ML20082V405
| ML20082V405 | |
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| Site: | Davis Besse  |
| Issue date: | 12/31/1994 |
| From: | CENTERIOR ENERGY |
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| NUDOCS 9505090233 | |
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{{#Wiki_filter:r Davis-Besse Nuclesr Power Station 1994 Annual Radiological Environmenta! Operating Report
- I ANNUAL RADIOLOGICAL :
ENVIRONMENTAL OPERATING ~ REPORT : for Davis-Besse Nuclear Power Station January 1,1994 to December 31,1994 Prepared by: Radiation Protection Section Davis-Besse Nuclear Power Station l Toledo Edison Company Toledo, Ohio April 1995 l l 9505090233 941231 PDR ADOCK 05000346 i R PDR l m _ _ _ __ ;
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l l Davis-Besse Nuclear Power Station 1994 AnnualRadiologicalEnvironmenta10perating Report TABLE OF CONTENTS Title Eage a L!st of Tables iv List of Figures vi P Executive Summary viii INTRODUCTION , Fundamentals 1 Radiation and Radioactivity 2 Interaction with Matter 3 Quantities and Units of Measurement 5 Sources of Radiation 7 Health Effects of Radiation 9 Health Risks 10 Benefits of Nuclear Power 11 Nuclear Power Production 11 Station Systems 17 Reactor Safety and Summary 20 Radioactive Waste 20 Description of the Davis-Besse Site 22 References 24 RADIOLOGICAL ENVIRONMENTAL MONITORING I PROGRAM Introduction 26 Preoperational Surveillance Program 26 Operational Surveillance Program Objectives 27 i
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report j Ihlt East , Quality Assurance 27 l Program Description 29 l Sample Analysis 32 ! Sample History Comparison 34 j 1994 Program Deviations 37 j 38 Atmospheric Monitoring Terrestrial Monitoring 45 Aquatic Monitoring 57 Direct Radiation Monitoring 68 Conclusion 79' f References 80 l RADIOACTIVE EFFLUENT RELEASE REPORT ; Protection Standards 83 Sources of Radioactivity Released 83 Processing and Monitoring 84 : Exposure Pathways 85 l Dose Assessment 86 l Results 87 ; i Regulatory Limits 88 ] Effluent Concentration Limits 89 ) 1 Average Energy 89 i Measurements and Approximations of Total Activity 90 Batch Releases 91 { Sources of Input Data 92 Dose to Public Due to Activities Inside the Site Boundary 92 l Inoperable Radioactive Effluent Monitoring Equipment 93 I Changes to the ODCM and PCP 94 Borated Water Storage Tank Radionuclide Concentration 94 ii 1
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Davis-Besse Nuclear Power Station 1994 AnnualRadiologicalEnvironmentalOperating Report r Title Page LAND USE CENSUS Program Design 111 Methodology 111 t Results 112 NON-RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring 118 Marsh Management 144 Water Treatment 146 Chemical Waste Management 151 Waste Minimization and Recycling 155 APPENDICF3 Appendix A: Interlaboratory Comparison Program Results 156 Appendix B: Data Reporting Conventions 183 Appendix C: Emuent Concentration Limit of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas 186 l i
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Appendix D: REMP Sampling Summary 188 i I
Davis Besse Nuclear Power Station 1994 Annua 1 Radiological Environmental Operating Report List of Tables ! Table Page Title Number Number 10 i ' Risk Factors 1 Sample Codes and Collection Frequencies 2 30
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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 Broadleaf Vegetation and Fruit Locations 8 49 Animal / Wildlife Feed Iocations 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 j Shoreline and Bottom Sediment locations 14 62 Fish Locations 15 64 Thermoluminescent Dosimeter Locations 16 70 Gaseous Effluents - Summation of All Releases 17 95 l Gaseous Effluents - Ground Level Releases - Batch Mode 18 % Gaseous Effluents - Ground Level Releases - Continuous 18 97 : Mode Gaseous Effluents - Mixed Mode Releases - Batch Mode 19 99 Gaseous Effluents - Mixed Mode Releases - Continuous 19 100 Mode i Liquid Effluents - Summation of All Releases 20 102 Liquid Effluents - Nuclides Released - Batch Releases 21 103 Liquid Effluents - Nuclides Released - Continuous Releases 21 105 ! Solid Waste and Irradiated Fuel Shipments 22 107 Doses Due to Gaseous Releases 23 108 Doses Due to Liquid Releases 24 109 Dose to The Most Exposed Member of The Public 25 110 iv
r 4 Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Description Hgurg, Eggt , Number Number Direct Radiation Sampling Locations on Davis-Besse Site 26 76 Direct Radiation Sampling Locations within a Five Mile : Radius 27 77 : Direct Radiation Sampling locations within a Twenty-Five , Mile Radius 28 78 Exposure Pathways 29 86 ! Land Use Census Map 30 113 Wind Rose Annual Average 100M 31 127 Wind Rose Annual Average 75M 32 128 Wind Rose Annual Average 10M 33 129 , Wind Rose Monthly Average 100M 34 130 Wind Rose Monthly Average 75M 35 133 i Wind Rose Monthly Average 10M 36 136 Water Treatment Plant Schematic 37 147 : r t P t I i I i 5 5 A e vii
f Davb-Besse Nuclear Power Station 1994 AnnualRadiologicalEnvironmentalOperating Report Executive Summary The Annual Radiological Environmental Operating Report is a detailed report on the Environmental Monitoring Programs conducted at the Davis-Besse Nuclear Power Station from January 1 through December 31,1994. 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 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, Marsh Management, Water Treatment, Chemical Waste Management , and Waste Minimization and Recycling. This report also includes the Radiological Effluent Release Report for July 01 - Dec 31,1994. 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.e and the Davis-Besse Offsite Dose Calculation Manual Section 6.0. This program includes the sampling and analysis of environmental samples and evaluating the effects of relenses of radioactivity on the environment. Radiation levels and radioactivity have been monitored within a 25 mile radius around Davis-Besse for more than 22 years. The REMP was established at Davis-Besse about five years before the Station became operational. This program provided data on background radiation and radioactivity which is normally present in the area. Davis-Besse has continued to monitor the environment by sampling air, groundwater, milk, edible meat, egg, fruit and vegetables, animal feed, soil, drinking water, surface water, fish, bottom and shoreline sediment, and by measuring radiation directly. Samples are collected from both 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. i viii l
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l Davb-Besse Nuclear Power Stauon ' 1994 Annual Radiological Environmental Operating Report j ~' ' Approximately 1,800 radiological environmental samples were collected and analyzed in , 1994. Only 7 intended samples were not collected during 1994; an explanation for the sampic program deviations is provided on page 37.- The results of the REMP indicate that Davis-Besse continues to be operated safely and in j accordance with applicable federal regulations. No measurable increase in background j radiation is attributed to the operation of Davis-Besse. l. 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 1994 results are similar to those observed in preoperational and previous operational programs. Only background and fallout i radioactivity normally present in the environment was detected and only at normal i concentrations.
- Terrestrial monitoring includes analysis of milk, groundwater, meat, fruits, ,
vegetables, animal feed, and soil samples. The results of the analyses of the other l' terrestrial samples also indicate concentrations of radioactivity similar to previous years and indicate no buildup of radioactivity due to the operation of Davis-Besse. l
- Aquatic monitoring includes the collection and analysis of drinking water, untreated :
surface water, fish and shoreline sediments. The 1994 results of analysis for fish, : untreated surface water, drinking water and shoreline sediment indicate normal ! background concentration of radionuclides and show no increase or buildup of l radioactivity due to the operation of Davis-Besse. ;
- Direct radiation averaged 13.6 mrem /91 days at indicator locations and j
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14.5 mrem /91 days at control locations. This is similar to results of previous years. The operation of Davis-Besse in 1994 caused no significant measurable 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 doses to the general public j due.to the operation of Davis-Besse in 1994 were also well below all applicable ! regulatory limits. l 5 In order to estimate radiation dose to the public, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual ; Land Use Census is performed as part of the REMP. During the census, Davis-Besse personnel travel every public road within a five mile radius of the Station to locate the radiological exposure pathways. He 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 1994 is a garden located 1660 meters west of the plant. ! e ix f i
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- Davis-Desse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Radiological Effluent Release Report The Radiological Effluent Release Report (RERR) is being incorporated into the Annual Radiological Environmental Operating Report for the first time in this document. The !
RERR was submitted to the NRC separately in the past. The most recent of these reports j was submitted for the period, July 1st,1993 through June 30,1994. The data in this submission is ror the period, July 1st through December 31,1994. , During this period, July 1,1994 through December 31,1994, the doses due to radioactivity released in effluents were estimated to be. ; Liquid Emuents: Maximum Individual Whole Body Dose 6.81E-02 mrem Maximum Individual Significant Organ Dose 8.87E-02 mrem l Total Integrated Population Dose 1.55E+00 person- rem i Average Dose to the Individual 8.16E-04 mrem ; e Gaseous Emuents: Maximum Individual Whole Body Dose due to 1.22E-03 mrem I-131, H-3 and Particulates with half-lives ; greater than 8 days Maximum Significant Organ dose due to I-131, 4.49E-03 mrem l H-3 and Particulates with half-lives greater than 8 days ; Total Integrated Population dose due to I-131, 3.06E-03 person-rem ! 11-3 and Particulates with halflives greater than ! 8 days j f Average dose to an Individual in the population 1.61E-06 mrem ! due to I-131, H-3 and Particulates with half-lives l greater than 8 days ! f x
Davis.Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Maximum Individual Skin dose due to noble gases 1.51E-03 mrad Maximum Individual Whole Body Dose due to 6.72E-3 mrad noble gases Total Integrated Population dose due to noble gases 2.24E-03 person-rem Average dose to individual in population due to 1.18E-06 mrem noble gases These doses represent an extremely small fraction of the limits set by the NRC or the limits set in the ODCM. There were no abnormal liquid releases and 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 (ODCM) however. Non-Radiological Environmental Programs
+ Meteorological Monitoring The Meteorological Monitoring Program at Davis-Besse is part of a program for evaluating the radiological effects of the routine operation of Davis-Besse on the surrounding environment. Meteorological monitoring began in October,1%8.
Meteorological instruments are monitored daily by trained personnel. 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 meteorotagical towers are used to collect data. Data recovery for the six instruments required to be operational by Davis-Besse Technical Specifications was 99.1%.
- 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 1994 with the cooperation of Ohio Department of Natural Resources included Canada goose banding, a Volunteer Eagle Watch Workshop and a xi
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Davis-Besse Nucicar Power Station 1994 Annual Radiological Environmental Operating Report Waterfowl Identification Seminar. In addition, unwanted and disruptive plant species, such as purple loosestrife (Lythrum salicaria) and the giant reed (Phragmities australisi), . , were controlled in order to enhance the ability of the marsh to support the resident
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g wildlife. Several artificial nesting structures were maintained throughout the year. Late . in 1994, a pair of American Bald Eagles nested in the Navarre Marsh. l l
+ Water Treatrnent .
Davis-Besse uses Lake Erie as a source of water for its Water Treatment Plant. The water is treated onsite to provide domestic water and to produce high purity water for use in the Station's cooling systems. Toledo Edison personnel collected and analyzed water samples from various locations on the station as part of the Zebra Mussel Control Program. Results show that the mussel , population appears to be leveling off or declining slightly, mostly due to the increasing clarity of Lake Erie. Wastewater generated by site personnel is treated onsite at the Davis-Besse Waste Water Treatment Plant (WWTP). The wastewater 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 12ke Erie. WWTP Number 2 was taken out of service for 6 months for needed repairs.
- Chemical Waste Management ,
The Chemical Waste Management Program at Davis-Besse was developed to ensure that I 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. i In 1994, approximately 18,000 gallons of rainwater / gasoline were disposed of as ; regulated waste. This was the liquid collected as a result of an on-site gasoline spill. The bulk gasoline was immediately recovered, the leak repaired and insitu bioremediation of ~ the gasoline contaminated soil is in progress. As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse reported hazardous products and chemicals to local fire departments and local and state , pianning commissions. As part of the program to remove PCB fluid from Davis-Besse, ., all electrical transformers have been retrofilled and reclassified as non-PCB transformers. : I
+ 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 l 1993 to include the recycling of paper, aluminum cans, cardboard, and metal. Throughout 1994, a total of 140,007 pounds of paper was collected and recycled and
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Davis-Besse Nuclear Power Station 1994 AnnualRadiologicalEnvironmentalOperating Report 34,833 pounds of cardboard was collected that would have otherwise been disposed of in a landfill. The scrap metal collected onsite was sold to scrap companies. Appendices , Appendix A contains results from the Interlaboratory Comparison Program required by Davis-Besse Technical Specifications. Samples with known concentrations of radioisotopes are 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 Nuclear Powei Station to analyze its REMP samples. The - results are then checked by the EPA to ensure consistency with the known values. The results from both the contracted laboratory and the EPA are provided in Appendix A. Appendix B contains data reporting conventions 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, and provide l comparison values for actual REMP sampling results for 1994. i Appendix D provides a REMP sampling summary from 1994. The appendix provides a listing of the following for each sample type:
- the number and types of analyses performed,
- the lower limit of detection for each analysis,
- the mean and range of results for control and indicator locations,
- the mean, range, and location description for the location with the highest annual mean,
- 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 Proyess Report to Toledo Edison (March 1994). l xiii
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Davb-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Introduction Coal, oil, natural gas rad hydropower are used to run this nation's electric generating stations; however, each method has its drawbacks. Coal-fired power can affect the environment through mining, acid rain and air pollution. Oil and natural gas are in limited supply and arc therefore costly, and hydropower is limited due to the environmental impact of darnming 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 fias a very small impact on the environment. In fact, the Davis-Besse Nuclear Power Station is surrounded by hundreds of acres of marshland which make up part of the Ottawa National Wildlife Refuge, the only national refuge in Ohio. In order to more fully understand this unique source of energy, background information on basic radiation characteristics, risk assessment, reactor operation and effluent control is provided in this chapter. Fundamentals The Atom All matter consist of atoms. Simply described, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, respectively (Figure 1). The relatively large protons and neutrons are packed tightly together in a cluster at the center of the atom called the nucleus. Orbiting around this nucleus are one or more smaller electrons. In an electrically neutral atom the negative charges of the electrons are balanced by the positive charges of the protons. Due to their dissimilar Figure 1: An atom consists of two parts: a nucleus containing positively charged protons and O i clectrically neutral neutrons and one or more negatively charged cledrons orbiting the nucleus. Protons and neutrons are nearly identical in size and weight, while cach is about 2000 times heavier than an electron. gm_ % [ \ O esoTon O FEUTAON O ELECTRON / k ) o \ " mum'- 4- CLE CTRCN
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Davis-Desse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report charges, the protons and electrons have a strong attraction for each other, which helps hold the atom together. other attractive forces between the protons and neutrons keep the densely packed protons from repelling each other, preventing the nucleus from breaking apart. Radiation and Radioactivity Isotopes and Radionuclides A group of identical atoms, containing the same number of protons, make up an element. In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms with one proton are hydrogen atoms and all atoms with eight protons are oxygen atoms. However, the number of neutrons in the nucleus of an element may vary. Atoms with the same number of protons, but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties and many are stable or nonradioactive. An unstable or radioactive isotope of an element is called a radioisotope, radioactive atom, or radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess energy is usually due to the excess number of neutrons in the nucleus. Radionuclides can be naturally occurring such as uranium-238, beryllium-7 and potassium-40, or man-made, such as iodine-131, cesium-137, and cobalt-50. Radiation Radiation is simply the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation is another type of radiation and has similar properties to those of the examples listed above. Ionizing radiation consists of both electromagnetic radiation and particulate radiation. Electromagnetic 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 consists 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 protons 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 of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go l 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 l example, when uranium-238 decays, it emits an alpha particle and, as a result, the atom loses 2 , J l 2 i
Davis-Besse Nuclear Power Station 1994 Annual Radiologica1 Environmental Operating Report r protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom determines its chemical identity. Derefore, when the uranium-238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of thorium-234. Thorium-234 is one of ' the 14 successive daughter products of uranium-238. Radon is another daughter product, and the series ends with stable lead-206. 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). f asso 234U' 4.5 x 10'y ,2.5 x 10'y l 23*Pa
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i 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, l tend to have comparably short half-lives. The length of time an atom remains radioactive is defined in terms of half-lives. Half-life is the amount of time required for a radioactive ! substance to lose half its activity through the process of radioactive decay. Half-lives vary from . millionths of a second to millions of years. ! i Interaction With Matter i i lonization l Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When } these forms of radiation interact with any fonn 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 m..nber of positive and negative charges cancel, and the atom is electrically neutral. When one or more electrons are removed an ica is formed. ; Ionization is one of the processes which may result in damage to biological systems. ! h 3 t l
Davis-Besse Nuclear Power Stetion 1994 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 protons and 2 neutrons, are relatively large, and carry an electtical charge of +2. Alpha particles are ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its comparatively large size, an alpha particle usually does not travel very far before it loses most of its energy through collisions and other interactions with atoms. As a result, alpha particles can easily be stopped by a sheet of paper or a few centimeters of air (Figure 3). Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed of light (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1. Because they are so small and have a low charge, they do not collide and interact as often as 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. Gamma rays are pure energy and travel at the speed of light. They have no measurable charge or mass, and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray finally loses all of its energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high energy gamma radiation can travel a considerable distance, whereas low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of lead or concrete may be needed to effectively shield gamma rays.
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8 '# 0, , I RADIOACTIVE ~ l M ATE RIA1. PAPER Al.UMINU M LEAD CONCRETE Figure 3: As radiation travels, it collides and interacts with other atoms and loses energy. Alpha particles can be I stopped by a sheet of paper, and beta particles by a thin sheet of aluminum. Gamma radiation is shicided by highly dense materials such as lead, while hydrogenous materials (those containing hydrogen atoms), such as water and concrete. are uscd to stop neutrons.
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within nuclear power reactors. However, neutrons are not of environmental concern since nuclear power stations are designed to keep neutrons within the containment building. Because neutrons have no charge, they are able to pass very close to the nuclei of the material j through which they are traveling.' As a result, neutrons may be captured by one of these nuclei ) i or they may be deflected. When deflected, the neutron loses some ofits energy. After a series of these deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal neutron. 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 l shielding materials commonly used to slow nuetrons down are water or polyethylene. The shield is then completed with a material such as cadmium, to absorb the now thermal neutrors. At Davis-Besse, concrete is used to form an effective neutron shield because it contains wat :r molecules and can be easily molded around odd shapes. Quantities and Units of Measurement There are several quantities and units of.neasurement used to describe radioactivity and its effects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent. Activity: Curie Activity is the number of atoms in a sample that disintegrate (decay) per ur.it of time. Each time an atom disintegrates, radiation is emitted. The curie (Ci)is the unit used to describe the activity of a material and indicates the rate at which the atoms of a radioactive substance are decaying. One curie indicates the disintegration of 37 billion atoms per second. A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. For example, one gram (1/28 th of an ounce) of radium-226 is the equivalent of one curie of activity, but it would take 9,170,000 grams (about 10 tons) of thorium-232 to equal one curie. Smaller units of the curie are often used, especially when discussing the low concentrations of radioactivity detected in environmental samples. For instance, the microcurie (uCi) is equal to one millionth of a curie, while the picocurie (pCi) represents one trillionth of a curie. 5
i Davis-Besse Nuclear Power Stolon 1994 Annual Radiological Environmental Operating Report 3 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 of ionizing radiation deposited per gram of absorbing material (1 rad = 100 erg /gm). The rate of absorbed dose is usually given in rad /hr. If the biological effect of radiation was directly proportional to the energy deposited by , radiation in an organism, the rad would be a suitable measurement of the biological effect. However, biological effects depend not only on the total energy deposited per gram of tissue, but on how this energy is distributed along its path. Experiments have shown that some types of radiation are more damaging per unit path of travel than others. Rus, another unit is needed to quantify the biological damage caused by ionizing radiation. Dose Equivalent: Rem Biological damage due to alpha, beta, gamma and neutron radiation may result from the ionization caused by these radiations. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the > same energy imparted as do gamma or X rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an I estimate of the possible biological damage resulting from exposure to a particular type of ionizing radiation. The dose equivalent is measured in rem (radiation equivalent man). An example of this conversion from absorbed dose to dose equivalent uses the quality factor for alpha radiation, which is 20. Thus,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 tem is a relatively large unit. Therefore, a smaller unit, the millirem,is often used. One millirem (mrem)is equal to 1/1000 of a rem. Deep Dose Equivalent (DDE) Deep dose equivalant is the measurement of dose from external sources that an individual might receive from radiation and radioactive material. It is what is measured and recorded by film badges and/or thermoluminescent dosimeter (TLD). For example, at Davis Besse or at any l l ; ) hospital that has x- ray equipment, you will see people wearing film badges or TLDs. These instruments are worn to measure deep dose equivalent (DDE). l 6
Davis-Besse Nuc1 car Power Station 1994 Annual Radiological Environmsntal Operating Report Committed Effectived Dose Equivalent (CEDE) Committed effective dose equivalent is the sum of the the products of the committed dose equivalent to the organ or tissue multipled by the organ or tissue weighting factor. 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). Previously, the dose to the individual was tracked separately for internal and external exposures but under the new 10CFR20 they are combined to obtain TEDE. The NRC limits occupational dose to a radiation worker to five rem (5000 mrem) TEDE per year. Sources of Radiation . 1 Background Radiation f 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 cf the average adult. In addition, radioactive decay also occurs naturally in soil, water, air, and space. All these common sources of radiation contribute to the natural background radiation to which everyone is exposed. The earth is constantly showered by a steady stream of high energy gamma rays and particulate radiation that come from space, known as cosmic radiation. The atmosphere shields us from most of this rad ation, 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 even 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 external and internal dose from naturally occurring background radiation is attributed to this radioactive isotope of potassium. The major source of background radiation is radon, a colorless, odorless, radioactive gas that results 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 does not typically pose a health hazard unless it is allowed to concentrate in a confined area, such as buildings, basements or underground mines. Radon-related health concerns stem from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it decays, this can cause damage to intemal tissues when ingested or ! inhaled. As a result, exposure to the lungs is of greatest concern, especially as the only j recognized health effect associated with exposure to radon is an increased risk of lung cancer. I 7 l I
DavD Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report i According to the National Council on Radiation Protection and Measurement (NCRP), over half of the radiation dose the average American receives is attributed to radon. SOURCES OF EXPOSURE TO THE PUBLIC Cosmic Irternal , 11% !
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; X-Rays 2%
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1% Rm GS% TOTAL MANMADE ! SOURCE - BEm V Figure 4:'Ihc most significant annual dose received by an individual of the public is that received from naturally occurring radon. A very small annual dose to the public results from producing electricity by nuclear power. Futher information on radon, its measurement, and actions to reduce the radon concentration in buildings can be obtained by contacting the state radon program office at the following address: Radiological Health Program Ohio Department of Health P.O. BOX 118 Columbus, Ohio 43266-0118 (614) 481-5800 (800) 523-4439 (in Ohio Only) Man-Made Radiaticn in addition to naturally occurring radiation and radioactivity, 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 receives is a result of having l electricity generated by nuclear power. l l l l l 8
Davb-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Repon 1 Health Effects of Radiation The effects of ionizing radiation on human health have been under study for more than eighty years. 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 relate the biological effects of irradiated laboratory animals to the potential health effects on humans. The effects of radiation on humans can be divided into two categories, somatic and genetic. Somatic effects are those which develop in the directly exposed inividual, 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 devel 3p shortly after exposure to large amount of radiation. Much study has been done with human populations that were exposed to ionizing radiation under various circumstances. These groups include the survivors of the atomic bomb, persons undergoing medical radiation treatment, and early radiologists, who accumulated large doses of radiation, unaware of the potential hazards. Chronic effects are a result of exposure to radiation over an extended period of time. Examples of such groups are clock dial painters, who ingested large amounts of radium by " tipping" the paint brushes with their lips, and uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (uranium ore). The studies performed on these groups have increased our knowledge of the health effects from large doses of radiation received over long periods of time. Ccmtinuous exposure to low levels of radiation may produce gradual 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 individual health effects of low level radiation. To be conservative, we assume the health effects resulting from low doses of radiation occur proportionally to those observed following large doses of radiation. Some 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 individuals exposed to low level radiation. Therefore, the most likely somatic effect of low level radiation is believed to be a small increased risk of cancer. Genetic effects may occur as a result ofionizing radiation interacting with the genes in the human cells. Radiation (as well as common chemicals) can cause physical changes or mutations in the genes. Chromosome fibers can breek and rearrange, causing interference with the normal cell division of the chromosome by affecting their number and structure. A cell can rejoin the enc' af a broken chromosome, but if there are two breaks close enough together in space and time, the broker, ends from one break may join incorrectly with those from another. This can cause translocations, inversions, rings, and other types of strucun al rearrangements. When this happens, new mutated g,enes are created. Radiation is not the anly mechanism by which such 9 l
Davis-Besse Nucicar Power Station 1994 Annual Radiolegical Environmental Operating Report I l I changes can occur. Spontaneous mutations and chemically induced mutations have been observed. Rese mutated genes may be passed from parent to offspring. l, Health Risks ; 1 While people may accept the risks inherent in their personal activities, such as smoking and driving to work each day, they are less inclined to accept the risk inherent in producing electricity. As with any industrial environment, it is not possible to guarantee a risk free , environment. Thus, attention should be focused on taking steps to safeguard the public, on developing a realistic assessment of the risks, and on placing these risks in persp ective. The perceptions of risk associated with exposure to radiation has, perhaps, the greatest misunderstanding. Because people may not understand ionizing radiation and its associated risks, they may fear it. This fear is compounded by the fact that we cannot hear, smell,i aste or feel ionizing radiation. ' Ilowever, we do not fear other potentially hazardous things for which we have the sane lack of sensory perception, such as radio waves, carbon monoxide, and small concentrations of numerous cancer causing substances. These risks are just as real as those associated with exposure to radiation. Most of these risks are with us throughout our lives, and can be added up t i over a lifetime to obtain a total effect. Table 1 shows a number of different factors that decrease the average life expectancy of individuals in the United States. l 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 lleart diseases 5.8 years Cancer 2.7 years City Living (not rural) 5.0 years All operating commerical nuclear less than 12 minutes power plan.s 10
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Opera:ing Report ; i . Benefits of Nuclear Power j i Nuclear power plays an important part in meeting today's electricity needs, and will continue to j serve as an important source of electric energy well into the future. Today more than twenty i percent of the electricity produced in the United States is from nuclear powered electrical generating stations. i Nuclear power offers several advantages over alternative sources of electric energy:
- nuclear power has an excellent safety record dating back to 1957 when the first f commercial nuclear power station began operating
- uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States
- nuclear power is the cleanest energy source for power stations that use steam to produce electricity. There are no " greenhouse" gases or acid gases produced when using nuclear fuel.
