1 Table A-4 lists results of the analyses on in-house " blank" samples for the past twelve months. Data for s previous years available upon request. Table A-5 list results of the in-house " duplicate" program for the past twelve months. Acceptance is based I
'j on the difference of the results being less than the sum of the errors. Data for previous years available l upon request.
1 The results in Table A-6 were obtained through participation in the mixed analyte performance j evaluation program. q The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program. 1 Attachment A lists acceptance criteria for " spiked" samples. Out-of-limit results are explained directly below the result.
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i 1 Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Oper: ting Report . I
- 12-31-97 ATTACHMEhTT A
. ACCEPTANCE CRITERIA 'FOR " SPIKED" SAMPLES
'1 LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' ~
- ( - One Standard Deviation !
' Analysis . Level for single determinations
. Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg 5% of known value 6
Strontium-89 - 5 to 50 pCi/ liter or kg 5.0 pCi/ liter
>50 pCi/ liter or kg 10% of known value 7.
Strontium' -906. 2 to 30 pCi/ liter or kg . . 5.0 pCi/ liter . M0 pCi/ liter or kg 10% of known value Potassium-40 BJ.1 g/ liter or kg 5% of known value Gross alpha s20 pCi/ liter 5.0 pCi/ liter
>20 pCi/ liter 25% of known value Gross beta $100 pCi/ liter 5.0 pCi/ liter-
>100 pCi/ liter 5% of known value Tritium s4,000 pCi/ liter is = {pCi/ liter) =
169.85 x (known)'**
>4,000 pCi/ liter ~ 10% of known value :
Radium-226,-228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value lodine-131, s55 pCi/ liter 6.0 pCi/ liter lodine-129 - 6 >55 pCi/ liter 10% of known value Uranium-238, ' s35 pCi/ liter 6.0 pCi/ liter Nickel-63 6 >35 pCi/ liter 15% of known value 6
. Technetium-99 50 to 100 pCi/ liter 10 pCi/ liter Iron-SS.
>100 pCi/ liter 10% of known value
. Others" -
20% of known value
- From EPA publication,'" Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
- Teledyne limit.
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'. Co'ncentration in pCi/I
- Lab Sample' Date Teledyne Results EPA Result' Control
= Code Type Collected Analysis 12 Sigma
- 1s, N=1 Limits STW-782 WATER Jan,1997 St-89 9.7i 0.6 12.0 i 5.0 33 - 20.7 STW-782 WATER Jan,1997 Sr-90 24.0il.0 25.0 5.0 163 - 33.7 STW-783 - . WATER Jan,1997 Gr. Alpha 10.0il.4 5.2 5.0 0.0 - 13.9 STW-783 WATER Jan,1997 Gr. Beta 15.812.0 14.7 5.0 6.0 - 23.4 STW-784 WATER Feb,1997 I-131 86.012.0 86.0 9.0 70.4 - 101.6 STW-784 WATER Feb,1997 I-131 79312.0 86.0 9.0 70.4 - 101.6 STWW-786 WATER Feb,1997. Ra-226 6.7 0.2 5.9i0.9 4.3 - 7.5 STWW-786 WATER Feb,1997 Ra-228 8.4 1.1 8.2 2.1 4.6 - 11.8 STWW-786 WATER Feb,1997 Uranium 26.5 i 1 3 27.0 i 3.0 21.8 - 323 STW-787 WATER Mar,1997 H-3 ,
7,594.0 1 279.7 7,900.0 790.0 6,529.4 - 9,270.6 STW-794, WATER Apr,1997 Gr. Alpha 44.3il.6 48.0112.0 27.2 - 68.8 STW-794 WATER Apr,1997 Ra-226 10.710.9 13.0 2.0 9.5 - 16.5 STW-794 WATER Apr,1997 Ra-228 4.7i 0.4 3.1 1 0.8 1.7 - 4.5 All raw ' data and calculations were reviewed for errors. The analysis was repeated with the technician observed by the lab supervisor; the result of the reanalysis 3.li0.5 pCi/L The suspected cause of the higher result was the lower than expected recovery of barium tracer. No further action is planned at this time. STW-794 WATER Apr,1997 Uranium 26.8 03 24.013.0 18.8 - 29.2 STW-795 WATER Apr,1997 Co-60 21.7 0.6 21.015.0 123 - 29.7 STW-795 WATER Apr,1997 Cs-134 27.311.2 31.0 t 5.0 223 - 39.7 STW-795 WATER Apr,1997 Cs-137 21.7 i 1.5 22.015.0 13.3 - 30.7 STW-795 WATER Apr,1997 Gr. Beta 98.2 2.1 102.1 15.3 75.6 - 128.6 STW-795 WATER Apr,1997 St-89 213il.2 24.015.0 153 - 32.7 STW-795 WATER Apr,1997 Sr-90 12.7 i 0.6 13.0 i 5.0 4 3 - 21.7 STW-796 WATER Jun,1997 Ba-133 24.7 1.2 25.015.0 163 - 33.7 STW-796 WATER Jun,1997 Co-60 18.7 i 0.6 18.0i5.0 93 - 26.7 STW-796 WATER Jun,1997 Cs-134 19.7 i 0.6 22.0 i 5.0 133 - 30.7 STW-796 WATER Jun,1997 Cs-137 52.012.0 49.0 i 5.0 403 - 57.7 STW-796 WATER Jun,1997 Zn-65 101.0 2.0 100.0 1 10.0 82.7 - 1173 STW-797 WATER Jun,1997 Ra-226 2.7 0.1 3.010.5 2.1 - 3.9 STW-797 WATER Jun,1997 Ra-228 23 0.3 3.1 i 0.8 1.7 - 4.5 STW-797 WATER . Jun,1997 Uranium 38.lil.0 40.3 4.0 33.4 - 47.2 STW-799 WATER Jul,1997 Sr-89 37.7 3.2 44.015.0 353 - 52.7 STW-799 WATER Jul,1997 Sr-90 16.011.0 16.015.0 73 - 24.7 STW-802 WATER Jul,1997 I-131 10.711.2 10.0 i 6.0. 0.0- 20.4 STW-800 WATER Jul,1997 Gr. Alpha 3.li0.3 3.115.0 0.0- 11.8 STW-800 WATER Jul,1997 Gr. Beta 13.9 0.2 15.1 5.0 6.4 - 23.8 STW-801 WATER , Aug,1997 H-3 11,348.7 1 241.4 11,010.0 i l,101.0 9,099.8 - 12,920.2 STW-803 WATER Sep,1997 Ra-226 20.0i0.8 20.0 3.0 14.8 25.2 157 , l I
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Opercting Report Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results*. 1 Concentration in pCi/L" Sample Date Teledyne Results EPA Result' Control Lab Type Collected Analysis 12 Sigma' - 1s, N=1 Limits ' Code Sep,1997 Ra-228 7.0i0.1 8.012.0 4.5 - 11.5 STW-803 ' WATER WATER Sep,1997 Uranium 5.0i0.1 5.1 i3.0 0.0 - 10.3 STW-803 WATER Nov,1997 Ba-133 97.3 i 5.0 99.0110.0 81.7 - 116.3 STW 811 WATER Nov,1997 Co-60 28.3 1.7 27.015.0 18.3 - 35.7 STW-811 Nov,1997 Cs-134 9.7 t l.0 10.0i5.0 1.3 - 18.7 STW-811 WATER STW-811 WATER - Nov,1997 Cs-137 78.0 i 3.5 74.0 5.0 65.3 - 82.7 WATER Nov,1997 Zn-65 76.712.1 75.0 i 8.0 61.1 - 88.9 STW-811 '
- 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, Nevada.
- 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 12 standard deviations for three determinations.
d USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and controllimits as defined by the EPA. h
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D'.vis-Besse Nuclear P wer Station 1997 Annual Radi: logical Environmental Operating Report Table A-2. Crosscheck program results; Ihermoluminescent Dosimeters. (TLDs).
,s mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Date Measurement - i 2 Sigma Value 2 Sigma (All Participants) 2nd International Intercomoarison 115-2 CaF2 : Mn Bulb Apr,1976 Field 17.011.9 17.1 16.4 t 7.7 115-2 CaF2 : Mn Bulb Apr,1976 Lab 20.814.1 21.3 - 18.8 7.6 Second Intemational Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (HASL), New York, new York, and the School of Public Health of the University of ' Texas, Houston, Texas.
3rd International Intercomoarison 115-3 CaF2 : Mn Bulb Jun,1977 Field 30.7 i 3.2 34.9 4.8 31.513.0 115-3 CaF2 : Mn Bulb Jun,1977 Lab 89.6 i 6.4 91.7 14.6 86.2 24.0 Third Intemational Intercomparison of Environmental Dosimeters conducted in the summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas. 4th International Intercomoarison 115-4 CaF2 : Mn Bulb Jun,1979 Field 14.111.1 14.1 1.4 16.019.0 115-4 CaF2 : Mn Bulb Jun,1979 Lab, High 40.4i l.4 45.8 9.2 43.9 13.2 -115 CaF2 : Mn Bulb Jun,1979 Lab, Low 9.8il.3 12.212.4- 12.0 7.4 Fourth Intemational Intercomparison of Environmental Dosimeters conducted in the summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 5th International Intercomoarison 115-5A CaF2 : Mn Bulb Oct,1980 Field 31.411.8 30.0 6.0 30.2 14.6 115-5A CaF2 : Mn Bulb Oct,1980 Lab,End 96.6 i 5.8 88.4 i 8.8 90.7 i 31.2 115-5A CaF2 : Mn Bulb Oct,1980 Lab, Start 77.4 i 5.8 75.2 i 7.6 75.8140A 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. 1 5th International Intercomoarison 115-5B - LiF-100 Chips Oct,1980 FieId 30.3 i 4.8 30.016.0 30.2 i 14.6 115-5B LiF-100 Chips Oct,1980 Lab,End 85.4 i 11.7 88.4 i 8.8 90.7 31.2 115-5B - LiF-100 Chips Oct,1980 Lab, Start 81.l i 7.4 75.2 7.6 75.8 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. 6th International Intercomparison
'115-6 Teledyne did not participate in the Sixth Intemational Intercomparison of Environmental Dosimeters.
7th International Intercomoarison 115-7A LIF-100 Chips Jun,1984 Field 75.412.6 75.816.0 75.1 29.8 115-7A LiF-100 Chips . Jun,1984 Lab, Co-60 80.0 & 3.5 79.9 i 4.0 - 77.9 27.6 115-7A LiF-100 Chips Jun,1984 Lab, Cs-137 66.6 i 2.5 75.0 i 3.8 73.0 i 22.2 159
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report i Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 12 Sigma ; Code TLD Type - Date Measurement 2 Sigma Value i2 Sigma (All Participants) i Seventh InternationalIntercomparison of Enviionmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by 'he US. Department of Energy, The Nuclear Regulatory Commission, and the US. Environmental Protecdon Agency. 7th international Intercomparison 115-7B LiF-100 Chips Jun,1984 Field 71.512.6 75.816.0 75.1 29.8 115-78 LiF-100 Chips Jun,1984 Lab, Co-60 84.816.4 79.914.0 77.9 27.6 115-7B ' LiF-100 Chips' Jun,19St Lab, Cs-137 78.811.6 75.0 i 3.8 73.0 22.2 Seventh International lntercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory
' Commission, and the U.S. Environmental Protection Agency. ,
1 7th International Intercomparison ) 115-7C CaSO.: Dy Jun,1984 Field 76.8 i 2.7 75.8 6.0 75.1 29.8 ( Cards 115-7C CaSO4 : Dy Jun,19&1 Lab, Co-60 82.5 3.7 79.914.0 77.9 i 27.6 )i Cards CaSO Lab, Cs-137 '79.0 3.2 75.013.8 73.0122.2 115-7C 4 : Dy Jun,1984 Cards l Seventh International 1ntercomparison of Environmental Dosimeters conducted in the spring and summer of ] 1984 at Las Vegas, Nevada, and sponsored by the US. Department of Energy,'Ihe Nuclear Regulatory { Commission, and the US. Environmental Protection Agency. l l 8th International Intercomparison 115-8A - LiF-100 Chips Jan,1986 Field, Site 1 29.5 i 1.4 29.711.5 28.9 i l2.4 115-8A LiF-100 Chips Jan,1986 Field, Site 2 11.310.8 10.410.5 10_.1 9.1 115-8A LiF-100 Chips Jan,1986 Lab, Cs-137 13.710.9 17.2 i 0.9 16.2 i 6.8 Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy. 8th International Intercomoarison 115-8B LiF-100 Chips Jan,1986 Field, Site 1 32.3 1.2 29.7il.5 28.9 i l2.4 115-8B LiF-100 Chips Jan,1986 Field, Site 2 9.0il.0 10.410.5 10.1 9.0 115-8B LiF-100 Chips Jan,1986 Lab, Cs-137 15.810.9 17.210.9 16.2 i 6.8 Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the US. Department of Energy. 8th' international Intercomparison 115-8C CaSO.: Dy Jan,1986 Field, Site 1 32.2 i 0.7 29.7 i 1.5 28.9 i 12.4 Cards 115-8C CaSO4 : Dy Jan,1986 Field, Site 2 10.610.6 10.410.5 10.1 9.0 Cards 115-8C . 6aSO4 : Dy Jan,1986 Lab, Cs-137 18.110.8 17.210.9 16.2 6.8 Cards x 160
Davis-Besse Nuclear Power Station 1997 Annual Radiological Envirsnmental Operaing Report Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs).
/ mR i l
Lab Teledyne Results Known Average i2 Sigma l Code TLD Type Date Measurement 2 Sigma Value t 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 sponsored by the U.S. Department of Energy. 9th International Intercomnarison 115-9
' The Ninth International Intercomparison of Environmental Dosimeters was not available to Teledyne's !
Midwest Laboratory. - 10th International Intercomoarison 115-10a LiF-100 Chips Aug,1993 Field 25.7il.4 27.0 1.6 26.4110.2 115-10A LiF-100 Chips Aug,1993 _ Lab,1 22.7 1.6 25.9 t 1.3 25.0 t 9.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62.7 i 2.6 72.7 1.9 69.8 20.3 Le Tenth Intemational Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State University and sponsored by the U.S. Department of Energy and the Idaho State University. 10th International Intercomoarison 115-10B CaSO4 Dy Aug,1993 Field 26.0 i 2.3 27.0 1.6 26.4 i 10.2 Cards 115-10B CaSOp Dy Aug,1993 Lab,1 24.lil.7 25.911.3 25.0 9.4 Cards 115-10B CaSO; Dy Aug,1993 Lab,2 69.213.0 72.7 1.9 69.8120.3 Cards ne Tenth Intemational Intercomparison of Environmental Dosimeters conducted in 1993 at I'daho State University and sponsored by the U.S. Department of Energy and the Idaho State University. lith International Intercomoarison , j 115-11 Apr,1997 The Eleventh Intemational Intercomparison of Environmental Dosimeters was conducted in 1997 and was organized by the Department of Energy's Environmental Measurements Laboratory in collaboration with ! Brookhaven National Laboratory and the Nationalinstitute of Standards and Technology. Results for the Eleventh Intemational Intercomparison were originally reported in error; The results are being ) re-evaluated and will be reported in a later update. Teledyne Testing 89-1 LiF-100 Chips Sep,1989 Lab 21.0 0.4 22.4 ND ND = No Data;Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in September,1989. Teledyne Testine 89-2 CaSO4 Dy Nov,1989 Lab 20.9il.0 20.3 ND j Cards l ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. l i 161
. Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs).
/. .mR Lab ' Teledyne Results . Known ' Average i2 Sigma
' Code TLD Type Date Measurement i2 Sigma Value i 2 Sigma (All Participants) 97-1 CaSO4 Dy ' Mar,1997 Reader 1, #1 15.510.1 - 15.0 ~ ND Cards
'97 1 CaSOg Dy ' Mar,1997. Reader 1, #2 34.0 0.1 30.1 ND Cards 97 1 CaSOg Dy ' Mar,1997 ' Reader 1, #3 68.312.1 60.2 ND Cards . Teledyne Testing 97 2- CaSOg Dy J Mar,1997 ' Reader 2, #1 16.8 i 0.3 15.0 ND
-Cards 97-2 CaSOg Dy Mar,1997 Reader 2, #2 36.2 i 0.2 30.1 ND
. Cards 97-2 CaSO4 : Dy ' Mar,1997 Reader 2, #3 69.6 0.2 '60.2 .ND Cards
. ND = No Data: Teledyne Testing was only performed by Teledyne.
Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1997. l
~
4 1 1 I i i
/
s. 4 162
D;vis-Besse Nuclear Power St' tion 1997 Annual Radiological Environmental Oper ting Report i 1 l Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). i mR l
\
Lab Teledyne Results Known Code TLD Type Average 2 Sigma Date Measurement i2 Sigma Value i 2 Sigma (All Participants) 3 95-1 CaSO : Dy Mar,1995 Reader 1, #2 34.9 i 0.1 32.3 ND Cards l 95-1 CaSO : Dy Mar,1995 Reader 1, #3 64.4 1.5 60.8 ND 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. Teledyne Testing 95-2 CaSO : Dy Mar,1995 Reader 2, #1 16.410.2 15.7 ND Cards 95-2 CaSO.i Dy Mar,1995 Reader 7,#2 33.910.4 32.3 ND Cards 95-2 CaSO4 : Dy Mar,1995 Reader 2, #3 60.5 0.3
~
60.8 ND 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. Teledyne Testmg ~ 96-1 LiF-100 Chips Mar,1996 Lab,1 15.910.3 15.4 96-1 LiF-100 Chips Mar,1996 Lab,2 29.410.3 30.8 96-1 LiF-100 Chips Mar,1996 lab,3 62.5il.3 62.5 96-1 CaSO : Dy Mar,1996 Reader 1, #1 14.410.1 15.4 ND Cards 96-1 CaSO : Dy Mar,1996 Reader 1, #2 31.8 i 0.1 30.8 ND-Cards 96-1 CaSO4 : Dy Mar,1996 Reader 1, #3 64.710.4 62.5 ND Cards Teledvne Testine 96-2 CaSO : Dy Mar,1996 Reader 2, #1 14.3 i 0.4 15.4 ND Cards 96-2 . CaSO : Dy Mar,1996 Reader 2, #2 31.810.1 30.8 ND Cards 96-2 CaSO : Dy Mar,1996 Reader 2, #3 68.610.1 62.5 ND Cards
- ND = No Data; Teledyne Testing was only performed by Teledyne.
Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westw ood, New Jersey, in March,1996. Teledyne Testing 97-1 LiF-100 Chips Mar,1997 Lab,1 13.411.4 15.0 07-1 LiF-100 Chips Mar,1997 Lab,2 29.8 0.6 30.1 97-T LIF-100 Chips Mar,1997 Lab,3 63.410.9 60.2 s 4 163
Davis-Desse Nuclear Power Station 1997 Annual Radioligical Environmental Operating Report Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (H.Ds). mR Lab Teledyne Results Known Average 2 Sigma Code TLD Type Date Measurement i2 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 April,1992. .Teledvne Testing 93-1 Teledyne Mar,1993 Lab,1 10.0il.0 10.2 ND LiF-100 Chips 93-1 Teledyne Mar,1993 Lab,2 25.212.2 25.5 ND i 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 giotential 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 Testing 94-1 Teledyne Nov,1994 Lab,1 15.6 0.4 14.9 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Lab,2 30.2 0.4 29.8 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Lab,3 59.2 i 0.3 59.7 ND LiF-100 Chips - 94-1 CaSOg Dy Nov,1994 Reader 1, #1 14.9 i 0.1 14.9 ND Cards 94-1 CaSOg Dy Nov,1994 Reader 1, #2 30.8 i 0.1 29.8 ND_ Cards 94-1 CaSOg Dy Nov,1994 Reader 1, #3 58.910.3 59.7 ND Cards 94-1 CabOg Dy Nov,1994 Reader 2, #1 15.4 i 0.2 14.9 ND Cards 94-1 CaSOg Dy Nov,1994 Reader 2, #2 31.4 i 0.2 29.8 ND Cards 94-1 CaSOg Dy Nov,1994 Reader 2, #3 60.li0.3 59.7 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in November,1994. . Teledyne Testing 95-1 ~ LIF-100 Chips Mar,1995 Lab,1 16.1 i 0.2 15.7 95-1 LiF-100 Chips Mar,1995 Lab,2 31.7 i 0.1 32.3 95-1 LiF-100 Chips Mar,1995 Lab,3 39.710.6 60.8 95-1 CaSOp Dy Mar,1995 Reader 1, #1 16.410.1 15.7 ND Cards s 164
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report i Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 2 Sigma Code TLD Type Date Measurement 2 Sigma Value i 2 Sigma (All Participants) Teledvne Testine 90-1 CaSO.: Dy Jun,1990 Lab 20.611.4 19.6 ND Cards ND = No Data;Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. Teledyne Testinc { 90-2 CaSO.: Dy Jun,1990 Lab 100.8 4.3 100.0 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Dosimetry Asssociates, Inc., Northville, MI, in October,1990. j Teledvne Testinc , 91-1 CaSO4 : Dy Oct,1990 Lab,1 33.412.0 32.0 ND ! Cards 91-1 CaSO,: Dy Oct,1990 Lab,2 55.2 i 4.7 58.8 ND Cards 91-1 CaSO4 : Dy Oct,1990 Lab,3 87.8 i 6.2 85.5 ND Cards ND = No Data; Tcledyne Testing was only performed by Teledyne. Cards were irradiated by Tcledyne Isotopes, Inc., Westwood, New Jersey, in October,1991. Teledyne Testinc 92-1 LIF-100 Chips Feb,1992 Lab,1 11.110.2 10.7 ND 92-1 LiF-100 Chips Feb,1992 Lab,2 25.610.5 25.4 ND-92-1 LIF-100 Chips Feb,1992 Lab,3 46.4 i 0.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in February,1992. Teledvne Testinc 92-2 CaSO,: Dy Apr,1992 Reader 1, #1 20.li 0.1 20.1 ND Cards 92-2 CaSO : Dy Apr,1992 Reader 1, #2 40.6i 0.1 40.0 ND Cards 92-2 CaSO4 : Dy Apr,1992 Reader 1, #3 60.011.3 60.3 ND Cards 92-2 CaSO : Dy Apr,1992 Reader 2, #1 20.310.3 20.1 ND Cards 92 2 CaSO4 : Dy Apr,1992 Reader 2, #2 39.210.3 40.0 ND Cards 92-2 CaSO.: ,Dy Apr,1992 Reader 2, #3 60.710.4 60.3 ND Cards ' s
*.g 165
l i D .vis-Besse Nuclear Power Str. tion 1997 Annual Radiological Environmental Operating Report l l Table A-3. In-house " spike" samples. Concentration in pCi/L' Teledyne Results Known Control' Lab Sample Date Collected Analysis 2s, n=1' Activity Limits Code Type 3.120 1 0.104 3.070 1.842 - 4.298 SPW-844 WATER Jan,1997 Th-230 335510.108 3.070 1.842 - 4.298 SPW-844 WATER Jan,1997 Th-232 WATER Feb,1997 Gr. Beta 43.88111305 41.860 31.860 - 51.860 SPW-548 MILK Feb,1997 Cs-134 48.649 1 4.940 56.400 46.400 - 66.400 SPMI-534 MILK Feb,1997 Cs-137 54.700 i 8.450 52300 42300- 62300 SPMI-534 MILK Feb,1997 Sr-89 49.849 1 7.940 40.030 30.030 - 50.030 SPMI-535 MILK Feb,1997 St-90 48.856 t l.740 50300' 40.240- 60360 SPMI-535 WATER Feb,1997 ~ H-3 27229.744 452.056 28234.000 225S7.200 - 338S0.800 SPW-536 WATER Feb,1997 Co-60 65.219 1 8.790 62.950 52.950 - 72.950 i SPW-547 WATER Feb,1997 Cs-134 52.996 1 8.000 56.430 46.430 - 66.430 l SPW-547 WATER Feb,1997 Cs-137 60.419 i l2.900 52320 42320- 62320 l SPW-547 Feb,1997 I-131 72.182 1 1.009 66300 53.040 - 79.560 l SPW-600 WATER Feb,1997 1-131(g) 68.816 1 14.800 66300 39.780 - 76 300 SPW-600 WATER 1.080 0.648 - 1.512 SPCH-701 CHAR L Feb,1997 1-131(g) 1.171 1 0.023 Feb,1997 Gr. Beta 6 302 i 0.041 5.740 0.000 - 15.740 SPAP-704 AIR FILTER Feb,1997 Ra-226 19.770 i 0.189 17300 12.110 - 22.490 SPW-838 WATER 36.784 1 2.571 31300 21.910 - 40.690 SPW-838 WATER Feb,1997 Ra-228 35.822t 2.020 33.520 26.816 - 40.224 SPW-840 WATER Feb,1997 Sr-90 15.525 1 0.854 14.942 2.942 - 26.942 SPW-841 WATER' Feb,1997 I-129 1.418 0.530 1.535 0.000 - 21.535 SPW-843 WATER Feb,1997 Fe-55 AlR FILTER Mar,1997 Cs-137 2.151 1 0.025 1.900 1.140- 2.660 SPAP-2730 MILK 50.282 i 8.920 53.600 43.600 _63.600 SPMI-1670 Apr,1997 Cs 134 56.090 i 14.900 52.100 42.100 - 62.100 l SPMI-1670 MILK Apr,1997 Cs-137 54.077 i 4.280 51300 41.300 - 61 3 00 SPW-2073 WATER Apr,1997 Co-60 47.636 i 4.150 53.200, 43.200 - 63.200 SPW-2073 WATER Apr,1997 Cs-134 60.688 1 5.760 52.100 42.100 - 62.100 SPW-2073 WATER Apr,1997 Cs-137 34.554 i 2.677 41300 20.650 - 61.950 SPW-2075 WATER Apr,1997 Gr. Alpha WATER 38.729 i l.658 41.700 31.700 - 51.700 SPW-2075 Apr,1997 Gr. Beta SPW-2546 WATER Apr,1997 H-3 25445.478 i 428 384 26257.000 21005.600 - 31508.400 FISH May,1997 Cs-134 0.199 1 0.020 0."F 0.133 - 0 311 SPF-3434 0.234 0.037 0.227 0.136- 0318 SPF-3434 FISH May,1997 ts-137 76.174 0.776 71.800 57.440 - 86.160 SPW-3750 WATER Jun,1997 I-131 66.587 1 8.750 71.800 43.080 - 81.800 SPW-3750 WATER Jun,1997 I-131(g) 79.851 i 0.833 71.800 57.440- 86.160 SPMI-3752 MILK Jun,1997 I-131 78.887 1 7.750 71.800 43.080 - 81.800 SPMI-3752 MILK Jun,1997 I-131(g) 81.869 t 0.317 76.600 45.960 - 86.600 SPCH-3754 CHAR AL Jun,1997 I-131(g) 38.265 i 5.450 39.500 29.500- 49.500 SPMI-4216 , MILK Jul,1997 Cs-134 46.472 i 10.600 41.500 31.500 - 51.500 SPMl-4216 M1LK Jul,1997 Cs-137 75.247 i 0.831 83.230 66.584 - 99.8767 SPMI-4216 MILK Jul,1997 I131 84.872 i 7.010 83.230 49.938 - 93.230 SPMI-4216 MILK Jul,1997 I131(g) 166
l l Davis-Besse Nuclear Power Station 1997' Annual Radiological Environmental Operating Report
, l Table A-3. In-house " spike" samples.
Concentration in pCi/L' j Lab Sample - Date Teledyne Results Known Control' Code : ' Type Collected Analysis 2s, n=1* ' ' Activity ~ Limits - SPMI-4216 MILK . Jul,1997 Sr-90 33.610 1.430 33.210 . 26.568 - 39.852 ' SPW-4420 WATER . .Jul,1997 Co-60 ' . 26.270 t 4.360 24.900 14.900 - 34.900 SPW-4420 ' WATER Jul,1997 Cs-134 . 36.591 5.040 39.540 29.540- 49.540 SPW-4420 WATER Jul,1997 Cs-137 45.552 i 7.770 41.480 . 31.480 - 51.480
' SPW-4420 ~ WATER Jul,1997 I-131(g) 85.221 1 9.660 -83.230 49.938 - 93.230 - ' SPW-4420 WATER Jul,1997 Sr-90: 36.285 i 1.629 ' 33.210 . 26.568 - 39.852 SPMI-4916 MILK Jul,1997 1-131(g) 84.870 i 7.010 83.230 49.938 - 93.230 SPW-5470 WATER . Jul,1997 Fe-55 4.548 i 0.640 5.477 0.000 - 25,477 SPW-5472 . WATER - Jul,1997 H-3 41026.000 i 329.000 41578.000 33262.400 - 49893.600 ~ SPW-5474 WATER Jul,1997 Gr. Alpha -49.266 1 2.081 41.305 20.653 - 61.958 SPW-5474 WATER Jul,1997 Gr. Beta 44.450 1.334 41.406 ~ 31.406 - 51.406 0.420 - 0.980 :
SPF-5476 FISH Jul,1997 Cs-134 0.641 0.030 0.700 SPF 5476 - FISH Jul,1997 Cs-137 0.632 i 0.042 0.527 0.316 - 0.73S SPW-7500 WATER Oct,1997 Co-60 30.424 1 7.530 33.642 23.642 - 43.642 SPW-7500 WATER Oct,1997 Cs-134 37A10i6.690 ' 36.086 . 26 086 - 46.086 SPW-7500 WATER . Oct,1997 Cs-137 52.845 i 11.300 41.221- 31.221 - 51.221
'Ihe Cs-137 spike is suspect. No errors were found in the spectroscopy program and the Cs 134 and Co-60 test results on the same sample were very good. Sample rescits prepared with a new standard are acceptable.
SPW-7500 WATER Oct,1997 I 131 78.126 1 1.201 78.302 62.642 - 93.962 SPMI 7505 MILK Oct,1997. Cs-134 15.166 i 3.250 '18.043 8.043 - 28.043 SPMl-7505 MILK Oct,1997 Cs-137 91.110 i 8.370 82.440 72.440- 92.440 ' SPMl-7505 . MILK Oct,1997 I-131 73.529
- 1.253 . 78.302 62.642 .93.962 SPMI-7505 MILK Oct,1997 I-131(g) 74.613 1 8.810 78.302 46.951 - 88.302 SPMI-7506. MILK Oct,1997 Sr-89.- 31.281 1 4.601) 39.490 29.490 - 49.490 SPCH-7727 CHARCOAL Oct,1997 I-131(g) 0.450 i 0.050 0.440 0.264 - 0.616 CANISTER SPAP-7730 - AIR FILTER Oct,1997 Gr. Beta 3.080 i 0.030 3.040 1.824 - 4.256 (ss)
SPF-8485 FISH .Nov,1997 Cs-134 0.306 i 0.025 0.318 0.191 - 0.445 SPF-8485 FISH Nov,1997 Cs-137 0.738 i 0.049 0.649 0.389 - 0.909 ! SPW-9315 : WATER . 2 Nov,1997 Gr. Alpha - 51A20i6.385 41.280 20.640 - 61.920
~ SPW-9315 - WATE R - Nov,1997 Gr. Beta 48.938 1 3.735 43.164 33.164 - 53.164
~ SPW-9706 WATER Dec,1997 Gr. Alpha 40.480 i 4.598 '41.280 '20.640 - 61.920 SPW-9853 WATER - Dec,1997 . Co-60 44.900 i 8.290 42.080 32.080 - 52.080 SPW-9853 WATER Dec,1997 Cs-134 40.010 1 7.010 37.850 27.850- 47.850 s.
'
- All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L; air filter samples,
- which are in pCi/ Filter; and food products, which are in mg/kg.
" All samples are the results of single determinations. j
' 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. 167 .
[ Davis-Besse Nuclear Power Station 1997 Annual Radiological Environnnntal Operating Report Table A-4. In-house " blank" samples. Concentration pCi/l'. Teledyne Results Acceptance Sample (4.66 Sigma) Criteria Lab Sample Code Type Date Analysis LLD' Activitv' (4.66 Sigma) SPW-845 WATER Jan1997 Th-228 <0.9 -0.263 i 0.560 <1.000 SPW 845 WATER . Jan 1997 Th 230 <0.2 - 0.191 0.236 <1.000 j
/ATER' <0.2 -0.018 0.145 <1.000 )
SPW-845 ' Jan 1997 Th-232 l
<2.7 -0.531 0.647 < 10.000 i SPMI-533 MILK Feb l997 Cs-134 SPMI-533 MILK Feb 1997 ' Cs-137 <5.5 0.526 3.380 < 10.000
' SPW-2 WATER Feb l997 Ra-226 <0.1 0.000 0.034 <1.000 SPMI-533 MILK Feb 1997 I-131 <0.5 -0.031 1 0.316 <0.500 SPMI-533 MILK Feb 1997 Sr-89 <0.7 -0.994 1 0.952 <5.000 SPMI-533 MILK Feb l997 Sr-90 N/A- 1.695 0.439 <1.000 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPW 537 .. WATER - Feb 1997 ' Co-60 . <3.1 0.065 0.179 < 10.000 SPW-537 WATER Feb l997 Cs-134 <3.5 0.905 1.100 < 10.000 SPW-537 WATER Feb 1997 Cs-137 <1.7 -1.430 1 1.800 < 10.000 : SPW-537 WATER Feb 1997 Gr. Alpha <0.4 -0.109 1 0.218 <1.000
- SPW-537 WATER Feb l997 Gr. Beta <0.9 -0.155 0.596 < 3.200 SPW-537 WATER Feb 1997 I-131 <0.4 -0.275 i 0.235 <0.500 SPW-537 WATER Feb 1997 Sr-89 <0.8 -0.167 1 0.557 < 5.000 SPW-537 WATER Feb l997 Sr-90 <0.5 0.099 0.239 <1.000 SPW-842 WATER Feb 1997 Fe-55 <0.7 -0.403 i 0.374 < 1000.000 SPW-842 WATER Feb l997 I-129 <0.9 -0.129 0.442 <1.500 SPW-842 WATER - Feb 1997 Ra-226 <0.04 0.013 1 0.026 <1.000 AIR FILTER Mar 1997 Co-60 <2.5 0.000 1 0.000 < 10.000 SPAP-2731 AIR FILTER Mar 1997 Cs-134 <2.6 -0.000 1 0.000 < 10.000 SPAP-2731 AIR FILTER Mar 1997 Cs-137 <2.9 0.000 1 0.001 < 10.000 SPAP-2731 MILK Apr1997 Cs-134 <5.5 0.069 i 0.118 < 10.000 SPMI-1669 MILK Apr1997 Cs-137 <3.8 0.717 1 2.480 < 10.000 SPMI-1669 WATER Apr1997 Co-60 <3.6 0.857 1 8.380 < 10.000 .