The following sections provide information on the fundamentals of how Davis-Besse uses 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 tums a turbine. In a fossil-fueled station, the fuel is burned in a furnace, which is also a boiler. Inside the boiler, water is turned into steam. In a nuclear station, the furnace is replaced by a reactor containing a core of nuclear fuel, primarily uranium. Heat is produced when the atoms of uranium are split, ! or fissioned, inside the reactor. What is Fission? ; A special force called the binding force holds the protons and neutrons together in the nucleus t af 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 l entire atom to split, proaucing 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. l i i I 1 11
1994 Annual Radiological Environmental Operating Report Davis-Desse Nuclear Power Station Hcat 0 s Bombardin
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Nntron Free 0i l0 Neutron A orn [fiEsion fragment Figurc 5: When a heavy atom, such as uranium-235 is split or fissioned, heat, free neutrons, and fission fragments result.~lhe 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 The fissioning of one uranium atom releases approximately 50 million times more energy than the combustion of a single carbon atom common to all fossil fuels. Since a single small reactor fuel pellet contains trillions of atoms, each pellet can release an extremely large amount of energy. The amount of electricity that can be generated from three small fuel pellets would require about 3.5 tons of coal or 12 barrels of oil to generate. Nuclear fission occurs spontaneously in nature, but these natural occurrences cannot sustain themselves because the freed neutrons either are absorbed by non fissionable atoms or quickly decay. In contrast, a nuclear reactor minimizes neutron losses, thus sustaining the fission process by several means:
. using fuel that is free of impurities that might absorb the free neutrons,
- enriching the concentration of the rarer fissioaable isotope of uranium (U-235) j relative to the concentration of U-238, a more common isotope that does not fission
[ easily,
- slowing neutrons down by providing a " moderator" such as water to increase the probability of fission l
l 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 f l percent U-235, in contrast to nuclear material used in nuclear weapons which is enriched to over l 97 percent. Because of the low 3vels of U-235 in nuclear fuel, a nuclear power station cannot explode like a bomb. 12
Davis.Besse Nuclear Power Station 1994 Annual Radiological Environment tl Operating Report After the uranium 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 (UF). UF,is a chemical form of uranium that exists as a gas at temperatures slightly above room temperature. The UF, is then highly purified and shipped to an enrichment facility where gaseous diffusion converters increase the concentration of U-235. The enriched gaseous UF,is then converted into powdered uranium dioxide (UO), a highly stable ceramic material. The UO2 Powder is put under high pressure to form fuel pellets, each about 5/8 inch long and 3/8 inch in diameter . Approximately five pounds of these pellets are placed into a 12 foot long metal tube made of zirconium alloy. The tubes constitute the fuel cladding. The fuel cladding is highly resistant to heat, radiation, and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods. The Reactor Core Two hundred eight fuel rods comprise a single fuel assembly. The reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fuel rods, the fuel assembly also contains 16 vacant holes for the insertion of control rods, and one vacant hole for an incore monitoring probe. This probe monitors temperature and neutron levels in the fuel assembly. The Davis-Besse reactor vessel, which contains all the fuel assemblies, weighs 838,000 pounds, has a diameter of 14 feet, is 39 feet high, and has 81/2 inch thick steel walls. O@
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1 ( / Fue Rod Fuel Assembey REACTOR VESSEL ! Figure 6: The reactor core at Davis-Ilcsse contains 177 fuel assemblics. Each assembly contains 208 fuel rods. Each fuel rod is filled with approximately five pounds of fuel pellets, cach pellet is approximately 3/8 inch in l diameter and 5/8 inch long. 1
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I Davis-Besse Nuclear Power Station 1994 Annua 1 R9diologica1 Environmental Operating Reprt l Fission Control l 1 The fission rate inside the reactor core is controlled by raising or lowering control rod assemblies into the reactor core. Each assembly consist of " fingers" containing silver, indium, j and cadmium metals that absorb free neutrons, thus disrupting the fission chain reaction. When l control rod assemblies are slowly withdrawn from the core, fissioning begins and heat is ; produced. If the control rod assemblies are inserted rapidly into the reactor core, as during a 1 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 l Davis-Besse, boric acid enriched in boron-10 is concentrated or diluted in the coolant to achieve the desired level of fission. Boron-10 readily absorbs free neutrons, forming boron-11, removing j the absorbed neutrons from the chain reaction. 1 Reactor Types l Virtually all of the commercial reactors in this country are either boiling water reactors (BWRs) or pressurized water reactors (PWRs). Both types are also called light water reactors (LWRs) because their coolant, or medium to transfer heat, is ordinary water, which contains the light isotope of hydrogen. Some reactors use the heavy isotope of hydrogen (deuterium)in the reactor coolant. Such reactors are called heavy water reactors, or HWRs. In BWRs, water passes through the core and boils into steam. The steam passes through separators which remove water droplets. The steam then travels to dryers before entering the turbine. After passing though the turbine the steam is condensed back into water and returns to the core to repeat the cycle. In PWRs, the reactor water or coolant is pressurized to prevent it from boiling. The reactor water is then pumped to a steam generator (heat exchanger) where its heat is transferred to a secondary 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. l 14
i Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report i i t FIGURE 7 LEGEND ; GREEN - Reactor Coolant System (Primary Coolant Water) RED - Main Steam System , BLUE - Condensate / Main Feedwater System (Secondary Coolant Water) l YELLOW - Circulating Water System (Tertiary Coolant Water) ! i ORANGE - Emergency Core Cooling System , SCARLET - Auxiliary Feedwater System [ VIOLET - Pressurizer and Associated Structures i i l i
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Davis-Desse Nuclear Power Station 1994 Annual Radiological Envimnmental Operating Repon Station Systems Containment Building and Fission Product Release Barriers The containment building houses the reactor vessel, the pressurizer, two steam generators, the reactor coolant pumps and reactor coolant system piping.The building is constructed of an inner 1 inch thick steel liner or containment vessel, and the shield building with steel reinforced concrete walls 2 feet thick. The shield building protects the containment vessel from a variety of environmental factors rnd provides an area for a negative pressure boundary around the ' steel containment vessel. In the event that the integrity of the containment ussel is compromised (e.g., a crack develops), this negative pressure boundary ensu a that any airborne radioactive contamination present in the containment vessel is prevented from leaking out into the environment. This is accomplished by maintaining the pressure inside the shield building lower than that outdoors, thus forcing clean outside air to leak in, while making it impossible for the contaminated air inside the containment vessel to leak out. The free-standing containment vessel is the third in a series of barriers that prevent the release of fission products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel cladding itself. The second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and associated piping. The Steam Generators The steam generators perform the same function as a boiler at a fossil-fueled power station. The steam generator uses the heat of the primary coolant inside the steam generator tubes to boil the secondary side feedwater (secondary coolant). Fission heat from the reactor core is transfered 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 and steam generator. Primary loop water (green in Figure 7) exits the reactor at approximately 606 F, passes through the steam generator, transferring some of its heat energy to the secondary loop water (blue in Figure 7) without actually coming in contact with it. Primary coolant water exits the steam generator at approximately 558 F to be circulated back into the 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 Pressurized Water Reactor. Secondary loop water enters the base of the steam generator at approximately 450 F and under 1,100 psi pressure. At this pressure, the water can easily boil into steam as it passes over the tubes containing the primary coolant water. Both the primary and the secondary coolant water are considered closed loop systems. This means they are designed not to come in physical contact with one another. Rather, the coolant water contained in each loop transfers heat energy by the process of convection. Convection is o* 17
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i Davb-Besse Nuclear Power St: tion 1994 Annual Radiological Environmentr.1 Operating Repon a method of heat transfer that can occur between two fluid media. It is the same process by < which radiators are used to heat homes. The water circulating inside the radiator is separated l from the air (a " fluid" medium) by the metal piping. The Turbine - Generator The turbine, main generator, and the condenser are all housed in what is commonly referred to as the Turbine Building. The purpose of the turbine is to convert the thermal energy of the steam produced in the steam generator (referred to as main steam, red in Figure 7) to rotational energy of the turbine generator shaft. The turbine at Davis-Besse is actually composed of one six-stage high pressure turbine and two seven stage low pressure turbines aligned on a common shaft. A turbine stage refers to a set of blades. Steam enters at the center of each turbine and flows outward along the shaft in opposite directions through each successive stage of blading. As the steam passes over the turbine blades, it loses pressure. Thus, the blades must be proportionally larger in successive stages to extract enough energy from the steam to rotate the shaft at the correct speed. The purpose of the main generator is to convert the rotational energy of the shaft to electrical energy for commercial usage and support of station systems. The main generator is composed of two parts, a stationary stator that contains coils of copper conductors, and a rotor that supplies a rotating magnetic field within the coils of the stator. Electrical current is generated in , the stator portion of the main generator. From this point, the electric current passes through a ! series of transformers for transmission and use throughout 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. Circulating water forms the third (or tertiary) and final loop of cooling water used at the Davis-Besse Station. . As the primary to secondary interface, the secondary to tertiary interface is based on a closed loop design. The circulating water is able to cool the steam in the condenser, without ever actually coming in contact with it, by the process of convection. Even in the event of a primary to secondary leak, the water vapor exiting the Davis-Besse cooling tower would remain non-radioactive. Closed loops are an integral part of the design of any nuclear facility. This design feature greatly reduces the chance of environmental impact from station operation. we 18
f Davis.Besse Nuclear Power Station 1994 Annual Radiologica1 Environmental Operating Report l The Cooling Tower q The cooling tower at Davis-Besse is easily the most noticeable feature of the plant. The tower j 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 l recycle water from the condenser by cooling it. After passing through the condenser, the circulating water has warmed to approximately 100 F. l In order to cool the water back down to around 70 F, the circulating water enters the cooling ! tower about 40 feet above the ground. The water is sprayed evenly over a series of baffles called filisheets which are suspended vertically in the base of the tower. A natural draft of air blowing ! up through these baffles cools the water through the process of evaporation. The evaporated water exits the top of the cooling tower in the form of water vapor. As much as 10,000 gallons of water per minute are lost to the atmosphere via the cooling tower. Even so, approximately 98 percent of the water drawn from Lake Erie for station operation can be recycled through the cooling tower for reuse. A small portion of the circulating water is discharged back to Lake Erie at essentially the same temperature it was withdrawn earlier. For example, in 1994, the average difference between the intake and discharge water temperatures was only 4.1*F. The slightly warmer discharge water had no adverse environmental impact on the area of lake surrounding the discharge point. Miscellaneous Station Safety Systems 1 i The orange system in Figure 7 is part of the Emergency Core Cooling System (ECCS) housed ; in the Auxiliary Building of the station. The ECCS consists of three overlapping means of keeping the reactor core covered with water, in the unlikely event of a Loss Of Coolant Accident (LOCA), thereby protecting the fuel cladding barrier against high temperature failure. Depending upon the severity of the loss of pressure inside the primary system, the ECCS will automatically channel borated water into the reactor by either high pressure injection pumps, a core flood tank, or low pressure injection pumps. Borated water can also be sprayed from the ceiling of the containment vessel to cool and condense any steam that may escape from the primary system. The violet system illustrated in Figure 7 is responsible for maintaining the primary coolant water in a liquid state. It accomplishes this by adjusting the pressure inside the primary system. _ Heaters inside the pressurizer turn water into steam. This steam takes up more space inside the pressurizer, thus increasing the overall pressure inside the primary system. The pressurizer is equipped with spray heads that shower cool water over the steam in the unit. In this case, the steam condenses and the overall pressure inside the primary system drops. The quench tank pictured in Figure 8 is simply where excess steam is directed and condensed for storage. The scarlet system in Figure 7 is part of the Auxiliary Feedwater System, a key safety system in event the main feedwater supply (blue in Figure 7) to the steam generator is inadequate. D 19
Davis-Besne Nuclear Power Station 1994 Annual Radiological Envimnrnental Operating Report Following a reactor shutdown, the Auxiliary Feedwater System can supply water to the steam generators from the Ccadensate Storage Tanks. The Auxiliary Feedwater System is housed in the Turbine Building along with the turbine, main generator, and the condenser. Reactor Safety and Summary Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. Also, many safety features are equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the local environment. Davis-Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features. If one system should fail, there are still back-up systems to assure the safe operation of the Station. During normal operation, the Reactor Control System regulates the power output by adjusting the position of the control rods. The reactor can be automatically shut down by a separate Reactor Protection System that causes all the control rod assemblies to be quickly and completely inserted into the reactor core, stopping the chain reaction.To guard against the possibility of a Loss Of Coolant Accident, the Emergency Core Cooling System is designed to pump reserve water into the reactor automatically if the reactor coolant pressure drops below a predetermined level. The Davis-Besse Nuclear Power Station was designed, constructed, and operates to produce a reliable, safe, and environmentally sound source of electricity. Radioactive Waste Many of the activities we depend on in our everyday lives produce radioactive waste by-products. Nuclear energy, industrial processes, and medical treatments are some of these activities. These by-products are managed and disposed of under strict requirements set by the federal 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 contaminated with radioactive materials. It includes plastic gloves and other protective clothing, machine partFmd tools, medical and laboratory equipment, filters, resins, and general scrap. The radioactive particles in low level radioactive waste emit the same types of radiation that naturally occurring materials tend to emit. Most low level radioactive waste " decays" to background levels of radioactivity in months or years. Nearly all of it diminishes to stable materials in less than 300 years. D-20
l l Davis-Besse Nuclear Power Stetion 1994 Annust Radiological Environmental Oprating Report I i In 1980, Congress passed the Imw-level Waste Policy Act. His law requires each state to ! develop an individual disposal site for waste, or to form " compacts" with other states tojointly 1 dispose of their low-level waste. Approximately 10 regional compacts have been formed. Ohio is a member of the Midwest Compact, which includes Indiana, Iowa, Missouri, Minnesota, and Wisconsin. Since Ohio is the largest producer of low-level waste in the Compact, it has the responsibility to site the first disposal facility, which would receive waste from all Compact states for 20 years. The responsibility then shifts to the Compact's next largest producer of waste, Minnesota, which will host the repository for the second 20 years. Davis-Besse presently holds all low-level radioactive waste on site. This has happened because the Barnwell, South Carolina site was closed to out-of-compact generators in June,1994. Davis-Besse has the capacity to store the low-level waste it produces on site for several years in the Low-Ixvel Radioactive Waste Storage Facility located inside the protected area of the plant. However, this storage is temporary and the material will be shipped when a Compact disposal facility becomes available. IIigh Level Nuclear Waste Like any industrial or scientific process, nuclear energy does produce waste. The most radioactive is defined as "high-level" waste (because it has high levels of radioactivity). Ninety-nine percent of high-level waste from nuclear plants is used nuclear fuel. The fuel undergoes certain changes during fission. Most of the fragments of fission, pieces that are left over after the atom is split, are radioactive. After a period of time, the fission fragments trapped in the fuel assemblies reduce the efficiency of the chain reaction. About every 18 months, the oldest fuel assemblies are removed from the reactor and replaced with fresh fuel. High-level nuclear waste volumes are small. Davis-Besse produces about 30 tons of used fuel each year. 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 chemical waste remains hazardous indefinitely. Davis-Besse presently stores its used fuel in a steel-lined concrete vault, filled with water, inside the plant. The Department of Energy is charged with constructing a permanent high-level waste repository for all of the nation's nuclear plants. At this time, 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 this will be done in the fuel pool until it reaches its capacity in 1995. At that time, the older fuel assemblies that no longer require water cooling will be placed in air cooled concrete shielded canisters. These will be 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. I 21
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Davis-Besse Nuclear Power Stotion 1994 Annual Radiological Environmental Operating Report Description of the Davis-Besse Site The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the southwestern shore of Lake Erie,just north of the Toussaint River. The site lies north and east of Ohio State Route 2, approximately 10 miles northwest of Port Clinton,7 miles north of Oak liarbor, and 25 miles east of Toledo, Ohio (Figure 8). This section of Ohio is flat and marshy, with maximum elevations of only a few feet above the level of Lake Erie. The area originally consisted of swamp forest and marshland, rich in wildlife but unsuitable for settlement and farming. During the nineteenth century, the land was cleared and drained, and has been farmed successfully since. Today, the terrain consists of farmland with marshes extending in some places for up to two miles inland from the Sandusky Lake Shore Ridge.
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DavD-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report 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 acqtit ed from the U.S. Bureau of Sport Fisheries and Wildlife, Department of the Interior. 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. 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 major resort area of the county is farther east, around Port Clinton, Lakeside, and the Bass Islands.
The non-marsh areas around the Davis-Besse site are utilized primarily for farming. The major crops include soybeans, corn, wheat, oats, hay, fruits and vegetables. Meat and dairy animals are not major sources of income in the area. The main industries within five miles of the site are located in Erie Industrial Park, about four miles southeast of the station. Most of the remaining marshes in the area have been maintained by private hunting clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife. The State of Ohio Department of Natural Resources operates many wildlife and recreational areas within 10 miles of the Station. These include Magee Marsh, Turtle Creek, Crane Creek State Park, and the Ottawa National Wildlife Refuge. Magee Marsh and Turtle Creek lie between three and six miles WNW of the Station. Magee Marsh is a wildlife preserve allowing public fishing, nature study, and controlled hunting season. Turtle Ocek, 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 l National Wildlife Refuge lies four to nine miles WNW of the Site, immediately west of Magee l Marsh. l 23
l Davb.Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report l References l 1
- 1. "A Citizen's Guide to Radon: What It Is and What to do About It," United States I Environmental Protection Agency, United States Department of Health Services, Centers for i Disease Control (August 1986).
- 2. " Basic Radiation Protection Criteria," Report No. 39, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1971).
- 3. " Cesium-137 from the Environment to Man: Metabolism and Dose," Report No. 52, National Council on Radiation Protection and Measurements, Washington, D.C. (January 1977).
- 4. Deutch, R., " Nuclear Power, A Rational Approach," fourth edition, GP Courseware, Inc.,
Columbia, MD. (1987).
- 5. Eisenbud, M., " Environmental Radioactivity," Academic Press, Inc., Orlando, FL. (1987).
- 6. " Environmental Radiation Measurements," Report No. 50, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1976).
- 7. " Exposure of the Population in the United States and Canada from Natural Background Radiation," Report No. 94, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1987). -
- 8. " Health Effects of Exposure to Low Levels ofIonizing Radiation: BEIR V," Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects Research Commission on Life Sciences, National Research Council, National Academy Press, Washington, D.C.
(1990).
- 9. Hendee, William R., and Doege, Theodore C., " Origin and Health Risks of Indoor Radon,"
Seminars in Nuclear Medicine, Vol. XVIII, No.1, American Medical Association, Chicago, IL. (January 1987).
- 10. Hurley, P., "Living with Nuclear Radiation," University of Michigan Press, Ann Arbor, MI.
(1982).
- 11. " 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).
- 12. Introduction to Davis-Besse Nuclear Power Station Plant Technology, July 1992, Rev. 4, Pg. 2-9.
24
Davis-Besse Nuclear Power Stction 1994 Annual Radiological Environmentcl Operating Report
- 13. " Ionizing Radiation Exposure of the Population of the United States," Report No. 93, National Council on Radiation Protection and Measurements, Washington, D.C (September 1987).
- 14. " Natural Background Radiation in the United States," Report No. 45, National Council on Radiation Protection and Measurement.s, Washington, D.C (November 1975).
- 15. " Nuclear Energy Emerges from 1980's Poised for New Growth," U.S. Council for Energy Awareness, Wahington, D.C (1989).
- 16. " Nuclear Power: Answers to Your Questions," Edison Electric Institute, Washington, D.C.
(1987).
- 17. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurement, Washington, D.C (December 1987).
- 18. " Radiation Protection Standards," Department of Environmental Sciences and Physiology and the Office of Continuing Education, Harvard School Of Public Health, Boston, MA. (July i
1989).
- 19. "1985 Radiological Environmental Monitoring Report for Three Mile Island Station," GPU Nuclear Corporation, Middletown, PA. (1985).
- 20. " 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 (198h).
- 21. " Standards for Protection Against Radiation," Title 10, Part 20, Code of Federal Regulation, Washington,D.C. (1988).
- 22. " Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50, Code of Federal Regulations, Washington, D.C (1988).
- 23. " Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40, Part 190, Code of Federal Regulations, Washington, D.C. (1988).
- 24. " Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1979).
25.1992 Site Environmental Report, Fernald Environmental Management Project, U.S. Department of Energy (June 1993). ; 25
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DavbBesso Naclear PowerStation 1994 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at Davis-Besse for several reasons: to provide a supplementary check on the adequacy of containment and effluent controls, to assess the radiological impact of the Station's operation on the surrounding area, and to determine compliance with applicable radiation protection guides
' standards. Environmental surveillance at Davis-Besse has been conducted at the Station for r 22 years. The REMP was established in 1972, five years before the Station became t y erational. This preoperational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of Davis-Besse.
When Davis-Besse became operational in 1977, the REMP continued to measure radiation and radioactivity in the surrounding areas. The operational surveillance program has been collecting environmental data for over 17 years. A variety of environmental samples are collected as part of the REMP at Davis-Besse. The selection of sample types is based on the established critical pathways for the transfer of radimuclides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population characteristics, and land usage in the area of interest. The selection of sampling frequencies for the various environmental media is based on the radionuclides of interest, their respective half lives, and their behavior in both the biological and physical environment. A description of the REMP at Davis-Besse is provided in the following section. In addition, a , brief history of analytical results for each sample type collected since 1972, and a more detailed summary of the analyses performed in 1994, are also provided. Preoperational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental monitoring prior to constructing the facility. This preoperational surveillance program is aimed at collecting the data needed to identify critical pathways, including selection of the radioisotope and sample media combinations to be included in the surveillance program conducted after facility operation begins. Radiochemical analyses performed on the environmental samples l should include not only those nuclides expected to be released during facility operation, but
)
26
. Davis-Desse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report i
should also include typical fallout radionuclides and natural background radioactivity. All environmental media with a potential to be affected by facility operation, as well as those media - directly in the critical pathways, should be sampled on at least an annual basis during the preoperational phase of the environmental surveillance program. The preoperational surveillance design, including nuclide/ media combinations, sampling frequencies and locations, collection techniques, and radicanalyses performed, should be ; carefully considered and incorporated in the design of the operational surveillance program. In ; this manner, data can be compared in a variety of ways (for example: from year to year, location to location, etc.) in order to detect any radiological impact the facility has on tne 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 yeam provide an extensive database from which Station personnel are able to identify l 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; to determine whether any significant increase occurs in the concenaation 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;
. to verify the adequacy of Station controls for the release of radioactive materials.
Quality Assurance - An important part of the environmental monitoring program at Davis-Besse is the Quality Assurance (QA) Program. It is conducted in accordance with the guidelines specified in NRC Regulatory Guide 4.15, Ouality Assurance for Radiological Monitoring Programs." The OA 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: J' 27 t
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report i
= performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keeping; !
- performing audits of contractor laboratories whicii . Jalyze the environmental ;
samples-
- requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross-Check Program;
- requiring analytical contractor laboratories to split samples for separate analysis f followed by a comparison of results;
- splitting samples prior to analysis by independent laboratories, and then comparing l the results for agreement, and, final 7y; I
- requiring analytical contractor laboratories to perform in-house spiked sample analyses.
OA audits and inspections of the Davis-Besse REMP are performed by Davis-Besse's OA department and the NRC. In addition, the NRC and the Ohio Department of Health (ODH) also perform independent environmental monitoring in the vicinity of Davis-Besse. The types of r,amples collected and the sampling locations used by the NRC and ODH were incorporated in Davis-Besse's REMP. Hence, the analytical results from the different programs can be compared. This practice of comparing results from identical samples, collected and analyzed by different parties, provides a valuable tool to verify the quality of the labora'ories' analytical ! procedures and the data generated. In 1987, environmental sampling personnel at Davis-Besse incorporated their own Quality l Assurance program into the REMP. Duplicate samples, called quality control samples, were collected at several locations. These duplicate samples were assigned different identification ; numbers than the numbers assigned to the routine samples. This ensured that the analytical l laboratory would not know the samples were identical. The laboratory results from analysis of the quality control samples and the routine samples cou' l then be compared for agreement. ; Quality control sampling has been integrated into the program and has become an important part i of the REMP since 1987. Quality control sampling locations are changed frequently in order to duplicate as many sampling locations as possible, and to ensure the contractor laboratory has no way of correctly pairing a quality control sample with its routine sample counterpart. ; t I
?
28
DavbBesse Nuclear Power Station 1994 Annual Radiological Environmental Operating Repon Program Description Overview The Radiological Environmental Monitoring Program at Davis-Besse is conducted in accordance with Title 10, Code of Federal Regulations, Part 50; Regulatory Guide 4.8; the Davis-Besse Nuclear Power Station Operating License, Appendix A (Technical Specifications); the Davis-Besse Offsite Dose Calculation Manual (ODCM) and Station Operating Procedures. Samples are collected either weekly, monthly, quarterly, semiannually, or annually, depending upon the sample type and nature of the radionuclides of interest. Environmental samples collected by Davis-Besse personnel are divided into four general types:
- atmospheric --including samples of airborne particulates and airborne radiciodine
- terrestrial -- including samples of milk, groundwater, broad leaf vegetation, fruits animal / wildlife feed, soil, eggs, and wild and domestic meat
- aquatic -- including samples of treated and untreated surface water, fish, and shoreline and bottom sediments
- direct radiation -- measured by thermoluminescent dosimeters All environmental samples are labeled using a sampling code. Table 2 provides the sample codes and collection frequency for each sample type.
REMP samples are collected onsite and offsite up to 25 miles away from the Station. Sampling locations may be divided into two general categories: indicator and control. Indicator locations are those which would be most likely to display the effects caused by the operation of Davis-Besse. Generally, they are located within five miles of the station. Controllocations 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 environmer.t. Data from indicator and control locations are also compared with preoperational data to determine whether significant variations or trends exist. Since 1987, the REMP has been reviewed and modified to develop a comprehensive sampling program adjusted to the current needs of the utility. Modifications have included additions of sampling locations above the mmimum amount required in the ODCM and increasing the number of analyses performed on each sample. Besides adding new locationz, duplicate or Quality control (OC) sample collection was initiated to verify ti,e accuracy of the lab analyzing the environmental samples. These additional samples are referred to as the REMP Enhancement Samples.1799 samples were collected and 2489 analyses were performed during 1994. In addition, of the 134 sampling locations utilized in 1994,16 % were quality control locations. Table 3 shows the number of sampling locations and number collected for each type of sample. e 29
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environrnental Operating Report Table 2: Sample Codes and Collection Frequencies l Sample Type Sample Collection Code Frequency [ l Airborne Particulate AP Weekly Airborne Iodine AI Weekly Thermoluminescent TLD Quarterly, Annually [ Dosimeter Milk MIL Monthly (semi-monthly during t grazing season) 6 Groundwater WW Ouarterly i Broad Leaf Vegetation BLV/ Monthly (when available) and Fruits FRU , Surface Water -Treated SWT Weekly 1 Surface Water - Untreated SWU Weekly i Fish FIS Semiannually i Shoreline / Bottom SED Semiannually Sediment i Soil SOI Semiannually Animal / Wildlife Feed DFE/WFE Annually ! Meat-Domestic DME Annually i Meat-Wild , WME Annually_ Egg Egg Annually l t w P 30
Davis-Besse Nuclear Power Station 1994 Annua 1 Radiological Envimnmental Operating Report Table 3: Sample Collection Summary Sample Collection Numberof Numberof Numberof , Type Type */ locations Samples Samples Missed (Remarks) Frequency ** Collected A'IMOSPflERIC i AktxmcIWimimes QW 10 520 0 Airtxmc Rabokx1ine CW 10 520 0 'IUtRINIRIAL ; Mik(lanAkc) GM 1 13 0 Grtux!wscr GO 3 16 0 111ible Meat wiki G/A 1 1 0 dunestic G/A 2 2 3 i Fp,p G'A 2 2 0 Iktxd leaf l Vegetuion/liuit GM 7 24 0 , Soil GS 11 11 11 AnunatWddlifelird G/A 4 4 0 l AQUA ~IIC 'ncaicd QunpWM 2 27 ; Surface Watcr GWM 3 48 0 i Untn:acd G/WM 1 24 0 ; Sufax Wate GM 10 G) 20 + OwnpWM 4 51 0 l IM(3 species) GSA 2 6 6 StrutlineSedurxnts GSA 5 8 0 DIRIXT. RADIA~IK)N :
'Durmolumirxxrnt QQ 111 3 73 3 IXwimetas CA 111 fD 4 [ ' 'I)pe of Odlockm: C = Qotinucu;; G = Grab; Qwnp a Qungsite " Fnxjucncy of Q>1kukn: WM = Weekly awngmited hkuthly; W = Weekly; SM = Semimanthly; M = Monthly;O = Quanctly; SA = Semiarrndly; A = Annually t f
e9 31
Davis-Besse Nuclear Power St tion 1994 Annual Radiological Environmental Operating Report Sample Analysis When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Davis-Besse REMP include: Gross beta analysis measures the total amount of beta emitting radioactive material present in a sample. Beta radiation may be released by many different radionuclides. Since beta decay gives a continuous energy spectrum rather than the discrete lines or " peaks" associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal 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 allows for swift and accurate identification. For example, gamma spectral analysis can be used to identify the presence and amount of iodine-131 in a sample. Iodine-131 is a man-made radioactive isotope of iodine that may be present in the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power stations. Tritium analysis indicates whether a sample contains the radionuclide tritium (11-3) and the amount present. As discussed in Chapter One, tritium is an isotope of hydrcy,en that emits low energy beta particles. Strontium analysis identifies the presence and amount of strontium-89 and strontium-90 in a sample. These man-made radionuclides are found in the environment as a result of fallout from nuclear weapons testing. Sirontium is usually incorporated into the calcium pool of the biosphere. In other words, strr ntium tends to rer, lace calcium in living organisms and becomes incorporated in bone tissue. Tne principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from airborne releases. Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure. Table 6 provides a list of the analyses performed on environmental samples collected for the Davis-Besse REMP. Often samples will contain little radioactivity, and may be below the lower limit of detection. The lower limit of detection (I LD) 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 l that it cannot be accurately measured with any degree of confidence by that particular method for an individual analysis. hd 32
Davis-Besse Nuclear Power Station. 1994 Annual Radiological Environmentcl Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples Sample Tvoe Analyses Performed ATMOSPHERIC MONITORING
. Airborne Particulate, Gross Beta Gamma Spectral -
Strontium-89 4 Strontium-90 l Airborne Radioiodine Iodine-131 j TERRESTRIAL MONITORING , Milk Gamma Spectral ! Iodine-131 Strontium-89 i 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 i Strontium-90 Animal / Wildlife Feed Gamma Spectral , Soil Gamma Spectral , Wild and Domestic Meat Gamma Spectral __ ! f Egg Gamma Spectral ; T M 33 !
- i Davis-Besse Nuclear Power Station _1994 - Annual Radiological Environmental Operating Report l l'
. Table 4: Radiochemical Analyses Performed on REMP Samples (continued) ;
i I l Sample Tvoc - Analyses Performed ! A' OUATICMoNIToRING 1 Untreated Surface Water Gross Beta .; Gamma Spectral Tritium i Strontium-89 - Strontium-90 ! i Treated Surface Water Gross Beta f Gamma Spectral Tritium [
- Strontium-89 Strontium-90 i Iodine-131 !
Fish Gross Beta ! Gamma Spectral : Shoreline Sediment Gamma Spectral ! DIRECT RADIATION MONITORING ; I Thermoluminescent Dosimeters Gamma Dose 1 Sample History Comparison ; The measurement of radioactive materials present in.the environment will depend on factors - -l such as weather or variations in sample collection techniques or sample analysis. This is one ; reason why the results of sample analyses are compared with results from other locations and : from earlier years. Generally, the results of sample analyses are compared with preoperational j and operational data. Additionally, the results of indicator and contr61 locations are also ! compared. This allows REMP personnel to track and trend the radionuclides present in the 1 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 j 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 l sample analyses performed from 1972 to 1994 is provided in the following section. l, o I 34 !
~ , . . - . , ,r . . . . ., .. . . . . , , - - - - . . - - - - ... , .- .r.-,_
Davis-Besse Nucker Power heinn 1994 Annual Radiological Environmentc1 Operating Report Atmospheric Monitoring l v
.l
- Airborne Particulates: No radioactive particulates have been detected as a result of l Davis-Besse's operation. ' Only natural and fallout radioactivity from_ nuclear weapons i
- testing and the 1986 nuclear accident at Oernobyl have been detected. j
- Airborne Radiolodine: Radioactive iodine-131 fallout was detected 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 Chemobyl. l Terrestrial Monitoring: j
- Groundwater: Only naturally occurring radioactive material has been ' detected in groundwater. l 1
- Milk: Iodine-131 from nuclear weapons testing fallout was detected in 1976 and !
1977 at concentrations of 1.36 and 23.9 picocuries/ liter respectively. In 1986, 'j concentrations of 8.5 picoeuries/ liter were detected from the nuclear accident at ! Chernobyl. No iodine-131 detected has been attributable to the operation of l Davis-Besse. !
- Domestic and Wild Meat: Only naturally occurring potassium-40 and very low l cesium-137 activity has been detected in meat samples. Potassium-40 has ranged i from 1.1 to 4.6 picoeuries/ gram wet weight. Cesium-137 was detected in 1974, i 1975, and 1981 due to fallout from nuclear weapons testing. I
. Broad leaf Vegetation and Fruits: Only natcrally occurring radioactive material 'l and material from nuclear weapons testing has been detected. :
Soil: Only natural background and material from nuclear weapons testing and the : 1986 nuclear accident at Oernobyl has been detected. 1
~
i
- Animal / Wildlife Feed: Only natural background and material from weapoils testing l has been detected. i l
- Eggs: Only natural background radioactive material has been detected. I i
Aquatic Monitoring 4
- Surface Water (Treated and Untreated): In 1979 and 1980, the tritium -
concentrations at location T-7 were above normal background. IAcation T-7 is a-beach well fed directly by Lake Erie. The founh quaner sample in 1979 read 590. picoeuries per liter, and the first quarter sample in 1980 had a concentration of 960 ' picocuries per liter. A follow up sample was collected in Lake Erie between T-7 and the Davis-Besse liquid discharge point. This sample contained tritium at a concentration of 2737 picoeuries per liter. These concentrations could be attributed to the operation of Davis-Besse. Even so, these results at T-7 were more than 39 times -
~
35 I u
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmentcl Operating Report 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. l 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 l from the mouth of the Toussaint River. The August composite read 884 picocuries per liter. Follow up samples read 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 maxium permissible concentration for tritium in an unrestricted area. This did not have any significant adverse effect on the environment or 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/1. This is only 1 0.032 percent of the maximum permissible concentration of 3,000,000 pCia for l tritium in an unrestricted area, as stated in 10 CFR 20, Appendix B, Part 20, Table 2. l Subsequent samples collected during January 1993 showed that the tritium had returned to below the LLD of 330 pCia. In the fourth quarter of 1994, tritium was detected at 336194 pCiA, slightly above the . lower limit of detection for tritium, at one of the treated water sampling locations. l Tritium was also detected at several of the untreated water sampling locations at an average concentration of 470 pCia 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 pCia to 590 pCia with an average concentration of less than 300 pCia. Fish: Only natural background radioactive material and material from nuclear testing has been detected.
- Shoreline Sediments: Only natural background, material from nuclear testing and from the 1986 nuclear accident at Chernobyl has been detected.
l Direct Radiation Monitoring:
. Thermoluminescent Dosimeters (TLDs): The annual average gamma dose rates recorded by TLDs have ranged from 46.2 to 72.3 millirem per year at control locations and between 32.6 and 74.7 millirem per year at indicator locations. No 36
l DevC)Hesse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report ; ; increase above natural background radiation attributable to the operation of l Davis-Besse has been observed - l 1994 Program Deviations li Provided below is a description and explanation of 1994 environmental sample collection
- deviations. 3
- On 1-3-94, at T-12, SWU composite not available, sampled via grab method. l
-t
- On 2-14-94, at T-12, SWU sample not composite. Sample compositor broke. .j Replaced the composite sample with a grab sample.
- On 2-14-94, at T-3, unable to collect the SWU sample at its location because the -
river was frozen. Replaced T-3 SWU sample with grab sample from T-28 spigot. ! r
- On 3-3-94, at T-3, air sample had a 3 hour discrepency between elapsed time and j pump run time, measured by hour meter. :
i
- On 3-14-94, at T-1, T-2, and T-3, a discrepency between elapsed clock time and pump run time of approximately 0.25 hour due to power supply breaker manipulations. :
- On 3-21-94, at T-4, approximately 5 hour discrepency between elapsed clock time {
and pump run time. There was a power loss of approximately 5 hours resulting from ! replacement ofline fuses.
- On 3 28-94, at T-1, T-2 and T-3, a discrepency of approximately 0.5 hour between l elapsed clock time and pump run time due to power supply breaker manipulations.
- On 4-13-94, at T-119 and T-150, quarterly and annual TLDs were missing. ;
Presumed to be removed by vandals. T-206, T-207 and T-208 Annual TLDs were l mistakenly removed from the field and sent for processing. They were not returned ! to the field.
- On 4-25-94, at T-27, a discrepency of approximately 2 hours between elapsed clock l l
time and pump run time was due to a 2 hour power outage.
- On5 - 94, at T-7, a discrepency of approximately 1 hour between elapsed time and .
pump run time. Suspect line outage. , - On 5-16-94, at T-3, discrepency of approximately I hour between elapsed clock time l and pump run time due to a defective timer. l
- On 5-16-94, at T-12, SWU grab sample was substituted for a composite sample ,
because composite sample was not available. l
- On 5-23-94, at T-12, discrepency of approximately 2 hours between elapsed clock ,
time and pump run time because of a power outage for approximately 2 hours- l i h 37 ! l
- , , - , , , - - , , . , , ..r
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, r [ Davis-Besse Nuclear Power Station - 1994 ( Annual Radaolopcal Environmental OperCing Report
. On 6-27 0 i, at T-8 and T-27, discrepency of approximately 2 hours between elapsed :
clock . ne and pump run time because of a power outage. l 1
~
.: On 7-18-94, at T-2 and T-3, discrepency of approximately 0.6 hour between elapsed !
clock time and pump run time due to power outage. a On 7-26-94, at T-12, pump run time indicated 0 when there was an elapsed clock time of 23 hours. The air sampler was removed for calibration. l
- On 8-11-94, at T-19, BLV was not available. The next available garden in the same
. meterological sector was approximately 563 meters more distant where BLV was obtained. ;
On 9-26-94, at T-4 and T-7, discrepency between elapsed clock times and pump run times of approximately 1.5 hours due to power line outage. j
- On 10-3-94, at T-4, air particulate filter had hole in it which was discovered when the ,
sample media was exchanged. Heavy precipitation during the sample period is - ; thought to be the cause. f
- On 10-12-94, at T-93 and T-203, TLDs were discovered missing when the quarterly l TLDs were being exchanged. The reason is thought to be random acts of vandalism.' j
. On 11-28-94, a:T-1, there was a discrepency between elapsed clock time and pump. ,
run time of approximately 2 hours. Power outage was eliminated as a probable cause. The pump timer was considered suspicious. l c
- On 12-12-94, at T-1, there was a discrepency of greater than 10 hours between the j elapsed clock time and the pump run time. A faulty pump run timer is considered to i be the cause. The sampler was replaced with another unit. ll
- On 12-26-94, at T-9, there was a discrepency of approximately 2 hours between l elapsed clock time and pump run time. A power interruption was the cause. l
- On 11-94, the second soil collection was scheduled but not collected. It was postponed until November because of the 9th refueling o~utage. It was not collected l in November because of rain and early snows preventing a representative collection.
]
- On 11-94, the second fish' collection of the year was not collected. The nets had been I removed from the indictator location earlier in the month. Conditions on the lake had - !
prevented collection early in November. i Atmospheric Monitoring - i Air Samples l l Environmental air sampling is conducted to detect any increase in the concentration of airborne ; radionuclides that may be inhaled by humans or serve as an external radiation source. Inhaled ,; radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skm. ! l
~
38 ! l . 1
Davis-Desse Nuclear Power Station 1994 Annual Radiological Environments! Operating Report _ 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 cartridge 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 radiciodine. The airborne samples are sent to an offsite contractor laboratory for analysis. At the laboratory, the airbome particulate filters are stored for 72 hours before they are analyzed to allow for the decay of naturally occurring short-lived radionuclides. However, due to the short half-life of iodine-131 (approximately eight days), the airbome radiciodine cartridges are analyzed upon receipt by the contractor laboratory. _ Airborne Particulates Davis-Besse continuotisly 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 (composited) and analyzed for gamma emitting radionuclides, strontium-89 and arontium-90. Beta emitting radionuclides were detected at both the indicator and control locations at average concentration of 0.020 pCi/m5 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 radiation. No other gamma emitting radionuclides were detected above their respective LLDs. Strontium-89 (Sr-89) was not detected above its LLD of 0.0009 pCi/m'. Strontium-90 (Sr-90) was detected in one sample (T-4) during the fourth quarter at 0.003i0.001 pCi/m'. For comparison purposes, Sr-90 in air during the preoperational period ranged from 0.0002 pCi/l to 0.0026 pCi/1. These results show no adverse change in radioactivity in air samples due to operation af the Davis-Besse Nuclear Power Station in 1994. Airborne Iodine-131 Airborne iodine-131 samples are collected at the same ten locations as the airborne particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly, scaled in separate collection bags and sent to the laboratory for gamma spectral analysis. In all of the samples collected in 1994, there was no detectable iodine-131 2 above the LLD of 0.07 pCi/m . 39
rc Da#0Besse Nuclear Power Station 1994~ ' Annual Radiological Environmental Operating Report e 9 Airbome Particulate-1994 ' l 0.03 k. 0.025 ! a. e 0.02 -
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Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental OperatMg Report Table 5: Air Monitoring Locations Sample Location Type of Location Description Number Location : T-1 1 Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station T-4 I Site boundary,0.8 miles S of Station T-7 I Sand Beach, main entrance,0.9 miles NW of Station T-8 I Earl Moore Farm,2.7 miles WSW of Station T-9 C Oak Harbor Substation,6.8 miles SW of Station T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station I T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-27 C Crane Creek State Park,5.3 miles WNW of , Station I wb 41
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Davis-Besse Nuclear Power Station 1994 ~ Annual Radiological Environmental Operating Report Terrestrial Monitoring The collection and analysis of groundwater, milk, meat, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. Animal and wildlife feed samples provide additional information on radionuclides that may be present in the food chain. 'Ihe data from soil sampling provides information on the deposition of radionuclides i 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: t tritium, present as a result of the interaction of cosmic radiation with the upper , atmosphere and as a result of routine release from nuclear facilities beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere 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 fem nuclear facilities potassium-40, a naturally occurring radionuclide normally found throughout the environment (including humans) fallout radionuclides from nuclear weapons testing, including strontium-89, strontium-90, cesium-137, cerium-141, cerium-144, and ruthenium-106. These radionuclides may also be released in minute amounts from nuclear facilities The radionuclides listed above are expected to be present in many of the environmental samples ! collected in the vicinity of the Davis-Besse Station. The contribution of radionuclides from the operation of Davis-Besse is assessed by comparing sample results with preoperational data, operational data from previous years, control location data, and the types and amounts of radioactivity normally released from the Station in liquid and gaseous effluents. Milk Samples l 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 i releases onto forage consumed by cows. The radionuclides present in the forage eating cow . become incorporated into the milk which is then consumed by humans. When milk is available, samples are collected at the indicator location and at the control location once a month from November through April, and twice a month from May through October. Sampling is increased in the summer when the herds are usually outside on pasture and not on stored feed. In December of 1993, the indicator location, T-8, was eliminated from the sampling ei I 45
Davis-Besse Nuclear Power Station 1994 Annual Radiological Envimnmental Operating Report program because the family there went out of the dairy business and sold the herd. 'Ihe control location will continue to be sampled monthly in order to gather additional baseline data. If any dairy animals are discovered within five miles of the station, efforts will be made to include them in the milk sampling program. The 1994 milk samples were analyzed for strontium-89, strontium-90, iodine-131 and other gamma emitting radionuclides, stable calcium and potassium. A total of 13 milk samples were collected in 1994. Strontium-89 was not detected above the LLD of 0.7 pCi/l in any of the samples. Strontium-90 was detected in all 13 samples collected. The annual average concentration of strontium-90 was 1.6 pCiA . 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 pCih. 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 (pCia) to the concentration of calcium (gA), and cesium radioisotopes radioactivity (pCiA) to the concentration of potassium (gA) 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. Table 6: Milk Monitoring Location Sample Location Type of Location Description Number Location T-24 C Toft Dairy, Sandusky,21.0 miles SE of Station C = control Groundwater Samples It is unlikely that groundwater will accumulate radioactivity from nuclear facilities, except for those facilities which discharge liquid effluents to the ground via cribs, pits, or trenches. This is because the soil acts as a filter and an ion exchange medium for most radinnuclides. Ilowever, tritium and other radionuclides such as ruthenium-106 have a potential to seep through the soil into the groundwater. Although Davis-Besse does not discharge its liquid ef0uents directly to the ground, REMP personnel sample local wells on a quarterly basis to ensure the early detection of any adverse impact on the local groundwater supplies due to Station operation. The wells 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 m* 46
1 DavbBesse Nuclear PowerStation 1994 Annual Radiological Environmental Operating Report samples are analyzed for beta emitting radionuclides, tritium, strontium-89, strontium-90 and gamma emitting radionuclides. i Beta emitting radionuclides were detected at all three locations at an average concentration 3.5pCi/1. Tritium was not detected above the LLD of 330 pCi/1. Strontium-89 was not detected above the LLD of 1.1 pCi/1. Strontium-90 was detected in indicator sample at an concentration of 0.8 pCi/1. There were no gamma emitting radionuclides detected above their respective LLDs in any of the samples collected. All sample analyses were within normal ranges and were similar to results of previous years. Groundwater 1982-1994 8 7 i l\ f'\ 6
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j ,l e 3, 3 I Y Ng' 2 . . . . , . . . . E E E E E E E E e 8 e 8 E e y{ e e e e e e e - - Figure 13: Shown above are the annual averages for gross beta in groundwater from 1982 - 1994. "Ihe 1994 results are well within the range of previous years. 47 f I
Davis-Besse Nuc1 car Power Station 1994 Annual Radiological Environmental Operating Repon Table 7: Groundwater Monitoring Locations Sample Location Type of Location Description Number Location 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 OC Roving Site I = indicator C = control OC = 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 effluents (from hospitals, nuclear facilities, etc.). Radionuclides from the soil may be absorbed by the roots of the plants and become incorporated into the edible portions. During the growing season, edible broad leaf vegetation, such as kale and cabbage, and fruits, such as apples and grapes, are collected from farms in the vicinity of Davis-Besse. In 1994, broad leaf vegetation samples were collected at two indicator locations (T-17 and T-19) and one control location (T-37). Fruit samples were collected at two indicator locations (T-8 and T-25) and two control locations (T-23 and T-173). Broad leaf vegetation was collected once a month during the growing season. Broad leaf vegetation collected consisted of kale, kohlrabi, lettuce, cabbage and Swiss chard. The fruits collected were apples, pears, and grapes. All samples were analyzed for gamma emitting radionuclides, strontium-89, strontium-90, and iodine-131. Iodine-131 was not detected above the LLD of 0.028 pCi/g (wet)in any broad leaf vegetation nor above the LLD of 0.017 pCi/g (wet)in fruit samples.The only gamma emitting l 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 abeve their LLDs of 0.002 pCi/g (wet) and 0.0067 pCi/g (wet). Strontium-90 (Sr-90) was detected at average concentrations of 0.002 pCi/g (wet) for indicator locations and 0.0014 pCi/g (wet) for control locations. In the fruit samples, Sr-90 was detected at k> cation T-25 (indicator) at 0.0009 l pCi/g. One control location (T-23) indicated 0.0014 pCi/g Sr-90. 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. , 1 l 48 l _ __ _ _ _
_. _. _. _ . _. ~ . . _ _ __.
-l Davis-Besse Nuclear Power Station -1994 Annual Radiological Environmental Operating Report o . .
-t Table 8: Broad Leaf Vegetation and Fruit Locations ;
1 Sample Number Type of Imation Description -. l,
' Imation Location .I i
T-8 I Moore Farm,2.7 miles WSW of Station l' T-17 I Centerior Energy property,0.68 mile SW of Station - 1 T-19 I Hemminger Farm,0.6 mile W of Station ) l T-23 C Heineman Winery, Put-In-Bay,14.3 j miles ENE of Station. , s T-25 I Miller Farm,3.7 miles S of Station T-37 C Bench Farm,13.0 miles SW of Station T-173 C- FireIands Winery, Sandusky,20.0 : miles SE of station. I = indicator C = control j Animal / Wildlife Feed Samples As with broad leaf vegetation and fruit samples, samples of domestic animal feed, as well'as a vegetation consumed by wildlife, provide an indication of airborne radionuclides deposited in ! the vicinity of the Station. Analyses of animal /wildlif feed samples also provide data for ' l determining radionuclide concentration in the food chain. Domestic animal feed samples are l collected at two domestic meat sampling locations. Wildlife feed samples are collected from the l Navarre Marsh onsite and from a local marsh within five miles of the Station. As in all l terrestrial samples, naturally occurring potassium-40, cosmic ray produced radionuclides such as j beryllium-7, and fallout radionuclides from nuclear weapons testing may be present in the feed i samples. ! l Domestic animal feed was collected annually at chicken sampling locations. There is one indicator location (T-197) and'one control location (T-34). The feed collected .j was chicken feed. All samples were analyzed for gamma emitting radionuclides. l Wildlife feed was collected annually at two locations (T-31 and T-198). The samples consisted of the edible portions of cattails. Samples were analyzed for gamma emitting radionuclides. In both the animal and wildlife feed, only naturally occuring potassium-40 was detected. All other radionuclides were below their respective LLDs. The operation of Davis-Besse had no adverse effect on the surrounding environment. 49
Davis-Desse Nuclear Power Station 1994 AnnualRadiologicalEnvironmentalOperatingReport Table 9: Animal / Wildlife Feed Locations Sample Location Type of In:ation Description Number Location i i T-31 I Davis-Besse, onsite roving location . l T-34 C Bertsch farm, Sandusky,20.0 miles SE of Station ! T-197 I Preisman Farm 1.7 miles W of Station T-198 I Toussaint Creek Wildlife Area ! 4.0 miles WSW of Station ; I = indicator C = control ; Wild and Domestic Meat Samples Sampling of domestic and wild meat provides information on environmental radionuclide l concentrations that humans may be exposed to through an ingestion pathway. The principle ; pathways for radionuclide conta'nination of meat animals include deposition of airborne ! radioactivity on their food and drinking water and contamination of their drinking water from i radionuclides released in liquid effluents. i The REMP generally collects wild meat and domestic meat (chickens) and eggs on an annual- ! basis. Wild animals commonly 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 i and mobility of the animal before drawing conclusions on radionuclides concentration in the i local environment or in a species as a whole. > l Both wild and domestic meat samples and eggs were sampled in 1994 as follows: i i Domestic Meat: Chickens were collected at one indicator location (T-197) and one [ control location (T-34). The samples were analyzed for gamma emitting nuclides. j _ . r Wild Meat: Muskrats were collected from the marsh on site (T-31). The sample was : analyzed for gamma emitting nuclides. Eggs: Eggs were collected from one indicator location (T-197) and one control location (T-34). The eggs were analyzed for gamma emitting radionuclides.The only gamma emitter detected in all the samples was potassium-40 which is naturtily i occurring. , l I r
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Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Table 10: Wild and Domestic Meat Locations Sample Location Type of Location Description Number Location T-31 I Onsite roving location T-34 C Bertsch Egg Farm, Sandusky,20.0 miles SE of Station T-197 I Priesman Farm,1.7 miles W of Station I = indicator C = control Soil Samples Soil samples are generally collected twice a year at the sites which are also equipped with air samplerr. Only the top layer of soil is sampled in an effort to identify possible trends in the local environmental nuclide concentration caused by atmospheric deposition of fallout and station released radionuclides. Generally, the sites are relatively undisturbed, so that the sample will be representative of the actual deposition in the area. Ideally, there should be little or no vegetation present, because the vegetation could affect the results of analyses. Approximately five pounds of soil are taken from the top two inches at each site. Many naturally occurring radionuclides such as beryllium-7 (Be-7) and potassium-40 (K-40) and fallout radionuclides from nuclear weapons testing are detected. Fallout radionuclides which are often detected include strontium-90 (Sr-90), cesium-137 (Cs-137), cerium-141 (Ce-141) and ruthenium-106 (Ru 106). During 1994, soil was collected at ten sites in April and one site in September. The indicator locations included T-1, T-2, T-3, T-4, T-7, and T-8. The control locations were T-9, T-11, T-12, T-23, and T-27. All soil :amples were analyzed for gamma emitting radionuclides. The results show that the only gamrna emitter detected in addition to naturally occurring Be-7 and K-40, was Cs-137. Cs-137 was found in both indicator and control locations at average concentrations of 0.24 and 0.48 pCi/g dry respectively. The concentrations were similar to that observed in previous years (Figure 14). 51 -
DaCBesse Nucicar Power Station 1994 Annual Radiological Environmentd Operating Report Soll 1972-1994 1.2 p* 1 E.
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Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report t Table 11: Soil Locations l Sample Location Type of Location Description I Number Location T-1 I Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary 1.4 miles ESE of Station T-4 I Site boundary 0.8 miles S of Station T-7 I Sand Beach, main entrance,0.9 miles NW of Station T-8 I Moore Farm,2.7 miles WSW of station T-9 C - Oak Harbor Substation,6.8 miles SW of Station T-11 C Port Clinton Water Treatme it Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-23 C South Bass Island,14.3 miles ENE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station I = indicator C = control d 53
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Dav2-Desse Nuc1 car Power St-tion 1994 Annual Radiological Environmental Operating Report Aquatic Monitoring Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-off/ soil erosion, and releases of radioactive material in liquid effluents from hospitals or 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 rtdionuclides through the aquatic food chain with eventual consumption of aquatic organisms, such as fish. To monitor these pr thways, Davis-Besse samples treated surface water (drinking water), untreated surface water (lake or rive,r water), fish, and shoreline sediments. Treated Surface Water Treated surface water is water from Lake Erie which has been processed for human consumption. Radiochemical analysis of this processed water provides a direct basis for assessing the dose to humans from ingestion of drinking water. Samples of treated surface water were collected from three indicator (T-28, T-50, and T-144) and two control locations (T-11 and T-12). These locations include the water treatment facilities for Davis-Besse, Erie Industrial Park, Port Clinton, Toledo, and Green Cove. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta emitting radionuclides. The samples were also composited in a quarterly sample and analyzed for strontium-89, strontium-90, gamma emitting radionuclides, and tritium. One QC sample was collected from a routine location which was changed each month. The annual average for beta emitting radionuclides for indicator and control locations were 2.1 and 2.2 pCi/l respectively. These results are similar to previous years as shown in Figure 18. One quarterly treated surface water sample at T-144 (Green Cove) had tritium detected at a concentration of 336194 pCi/1. All other quarterly tritium analysis results were less than the LLD of 330 pCi/l. All cesium-137 results were less than the LLD of 10.0 pCi/1. Strontium-89 and strontium-90 were not detected in any sample above 1.6 pCi/1. Strontium 90 was detected at 0.6 pCi/l(the LLD for Sr-90) at two indicator locations and 0.8 pCi/l at a third location. These results are similar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse. 1 I i I 57 l
Davis-Besse Nuclear Power Stclion 1994 Annual Radiological Environmental Operating Report Treated Saface Water 1972-1994 3 3.3 ,7 3.1 - k- ,. < I\ R J 2.9- ,, - t Ar- ' t a .
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Table 12: Treated Surface Water Locations i Sample location Type of Location Description Number Imcation T-11 C Port Clinton Water Treatment Plant 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant 23.5 miles WNW of Station T-23 C Put-In-Bay Water Treatment Plant 14.3 miles , ENE of Station. (1st quarter 1994 only- then deleted from the program) T-28 1 Treated Water supply from Davis-Besse site T-50 1 Erie Industrial Park, Port Clinton,4.5 miles SE of Station T-143 OC Ouality Control Site T-144 1 Green Cove Condominiums,0.9 miles NNW of Station 1 = indicator C = control OC = quality control s 58
= Davis-Besse Nuclear Power Station 1994 Annual Radiological Environm:nt:1 Operating Report Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to humans from external exposure from the lake surface as well as immersion in the water. It also provides information on the radionuclides present which may affect drinking water, fish, and irrigated crops. Reutine 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, Erie Industrial Park, and Put-In-Bay Water Treatment Plants. A sample is also collected from Lake Erie at the mouth of the Toussaint River. These samples are collected weekly and composited monthly. The monthly composite is analyzed for beta emitting radionuclides, tritium, and gamma emitting radionuclides. The samples are further composited quarterly and analyzed for strontium-89 and strontium-90. A OC sample is also collected weekly. It is at a different location each month. Summer Program : The summer program is designed to supplement the routine untreated water sampling program in order to provide a more comprehensive study during the months of high lake recreational activity, such as boating, fishing, and swimming. These samples are obtained in areas along the shoreline of Lake Erie.The samples are collected monthly and analyzed for beta emitting radioactivity, tritium, strontium-89, strontium-90 and gamma emitting radionuclides. Beta emitting radionuclides had an average concentration of 2.2 pCiM at indicator and 2.4 pCiM at control locations respectively. Of the 135 tritium analyses performed on untreated water,115 were less than the LLD of 330 pCi/1. The October indictur locations had tritium detected at concentrations ranging from l 753-1256 pCi/1. Two control locations indicated 389 and 338 pCi/l respectively. It is presumed I that the tritium was caused by the operation of Davis-Besse. The maximum tritium I concentration detected is only 0.0012 of the effluent concentration limit of 1,000,000 pCi/l for l tritium in an unrestricted area, as provided by 10CFR20, Appendix B, Table 2, Column 2. Cesium-137 and strontium-89 were not detectable in samples of untreated water above their l LLDs of 10 pCi/l and 1.2 pCi/1, respectively. Strontium-90 was detected at an average concentration of 0.7 pCi/l at indicator locations and 0.7 pCi/l at control locations. The results of untreated water show that the operation of Davis-Besse had no adverse impact on nearby residents or on the environment. l l l l
.- l 59
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmentc1 Operating Report i Untreated Surface Water 1977-1994 6.5 , ! 6- -/3 . 5.5 - -1
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3- A. 2.5 3 -- + l 2 1.5 . , , , . . . , , , , , , , RRSEEEE3EEEEEEEEE3 3333322232 SSSSSSSS Figure 19: De average concentration of beta emitting radionuclides in untreated water was similiar betwecn control and indicator locations. His demonstrates that Davis-Hesse had no radiological impact on the surrounding environment. 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 3.1 pCi/l and 2.6 pCi/l at routine locations. Tritium and cesium-137 were below their respective LLDs.- ; There was good agreement between the routine and OC locations. s w-I t \ . f 60
1 Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report l Table 13: Untreated Surface Water Locations l Sample Iacation Type of Location Description l Number location j T-3 I Site boundary,1.4 miles ESE of Station [ T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant, sample taken ; from intake crib,11.25 miles NW of Station , i T-28 I Davis-Besse Water Treatment Plant iI T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE , of Station ! i T-131 I Lake Erie,0.8 miles NE of Station T-132 I Lake Erie,1.0 miles E of Station ; T-133 I Lake Erie,0.8 miles N of Station T-134 I Lake Erie,1.4 miles NW of Station f T-135 I Lake Erie,2.5 miles WNW of Station T-137 C Lake Erie,5.8 miles WNW of Station I i T-138 C Lake Erie,11.0 miles NW of Station j T-145 QC Roving Quality Control Site T-152 C Lake Erie,15.6 miles WNW of Station , T-158 C Lake Erie,10.0 miles WNW of Station ! T-162 C Lake Erie,5.4 miles SE of Station T-167 C Lake Erie,11.5 miles E of Station I = indicator C = control 7 61
Davis-Besse Nuclear Power St-tion 1994 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 Lupplies, or as an xternal radiation source from shoreline exposure to fishermen and swimmers. Samples of deposited sediments in water along the shore were collecteJ at orious times from three indicator sites (T-3, T-4, and T-132) and one control location (T-//} choreline sediment was collected with a shovel, or a hand held dredge. All samples were :auy; -d for gamma emitting radionuclides. Naturally occurring potassium-40 was detected a brth controls and indicator locatioic. r ium-137 es was detected at average concenta ions of 0.09 pCi/g at indicator locations a d <0.007 pCi/g at control locations respectivciy. Atmospheric testing of nuclear weapons has been the principal sourcs of (cd im-137 in the environment to date. Although no atmospheric nuclear weapons tests m been reported since 1980, cesium-137 is still present in shoreline aediment samples because -J hs long half life (approximately 30 years). No other gamma emitting radionuclides were aetected in any of the samples. The concentrations of those detected were consistent with normal concentrations for this area and were not attributed to plant operation. Table 14: Shoreline and Bottom Sediment Locations Sample Location Type of location Description Number Location T-3 1 Site boundary,1.4 miles ESE of Station T-4 I Site boundary,0.8 miles S of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station T-132 I Lake Erie,1.0 miles E of Station 1 = indicator C = control 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 l
=
62
Davis.Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report cesium-137, and strontium-90. Depending upon the feeding habit of the species (e.g., bottom-feeder versus predator), results from sample analyses may vary. With the aid of a local commercial fisherman, Davis-Besse routinely collects three species of fish (walleye, white perch or white bass and carp) twice a year from sampling locations near the Station's liquid discharge point and more than ten miles away from the Station where fish 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 bottom feeders and thus would be more likely to be affected by radionuclides deposited in lake sediments. The edible portion of fish were analyzed for beta and gamma emitting radionuclides. The average concentration of beta emitting radionuclides in fish muscle was similar for indicator ; and control locations (3.35 pCi/g and 3.43 pCi/g wet weight, respectively). Cesium-137 was detected in a white bass sample at T-33, an i.'Ai:ator location. The concentration of Cs-137 was 0.02 pCi/g. For comparison, the LLD for carp taken at the same time in the same location was 0.025 pCi/g which is similar to concentration of previous years. ; Fish 1972-1994 , 5 4.5 4 A, 3.5 - A,- 3 --*c e
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Davis-Besse Nuclear Power Station 1994 Annual Radiological Environm:nt:.1 Operating Report Table 15: Fish IAcations l l Sample I.ocation Type of Iacation Description Number Location T-33 I Lake Erie, within 5 miles radius of Station T-35 C Lake Erie, greater than 10 mile radius of Station I = indicator C= control
@A 64
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Davis.Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Therrnoluminescent Dosimeters Radionuclides present in the air, and those deposited on the ground, cause dose to humans due to the immersion of the human in the atmosphere or by the human walking, standing, etc. on the ground. Direct radiation levels at and around Davis-Besse are constantly monitored by thermoluminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information. The TLDs used at Davis-Besse contain a calcium sulfate: dysprosium (CaSO :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 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 of light detected is directly proportional to the amount of radiation to which the TLD was exposed. The reading process rezeros the TLD and prepares it for reuse. TLD Collection Davis-Besse has 75 TLD locations (64 indicator and 11 control) which are collected and replaced on a quanerly and annual basis. Eighteen OC 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. In 1994, the average dose equivalent for quarterly TLDs at all indicator locations was 13.6 mrem /91 days, and for all control locations was 14.5 mrem /91 days. The average dose equivalent for annual TLDs in 1994 was 49.6 mrem /365 days at indicator locations and 52.0 mrem /365 days for control locations. These results are similar to those observed in past years; in 1974,55-62 mrem in one year was reported as being the annual average dose equivalent. Quality Control TLDs 1 Duplicate TLDs have been placed at 18 sites. These TLDs were placed in the field at the same time and at the same location as some of the routine TLDs, but were assigned quality control site numbers. This allows us to take several measurements at the location without the laboratory 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 14.5 mrem /91 days while the quality control TLDs yielded an average dose equivalent of 15.3 mrem /91 days. All the quality control and routine sample 68
l Davis-Besse Nuc1 car Power Station 1994 - Annual Radiological Environmental Operating Report results were similar, demonstrating the accuracy of both the TLDs and the laboratory's measurements. Environmental TLDs 1973-1994 25 : U 20 - 15 ,
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5 10 - E i 5 - - 0 . , l . . . : . . . . . . . . . . - R R R R E 2 E S S E N 2 S S S S S S S S 3 , Figure 24: The similarity between indicator and mntrol results demonstrated that the operation of Davis-Besse has not caused any abnormal gamma dose. NRC TLD Monitoring The NRC has 22 TLDs located around Davis-Besse as part of their Direct Monitoring Network Program. Davis Besse maintains TLDs at all the NRC TLD monitoring sites. The NRC collects their TLDs on a quarterly basis, whereas Davis-Besse collects TLDs quarterly and annually at 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 of lithium borate: copper l (Li 2B,0,: Cu) and two elements of calcium sulfate: thulium (CaSO,: Tm). The difference in t 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 15.912.9 mrem /91 days for the Davis-Besse TLDs tnd 17.lf2.8 mrem /91 days for the NRC TLDs (data from first, second, and third quarter). As the confidence intervals overlap, there is no statistical difference between the measurements.. s 69
DavD-Besse Nuclear Power Station 1994 Annual Radiological Environmentcl Opercing Report NRC and Davis-Besse TLD Results for 1988-1994 20 18 - u..'
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4 2 0 , , , , , 1988 1989 1990 1991 1992 1993 1994 Figure 25: Comparcs NRC and Davis-Besse TLDs for last six years. Table 16: Thermoluminescent Dosimeter Locations Sample Location Type of Location Description Number Location T-1 I Site boundary,0.6 miles ENE of Station T-2 I Site boundary,0.9 miles E of Station T-3 I Site boundary,1.4 miles ESE of Station T-4 I Site boundary,0.8 miles S of Station _ T-5 I Site boundary,0.5 miles W of Station T-6 I Site boundary,0.5 miles NNE of Station T-7 I Sand Beach, main entrance,0.9 miles NW of Sation ese 70
i DavC>Besse Nuclear Power Station - 1994' ' Annual Radiological Envitonmental Operating Report I Table 16: Thermoluminescent Desimeter Locations (continued) j i Sample Location Type of Location Description ! Number - Location i i T-8 I Earl Moore Farm,2.7 miles WSW of Station ; I T-9 C. Oak flarbor Substation,6.8 miles SW of Station l T-10 I Site boundary,0.5 miles SSW of Station near ! warehouse T-11 C Port Clinton Water Treatment Plant,9.5 miles - 1 SE of Station ; T-12 C Toledo Water Treatment Plant,23.5 miles l WNW of Station i South Bass Island,14.3 miles ENE of Station, ' T-23 C near lighthouse - T-24 C Sandusky,21.0 miles SE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station , i 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 T-44 I Site boundary,0.5 miles WSW of Station T-45 I Site boundary,0.5 miles WNW of Station i e >
.e 71 '
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmenta10perating Repon - Table 16: Thersnoluminescent Dosimeter Locations (continued) Sample Location Type of Location Description : Number Location l l T-46 I Site boundary,0.5 miles NW of Station T-47 I Site boundary,0.5 miles N of Station T-48 I Site boundary,0.5 miles NE of Station f T-49 I Site boundary,0.5 miles NE of Station T-50 I Eric Industrial Park, Port Clinton,4.5 miles SE of Station T-51 C Daup Farm,5.5 miles SSE of Station , T-52 I Miller Farm,3.7 miles S of Station T-53 I Nixon Farm,4.5 miles S of Station . T-54 I Weis Farm,4.8 miles SW of Station T-55 I King Farm,4.5 miles W of Station T-60 I Site boundary,0.3 miles S of Station T-61 1 Site boundary,0.6 miles SE of Station T-62 I Site boundary,1.0 mile SE of Station T-63 I Site boundary,1.1 miles ESE of Station T-65 I Site boundary,0.3 miles E of Station i T-66 I Site boundary,0.3 miles ENE of Station T-67 I Site boundary,0.3 miles NNW of Station T-68 I Site boundary,0.5 miles WNW of Station T-69 I Site boundary,0.4 miles W of Station O e4 72
fi Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmentc! Operating Report Table 16: Thermelundnescent Dosimeter Locations (continued) Sample Imtion Type of Location Number Number Location T-71 I Site boundary,0.1 mile NNW of Station L T-73 I Site boundary,0.1 mile WSW of Station T-74 I Site boundary,0.1 mile SSW of Station T-75 I Site boundary, 0.2 mile SSE of Station - T-76 I Site boundary,0.1 mile SE of Station T-80 OC Ouality Control Site - T-81 OC Ouality Control Site T-82 OC Ouality Control Site T-83 OC Ouality Control Site T-84 OC Ouality Control Site T-85 OC Ouality Control Site T-86 OC Ouality Control Site T-88 OC Ouality Control Site T-89 OC Ouality Control Site T-91 I State Route 2 and Rankie Road,2.5 miles SSE of Station T-92 I 1.ocust 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
~
73
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued) . l l Sample Imtion Type of Location Number , Number Location T-95 C State Route 579,9.3 miles W of Station 'T-100 C Ottawa County Highway Garage, Oak Harbor, i 6.0 miles S of Station t T-111 C Toussaint North Road,8.3 miles WSW of Station T-112 I Thompson Road,1.5 miles SSW of Station ; I T-113 OC Ouality Control Site ! T-114 OC Ouality Control Site T-115 OC Ouality Control Site , T-116 OC Ouality Control Site
.-117 OC Ouality control Site T-118 OC Ouality Control Site T-119 OC Ouality Control Site f T-120 OC Ouality Control Site 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 of Station T-123 I Zetzer Road,1.6 miles WSW of Station T-124 C Church and Walnut Street, Oak Harbor,6.5 -
- miles SSW of Station >
l T-125 I Behlman and Bier Roads,4.4 miles SSW of Station I l T-126 I Camp Perry Western and Toussaint South Road,3.7 miles S of Station
~
74
i Davis.Bense Nuclear Power Station 1994 Annual Radiological Environmentcl Opedng Report . Table 16: Thermoluminescent Dosimeter Locations (continued) ; i Sample Location Type of Location Number Number location j 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-150 I Humphrey and Hollywood Road,2.1 miles NW of Station l T-151 I State Route 2 and Humparey Road,1.8 miles WNW of Station T-153 I Leutz Road,1.4 miles SSW of Station , T-154 I State Route 2,0.7 miles SW of Sation T-200 OC Ouality Control Site . T-201 I Sand Beach,1.1 miles NNW of Station , T-202 I Sand Beach 0.8 miles NNW of Station L T-203 I Sand Beach,0.7 miles N of Station ; l l T-204 I Sand Beach,0.7 miles N of Station i i l T-205 I Sand Beach,0.5 miles NNE of Station T-206 I Site Boundary,0.6 miles NW of Station T-207 I Site Boundary,0.5 miles N of Station _T-208 I Site Boundary,0.5 miles NNE of Station. l t 75 I ..