SPW-2074 WATER - Apr1997 Cs-134 <4.7 1.610 i 10.200 < 10.000
. SPW-2074
' WATER Apr1997 Cs 137 <5.0 1.800 1 3.200 < 10.000 SPW-2074
- WATER Apr1997. Gr. Alpha <0.5 0.119 i 0.307 <1.000 SPW-2074 WATER Apr1997 Gr. Beta <1.3 0.464 0.720 < 3.200 SPW-2074 Apr1997 H-3 < 150 12.822 i 75.126 < 200.000 SPW-2547 WATER WATER May 1997 Ra-226 <0.03 -0.053 i 0.025 <1.000 SPW-5 FISH May 1997 Cs '64 <0.015 -0.014 i 0.002 < 10.000 SPF-3435 SPF-3435 FISH May 1997 Cs 137 <0.016 0.001 1 0.011 < 10.000 2 l
WATER <0.04 -0.044 i 0.027 <1.000 SPW-6 Jun1997 Ra 226 y 168 -
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table A-4. In-house " blank" samples. Concentration pCi/l'. Teledyne Results Acceptance Sample (4.66 Sigma) Criteria Lab Sample Activity" Type Date Analysis LLD (4.66 Sigma) Code SPW-3751 WATER Jun1997 I-131 <0.3 -0.127 0.145 <0.500 SPMI-3753 MILK Jun1997 I-131 <0.3 0.089 0.167 < 0.500 CHARCOAL Jun1997 I-131(g) <0.017 0.010 1 0.009 < 9.600 SPCH-3755 CANISTER SPMI-4217 MILK Ju11997 Co-60 < 4.8 -0.392 1.230 < 10.000 MILK <3.0 -0.874 1.700 < 10.000 SPMI-4217 Jul1997 Cs-134 SPMI-4217 MILK Jul1997 Cs-137 <5.9 1.600 3.430 < 10.000 SPMI-4217 MILK Jul1997 I-131 <0.3 -0.049 0.171 <0.500 SPW-4421 WATER Jul1997 Co-60 < 1.9 -4.660 4.750 < 10.000 SPW-4421 WATER Jul1997 Cs-134 <4.7 -1.450 3.090 < 10.000 SPW-4421 WATER Jul1997 Cs-137 <6.7 0.739. 4.550 < 10.000 Sl'MI-4217 MILK Jul1997 Sr-89 < 1.5 -0.165 1.901 <5.000 MILK N/A 1.677 i 0.418 <1.000 SPMI-4217. Jul1997 Sr-90 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPW-4421 WATER Jul1997 Sr-89 <1.7 0.917 1.547 < 5.000 SPW-4421 WATER Jul1997 Sr-90 <0.6 0.341 1 0.332 <1.000 SPW-5471 WATER Ju!1997 Fe-55 <733 48.157 448.317 < 1000.000 SPW-5473 WATER Jul1997 H-3 <161 22.700 58.200 < 200.000 SPW-5475 WATER ,Jul1997 Gr. Alpha <0.6 0.170 0.425 <1.000 SPW-5475 WATER Jul1997 Gr. Beta <0.5 0.173 0.473 < 3.200 FISH <0.011 -0.001 1 0.002 < 10.000 SPF-5477 Jul1997 Co-60 FISH <0.015 0.005 i 0.00S < 10.000 SPF-5477 Jul1997 Cs-134 FISH <0.018 0.006 1 0.010 < 10.000 SPF-5477 Jul1997 Cs 137 SPW-7501 WATER Oct1997 I-131 <0.4 0.010 i 0.009 < 0.500 SPW-7504 WATER Oct 1997 St-89 < 1.1 -0.650 1 0.800 <5.000 SPW-7504 WATER Oct 1997 Sr-90 <0.4 0.150 0.210 <1.000 SPMI-7507 MILK Oct 1997 Co-60 <6.2 -1.190 i 1.620 < 10.000 SPMI-7507 MILK Oct 1997 Cs-134 <4.9 1.710 1.950 < 10.000 SPMI-7507 MILK Oct1997 Cs-137 <6.5 -0.232 3.740 < 10.000 SPMI-7507 MILK Oct1997 I-131 <0.3 -0.022 0.157 < 0.500 SPMI 7507 MILK Oct1997 St-89 <1.0 0.862 1.107 <5.000 SPMI 7507 MILK Oct 1997 Sr-90 N/A 1.031 0.319 <1.000 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. . WATER Dec1997 Ra-228 <0.7 0.134 0.318 <1.000 RA-Vfr11 WATER Dec1997 Co-60 <2.4 -1.600 1 9.460 < 10.000 ~ SPW-9852 ~' SPW-9852 - WATER Dec1997 Cs-134 <5.7 -0.450 i 2.340 < 10.000 169
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmintal Operating Report Table A-4. In-house " blank" samples. Concentration pCi/L'. Teledyne Results Acceptance Lab Sample ' . Sample (4.66 Sigma) . Criteria Activitv' Code- Type Da te Analysis LLD (4.66 Sigma) SPW-9852 WATER ' Dec 1997 Cs-137 <6.0 2.190 1 3.550 < 10.000 )
' Liquid sample results are reported in pCi/ Liter, air filter sample results are in pCi/ filter, charcoal sample results are in pCi/ charcoal, and solid sample results are in pCi/ kilogram. !
- The activity reported is the net activity result. -)
i l I l l I l
- s.
9 170
}
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report I I Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sarnple First Second Averaged Date Analysis Result Result Result Codes" 3.0753 i 0.9097 2.5036 0.8819 2.7894 1 0.6335 SW - 42,43 ' Jan,1997 Gr. Beta Co-60 0.8960 i 2.5500 0.8290 i 1.4300 0.8625 1.4618 MI- 63,64 Jan,1997 MI- 63,64 Jan,1997 Cs-137 0.4480 i 2.0600 0.7240 i 1 3 800 05860 1.2398 2.7900 i 2.6200 1.4300 1 2.4700 2.1100 1.8004 ( MI- 19,20 Jan,1997 Co-60
-0.8750 i 2.7600 23900 1 1.9100 0.7575 i 1.6782 i MI- 19,20 Jan,1997 Cs-137 I-131 0.0455 t 0.2124 0.1031 i 0.2405 0.0743 i 0.1604 ;
MI - 91.,93 Jan,1997 1,466.8000 i 129.0000 1,4173000 163.0000 1,442.0500 103.9351 MI- 92,93 Jan,1997 K-40 I-131 0.1299 i 0.2579 -0.0824 t 0.2359 0.0237 i 0.1747 WW - 116,117 Jan,1997 Co-60 -0.1850 i 0.4500 1.9100 i 16.9000 0.8625 8.4530 LW - 146,147 Jan,1997
-0.8360 1 2.1600 0.2350 i 3.4500 -0 3005 i 2.0352 l LW - 146,147 Jan,1997 Cs-137 Gr. Beta 6.9782 1.4082 7.8900 i l 5 599 7.4341 1 1.0507 l LW - 146,147 Jan,1997 Co-60 1.8300 1 4.2500 -1.2200 1 0.9290 0 3050 i 2.1752 LW - 224,225 Jan,1997
-0.9650 i 3.4000 1.4500 i 1.7100 0.2425 i 1.9029 LW - 224,225 Jan,1997 Cs-137 6.2889 i 1 3951 7 3610 i 1.5370 6.8250 i 1.0379 LW - 224,225 Jan,1997 Gr. Beta H-3 -5.4270 1 80.6586 -14.4721 i 80.2518 -9.9496 i 56.8906 WW - 322,323 Jan,1997 Gr. Beta 3.1262 1 1.4281 2.0589 1 1.4561 2.5926 i l.0198 ,
CW - 355,356 Jan,1997
-03849 1 1.2993 0.4440 1 1 3 725 0.0296 1 0.9450 CW - 355,356 Jan,1997 Gr. Beta 2.4965 1 1.0877 2.7913 1 1.4707 2.6439 t 0.9146 l CW - 299,300 Jan,1997 Gr. Beta 0.2070 1 1 3507 0.7394 i 1.3967 0.4732 i 0.9715 CW - 299,300 Jan,1997 Gr. Beta Co-60 -0.2460 i 1 3100 03250 1 0.3190 0.0395 i 0.6741 SW - 441,442 Jan,1997 Cs-137 0.0619 1 2.3900 3.0200 1 2.8400 1 3410
- 1.8559 {
SW - 441,442 Jan,1997 2.7555 i 0.5392 2.6585 i 0.5182 2.7070 i 0 3739 { SWU - 389,390 Jan,1997 Gr. Beta SWU - 389,390 Jan,1997 H-3 158.6398 1 94.8968 125.0455 93.5661 141.8427 66.6333 l f 0.1482 1 0.2260 0.0950 1 0.2541 ^ 0.1216 i 0.1700 M1- 377,378 Jan,1997 I-131 1,379.5000 i 122.0000 1,304.8000 113.0000 1,342.1500 i 83.1460 j MI - 377,378 Jan,1997 K-40 Sr-89 -0.4172 1 0.8436 -0.2671 t 0.7827 -03421 0.5754 MI- 377,378 Jan,1997 0.9881 03785 1.0431 1 03340 1.0156 i 0.2524 ; MI- 377,378 Jan,1997 Sr-90 i 3.7493 i l.2558 4.5363 i l.1489 4.1428 i 0.8510 ;
- CW - 416,417 Jan,1997 Gr. Beta 1 0.1479 i 1 3455 0.6807 1 1 3926 0.4143 1 0.9682 CW - 416,417 Jan,1997 Gr. Beta
-0.4870 i 0.6140 0.8310 1 2.4300 0.1720 i 1.2532 PW - 607,608 Jan,1997 Co-60
-0.7370 i 2.6100 0.2580 i 3.0900 -0.2395 i 2.0224 PW - 607,608 Jan,1997 Cs-137 5.5786 1.7689 5.6550 12933 l PW - 607,608 Jan,1997 Gr. Deta 5.7315 i 1.8872 0.0484 1 0.4520 0.6758 0.4786 03621 03292 CW - 846,847 Jan,1997 Gr. Alpha ,
1 3287 i 0.5381 1.7268 i 0 3817 CW - 846,847 Jan,1997 Gr. Beta 2.J25010.5415 1,518.5023 i 131.0155 1,631.7608 1 134.0877 1,575.1316 i 93.7344 CW - 846,847 Jan,1997 H-3 0 3800 i 0.5210 0.7406 i 0.8976 0.5603 i 0'5189 CW - 846,847 Jan,1997 Sr-89 I Sr-90 0.1424 0.2458 0.7292 i 0 3 717 0.4358 i 0.2228 CW - 846,847 Jan,1997 171
l f. l Divis' Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table A-5. In-house duplicate" sampics. Concentrationin pCi/L' Lab Sample First Second Averaged Date Analysis Result Result Result Codes
- WW - 576,577 Feb,1997 H-3 150.9770 i 84.0813 241.2023 i 87.8687 196.0897 60.8083 MI- 486,487 Feb,1997 I-131 0.0797 1 0.1694 -0.1161 1 0.1703 -0.0979 i 0.1201 Feb,1997 K-40 1,278.2000 167.0000 1,316.5000 i 141.0000 1,297.3500 109.2817 MI- 486,487 MI- 486,487 Feb,1997 Sr-89 -0.8027 0.9962 -0.4554 1 0.9484 -0.6290 0.6877 MI- 486,487 Feb,1997 Sr-90 1.8013 1 0.4825 1.4892 1 0.4537 1.6453 0.3312 MI- 510,511 Feb,1997 Co-60 0.6890 i 1.0200 -2.2000 i 4.1400 -0.7555 2.1319 Feb,1997 0.7830 i 2.6300 2.2400 1 3.2800 1.5115 2.1021 MI- 510,511 Cs-137 MI-510,511 Feb,1997 I-131 0.0764 i 0.2227 0.0373 0.2345 0.0568 0.1617 Feb,1997 I-101 0.0368 i 0.1942 -0.0045 i 0.2095 0.0161 0.1429 MI- 531,532 1,3003000 178.0000 1,488.5000 1 156.0000 1,394.'4000 1183427 MI- 531,532 Feb,1997 K-40 Feb,1997 C r. Beta 3.6552 1.5170 2.7825 i 1.4922 3.2189 1 1.0639 CW - 554,555 Feb,1997 Gr.Deta 0.5033 i 1.0364 -0.2368 1 0.9931 0.1332 0.7177 CW - 554,555 I-131 -0.2709 i 0.2349 -0.1024 i 0.1676 -0.1867 1 0.1443 MI- 632,633 Feb,1997 1,408.0000 165.0000 1,243.1000 145.0000 1,325.5500 109.8294 MI- 632,633 Feb,1997 K-40 Feb,1997 I-131 -0.0581 0.2376 0.2433 i 0.2658 0.0926 0.1783
! MI- 723,724 1,574.8000 i 218.0000 1,396.8000 1 162.0000 1,485.8000 135.8013 MI -723,724 Feb,1997 K-40 Feb,1997 Gr. Deta 3.7439 i 0.9482 4.0547 i 0.9711 3.8993 0.678( LW - 757,758 2.3358 i 1 3877 1.8177 i 0.9474 CW- 883,884 Feb,1997 Gr. Beta 1.2996 i 1.2901 2.059/.1 0.5098 2.0694 0.3507 DW - 1030,1031 Feb,1997 Gr. Beta 2.0791 i 0.4817
-0.1816 i 0 3127 -0.1217 i 0 3071 -0.1517 1 0.2192 DW - 1030,1031 Feb,1997 I-131 2.4729 i 0.6238 2.9908 i 0.6691 2 7319 0.4574 SWU - 929,930 Feb,1997 Gr. Beta 170.1477 84.5878 202.2735 i 85.9328 186.2106 60.2900 SWU - 929,930 Feb,1997 H-3 12.4533 i 88.3392 57.2850 63.7918 WW - 979,980 Feb,1997 H-3 102.1168 i 92.0531 '
-8.0656 i 76.2734 213161 1 54.8669 i SW - 1370,1371 Feb,1997 H-3 50.6979 i 78.8916 0.7490 i 1.7500 -1.3300 1 3.8800 -0.2905 2.1282 LW - 953,954 Mar,1997 Co-60
-0 3220 i 2.2800 1.5500 i 2.7200 0.6140 1.7746 LW - 953,954 Mar,1997 Cs-137 3.7343 i 1.0079 4.6558 i 0.9898 4.1951 0.7063 LW - 953,954 Mar,1997 Gr. Beta 2.1268 i 0.7453 1.9502 0.5209
' SW - 1036,1037 Mar,1997 Gr. Beta 1.7736 1 0.7279 250.7943 i 85 3666 235.2277 59.9156 SW - 1576,1577 Mar,1997 H-3 219.6612 i 84.0956
-0.6149 1 0.9822 -0.5704 0.7442 SW - 1576,1577 Mar,1997 Sr-89 -0.5258 i 1.1183 0.7181 1 03074 0.6952 0.2315 SW - 1576,1577 Mar,1997 Sr-90 0.6723 t 0.3462 l 0.0400 1 0.1677 0.0741 0.1204 MI-1055,1056 Mar,1997 I-131 0.1081 i 0.1729 1,530 3000 i 124.0000 1,491.6000 88 3912 MI- 1055,1056 Mar,1997 K-40 1,452.9000 i l26.0000 1.8604 1 0.6077 2.2283 0.4298 Mar,1997 Gr. Beta 2.5963 1 0.6078 kW - 1120,1121 0.0708 i 0.2015 0.0473 0.1434 MI- 1158,1159 Mar,1997 I-131 0.0239 i 0.2040 1,523.5000 i l52.0000 1,418.5000 i l57.0000 1,471.0000 10927 MI- 1158,1159 Mar,1997 K-40 3.4999 i 1.8196 4.1684 132l, CW - 1187,1188 Mar,1997 Gr. Beta 4.8369 1 1.9131
~
172
I
- Davis-Besse Nuclear Power Station' 1997 Annual Radiological Environmental Operating Report
! Table A'-5. In-house " duplicate" samples. Concentration in pCi/L' L Lak Sample . First Second Averaged Codes
- Date Analysis Result ' Result Result '
l l CW-1187,1188 Mar,1997 Gr. Beta 0.1481 1 1.5087 -0.0888 i 1.4896 0.02 % i 1.0601
- LW - 1145,1146' Mar,1997 ' Co-60 '1.5000 1 33300 3.6600 1 6.9500 2.5800 i 3.8533 l
j LW - 1145,1146 . Mar,1997 Cs-137 1.6200 i 3.2500' -0.9330 t 4.1100 0 3435 i 2.6199' LW - 1145,1146 Mar,1997 Gr. Beta 4.2278 i 1.2135 3.5675 i 1.2356- 3.8976 i 0.8659 l - MI- 1275,1276 Mar,1997 I-131 -0.0683 i 0.2309 0 3734 i 0.4565 0.1525 i 0.2558 MI- 1275,1276. Mar,1997 - K-40 1,491.1000 1 193.0000 1,754.0000 i 177.0000- 1,622.5500 i 130.9370 j WW - 1309,1310 Mar,1997 . H-3 4,282.8089 1 188.1304 '4,034.4635 i 183.5207 4,158.6362 i 131.4086 SWT- 1519,1520 Mar,1997 : Gr. Beta ~ 2.5242 i 0.6065. 2.0921 i 0.5846 23082 0.4212 WW - 1539,1540 Mar,1997 Gr. Beta 1.2878 i 0.6803 1.8468 i 0.7043'- 1.5673 0.4896 WW - 1539,1540 Mar,1997 H-3 -34.4755 i 72.6445' 413706 i 76.1590 3.4476 52.6246 DW - 1688,1689 Mar,1997 Gr. Beta 4.5141 1 1.3660 - 4.6886 1 1.2681 '4.6013 i 0.9319 ! - DW - 1688,1689 Mar,1997 I-131 -0.1688 i 0.3758 0.3183 i 0.3363 'O.0748 i 0.2522
- SW - 2204,2205 - Mar,1997 H-3 . 62.0000 t 152.0000 112.0000 152.0000 87.0000 i 107.4802