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Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Conclusion The Radiological Environmental Monitoring Program at Davis-Besse is conducted to determine the radiological impact of the Station's operation on the environment. Radionuclide concentrations measured at indicator locations were compared with concentrations measured at control locations, in previous operational studies and in the preoperational surveillance program. l These comparisons indicate normal concentrations of radioactivity in all environmental samples collected in 1994. Davis-Besse's operation in 1994 had no adverse impact on the residents and environment surrounding the station. In fact, the dose associated with the operation of 1 Davis-Besse is estimated to be 0.043 percent of that received from natural and man-made sources. The results of the sample analyses performed during the period of January through December,1994 are summarized in Appendix D of this report. r s 79
. Davis-Desso Nuc! car Power Station 1904 Annual Radiologicel Environmental Operating Report References l
- 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. Eisenbud ,M., Environmental Radioactivity, Academic Press, Inc., Orlando, FL (1987).
- 3. " Environmental Radiation Measurements," Report No.50, National Council on Radiation Protection and Measurement, Washington, D.C (December 1976). j
- 4. " Exposure of the Population in the United States and Canada from Natural Background Radiation," Report No.94, National Council on Radiation Protection and Measurement, Washington, D.C (December 1987).
1 1 5. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy l Installations," DOE /EP-0023, Department of Energy, Washington, D.C (July 1981).
- 6. " Ionizing Radiation Exposure of the Population of the United States," Report No.93, National Council on Radiation Protection and Measurement, Washington, D.C (September 1987).
- 7. Kirk, T.J. and G.N. Midkiff, Health Physics Fundamentals, General Physics Corporation !
(1980). ) 8. Natural Background Radiation in the United States," Report No.45, National Council on l Radiation Protection and Measurement, Washington, D.C (November 1975).
- 9. " Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion "As Low As Reasonably Achievable' for Radioactive Material in Light WR Cooled Nuclear Power Reactor Effluents," Code of Federal Regulations, Title 10 Energy, Part 50
" Domestic Licensing of Production and Utilization Facilities," Appendix I(1988).
l
- 10. " Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry,"
American National Standards Institute, Inc., ANSI-N45-1975, New York, New York (1975).
~~
- 11. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No.92, National Council on Radiation Protection and Measurement, Washington, D.C.
f. (December 1987).
- 12. " Radiological Assessment: Predicting the Transport , Bioaccumulation and Uptake by Man of Radionuclides Released to the Environment, " Report No.76, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1984).
80
. .-- . ~ . . _ . . - . ..
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report '13. Regulatory Guide 4.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," US NRC(April 1975). 14.. Regulatory Guide 4.13," Performance, Testing, and Procedural Specifications for 4 Thermoluminescent Dosimetry: Environmental Applications," US NRC (July 1977). l
- 15. ' Regulatory Guide 4.15," Quality Assurance for Radiological Monitoring Programs (Normal >
Operations) - Effluent Streams and the Environment," US NRC (February 1979).
- 16. Regulatory Guide 0475, " Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities," US NRC (September 1978).
- 17. Regulatory Guide 0837,"NRC TLD Direct Radiation Monitoring Network," US NRC (1993).
18.' " Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, Part 20 (1993). :
- 19. 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). ; 20.Teledyne Isotopes Midwest L2boratory, " Final Monthly Progress Report to Toledo Edison Company", (1991-1993).
- 21. Teledyne Isotopes Midwest Laboratory,"Preoperational Environmental Radiological Monitoring for the Davis-Besse Power Station Unit No.1", Oak Harbor, Oh (1972-1977).
- 22. Toledo Edison Company, " Davis-Besse: Nuclear Energy for Northern Ohio."
- 23. Toledo Edison Company, " Davis-Besse Nuclear Power Station, Unit No.1, Radiological !
Effluent Technical Specifications," Volume 1, Appendix A to License No. NPF-3. ;
- 24. Toledo Edison Company, " Final Environmental Statement -Related to the Construction of Davis-Besse Nuclear Power Station," Docket #50-346 (1987). ,
- 25. Toledo Edison Company, " Performance Specifications for Radiological Environmental Monitoring Program," S-72N, Revision 2 (1993).
- 26. Toledo Edison Company, " Radiological Environmental Monitoring Program," t DP-HP-00015.
- 27. Toledo Edison Company, " Radiological Environmental Monitoring Quarterly, Semiannual, ,
and Annual Sampling,: DB-HP-03004. 1 w.
Davb-Besse Nucicar PowerStation 1994 Annual Radiological Environmental Operating Report
- 28. Toledo Edison Company, " Radiological Monitoring Weekly, Semimonthly, and Monthly Sampling," DB-HP-03005.
- 29. Toledo Edison Company, "REMP Enhancement Sampling, "DB-HP-10101, Revision 1, (1992).
- 30. Toledo Edison Company, " Updated Safety Analysis for the Offsite Radiological Monitoring Program," USAR 11.6, Revision 14,(1992).
- 31. Tcledo Edison Company, " Annual Radiological Environmental Operating Report Prepartion and Submittal," DB-HP-00014, Revision 0,(1990).
- 32. Toledo Edison Company, Davis-Besse Nuclear Power Station, Offsite Dose Calculation Manual, Revision 5.2.
I 33. " Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979). o* 82
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Davfo 13csse Nuclear Power Station 1994 Annual Fadiological Environmental Operating Report Radioactive Effluent Release Report July 1 to December 31,1994* Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ionizing radiation were recognized and efforts were made to establish radiation protection standards.The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recommendations have been given legislative authority through publication in the Code of 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 is Reasonably Achievable (ALARA). The ALARA principle applies to educing 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 During the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in the primary coolant water. The three types of radioactive material released are noble gases, 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. These gases are then collected by a system designed for gas collection and storage for radioactive decay prior to release. Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primary coolant system. These liquids are collected through a series of floor and equipment drains and sumps. All liquids of this nature are monitored and processed, if necessary, prior to release. l
*Jan 1 - June 30,1994 were previously submitted in the 1993 to 1994 Radioactive Effluent Release Report i 83
l l Davis.Besse Nuclear Power Stalon 1994 Annual Radiological Environmental Operating Report I i Noble Gas 1 Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologically and chemically nonreactive. They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an external source of radiation exposure to the body. Xenon-133 and xenon-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive noble gases released. They are readily dispersed in the atmosphere. Iodine and Particulates Annual releases of radioisotopes ofiodine, and those particulates with half-lives greater than 8 l days, in gaseous and liquid effluents are small. Factors such as their high chemical reactivity l and solubility in water, combined with the high efficiency 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 contribution of radioactive iodine to human dose is to the thyroid gland, where the body concentrates iodine. l The principal radioactive particulates released are fission products (e.g., cesium-134 and cesium-137) and activation products (e.g., cobalt-58 and cobalt-60). Radioactive cesiums and cobalts contribute to internal radiation exposure of tissues such as the muscle, liver, and intestines. These particulates are also a source of external radiation exposure if deposited or the ground. Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in liquid effluents. It is also present in gaseous effluents. Tritium is produced in the reactor coolant as a result of l neutron interaction with deuterium (also a hydrogen isotope) present in the water and with the boron in the primary coolant. When tritium is ingested or inhaled it is dispersed throughout the l body until eliminated. Processing and Monitoring Effluents are strictly controlled to ensure radioactivity released to the environment is minimal l and does not exceed regulatory limits. Effluent control includes the operation of monitoring _ _ systems, in-plant and environmental sampling and analyses programs, quality assurance programs for effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring. l l The radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gaseous wastes which contain radioactivity. For example, the Waste Gas Decay Tanks are holding tanks which allow radioactivity in gases to decay prior to release via the station vent. . l 84
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits. These instruments provide a continuous indication of the radioactivity present. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure the lim' aill not be exceeded. If a monitor alarms, a release from a tank is automatically st' pd. All wastes are sampled prior to release and analyzed in a laboratory to identify the specific concentrations of radionuclides being released. Sampling and analysis provide a more sensitive and precise method oidetermining effluent composition than with monitoring instruments alone. A meteorological tower is located in the southwest sector of the Station. It is linked to computers which record the meteorological data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public. Beyond the plant, devices maintained in conjunc' ion 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 define the methods by which people may become exposed to radioactive material. The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the environment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. Information on the water flow, wind speed, and wind direction at the time of a gaseous or liquid release is used to evaluate how the radionuclides will be distributed in an area. An important factor in evaluating the exposure pathways is the use of the environment. Many factors are considered such as dietary intake of residents, recreational use of the area, and the locations of homes and farms in the area. i The external and internal exposure pathways considered are shown in Figure 29. The release of f radioactive gaseous effluents 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 i effluents involves pathways such as drinking water, fish consumption, and direct exposure from the lake at the shoreline and while swimming. l i 85
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Davis-Hesse Nuclear Power Station 1994 Annual Radiological Environmentc1 Operating Report : Diluted By Atmosphere Airborne Releases r~ Q ll : Animals Plume \b > Exposure . , . (Milk, Meat) MUM Y ::. p[:D;y:::1 :;& I bf }el - Consumed N [ t Bvman lQ % \ {
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m.., e y, { i.- LAKE I ? t Figure 29: 'Ihe exposure pathways shovn here, are monitored through the Radiological Environmental Monitoring ; Pmgram (REMP), and are considered when calculating doses to the public. Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure pathway which will provide, for a specific radionuclide, the greatest dose to a pcpulation, or to a specific group of the population, called the critical group. The critical group may vary depending on the radionuclides involved, the age . and diet of the group, or other cultural factors. The dose may be delivered to the whole body or .! to a specific organ. The organ receiving the greatest fraction of the dose is called the critical ! l organ. Dose Assessment i ! l Dose is the energy deposited by radiation in an exposed individual. Whole body exposure to i i 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 j 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. . i i t 86 ' 1
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report The total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the amount of time that the radionuclide remains in the organ. l Some 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. , The dose to the general public in the area surrounding Davis-Besse is calculated for each liquid or gaseous release. The dose due to radioactive material released in gaseous effluents is calculated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the weather conditions 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 released in liquid effluents is calculated using factors such as the total volume of liquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption, shoreline and swimming factors). These calculations produce a conservative estimation of the dose. ReSults The Radioactive Effluent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Station during the period from Julyl,1994 through December 31,1994.
- Summation of the quantities of radioactive material released in gaseous and liquid effluents
- Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites A listing of all radioactive effluent monitoring instrumentation required by the Offsite Dose Calculation Manual (ODCM), but which were inoperable for more than 30 days During the period of July 1,1994 through December 31,1994, the estimated maximum individual offsite dose due to radioactivity released in effluent was:
Liquid Effluents:
- 6.81E-02 mrem, whole body
. 8.87E-02 mrem, liver Gaseous Effluents:
Noble Gas: 1.51E-03 mrad, whole body
- 6.72E-03 mrad, skin D4 87
Davis-Desse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Iodine - 131, Tritium, and Particulates with Half-lives greater than 8 Days:
. 1.22E-03 mrem, whole body
. 4.49E-03 mrem, thyroid These doses are an extremely small fraction of the limits set by the NRC in the Davis-Besse ODCM.
Additional normal release pathways from the secondary system exist. For gaseous effluents, these pathways include the auxiliary feed pump turbine exhausts, the main steam safety valve system and the atomspheric 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 release tables in this report. There were no abnormal liquid releases and one abnormal gaseous release during this reporting period. No changes to the Process Control Program (PCP) occurred during this time period. Revision 7 to the Offsite Dose Calculation Manual was written during this reporting period and accompanies this report. Regulatory Limits Gaseous Effluents In accordance with Offsite Dose Calculation Manual, dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following: Noble gases:
. Released at a rate equal to or less than 500 mrem TEDE per year. (Note: the total dose due to these releases is also limited to 50 mrem in any calendar year.)
. Released at a rate such that the total dose to the skin will be less than or equal to 3000 mrem in a year. _
Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
. Released at a rate such that the total dose to any organ will be less than or equal to 1500 mrem in a year.
V' Davis-Besse Nucicar Power Stationi 1994' Annual Radiological Environmental Operating Report In accordance with 10CFR50, Appendix I, Sec. IIB.1, air dose due to radioactivity released in j gaseous effluents to areas at and beyond the site boundary shall be li:nited to the following: 1 i
- - 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 lodine-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 limited to the ! 1 following:
- less than or equal to 7.5 mrem total to any organ in any calendar quarter.
- Less than or equal to 15 total mrem to any organ in any calendar year.
Liquid Effluents i In accordance with 10CFR50, Appendix I, Sec IIA, the dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited ! to accumulated doses of:
. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to l any organ in any calendar quarter. j i
- - less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to ! any organ in any calendar year. ; Effluent Concentration Limits The Effluent Concentration Limits (ECs) for liquid and gaseous effluents at and beyond the site boundary are listed in 10CFR20, Appendix B, Table II, Column 2, with the most restrictive EC : being used in all cases. For dissolved and entrainea gases the EC of 2.0E-04pCi/ml is applied. < This EC is based on the Xe-135 DAC of 1x10-5 pCi/mi of air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2. ; Average Energy : 1 The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and .j activation products to less than or equal to 500 mrem in a year to the total body and less than or equal to 3000 mrem in a year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, " Measuring, Evaluating, and j 89
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f Ds4Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report -
.- i 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 : a Fission and Activation Gases-These gases, excluding tritium, are collected in a marinelli beaker specially modified for gas sampling, steel flasks, or glass vials and are counted on a germanium detector for principal ; gamma emitters. Radionuclides that are detected are quantified via gamma spectroscopy. Tritium gas is collected using a bubbler apparatus and counted by liquid scintillation. f Iodines ! Iodines are collected on a charcoal cartidge filter and counted on a germanium detector. .l Specific quantification of each iodine radionuclide is via gamma spectroscopy. Particulates Particulates are collected on filter paper and counted on a germanium detector. Specific j quantification of each radionuclide present on the filter paper is via gamma spectroscopy.. ; Liquid Effluents Liquid effluents are collected in a marinelli beaker and counted on a germanium detector. Quantification of each gamma-emitting radionuclide prese.it in liquid samples is via gamma j spectroscopy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite l sample in a liquid scintillation counting system. j i r f 1 i l i
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Davis-Iksee Nuclear Pbwer Sation 1994 L AnnualRadiolopen!EnvironmerwalOperating Report Batch Releases Liquid from 7/1/94 to 12/31/94
- 1. Number of batch releases: 44
- 2. Total time period for the batch releases: 74.9 hours
- 3. Maximum time period for a batch release: 205 minutes
- 4. Minimum time period for a batch release: 75 minutes
- 5. Average tirae period for a batch release: 102 minutes i Gaseous from 7/1/94 to 12/31/94 l
- 1. Number of batch releases: 8
- 2. Total time period for the batch releases: 77.5 hours : ;
- 3. Maximum time period for a batch release: 1320 minutes i
- 4. Minimum time period for a batch release: 156 minutes l
- 5. Average time period for batch release: 581 minutes I Abnormal Releases On August 21,1994, while venting and draining the Auxiliary boiler, small amounts of steam ;
were released to the atmosphere. There was a total of 6.02E-05 curies of tritium released which ' resulted in no quantifiable gamma and beta air dose. A dose of 4.81E-08 mrem resulted from iodine and particulate which is 3.21E-07 percent of the annual limit. .
+
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Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report Percent of ODCM Release Limits 1 l The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent oflimits, for July 1,1994 through December 31,1994. 1 SPECIFICATION IlMIT PERCENTOFIlMIT ReportPeriod: July 1,1994 - December 31,1994 (gaseous) ; Noblegases(gamma) 10 mrad 1.51E4)2 ; Noblegases(beta) 20 mrad 3.36E-02 ; I-131, tritium and particulates with half-lives > 8 days 15 mrem 2.99E-02 Report Period: July 1,1994 to Decemixr 31,1994 (liquki) Totalbody 3 mrem 2.27E+00 Organ 10 mrem 8.87E-01 Sources of Input Data
- Water Usage: Appendix I analysis, NRC Docket 50-346, " Evaluation of Compliance with Appendix I to 10CFR50, June 4,1976, Davis-Besse Nuclear Power Station." :
. 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 entitled " Agricultural Statistics and j Livestock Marketing Account,1980"; the Agricultural Ministry of Ontario 1980 ; report entitled " Agricultural Statistics for Ontario - 1980 Publication 21,1980"; the ! Michigan Department of Agricullture, July,1981 report entitled " Michigan Agricultural Statsitics,1981"; the Ohio Crop Reporting Service,1981 report entitled,
" Ohio Agricultural Statistics,1981." ;
- Gaseous and liquid source terms: Tables 17 through 21 of this report.
- Location of the nearest individuals and pathways by sector out to 5 miles, see Limd Use Census Section of the report.
DOSE to Public Due to Activities InSide the Site Boundary in accordance with ODCM Section 7.2, the Radioactive Effluent Release Report includes an assessment of radiation doses from radioactivity released in liquid and gaseous effluents to members of the public due to activities inside the site boundary. 92 ,
Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Repon In special instances, members of the public are permitted access to the Radiologically Restricted Area within the Davis-Besse Station. Tours for the public are conducted with the assurance that no individual will receive any appreciable dose due to radioactivity released in gaseous or liquid effluents (i.e., not more than a small fraction of the 40CFR190 standards.) The Visitor Center located inside the Davis-Besse Administration Building (DBAB)is also accessible to members of the public. Considering the frequency and duration of the visits, the resultant dose would be a small fraction of the calculated maximum site boundary dose. For purposes of assessing the dose to members of the public in accordance with ODCM Section 7.2, the following exposure assumptions are used:
- Exposure time for maximumally-exposed visitors is 20 hours (4 visits,5 hours per visit).
- Annual average meteorological dispersion (conservative, default use of maximum site boundary dispersion).
The equations in the ODCM may be used for calculating the potential dose to a member of the public for activities inside the site boundary. Based on these assumptions, this dose would be at least a factor of 400 less than the maximum site boundary air dose as calculated in the ODCM. There are no areas onsite accessible to the public where exposure to liquid effluents could occur. Therefore, the modeling of the ODCM conservatively estimates the maximum potential dose to members of the public. Inoperable Radioactive Effluent Monitoring Equipment The following radioactive effluent monitoring equipment required to be operable by ODCM Section 2.1 and 3.1 was inoperable for more than 30 days during this reporting period.
- The following radioactive effluent monitors were unavailable for more than thirty days due to modification (MOD 92-0046) which replaced the detector and Control Room readouts. The logarithmic meter readouts were replaced with digital readouts. l The detectors were replaced with new detectors. Affected monitors were- l RE 1770A Clean Waste Outlet !
RE 1770B Clean Waste Outlet l RE 1878A Radwaste Outlet RE 1878B Radwaste Outlet RE 1822A Radioactive Waste Gas Discharge RE 4686 Storm Sewer Outlet RE 8432 Service Water Outlet RE 8433 Collection Box To The Lake
- RE-4598AA/AB was inoperable due to flow measuring system failure. No replacement parts we.e available because the system is obsolete and is no longer i manufactured. A new flow system was ordered and will be installed.
93
c- 7 Davis-Besse Nuclear Power Station .1994 : AnnualRadiologicalEnvironmentalOpenting Report
- RE1003A was inoperable due to a change made in the flow system alarm logic
~ (FPR/MWo 1-94 0423-00). This change allows both RE1003A and RE1003B to be in-service at the same time. This increases the monitoring capabilities on the Steam Jet Air Ejector Exhaust. Previous, only one monitor could be in service at a time.
RE1003B was operable during this time period.
- Total Dilution Flow, Computer Point F-201, was unavailable for greater than 30 days due to F886, Backup Service Water Dilution Flow, which was reading high. Upon '
completion of maintenance activities, the computer point was returned to service. During the time period that F201 was inoperable, total dilution flow was estimated using other methods. Change to the ODCM and PCP There were no changes to the PCP and one revision (7) to the ODCM. Borated Water Storage Tank Radionuclide Concentration During this reporting period, the sum of the limiting fraction of radionuclides was exceeded in the BWST. This occurred during october 1994 after the refueling outage. The concentration in the tank was reduced to within the desired limit using demineralization. 94
DmisaceeNuclearIbarStaban 1994 AnnualRasolopcalEmimnmenalWagRqxwt Table 17 Gaseous Effluents - Summation of All Releases
- Type Unit 3rd Qtr 4th Qtr Est. Total 1994 1994 % Error Fission and Activation Gases Total Release Ci 2.22E+01 8.07E+01 2.50E+01 i Average Release Rate for Period' pCi/sec 2.79E+00 1.02E+01 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section Iodines Total Iodines Ci 8.34E-05 9.93E-04 2.50E+01 Average Release Rate for Period' pCi/sec 1.05E-05 1.25E-04 Percent of ODCM limits See Supplemental Information in ODCM Release Limits Section Particulates !
Particulates with half-lives greater than 8 days Ci 1.06E-06 2.52E-05 2.50E+01 Average Release Rate for Period
- pCi/sec 1.33E-07 3.17E-06 Percent of ODCM Limits See Supplemental Information in ODCM i Release Limit Section Gross Alpha Activity Ci 3.53E-07 5.89E-07 2.50E+01 ,
Tritium Total Release Ci 4.26E+00 1.01E%1 2.50E+01 , Average Release Rate for Period' pCi/sec 5.36E-01 1.27E40 ! Percent of ODCM Limits See Supplemental Information in ODCM ^ Release Limit Section r a The average release rate is taken over the entire quaner. It is NOT averaged over the time period of the releases. 95
r-DewBemeNudcarhrSumn 1994 AnnualFWEmisonmerdalOpenugRqxxt Table 18 Gaseous Emuents - Ground Level Releases' Batch Mode
- Nuclides Unit 3Qtr 1994 4Qtr 1994 ,
Fission Gases Ci Kr-85 LLD' LLD6 Kr-85m LLD LLD Kr-87 LLD - LLD , Kr-88 LLD LLD , Xc-133 LLD LLD Xel35 LLD LLD Xe-135m LLD LLD Xe-138 M LLQ Total for Period: N/A N/A lodines Ci I-131 LLD LLD I-133 LLD LLD , I-135 LLQ LLQ Total for Period: N/A N/A Particulates Ci 11-3 4.25E-03 7.74E-06 Sr-89 LLD LLD , Sr-90 LLD LLD Cs-134 LLD 2.46E-06 l Cs-137 LLD 1.56E-06 Ba-140 LLQ LLQ l Total for Period: 4.25E-03 1.18E-05 b c Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, AVV Testing, and Auxiliary Boiler Outage Release are listed as batch releases. 96 l
Dever,aameNudear AmarStanon 1994 AnnualPariminEPe=1EmironmentalOpciatmgReport Table 18 (Continued) I Gaseous Effluents - Ground Level Releases
- Continuous Mode' Nuclides Unit 3Qtr 1994 4Qtr 1994 Fission Gases Ci Kr-85 LLD 6 LLD' Kr-85m LLD LLD Kr-87 LLD LLD l Kr-88 LLD LLD Xe-133 LLD LLD Xe135 LLD LLD Xe-135m LLD LLD ,
Xe-138 LLD @ < Total for Period: N/A N/A ! Iodines Ci 1-131 LLD LLD I-133 LLD LLD ! I-135 LLD E Total for Period: N/A N/A Particulates Ci [ H-3 1.11E-06 8.56E-07 l Sr-89 LLD LLD ! Sr-90 LLD LLD Cs-134 LLD 2.04E-06 [ Cs-137 LLD 2.65E-06 Ba-140 LLQ LIR _i Total for Period: 1.1IE-06 5.55E-06 , i l d Atmospheric Vent Valve weepage and Steam Packing Exhaust are continuous releases. f
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DeusBesseNuclearPomsStahon 1994 AnnualF=Iv& T ralEmimnmentalWia-Reort Table 18 (Continued) Gaseous Effluents - Ground Level Releases' . Continuous Mode b These radionuclides were not identihed in concentrations above the lower limit of detection (LLD) listed below: i Xe-133: <4.6E-08 pCi/ml Kr-85: <6.2E-06 pCi/ml , Xe-133m: <l.6E-07 pCi/ml Kr-85m: <2.0E-08 pCi/ml Xe-135: <l.9E-08 pCi/mi Kr-87: <3.4E-08 pCi/ml Xe-138: <2.5E-07 pCi/mi 1-131: <l.0E-06 pCi/ml Cs-134: <2. lE-08 pCi/ml I133: <2.lE 08 pCi/ml I-135: <2. lE-08 pCi/ml Sr-89: <5.0E 08 pCi/ml - Sr-90: <6.0E-09 pCi/ml Kr-88: <4.0E-08 pCi/ml Cs-137: <3.0E-08 pCi/ml Xc-135m: <4.0E 07 pCi/ml Ba 140: <7.0E-08 pCi/ml Ar-41 <2.2E-08 pCi/ml l 98 i 1 I
osmaceeNudcarRwrSum 1994 AnnualWEm' u.MOperangRepmt o Table 19 Gaseous Effluents - Mixed Mode Releases
- Batch Mode NUCLIDES UNIT 3Qtr 1994 4Qtr 1994 Fission Gases Ci Ar-41 LLD6 2.14E-02 l
Kr-85 6.86E-01 8.62EM0 ( Kr-85m LLD 7.01E-04 , Kr-87 lid LLD' Kr-88 LLL' LLD Xe-131m 9.32E 02 1.15EMO Xe-133 5.12E-01 2.46E+01 Xe-133m LLD 1.29E-01 Xe-135 LLD 1.68E-01 Xe-135m LLD LLD Xe-138 LLQ LLR Total for Period: 1.29E+00 3.47E+01 Iodines 1-131 LLD 2.23E-06 I-132 LLD LLD I-133 LLD 3.08E-06 I-135 LLD LLE Total for Period: N/A 5.31E-06 Particulates H-3 3.67E-03 3.78E-01 Na-24 LLD LLD Co-58 LLD LLD l Co-60 LLD LLD 1 Ru-106 LLD LLD Cs-134 LLD 4.29E-07 Cs-137 LLD 1.17E-06 Ba-140 LLD LLD Total for Period: 3.67E-03 3.78E-01 f 99 l
Desis-DameNudearPoncrStahan 1994 AnnualRa&ologsalEmironnotalWaaReport Table 19 (Continued) Gaseous Effluents- Mixed Mode Releases C. itinuous Mode NUCLIDE UNIT 3Qtr 1994 4Qtr 1994 Fission Gases Ci Ar-41 LLD6 LLD6 Kr-85 LLD LLD Kr-85m LLD LLD Kr-87 LLD LLD Kr-88 LLD LLD Xe-131m LLD LLD Xe-133 2.10E+01 4.57E+0! Xe-133m LLD LLD Xe-135 LLD 3.08E-01 Xe-135m LLD LLD Xe-138 LLH LLD Total for Period: 2.10E401 4.60E401 Iodines I-131 3.90E-05 6.61E-04 I-132 LLD 5.84E-05 I-133 4.44E-05 2.69E-04 I-135 LLQ LLQ Total for Period: 8.34E-05 9.88E-04 Particulates H-3 4.25E+00 9.75E+00 Co-58 LLD 4.23E-07 Sr-89'd LLD LLD Sr-90'd LLD LLD Cs-134 LLD LLD Cs-137 1.06E-06 1.45E-05 Ba-140 LLQ LLD Total for Period: 4.25E400 9.75E+00 100
3 Dams &aseNudearPburSemon 1994 AnnualRadmiogimiEnvuonmentalOpeatagRgort ! Table 19 (Continued) . I Gaseous Effluents - Mixed-Mode Releases k a Abnormal releases included. , t i b These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed below. The largest LLD value is listed. Continuous Mode Batch Mode Kr-85 <3.3E-06 pCi/mi Kr-85m <2.2E4 pCi/ml Kr-85m <l.3E-08 pCi/mi Kr-87 <4.5E-06 pCi/ml. Kr-87 <6.0E-08 pCi/ml Kr-88 <6.6E-06 pCi/ml. Kr-88 <6.0E-08 pCi/mi Xe-133m <l.8E-05 pCi/ml. , Xe 131m <4.4E-07 pCi/mi Xel35m <l.4E-05 pCi/ml. , Xc-133m <7.2E-08 pCi/ml 1-135 <l.0E-05 pCi/ml. Ar-41 <2.9E-08 pCi/mi Co-60 <3.7E-06 pCi/ml. Xc-135m <$.9E-06 pCi/ml Ru-103 <2.8E-06 pCi/ml. y Xc-135 <l.lE-08 pCi/mi Ba-140 <l.lE-05 pCi/ml. , I-135 <3.9E-10 pCi/mi Cc-144 <l.4E-05 pCi/ml. , Mn-54 <2.6E-14 pCi/ml Mn-54 <9.5E 07 pCi/ml. > Co-58 <l.6E-14 pCi/mi Na-24 <9.8E-07 pCi/ml. Co-60 <2.5E-14 pCi/mi Co-58 <3.0E-06 pCi/ml. . Sr-89 <9.3E-16 pCi/ml 1-131 <2.7E-06 pCi/ml Sr-90 <3.lE-16 pCi/ml 1-132 <l.lE-06 pCi/ml ! Cs-134 <l.8E-14 pCi/ml 1-133 <3.0E-06 pCi/ml l Cc-144 <l.2E-13 pCi/ml Ru-106 <l.2E-05 pCi/ml ! Ba-140 . <8.4E-15 pCi/ml Cs-134 <2.8E 06 pCi/mi r Ru-103 <2.4E-14 pCi/ml Cs-137 <3.3E-06 pCi/ml. i Xc-138 <2.0E-05 pCi/ml Xe-135 <2.lE-06 pCi/ml. ; Xe-138 <2.8E-05 pCi/ml j 1 i l l c Quarterly composite sample for continuous mode. d Analysis not required for batch release. ; 1 l 101 l 1 i _ j l
om.aemeMs*nrPtwrsanon 1994. AnnumiRadidgpcalEnvuonmentOpenongRgort l j i l Table 20 ; Liquid Emuents - Summation.of All Releases i o Type. Unit 3Qtr 1994 4Qtr 1994 Est. Total :
% Error .