- CW - 1909,1910 Mar,1997 H-3 435.8375 i 96.4774 430.4271 i 96.2750 433.1323 i 68.1483 LW - 1931,1932 Mar,1997 H-3 168.9801 i 83.1073 137.7304 i 81.7913 1533552 583023 ,
CW -1599,1600 Mar,1997 Gr. Beta 3.4372 i l.5949 3.4464 i l.5289 3.4418 1.1047 CW - 1599,1600 Mar,1997 - Gr. Beta 1.0978 i 0.9656' 1.0340 1 0.9528 1.0659 i 0.6783
. AP-2572,2573 Mar,1997 Co-60 -0.0006 i 0.0102 -0.0002 1 0.0002 -0.0004 0.0051 AP -2572,2573 Mar,1997 Cs-137 0.0008 i 0.0007 0.0000 i 0.0005 0.0004 i 0.0004 SWU - 2045,2046 Mar,1997 Sr-89 . -0.0237 i 0.7179 0.1072 i o.6305 0.0417io.4777 ~
' SWU - 2045,2046 Mar,1997 Sr-90 03676i03471 0.1910 i 0.2933 d.279310.2272 MI-1641,1642 Apr,1997 I-131 -0.6675 1 03099- -0.5511 i 0.3244 -0.6093 0.2243 l
MI- 1641,1642 . . Apr,1997 K-40 1,556.3000 1 111.0000 1,393.1000 i 160.0000 1,474.7000 i 973666 LW -1763,1764 Apr,1997 Gr. Beta 23656 i 0.8258 2.1732 i 0.8478 2.2694 0.5917-128.7514 i 57.0295 l LW - 1763,1764 ' Apr,1997 H-3 - 97.1488 1 79.2640 160 3540 i 82.0162
~
. AP-1974,1975 Apr,1997 Sr-89 -0.0001 1 0.0006 -0.0005 i 0.0015 -0.0003 i 0.0008 0.0001 i 0.0004 0.0001 i 0.0002 j
' AP-1974,1975 Apr,1997 Sr-90 0.0001 1 0.0002 l
'AP - 1994,1995. Apr,1997 Co-60 -0.0003 1 0.0013 0.0002 i 0.0007 -0.0000 i O.0007 L
[AP-1994,1995 Apr,1997 Cs-134 -0.0001 i 0.0006 -0.0001 i 0.0016 -0.0001 0.0008 ! lL
, AP - 1994,1995 - Apr,1997 Cs-137 -0.0002 i 0.0005 -0.0001 i 0.0005 -0.0002 i 0.0004
. " AP - 1994,1995 '. . Apr,1997 I-131(g) - -0.0001 i 0.0002 0.0001 i 0.0002 0.0000 1 0.0001 AP -1994,1995 Apr,1997- K-40 0.0306 i 0,0192 0.0114 i 0.0180 0.0210 i 0.0132 ;
WW - 1665,1666 Apr,1997 I-131 -0.4430 i 0.2674 ' 0.0311 i 0.2626
- -0.2370 1 0.1874
. WW - 1708;1709 Apr,1997 Gr. Beta '1.2245 i 0.6161 1.2858 i 0.6134 , 1.2551 0.4347
. WW - 1785,1786 - . Apr,1997 Gr. Beta 2.9118 i 2.0703 -0 3820 i 2.1095 1.6469i1A779 I WW - 1785,1786 - Apr,1997 - H-3 -19.0365 i 73.7753 -74.4153 i 71.1298 -46.7259 51.2402 WW - 1785,1786 'Apr,1997 : Sr-89 0.6539 1 0.6546 -0.4951 t 0.5197 0.0794 i 0.4179
> 173 l m s
r , l Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l I l l Table A-5. In-house " duplicate" samples, i l Concentration in pCi/L' I Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result WW - 1785,1786 Apr,1997 Sr-90 -0.0023 1 0.2013 0.2468 0.2347 0.1223 0.1546 WW - 1737,1738 Apr,1997 Gr. Beta 15.0355 i 1.5075 15.6924 1.6231 15 3640 1.1076 WW - 1737,1738 Apr,1997 H-3 13.8405 1 75.2790 -5.1902 74 3991 43251 52.9201 LW - 2848,2849 Apr,1997 Gr. Beta 2.4095 1 0.6377 1.7316 1 0.5601 2.0706 0.4244 MI- 1845,1846 Apr,1997 Co-60 0.0309 i 0.0778 -1.8500 1 22.4000 -0.9096 i 11.2001 Mi - 1845,1846 Apr,1997 Cs-134 0.1600 1 0.1350 0.5860 2.2600 03730 1.1320 MI- 1845,1846 Apr,1997 Cs-137 0.7580 i 1.1500 0.6290 1 2.6700 0.6935 1.4536 l MI- 1845,1846 Apr,1997 I-131 -0.2586 i 0.2297 -0.0829 i 0.2149 -0.1708 0.1573 MI- 1845,1846 Apr,1997 I-131(g) -0.0707 i 0.2970 -0.7200 i 3.2700 -03954 1.6417 MI- 1845,1846 Apr,1997 K-40 1,592.5000 1 52.5000 1,5593000 1 127.0000 1,575.9000 6S.7115 MI- 1845,1846 Apr,1997 Sr-89 0.2592 i l.3259 -03095 0.8315 -0.0252 1 0.7825 MI- 1845,1846 Apr,1997 Sr-90 13583i03573 0.8755 i 0.2294 1.1169 0.2123 F - 2175,2176 Apr,1997 Gr. Alpha 0.0245 i 0.0359 0.0672 0.0377 0.0458 0.0260 F - 2175,2176 Apr,1997 Gr. Beta 23387 1 0.2713 1.7003 1 0 3684 2.0195 0.22SS F - 2175,2176 Apr,1997 K-40 2.5383 03610 2.5345 1 0 3640 2.5364 0.2563 F - 2175,2176 Apr,1997 Sr-89 0.0003 1 0.0053 0.0021 i 0.0048 0.0012 0.0036 F - 2175,2176 Apr,1997 Sr-90 -0.0002 1 0.0018 -0.0003 i 0.0016 -0.0002 0.001~
SWU - 2091,2092- Apr,1997 Gr. Beta 33295 0.6698 2.7374 i 0.6670 3.0334 0.4726 SWU - 2091,2092 Apr,1997 H-3 42.6019 76.2782 46.1034 1 76.4388 44 3526 53.993' SWU - 2636,2637 . Apr,1997 H-3 17.9011 i 75.4236 92.3927 i 78.7712 55.1469 54.529: SL - 2432,2433 Apr,1997 K-40 1.8447 i 0.4400 1.6811 1 0.5400 57629 034S3 WW - 2462,2463 Apr,1997 Co-60 -0.5320 1 0.7550 0.4650 i 0.7810 -0.0335 0.5431 WW - 2462,2463 Apr,1997 Cs-137 0.6250 i 3.6500 -1.4600 3.4400 -0.4175 2.5076 WW - 2462,2463 Apr,1997 H-3 19.6154 1 75.4335 -21.9230 i 73.5027 -1.1538 52.6613 F - 2412,2413 Apr,1997 K-40 3.0009 i 0.1660 3.0594 1 0.1470 3.0302 i 0.1109 LW - 2550,2551 Apr,1997 Gr. Beta 2.0074 i 0.8317 3.6936 i 0.8973 2.8505 0.6117 LW - 2550,2551 Apr,1997 K-40 102.7800 i 55.6000 96.6520 54.9000 99.7160 39.06M SP - 2806,2807 Apr,1997 Gr. Alpha 0.02451 03861 0.1365 1 03720 0.0S05 0.26S1 SP - 2806,2807 Apr,1997 Sr-89 -1.4194 6.8147 -5.6447 i 8.6109 -3.5321 i 5.4906 Sr-90 2.6542 1 23158 7.1752 i 2.9780 4.9147 1 1.8862 SP - 2806,2807 Apr,1997 PW - 2736,2737 Co-60 0.1300 4.6800 -0.6250 1 9.8400 -0.2475 1 5.44S1 I Apt,1997 PW - 2736,2737 Apr,1997 Cs-137 -0.2740 i 4.2100 1.7400 i 3 3400 0.7330 2.6870 i PW - 2736,2737 Apr,1997 Gr. Beta 2.8037 i 1.5036 2.6658 i 1.4461 2.7348 LO43: H-3 1,482.0205 i 125.6515 1,596.1107 i 128.7524 1,539.0656 89.9520 WW - 2712,2713, Apr,1997 SW - 2657, 2658 May,1997 Gr. Beta 13.2739 1 13358 ', 13.1663 i 1.2719 13.2201 0.9222 S O - 2677,2678 May,1997 Cs-137 0.1078 i 0.1000 0.2315 1 0.0507 0.1697 9.05F S O - 2677,2678 May,1997 Gr. Alpha 5.5187 i 3.4094 8 3190 1 4.0540 6.9189 i 2.645-l 174 l
; Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report -
Table A-5. In-house ** duplicate" samples, j Concentration in pCi/I
- Lab ' Sample . .
First Second Averaged Codes * ' Date Analysis Result Result Result S O - 2677,2678 .May,1997 Gr. Beta , 21.9926 2.7808 21.8461 1 3.0806 21.9193 2.0750 j S O - 2677,2678 May,1997. Sr-89 0.0075 i 0.0954 ' -0.0008 0.0808 0.0034 0.0625 j, S O - 2677,2678. May,1997 Sr-90 0.0713 0.0197 . 0.0642 i o.0164 0.0677 0.0128
. MI-2764,2765 May,1997 Co-60 0.0636 i 0.0966 .-1.5300 i 7,2300 -0.7332 3.6153 e MI-2764,2765 May,1997 Cs-137 5.5000 i 5.2800 1.7700t 4.9900 3.6350 3.6324
- , MI-2764,2765 May,1997 I-131 -0.163S i 0.1612 -0.0766 i 0.1452 -0.1201 i 0.1085 MI- 2828,2829 May,1997 I-131 -0.0153 0.2503. 0.0855 0.2257 -0.0504 i 0.1685 l
[ MI-2828,2829 May,1997 K-40 1,786.4000 i l26.0000 1,897.0000 i 192.0000 1,841.7000 i 114.8260 GJ2879,2880 May,1997 Co-60 0.0044 i 0.1100 -0.0207 0.2030 -0.0081 0.1154 f ~ G-2879,2880 May, '1997 Cs-134 0.0081 i 0.0305 -0.0030 i 0.0133 0.0025 0.0166 l- G -2879,2880 May,1997 Cs-137 0.0006 0.0234 0.0013 i 0.0166 -0.0010 i 0.0143 ! 1G-2879,2880 May,1997 Gr. Beta ' 6.4712 i 0.2029 6.6206 i 0.1927 6.5459 i 0.1399 l - G - 2879,2880 May,1997 I-131(g) 0.0093 i 0.0456 0.0220 i 0.6620 0.0157 0.3318 i G.-2879,2880 May,1997 K-40 6.2539 i 0.8340 -5.7979 i 0.7160 '6.0259 0.5496
- l. S O -2904,2905 May,1997 Co-60 -0.0097 i 0.0201 -0.0021 0.0224 -0.0059 0.0150
.S O - 2904,2905 - May,1997 Cs-134 ' O.0348 i 0.0682 0.0208 0.1500 0.0278 0.0324 I L O - 2904,2905 May,1997 Cs-137 0.2709 i 0.0541 0.2768 0.0463 0.2738 i 0.0356
'S O - 2904, 2905.- May,1997 Gr. Beta 24.4695 i 2.3915 26.5459 i 2.5962 25.5077 i 1.7649 t 2 S O - 2904,2905 May,1997 K-40 18.8100 i l.0100 19.1610 i 0.8920 18.9855 0.6738-
- F - 2926,2927- May,1997 Co-60 0.0071 i 0.0082 .-0.0010 i 0.0015. 0.0031 i 0.0042 .i p F - 2926,2927 May,1997 Cs-137 -0.0047 i 0.0122 -0.0029 i 0.0088 -0.0038 i 0.0075 3 - SW - 3008,3009 . May,1997 H-3 101.2957 i 91.5729 123.2634 92.4471 112.2795 65.0616 MI-3050,3051 May,1957 Sr-89 -0.1527 i 0.9022 0.0234 i 0.8795 .-0.0646 1 0.6300 MI- 3050,3051. May,1997 Sr-90 0.9779 i 0.3707 0.9427 i 0.3596 0.9603 1 0.2583 F - 3070,3071 : May,1997 ' Co-60 -0.0093 i 0.0979 0.0094 i 0.0303- 0.0000 1 0.0512
! - F - 3070,3071 . May,1997 Cs-137 0.0064 i 0.0113 -0.0003 i 0.0078 0.0030 i 0.0069
~
~G - 3090,3091 ' May,1997 K-40 5.0649 i 0.2170 4.9752 1 0.2830 5.0201 1 0.1783 MI- 3116,3117 May,1997 I-131 -0.1346 i 0.1762 -0.0964 i 0.1650 -0.1155 0.1207 1 F- 3277,3278 May,1997 Gr. Beta - 2.9487 i 0.1093 3.0022 i 0.1035 2.9755 0.0753
- F-3277,3278 - May,1997 . K-40 - 2.8485 i 0.2780 2.4647 i 0.3130 2.6566 i 0.2093
- MIi3232,3233 May,1997 .I-131 -0.1723 i 0.2021 -0.2680 i 0.2044 -0.2202 1 0.1437
' MI- 3232,3233 - May,1997 K-40 1,550.6000 i 121.0000 1,517.9000 i 141.0000 1,534.2500 1 92.9005 BS - 3311,3312 May,1997 Co-60 -0.0035 0.0348 -0.0044 i 0.0031 -0.0039 i 0.0175 BS - 3311,3312 May,1997 Cs-137 0.0676 i 0.0334 0.0677 i 0.0297 0.0676 i 0.0223
- F-3484,3485 May,1997 K-40 2.4582 i 0.3320 1.8380 i 0.2990 2.1481 i 0.}234
? W - 3533,3534 May,1997 H-3 -95.4129 1 90.4309 -117.7172 i 89.5093 -106.5650 1 63.6193
= WW - 3395,3396.- May,1997 I-131 -0.1507 i 0.1841 -0.0473 i 0.2108 -0.0990 i 0.1399 175-
- Divis-Besse Nucle r Power Station 1997 Annual Radiological Environmental Operating Report -
r,> {
. Table A-5. -In-house " duplicate" samples.
Concentration in pCi/L' 1 ,. Lab Sample First Second Averaged I L Codes
- Date ? Analysis Result .. Result - Result j
. F - 3720,3721 - May,1997 K 2.6063 i 0.4030 2.6623 i 03390 2.6343 i 0.2633 LW - 3464,3465 May,1997 - Co-60 -
-0.2860t i.2700 -0.0583 i 0.0489 -0.1722 1 0.6355-l L 4 LW - 3464,3465 . May,1997 Cs-137 2.4600 1 2.8100 1.5000 i 3.2400 1.9800 i 2.1444 l LW - 3464,3465 ' May,1997 Gr. Beta 3 3532 1 0.9801 3.7723 i 0.9839 3.5628 i 0.6944 -
SW - 3883,3884 May,1997 ' . H-3 -20.5031 i 87.7694 124.8827 1 93.7412 52.1898 i 64.2084 MI- 3513,3514 :Jun,1997 I-131 -0.1592 i 0.1592 -0.1028 i 0.1714 -0.1310 1 0.1170 j
- MI- 3513,3514 .Jun,1997 K-40 1,5603000i129.0000 ~ 1,521.9000 i 179.0000 1,541.1000 i 110 3200 P.- 3794,3795 Jun,1997. H-3 109.9207 1 93.1034 24.2198 i 89.6079 67.0702 i 64.6100 F - 4049,4050 Jun,1997. K-40 2.8350 i 03980 3.0237 1 0.2420 2.9294 1 0.2329 l- ' MI-3903,3904 Jun,1997 I-131 ' O.1550 i 0.1840 -0.1290 i 0.1587 0.0130 i 0.1215
' MI-3903,3904 Jun,1997 K-40 2,020.1000 i 142.0000 1,822.5000 i 188.0000 1,9213000 i 117.8007.
s ~ VE - 3839,3840 Jun,1997 Gr. Alpha 0.2489 0.0857 'O.1876 i 0.0698 0.2183 i 0.0553 , L VE -3839,3840 Jun,1997. Gr. Beta 4.4859 i 0.4451 4.1281 i 0.4123 43070103034 !
- VE - 3839,3840 - Jun,1997 K-40 5.4016 03360 = 4.6'/83i0.4282 5.0400 i 0.2721- I
= F- 3928,3929 Jun,1997 Co -0.0025 i 0.0121 0.0045 i 0.0034 . 0.0010 1 0.0063 F - 3928,3929 Jun,1997 = Cs-134 0.0050 i 0.0115 -0.0030 i 0.0114- 0.0010 1 0.0081-F - 3928,3929 ' Jun,1997- Cs-137 0.0841 1 0.0225 0.07 % i 0.0286 0.0818 i 0.0182
~
F -3928,3919 Jun,1997 Gr. Beta 2.7146 i 0.0950 2.6357 i 0.0977 2.6752 i 0.0681 .i F- 3928,3929 Jun,1997 I-131(g) . 0.0206 1 0.0449 0.0158 1 0.0458 0.0182 1 0.0321 F- 3928,3929 Jun,1997 K-40 1.8883 i 0 3970 1.4854 i 03 780 1.6869 i 0.2741 SWU - 3980,3981 Jun,1997 Gr. Beta 2.1443 1 0.6206 23149 i 0.6407 2.2296 2 0.4460
. SWU - 3980,3981 Jun,1997 H-3 221.0233 i 89.9165 -105.6271 i 85.0852 1633252 i 61.8960
- CW - 3948,3949 Jun,1997 Gr. Beta -0.4402 i l.0747 -0 3764 i l.1259 -0.4083 1 0.7782
- SW - 4150,4151 Jun,1997 H-3 30.4430 i 77.1886 56.0152 78 3895 43.2291 1 55.0068 MI- 4091,4092 Jun,1997 I-131 -0.0475 i 0.1439 .-0.0071 1 0.1516 -0.0273 i 0.1045 SWT- 4240,4241 Jun,1997- Gr. Beta 2.1204 i 0.6338 2.8553id.6330 2.4879 0.4479
' SW - 5186,5187 Jun,1997 H-3 1903311 i 89.7491 192.1730 i 89.8246 191.2521i 63.4SS9
. DW - 4280,'4281 Jun,1997 Gr. Alpha -0.4934 t o.7635 -0.4930 i 0.7640 -0.4932 0.5401 DW - 4280,4281 Jun,1997- Gr. Beta 2.0633 i 0.8600 2.0630 i 0.8700' 2.0631 0.6117
- WW - 4811,4812 ' .