Fission and Activation Products i Total Release (without Tritium, Gases, Alpha) Ci 4.21E-03 1.54E-01 2.00E+01 Average Diluted Concentration during Period' pCi/ml 3.08E-08 6.94E-07 j l'ercent of ODCM Limit % See Supplement information in ODCM l Release Limits Section Percent of10CFR20 Limit % 6.07E-01 3.99E+00 Tritium Total Release Ci 1.61E+02 1.08E+02 2.00E401 j Average Diluted Concentration During Period' pCi/ml 1.31E-05 1.28E-05 l Percent of 10CFR20 Limit % 1.31E+00 1.28E+00 : Dissolved and Entrained Gases . Total Release Ci 1.20E+00 5.19E-02 2.00E+01 ! i Average Diluted Concentration During Period' pCi/ml 8.79E-06 2.34E-07 : t Percent of 10CFR20 Limit % 4.40E+00 1.17E-01 l Gross Alpha : Total Release Ci 8.90E-06 3.45E-05 2.00E+01 j Volume of Waste Released (prior to dilution) l Batch liter 5.17E+05 9.76E+05 2.00E+01- : Continuous liter 8.48E+07 9.92E+07 f Volume ofDiluted Water Batch liter 1.36E408 2.21E+08 2.00E+01 ] Continuous liter 1.21E+ 10 8.10E+09 i Total Volume of Water Released liter 1.23E+10 8.42E+09 2.00E+01 ! i i I a Tritium is found in both continuous and batch releases. Fission and Activation products : and Dissolved and Entrained Gases are only found in batch releases. j i l l 102
omiwkmemeiearn=rScean 1994 AnnualPWEmbreOpranngRgxrt Table 21 Liquid Effluents - Nuclides Released . Batch Releases
- NUCLIDES UNIT 3QTR 1994 4QTR 1994 Fission and Activation Products Na-24 Ci LLD6 1.80E-05 ;
Cr-51 LLD 3.34E-03 Mn-54 LLD 2.05E-04 Fe-55 9.06E-04 1.08E-02 Fe-59 LLD 4.85E-04 Co-57 7.31E-06 3.37E-04 Co-58 7.80E-05 1.12E-01 Co-60 6.04E-04 8.34E-03 , Zn-65 LLD 1.41 E-05 Sr-89'd LLD LLD 6 Sr-90'd LDD LLD Nb-95 LLD 1.43E-03 Nb-97 6.30E-06 LLD Zr-95 LLD 7.63E-04 Zr-97 3.48E-05 8.50E-05 Mo-99 LLD 1.45E-04 Tc-99m 4.I1E-07 1.77E-04 Ru-103 LLD 3.21E-04 Ru-106 LLD 6.96E-04 Ag-110m 8.67E-04 2.22E-03 . Sn-113 2.16E-06 4.83 E-04 Sb-124 LLD 1.08E-03 Sb-125 7.85E-04 6.13E-03
~~
1-131 LLD 2.79E-04 I-132 LLD 5.63E-04 Te-132 LLD 4.90E-04 Cs-134 2.90E-04 9.44E-04 - Cs-137 6.24 E-04 2.12E-03 i e 103 . 1
i DesirraemeNudcarPtwrStahan 1994 AnnualRadologicalEmironmentalOpeutg3R@ ort Table 21 (continued) Liquid Effluents - Nuclides Released Batch Releases
- NUCLIDES UNIT 3QTR 1994 4QTR 1994 Fission and Activation Products Ce-144 5.85E-06 2.02E-04 La-140 LLD6 1.35E-04 Ba-140 LLD 1.53E-05 NP-239 LLD 1.53E-05 Total for Period: 4.21E-03 1.54E-01 Tritium Ci 1.60E+02 1.07E+02 !
Dissolved and Entrained Gases Kr-85 Ci 1.05E-02 8.08E-03 Xe-131m 1.14E-02 2.45E-03 Xe-133 1.17E+00 4.12E-02 Xel33m 6.84E-03 6.75E-05 Xe-135 2.77E-05 6.23E-05 Total for Period: 1.20E+00 5.19E-02 t I 104 ,
DmisaeseNudcarPtwrSunon 1994 AmalRabokgcalEmb uOpenengRgxxt Table 21 (continued) Liquid Effluents - Nuclides Released Continuous Releases
- NUCLIDES UNIT 3QTR 1994 4QTR 1994 Fission and Activation Products Cr-51 Ci LLD 6 LLD6 Mn-54 LLD LLD Fe-59 LLD LLD Co-58 LLD LLD Co-60 LLD LLD Zn-65 LLD LLD ,
Sr-89" LLD LLD Sr-90" LLD LLD Nb-95 LLD LLD Zr-95 LLD LLD Mo-99 LLD LLD , Tc-99m LLD LLD I-131 LLD LLD Cs-134 LLD LLD Cs-137 LLD LLD Ba-140 LLD LLD Ce-141 LLQ LLQ Total for Period: N/A N/A Tritium Ci 7.96E-01 5.29E-01 Dissolved and Entrained Gases Kr-85 Ci LLD LLD , Xe-131m LLD LLD Xe-133 LLD LLD Xel33m LLD LLD Xe-135 LLD LLQ Total for Period: N/A N/A 105 I
m r DavisHesseNudearI%crStanon 1994 AnnualRasologualEmtunnonalOpcratingReport Table 21 (continued) Liquid Effluents - Nuclides Released b These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed below. The largest LLD value is used for each radionuclide. Na-24 . <2.0E-08 pCi/ml Sn-113 <2.8E-08 pCi/mi Cr-51 <l 7E-07 pCi/ml Sb-124 <l 7E-08 pCi/ml - Mn-54 <2.lE-08 pCi/ml Sb-125 <l.7E-08 pCi/ml Fe-55 <7.0E-07 pCi/ml Te-132 <l.8E-08 pCi/ml r Fe-59 <4.2E 08 pCi/ml Cc-141 <3.0E-08 pCi/ml ! Co-57 <l.6E-08 pCi/ml- Cc-144 <l.7E-07 pCi/ml Co-58 <l.9E-08 pCi/ml Cs-134 <2.1E-08 pCi/ml Co-60 <2.5E-03 pCi/mi Cc-136 <2.8E-08 pCi/ml Zn45 <5.2E-08 pCi/ml Cs-137 <2.7E-08 pCi/ml h Se-75 <2.4E 08 pCi/mi Cs-138 <6.7E-08 pCi/ml : Sr-89 <3.0E-08 pCi/ml Ba-140 <7.0E-08 pCi/ml Sr 90 <8.0E-09 pCi/ml Np-239 <l.2E-07 pCi/ml Zr-95 <4.0E-08 pCi/mi I-131 <2.5E-08 pCi/ml Zr-97 <2.5E-08 pCi/ml 1-132 <2.2E-08 pCi/ml Nb-95 <2.lE-08 pCi/ml 1133 <2.lE-08 pCi/ml Nb-97 <2.5E-08 pCi/mi Kr-85 <6.2E-06 pCi/ml Mo-99 <l.6E-07 pCi/ml Xe-131m <7.7E-07 pCi/ml Tc-99m <l.8E-08 pCi/ml Xe-133 <4.6E-08 pCi/ml Ru-103 <2.2E-08 pCi/ml Xc-133m <l.6E-07 pCi/ml l Ru-106 <2.lE-07 pCi/mi Xe-135 <l.9E-08 pCi/ml Ag-l10m <2.5E-08 pCi/ml I a Quarterly composite sample c There were no abnormal liquid releases during the reporting period. d LLDs are applicable to both batch and continous modes due to identical sample and analysis l methods. i i l : I 1 l L i . l 106 j l
WMxkarRm:rStanon 1994 AnnelPWEnvuonmmtalMRqat Table 22 Solid Waste and Irradiated Fuel Shipments Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) Type of Waste Unit Quantity Est. Total
% Error Spent resins, filter sludges, evaporator bottoms, etc. m' O.00E+00 0.00E+00 Ci 0.00E+00 0.00E@0 Dry compressible waste, contaminated equipment, etc. m' O.00E+00 0.00E+00 Ci 0.00E+00 0.00E+00 Irradiated components, control rods, etc. m' O.00E%0 0.00E+00 .
Ci 0.00E+00 0.00E+00 Others: Dewatered Primary Syrtem m' O.00E+00 0.00E+00 Cartridge Filters Ci 0.00E+00 0.00E+00 Estimate of Major Nuclide Composition (by type of waste) None There were no shipments ofirradiated fuel. . Note: As ofJuly 1,1994, a disposal facility was no longer available for solid radioactive waste ; generated in Ohio. All solid radioactive waste, after processing, will be placed in temporary storage until a disposal facility is available.
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Desee=c NudearI%crStahmt 1994 AmalRadrkgicalEmine.mmsalWagRepmt TABLE 23 FOR JULY-DECEMBER 1994 DOSES DUE TO GASEOUS RELEASES ; i l Maximum Individual doses due to I-131, H-3 and Particulates with Half-Lives Greater j than 8 Days. Whole Body Dose 1.22E-03 mrem j f Significant Organ Dose 4.49E-03 mrem I Maximum Individual Dose Due to Noble Gas Whole Body Dose 1.51E-03 mrad Skin Dose 6.72E-03 mrad l Population Doses due to I-131,11-3, and Particulates with IIalf-Lives Greater than 8 Days. I TotalIntegrated Population Dose 3.06E-03 persen-rem Average Dose to Individual in Population 1.61E-06 mrem ; Population Dose due to Noble Gas ; i TotalIntegrated Population Dose 2.24E-03 person-rem t Average Dose to Individual in Population 1.18E-06 mrem 1 i 108
omisasseNu&arhSueon 19% AmalRWEm-MCpxsingRest t TABLE 24 l FOR JULY-DECEMBER 1994 , t DOSES DUE TO LIQUID RELEASES
. t Maximum Individual Whole Body Dose 6.81E-02 mrem .
Maximum Individual Significant Organ Dose 8.87E-02 mrem l Population Dose TotalIntegrated Population Dose 1.55E+00 person- rem Average Dose to Individual 8.16E-04 mrem t i i P 109
1 Dmw& menu &arPtwrSwxm 1994 AnnualPWEnvl=-dOpentmgRgxst i Table 25 Annual Dose to The Most Exposed Member of The Public i
- j. ANNUAL DOSE 40CFR190 PERCENT (mrem) LIMIT (mrem) OF LIMIT Whole Body Dose Noble Gas 1.51E-03 Iodine, Tritium, Particulates 1.22E-03 j.
i Liquid 6.81 E-02 Total Whole Bodyl>ose 7.08E-02 25 2.83E-01 Thyroid Dose Iodine, Tritium, Particulates 4.95E-02 75 6.60E-02 Skin Dose Noble Gas 6.72E-03 25 2.69E-02 Significant Organ Dose (Liver) Liquid 8.87E-02 25 3.55E-01 4 Meteorological Data Meteorological data on 31/2 inch microdisk for July 1,1994 through December 31,1994 has been submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washingtoa, D. C. 20555. I10
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'l 1 , s Land Use Census !_ 1
Davis-Desse Nuclear Power Station 1994 Annual Radiological Environmental Opvating Report I Land Use Census ! Program Design Each year a Land Use Census is conducted by Davis-Besse in order to update information l necessary to estimate radiation dose to the general public and to determine if any modifications are necessary to the Radiological Environmental Monitoring Program. The Land Use Census is 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 the various pathways by which radioactive ' material may reach the general population around Davis-Besse. The information gathered during the Land Use Census for dose assessment and input into the REMP ensure these i programs are as current as possible. The pathways of concern are listed below:
. Inhalation Pathway- Internal exposure as a result of breathing radionuclides carried in the air.
- Ground Exposure Pathway- External exposure from radionuclides deposited ou 1 the ground !
- Plume Exposure Pathway- External exposure directly from a plume or cloud of rad;aactive material.
Vegetation Pathway- Internal exposure as a result of eating vegetables, fruit, etc. ! which have a build up of deposited radioactive material or which have absorbed radionuclides through the soil. Milk Pathway Internal exposure as a result of drinking milk which may contain radioactive material as a result of a cow or goat grazing on a pasture contaminated by radionuclides. Methodology The Land Use Census consists of recording and mapping the locations of all residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) within a five , mile radius of Davis-Besse. The surveillance portion of the 1994 Land Use Census was performed during the month of July. In order to gather as much information as possible, the locations of residences, dairy cows, dairy goats, vegetable gardens, beef cattle, fowl, fruit trees, grapes, sheep, and swine were recorded. Ilowever, only the residences, vegetable gardens, and milk animals are used in the dose 111
- Davis-Besse Nuclear Power Stilon 1994 Annual Radiological Environmental Operating Report assessment program. The vegetable gardens must be at least 500 square feet in size, with at least 20% of the vegetables being green leafy plants (such as lettuce, cabbage, and kale) yielding 2 kg/m2 ,
Each residence is tabulated as being an inhalation pathway, as well as ground and plume exposure pathways. Each garden is tabulated as a vegetation pathway. All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 l minute series of the relevant quadrangles) which has been divided into 16 equal sectors , corresponding to the 16 cardinal compass points (Figure 30). The closest residence, milk animal, and vegetable garden in each sector are determined by measuring the distance from each to the station vent at Davis-Besse.
- RcSultS :
1 1 ! The following changes in the pathways were recorded in the 1994 census:
. S Sector -The garden at 1440 meters was replaced by a garden at 3280 meters.
- SW Sector - The garden at 1050 meters was replaced by a garden at 4150 meters.
- WSW Sector - The garden at 1620 meters was replaced by a garden at 4270 meters.
. W Sector -The vegetation pahway at 1060 meters was deleted in favor of a site at 1660 meters. The goat milk pathway at 6550 meters was deleted.
- NW Sector - The garden at 2660 meters was replaced by a garden, the new vegetation pathway site is at 2340 meters.
. NNW Sector - The garden at 1990 meters was replaced by a garden at 1370 meters.
The critical receptor identified by the 1994 Land Use Census is a child for the vegetation pathway at 1660 meters in the W sector. This is a change from the 1993 Land Use Census. The detailed list in Table 26 was used to update the database of the effluent dispersion model used in dose calculations. Table 26 is divided by sectors and lists the distance (in meters) of the closest pathway in each meteorological sector. ; Table 27 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and deposition (D/0) parameters for each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and ' in calculating liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. s l l 112 i
DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PRIMARY PATHWAYS WITHIN 5 MILE RADIUS
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Davis-Besse Nuclear Power Station 1994 . Annual Radiologal Environmentc10pescing Report Table 26 : Closest Exposure Pathways PreSent in 1994 Sedor Distanceimm Station (meters) Cosest Pathways N 880 Inhalation Grand Ex1mure Plume Exposure i NNE 870 Inhalation Ground Exposure Plume Exposure NE 900 Inhalation Ground Exposure Plume Exposure t ENE, E, ESE, SE N/A located over Lake Erie SSE 2010 Inhalation . Ground Exposure i Plume Exposure SSE 2880 Vegetation i S 1070 Inhalation Ground Exposure Plume Exposure S" 3280 Vegetation SSW 980 Inhalation Ground Exposure ; Plume Exposure ; SSW 1560 Vegetatim ; 114
p Davis-Besse Nuclear Power Station 1994 Annual Radiological Environmental Operating Report l Table 26 : Closest Exposure Pathways Present in 1994 (continued) Sedor Distanw from Station (meters) Casest Pathways SW 1050 Inhalation : Ground Exposure Plume Exposure , SW*
- 4150 Vegetation WSW** 1620 Inhalation ;
Ground Exposure Plume Exposure WSW** 4270 Vegetation , W 980 Inhalation Ground Exposure Plume Exposure W" 1660 Vegetation WNW 1730 Inhalation Ground Exposure Plume Exposure , WNW 1750 Vegetation : NW 1100 Inhalation Ground Exposure Plume Exposure NW*
- 2340 Vegetation i
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Davb-Besse Nuclear Power Station 1994 Annual Radiological Environment 10perating Report . Table 26 : Closest Exposure Pathways Present in 1994 - ! (continued): Secor Distance from Station (meters) Casest Pathways i NNW 1210 Inhalation i Ground Exposure } Plume Exposure NNW*
- 1370 Vegetation i l
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- Changes since 1993 l
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Davis-Hesse Nucicar Power Station 1994 Annual Radiological Environmental Operc3ing Report ; Table 27: Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters SECTOR METERS CRITICAL AGE XO DO 2 PA'IliWAY GROUP (SEQM*) (hf ) am INHALATION GEID 9.15EM 8A0E G N 8A) INHALATION GEID 1.27D06 1A7Em NNE 900 INiiAIATION GELD 126EG 158EG NE _ ENE* - E* - - ESE* - SE* - 28m VEGETA110N Oi!LD 6B5Em 8mslo SSE 32m VEGETATION OULD 437EM 4.98 &l0 S" SSW 1560 VEGEFA110N OilLD ImEM 2.28E6 OilID 4B8E M 5.13510 SW" 4150 VEGETAT10N 430 VEGETAT10N OffLD 5.71FX18 531510 WSW*
- QUID 243E M 4.11EM W" 1660 VEGETATION VEGEFA110N OillD 1A6EM 1.72E&
WNW 1750 NW" 2M) VEGETATION GELD 634Em 541510 VEGETATION GELD 2DIEG 1A8EG NNW" 137)
- Since these sectors are kated over marsh areas and Lake Eric, no ingestion pathways are present.
" Changes since 1993.
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Dmis4ksseNuclearPourStaban 1994 AnnualPWkpal Erwin=- t QweingRqort Meteorological Monitoring Introduction The Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nuclear power stations on the surrounding environment. Both NRC regulations and Davis-Besse Technical Specifications provide guidelines for the Meteorological Monitoring Program. These guidelines ensure that Davis-Besse has the proper equipment, in good working order, to support the many programs utilizing meteorological data. Meteorological observations at Davis-Besse began in October 1968. The Meteorological Monitoring Program at Davis-Besse has an extensive record of data with which to perform climatological studies which are used to determine whether Davis-Besse has had any impact upon the local climate. After extensive statistical comparative research the meteorological personnel have found no impact upon local climate or short term weather patterns. The Meteorological Monitoring Program also provides data that can be used by many other groups and programs: Radiological Environmental Monitoring Program, The Emergency Preparedness Program, The Environmental Activities Program, and groups such as Plant Operations, Plant Security, Materials Management, Industrial Safety Program, Toledo and Cleveland Service Dispatch, Legal Affairs, plant personnel and members of the surrounding community. The Radiological Environmental Monitoring Program uses meteorological data to evaluate the biological effects of radioactivity released in Station effluents. The meteorological data is used to evaluate radiological environmental monitoring sites, to monitor severe weather conditions, and to predict the development of adverse weather trends, such as flooding or high winds. The Emergency Preparedness Program uses meteorological data to calculate emergency dose scenarios for emergency drills and exercises and uses weather data to plan evacuations or station isolation during adverse weather. The Environmental Activities Program uses meteorological data for chemical spill response activities, marsh management studies, and waste water outfall flow calculations. Plant Operations uses meteorological data for cooling tower efficiency calculations, forebay water level availability and plant work which needs certain environmental conditions to be met before work begins, such as humidity percentages and barometric pressures for sensitive plant components. Plant Security utilizes weather data in their routine 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. Service Dispatch in both Toledo and Cleveland utilize Davis-Besse weather satellite imagery for planning and scheduling maintenance crews to restore power to customers more efficiently.
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.I Deve BaseNederPbewSesoon 19M Annual Radiolopcal Envimamental Opsanng Report J-legal Affairs uses climatological data for their investigation into adverse westher accidents to ,i the plant and personnel; and company employees and members of the surrounding' community rely on daily weather forecasts provided by meteorological personnel at Davis-Besse to better - l plan their daily and routine work activities. !
On-Site Meteorological Monitoring
System Description
At Davis-Besse there are two meteorological systems, a primary and a backup. They are both j housed in separate environmentally controlled buildings with independent power supplies. Both j primary and backup systems have been analyzed to be " statistically identical" to the other so if one ; system fails the other can take its place. The instrumentation of each system follows: i PRIMARY BACKUP l 100 Meter Wind Speed 100 Meter Wind Speed i 75 Meter Wind Speed 75 Meter Wind Speed .l' 10 Meter Wind Speed 10 Meter Wind Speed-l 100 Meter Wind Direction 100 Meter Wind Direction' 75 Meter Wind Direction 75 Meter Wind Direction : 10 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 100 Meter Delta Temperature i 75 Meter Delta Temperature 75 Meter Delta Temperature ; 10 Meter Ambient Temperature 10 Meter Ambient Temperature - l 10 Meter Dew Faint 10 Meter Solar Insolation j Precipitation Barometric Pressure ; l Meteorological Instrumentation The meteorological system consists of one monitoring site located at an elevation of 577 feet i above mean sea level (IGLD 1955)*. A 100 m free-standing tower located about 3,000 feet SSW of the cooling tower, and an auxiliary 10 m foot tower located 100 feet west of the 100 m tower, are used to gather the meteorological data. The 100 m tower has primary and backup- : instruments for wind speed and wind direction at 100 m and 75 m. The 100 m tower also
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j measures differential temperature (delta Ts): 100-10 m and 75-10 m. The 10 m tower has j instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket i f rain gauge located near the base of the 10 m tower. According to the Davis-Besse Nuclear Power Station operating License, Appendix A, Technical i International Great Lakes Data - 1955 i
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119 , l
Dmis-Besse NuclearPour Stauon 1994 Annual P*%d Emironmental Opraung Rgxxt Specification, a minimum of six instruments are required to be operable at the two lower levels (75 m and 10 m) to measure temperature, wind speed, and wind direction. During 1994, annual data recovery for all required instruments were 99.1 percent. The annual data recovery for all other measured parameters was 98.89 percent. Minor losses of data occurred during routine instrument maintenance, calibration, and data validation. Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly. Data is reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required. Tower instrumentation maintenance and semiannual calibrations are performed by in-house facilities and an outside consulting firm. These instruments are wind tunnel tested to assure compliance with applicable regulations and plant specifications. Meteorological Data Handling and Reduction Each meteorological system, primary and backup, have two Campbell Scientific Dataloggers (model 21XL) assigned to them. The primary system has a first datalogger to communicate 900 second averages to the control room via a Digital 11/84 and VAX computer system. This is a dedicated line. If a failure occurs at any point between the primary meteorological system and the control room the second data logger in the primary shelter can be utilized by the control room. Each datclogger has its own dedicated communication link with battery backup. The backup meteorological system is designed the same as the primary; so to lose all meteorological data the primary and backup meteorological systems would have to lose all four dataloggers. However, this would be diflicult since each is powered by a different power supply and equipped with lightning and surge protection, plus four independent communication lines and datalogger battery backup. The data frorn the primary and backup meteorological systems are stored in a 30-day circular storage module with permanent storage held by the Digital VAX computer. Data goes back to 1988 in this format and to 1968 in both digital and hardcopy formats. All data points are scnrinized every 900 seconds by meteorological statistics programs running continuously. These are then reviewed by meteorological personnel daily for validity based on actual weather conditions. A monthly review is performed using 21 NRC computer codes which statistically analyze all data points for their availability and validity. If questionable data on the primary system can't be corroborated by the backup system, the data in question is climinated and not incorporated into the final data base which dose calculations and quarterly / annual batch release calculations are performed. All validated data is then documented and stored on hard copy and in digital format for a permanent record of meteorological conditions. Joint Frequency Distributions and Wind Sector Graphics Summary statistics and Joint Frequency Distributions (JFDs) of wind and stability data are generated and the results are reviewed for consistency in terms of known site characteristic and regional climate. The end result of the review process is a validated final database suitable for use by atmospheric dispersion models and for site meteorological characterizations. Wind - 120
Davis-DesscNuclearPomStaban 1994 AnnualPMM EmL-uiOperaungEqxxt Sector Graphics represent the frequency of wind direction by sector and the wind speed in MPH by sector. This data is used by the NRC to better understand local wind patterns as they relate to defined past climatological wind patterns as reported in Davis-Besse's " Updated Safety Analysis Report." Meteorological Data Summaries This section presents summaries of the meteorological data collected from the on-site monitoring program at Davis-Desse during 1994. Tables 28 through 30, discussed in this section, can be ' found on pages 124 through 143. Wind Speed and Wind Direction The maximum wind speeds for 1994 were 48.79 mph for the 100m level on November 28,46.76 mph for the 75m level on November 28, and 36.61 mph for the 10m level on November 28. Figures 31-33 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 b .. 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 Pasquill Stabilities. Calms (less than or equal to 1.0 mph) are shown in perced in the middle of the wind sector graphic. Ambient and Differential Temperatures hionthly average, minimum and maximum ambient temperatures for 1994 are given in Table 29. These data are measured at the 10m level; with differential temperatures taken from 100m and 75m levels. The yearly average ambient temperature for 1994 was 50.297. The maximum temperature was 93.0T on June 15 with the minimum temperature of-18.0T on January 19. Yearly average differential temperatures were -0.09T(100m), and -0.04T(75m). hiaximum differential temperatures for 100m and 75m levels were 8.00T on February 18 (100m), and 8.007 on hiay 14 (75m). hiinimum differential temperatures for 100m and 75m levels were -5.70T on August 17 (100m) and -3.76T on hiay 26 (75m). Differential temperatures are a measurement of atmospheric stability are used to calculate radioactive plume dispersions based on the Gaussian Plume hiodels of continuous efiluent releases. Dew Point Temperatures and Relative Humidity hionthly average and extreme dew point and humidity temperatures for 1994 are provided in Table 29. These data are measured at the 10 meter level. The average dew point temperature was 41.29T with a maximum dew point temperature of 95.877 on September 25. Pl ase note that dew point temperatures above 757 are highly suspect and are possibly due to u m winds and high solar heating allowing the aspirated temperature processor to retain heat. The minimum dew point (dew point under 32T is frost point) temperature was -17.907 on January 19. Average : 121 !
Dmis&sseNudcarPtmer Staban 1994 Anrael P MW EmironncLi Openmng Report relative humidity is 74.01 for the year. The maximum relative humidity was 100.00 percent on December 31. The minimum relative humidity was 0.00 percent on October 17. 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. Precipitation i Monthly totals and extremes of precipitation at Davis-Besse for 1994 are given in Table 29. Total precipitation for the year was 28.45 inches. The maximum monthly precipitation total was 4.72 inches in June. The minimum was 0.57 inches recorded in September. It is likely that precipitation totals recorded in colder months are somewhat less than actual due to periods of freezing precipitation and strong winds blowing across the gauge. , Lake Breeze and Lake Level Monitoring Lake Breeze is monitored at Davis-Besse because ofits potential to cause major atmospheric / dispersion problems during an utdely radioactive release. A lake breeze event occurs during the daytime, usually during the summer, where the land surface heats up faster than the water, and therefore reaches higher temperatures than the water. The warmer air above the land rises faster because it is less dense than the cooler air over the lake. This leads to rising air currents over the land with descending denser air over the lake. This starts a wind circulation which draws air from the water to the land during the daytime, creating a " lake breeze" effect. This event could be problematic if a release were to occur because diffusion would be slow thus creating an adverse atmosphere to the surrounding site. Lake and forebay levels are monitored at Davis-Besse to observe, evaluate, predict and disseminate 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 j fluctuation to occur within an eight to ten hour period. High water levels also effect the plant due to emergency transportation and evacuation pathways. Satellite Imagery A state-of-the-art satellite weather system was installed in 1994. This system consists of a remote one-meter satellite dish, a host computer receiver which has four remote user connections, with a real-time weather access. The weather satellite is 22,000 miles out in space, with a geosyncronous orbit situated over North America. Data from the satellite is fed to WSI corporation for base map interpretation and then sent to a communication satellite which then sends the completed imagery to the receiving satellite dish at Toledo Edison. Data from this site . 122
i Dasi+BesseNuclear Pbuct Stauon 1994 Annual Raiolopcal Embonnaital Operating Report can then be sent to all four remote users; two users in the Toledo area and two in Cleveland. This advanced weather station allows meteorological staff to forecast adverse weather conditions long before they arrive. This enables planners in Service Dispatch to keep needed crews available if adverse weather conditons dictate; or to send home uneeded crews if a projected storm tracks out of the customer service area. Load Dispatch utilizes the weather system to get an idea where the peak and low electricity loads will be either during very hot days or very cold ones. High winds, solar flares, freeze lines, wind chill, min-max temperatures and graphic imagery can all be obtained digitally through this weather satellite system, allowing better planning by staff and better service to customers; saving time and money as well. 123
Table 28 Summary of Meteorological Data Recovery For The Davis-Besse Nuclear Power Station January 1,1994 through December 31,1994 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1994 100M Wind Speed 100 100 100 95.28 100 100 100 100 9236 95.83 100 99.6 98.6 g 100m Wind Direction 100 100 100 100 100 100 100 100 92.36 95.83 100 99.6 98.98. it - 75m Wind Speed 75m Wind Direction 100 100 100 100 100 95.28 100 100 100 100 100 100 100 100 100 9236 95.83 100 9236 95.83
'100 99.6 100- 99.6 98.98 98.6 f
10m Wind Speed 100 100 100 100 100 100 100 100 90 . 95.83 100 99.6 98.79
- 10m Wind Direction 100 100 100 100 100 100 100 100 92.36 95.83 100 99.6 98.98 g E 10m Ambient AirTemp 100 100 100 100 100 100 100 100 9736 95.83 100 99.19 9936 g, l
10m Dew Point Temp 100 100 100 100 93.82 100 100 100 97.92 95.83 100 92.88 9834 Delta T(100m-10m) 100 100 100 100 100 100 100 100 9736 95.83 100 .99.46 9938 Delta T (75m-10m) 100 100 100 100 100. 100 100 100 97.36 95.83 100 99.6 9939 Joint 100m winds and Delta T (100m-10m) 100 100 100 95.28 100 100 100 100 90 -95.83 100 99.46 9839 Joint 75m winds and ~ Delta T(100m-10m) 100 100- 100 95.28 100 100 100 100 90 95.83 100 99.46 98.39 du Joint 10m winds and Delta T (75m-10) 100 100 100 .95.28 100 100 100 100 90- 95.83 100 99.46 9839 f
*all data for individual months expressed as percent of time instrument was operable during the month, divided by the maximum number of hours in that month that the instrument could be operable. Values for annual data recoveries = percent of time instrument was operaable during the' year, divided by the number of hours in the year that the instrument was operable.
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Table 29 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station p January 1,1994 through December 31,1994 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1994 100M WIND 27.7 30.34 26.43 30.39 48.79 32.93 48.79 f Max Speed (mph) 39.25 47.89 33.9 40.88 41.45 38.85 Date of Max Speed 28 23 16 16 11 13 9 13 28 31 28 1' 11/28 , Vin Speed (mph) 1.6 1.8 1.66 2.35 1.7 1.9 2.4 0.67 2.96 1.46 1.63 1.42 0.67 j Date of Min Speed 7 27 30 1 22 18 18 30 30 30 19 5 8/30 y Ave Wind Speed 19.07 18.99 17.28 20.17 15.65 13.62 12.84 13.22 14.34 15.53 20.98 14.21 16.29 75M WIND , Max Speed (mph) 37.71 44.46 32.04 38.18 39.29 36.79 26.61 28.12 25.26 28.36 46.76 31.46 46.76' i Date of Max Speed 28 23 24 16 11 13 9 28 28 23 28 7 11/28 i Min Speed (mph) 1.8 1.56 1.97 2.64 1.61 1.58 1.5 1.56 2.25 1.41 2.1 1.53 1.41 E.
- Date of Min Speed 7 27 28 20 .20 11 18 30 26 30 19 22 10/30 l Ave Wind Speed 17.83 17.64 15.92 18.47 14.62 12.56 11.72 12.09 13.07 14.1 19.1 13.16 15.01 [
10M WIND Max Speed (mph) 29.58 28.97- 25.2 29.34 29.7 27.26 19.83 21.28 18.9 23.64 36.61 25.13 36.61 ,g Date of Max Speed 28 23 24 16 11 13 9 28 28 31 28 7 11/28 Min Speed (mph) 1.62 1.4 1.43 1.43 1.8 0.64 1.12 1.35 1.06 0.9 1.35 1.09 0.64 Date of Min Speed 7 7 7 8 20 11 18 11 15 30 20 15 6/11 Ave Wind Speed 12.84 11.22 10.39 12.61 10.02 8.18 7.34 7.37 7.8 ~ 8.51 12.42 8.46 9.77-t .
Table 29(continued) Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1,1994 through December 31,1994 h{- N JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1994 10M AMBIENTTEMP Max (F) Date of Max 40.73 27 60.2 71.33 83.97 83.57 19 23 26 31 93 91.77 86.07 86.57 77.23 67.15 59.63 15 20 25 15 7 13 3 93 6/15 f_ Min (F) -18.01 -0.55 18.43 29.48 35.44 52.76 59.24 53.11 45.61 36.64 23.74 20.15 -18.01 $ g Date of Min 19 1 3 7 2 2 11 15 30 26 24 13 1/19 g
- Ave Temp 17.79 24.7 36.34 50.77 57.79 70.35 73.41 69.28 64.98 54.65 46.51 35.88 50.29 5.