Jun,1997 H-3 ' 48.4888 i 83.6998 50.3302 i 83.7808 49.4095 59.2133
? CW 4 5207,5208 Jun,1997 H-3 151.5810 i 88.1060 135.0114 i 87.4113 143.2962 1 62.0552
~
QSW - 4364,4365 Jun,1997' H-3 83.4415 i 83.9269 94.4046 i 84.4029 88.9230 59.5138 l ' AP-4983,4984 Jun,1997 Co-60 -0.0002 i 0.0009 0.0001 1 0.0007 -0.0000 t 0.0006 AP- 4983,4984 Jun,1997- Cs-137 0.0003 i 0.0004 -0.0001 i 0.0007 0.0001 1 0.0004
- AP-5004,5005 - .Jun,1997 Co-60 0.0002 i 0.0002 0.0003 i (0008 0.0002 i 0.0004
[ ' AP-5004,5005 :Jun,1997 Cs-137 -0.0002 1 0.0004 0.0002 i 0.0006 -0.000010.0dO4 DW - 4484,4485 Jun,1997 Gr. Beta 2.0708 i 0.6272 1.9172 1 0.5805 1.9940 i 0.4273 176
Davis-Besse Nuclear Power Station 1997 Annual Radi: logical Environmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result 1 DW - 4484,4485 Jun,1997 H-3 39.2579 i 83.2425 66.8612 i 84.4541 53.0596 59.2913 SW - 4460,4461 Jul,1997 Gr. Beta 1.8471 i 0.7685 2.2801 i 0.7788 2.0636 0.5471 DW - 4510,4511 Jul,1997 H-3 1.2216 i 80.7150 21 3 772 81.6249 11.2994 573967 AP - 4917,4918 Jul,1997 Co-60 0.0002 i 0.0003 0.0002 i 0.0006 0.0002 0.0003 l
.AP - 4917,4918 Jul,1997 Cs-134 0.0002 1 0.0003 0.0002 0.0052 0.0002 1 0.0026 AP - 4917,4918 Jul,1997 Cs-137 0.0005 i 0.0004 0.0002 1 0.0004 0.0003 0.0003 AP - 4917,4918 Jul,1997 I-131(g) -0.0009 i 0.0017 0.0022 i 0.0762 0.0006 i 0.03S1 AP- 4917,4918 Jul,1997 K-40 0.0239 i 0.0081 0.0305 1 0.0086 0.0272 0.0059 SP - 5024,5025 Jul1997 Gr. Alpha 0.4224i0.9602 1.7836 i 1.2429 1.1030 0.7853 {
SP - 5024,5025 Jul,1997 Sr-90 65.8931 i 7.2660 61.7".18 6.1959 63.8024 i 4.7745 l l BS - 4573,4574 Jul,1997 K-40 11.9570 1 0.5550 12.0610 0.5170 12.0090 03792 WW - 4535,4536 Jul,1997 Co-60 -0.0955 0.4620 1.0800 i l.5100 0.4923 0.7895 WW - 4535, 4536 Jul,1997 Cs-137 -0.7200 i 2.3500 0.1650 33100 -0.2775 2.0297 l WW - 4535,4536 Jul,1997 H-3 565.2121 1 103.8753 524.7523 102.4326 544.9822 i 72.9426 G - 4745,4746 Jul,1997 Co-60 -0.0147 1 0.1270 -0.0016 0.0036 -0.0082 0.0635 , G - 4745,4746 Jul,1997 Cs-134 0.0055 0.0386 -0.0118 0.0963 -0.0032 0.0519
'i-4745,4746 Jul,1997 Cs-137 0.0057 i 0.0186 0.0132 1 0.0180 0.0095 i 0.0129 G - 4745,4746 Jul,1997 Gr. Beta 5.0148 i 0.1659 4.7792 i 0.1700 4.8970 i 0.1188 )
G - 4745,4746 Jul,1997 I-131(g) 0.0040 t 0.0078 0.01041 0.0269 0.0072 i 0.0140 l G - 4745,4746 Jul,1997 K-40 4.5596 i 0.5840 4.1530 1 0.6150 4 3563 i 0.4241 ) SWU - 4832,4833 Jul,1997 Gr. Beta 2.7683 0.6756 3.4254 i 0.6591 3.0968 0.4719 LW - 4782,4783 Jul,1997 Co-60 2.8200 i 203000 -1.9900 1 6.6500 0.4150 10.6807 LW - 4782,4783 Jul,1997 Cs-137 0.6730 i 3.2000 -0.6030 i 2.2500 0.0350 i 1.9559 LW - 4782,4783 Jul,1997 Gr. Beta 4.0046 i 1.0458 3.5274 i 0.9990 3.7660 0.7232 M1 - 4897,4898 Jul,1997 I-131 -0.0412 i 0.2182 0.0463 1 0.2335 0.0026 0.1598 MI- 4897,4898 Jul,1997 K-40 1,5313000 i 123.0000 1,270.5000 1 152.0000 1,400.9000 i 97.7663 l CW - 5150,5151 Jul,1997 Gr. Deta 4.7218 1.5818 4.2648 i 1.6666 4.4933 i 1.1488 CW - 5150,5151 Jul,1997 Gr. Beta -0.2253 1.0995 0.5464 1.2464 0.1605 0.8310 G - 5296,5297 Jul,1997 K-40 6.8000 i 0.6000 8.2000 0.8000 7.5000 0.5000 WW - 5369,5370 Jul,1997 H-3 18,013.8557 373.4409 18,133.8988 1 374.6263 18,073.8773 i 264.4820 CW - 5321,5322 Jul,1997 Gr. Beta 1.5612 i 1.4170 1.3507 i 1.2764 1.4560 0.9535 CW - 5321,5322 Jul,1997 Gr. Beta -0.6334 i 1.0849 0.5162 i 1.2191 -0.0586 i 0.8160 WW - 5348,5349 Jul,1997 H-3 1,763.0308 1 139.9964 1,813.1908 i 141 3214 1,788.1108 99.4620 MI-5464 p5465 Jul,1997 I-131 -0.2555 i 0.2878 -0 3511 i 0.2946 -03033 0.2059 MI-5464,5465 Jut 1997 K-40 1,282.9h)0i143.0000 1,380.0000 1 124.0000 1,331.4500 94.6375 VE - 5506,5507 Jul,1997 Gr. Beta 7.2756 1 0.2197 7.0057 i 0.2090 7.1407 1 0.I'516 VE- 5506,5507 Jul,1997 K-40 8.1566 1 03970 8.1817 i 0.4360 8.1692 0.2948 177
r Davis-Bcsse Nuclear Power Station 1997 Annual Radiological Environmental Opercting Report Table A-5. In-house " duplicate" sarnples. Concentration in pCi/L' Lab Sample First Second Averaged Codes? Date Analysis Result Result Result kVW - 5848,5849 Jul1997 H-3 51.6431 83.4870 40.4434 i 82.9847 46.0433 i 58.8569 WW - 5529,5530 Aug,1997 Gr. Beta 5.1545 1 2.1632 4.3564 i 1.9691 4.7555 i 1.4626 WW - 5529,5530 Aug,1997 H-3 235.5502 i 91.5917 372.4741 97.6610 304.0122 66.9453 MI- 5606,5607 Aug,1997 I-131 -0.0759 i 0.3043 -0.1020 1 0.3423 -0.0889 0.2290 SL - 5563,5564 Aug,1997 Gr. Deta 1.9301 0.2206 2.0961 1 0.2125 2.0131 0.1531 SL - 5563,5564 Aug,1997 K-40 1.1254 i 0.3530 1.3185 1 0.4050 1.2220 0.2686 SL - 5563,5564 Aug,1997 Sr-89 -0.0078 1 0.0216 0.0096 i 0.0196 0.0009 i 0.0146 SL-5563,5564 Aug,1997 Sr-90 0.0097 i 0.0059 0.0031 1 0.0048 0.0064 0.0038 I SW - 5584,5585 Aug,1997 Gr. Beta 2.9875 i 0.7744 2.0205 1 1.0326 2.5040 0.6454 LW - 5678,5679 Aug,1997 Co-60 0.4180 1.2900 0.7270 i 1.4500 0.5725 i 0.9704 LW - 5678,5679 Aug,1997 Cs-134 0.8140 0.6510 0.8340 0.4840 0.8240 i 0.4056 j LW - 5678,5679 Aug,1997 Cs-137 1.1400 1 1.1800 0.7750 i 1.1900 0.9575 1 0.8379 l LW - 5678,5679 Aug,1997 Gr. Beta 2.6926 1 0.6727 2.4242 1 0.6023 2.5584 1 0.4515 ) LW - 5678,5679 Aug,1997 I-131 -0.1036 1 0.3234 -0.0921 i 0.3371 -0.0979 0.2336 I LW - 5678,5679 Aug,1997 I-131(g) -10.1000 i 11.1000 -3.6000 i 5.8200 -6.8500 i 6.2666 LW - 5678,5679 Aug,1997 K-40 137.0000 16.5000 124.0000 i 17.3000 130.5000 i 11.9535 G -5653,5654 Aug,1997 K-40 6.0419 1 0.5940 5.5554 0.5870 5.79S7 i 0.4176 CW - 5759,5760 Aug,1997 Gr. Beta 4.3051 i l.5501 2.0048 i l.4570 3.1550 i l.0637 CW - 5759,5760 Aug,1997 G r. Beta -0.5860 1.1030 -0.0177 i l.1407 -0.3018 0.7934 CW - 5708,5709 Aug,1997 Gr. Beta 1.7190 i 1.4125 1.8843 1 1.4139 1.8017 i 0.9993 MI- 5891,5892 Aug,1997 I-131 0.0000 i 0.2400 0.1928 i 0.2253 0.I)964 i 0.1646 MI-5891,5892 Aug,1997 K-40 1,438.6000 1 131.0000 1,218.6000 1 175.0000 1,328.6000 i 109.3000 MI- 5926,5927 Aug,1997 I-131 -0.0311 1 0.1690 -0.1446 1 0.1748 -0.0879 1 0.1216 MI-5926,5927 Aug,1997 K-40 1,577.8000 1 216.0000 1,429.9000 178.0000 1,503.8500 i 139.9464 SWU - 5972,5973 Aug,1997 H-3 274.7574 1 93.6817 157.2707 i 88.8812 216.0140 1 64.5681 CW - 6013,6014 Aug,1997 Gr. Beta 4.9801 i l.3048 4.5882 1 1.6114 4.7841 1 1.0367 CW - 6013,6014 Aug,1997 Gr. Beta -0.5668 1.0528 -0.6145 1 1.1307 -0.5907 0.7725 SL - 6034,6035 Aug,1997 Co-60 0.0183 0.0235 0.0159 i 0.2550 0.0171 1 0.1280 SL- 6034,6035 Aug,1997 Cs-134 0.0046 1 0.0136 0.0015 i 0.0020 0.0030 0.0069 SL - 6034,6035 Aug,1997 Cs-137 0.0118 0.0097 0.0175 1 0.0098 0.0147 i 0.0069 SL - 6034,6035 Aug,1997 Gr. Beta 2.1826 i 0.1949 1.9837 i 0.1773 2.0831 1 0.1317 I SL- 6034,6035 Aug,1997 I-131(g) -0.0039 i 0.0134 0.0013 i 0.0060 -0.0013 0.0073 SL - 6034,6035 Aug,1997 K-40 1.6231 i 0.2940 1.4676 i 0.2750 1.5454 0.2013 CW - 6172,6173 Aug,1997 Gr. Beta 3.2828 1 1.0951 3.7336 1.6212 3.5082 i 0.9782 CW - 6172,6173 Aug,1997 Gr. Beta 1.2291 i 1.3108 0.0271 1 1.1175 0.6281 1 0.8612 CW - 6080,6081 Aug,1997 Gr. Beta 2.4263 i 1.5665 4.0378 i 1.5325 3.2321 1 1.0957 CW - 6080,6081 Aug,1997 Gr. Beta -0.0198 i l.1927 0.9870 1 1.1701 0.4836 0.8354 l 178
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Ikport f Table A-5. In-house " duplicate" samples. Concentration in pCi/L' 12b Sample First Second Averaged Date Analysis Result Result Result Codes
- VE - 6106,6107 Aug,1997 Co-60 0.0021 i 0.0173 0.0019 i 0.0087 0.0020 0.0097 VE - 6106,6107 Aug,1997 Cs-137 0.0017 i 0.0057 -0.0005 1 0.0072 0.0006 1 0.0046 VE - 6149,6150 Aug,1997 Co-60 0.0043 i 0.1740 0.0004 0.0012 0.0024 0.0870 VE - 6149,6150 Aug,1997 Cs-137 -0.0026 i 0.0056 0.0018 0.0060 -0.0004 0.0041 MI- 6203,6204 Aug,1997 Co-60 2 3200 1 83.8000 0.7940 i 1.9700 1.5570 1 41.9116 MI - 6203,6204 Aug,1997 Cs-137 0.5560 i 3.0200 1.2900 1 2.6500 , 0.9230 2.00S9 MI- 6203,6204 Aug,1997 I-131 -0.2456 i 03252 -0.1688 1 03245 -0.2072 0.2297 VE - 6224,6225 Aug,1997 Co-60 -0.0042 i 0.0160 0.0045 i O.0078 0.0002 0.0089 VE - 6224,6225 Aug,1997 Cs-137 -0.0057 i 0.0131 0.0071 0.0047 0.0007 0.0070 VE - 6251,6252 Aug,1997 Gr. Beta 3.4988 i 0.1337 3.5009 0.1338 3.4998 1 0.0946 VE - 6251,6252 Aug,1997 K-40 3.8744 i 0.5410 3.3980 i 0.6150 3.6362 1 0.4095 !
MI - 6335,6336 Aug,1997 I-131 0.0196 i 0.2826 0.0564 1 0.2698 0.0380 i 0.1953 MI - 6335,6336 K-40 1,488.7000e t%0000 1,5384 000 1 116.0000 1,513.6500 1 86 3713 Aug,1997 SL - 6982,6983 Aug,1997 Co-60 0.0869 i o.0110 0.0888 i 0.0135 0.0879 0.0087 SL - 6982,6983 Aug,1997 Cs-137 0.0826 1 0.0110 0.0993 1 0.0165 0.0909 0.0099 SL - 6982,6983 Aug,1997 Gr. Beta -0.7733 i 0.1093 -0.6988 i 0.0989 -0.7361 0.0737 WW - 6312,6313 H-3 4,401.6798 i 200.9023 4,585.7685 1 2043507 4,493.7241 143.2837 Aug,1997 LW - 6560,6561 Aug,1997 Gr. Alpha 0.4838 1 03847 0.7647 1 0 3421 0.C?42i 0.2574 LW - 6560,6561 Aug,1997 Gr. Beta 1.6502t 03609 1.6339 1 03320 1.6420 1 0.2452 LW - 6560,6561 Aug,1997 H-3 164.1455 i 90.4249 131.5719 i 89.0337 147.8587 i 63.4501 2 1774 i 0.4247 LW - 6520,6521 Sep,1997 Gr. Beta 1.9762 i 0.5715 23786 1 0.6284 LW - 6520,6521 Sep,1997 H-3 104.7304 87.8580 66.4144 i 86.1708 85.5724 61.5314 CW - 6489,6490 Sep,1997 Gr. Beta 0.2448 i l.3049 1.9046 i 1 3290 1.0747 0.9313 G - 6773,6774 K-40 3.7979 i 0.2420 3.5568 i 0.3270 3.6774 1 0.2034 Sep,1997 CW - 6796,6707 Gr. Beta 3.3658 1 1.5585 5.0139.t l.1808 4.1899 i 0.9777 Sep,1997 CW - 6796,6797 Sep,1997 Gr. Beta -1.1040 i 1.0241 -0.7623 1 1.0723 -0.9332 i 0.7414 SWU - 7009,7010 Sep,1997 Cr. Beta 3.2034 0.6793 3.2645 0.6681 3.2339 0.4764 SWU - 7009,7010 Sep,1997 H-3 165.8491 i 90 515 150.5986 i 89.9273 158.2239 63.8164 G - 6820,6821 K-40 4.811.5 i 0.4160 4.7307 i 0.5360 4.7710 1 0.3392 Sep,1997 0.0177 0.1519 0.0180 1 0.1520 0.0179 i 0.1074 l MI-6M6 6887 Sep,1997 I-131 MI - 6886,6887 K-40 1,241.7000 i 155.0000 1,062.0000 i 156.0000 1,151.8500 109.9557 I Sep,1997 WW - 7031,7032 Sep,1997 H-3 -38.0852 1 81.4466 -19.0426 82 3323 -28.5639 57.9054 CW - 6907,6908 Sep,1997 Gr. Deta 3.8333 i 1.5682 4.5001 i 1.6814 4.1667 1.1496 CW - 6907,6908 Sep,1997 Gr. Beta -0.0397 i 1.1726 -0.1621 1.1478 -0.1009 0.8204 F - 7221,7222 Sep,1997 K-40 3.0101 i 03970 2.6722 1 0.4720 2.8412 i 03084 CW - 7177,7178 Sep,1997 Gr. Deta 0.5864 i 0.9867 2.3794 i 1.4286 1.4829 i 0.8681 CW - 7177,7178 Sep,1997 Gr. Beta -1.0971 1 1.0379 -0.1387 i 1.1507 -0.6179 0.7748 l 179
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table A-5. In-house duplicate" samples. Concentration in pCi/L' Lab Sample . First Second Averaged Codes
- Date Analysis Result Result Result LW - 7198,7199 - Sep,1997 Gr. Beta 1.6523 1 0.6116 2.3619 i 0.6044 2.0071- 0.4299 VE - 7141,7142 Sep.1997 Co-60 ' O.0012 i 0.0118 -0.0001 1 0.0004- 0.0005 0.0059 VE - 7141,7142 Sep,1997 Cs-137 -0.0011 1 0.0090 0.0081 i 0.0103 0.0035 i 0.0068 SWU - 7364,7365 Sep,1997 Gr. Beta 2.4372 1 0.6226 2.7949 1 0.6153 2.6160 0.4377 SWU - 7364,7365 Sep,1997 H-3 245.3799 i 94.1721 269.0627 i 95.15'96 257.2213 i 66.9398 l WW - 7408,7409 ' 2.0100 6.7100 1.2135 i 3.3788 l Sep,1997. Co-60 0.4170 i 0.8010 WW - 7408,7409 Sep,1997 Cs-137 -0.2190 1 1.6500 0.8220 1 3.0600 0.3015 i 1.7383 )
WW - 7408,7409 Sep,1997 H-3 7,907.0011 i 264.0275 7,543.2790 1 258.5239 7,725.1400 i 184.7601 1 LW - 7765,7766 Sep,1997 Gr. Alpha 0.2614 i 0.4857 0.3882 1 0.5450 0.3248 0.3650 ! LW - 7765,7766 Sep,1997 Gr. Beta 3.6490 1 0.5140 2.7232 1 0.4728 3.1861 0.3492 LW - 7765,7766 Sep,1997 H-3 3,168.6312 176.2295 3,030.6146 i 173.2010 3,099.6229 1235470 AP - 8208,8209 Sep,1997 Co-60 0.0002 0.0004 0.0004 1 0.000S 0.0003 0.0005 , AP - 8208,8209 Sep,1997 Cs-137 0.0003 i 0.0005 -0.0004 i 0.0006 -0.0000 0.0004 G - 7244,7245 Oct,1997 Gr. Beta 9.0000 1 0.3000 8.4000 1 0.3000 8.7000 0.2121 ! 1 G -7244,7245 Oct,1997 K-40 8.8853 i 0.7960 9.1594 1 0.7550 9.0224 0.5186 l G - 7244,7245 Oct,1997 Sr-89 -0.0058 1 0.0181 -0.0056 0.0097 -0.0057 0.0103 G - 7244,7245 Oct,1997 Sr-90 0.0053 1 0.0052 0.0017 0.0029 0.0035 0.0029 G - 7265,7266 Oct,1997 K-40 6.5763 1 0.5250 .6.0640 1 0.6540 6.3202 0.4193 , 1 SW - 7313,7314 Oct,1997 Gr. Deta 24.5727 2.0773 21.9706 1 2.0623 23.2717 i 1.4636 l SW - 7313,7314 Oct,1997 K-40 114.6700 i 41.9000 90.9920 37.6000 102.8310 28.1486 G - 7432,7433 Oct,1997 Co-60 0.0073 i 0.0252 0.0041 1 0.0059 0.0057 0.0129 G - 7432,7433 Oct,1997 . Cs-134 0.0057 0.0110 0.0009 i 0 0010 0.0033 0.0055' G - 7432,7433 Oct,1997 Cs-137 0.0863 i 0.0217 0.0835 i 0.0247 0.0849 0.0164 G - 7432,7433 Oct,1997 Gr. Beta 5.3675 i 0.2025 5.3318i0.2123 5.3496 0.1467 ; G - 7432,7433 Oct,1997 1-131(g) -0.0038 i 0.0069 0.0218 1 0.4830 0.0090 0.2415 G - 7432,7433 Oct,1997 K-40 4.4899i0.e020 4.9632 1 0.5470 4.7266 0.3394 CW - 7339,7340 Oct,1997 Gr. Beta 0.2969 i 1.2051 -0.2575 i 0.8630 0.0197 i 0.7411 AP - 7537,7538 Oct,1997 Sr-89 0.0006 1 0.0008 -0.0001 1 0.0008 0.0002 0.0006 AP - 7537,7538 Oct,1997 Sr-90 -0.0001 i 0.0003 0.0001 i 0.0003 0.0000 0.0002 CW - 7560,7561 C t,1997 Gr. Beta 3.7764 i 1.5088 3.7707 1 1.5155 3.7735 i 1.0692 CW - 7560,7561 Oct,1997 Gr. Beta 0.4496 i l.1864 0.3374 t l.2009 0.3935 0.8440 F - 7474,7475 Oct,1997 Co-60 -0.0010 0.0016 0.0020 1 0.0058 0.0005 0.0030 F - 7474,7475 Oct,1997 Cs-137 0.0071 i 0.0064 0.0001 i 0.0113 0.0036 0.0065 F,- 7495,7496 Oct,1997 Co-60 0.0025 1 0.0076 0.00 % i 0 1430 0.0055 0.0716 F - 7495,7496 Oct,1997 Cs-137 O.0078 i 0.0083 0.0044 i 0.0056 0.0061 0.0050 F - 7626,7627 Oct,1997 K-40 2.2464 0.3120 1.5663 i 0.3760 1.9064 1 0.1443 CW - 7669,7670 Oct,1997 Gr. Beta 5.7005 t l.8448 3.6801 1 1.7132 4.6903 1.258t. 180
Davis-Besse Nucear Power Station 1997 Annual Radiological Environmental Operating Report - Table A-5. I Jn-house " duplicate" samples. Concentration in pCi/L'
., Lab Sample First Second Averaged -
Codes * . Date - Analysis . Result Result - Result - CW - 7669,7670. Oct,1997. Gr. Beta - -0.0304 1.1674- 0.1259 t l.1344. 0.0478 0.8139 L WW - 7648,7649 - Oct,1997 ' Co-60 383320 i 4 3000 - 31.7400 1 3.3600 35.0360 2.7285 . L WU? - 7648, 7649 . Oct,1997 Cs-137 2.8800 i 2.3000 - 0.5180 i 1.9100 1.6990 1 1.4948 WW - 7648,7649 Oct,1997 ' H-3 2413364 105.7031 265.5372 i 106.6226' 253.4368 75.0692
. MI- 7787,7788 : Oct,1997 I-131 ' 0.0456 i 0.2490 0.0257 i 0.2696- -0.0099 1 0.1835 ; MI .7787,7788. . ~Oct,1997 K-40 1,514.0000 1 114.0000 . 1,684.0000 i 102.0000 1,599.0000 76.4853 'S O - 8010, 8011 Oct,1997 .Cs-137 0 3513 i 0.0712. 0 3182 i 0.0693 - 03347 0.0497
- S O 8010,8011. Oct,1997 K-40 22.4300 i 13200 22.0830 i 1.2900 22.2565 0.9228 l SL- 8123,8124 Oct,1997 Cs-137 0.0368 i 0.0335 0.0242 i 0.0137- 0.0305 0.0181-SL- 8123,8124 Oct/1997 K 2.8000 i 0.5510 ' 2.5777 i 0.2960 2.6889 03127 F-7915,7916 ' Oct,1997 Cs .137 0.0072 i 0.0118 0.0031 1 0.0085 0.0052 0.0073 -
- MI- 7968,7969 Oct,1997 I-131 -0.1451 1 03579 -0.4853 03455 -03152 0.24S7 MI- 7968,7969 Oct,1997 L K 40 1,324.1000 i 132.0000 f,313.0000i 118.0000 1,318.5500 88.526S-MI-7968,7%9 - Oct,1997 Sr-90 1.2892 i 0.4152 1.2892 i 0.7200 1.2892 0.4156 ~ VE~- 7934,7935 Oct,1997 Co-60 0.0071 i 0.1160 -0.0029 i 0.0139 0.0021 0.0384 VE - 7934,7935 .Oct,1997 ' ~ Cs-137 0.0022 1 0.0110. -0.0041 0.0099 -0.0010 0.0074 SWU - 8946,8947 - Oct,1997. Gr. Beta 2.9772 i 0.6530 2.2888 i 0.5953 2.6330 1 0.4418 SWU - 8946,8947 .Oct,1997 : H-3 .187.7210 1 97.3682 -125.5659 i 94.9331 156.6435 67.9943 - CW - 8230,8231 - Oct,1997 Gr. Beta 3.6262 1 1.7126 4.9561 1 1.7938 4.2911 1.2400
- CW - 8230,8231 Oct,1997- Gr. Beta 1.7276 i 0.9533 . 0.1316 1 1.1929 0.9296 i 0.7635 ,
CW - 8100,8101 Oct,1997 Gr. Beta 4.1481 i 1.6095 4.5744 i 1.5764' 4 3612 i 1.1264 CW - 8100,8101 - - Oct,1997 : Gr. Beta ' -0.5655 i 0.8528 0.9791 i 1.2280 '0.2068 0.7475-
"SS - 8501, 8502 Oct,1997 Gr. Alpha'. 7.9580 i 3.4566 6.5709 i 3.1487 7.2645 2.3379 i SS - 8501, 8502 - Oct,1997 . Gr. Beta 19.4568 i 2.9472 17.6686 1 2.6664 18.5627 1.9S72 i SS .8501, P502 ' Oct,1997 ~ K-40 . 12.4630 i 0.4450- 13.4420 i 0.7910 12.9525 0.4538 - CW - 8316,8311 Oct,1997 ' Gr. Beta 2.1293 i 1.4423 2.1830
- 1.4550 -2.1562 i 1.0243 CW - 8310,8311 - Oct,1997 . Gr. Beta 0.1798 i 1.1387 -0.0397 i 1.1504 0.0701 0.8093 iCW - 8376,8377 Oct,1997 Gr. Beta 4.7932 i 2.0194 7.3047 i 1 36371 6.0490 1.2184 ;
CW _8376,8377. - Oct,1997 Gr. Beta 0.5653 i 1.8020 -0.0566 i 1.7632 0.2544 1.2606 ' l
. MI- 8442,8443 Oct.1997 I-131 -0.0290 1 0.2689 - 0.1059 i 0.2666 0.0384 0.1893 ! . MI- 8442,8443 ~ O.t,1997 ~ K 1,591.7000 1 178.0000 1,456.0000 i 116.0000 1,523.8500 106.2309 SWU i 8543,8544~ 'Oct,1997 - Gr. Beta : 2.2027 1 0.6193 2.1585 i 0.6134 2.18 % 0.4358 SWU - 8543,8544 Oct,1997 H-3 120.4712 i 87.0152 174.9557 89.2606 147.7134 623280 WW - 8473,8474 Oct,1997 - H -28.9600 i 77.6404 27.1500 i 80.2139 -0.9050 55.8174 J WW - 8566,8567 Oct,1997 Co-60 0.4520 i l.7400 0 3400 1 4.0500- 039601 22040' > WW - 8566,8567 - Oct,1997 : Cs 137. 1.0300
- 2.2000 -0.7300 1 2.8600 0.1500 13041
? LW - 8608,8609 - Oct,1997 Gr. Beta - 2.8483 1 0.6660 23035 1 0.6052 2.5759 i 0.4500 181 -
]
; Davis-Besse Nuclear Power Statirn 1997 Annual Radiological Environnuntal Operating Report ,
l l I
' Table A-5. - In-house " duplicate" samples.' l Concentration in pCi/l * ;
Lab Sample . First Sec'o nd Averaged ~ Codes * , Date i Analysis . . Result - Result . Result .!
' MI- 8587,8588 ' Nov,1997J I-131 ' -0.0013 1 0.13 % 0.0109 i 0.1350 0.0048 0.0971 MI-8587,8588 Nov,1997 K 1,441.6000 i 160.0000 1,499.6000 1 176.0000 1,470.6000 1 118.9285 WW - 8654,8655 - Nov,1997 Gr. Beta 0.6704 i 0.5213 ' O.8560 0.5226 0.7632 0.3691 WW - 8654,8655 Nov,1997 - H-3 -131.2268 i 87.3749 87.6861 85.5477 109.4565 61.1408 -1 CW - 8753,8754 ' Nov,1997 Gr. Beta 5.4805 1 1.9992 4.3820 2.0409- ~4.931211.4285 : - CW - 8753,8754 Nov,1997 Gr. Beta 0.2821 i 1.7806 0.1129 i 1.7701.. 0.1975 1.2554 i F- 9131,9132 Nov,1997 ~ Cs-137 0.0576 i 0.0192 0.0568 i 0.0171 0.0572 i 0.0129- I F- 9131,9132 Nov,1997 Gr. Beta 2.9445 i 0.0965 3.0473 1 0.0919 2.9959 i 0.0666 I ~ F - 9131,9132 Nov,1997 K-40 2.3452 i 0.3460 2.4680 i 0.3260 2.4066 0.2377
- CW - 8854,8855 Nov,1997 Gr. Beta 5.6208 i 1.7991 3.5028 1 1.6326 4.5618 1.2147
' CW - 8854,8855 Nov,1997 Gr. Beta 0.0000 i 1.1731 0.6107 1.1604 0.3053 0.8250
)
WW - 9087,9088 Nov,1997 H-3 - 20.1985 81.0438 73.4489 i 83.4219 46.8237 i 58.1535 l i
. WW - 9160,9161 Nov,1997 Co-60 -0.9580 i 9.1800 -0.4340 4.2400 -0.6960 1 5.0559 WW - 9160,9161 Nov,1997 Cs-137 -0.1440 1 2.3300 -0.5270 i 2.0700 -0.3355 1.5583 SWT - 9341,9342 Nov,1997 Cr. Beta 1.4657 i 0.7780 2.7123 0.8202 2.0890 0.5652 CW - 9410,9411 Dec,1997 Gr. Beta 3.2958 i 1.5674 4.2062 i 1.5722 3.7510 i 1.1100 CW - 9410,9411 Dec,1997 Gr. Beta 0.6244 1 1.1948 -0.6229 i 1.0939 0.0007 0.8099 CW- 9466,9467 Dec,1997 Gr. Beta 1.6082 i 1.6557 2.0375 i l.6921 1.8228 1.1837 CW- 9466,9467 Dec,1997 Gr. Beta -0.0563 i 1.7639 -1.1838 i 1.6912 -0.6201 i 1.2218 -! - WW - 9603,9604 Dec,1997 Co-60 1.7300 i 1.7600 -0.6190 1 0.7560 0.5555 1 0.9577 -
WW - 9603,9604
- Dec,1997 Co-60 1.7300 i 1.7600 -0.0389 i 0.3420 0.8f56i 0.8%5 !
WW - 9603,9604 Dec,1997 - Cs-137 0.4460 i 2.0800 0.0557 1 1.2900 - 0.2509 1.2238 dW - 9789,9790 Dec,1997 Co-60 0.1010 i 0.1080 0.1510 i 2.0300 0.1260 1 1.0164- - LW'- 9789,9790 Dec,1997 Cs-137 1.0000 1 2.1300 0.9130 i 2.0300 0.9565 1.4712 .) LW - 9789,9790 Dec,1997 Gr. Beta 5.6924 i 1.0952 4.5180 1 0.7757 5.1052 0.6711 CW - 9947,9948 Dec,1997 Gr. Beta 0.9320 1 0.9447 1.5072 0.9762 1.2196 0.6792 AP - 10249,10250 Dec,1997 Co-60 . 0.0000 1 0.0001 0.0004 i 0.0016 0.0002 0.000S
- AP- 10249,10250 Dec,1997 Cs-137 0.0005 i 0.0008 0.0002 0.0003 0.0004 0.0004 ,
- All concentrations are reported in pCi/ liter, except solid samples, which are reported in pCi/ gram.
- Lab codes are comprised of the sample media and the sample numbers. Client codes have been eliminated to protect client anonymity.
~
182
Divis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP), comparison of MAPEP and Teledyne's Midwest Laboratory results for various sample media'. Concentration
- Lab . Sample Date Teledyne Results MAPEP Result' Control Code Type Collected Analysis iStandard Deviation
- 1s, N=1 Limits STW-751 WATER Sep,1995 Am-241 1.370 0.720 1.320 0.070 1.056 - 1.5S4 STW-751 WATER Sep,1995 Co-57 91.000 1 0.950 92.380ic.600 73.904 - 110.856 STW-751 WATER Sep,1995 Cs-137 55.000 0.500 58.770 1 0.730 47.016 - 70.524 STW-751 WATER Sep,1995 Mn-54 99.170 1.600 99.080 1.000 79.264 - 118.896 STW-751 WATER Sep,1995 Pu-238 1.700 t 0.040 1.830 1 0.080 1.464 - 2.196 STW-751 WATER Sep,1995 Pu-239 1.380 1 0.220 1.340 1 0.060 1.072 - 1.60S STW-751 WATER Sep,1995 Sr-90 13.730 0.950 15.690 0.300 12.552 - 18.82S STW-751 WATER Sep,1995 U-234 0.630 1 0.070 0.650 i 0.050 0.520 - 0.780 STW-751 WATER Sep,1995 U-238 0.700 0.020 0.650 0.050 0.520 - 0.780 STSO-776 SOIL Sep,1996 Am-241 27.000 28.700 2.830 20.900 - 37.310 Standard deviation for three determinations not reported in Mixed Analyte Performance Evaluation Program Summary Report.
STSO-776 SOIL Sep,1996 Co-60 879.000 812.000 i S3.500 568.400 - 1,055.600 STSO-776 SOIL Sep,1996 Cs-137 1//16.000 1,531.000 i 193.420 1,071.700 - 1,990.300 STSO-776 SOIL Sep,1996 Pu-238 13.000 15.900 1.770 11.130 - 20.670 STSO-776 SOIL Sep,1996 Pu-239/240 18.000 19.700 1 1.960 13.790 - 25.610 STSO-776 SOIL Sep,1996 Sr-90 441.000 536.000 1 57.110 375.200 - 696.800 STSO-776 SOIL Sep,1996 U-234/233 59.000 63.900 7.270 44.730 - 83.070 STSO-776 SOIL Sep,1996 U 238 60.000 64.000 1 6.360 44.800 - 83.200
- Results obtained by Teledyne Brown Enginee-ing Environmental Services Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho,
- All results are in Bq/kg or Dg/L as requested by the Department of Energy.
- Unless otherwise indicated, the TBEESML results are given as the mean i i standard deviations for three determinations.
' MAPEP nesults are presented as the known values and expected laboratory precision (1 sigma,1 determination) and control limits as defined by the MAPEP.
l l l l l
/
~
183 !