10M DEW POINTTEMP Mean (F) 15.42 19.34 28.53 37.35 44.8 59.4 64.03 60.86 51.31 43.15 37.78 31.84 41.29 g Max (F) 42.47 50.67 55.23 61.8 64.86 74.6 75.17 74.13 95.87 61.18 58.74 52.58 95.87 f Date of Max 12 20 24 27 15 18 5 13 25 19 4 5 9/25 [ Min (F) -17.9 19.34 5.9 17.4 25.52 33.5 52.11 41.69 3.5 0 12.% 15.48 -17.9 [- Date of Min 19 1 16 7 9 2 10 5 24 17 22 30 1/19 d PRECIPITATION Total (inches) 1.83 1.14 2.02 3.81 1.42 4.72 1.38 3.82 0.57 1.78 2.1 3.86 28.45 Max. in One Day 0.42 0.41 0.79 0.78 0.55 0.94 0.53 1.58 0.24 0.77 0.75 0.83 1.58 Date 27 23 6 11 25 23 21 20 30 5 8 6 8/20
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M DMmeMMC m s DAVIS-BESSE DAVIS-BESSE ' NOVEMBER 1994 DECEMBER 1994 10M LEVEL 10M LEVEL , 138
Table 30 Joint Frequency Distribution by Stability Class
*** * *** DATIS-BESSE ENY1AONMENTAL COMPLIARCE UNIT *** * **12-JAN-95 TIME OF Daft 09:17:55 PB00 RAM JFD VERStoNt F7?-1.0
******** DAVIS-BESSE 15-10 DT, NO BACEUP ******** SITE IDENTIFIER: 94 12/ 31/ 94 DATA PERIOD EIAMINED: 1/ 1/ 94 -
i *** ANNUAL *** STABILITY CLASS A STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED ATI 35.0 FEET ** WIND THRESNOLD AT: 1.00 MPH - JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN ROURS AT 35.00 FEET SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL (MPN) w L4 0 CALM + MD 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01- 3.49 1 0 0 0 0 0 0 0 1 0 0 0 5 0 12 h.50- 7.49 3 2 45 7.50-12.49 2 0 0 0 0 0 0 0 0 1 1 2 1 21 16 1 0 0 0 0 3 2 1 2 0 8 12.50-18.49 0' 0 0 0 0, 0 0 0 22 0 -0 0 0 0 0 0 0 0 0 0 3 4 3 18.50-24.49 3
>24.49 0 0 0 0 0 0 0 1 0 0 0 0- 0 0 2 0 2 0 0 0 0 0 0 1 2 5 6 30 33 1 49 TOTAL a 2 1 STABILITY CLASS S STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED DT 35.0 FEET WIND THRESNOLD STt 1.00 MPH JOINT FREQUENCY EISTRIBUTION OF WIND SPEED AND DIRECTICN IN NOURS AT 35.00 FEET j SPEED (MPN) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 f 0 0 0 0 0 0 0 0 (9 i 1.01- 3.49 0 0 0 0 0 0 0 0 0 3.50- 7.49 2 0 1 0 0 0 0 0 0 0 0 1 1 1 5 4 15 0 0 1 2 2 4 7 3' 27 7.50-12.49 4 1 0 0 3 0 0 0 7 7 7 0 28 12.50-18.49 1 1 1 0 0 0 0 0 0 0 1 3 0 0 'O O 0. 0 0 0 0 0 0 3 5 4 1 15 18.50-24.49 2 0
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 324.49 9- 0 0 0 0 0 0 2 10 9- 17 23 8 85 l TOTAL 2 2- 3 I a
~ , _ . - _ . . _ _ _ , . . . _ . . , - , . - . - - . . ~ , _ . . _ . _ _ _ _ - , - . . - . . _ - - - _ - - . . . . - _ . _ _ - - . ~ . . _ . _ __. _.. _ _ _ __________a
Table 30 (Continued) Joint Frequency Distribution by Stability Class
*** * *** DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT *** * **12-JAN-95 TIME OF DAY: 09:17:55 PROGRAM JFD VERSION: F77-1.0
******** DAVIS-BESSE 75-10 DT, NO BACEUP ******** SITE IDENTIFIER: 94 DATA PERIOD EXAMINED: 1/ 1/ 94 - 12/ 31/ 94
*** ANNUAL ***
STABILITY CLASS C STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET - WIND MEASURED ATt 35.0 FEET ** WIND THRESHOLD ATt 1.00 MPN JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S $$W SW WSW .. W WNW NW NNW TOTAL w.* Sh CAIM 0 CD 1.01- 3.49 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1 0 2 3.50- 7.49 1 6 2 0 1 0 0 1 4 2 2 0 3 4 3 5 34 7.50-12.49 9 5 5 16 14 3 0 0 0 4 8 13 15 8 15 14 129 12.50-18.49 2 2 5 3 1 0 0 0 0 5 7 13 4 12 3 5 62 18.50-24.49 0 0 0 0 0' O O 0 0 2 1 6 10 2 3 1 25
>24.49 0 0 0 0 0 0 0 0 0 0 0 5 0 0 0 0 5 ,
TOTAL 12 13 12 20 16 3 0 1 4 13 18 37 32 26 25 25 257 STABILITY CLASS D STABILITY BASED ON: DELTA T- BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESHOLD ATt 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET ' SPEED , (MPH) N NNE NE . ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0 CALM 70 (pa 1.01- 3.49 4 4 1 4 6 8 3 4 6 7 5 4 3 2 6 3 3.50- 7.49 46 34 12 87 115 93 46 35 41 19 84 32 15 12 18 39 848 7.50-12.49 81 83 174 240 156 El 21 19 26 156 200 171 67 59 74 99 1687 12.50-18.49 41 90 145 73 53 22 4 13 6 58 152 180 65 38 11' 81 1992 18.50-24.49 15 40 43 39 5 0 0 0 0 3 87 ' 99 19 17 23 14 404
>24.49 5 9 2- 10- 0 0 0 0 0 0 22 32 6 1 6 0 93 TOTAL 192 260 431 453 335 184 14 71 79 303 530 518 175 129 198 236 4194 i ,
__m__-____._____.-.m __ .--m..,. . . .w m4-. r.- . -- ~,--m--~ , , . . u re2._m.n,-, , ,.-c.e- .re- iv._y _ , - _%- ...,.-..._2 ,.rw..,
1 Table 30 (Continued) Joint Frequency Distribution by Stability Class
*** * *** DAVIS-BESSE ENVIRONMENTAL COMPLI A. .'1 UNIT *** * **12-JAN-95 i
TIME OF DAYt 09:17:55 PROGRAM: JFD YERSION: F77-1.0
******** DAVIS-BESSE 75-10 DT, NO BACKUP ******** SITE IDENTIFIER: 94 ~
DATA PERIOD EX AMINED: 1/ 1/ 94 - 12/ - 31/ 94
*** ANNUAL ***
STABILITY CLASS E ! STABILITY BASED ON: DELTA T BF"l WEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND THRESNOLD AT: 1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN NOURS AT 15.00 FEET 4 SPEED (MPN) N NNE NE ENE E ESE SE SSE S S$w SW WSW W WNW NW NNW - TOTAL Sh i
** CALM 1.01- 3.49 2 4 5 9 10 20 24 32 36 34 20 9 12 5 6 3 231 3.50- 7.49 14 30 24 55 54 87 110 80 139 243 110 83 55 - 31 28 17 1160 7.50-12.49 16 19 22 29 67 38 23 21 45 257 226 130 64 39 44 19 1059 12.50-18.49 5 10 12 17 7, 4 3 9 9 49- 85 59 15 15 17 7 323 18.50-24.49 0 1 7 4 1 0 0 2 4 5 30 17 0 1. 0 0 72 0 0 0 0 0 1 0 0 3 1 1 0 0 0 7 124.49 0 1 TOTAL 37 64 71 114 139 149 160 145 231 588 474 299 147 91 95 46 2453 ,
2 STABILITY CLASS F STABILITY BASED ONt DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 F E E'? WIND THRESROLD AT: 1.00 MPR JOINT FREQUENCT DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPN) N' NNE NE ENE E ESE SE SSE S SSW SW WSW W- WNW NW NNW TOTAL 1 CALM 0 0 2 0 2 7 11 36 58 27 23 14 15 7 3 5 210 1.01- 3.49 581 3.50- 7.49 2 2 1 9 8 33 31 56 100 146 94 45 41 8 5- 0 7.50-12.49 0 2 10 4 6 6 3 6 ?" 24 18 17 12 8 0 0 132 0 0 0 2 0 0 0 0 5 3 0- 0 0 0 11 12.50-18.49 1 . 0 18.50-24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0. 0 0 0 0 0 0 0 1 0 0 0 0 0- 1
>24.49 0 0 0 TOTAL 2 4 14 13 18 46 45 98 174 197 141 19 68 13 4 5 436 1
I b r-., , - --.~r ,- -,m.--4,,-...,-,rw-e., , , - - - - - - - , - ,,- e-. . - - , . .-.r---- -- ., .,~r ,- m., w cw . . - . , v...m.,- --%, .
Table 30 (Continued) Joint Frequency Distribution by Stability Class
*** * *** DAVIS-BESSE ENVIRONMENTAL COMPLIARCE UNIT *** * **12-JAN-95
, TIME OF DAT: 09:17:55 PROGRAM: JFD TERSION: F77-1.0
******** DAVIS-BESSE 75-10 DT, NO BACEUP ******** SITE IDENTIFIER: 94 DATA PERIOD REAMINED: 1/, 1/ 94 - 12/ 31/ 94
*** ANNUAL ***
STABILITY CLASS G STABILITT BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET 5 WIND MEASURED AT: 35.0 FEET WIND THRESMOLD AT: 1.00 MPM == JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET { SPEED (MPM) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WWW NW NNW TOTAL w SE CALM e bJ 1.01- 3.49 0 1 0 2 0 1 4 10 16 22 22 8 2 1 1 0 90 3.50- 7.49 1 0 2 2 6 12 7 9 14 35 20 8 8 3- 0 1 128 7.50-12.49 0 0 0 0 5 5 0 5 0 0 4 1 1 0 0 0 21 12.50-18.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.50-24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
>24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 1. 2 4 11 18 11 24 30 57 46 17 11 4 1 1 239 STABILITY BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET STABILITY CLASS ALL f' a
WIND MEASURED AT: WIND THRESROLD AT: 35.0 FEET 1.00 MPM ly, JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN NOURS AT 35.00 FEET B SPEED (MPa) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CA LM 2 1.01- 3.49 6 9 8 16 18 36 42 82 118 90 70 - 35 32 15 17 11 603 3.50- 7.49 69 74 103 153 184 225 194 181 298 50,5 311 169 123 59 64 66 2778 7.50-12.49 112 110 211 289 251 113 47 51 87 442 458 336 162 139 156 136 3100 12.50-18.49 49 103 164 93 63 26 7 22 15 112 250 265 89 73 100 93 1524 18.50-24.49 20 41 50 43 6 0 0 2 4 10 118 122 35 33 38 16 538 324.49 5 9 3 10 0 0 0 1 0 0 26 38 7 1 8 0 108 TOTAL 261 346 539 604 522 400 290 339 520 1159 1233 965 448 320 343 322 8653 5 e __ _. _ ___._---.. __m., . _ _ _ _ - . . . . _ . , - . . . . . ~ . , , . . _ . . . _ - - . . . - . - --- ,. . , - - . , . . - . . _ - . _ - ~ - , . , , . -. . , , - - - .., _ _ . . _ , - . . . . , . - - , . - - - _ - .
Table 30 (Continued) Joint Frequency Distribution by Stability Class
*** * *** DATIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT *** * **12-JAN-95 TIME OF Daft 09:17:55 PROGRAM: JFD TERSION: F77-1.0
******** DAVIS-BESSE 75-10 DT. No BACEUF ******** SITE IDENTIFIER 2 94 '
DATA PERIOD EEAMINED: 1/ 1/ 94 - 12/ 31/ 94
*** ANNUAL ***
STABILITT BASED ON: DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT: 35.0 FEET WIND TNRESNOLD ATt 1.00 MPN 2 TOTAL NUMBER OF OBSERVATIONS: 8760 TOTAL NUMBER OF TALID OBSERYATIONS: 8653 . TOTAL NUMBER QT' MISSING OBSERVATIONS: 107 PERCENT DATA kECOVERT FOR TNIS PERIOD: 98.8 % MEAN WIND SPEED FOR TNIS PERIODt 9.8 MPH TOTAL NUMBER OF OBSERVATIONS WITN BACEUP DATA 0 { t.e4 PERCENTAGE OCCURRENCE OF STABILITT CLASSES A B C D E F G 1.03 0,98 , 2.97 48.47 32.97 10.82 2.76 DISTRIBUTION OF WIND DIRECTION TS STABILITT @ , N NNE NE ENE E ESE SE $$E S SSW SW WSW W WNW NW NNW CALM 9, i A 8 2 1 0 0 0 0 0 0 1 2 5 -6 30 33 1 0 8 9 2 2 0 J 0 0 0 0 0 2. 10 9 17 23 8 0 C 12 13 12 20 16 3 0 1 4 13 18 37 32 26 25 25 0 D 192 260 437 453 335 184 74 11 19 303 550 518 175 129 198 236 0 ag E 37 64 11 114 139 149 160 145 233 588 474 299 147 91 95 46 1 , e F 2 4 14 13 18 46 45 98 174 197 141 79 68 23 8 5 1 N G 1 1 2 4 11 18 11 24 30 57 46 17 11 4 1 1 0 '! TOTAL 261 346 539 604 522 400 290 339 520 1159 1233 965 448 320 383 322 2 d. s
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em , t,-w v +-~s, c g-,--y y gy. .ys.-i--, .g ,-
~~~ w w a n n . a~- w Marsh Management l
l Navarre Marsh l Navarre Marsh, which is part of the Ottawa National Wildlife Refuge, is located on 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 l 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 control and to encourage beach formation. Revetments are built with a gradual slope which causes waves to dissipate their energy when they strike the revetment. This encourages beach formation through passive deposition of sediment. A dike is a retaining structure designed to hold back water for the purpose of flood control and to aid in managing wetland habitat. When used as a marsh management tool, dikes aid in controlling water levels in order to obtain desired vegetation and animal species. Manipulating water levels is one of the most important marsh management tools used in Navarre Marsh. Three may>r types of wetland communities exist in Navarre Marsh, the freshwater marsh, swamp forest, and wet meadow. Also, there exists a narrow dry beach ridge along the lake front with a sand bar extending out into Lake Erie. All these areas provide essential food, shelter, and nesting habitat as well as a resting area for migratory birus. Davis-Besse personnel combine their efforts with a number of conservation agencies and organizations, including The Ottawa National Wildlife Refuge, The Ohio Department of National Resources (ODNR), and the Black Swamp Bird Observatory to preserve and enhence existing habitat, to gain knowledge through ongoning research, and to help educate the public about the importance of native wetlands. Being located along a 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 ever, a pair of mature American Bald Eagles have chosen the Navarre Marsh as their nesting site. The pair began building their nest in October and were nearly finished in early December, in time for the 1995 breeding season. , 144 i
t i i Desaesse Nudcarlimer9*=i 1994 Annual RW Envuonmersal Operatmg Rgort Goose banding took place in June, and was conducted in cooperation with the ODNR. i Davis-Besse also hosted a Volunteer Eagle Watches Workshop and a Waterfowl Identification Seminar, both of which were sponsored by the ODNR, and contributed to a reward fund when , an eagle was shot in Erie County in April. l t Toledo Edison is committed to protecting the Navarre Marsh and has gone to great lengths to l preserve this valuable resource. ; r h i [ h i i f i I
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om m m m m - w g m ee->em.... maogc n.go,i ; Water Treatment j Water Treatment Plant Operation Description i 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. , Operation of the water treatment plant is monitored by the Ohio Environmental Protection Agency (OEPA) and the Ohio Department of Health. The operation of the facility is reviewed by a Public Water Supply certified operator. Activities at the water treatment plant ' . are conducted in compliance with the Safe Drinking Water Act and the regulations for public water supply as set forth by the OEPA. Monthly operational reports, required by the OEPA, are completed by Toledo Edison personnel and submitied 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 compliance 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 certain organic chemicals. The health and ; safety of the water treatment plant operators and other site personnel is ensured through l weekly housekeeping inspections of the facility. Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens ! which remove debris and large particles. The water is then pumped to chlorine detention tanks. Next the water passes through one of two clarifiers. Davis-Besse uses upflow clarifiers, or precipitators, to remove sediment, organic debris, and dissolved agents from the raw water prior to filtration. Clarifiers combine the conventional treatment steps of coagulation, flocculation, and sedimentation into a single unit. Coagulation is the process by which a chemical, called a coagulant, is added, causing the small particles in the water to adhere to each other and form larger particles. During flocculation, the water is gently circulated, allowing these conglomerate particles to mass together further. Finally, during sedimentation, large conglomerate particles ; settle to the bottom of the clarifier. These processes normally require large separate tanks. Ilowever, the use of clarifiers saves both space and the manpower needed to operate the ; treatment plant. l l
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l
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146
DaviSBesseNucicarPom:r Station 19St Annual Rad ological Emironnwel Operating Report MAW WATM HTAKE smucTtnt rtow ~
~e WG AUTOMATIC wATtn cetonal vAtvarss DCTomOn 7
ctAninEns - CLEARWELL mcATuon \ - nLTEnS REED PUMPS TAtMS ctEAnwEtt TRAtG UI PUMPS TO DOMESTIC TO NAE WATEA (DntNKitG) WATER SYSTEM SYSTEM TO DEMINERAll2ED WATm SYSTDA Figure 37 : At Davis-Besse, raw water is drawn into the water treatment plant and processed to make drinking water and water for plant systems. After the clarifier, the water goes through a flow-splitting box which equally divides the water flow to the Automatic Valveless Gravity Filters (AVGF).These AVGFs consist of a 50:50 ratio of anthracite to filter sand. During this filtration process, suspended matter is removed from the water by the anthracite and sand media. This filtering reduces the turbidity and odor and improves 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 fire water, demineralized water, and also drinking water. Zebra Mussel Control Introduction The plant receives all ofits water from an intake system from Lake Erie. Zebra mussels can severely 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 1988 and was discovered in Lake Erie in 1989. Zebra mussels are prolific breeders which rapidly colonize an area by secreting byssal threads which enable them to attach to solid surfaces and to each other. Because of their ability to attach in this manner, they may form layers several inches deep. This poses a problem to facilities that rely on water intakes from Lake Erie because mussels may attach to the intake structures and restrict water flow. Zebra mussels have not yet caused any significant problems at Davis-Besse, but mussels have been found attached to the intake crib (the structure that 147
. Davisacsse NudcarPtmerStahan 1994 AnnualPN EmLunesa OperahngRgxxt 1 allows water to be pulled in from the lake) and the first section of the intake conduit (the pipe that connects the crib to the intake canal). ) Monitoring l l The Zebra Mussel Monitoring Program has been in place since April,1990. The program involves the collection of several types of samples which are observed for the presence of adult zebra mussels or the free-swimming larval forms, veligers. The frequency of sampling is i determined by lake water temperature. Samples are taken when the lake temperature is above 12 C since this is the temperature above which spawning may occur. At temperatures above 18'C, spawning conditions are most favorable, and more frequent samples are taken. Weather data and water temperatures are also recorded to determine their effects on veliger/ mussel population. Water samples are collected in the station's intake forebay. These samples are collected using a plankton net sampler: a net support system with a straining bucket used for plankton-size (microscopic) organisms including veligers. One milliliter from each sample is observed under a microscope to check for the presence of veligers to determine the average number of veligers per liter. In August of 1994 the intake system was inspected by divers and no problems were identified with respect to zebra mussel infestation. The mussel population appears to be levelling off or declining. This is likely due to the increasing clarity of Lake Erie. As the food source for the zebra mussels decline, decreasing populations of mussels result. Wastewater Treatment Plant Operation The wastewater treatment plant (WWTP) operation is supervised by a state Certified Waste-water 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. The wastewater is then pumped into the aeration tanks. Here, organic materials are digested by microorganisms which are provided with a source of oxygen. This is accomplished through the use of blowers. The mixture of organics, microorganisms, and decomposed wastes is called activated sludge. The treated wastewater settles in a clarifier, and the clear liquid passes over a weir, leaving the plant by an efiluent 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 efiluent leaving the plant is disinfected with chlorine and is pumped to the wastewater treatment basin (NPDES Outfall 601) where further treatment takes place. 148
DaisecsseNudcarPourStanon 1994 AnnualP r*-Sr.:EnGumcdid OperaungReport Summary of 1994 Wastewater Treatment Plant Operations Wastewater Treatment Plant (WWTP) Number 2 was taken out of service from April through September 1994. During this time, needed repairs were made to the plant, such as painting and rewiring. With WWTP Number 2 back in service, plans are to make repairs to WWTP Number 1 in the near future. 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. Rese limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 21B00011
- ED.
Parameters such as chlorine, suspended solids and pH are monitored under the NPDES permit. Toledo Edir,on personnel 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: Outfall 001 Collection Box: At a point representative of discharge to Lake Erie. Source of Wastes: Irw volume wastes (Outfalls 601 and 602), circulation system blow down and occasional service water (sample collected at Davis-Besse Beach Sampling Station). Outfall 002 Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water runoff, circulating pump house sumps (sample collected at discharge of Training Center Pond). 1 Outfall 003 Screenwash Catch Basin: Outfall to Navarre Marsh. Source Of Wastes: Wash debris from water intake screens (sample collected at overflow of screenwash basin). Outfall 601 l 149
DavisacacNudcarPtmcrStanon 19 % AnnualP=iM EmironmcotalWagReport Wastewater Plant Tertiary Treatment Basin: Discharge from wastewater treatment system. Sources Of Wastes: Wastewater Treatment Facility. Outfall 602 Low volume wastes: Discharge from settling basins. Sources of wastes: Water treatment residues, condensate polishing resins (sample collected i at overflow of number 2 basin), and condensate pit sumps. ; Sampling Point 801 Intake Temperature: Intake water prior to cooling operation (temperature taken at the east end of the intake forebay). l t 1994 NPDES Summary - During 1994, there were two permit noncompliance incidents and one unauthorized ; discharge. The first noncompliance incident occurred in February, when the pH at Outfall 001 reached 9.09 Standard Units (3.U.), exceeding the permit limit of 9.00 S.U.; the second noncompliance incident occured in December, when the free available chlorine duration ' limit of two hours was exceeded at Outfall 001 due to operational error in valving. The unauthorized discharge occurred in October, when hydrazine was discharged through Outfall ; i 001 during a scheduled plant maintenance and tefueling outage. i 1 l 150 i
l DmirrDesseNuckarIbm:rStaban 19M Annual Radiobgical Emironmmtal Operaung Report Chemical Waste Management ) Introduction The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes generated at the Davis-Besse Nuclear Power Station was developed to ensure wastes are managed and disposed of in accordance with all applicable state and federal regulations. Waste Management Resource Conservation and Recovery Act The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid 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.
- Small quantity Generators - A facility which genemtes less than 1000 kilograms / month (2200lbshnonth).
- Conditionally Exempt Small Quantity Generators - A facility which generates 100 kilograms / month (220lbs/ month)
In 1994, the Davis-Besse Nuclear Power Station generated 700 gallons of hazanlous wastes. Additionally, approximately 18,000 gallons of rainwater containing small amounts of gasoline from a minor on-site gasoline spill were disposed of as regulated waste.%e bulk gasoline was immediately recovered, the leak repaired and insitu bioremediation of the gasoline contaminated soil is in progress. Here were 4,500 gallons of non-hazardous waste oil generated in 1994. RCRA also mandates other requirements such as the use of pmper 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. He following are completed 151
DavisBesse hicarPom Stauon 19M Anal RMW Environmcrual Operaung Rgxxt as part of the hazardous waste management program to ensure compliance with the RCRA regulations.
- Inspections Chemical Waste Accumulation Areas are designated throughout the site to ensure proper handling and disposal of chemical waste. Dese, 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 waming 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 accumulation 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.
- 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 per million of halogens and has a flash point above 140 F is considered to be nonhazardous waste.
Emergency Response Planning Comprehensive Environmental Response, Compensation, and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, sometimes referred to as Superfund) established a federal authority and source of funding for responding to spills and other releases of hazardous materials, pollutants, and contaminants into the environment. Superfund establishes " reportable quantities" for several hundred hazardous materials, and regulates the cleanup of abandoned hazardous waste disposal sites. Superfund Amendment and Reauthorization Act (SARA) Superfund was amended in October,1986, to establish new reporting programs dealing with emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enhanced by ensuring that the potential for release of hazardous substances is minimized and adequate and timely responses are made to protect surrounding populations. Davis-Besse conducts site-wide inspections to identify and record all hazardous products and chemicals onsite as required by SARA. Determint us were made as to which products and chemicals were present in sufficient quantities to report. Annual SARA reports are submitted to local fire departments, and local and state planning commissions by March I for the preceding calendar year. No additional chemical products were identified for calendar year 1994. 152
Davis-DesseNucicarIbwerStauan 1994 Annual P A*W Environmcotal Operaung Rgxxt Spill Kits Fifty-five gallon drums containing protective equipment and spill control equipment are maintained throughout the Station at chemical storage areas and at appropriate hazardous chemical and oil use points. Equipment in the kits includes such items as chemical resistant coveralls, gloves, absorbent cloth, goggles, and warning signs. Other Regulating Acts Toxic Substances Control Act (TSCA) The Toxic Substance Control Act (TSCA) was enacted to provide the USEPA with the authority to require testing of new chemical substances for potential health effects before they are introduced into the environment, and to regulate them where necessary. This law would have little impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management system, very similar to the hazardous waste management system established under RCRA. In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers onsite. PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with non-PCB liquid. Retrofilling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with PCB-leaching solvents and allowing the solvent to circulate in the transformer during operation. The entire retrofill process takes several years and will extract almost all of the PCB. In all, Davis Besse retrofilled eleven PCB transformers, the majority being completed and reclassified non-PCB in 1991. The eleventh PCB transformer was declared non-PCB in early I 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors. These capacitors are being replaced and disposed of during scheduled j maintenance activities. In 1994, about 30 kilograms of PCBs were disposed of. < Clean Air Act l The Clean Air Act identifies substances which are considered air pollutants. Davis-Besse l holds an OEPA permit to operate an Air Contaminant Source for the station auxiliary boiler. l This boiler is used to heat the station and provide steam to plant systems when ths ceactor is not operating. A report detailing auxiliary boiler operation is submitted annually. Applications for Permits to Operate an Air Pollution Source were submitted to the Ohio EPA l for our six emergency diesel engines, including the Station Blackout Diesel Generator, the 2 l Emergency Diesel Generators, the Emergency Response Facility Diesel, the Miscellaneous 153 I
Daireesse Nucicarher Staban 1994 Annual Radd@ Emironnental Operaung Rgxst 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 asbestos removal from renovation and demolition projects for which USEPA has outlined specific regulations conceming handling, removal, environmental protection, and disposal. Also the Occupational Safety and Health Protection Administration (OSIIA) 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 off site, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations, including verification that the vehicle has appropriate placards and it is in good 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 one 8,000 gallon diesel fuel storage tank and one 2,000 gallon waste oil tank are regulated as USTs. 154
m m - wn w w - m m 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, otherwise known as Ohio House Bill 592. This legislation divides Ohio's 88 counties into 48 Solid Waste Management Districts. Each Solid Waste Management District is responsible for reducing MSW by 25% by 1994. 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." Statewide, it is prohibited to place the following items in a landfill: Lead acid batteries Yard and lawn waste Whole tires or shredded tires Davis-Besse and Centerior Energy have implemented several programs which emphasize the reduce, reuse, recycle approach to MSW management. Improved efficiency in collection and hauling, resulted in a two year reduction of approximately 71 % for disposal cost MSW. Additionally, joint partnership agreements with yard waste composters have been developed . for yard and lawn waste recycling. Other programs include paper and cardboard recycling. A total of 140,007 pounds of paper was recycled in 1994. Also,34,883 pounds of corrugated cardboard have been collected that would have otherwise been placed in a landfill. Aluminum soft drink cans are collected on site for the Boy Scouts to recycle.12ad-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 of MSW stream are targeted for reduction. t 155
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1 1 4 i i l I l 4 i ! i t t i Appendices i 1 4 l il i l l i I I 4 1 i i 1 i l , .I ' i J r I i i f 5
_. __. . - _ ._ _ . . .-.. -._ __ ._ ._ _~ .._ . _ - _ - . - _ - . i 1 1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report
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i I t i i I APPENDIX A Interlaboratory Comparison Program Results i 1 I 4 l [ t 4 ; e t e
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. . - ~ . . . -_ _ . . _ - -. . . - - - - - . - 1994 Davis-Besse Nuclear Power Stauon Annual Ra6olopcal Environmental Operating Report y I Teledyne Brown Engineering Environmental Services Midwest Laboratory (formerly Teledyne Isotopes and Hazleton Environmental Sciences) has participated in interlaboratory comparison i (crosscheck) programs since the formulation of its quality control program in December 1971. These l programs are operated by agencies which supply environmental-type samples (e.g., milk or water) - l
, containing concentrations of radionuclides known to the issuing agency but not to the Participant
. laboratories. The purpose of such a program is to provide an independent check on the laboratory's j analytical procedures and to alert it to any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the ; issuing agency. Several months later, the agency reports the known values to the participant l laboratories and specifies control limits. Results consistently higher or lower than the known values ! or outside the control limits indicate a need to check the instruments or procedures used. l The results in Table A-1 were obtained through participation in the environmental sample crosscheck t program for milk,' water, air filters, and food samples during the period January through December i 1994. This program has been conducted by the U.S. Environmental Protection Agency. l
' Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and l Support Laboratory, Las Vegas, Nevada. j f
The results in Table A-2 were obtained for thermoluminescent dosimeters (TLDs) during the : International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table l A-2. Also Teledyne testing results are listed. ; i Table A-3 lists results of the analyses on in-house spiked samples. ; Table A-4 lists results of the analyses on in-house " blank" samples. { Table A-5 lists results of the analyses on in house " duplicate" samples. Attachment A lists acceptance criteria for " spiked" samples. f i e
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1994 Davis-Besse Nuclear Power Station Aar.ual Radsological Erwironmental Operating Report I Attachaient A: Acceptamec Criteda For " Spiked " Samples Laboratory Prweision: One Standaril Deviaties Values for Vadous Analyses * , e One Standard Deviation . Analysis Level For Single Deteruslaation l 1 Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter l
>100 pCi/ liter or kg 5% of known value '
Strontium-89 2 to 30 pCi/ liter or kg 5.0 pCi/ liter
>50 pCi/ liter or kg 10% of known value ,
Strontium-90' 2 to 30 pCl/ liter of kg 5.0 pCl/ liter l
>30 pCi/ liter or kg 10% of known value -r Potassium >0.1 g/ liter or kg 5% of known value Gross alpha < 20 pCi/ lier 5.0 pCI/ liter
>20 pCi/ liter 25% of known value i
Gross beta <100 pCi/ liter 5.0pCi/ liter
>100pCi/ liter 5%of known value Tritium <4,000pCi/ liter Is = (pCi/ liter) = i 169.85 X (known)*"
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 j lodine-131, <55pCi/ liter 6.0 pCi/ liter i Iodine-129 >55pCi/ liter 10% of known value ; Uranium-238, <35 pCi/ liter 6.0 pCi/ liter ! Nickel-64' >35 pCi/ liter 15% of known value 6 Tecimetium-99 l Iron-55' 50 to 100.pCi/ liter 10pCi/ liter
>100pCi/ liter 10% of known value Others' - 20% of known value a From EPA publication, Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982 EPA &O/4 81004.
b _ Tcledynelimit. l 9 f 158
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l 1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report i I Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's ' Midwest Laboratory results for various sample media'. Concentration in pCi/1? 3 Lab Sample Date Tcledyne Results EPA Result d Control ; Code Type Collected Analysis 12 Sigma' Is, N=1 Limits { STW-702 WATER Jan,1994 St-89 20.011.7 25.0i5.0- 16.3 - 33.7 ; STW-702 WATER -Jan,1934 Sr-90 14.011.0 15.0i5.0 6.3 - 23.7 STW-703 WATER Jan,1994 Gr. Alpha 20.310.6 15.0 i 5.0 6.3 - 23.7 STW-703 WATER Jan,1994 Gr. Beta 55.3 i 3.2 62.0110.0 44.7 - 79.3- > STW-704 WATER Feb,1994 I-131 110.0 i 2.7 119.0 1 12.0 98.2 - 139.8 STW-705 WATER Feb,1994 Ra-226 19.4 i 1.5 19.9 i 3.0 14.7 - 25.1 STW-705 WATER Feb,1994 Ra-228 15.010.8 14.713.7' 8.3 - 21.1 STW-705 WATER Feb,1994 Uranium 9.710.4 10.l i 3.0 4.9 - 15.3 l STW-706 WATER Mar,1994 H-3 4,843.31 231.2 4,936.0 1 494.0 4,078.9 - 5,793.1 STW-707 WATER Mar,1994 Pu-239 28.210.9 27.6 i 2.8 22.7 - 32.5 STW-708 WATER Apr,1994 Gr. Alpha 73.312.9 86.0 i 22.0 47.8 - 124.2 STW-708 WATER Apr,1994 Ra-226 16.9 1.2 20.0 i 3.0 14.8 - 25.2 i STW-708 WATER- Apr,1994 Ra-228 19.7 i 0.7 20.115.0 11.4 - 28.8 STW-708 WATER Apr,1994 Uranium 25.110.1 25.0 i 3.0 19.8 - 30.2 STW-709 WATER Apr,1994 Co-60 20.310.6 20.0 i 5.0 11.3 - 28.7 STW-709 WATER Apr,1994 Cs-134 32.310.6 34.015.0 25.3 - 42.7 STW-709 WATER Apr,1994 Cs-137 31.3 i 0.6 29.015.0 20.3 - 37.7 STW-709 WATER . Apr,1994 Gr. Beta 101.0 1 10.5 117.0 i 18.0 85.8 - 148.2 STW-709 WATER Apr,1994 Sr-89 15.011.7 20.015.0 11.3 - 28.7 STW-709 WATER Apr,1994 Sr-90 14.310.6 14.015.0 5.3 - 22.7 STW-710 WATER Jun,1994 Ba-133 87.310.6 98.0110.0 80.7 - 115.3 ; STW-710 WATER Jun,1994 Co-60 48.7i 3.2 50.0 i 5.0 41.3 - 58.7 t STW-710 WATER Jun,1994 Cs-134 35.012.7 40.015.0 31.3 - 48.7 , STW-710 WATER Jun,1994 Cs-137 51.310.6 49.015.0 40.3 57.7 STW-710 WATER Jun,1994 Ru-106 184.716.7 252.0 i 25.0 208.6 - 295.4 l A letter from the EPA was received with the report. It states,"The Radiation Quality Assurance Program ; has been experiencing problems with the Ruthenium-106 currently used in the Performance Evaluation (PE) , t Studies and in the Standards Distribution Program. If these problems can be satisfactorily resolved, this ~ analyte will once again be placed into this PE Study. If the problems cannot be resolved, the Ruthenium-106 l will be replaced. Formal written notice will be given to all participants in the Gamma in Water PE Study J before the Ruthenium-106 is reintroduced or replaced. At that time, new calibration standards will be [ available to all participants in the Gamma in Water PE Study." Teledyne will continue to monitor this > situation, but at this time, plans to take no additional action. l STW-710 WATER Jun,1994 Zn-65 135.312.3 134.0 1 13.0 111.4 - 156.6- l STW-711 WATER Jun,1994 Ra-226 15.010.4 15.012.3 11.0 19.0 } STW-711 WATER Jun,1994 Ra-228 14.810.3 15.4 i 3.9 8.6 - 22.2 , STW-711 WATER Jun,1994 Uranium 45.7i 0.2 52.615.3 43.4 - 61.8 j STW-712 WATER Jul,1994 Sr-89 26.011.7 30.0 i 5.0 21.3 - 38.7 - j h 159
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^ 1994 Davis-Besse Nuclear Pour Station Annual Radiological Environmental Operating Report i Table A 1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media *. l Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result d Control l Code Type Collected Analysis 12 Sigma
- 1s, N=1 Limits l STW-712 WATER Jul,1994 Sr-90 18.7 i 0.6 20.015.0 11.3 - 28.7-STW-713 WATER Jul,1994 Gr. Alpha 19.3 i 1.2 32.0 i 8.0 18.1 - 45.9 i STW-713 WATER Jul,1994 Gr. Beta 12.711.5 10.0 5.0 1.3 - 18.7 STW-714 WATER Aug,1994 H-3 10,186.71 66.6 9,951.0 1 995.0 8,224.7 - 11,677.3 STAF-715 AlR FILTER Aug,1994' Cs-137 14.010.0 15.0 i 5.0 6.3 - 23.7 ,
STAF-715 AIR FILTER Aug,1994 Gr. Alpha 29.311.2 35.0 i 9.0 19.4 - 50.6 STAF-715 AlR F1LTER Aug,1994 Gr. Beta 56.010.0 56.0 i 10.0 38.7 - 73.3 ' E STAF-715 AIR FILTER Aug,1994 Sr-90 18.0 i l.0 20.015.0 11.3 - 28.7 STW-716 WATER Sep,1994 Ra-226 10.1 i 0.3 10.0 i 1.5 7.4 - 12.6 STW-716 WATER Sep,1994 Ra-228 9.8 i 0.1 10.212.6 5.6 - 14.7 STW-716 WATER Sep,1994 Uranium 31.9 i 1.8 35.0 i 3.0 29.8 - 40.2 STW-718 WATER Oct,1994 I131 81.3 i 3.1 79.018.0 65.1 - 92.9
- Results obtained by Teledyne's Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Uranch, Environmental l' Monitoring and Support Laboratory, U.S. Environmental Protection Agency (EPA), Las Vegas, Nevada.
6 All results are in pCi/ liter, except for elemental potassium (K) data in milk, which are in mg/ liter; air filter i samples, which are in pCi/ filter; and food products, which are in mg/ kilogram. l
' Unless otherwise indicated, the Teledyne results are given as the mean i 2 standard deviations for three determinations. :
d U.S. EPA results are presented as the known values and expected laboratory precision (1s,1 determination) f and control limits are defined by the EPA. f 3 l i
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1994 Davis-Besse Nuc! car Pour Station Annual Radiological Emironmental Operating Report Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) 2nd International Intercomparison 115-2 CaF,: Mn Bulb Apr,1976 Field 17.011.9 17.1 16.4 i 7.7 115-2 CaF,: Mn Bulb Apr,1976 Lab 20.8 i 4.1 21.3 18.817.6 Second InternationalIntercomparison of Environmental Dosimeters conducted in April of 1976 by the liealth and Safety Laboratory (HASL), New York, new York, and the School of Public flealth of the University of Texas, llouston, Texas. 3rd International..Intercomparison 115-3 CaF,: Mn Bulb Jun,1977 Field 30.713.2 34.914.8 31.513.0 115-3 CaF,: Mn Bulb Jun,1977 Lab 89.6 i 6.4 91.7114.6 86.2124.0 Third International Intercomparison of Environmental Dosimeters conducted in the summer of 1977 by Oak Ridge National 1.aboratory and the School of Public Health of the University of Texas, Houston, Texas. 11ILiniernaticnaUntercenmarit on 115-4 CaF,: Mn Bulb Jun,1979 Fieid 14.1 i 1.1 14.111.4 16.019.0 115-4 CaF2 : Mn Bulb Jun,1979 Lab, High 40.4 i 1.4 45.819.2 43.9113.2 115-4 CaF2 : Mn Bulb Jun,1979 Lab, Low 9.811.3 12.212.4 12.017.4 Fourth Intemational Intercomparison of Environmental Dosimeters conducted in the summer of 1979 by the School of Public 1lealth of the University of Texas, liouston, Texas. 5th International Inter.colnparison 115-5A CaF,: Mn Bulb Oct,1980 Field 31.411.8 30.016.0 30.2114.6 115-5A CaF,: Mn Bulb Oct,1980 lab, End 96.6 i 5.8 88.4 i 8.8 90.7 i 31.2 115-5A CaF,: Mn Bulb Oct,1980 Lab, Start 77.415.8 75.2 i 7.6 75.8 i 40.4 Fif th International Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. Sltlaternalienal_Intercompa rison 115-5B LiF-100 Chips Oct,1980 Field 30.314.8 30.016.0 30.2114.6 115-3B LiF-100 Chips Oct,1980 Lab,End 85.4 i 11.7 88.4 i 8.8 90.7131.2 115-5B LiF-100 Chips Oct,1980 Lab, Start 81.117.4 75.217.6 75.8140.4 Fifth Intemational Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 6th Internatienalintercomparison 115-6 Teledyne did not participate in the Sixth Intemational Intercomparison of Environmental Dosimeters. ZilLinternational Intercomp_atisen 115-7A LiF-100 Chips Jun,1984 Field 75.4 i 2.6 75.816.0 75.1129.8 161
1994 Davis-flesse Nuclear Power Station Annual Radiological Erivitonmental Operating Report Tabic A 2. Crowick program resulta;1hermoluminncent Dosimetcra,(11.th). mR I.ab Tcledync itnulta Krnwn Average 12 Sigma Cale Tl D Type Date Mena.urement 12 Sigma Value 12 Sintna (All Participants) 115 7A l.ilL100 Chips jun,19&1 1,ab, Co 60 80013,5 79.9 i 4.0 77.9127.6 115 7A l.ilL100 Chips jun,19&l 1.ab, Cn 137 66 6 i L5 75 013E 73.0122.2 Seventh International Intercompartwn of l'avironmental Ikn.imetern conducted in the spring and summer of 1984 at las Vegas, Nevada, and sponwred by the U.S Department of Fncrgy,lhc Nuclear l<cgulatory Comminion, and the U.S Favbontnrntal Pmtection Agency. 7thintonativaallutcrtumparbon 115 711 1.11L100 Chips jun,19&l l'icld 71.512.6 75E i ti 0 75.1129E 115 711 1.ilL100 Chipe jun,19&l Iab, Co 60 HIH16.4 79.914.0 77.9 i 27.6 115 711 1.iI: 100 ChIpn Jun,19&l 1.ab, Ca 137 78Hi1.6 75.0138 730122.2 Seventh International Interrompanimn of l'avironmental i hnhneters conduc ted in the s>pring and suminer of 1981 at 1.4s Vegas, Nevada, and sponsored by the US I A partment of Energy,1hc Nuclear Regulatory Cr.m nluion, and the US favironmental PaolciImn Agency. 7th Internatjunalintacompatiwn 115 7C CaSOc Dy jun,1931 l'ictd 76 H12.7 75E A 6.0 75.1129 H Cards 115 7C CaSOc Dy jun,1961 1.ab, Co u) H2.5 i 3.7 79.914.0 77.9127.6 Cards 115 7C Casoc Dy jun,19&l Ieb,cr137 79013.2 75 013 H 730122.2 Cardn Ses enth International Intercompasima of lavitonmental Dosimeterk condu< ted in the Sprbig and Suinmcr of 1984 at 1.as Vegas, Nevada, .md r.ponwied by the U S I A partment of Frergy,lhc Nuclear Regulatory Conuniwion, and the U.S l.nvironmental Protes tion Agency. bih intctnational]nintempauwn i15-HA lar.100 Chips jan,1986 licid, Site 1 29.511.4 29.711.5 28.9 i 12.4 115 HA !.il:-100 Chip. jan,1986 Field, Site 2 11.3108 10430.5 10119.1 115.HA talt100 Chips jan,19tw I.ab, Co.137 13.710.9 17.210.9 16 216 H 1:ighth Inte nationalIntertornpariwn of Tnvironmental thimeterr, ronducted in the fall ar.d winter of 1965>1986 at New York, New Yo:L, and sponsored by the US Department of Energy. fithlniunstiunallutacomparisun i15 Hil I.ill100 Chips jan,1986 Taeld, Site 1 32.311.2 29.711.:. 2A9112.4 115 811 1.iF-100 Chips jan,1936 field, Site 2 9.011.0 10.410.5 10.119,0 115 till 1.116100 Chipa jan,1986 1.ab,Cn137 15 H 10.9 17.210.9 16.2 2 6E righth International Interromparimn of l' avitonmental Dosimetern condmled in the f all and winter of 19851986 at New York, New Yoik, and sponwred by the US Depastment of T.ncrgy. 6thJninnationalJntacompathon 115-3C CaSov Dy Jan.1986 Iicid, Site 1 32.2107 29.7 i 1.3 289112.4 Canin l 162
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'i 1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report j I
Table A 2. Crosscheck program results;Thermoluminescent Dosimeters. (ILDs). i f mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Date _ Measurement i 2 Sigma Value i 2 Sigma (All Participants) ' 115-8C CaSO.: Dy Jan,1986 Pield, Site 2 10.6i 0.6 10.410.5 10.119.0 i Cards l 115-8C CaSO.: Dy Jan,1986 . Lab, Cs 137 18.110.8 17.210.9 16.216.8 l Cards Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of ! 1985-1986 at New York, New York, and sponsored by the U.S. Departmert of Energy. l j 9th International Intercomnarison 115-9 ]
' The Ninth International Intercomparisen of Environmental Dosimeters was not available to Teledyne's !
Midwest Laboratory. lQi}LIDieInational IntcIrgglparison l 115-10A LiF-100 Chips Aug,1993 Field 25.711.4 -27.011.6 26.4110.2 l 115-10A LiF-100 Chips Aug,1993 Lab,1 22.711.6 25.911.3 25.019.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62.712.6 72.711.9 69.8120.3 l The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho Stat j University and sponsored by the U.S. Department of Energy and the Idaho Stat University- i 101b International Intercomparison l . 115-10B CaSO.: Dy Aug,1993 Field 26.012.3 27.011.6 26.4i112 ; Cards - . l 115-10B CaSO.: Dy Aug,1993 Lab,1 24.111.7 25.911.3 25.019.4 ; Cards, ,t 115-10B CaSO.: Dy . Aug,1993 Lab,2 69.2 i 3.0 72.711.9 69.8 i 20.3 l Cards The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho Stat i University and sponsored by the U.S. Department of Energy and the Idaho Stat University. : 3 Icledyne Testine j 89-1 LiF-100 Chips Sep,1989 Lab 21.010.4 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. , Irledvne Testing ? 89-2 Teledyne Nov,1989 Lab 20.911.0 20.3 ND CaSo.: Dy . Cards j ND = No Data; Teledyne Testing was only performed by Teledyne. ! Cards were irradiated by Tcledyne isotopes, Inc., Westwood, New Jersey, in June,1990. j i l j I 163 i
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i j 1994 Davis-Besse Nuclear Power Station Annual Radaological Environmental Operating Report l i I
)
Table A-2. Crosscheck program results;"Ihermoluminescent Dosimeters. (TLDs). mR $ 4 Lab Teledyne Results Known Average i 2 Sigma I Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) _{ Teledyne Testine 90-1 Teledyne Jun,1990 Lab 20.611.4 19.6 ND . CaSo.: Dy Cards ND = No Da'a; TelQae Testing was only performed by Teledyne. f Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. ; Teledyne Testine j 90-2 Teledyne Jun,1990 Lab 100.814.3 100.0 ND ; CaSo.: Dy j Cards . ND = No Data;Teledyne Testing was only performed by Teledyne. , Cards were irradiated by Dosimetry Asssociates, Inc., Northville, MI, in October,1990. j Tcledync.Issting l 91-1 Teledyne Oct,1990 Lab,1 33.412.0 32.0 ND ! CaSo : Dy : Cards ! 91-1 Tcledyne Oct,1990 Lab,2 55.2 i 4.7 58.8 ND r CaSo.: Dy i Cards 91-1 Teledyne Oct,1990 Lab,3 87.816.2 855 ND f CaSo.: Dy , Cards ND = No Data; Teledyne Testing was only performed by Teledyne. l Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in October,1991. Teledyne Testinc j 92-1 LiF-100 Cbips Feb,1992 lab,1 11.110.2 10.7 ND c 92-1 LiF-100 Chips Feb,1992 Lab,2 25.610.5 25.4 ND : 92-1 LiF-100 Chips Feb,1992 Lab,3 46.410.5 46.3 ND 3 ND = No Data; Teledyne Testing was only performed by Teledyne. j Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in February,1992. I Teledyne Testinc 92-2 Tcledyne Apr,1992 Reader 1, #1 20.110.1 20.1 ND l CaSo.: Dy j Cards j 92-2 Teledyne Apr,1992 Reader 1, #2 40.610.1 40.0 ND f CaSo.: Dy i Cards I ( 1 1 164 l
1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report Table A-2. Crosscheck progrem results;Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Date Measurement i 2 Sigma Valuei 2 Sigma (All Participants) 92-2 Teledyne Apr,1992 Reader 1, #3 60.011.3 60.3 ND CaSoc Dy Cards 92-2 Teledyne Apr,199.2 Reader 2, #1 20.310.3 20.1 ND CaSo; Dy Cards 92-2 Teledyne Apr,1992 Reader 2, #2 39.210.3 40.0 ND CaSo; Dy Cards 92-2 Teledyne Apr,1992 Reader 2, #3 60.710.4 60.3 ND CaSo; Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in April,1992. Teledyne Testing 93-1 Teledyne Mar,1993 Lab,1 10.0i 1.0 10.2 ND LiF-100 Chips 93 1 Teledyne Mar,1993 Lab,2 25.212.2 25.5 ND LiF-100 Chips 93-1 Tcledyne Mar,1993 Lab,3 42.715.7 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 potential error of 10-12% when cards where irradiated, results of the testing on the cards will not be published. Data is available upon request. Icledyne Testing 94-1 Teledyne N,v,1994 Lab,1 15.610.4 14.9 ND LiF-100 Chips 94-1 Tcledyne Nov,1994 12b, 2 30.210.4 29.8 ND LiF-100 Chips 94-1 Tcledyne Nov,1994 Lab,3 59.210.3 59.7 ND LiF-100 Chips 94 1 Teledyne Nov,1994 Reader 1, #1 14.910.1 14.9 ND CaSo; Dy i Cards 94-1 Teledyne Nov,1994 Reader 1, #2 30.810.1 29.8 ND CaSo; Dy Cards l
~
165 l
\
J 1994 Davis-Besse Nuclear Power Station Annual Radiological Ens.unmental Operating Report l , i l I m Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). ! 4 mR ! Lab Teledyne Results Known Average i2 Sigma ! Code TLD Type Daie Measurement i 2 Sigma Value i 2 Sigma (All Participants) , 94-1 Teledyne Nov,1994 Reader 1, #3 58.9 i 0.3 59.7 ND CaSo; Dy Cards 94-1 Teledyne Nov,1994 Reader 2, #1 15.4 i 0.2 14.9 ND l CaSo; Dy ; Cards ; 94-1 Teledyne Nov,1994 Reader 2, #2 31.410.2 29.8 ND ; CaSo; Dy ! Cards ! 94-1 Teledyne Nov,1994 Reader 2, #3 60.110.3 59.7 ND l CaSo; Dy , Cards i ND = No Data; Teledyne Testing was only performed by Teledyne. f Cards were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in November,1994. i t i f i l i i i i 166 1
1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report ; Table A-3. In-house " spike" samples. . Concentration in pCi/11 l Lab Sample Date Teledyne Results Known Control' I Code- Type Collected Analysis 2s, n=1 6 Activity Limits -j SPW-4821 WATER Jan,1994 Cc-144 2593.1 1 54.9 - 2692.5 1615.5 - 2961.8 j SPW-4822 WATER Jan,1994 Cc-144 1705.1 1 48.1 1749.8 1049.9 - 1924.8 l SPW-4823 WATER Jan,1994 Ce-144 55.4117.5 49.0 29.4 - 59.0 l SPW-4825 WATER Jan,1994 Gr. Alpha 34.411.6 41.7 20.9 - 62.6 SPW 4825 WATER Jan,1994 Gr. Beta 33.611.2 30.2 20.2 - 40.2 ; SPW-4826 WATER Jan,1994 Gr. Alpha 66.8 i 2.1 83.4 41.7 - 125.1 SPW-4826 WATER Jan,1994 Gr. Deta 63.811.5 60.4 50.4 - 70.4 ; SPMI-4848 . MILK Jan,1994 Cs-134 27.215.7 31.7 21.7 - 41.7 SPMI-4848 MILK Jan,1994 Cs-137 34.618.2 34.8 24.8 - 44.8 ; SPMI-4848 MILK Jan,1094 St-89 28.2i 3.8 35.0 25.0 - 45.0 ; SPM14848 MILK Jan,1994 Sr-90 41.211.2 40.7 32.6 - 48.8 SPMI-4849 MILK Jan,1994 Sr-89 9.511.6 11.9 1.9 - 21.9 SPMI-4849 MILK Jan,1994 Sr-90 19.410.8 20.1 10.1 - 30.1 , SPMI-4862 MILK Jan,1994 Cs-134 328.31 16.3 338.0 304.2 - 371.8 l SPMI-4862 MILK 'Jan,1994 Cs-137 1019.6 1 18.3 1114.4 1003.0 - 1225.8 SPAP-4953 AIR FILTER Jan,1994 Gr. Beta 4.810.1 4.2 0.0 - 14.2 'j SPAP-4954 AIR TILTER Jan,1994 Cs-137 1.4 1 0.1 1.3 0.8 - 1.8 ! f SPW-4955 WATER Jan,1994 H-3 17080.0 i 364.0 17163.0 13730.4 - 20595.6 SPW-4956 WATER Jan,1994 Co-60 1514.0i 46.2 1545.0 1390.5 - 1699.5 SPW-4956 WATER Jan,1994 Cs-134 433.71 25.5 479.0 431.1 - 526.9 SPW-4956 WATER Jan,1994 Cs-137 742.71 45.9 732.0 658.8 - 805.2 ! SPCIl-4928 ClIARCOAL Feb,1994 1131(g) 1449.9 i 65.1 1452.8 871.7 - 1598.1 l CANISTER j SPW-4934 WATER Feb,1994 1-131 76.4 i 1.4 90.8 72.6 - 109.0 ; SPW-4934 WATER Feb,1994 I-131(g) 90.217.6 90.8 54.5 - 100.8 SPMI-4935 MILK Feb,1994 I-131 40.411.0 43.6 31.6 - 55.6 i SPMI-4935 MILK Feb,1994 1-131(g) 41.816.7 43.6 26.2 - 53.6 SPBS-5102 SEDIMENT Mar,1994 11-3 97.211.0 105.4 0.0 - 630.0 SPW-5146 WATER Mar,1994 Sr-89 25.513.9 26.4 16.4 - 36.4 I SPW-5146 WATER Mar,1994 Sr-90 16.211.1 18.8 8.8 - 28.8 . SPW-646 WATER Apr,1994 113 9847.8 1 294.9 9855.0 7884.0 - 11826.0 l SPW-648 WATER ' Apr,1994 Co-60 21.616.6 22.6 12.6 - 32.6 [ WATER 33.318.5 33.6 23.6 - 43.6 l SPW-648 Apr,1994 Cs-134 36.3 26.3 - 46.3 I SPW-648 WA1 ER Apr,1994 Cs-137 37.619.8 SPMI 650 MILK Apr,1994 Cs-134 52.015.3 50.6 40.6 - 60.6 f
~'
167
~ - ._ -. .. . ~ ..- - - .-. - . . - ..
t C 1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report i l Table A-3. . In-house " spike" samples. Concentration in pCi/L' f Lab Sample Date Teledyne Results Known ControF Code Type Collected Analysis 2s, n=1 6 Activity Limits SPMl-650 MILK Apr,1994 Cs-137 61.6 i 8.3 54.5 44.5 - 64.5 i SPW-652 WATER Apr,1994 Gr. Alpha 44.8 i l .2 41.6 20.8 - 62.4 , SPW-652 WATER Apr,1994 Gr. Deta 24.lil.0 25.4 15.4 - 35.4 SPAP-654 AIR FILTER Apr,1994 Cs-137 1.~.1 0.1 1.3 0.8 - 1.8 t SPW-974 WATER May,1994 Fe-55 56.7 i 12.0 58.5 38.5 - 78.5 SPF-1023 FIS11 UELLO) May,1994 Cs-137 6.9 1 0.1 6.8 0.0 - 16.8 [ SPBS-1024 SEDIMENT May,1994 Cs-137 6.210.1 6.0 0.0- 16.0 I SPW-1850 WATER Jun,1994 1-131 46.010.7 51.8 39.8 - 63.8 [ SPW-1850 WATER Jun,1994 1-131(g) 50.9 8.3 51.8 31.1 - 61.8 i SPMI-1831 MILK Jun,1994 1-131 51.710.6 51.8 39.8 - 63.8 SPMI-1851 MILK Jun,1994 I-131(g) 51.3110.8 51.8 31.1 - 61.8 f SPVE-1854 VEGETATION Jun,1994 I-131(g) 0.9 1 0.1 1.0 0.6 - 1.4 i (SAWDUST) SPCH 1855 CIIARCOAL Jun,1994 1-131(g) 1.9 i 0.1 1.8 1.1 - 2.5 [ CANISTER i SPW 3278 WATER Jun,1994 Gr. Alpha 20.811.1 23.4 11.7 - 35.1 l SPW-3278 WATER Jun,1994 Gr. Beta 29.5 i 1.1 31.8 21.8 - 41.8 l SPW-3276 WATER Jul,1994 H-3 24504.6 i 421.7 25019.0 20015.2 30022.8 l SPMl-3282 MILK Jul.1994 Sr-89 16.414.8 22.5 12.5 - 32.5 : SPMI-3282 MILK Jul,1994 Sr-90 25.3 i 1.4 25.4 15.4 - 35.4 SPW-3284 WATER Jul,1994 Cs-137 240.8 1 19.3 221.5 199.4 - 243.7 SPAP-3388 AIR FILTER Jul,1994 Gr. Beta 7.9 1 0.1 8.3 0.0- 18.3 { SPAP-3390 AIR FILTER Jul,1994 Cs-137 1.3 i 0.1 1.3 0.8 - 1.8 SPF-3603 FIS110ELLO) Jul,1994 Cs-137 8.311.3 8.5 0.0 - 18.5 ! SPW-5549 WATER Oct,1994 1-131 77.410.9 79.9 63.9 - 95.9 l r SPW-5549 WATER Oct,1994 1-131(g) 85.5 i 9.5 79.9 47.9 - 89.9 ; t SPMI-5550 MILK Oct,1994 Cs-134 35.016.0 36.4 26.4 - 46.4 i SPMI-5550 MILK Oct,1994 Cs-137 46.1 i 9.4 44.1 34.1 - 54.1 ! SPMI-5550 MILK Oct,1994 I-131 65.210.9 63.9 51.1 - 76.7 ') SPMl 5550 MILK Oct,1994 1-131(g) 68.4 i 11.1 63.9 38.3 - 73.9 l SPW-5594 WATER Oct,1994 1-131 92.511.0 95.8 76.6 - 115.0 SPW-5594 WATER Oct,1994 I-131(g) 98.2 i 10.1 95.8 57.5 - 105.8 SPVE-6067 VEGETATION Oct,1994 1-131(g) 1.710.1 1.6 1.0 - 2.2 (SAWDUST) SPS 5946 SEDIMENT Oct,1994 Cs-134 0.3124.2 0.3 0.20.5 (BOTTOM) SPF-6208 Fis11 UELLO) Oct,1994 Cs-137 11.610.1 12.1 2.1 - 22.1 ,
6 l l 1994 Davis-Besse Nuclear Power Station Annual Ra&olopcal Environmental Operating Report j i t l Table A-3. In-house " spike" samples. .l t Concentration in pCi/1/ ; Lab Sample Date Teledyne Results Known Control' 'l Code- Type Collected Analysis 2s, n=1 6 Activity ~ Limits ! SPW-6955 WATER Nov,1994 Ni-63 1851.6 i 34.3 1931.0 1158.6 - 2703.4 SPW-6994 WATER Nov,1994 Tc-99 63.217.8 66.0 46.2 - 85.7 - l SPW-7440 WATER Nov,1994 - }{-3 24099.2 1 423.9 24260.0 19408.0 - 29112.0 l
- SPAP.7507 AIR FILTER ~ Nov,1994 Cs-137 2.210.0 1,9 1.2 '2.7 a
t i l t a
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- i 1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report e r l
?
I h Table A-4. In-house " blank" samples. ! Concentration pCi/L*. Teledyne Results Acceptance ! Lab Sample Sample (4.66 Sigma) Criteria i Code Type Date Analysis LLD Activity" (4.66 Sigma) l SPW-4820 WATER Jan 1994 Cs-134 < 1.9 -1.7617.24 < 10.0 i SPW-4820 WATER Jan1994 Cs-137 <4.4 -0.31 i 2.67 < 10.0 f SPW-4824 WATER Jan 1994 Gr. Alpha <0.3 0.0010.20 < 1.0 i SPW-4824 WATER Jan 1994 Gr. Deta <0.9 0.4010.59 < 3.2 [ SPW-4827 WATER Jan1994 Co-60 <1.8 1.1011.04 < 10.0 f SPW-4827 WATER Jan 1994 Cs-134 < 1.9 0.5116.?6 < 10.0 ! SPW-4827 WATER Jan 1994 Cs-137 <2.0 0.43 0.84 < 10.0 f SPW-4827 WATER Jan 1994 Gr. Alpha <0.4 0.1210.25 < 1.0 ! SPW-4827 WATER Jan1994 Gr. Beta <0.8 0.2110.55 < 3.2 l SPW-4827 WATER Jan 1994 11-3 <192.0 133.90 1 101.00 < 200.0 ! SPW-4827 WATER Jan 1994 I-131 <0.3 -0.1210.14 < 0.5 . [ SPMI-4846 MILK Jan 1994 Co-60 <3.6 0.62 i 2.67 < 10.0 I SPMI-4846 SPMI-4846
. MILK MILK Jan 1994 Cs-134 <5.4 0.52 i 3.83 < 10.0 [
Jan 1994 Cs-137 <3.4 -0.7412.93 < 10.0 l SPMI-4846 MILK Jan 1994 I-131 <0.5 0.27 i 0.34 < 0.5 SPMI-4846 MILK ' Jan 1994 Sr-89 <0.5 -0.5410.79 < 5.0 .i SPMI-4846 MILK Jan1994 Sr-90 N/A 1.9310.44 < 1.0 l Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPAP-4950 AIR FILTER Jan 1994 Co-60 <2.2 -2.61 2.19 < 10.0 SPAP-4950 AIR FILTER Jan 1994 Cs-134 <3.1 -0.3113.65 < 10.0 . SPAP-4950 AIR FILTER Jan1994 Cs-137 <2.9 2.78 23.94 < 10.0 SPAP-4952 AIR FILTER Jan 1994 Gr. Beta <0.9 0.0010.58 < 3.2 ! SPCII-4951 CHARCOAL Feb 1994 I-131(g) <7.0 0.6414.80 <9.6 [ CANISTER ; SPW-5054 WATER Mar 1994 Ra-226 <0.1 0.0110.03 < 1.0 l SPW-5054 WATER Mar 1994 Ra-228 <1.0 0.5410.67 < 1.0 i SPDS-5101 SEDIMENT Mar 1994 Co-60 <5.9 -0.19 i 1.63 < 10.0 SPBS-5101 SEDIMENT Mar 1994 Cs-134 76.2 -31.20 i 13.10 < 10.0 SPDS-5101 SEDIMENT Mar 1994 Cs-137 <4.4 -0.2612.75 <10.0 f SPW-647 WATER Apr1994 Co-60 <5.8 0.56 i 0.53 < 10.0 SPW-647 WATER Apr1994 Cs-134 <3.4 0.86 i 0.72 < 10.0 { SPW-647 WATER Apr1994 Cs-137 <5.1 2.6512.75 < 10.0 l SPW-647 WATER Apr 1994 H-3 <191.5 148.40 1 100.90 < 200.0 ; SPW-647 WATER Apr 1994 1-131 <0.5 -0.3410.22 <0.5 [ SPMI-649 MILK Apr 1994 Co-60 <6.5 0.55 i 1.39 . < 10.0 - l l I 170 ) I
=
1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report Table A-4. In-house " blank" samples. Concentration g<i/L*. Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity" (4.66 Sigma) SPMI-649 MILK Apr 1994 Cs-134 <3.4 -3.4515.60 < 10.0 SPMI-649 MILK Apr 1994 Cs-137 <4.6 0.5913.98 < 10.0 SPMI-649 MILK Apr 1994 I-131 <0.5 -0.11 0.19 <0.5
~
SPW-651 WATER Apr 1994 Gr. Alpha <0.4 0.1410.25 < 1.0 SPW-651 WATER Apr 1994 Gr. Beta <0.8 0.1210.54 <3.2 SPAP-653 AIR FILTER Apr 1994 Cs-134 <2.1 -0.1210.18 < 10.0 SPAP-653 AIR FILTER Apr 1994 Cs-137 <3.4 1.0511.55 < 10.0 SPCil-654 CliARCOAL Apr 1994 I-131(g) < 6.1 OE513.84 < 9.6 CANISTER SPAP-4956 AIR FILTER Apr 1994 Gr. Beta < l .0 0.3210.96 < 3.2 SPW-974 WATER May 1994 Fe-55 <0.8 0.1010.47 < 1000.0 SPF-1022 FIS)i 0ELLO) May 1994 Cs-134 <9.2 12.70 1 31.70 < 10.0 SPF-1022 FISil UELLO) May 1994 Cs-137 <10.0 27.30 1 58.30 < 10.0 SPW-1075 WATER May 1994 Ra-226 <0.1 0.0110.04 < 1.0 SPDS-3254 SEDIMENT May 1994 Co-60 <5.8 5.9318.06 < 10.0 SPilS-3254 SEDIMENT May 1994 Cs-134 <2.0 5.6716.69 < 10.0 SPDS-3254 SEDIMENT May 1994 Cs-137 <5.0 -2.1114.69 < 10.0 SPVE-1852 VEGETATION Jun1994 Cs-134 <5.4 -1.4712.14 < 10.0 l (SAWDUST) SPVE-1852 VEGETATION Jun1994 Cs-137 <6.6 2.1213.44 < 10.0 (SAWDUST) SPVE-1852 VEGETATION Jun1994 I-131(g) <S.6 -0.7311.08 < 20.0 (SAWDUST) SPW-3277 WATER Jun 1994 Gr. Alpha <0.3 0.1010.22 < 1.0 SPW-3277 WATER Jun 1994 Gr.11cta <0.8 0.1410.54 < 3.2 SPW-3275 WATER Jul 1994 11-3 <154.9 22.81 1 77.81 < 200.0 SPM1-3281 MILK Jul1994 Co44 <3.6 0.8712.22 < 10.0 SPMI-3281 MILK Jul1994 Cs-134 <2.3 -0.45 i 2.61 < 10.0 SPMI-3281 MILK Jul1994 Cs-137 <4.2 0.0712.28 < 10.0 SPMI-3281 MILK Jul1994 1-131 <0.2 0.1010.16 <0.5 SPMI-3281 MILK Jul 1994 Sr-89 <0.9 -0.5411.32 < 5.0 SPMI-3281 MILK Jul1994 St-90 N/A 2.2910.56 < 1.0 Low level of Sr 90 concentration in milk (1-5 pCi/L) is not unusual. SPW-3283 WATER Jul1994 Co4>0 < 2.2 -3.0913.52 < 10.0 SI'W-3283 WATER Jul1994 Cs-134 <5.4 0.79 i 3.13 < 10.0 171
1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report Table A-4. In-house " blank" samples. Concentration pCi/L'. , Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity" (4.66 Sigma) SPW-3283 WATER Jul1994 Cs-137 <5.0 -0.1013.05 < 10.0 SPW 3283 WATER Jul1994 1-131 <0.4 0.1410.22 <0.5 SPAP-3389 AIR FILTER Jul1994 Gr. Beta <0.2 0.1610.26 < 3.2 SPAP-3391 AIR FILTER Jul 1994 Co-60 < 1.7 -0.74 i 1.44 < 10.0 SPAP-3391 AIR FILTER Jul1994 Cs-134 <2.3 0.9514.86 < 10.0 SPAP-3391 AIR FILTER Jul1994 Cs-137 <4.1 -3.03 i 3.15 < 10.0 SPF-3602 FISH UELLO) Jul1994 Co40 <3.6 -4.45 i 4.27 < 10.0 SPF-3602 FISli (JELLO) Jul1994 Cs-134 <4.1 -3.91 i 5.63 < 10.0 SPF-3602 FISH OELLO) Jul1994 Cs-137 < 4.7 -5.1715.80 < 10.0 SPMI-5551 MILK Oct 1994 Cs-134 <4.3 0.9013.34 < 10.0 SPMI-5551 MILK Oct 1994 Cs-137 < 4 .1 -0.5513.43 < 10.0 SPMI-5551 MILK Oct 1994 1-131 <0.2 -0.0310.16 <0.5 SPSO-5947 SOIL Oct 1994 Cs-134 <2.3 -4.84 14.84 < 10.0 SPSO-5947 SOIL Oct 1994 Cs-137 <6.4 -0.5014.71 < 10.0 SPW-6995 WATER Nov 1994 Tc-99 <4.2 1.2412.19 < 10.0 SPW-7441 WATER Nov 1994 H-3 <169.0 -74.64 i 80.48 < 200.0 SPW-7442 WATER Nov 1994 H-3 <169.0 -37.02 82.14 < 200.0 SPAP-7506 AIR FILTER Nov 1994 Co-60 <2.1 0.1711.63 < 10.0 - SPAP-7506 AIR FILTER Nov 1994 Cs-134 <1.6 1.0811.70 < 10.0 SPAP-7506 AIR FILTER Nov 1994 Cs-137 <3.0 -0.55 i 1.65 < 10.0
- Liquid sample results are reported in pCi. Liter, air filter sample results are in pCi/ filter, charcoal sample results are in pCi/ charcoal, and solid sample results are in pCi/ kilogram.