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML), l l comparison of EML and Teledyne's Midwest Laboratory results for various sample media *. Concentration in Dq/L* Sample Date Control Lab d Code Type Collected Analysis Teledyne Result
- EML Result Limits' STW-755 WATER Mar,1996 Am-241 0.800 1 0.100 0.766 0.013 0.660 - 1.560 STW-755 WATER Mar,1996 Co-60 33.600 i 1.000 32.800i0.5SO 0.870 - 1.170 STW-755 WATER Mar,1996 Cs-137 42.800i 1300 38 300 i 0.881 0.900 - 1.250 l WATER Mar,1996 Fe-55 109.000 1 21.700 83.000 3.440 0.270 - 1.620 STW-755 WATER Mar,1996 H-3 434.000 i 34.100 251.000 11.400 0.690 - 1.910 STW-755 WATER Mar,1996 Mn-54 41.900 1 1.400 38.400 i l.160 0.880 - 1.210 STW-755 WATER Mar,1996 Pu-238 0.900 i 0.100 0.982 i 0.074 0.680 - 1330 STW-755 WATER Mar,1996 Pu-239 0.700 i 0.100 0.772 1 0.056 0.620 - 1.380 STW-755 WATER Mar,1996 Sr-90 2.200 i 0.700 1.450 0.034 0.730 - 1.650 STW-755 WATER Mar,1996 Gr. Alpha 2,180.000 i S3.500 1,850.000 185.000 0.550 - 1 310 STW-756 WATER Mar,1996 Gr. Beta 872.000 i 27.000 744.000 74.000 0.750 - 1.650 STW-756 SOIL Mar,1996 Am-241 6.230 i 2.880 3.690 0.454 0.520 - 2.410 STSO-757 SOIL Mar,1996 Cs-137 404.000 i 0.150 359.000 10.000 0.740 - 1.400 STSO-757 SOIL Mar,1996 K-40 525.000 1 23300 465.000 ~20.000 0.700 - 1.590 STSO-757 SOIL Mar,1996 Pu-238 42.300i t.590 43.000 1.440 0.220 - 1.990 STSO-757 STSO-757 SOIL Mar,1996 Pu-239 9.000 i 0.700 9.230 0336 0.620 - 1.990 SOIL Mar,1996 Sr-90' 1,200.000 i 32300 1,340.000 i 113.000 0.580 - 2.960 STSO-757 SOIL Mar,1996 Uranium 68.200 i 2.400 71.700 4.150 0.270 - 1.480 STSO-7f7 VEGETATION Mar,1996 Am-241 6.100 i 13 00 5.600 1 0.184 0.580 - 2.860 STVE-758 VEGETATION Mar,1996 Cm-244 6.000i t.200 4.440 0.202 0.400 - 1.870 STVE-758 VEGETATION Mar,1996 Co-60 65.600 t 4.000 59.700 1 0.963 0.q40 - 1.490 STVE-758 VEGETATION Mar,1996 Cs-137 1,100.000 12.600 944.000 i 16.200 0.750 - 1.480 STVE-758 VEGETATION Mar,1996 K-40 1,190.000 61.600 1,030.000 1 33.000 0.450 - 1.510 STVE-758 VEGETATION Mar,1996 Pu-239 9.200 i 1300 9.820 i 1.220 0.600 - 1.980 STVE 758 VEGETATION Mar,1996 Sr-90 1,210.000 32.200 1,300.000 52.400 0.500 - 1 3 70 STVE-758 AIR FILTER Mar,1996 Am-241 0.270 i 0.040 0.189 1 0.007 0.620 - 1.930 STAF-759 AIR FILTER Mar,1996 Cc-144 23.200 1 1.020 3330013300 0.610 - 1.310 STAF-759 AIR FILTER Mar,1996 Co-57 6.050 1 0.130 8.900 1 0.900 0.630 - 1.290 STAF-759 AIR FILTER Mar,1996 Co-60 26.500 0.430 29.500 i 2.900 0.740 - 1.250 STAF-759 AIR FILTER Mar,1996 Cs-134 12.900 1 0.280 14.700 i l.460 0.700 - 1.210 STAF-759 AIR FILTER Mar,1996 Cs-137 6.200 0.900 6.640 i 0.700 0.720 - 1 320 STAF-759 AIR FILTER Mar,1996 Mn-54 3.270 0350 3.4401 0380 0.760 - 1 330 STAF-759 AIR FILTER Mar,1996 Pu-238 0.080 0.020 0.096 i 0.002 0.610 - 1.550 STAF-759 AIR FILTER Mar,19% Pu-239 0.090 1 0.020 0.093 i 0.003 0.670 - 1.580 STAF-759 AIR FILTER Mar,1996 Ru-1% 10.200 1 1.850 11.600 1.440 0.540 - 1.590 STAF-759 AlR FILTER Mar,1996 Sb-125 10.100 1 0.750 9.780 i 1.030 0350 - 1.400 STAF-759 AIR FILTER Mar,19% Sr-90 1.070 1 0.230 1.060 i 0.037 0.(20 - 2.260 f STAF-759 AlR FILTER Mar,1996 Uranium 0.118 i 0.020 0.107 i 0.003 0.790 - 2.880 S TAF-759 184
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operrting Report j Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML), comparison of EML and Teledyne's Midwest Laboratory results for va' .ous sample media'. Concentration in Bq/L' Lab Sample Date Control Code Type Collected Analysis Teledyne Result
- EML Result' Limits' STAF-760 AIR FILTER Mar,1996 Gr. Alpha 2.210 i 0.050 1.620 0.150 0.820 - 1.580 STAF-760 AIR FILTER Mar,1996 Gr. Beta 1.950 0.040 1.770 0.150 0.750 - 1.940 STW-770 WATER Sep,1996 Am-241 1.300 i 0.200 1.080 1 0.040 0.640 - 1.730 STW-770 WATER Sep,1996 Co-60 65.000 i 2.210 61.100 1 0.730 0.920 - 1.180 STW-770 WATER Sep,1996 Cs-137 96.100 3.010 89.500 1.3'6 0 0.900 - 1.280 STW-770 WATER Sep,1996 Gr. Alpha 993.000 12.200 1,210.000 1 121.000 0.500 - 1.290 STW-770 WATER Sep,1996 G r. Deta 579.000 8.070 540.000 54.000 0.600 - 1.640 STW-770 WATER Sep,1996 H-3 488.000 i 34.600 587.000 i S8.000 0.650 - 1.910 STW-770 WATER Sep,1996 Mn-54 65.000 1 2.960 60.500 1 0.550 0.870 - 1.220 STW-770 WATER Sep,1996 Pu-238 1.320 i 0.333 1.910 i 0.070 0.740 - 1.270 An investigation was conducted. No errors in calculations or transc~iption were noted. The analysis was repeated in duplicate under the observation of the Technical Lead. No discrepancies were noted in the performance of the procedure. The result of the reanalysis was 2.14i0.* 1 Bq/L No further action is planned.
STW-770 WATER Sep,1996 Pu-239 0.698 0.247 0.840 i 0.030 0.780 - 1.420 STW-770 WATER Sep,1996 Sr-90 3.600 1 0.700 2.710 i 0.240 0.720 - 1.660 STW-770 WATER Sep,1996 U-234 0.517 0.196 0.480 i 0.040 0.770 - 1.530 STW-770 WATER Sep,1996 U-238 0.416 i 0.118 0.480 0.370 0.770 - 1.350 STSO-771 SOIL Sep,1996 Am-241 15.600 1 3.830 13.500 0.510 0.520 - 2.650 STSO-771 SOIL Sep,1996 Co-60 4.030 2.500 2.920 1 0.210 0.500 - 1.500 STSO-771 SOIL Sep,1996 Cs 137 1,750.000 24.400 1,550.000 22.200 0.800 - 1.340 STSO-771 SOIL Sep,1996 K-40 369.000 59.500 300.000 i 25.000 0.730 - 1.670 STSO-771 SO!L Sep,1996 Pu-238 0.770 1 0.360 1.130 i 0.240 0.4CIO - 1.900 STSO-771 SOIL Sep,1996 Pu-239 24.000 1.940 21.800 1.080 0.660 - 1.930 STSO-771 SOIL Sep,1996 Sr-90 63.600 3.950 69.900 i 5.100 0.460 - 2.840 STSO-771 SOIL Sep,1996 U-234 37.200 3.750 39.200 2.440 0.380 - 1.260 STSO-771 SOIL Sep,1996 U-238 40.800 3.980 41.600 t 0.610 0.350 - 1.550 STVE-772 VEGETATION Sep,1996 Arn-241 1.530 0.884 1.230 1 0.410 0.680 - 2.780 STVE-772 VEGETATION Sep,1996 Cm-244 0.612 1 0.495 0.830 i 0.120 0.490 - 1.690 STVE-772 VEGETATION Sep,1996 Co-60 14.000 4.420 10.900 0.710 0.620 - 1.420 STVE-772 VEGETATION Sep,1996 Cs-137 219.000 i 10.100 190.000 i 6.680 0.810 - 1.450 STVE-772 VEGETATION Sep,1996 K-40 1,160.000 99.400 992.000 1 29.000 0.790 - 1.500 STVE-772 VEGETATION Sep,1996 Sr-90 1,420.000 35.100 1,390.000 1 12.000 0.480 - 1.290 STAP-773 AIR FILTER Sep,1996 Co-57 11.800 i 0.296 14.800 1 0.814 0.620 - 1.220 STAP-773 AIR FILTER Sep,1996 Co-60 9.230 i 0.402 8.640 1 0.431 0.740 - 1.240 STAP-773 AIR FILTER Sep,1996 Cs-134 9.620 0.376 10.800 0.392 0.720 - 1.210 STAP-773 AIR FILTER Sep,1996 Cs-137 8.720 i 0.403 8.520 1 0.366 0.720 - 1.320 STAP-773 AIR FILTER Sep,1996 Gr. Alpha 0.731 1 0.037 1.150 i 0.110 0.830 - 1.550 An investigation was conducted and a transcription error while calculating the resul,was t discovered. The recalculated value is 1.1510.01Bq/ filter. No further action is planned. " 185
l Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Reprt Table A-7. Enviromnental Measurements laboratory Quality Assessment Program (EML), comparison of EML and Teledyne's Midwest Laboratory results for various sample media'. Concentration in Bq/L' Lab Sample Date Control Code Type Collected Analysis Teledyne Result' EML Result d Limits
- STAP-773 AIR FILTER Sep,1996 Gr. Beta 05401 0.037 0.500 i 0.050 0.730 - 1.840 STAP-773 AIR FILTER Sep,1996 Mn-54 7.0601 0.472 6350 0.270 0.750 - 1.270 STAP-773 AIR FILTER Sep,1996 Ru-106 11.500 3.190 10.800 ~1.140 0.580 - 1 300 STAP-773 AIR FILTER Sep,1996 Sb-125 12.400 1 0.965 10.800 0.540 0.600 - 1 390 STW-788 WATER Mar,1997. Am-241 0.840 1 0.220 0.837 0.028 0.640 - 1.730 l
STW-788 WATER Mar,1997 Co-60 96.000 3.500 90.850 1.150 0.920 1.180 STW-788 WATER Mar,1997 Cs-137 77.00013500 69.780 i 1.230 0.900 - 1.280 STW-788 WATER Mar,1997 Fe-55 175.500 i 25.400 235.000 20.000 0310 - 1.540 STW-788 WATER Mar,1997 Gr. Alpha 1,042.600 i 36.800 1,130.000 10.000 0.500 - 1.290 STW-788 WATER Mar,1997 Gr. Beta 591.400 1 23300 744.000 10.000 0.600 - 1.640 STW-788 . WATER Mar,1997 H-3 272.000 1 29.700 250.300 4.200 0.650 - 1.910 STW-788 WATER Mar,1997 Mn-54 23.700 3.400 20.850 0310 0.870 - 1.220 STW-788 WATER Mar,1997 Pu-238 1.400 i 0.200 1.291 i 0.063 0.740 - 1.270 STW-788 WATER Mar,1997 Pu-239 0.900 1 0.100 0.850 0.050 0.780 - 1.420 STW-788 WATER Mar,1997 Sr-90 25.500 1 1.700 23.200 1.350 0.720 - 1.660 l STW-788 WATER Mar,1997 U 1.500 0.200 1.105 0.050 0350 - 1.420 l STSO-790 SOIL Mar,1997 Am-241 6.740 3.730 5.680 0.500 0.520 - 2.650 STSO-790 SOIL Mar,1997 Co-60 2.010 i 1.170 1.060 i 0.120 0500- 1.500 The sample size was too small for an accurate measurement. The activity i error overlap the known value. STSO-790 SOIL Mar,1997 Cs-137 918.640 i 8.400 825.500 1 14.100 0.800 - 1 340 STSO-790 SOIL Mar,1997 K-40 359.140 32.100 334.250 7.140 0.730 - 1.670 STSO-790 SOIL Mar,1997 Pu-238 0 300 i 0.200 0.530 i 0.110 0.400 - 1.900 STSO-790 SOIL Mar,1997 Pu-239 132.420 i 5.170 134.930 1 17.100 0.660 - 1.930 STSO-790 SOIL Mar,1997 Sr-90 38.830 1 5.770 40310i0.420 0.460 - 2.840 STSO-790 SOIL Mar,1997 U 79.260 1 3.800 81.270 1 4.830 0.270 - 1.360 STVE-791 VEGETATION Mar,1997 Am-241 1.673 i 0.688 1.183 i 0.113 0.680 - 2.780 STVE-791 VEGETATION Mar,1997 Cm-244 0.688 1 0.468 0.9M i o.050 0.490 - 1.690 STVE-791 VEGETATION Mar,1997 Co-60 16.914 i 3.580 12.500 0320 0.620 - 1.420 STVE-791 VEGETATION Mar,1997 Cs-137 216.667 1 9383 189.250 7.270 0.810 - 1.450 STVE-791 VEGETATION Mar,1997 Pu-239 1.771 1 0.817 1.942 0.222 0.650 - 1.950 STVE-791 VEGETATION Mar,1997 Sr-90 361.130 1 19.715 361.000 43300 0.480 - 1.290 STAP-792 AIR FILTER Mar,1997 Co-57 9.528 1 0.230 10.810 1.000 0.620 - 1.220 STAP-792 AIR FILTER Mar,1997 Co-60 5.325 1 0.266 5.010 0300 0.740 - 1.240 STAP-792 AlR FILTER Mar,1997 Cs-134 10.767 i 0337 10.880 1 1.000 0.720 - 1.210 STAP-792 AIR FILTER Mar,1997 Cs-137 9.116 1 0.404 8.700 0.800 0.720 - 1.320 STAP-792 AIR FILTER Mar,1997 Gr. Alpha 1.1991 0.045 0.960 0.050 0.830 - 1.550 STAP-792 AJR FILTER Mar,1997 Gr. Beta 0.608i0.024 0.450 1 0.030 0.730 - 1.840 STAP-792 AIR FILTER Mar,1997 Mn-54 8.494 1 0.429 7.620 1 0.600 0.750 - 1.270-
.s 186
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Reprt Table A-7. Environmental Measurement.s Laboratory quality Assessment Program (EML), comparison of EML and Teledyne's Midwest Labcratory results for various sample media *.
, Concentration in Bq/L' Lab Sample Date Code Type Control Collected Analysis Teledyne Result' EML Result' Limits
- STAP,.2 AlR FILTER Mar,1997 Pu-238 0.022 i 0.016 0.100 1 0.006 0.620 - 1.460 The cause of the deviation for the transuranic analysis (Pu-238,239, U) is unknown. A dilution error is suspected.The analysis is being repeated.
STAP-792 AIR FILTER Mar,1997 Pu-239 0.031 0.010 0.119 0.006 0.500 - 1.500 STAP-792 AIR FILTER Mar,1997 Sb-125 14.118 1.099 12.330 1 1.000 0.600 - 1.390 STAP-792 AIR FILTER Mar,1997 Sr-90 1.291 0.275 1.450 i 0.149 0.660 - 2.650 STAP-792 AIR FILTER Mar,1997 U 0.150 0.020 0.211 0.003 0.808 3.360 STW-805 WATER Sep,1997 Co-60 23.630 i l.450 23.300 1.200 0.920 - 1.180 STW-805 WATER Sep,1997 Cs-134 63.500 i 2.600 66.000 2.600 0.500 - 1.500 STW-805 WATER Sep,1997 Cs-137 34.880 1 2.430 34.300 1.700 0.900 - 1.280 STW-805 WATER Sep,1997 Fe-55 101.730 33.530 115.000 10.000 0.310 - 1.540 STW-805 WATER Sep,1997 Gr. Alpha 597.000 12.000 557.000 60.000 0.500 - 1.290 STW-805 WATER Sep,1997 Gr. Beta { 985.000 13.000 712.000 70.000 0.600 - 1.640 STW-805 j WATER Sep,1997 H-3 227.600 1.800 115.000 1 6.000 0.650 - 1.910 The sample was acidic, causing a breakdown of resin in the tritium column. The sample was neutralized to pH 7 and reanalyzed. Results of reanalysis: 116.2i3.6 Bq/L STW-805 WATER Sep,1997 Mn-54 38.480 1 3.230 37.800 1.900 0.870 - 1.220 STW-805 WATER Sep,1997 Sr-90 3.460 0.690 2.940 i 0.180 0.720 - 1.660 STVE-806 VEGETATION Sep,1997 Co-60 32.330 5.560 32.400 i 1.600 0.620 - 1.420 STVE-806 VEGETATION Sep,1997 Cs-137 627.330 1 16.670 624.000 31.000 0.810 - 1.450 STVE-806 VEGETATION Sep,1997 K-40 1,091.670 95.180 1,130.000 70.000 0.79,0 - 1.500 STVE-806 VEGETATION Sep,1997 St-90 1,335.000 i 32.000 1,434.000 i 75.000 . 0.480 - 1.290 STSO-807 SOIL Sep,1997 Cs 137 1,239.440 22.460 810.000 40.000 - 0.800 - 1.340 The sample size was not standard. The sample was reanalyzed using a different geometry. Results of reanalysis: Cs-137 - 813.li9.0 Bq/kg; K-40 -275.9 34.6 Bq/kg. STSO-807 SOIL Sep,1997 K-40 478.000 29.000 315.000 1 70.020 0.730 - 1.670 STSO-807 SOIL Sep,1997 Pu-239 10.800 1 0.400 10.160 0.370 0.660 - 1.930 STSO-807 SOIL Sep,1997 Sr-90 31.480 1 5.560 34.750 i 1.000 0.460 - 2.840 STSO-807 SOIL Sep,1997 U 57.000 1.100 72.900 1 0.850 0.270 - 1.360 STAP-808 AIR FILTER Sep,1997 Gr. Alpha 1.820 i 0.080 1.490 0.090 0.830 - 1.550 STAP-808 AIR FILTER Sep,1997 Gr. Beta 3.250 0.080- 3.000 0.140 0.730 - 1.840 STAP-808 AIR FILTER Sep,1997 Pu-238 0.230 i 0.100 0.210 i 0.007 0.620 - 1.460 STAP-808 AlR FILTER Sep,1997 U 0.130 i 0.100 0.110 i 0.004 0.800- 3.360
' STAP-809 AIR FILTER Sep,1997 Ce-144 16.250 i l.670 19.120 1 0.700 0500 - 1.500
- STAP-809 AIR FILTER Sep,1997 Co-57 10.570 1 0.270 12.640 i 0.430 0.620 - 1.220 STAP-809 AIR FILTER Sep,1997 Co-60 9.820 0.270 10.730 1 10.900 0.740 - 1.240 STAP-809 AlR FILTER Sep,1997 Cs-134 24.700 1 0.490 28.170 1 0.730 STAP-809 AIR FILTER Sep,1997 Cs-137 0.720 - ljl0 7.240 0.370 7.310 i 0.250 0.720 - 1.320~
STAP-809 AIR FILTER Sep,1997 Mn-54 6.800 i 0.430 6.720 i 0.270 0.750 - 1.270 ' I87 i
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t I Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report i Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML), ! comparison of EML and Teledyne's Midwest Laboratory results for various sample media'. Concentration in Bq/L" j Lab Sample Date Control Code Type Collected Analysis Teledyne Result' EML- Result' Limits
- STAP-809 AIR FILTER Sep,1997 Sb-125 17.980 i l.270 i
16.120 0.790 0.600 - 1.390 ) STAP-809 AIR FILTER Sep,1997 Sr-90 2.830 i 0.370 2.760 1 0.100 0.660 - 2.650
- The Environmental Measurements Laboratory provides the following nuclear species : Air Filters, Soit, 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 Dq/Kg, Vegetation results are reported in Bq/Kg.
- Teledyne results are reported as the mean of three determinationsistandard deviation.
' The EML result listed is the mean of replicate determinations for each nuclideithe standard error of the mean.
- The controllimits are reported by EML as the ratio of Reported Value / EML Value and are established from percentiles of historic data distributions (19821992). The evaluation of this historic data and the development of the control limits is present'ed in DOE report EML-564.
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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report APPENDIX B DATA REPORTING CONVENTIONS
=
B-1 '; 189
Davis-Besse Nuclear Power Station 1997 Annual Radiologiccl Environmental Operating Report Data Rennr+ing (*nnvanH^nt 1.h All activities except gross alpha and gross beta are decay corrected to collection time or the end of the collection period. 2.0. Single Measurernent< Each single measurement is reported as follows: x s where x = value of the measurement; s = 2s counting un:ertainty (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 4/4s uncertainty for a background sample. 3.0. nupliente analyses 3.1 Individual re<ntese xlis1 x1is2 Reoorted recule xis where x = (1/2)., (xlix2) - 2 2 s= (1/2) s+s g 2 3.2. Indivl'dual re<ults: <L1
<l2 Reoorted re< ult- <L where L = lower of L1 and L2
- 33. Individual results: xs
<L Reoorted result- xis if x214 /
~
<L otherwise l
190
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmentil Operating Rrport 4.0. Comontation of Averaces and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurernents 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. . .nx are defined as follows: 1 x =- Ex 5" I(x-x)2 n-1 42 Values below the highest lower limit of detection are not included in the average. 45 If all of the values in the averaging group are less than the higlest LLD, the highest LLD is reported. 4.4 If all but one of the values are less than the highest LLD, the' single value x and associated two sigma error is reported. 4.5 In rounding off, the following rules are followed: 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example,11.443 is rounded l off to 11.44. i 4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure j is dropped and the last retained figure is raised by 1. As an example,11.445 is j rounded off to 11.45. j i 1 i l
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191
' Davis Besse Nuclear Power Station 1997 Annual Radiological Emironmental Operating Rcport l
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APPENDIX C Emuent Concentration Limit of
' Radioactivity in Air and Water Above Natural Background in Unrestricted Areas I
I 1 l l 192 l
Davis-Besse Nuclear Power Stati:n 1997 Annual Radiologicsl Environmental Opcrating Rcport Table C-1 Efiluent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas' Air Water 3 Gross Alpha IE-03 pCi/m Strontium-89 8,000 pCi/l 3 Gross Beta 1 pCi/m Strontium-90 500 pCi/l b Iodine-131 2.86E-01 pCi/m' Cesium-137 1,000 pCi/l Barium-140 8,000 pCi/1 1 Iodine-131 1,000 pCi/l Potassium-40' 4,000 pCill Gross Alpha 2 pCi/l Gross Beta 100 pCi/l Tritium lx106 pCi/l l 1 Taken from Code of Federal Regulation Title 10, Part 20, Table II and appropriate footnotes. Concentrations may be averaged over a period not greater than one year. I b i From 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting from the air- t grass-cow-child pathway. A natural radionuclide. 193 ,
[ I Davis-Besse Nuclear Power Station 1997 Annual Radiil gical Emironmental Operating Report l l l APPENDIX D REMP SAMPLING SUMMA.RY
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l 194
Davis-Besse Nuclear PowerStation 1997 Annual Radiological Environmental Operating Report Table 4.5 RadiologicalEnvironmentalMondoringProgramSummary.
' Nameof Facility Davis-Besse Nudear PowerStation Docket No. '50-346 location of Facility Ottawa. Ohio - Reporting Period . Januarv - December 1997 (County, State)
Indscator taation with Highest Control Number Sample Type and Locations Annual Mean Type . locations . Non-Number of LLob Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analysesa locationd .Rangec Range Results' Alvbome CB 520 0.005I 0.019 (312/312) T-11, Port Clinton, particulates 0.024 (52/52) 0.021 (207/208) o (0.006-0.044) 9.5 mL SE (0.00S-0.056) (pCi/m3) (0.006-0.056). Sr-69 -40 0.0010 <LLD - -
<LLD 0 Sr-90 ' 40 0.0007 <LLD - -
<LLD 0 CS' 40 Be-7 0.015 0.079 (24/24) T 11, Port Clinton, 0.0S8 (4/4) 0.083 (16/16) 0 (0.055-0.10) - - 9.5 mi. SE (0.075-0.10) (0.054-0.11)
K-40 0.039 <LLD - -
<LLD 0 Nb-95 0.0016 <LLD - -
<LLD 0 Zr 0.0026 <LLD - -
<LLD- 0 Ru-103 0.0013 <LLD - -
<LLD 0 Ru 106 0.011 <LLD - -
<tLD 0 Cs-134 ' O.0018 <LLD - -
<LLD' O Cs-137 0.0013 <LLD - -
<LLD 0 Ce-141 0.0022 <LLD - -
<LLD #
Ce-144 0.0063 <LLD - -
- <LLD 0 Airterne lodine 1131 520 0.07I <LLD - -
<LLD 0 (pCi/m3).
ILD(Quarterly) Camma 289 1.0 13 5 (245/245) T-8. Farm, 19.6 (4/4) 14.1 (44/44) 0 (mR/91 days) (7.3-22.4) 2.7 mi WSW . (18.2 22.4) (10.6-18.1) u., 4 TLD (Quarterly) Camma 4 1.0 5.6 (4/4) - (mR/91 days) None 0
',(5.5-5.9)
. (Shield)
TLD (Annual) Camma 66 1.0 53.8 (55/55) ' T-8. Farm, 0 (mR/365 days) 77.1 (1/1) 59.0 (11 /11) (32.6 77.1) 2.7 mi WSW (45.0-72.2) TLD (Annual) Camma 1 1.0 21.5 (1/1) - - None 0 (mR/365 days) p .. (Shield) { i s j
*e% .
I i 195 l
,i Davis-Besse Nuclear Power Station : 1997 Annual Radiological Environm:ntal Operating Report Table 4.5 RadiologicalEnv'i-:- :O! Monitoring Program Summary.
~
Nameof Facility Davis-Besse Nuclear Power Station Dociwt No- . _50-346 location of Facility Ottawa, Ohio Reporting Period E uary Decemtwr tw7 (County, State) . I - Indicator . Location with Highest : Control - Number Sample Type and locations Annual Mean . Locations Non. LType. Number of LLDb Routine Mean (F)C Mean (F)C Mean (F)c
. (Umts)
Analyses
- Rangec. Locationd gange c Range- Results' s
Milk (pC1/L). I131: 12 0.5 none- - .
<LLD- 0 Sr-89 12 1.1. none - -
~ <LLD 0 I
1 Sr 12 0.7 none T-24,Sandusky, k 1.1 (11/12) - . 1.1 (11/12) . O i 21.0 mise (0.8-1.8) (0.5-1.8) !1 GS 12 K-40 100 none T-24, Sandusky, 0 1430 (12/12) 1430 (12/12) 21.0 mise (1330-1570) (1330-1570) Cs 137 10 ' none - -
<LLD 0 Ba-La 140 10 none - -
<LLD 0 (g/L) Ca 12 0.50 none T 24, Sandusky, 0.88 (12/12) 0.88 (12/12) 0 21.0 mise (0.78-0.97) (0.78497)-
(g/L) - ) K(stable) 12 . 0.1 none T 24, Sandusky, 1.65 (12/12) 1.65 (12/12) 0 21.0 mi SE
-l
. (1.54-1.81) (1.541.tll)
(pCi/g) Sr 90/Ca 12' O.36 none T 24,Sandusky, 1.20 (12/12) 1.20 (12/12) 0
- l 21.0 mise - (0.81 2.02) (0.til-2.02) j
; (pC1/g) Cs 137/K 12 6.48 none. - . <LLD 0 Cround Water CB (TR) 12 4.0 6.8 (6/8) T-7, Sand Beach.- 7.3 (4/4) 5.7 (2/4) .0 (pCi/L) (4.6-8.6) 0.9 mi NW (6.3-8.6) 3 I
H3 12 330 355 (1/8) T-7, Sand Beach, 355 (1/4)- <LLD 0 0.9 mi NW Sr-89 12 1.4 <LLD - . <LLD 0 St-90 12 0.6 <LLD . -
<LLD 0 CS 12 Mn 54 <LLD 15 - -
<LLD 0 Fe-59 30 <LLD - -
<LLD 0 Co-58 15 <!LD - -
<LLD 0 Co-60 15 <LLD - -
<LLD 0 Zn 30 <LLD - -
<LLD 0 Zr 95 15 <LLD . -
<LLD 0 s Cs 134 10 <tLD . . <LLD 0 Cs-137 10 <LLD . 7 <LLD 0 Ba-La 140 15 - <LLD - . <LLD 0 E 196 .
Davis-Besse Nuclear Power Station 1997 Annust Radiological Environmental Operating Report
' Table 4.5 Radiological Environmental Monitoring Program Summary.
Name of Facility Davis-Benee Nudear Power Station Docket No. 50-346 locationof Facility Ottawa, Ohio Reporting Period January December IW7 (County, State) Indicator location with Highest Contml Number Sample Type and . tocations Annual Mean Locations Non-Type Number of Ltob . ~
. Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analyses
- locationd l
kanzec: Ranzec Range Results' Edible Meat CS 2 (pCi/g wet) l K-40 0.1
- 2.92 (1/1) T 197, Farm - 2 92 (1/1) 0 2.55 (1/1) j 1.7 mi. W '
Cs-137 l 0.017 <LLD -
<LLD 0 I p
Sr-89 3 0.001 <LLD - -
<LLD 0 Vegetables (pCi/g wet) Sr 90 3 0.001 <LLD - -
<LLD O' I131 3 0.015 <t LD -
<tLD 0
CS 3 K-40 0.50 1.14 (2/2) T-25, Farm 1.14(1/1) 0.9H (1/1) 0 (1.'.51.14) 3.7 mi S i Nb-95 0.012 <tLD -
<LLD 0
Zr-95 0.023 <LLD - -
<LLD 0 Cs-137 0.013 <LLD l
<LLD 0 Ce-141 0.023 <LLD - -
<LLD 0 Ce-144 0.096 <LLD - -
<LLD 0 8
Broad Leaf St-69 12 0.008 <LLD Vegetation
- - <LLD 0 (pCi/g wet) St-90 12 0.005 <LLD T-37, Fann, 0.010 (1/4) 0.010 (1/4) 0 13.0 mi. SW 1131 12 OSil <LLD - -
<LLD 0 CS 12 K-40 0.1 2.92 (8/8) T-36. Carden 3.36 (2/2) 2.55 (4/4) 0 (1.92-4.32) 2.3 mi. NW (2.40-4.32) (2.17-3.23)
Nb-95 0.018 <LLD - -
<LLD 0
' Zr-95 0.040 <LLD - -
<LLD 1 0 j Cs 137 0.018 <LLD - -
<LLD 0 )
Ce-141 0.038 <LLD - -
<LLD 0 I
i / Ce-144 0.17
/ \
<LLD - -
<LLD 0 % .
t I i 197 i
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 45 Radiological Environmental Monitoring Program Summary. Nameof Facility _ Davis-Besse Nudear Power Station location of Facility _ Ottawa. Ohio Docket No. 50-346 Reporting Period January - Deannber Iw7 (County, State) Sample Indwator location with Highest Type and Locations Control Number Type Number of Annual Mean locatkms Non. (Units) Llob Mean (F)< Analysesa Mean (F)C Mean (F)c Routine RangeC Imcationd Rangee Range Results' l
' Animal . GS 4 Wildlife feed .
(pC1/g wet) Be-7 0.18 'LO! (1/3) T-32, Onsite . 2.01(1/l) <LLD 0 Roving location ) K-40 j 0.1 436(3/3) T 197, Farm
- 7.11 (1/1) 6.21 (1/1) 0 (1.13-7.11) 1.7 mi. W Nb 0.021 <LLD -
<LLD 0
' Zr-95 0.039 <LLD -
<LLD 0 Ru 103 0.023 <LLD -
<tLD i 0 l Ru 106 0.13 <LLD -
<LLD 0 Cs 137 0.017 <LLD -
l
<LLD' O Ce-141 0.033 <LLD -
<LLD .O !
Ce-144 0.10 <LLD -
<LLD 0 Soil CS 20 i . (pCi/g dry)
Be-7 0.62 0.66 (1/12) T 4, Site Boundary, 0.66 (1/2) I
<LLD 0 -'
03 mi.S K-40 1.0 17.45 (12/12) T-9, Oak Harbor , 23.52 (2/2) (10.36-26 04) 6.8 mi.. SW 20.57 (8/8) 0 (1.88-26.tna - Nb-95 0.12 <LLD - -
<LLD 0 Zr 95 0.16 <LLD -
<LLD 0 Ru-103 . 0.061 <LLD -
<LLD 0 Ru 106 0.42 - <LLD. -
<LLD 0 Cs 137 0.029 0.25 (8/12) T-9, Oak Harbor. 0.53 (2/2) 035(7/8) 0 (0.11 0.76) 6.8 mi. SW (0.31-0.75)
(0.11 0.75) Ce-141 0.16 <LLD - -
<LLD 0 Ce-144 032 <LLD -
<LLD 0 Treated CB (TR) 48 1.0 2.3 (24/24) T 50, Erie Ind. Park Surface Water 2.5 (12/12) 2.1 (24 /24) 0 (1.6-3.4) 4.5 mL SE (2.1 3.4) (13-2.6)
(pCl/L) H3 16 330 <LLD - -
<LLD 0 St-89 16 13 <LLD -
<LLD 0 St-90 16 0.7 0.8 (1/8) T 11, T-50 0.8 (2/8) 0.8 (1/t() 0 ~
(Both identical) 198-
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitonng Program Summary. Name of Facility Davi&Besse Nuclear Power Station Docket No. 50-346 1.ocation of Facility _ Ottawa, Ohio Reporting Period January December 1997 (County, State) Indicator Location with !fighest Sample Type and Control Number Locations Annual Mean Non-Type Number of Locati<ms LLob y,,n (p)c Routine l (Units) Analyses a Mean (F)C Mean (F)c Ranget Locationd Rangec Range Results' GS 16 Treated Surface Water (pCi/L) (contmurd) Mn-54 15 <LLD - -
<LLD 0 Fe-59 30 <LLD - -
<LLD 0 Co 15 <LLD - -
<LLD 0 Co-60 15 <LLD - -
<LLD 0 Zn45 30 <LLD -
<LLD 0 Zr-95 15 <LLD - i
<LLD 0 '
Cs 134 10 <LLD - -
<LLD 0 Cs-137 10 <LLD - -
<LLD 0 Da La 140 15 <LLD - -
<LLD 0 Untreated ' GB (TR) 130 1.0 T-152, 3.0 (78 /78) 4.0'(7/7)
Surface Water 2.7 (52/52) O (pCi/L) (1.34.7) Canal Entrance to (2A4.1) (1.7-4.1) Maumee Bay S.P. 15.6 mi. WNW H3 130 130 457 (3/78) T 152, 5 75 (1 / 7) 348 (1/52) 0 (340-575) Canal Entrance to j Maumee Bay S P. 15 6 mi. WNW
$r-89 20 2.4 <tLD - -
<LLD 0 St-90 20 1.2 <tLD -
i
<LLD 0 GS 130
. Mn 54 15 <LLD - -
<LLD 0 Fe-59 30 <LLD - -
<LLD 0 Co-58 15 (LLD - -
<LLD 0 Co40 15 <LLD - -
<LLD 0 Zn-65 30 <LLD - -
<LLD 0 Zr-95 15 <LLD - -
<LLD 0 Cs-134 10 <LLD - -
<LLD 0 Cs-137 10 <LLD -
<LLD 0 Ba La-140 15 <LLD -
<LLD 0 .
.199
Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 45 Radiological Environmental Mondonng Psogram Summary. Nameof Facility Davis-Besse Nudear PowerStation Docket No. 50-346 location of Facility _ ottawa, Ohio Repostin6Period January - Decemtwr 1997 - (County, State) indicator Laation with Highest Control - Number Sample * *pe and locations Annual Mean Locations Non.
.T Nanber of Ltob Routine Mean (F)C Mean (i)< Mean (F)c N 8) Analyses a Rangee Imcationd c Range Resuhs' Rans.e Fish CB 6 0.1 2.80 (3/3) T 35, take Erie, 2.91 (3/3) 0-2.91 (3/3) -
(pCi/g wet) (2.59-2.98) > 10 mL radius (2.77 3.09) - (2.77-3.09) CS' 6 K-40 0.1 2.70 (3/3) T-35, Lake Erie, 2.74 (3/3) 2.74 (3/3) 0 (2.42-3.01) > 10 mL radius (2.38 3.08) (2.38-3.08)
. Mn-54 0.011 <LLD . . <LLD 0 '
Fe-59 0.039 <LLD . . <LLD 0 i Co-58 ! 0.014 <LLD - -
<LLD 0 ,
Co40 0.015 ' <LLD <LLD I 0 j Zn45 0.029 <LLD . . <LLD 0 I Cs-134 0.011 <LLD - . <LLD 0
. Cs 137 0.017 <LLD T-35, Lake Erie, 0.027 (1/3) 0.027 (l/3) 0
> 10 mi. radius Shoreline CS 10 Sediments
- (pCi/g dry) K-40 0.1 12.80 (8/8) T-4P, Site 20.66 (2/2) 9.88 (2/2) 0 (7.09-22.80) Boundary,0.8 mi. S (18.51-22.80) (7.19 12.56)
Mn-54 0.038 <LLD . -
<LLD Co-58 ~
0 0.044 - <LLD ~
<LLD Co40 0.038 <LLD . .
<LLD 0
' Cs-134 0.068 <LLD . . . <LLD o Cs 137 0.043 <LLD - -
<LLD o l
a CB = gross beta, CS = gamma scan,TR = total residue. b LLD = nommat lower limit of detection based on 4.66 sigma counting error for background sample. c Mean based upon detectable measurements only. Fraction of detectable measurements at specifid kwations is indicated in parentheses (F). d i Locations am specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site. I
- Non-soutine results are those which exceed ten times the control station value.
I 3 -1 One result for airborne iodine 131 (<0.12 pC1/m , Station T-9 for the week ending August 19,1997) exceeded the required LLD, due to low volume. The gross beta result for the same week and location (<0.027) was not included in the LLD calculation. 1
) /_ ' l
. m. 200 -
,}}