- 'Ihe activity reported is the net activity result.
i 172
I 1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report ; Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Code # Date Analysis Result Result Result WATER-4607, 4608 jan,1994 Gr. Beta 1.35 0.70 1.3810.70 1.3710.49 MILK-166,167 Jan,1994 Co-60 1.4213.73 -1.13 i 4.25 0.1512.83 MILK-166,167 Jan,1994 Cs-137 -0.2613.42 -0.65 i 2.61 -0.4612.15 M1LK-166,167 Jan,1994 1-131(G) -0.1010.22 0.2210.22 0.06 i 0.16 WATER-4711, 4712 Jan,1994 Gr. Beta 1.7010.60 1.8010.60 1.7510.42 MILK-187,188 Jan,1994 Co-60 0.0512.88 -1.4313.35 -0.69 i 2.21 MILK-187,188 Jan,1994 Cs-137 0.16 i 1.87 1.8612.61 1.0111.61 MILK-187,188 Jan,1994 1-131 0.1610.18 0.13 i 0.23 0.15 0.15 WATER-4664, 4665 Jan,1994 Gr. Beta 8.8011.80 4.4011.40 6.6011.14 A review of the raw data revealed no errors or discrepancies. The sample was reanalyzed. The result of the recalysis was 6 611.5 pCi/L. No further action is planned. W ATER-4664, 4665 Jan,1994 11-3 92.98 i 95.90 37,19 1 93.63 65.09 1 67.01 WATER-4687, 4688 Jan,1994 Gr. Alpha 1.5711.48 0.00i l.19 0.7910.95 WATER-4687,4688 Jan,1994 Gr. Beta 3.2310.82 2.5110.79 2,871057 WATER-4687, 4688 Jan,1994 11-3 171.80 1 98.99 183.40 1 99.44 177.60 1 70.16 WATER-4741, 4742 Jan,1994 11-3 105.00 1 101.00 127.00 1 102.00 116.00 1 71.77 MILK-208,209 Jan,1994 K-40 1,396.00 1 148.00 1,586.00 162.00 1,491.00 1 109.71 M1LK-208, 209 Jan,1994 Sr-90 2.9610.56 3.58 i 0.68 3.2710.44 WATER-4830, 4831 Jan,1994 11-3 73.80 1 39.38 79.33 1 89.60 76.571 63.28 WATER-4865, 4866 Jan,1994 Gr. Deta 1.93 e 0.19 1.9410.18 1.9410.13 WATER-5052, 5053 Jan,1994 Gr. Deta 2.2( i 0.55 2.5810.56 2.3910.39 WATER-4890, 4891 Jan,1994 11-3 421.90 1 109.00 454.80 1 106.60 438.35 i 76.23 WATER-4919, 4920 Jan,1994 Gr. Beta 2.8010.80 3.4010.80 3.1010.57 WATER-4952, 4953 Feb,1994 Gr. Beta 2.6610.55 2.1410.52 2.4010.38 WATER-5010, 5011 Feb,1994 Ii-3 142.00 1 99.00 119.00 1 96.00 130.50 1 69.65 MILK-250, 251 Feb,1994 K-40 1,087.00 1 77.00 1,036.00 i 98.00 1,061.50 1 62.32 ; MILK-250, 251 Feb,1994 Sr-90 3.681062 4.0910.61 3.8910.43 MILK-271,272 Feb,1994 K-40 1,510.00 1 90.00 1,520.00 1 110.00 1,515.00 1 71.06 WATER-4978, 4979 Feb,1994 11-3 33.75 i 96.98 69.80 i 96.41 76.78 i 68.37 MILK-229,230 Feb,1994 Co-60 -1.48 i 4.16 -1.6015.54 -1.5413.46 MILK-229, 230 Feb,1994 Cs-137 -0.67i 3.05 -1.96 i 3.72 -1.3212.41 MILK-229,230 Feb,1994 1-131 0.17 i 0.24 0.1010.17 0.14 i 0.15 WATER-5081, 5082 Feb,1994 11-3 28.00 1 95.00 72.00 1 96.00 50.00 i 67.53 WATER-5124, 5125 Feb,1994 11-3 465.80 1 113.65 358.00 1 109.80 411.90 1 79.01 WATER-5212, 5213 Feb,1994 Gr. Deta 2.86 i 0.67 2.2210.59 2.54 i 0.45 WATER-5183, 5184 Feb,1994 Co-60 1.46 i 1.64 -0.7012.04 0.38 i 1.31 WATER-5183, 5184 Feb,1994 Cs-137 0.3311.63 0.3712.05 0.3511.31 WATER-5183, 5184 Feb,1994 Gr. Beta 4.9211.09 4.52 i 1.07 4.7210.76 M1LK-292, 293 Mar,1994 K-40 1,377.00 1 85.00 1,364.00 i 100.00 1,370.50 1 65.62 MILK-292,293 Mar,1994 Sr-90 1.2010.38 1.4910.41 1.35 i 0.28 MILK-5246, 5247 Mar,1994 Gr. lieta 6.5410.83 6.42 i 0.88 6.4810.60 . 173
1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result WATER-5270, 5271 Mar,1994 Gr. Beta 3.2810.98 2.84 i 0.96 3.06 i 0.69 WATER-5293, 5294 Mar,1994 H-3 620.18 i 118.74 582.33 1 117.46 601.26 i 83.51 MILK-313,314 Mar,1994 1-131(G) 1.26 1 47.70 -0.3010.78 0.48 1 23.85 MILK-334, 335 Mar,1994 K-40 1,392.00 i 95.00 1,437.00 1 115.00 1,414.50 1 74.58 WATER-5400, 5401 Mar,1994 H-3 77.70 1 97.20 66.76 1 96.54 72.23 1 68.50 WATER-5485, 5486 Mar,1994 H-3 336.00 i 107.00 272.00 1 105.00 304.00 1 74.96 WATER-5446, 5447 Mar,1994 Co-60 1.84 i 4.35 0.0710.45 0.96 i 2.19 WATER-5446, 5447 Mar,1994 Cs-137 0.6811.61 1.0111.91 0.8511.25 WATER-5446, 5447 Mar,1994 Gr. Beta 3.8411.25 3.7211.25 3.7810.88 WATER-5510, 5511 Mar,1994 11-3 396.00 1 89.00 458.51 1 113.14 427.26 i 71.98 WATER-5538, 5539 Mar,1994 Gr. Deta 2.58 0.62 2.02 0.60 2.3010.43 WATER-5593, 5594 Mar,1994 H-3 139.87 1 101.14 169.37 i 101.75 154.62 i 71.73 WATER 5614,5615 Mar.1994 Co-60 0.3611.04 0.22 i 2.15 0.29i l.19 WATER-5614, 5615 Mar,1994 Cs-137 0.90 i 3.78 -0.3912.59 0.2612.29 WATER-5566, 5567 Mar,1994 Gr. Deta 2.76 0.50 2.2010.48 2.4810.35 WATER-72, 73 Mar,1994 Gr. Beta 1.5810.50 1.4610.48 1.5210.35 WATER-49, 50 Apr,1994 Gr. Beta 3.43 i 0.92 3.4310.92 3.4310.65 WATER-102,103 Apr,1994 Gr. Beta 2.0210.50 2.0510.47 2.0410.34 WATER-102,103 Apr,1994 H-3 165.00 i 102.00 79.00 i 98.00 122.00 i 70.72 WATER-187,188 Apr,1994 Gr. Beta 3.3810.66 3.1910.64 3.2910.46 MILK-246, 247 Apr,1994 Co40 1.75 i 1.61 1.7611.61 1.7611.14 MILK-246,247 Apr,1994 Cs-137 0.1011.86 0.1011.86 0.10 i 1.32 M!LK-246, 247 Apr,1994 1-131 0.073 0.23 0.1510.34 0.11 i 0.21 WATER-257, 258 Apr,1994 Gr. Beta 320.c 0.74 3.2810.79 3.28 i 0.54 WATER-267, 268 Apr,1994 Cs-137 0.19 i 2.69 1.22 i 2.18 0.7111.73 WATER-281, 282 Apr,1994 Gr. Deta 15.73 2.02 30.38 i 2.60 23.% 1 1.65 A review of the raw data revealed no errors or discrepancies. Both samples were recounted. The results of the recounts were in agreement with the initial results. The sample was reanalyzed. The result of the reanalysis was 30.712.1 pCi/L. No further action is planned.
WATER-281, 282 Apr,1994 H-3 381,181.00 1 1,740.00 378,406.00 1 1,733.00 379,793.50 i 1,227.89 , WATER-454, 455 Apr,1994 Gr. Beta 3.3412.10 3.6712.20 3.51 i 1.52 WA'ER-405, 406 Apr,1994 H-3 65.901 98.21 61.95 i 98.05 63.93 i 69.39 MILK-464, 465 Apr,1994 K-40 1,630.00 i 130.00 1,589.00 i 162.00 1,609.50 i 103.86 WA'GR-516, 517 Apr,1994 H-3 37.60 1 94.95 69.26 i 95.77 53.43 1 67 43 ; WATER-267, 268 Apr,1994 Cs-137 0.19 i 2.69 1.2212.18 0.7111.73 l WATER-616, 617 Apr,1994 Gr. Deta 2.50 i 0.52 3.0410.55 2.77 i 0.38 WATER-616, 617 Apr,1994 H-3 193.00 1 102.00 203.00 1 103.00 198.00 1 72.48 l WATER-739, 740 Apr,1994 Co-60 0.84 i 11.40 0.31 i 0.43 U.58 i 5.70 ; WATER-739, 740 Apr,1994 Cs-137 -0.30 i 3.59 0.7713.23 0.2412.41 l WATER-739, 740 Apr,1994 Cs-137 -0.3013.59 0.7713.23 0.2412.41 WATER-697, 698 Apr,1994 Co-60 3.4114.36 2.0512.79 2.7312.59 . l
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1994 Davis-Besse Nuclear Power Station 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 WATER-697, 698 Apr,1994 Gr. Beta 2.9310.98- 3.0910.78 3.0110.63 ,
WATER-1003,1004 - May,1994 Gr. Deta - 2.77 i 0.29 2.5710.34 2.6710.22 WATER-796, 797. May,1994 Gr, Beta 1.6610.47 2.1310.48 1.9010.34 WATER-931, 932 May,1994 11-3 531.26 i 109.73 554.52 1 110.55 542.89 1 77.88 WATER-893, 894 May,1994 Co-60 -1.4514.08 1.2713.23 -0.09 i 2.60 WATER-893, 894 May,1994 Cs-137 0.8512.25 1.4613.09 1.16 i 1.91 WATER-893, 894 May,1994 Gr. Beta 1.34 i 1.85 -0.2211.75 0.5611.27 WATER-893, 894 May,1994 }{-3 158.96 1 95.60 118.25 1 93.99 138.61 1 67.03 MILK-900, 901 May,1994 Co-60 -2.76 i 2.98 -1.74 i 6.09 2.25 i 3.39 MILK-900,901 May,1994 Cs-137 -0.14 i 1.31 0.54 i 1.67 0.20 i 1.06 MILK-900,901 May,1994 I131 0.10 i 0.17 0.1110.19- 0.1110.13 MILK-1001,1002 May,1994 K-40 1,250.00 1 180.00 1,370.00 i 140.00 1,310.00 1 114.02 WATER-1171,1172 May,1994 Gr. Beta 9.6912.01 7.4912.21 8.59 i 1,49 WATER-1171,1172 May,1994 11 3 950.00 1 108.00 1,012.00 1 109.00 981.00 1 76.72 MILK-1214,1215 May,1994 Co-60 0.72 2.41 0.2110.58 0.4711.24 MILK-1214,1215 May,1994 Cs-137 -0.42 i 1,47 1.4211.82 0.5011.17 MILK-1214,1215 May,1994 1131 0.1010.19 0.06 i 0.17 0.08 i 0.13 WATER-1565,1566 May,1994 Gr. Beta 2.6310.88 2.6110.91 2.6210.63 i WATER-1399,1400 May,1994 Gr. Deta 5.9710.67 5.4610.65 5.7210.47 MILK-1301,1302 May,1994 1-131(G) -0.1010.18 0.0010.18 .-0.0510.13 SEDIMEN15-1550,1551 May,1994 Gr. Beta 2.1010.10 -2.1510.10 2.13 i 0.07 WA'IER-1545,1546 May,1994 Gr. Beta 6.6310.62 5.3810.63 6.0110.44 WATER-1670,1671 May,1994 Co-60 -0.3310.55 1.3512.44 0.5111.25 WATER-1670,1671 May,1994 Cs-137 1.7312.95 -1.7312.64 0.00 i 1.98 MILK-1510,1511 May,1994 1-131(G) 0.08 i 0.13 -0.0710.12 0.0110.09 WATER 1520,1521 May,1994 11-3 48.44 1 97.26 79.871 98.52 64.16 1 69.22 MILK 1744,1745 Jun,1994 1-131 0.9010.15 0.1010.15 0.50 i 0.11 ' WATER-1786,1787 Jun,1994 Gr. Deta 31.36 i 3.13 31.37 i 2.98 31.37-i 2.16 . WATER-1786,1787 Jun,1994 Il-3 236,078.00 1 1,364.00 235,776.00 1 1,363.00 235,927.00 i 964.14 WATER-1843,1844 Jun,1994 Co-60 1.25 i 1.03 0.4812.23 0.87 i 1.23 WATER-1843,1844 Jun,1994 Cs-137 -0.02 i 1.10 1.02 i 1.79 0.50 i 1.05 WATER 1843,1844 Jun,1994 11-3 138.74 79.60 69.64 1 76.69 104.19 i 55.27 . MILK 1818,1819 Jun,1994 Co-60 -1.28 i 3.11 0.1614.48 -0.56 i 2.73 MILK-1818,1819 Jun,1994 Cs-137 0.3412.27 1.9213.45 1.1312.06 l MILK-1818,1819 Jun,1994 1-131(G) -0.1510.16 0.0410.14 -0.0610.11 WATER-1882,1883 Jun,1994 Gr. Beta 5.0010.72 5.6110.77 5.3110.53 WATER-1882,1883 Jun,1994 11-3 -32.60 1 76.90 -55.80 1 76.90 -44.20 1 54.38 ; GRASS-1900,1901 Jun,1994 Be-7 0.5110.08 0.4910.07 0.5010.05 GRASS-1900,1901 Jun,1994 K-40 4.3110.17 4.28 i 0.17 4.3010.12 MILK-1982,1983 Jun,1994 1-131 0.0010.23 0.0810.13 0.0410.13 MILK-1982,1983 Jun,1994 K-40 1,562.00 i 98.00 1,553.00 116.00 1,557.50 1 75.93 - I
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1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report i' Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sarnple First Second Averaged Codes
- Date Analysis Result Result Result WATER-1972,1973 Jun,1994 Gr. Beta 25.66 i 2.41 23.67 1 2.33 24.67 1 1.68 ;
MILK 2092,2093 Jurt1994 K-40 1,430.00 1 170.00 1,430.00 i 140.00 1,430.00 i 110.11
~ WATER-2116,2117 Jurt19M C-14 -28.00 t 49.00 -9.00 i 52.00 -18.50 1 35.72 ,
. WATER-2116, 2117 Jun,1994 Gr. Alpha 0.60 i 0.50 1.1010.60 0.85 i 0.39 ;
WATER-2116, 2117 Jurt1994 Gr. Beta 8.4010.80 7.2010.70 7.80 i 0.53 ! WATER-2116,2117 Jurt1994 H3 2,544.00 1 152.00 2,522.00 1 152.00 2,533.00 1 107.48 WATER-2116,2117 Jun,1994 U-233/4 1.5410.20 1.4610.19 1.5010.14 , WATER-2116,2117 Jun,1994 U-235 0.0010.06 0.0010.06 0.0010.04 WATER-2116, 2117 Jun,1994 U-238 0.9110.16 1.0710.17 0.99 i 0.12 WATER-2198, 2199 Jun,1994 Gr. Beta 5.3110.92 5.1610.84 5.2410.62 MILK-2156,2157 Jun,1994 Co-60 -0.5113.05 1.5413.95 0.52 i 2.50 ! MILK-2156,2157 Jun,1994 Cs-137 1.27 i 3.59 1.1615.91 1.22 i 3.46 MILK-2156,2157 Jun,1994 I-131(G) -0.0810.23 0.0110.18 -0.0410.15 MILK-2194,2195 Jun,1994 I-131 0.15 i 0.32 0.0810.21 0.1210.19 WATER-2238, 2239 Jun,1994 - Gr. Deta 1.5010.63 1.68 i 0.62 1.59 i 0.44 WATER-2363, 2364 Jun,1994 Gr. Deta 69.49 1 84.03 5.89 i 81.31 37.69 i 58.46 WATER-2336, 2337 Jun,1994 Gr. Beta 6.1711.26 6.44 i 1.27 6.3110.89 I WATER 2336,2337 Jun,1994 H-3 23.60 1 80.07 -20.93 1 78.21 L34155.96 SLIME-2480, 2481 Jun,1994 Be-7 0.41 i 0.20 0.4010.17 0.4110.13 SLIME-2480, 2481 Jun,1994 Cs-137 0.0310.01 0.0310.01 0.03 i 0.01 SLIME-2480,2481 Jun,1994 K-40 1.3110.20 1.3310.19 1.32 i 0.14 MILK-2334, 2335 Jun,1994 I-131 0.0610.17 0.04 i 0.20 0.05 i 0.13 i WATER-2733, 2734 Jun,1994 Gr. Beta 1.98 i 0.45 1.57 i 0.44 1.78 i 0.31 WATER-3056, 3057 Jun,1994 Sr-89 -0.6411.05 -0.1210.76 -0.3810.65 WATER-3056, 3057 Jun,1994 Sr-90 0.47 i 0.36 0.2810.25 0.38 i 0.22 MILK-2405,2406 Jun,1994 K-40 1,730.00 1 190.00 1,710.00 1 120.00 1,720.00 112.36 WATER-2432, 2433 Jun,1994 H-3 26.85 i 81.89 123.15 1 85.91 75.00 1 59.34 WATER-3000, 3001 Jun,1994 H-3 213.35 1 86.19 192.43 i 85.32 202.99 i 60.64 WATER-2459, 2460 Jun,1994 Gr. Alpha 0.1210.20 0.02 i 0.18 0.0710.13 WATER-2459, 2460 Jurt1994 Gr. Beta 2.26 0.15 2.03 i 0.17 2.15 i 0.11 WATER-2712, 2713 Jun,1994 H-3 260.00 1 90.00 170.00 1 80.00 215.00 i 60.21 WATER-2501, 2502 Jun,1994 H-3 70.00 i 80.00 _ 137.00 1 80.00 103.50 i 56.57 ,
- WATER-2662,2663 Jun,1994 Gr. Beta 5.0110.89 5.53 i 0.88 5.2710.63 WATER-2691, 2692 Jun,1994 Gr. Dela 2.41 i 0.52 2.1210.46 2.2710.35 ,
WATER-2691, 2692 Jun,1994 H-3 192.56 1 87.03 108.28 1 83.56 150.42 i 60.33 MILK-2522,2523 Jul,1994 Co-60 5.7214.46 -3.2115.27 1.26 i 3.45 MILK-2522, 2523 Jut,1994 Cs-137 0.2213.28 2.03 i 3.29 1.13 i 2.32 MILK-2522,2523 Jul,1994 I-131(G) 0.08 i 0.20 0.0910.23 0.09 i 0.15 , WATER-2543, 2544 Jul,1994 Gr. Beta 1.1310.31 1.1110.44 1.1210.27 ; WATER-2543, 2544 Jul,1994 K-40 1.2010.12 1.2010.12 1.2010.08 WATER-2631, 2632 Jul,1994 Gr. Alpha 0.2810.87 0.8410.98 0.5610.66 - 176 !
1994 Davis-Besse Nuclear Power Station Annual Radiologx:al Emironmental Operating Report I Table A-5. In-house " duplicate" samples.
! Concentration in pCi/L' l Lab Sample First Second Averaged Codes 6 Date Analysis Result Result Result WATER-2631, 2632 Jul,1994 Gr. Beta 8.05 i 1.01 7.1310.99 7.59 i 0.71 l MILK-2863,2864 Jul,1994 I-131 0.1010.21 0.03 i 0.20 0.0710.15 l MILK-2863,2864 Jul,1994 K-40 1,360.00 1 130.00 1,450.00 1 100.00 1,405.00 1 82.01 GRASS-2754, 2755 Jul,1994 Be-7 2.1510.18 2.18 i 0.08 2.1710.10 GRASS-2754,2755 Jul,1994 K-40 7.2910.35- 6.9310.16 7.1110.19 ;
E WATER-2775, 2776 Jul,1994 Co.60 -0.53 i 3.13 0.30 i 3.26 -0.1212.26' WATER-2775, 2776 Jul,1994 Cs-134 0.7613.35- -1.03 i 3.16 -0.9012.30 WATER-2775, 2776 Jul,1994 Cs-137 1.9413.03 0.6512.91 1.3012.10 : WATER-2775, 2776 Jul,1994 Gr. Beta 3.0310.52 2.94 :t 0.54 2.9910.37 r WATER-2775, 2776 Jul,1994 I-131 0.0110.15 0.0710.20 0.0410.13 [ MILK-2889,2890 Jul,1994 1-131 0.1110.21 0.1510.22 0.1310.15 - WATER-2842, 2843 Jul,1994 Gr. Beta 3.97 i 1.14 5.20 i 1.19 4.59 i 0.82 i WATER-2842, 2843 Jul,1994 11-3 65.78 1 83.65 32.30 1 82.23 49.04 1 58.65 [ WATER-2910, 2911 Jul,1994 Gr. Deta 1.58 i 0.44 1.4810.45 1.53 i 0.31 l 146.79 1 85.57 110.83 i S9.46 I WATER-2910, 2911 Jul,1994 11-3 74.86 1 82.57 WATER-2930, 2931 Jul,1994 Gr. Beta 1.6610.56 2.19 i 0.58 1.93 i 0.40 MILK-2958,2959 Jul,1994 I-131 -0.07 i 0.24 -0.0610.24 -0.07i 0.17 ; K-40 1,445.00 i 122.00 1,445.00 1 134.00 1.445.00 1 90.61 i MILK-2958,2959 Jul,1994
.si!LK-3010,3011 Jul,1994 Sr-89 0.54 i 1.01 -0.3610.73 -0.4510.62 ;
i MILK-3010,3011 Jul,1994 Sr-90 1.64 i 0.55 1.3410.39 1.49 i 0.34 WATER-3031, 3032 Jul,1994 1-131 0.2310.24 0.24 i 0.28 0.2410.18 ! MILK-3083,3084 Jul,1994 1-131 0.2110.22 0.08 0.22 0.1510.16 MILK-3083,3084 Jul,1994 K-40 1,420.00 1 170.00 1,380.00 i l50.00 1,400.00 1 113.36 ; WATER-3106, 3107 Jul,1994 11-3 79.09 i 80.43 98.42 i 81.27 88.76 i 57.17 WATER-3154,3155 Jul,1994 G r. Deta 1.7310.76 2.2010.78 1.97 i 0.54 l URINE-3748, 3749 Jul,1994 C-14 76.00 i 83.00 74.00 1 96.00 75.00 i 63.45 l URINE-3748, 3749 Jul,1994 Gr. Alpha 0.30 i 2.30 2.10 i 2.50 1.2011.70 t URINE-3748, 3749 Jul,1994 Gr. Beta 3.9012.50 3.30 i 2.70 3.60 i 1.84 ; URINE-3748, 3749 Jul,1994 11-3 175.00 1 583.00 198.00 i 584.00 186.50 1 412.60 WATER 3209,3210 Jul,1994 II 3 -25.26 i 82.29 0.87 i 83.39 -12.20 i 58.58 WATER-3234, 3235 Jul,1994 11-3 7.67 1 82.81 -38.33 1 80.82 -15.33 1 57.86 WATER-3261,3262 Jul,1994 Gr. Beta 4.4210.82 4.7910.87 4.61 i 0.60 WATER-3310, 3311 'Jul,1994 Gr. Beta 2.60 i 1.30 1.40 i 1.20 2.0010.88 VEGETATION 3403,3404 Jul,1994 K-40 3.38 0.41 3.5010.44 3.4410.30 t WATER-3469, 3470 Jul,1994 H-3 563.13 i 99.60 510.56 i 97.74 536.85 i 69.77 l WATER-3811, 3812 Jul,1994 Co-60 5.5714.23 0.1212.26 2.8512.40 WATER-3811, 3812 Jul,1994 Cs-137 2.9313.99 -0.3512.27 1.2912.30 WATER-3358, 3359 Jul,1994 180.00 1 100.00 200.00 1 100.00 190.00 1 70.71 11-3 [ WNIT;R-3559, 3560 Aug,1994 Gr. Beta 2.1010.78 1.4110.74 1.7610.54 , l GRASS-3586, 3587 Aug,1994 Be-7 3.5210.51 3.68 i 0.51 3.6010.36 , GRASS-3586, 3587 Aug,1994 Gr. Beta 7.4210.25 7.07 0.23 7.25 0.17 (
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177 i
1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sarnple First Second Averaged l Codes
- Date Analysis Result Result Result GRASS-3586, 3587 Aug,1994 K-40 7.39 i 0.78 7.07 i 0.79 7.2310.56 GRASS-3586, 3587 Aug,1994 Sr-89 0.0010.01 0.0010.01 0.0010.01 GRASS-3586, 3587 Aug,1994 Sr-90 0.00 i 0.00 0.00 i 0.00 0.0010.00 WATER-3611, 3612 Aug,1994 Gr. Deta 1.8710.57 2.02 i 0.49 1.95 i 0.38 MILK-3942,3943 Aug,1994 1-131 -0.1410.23 0.18 i 0.25 0.0210.17 MILK-3942,3943 Aug,1994 K-40 1,544.00 1 128.00 1,416.00 1 191.00 1,480.00 1 114.%
WATER-3638, 3639 Aug,1994 H-3 147.41 1 86.26 38.61 i 81.71 93.01 1 59.41 WATER-3683, 3684 Aug,19N H-3 7.07 i 80.96 38.90 1 82.34 22.99 i 57.74 WATER-3727, 3728 Aug.1904 Gr. Beta 4.4710.77 4.82 i 0.84 4.6510.57 MILK-3842,3843 ' q,,1994 K-40 1,419.00 i 120.00 1,411.00 i 142.00 1,415.00 i 92.96 WATER-3869, 3870 Aug,1994 G r. Ucta 4.1510.67 3.1510.64 3.65 i 0.46 WATER-3869, 3870 Aug,1994 H-3 43.82 81.84 33.30 i 81.38 38.56 i 57.71 VEGETATION-3892,3893 Aug,1994 Gr. Beta 2.4910.08 2.5410.08 2.5210.% VEGETATION-3892,3893 Aug,1994 K-40 1.8910.26 2.27 i 0.28 2.0810.19 WATER-3964, 3965 Aug,1994 Gr. Beta 3.9110.73 4.9010.83 4.4110.55 WATER-3913, 3914 Aug,1994 Gr. Beta 4.26 0.83 3.8410.73 4.0510.55 WATER-3991, 3992 Aug,1994 Tc-99 84.90 i 9.30 96.40 i 9.90 90.65 1 6.79 MILK-4016, 4017 Aug,1994 Co-60 0.9613.58 -0.9010.43 0.03 i 1.80 MILK-4016,4017 Aug,1994 Cs-137 -0.30 2.66 2.33 i 3.87 1.02 i 2.35 M1LK-4016,4017 Aug,1994 I131 0.17 i 0.22 0.0410.23 0.1110.16 MILK-4040,4041 Aug,1994 Sr-89 0.91 i 1.05 -0.0510.82 0.43 i 0.67 M1LK-4010, 4041 Aug,1994 Sr-90 0.92 i 0.45 1.05 i 0.40 0.99 i 0.30 MILK-4459,4460 Aug,1994 K-40 1,528.00 1 170.00 1,481.00 i 151.00 1,504.50 1 113.69 WATER-4061, 4062 Aug,1994 Gr. Deta 4.56 i 0.84 4.5710.79 4.57 i 0.58 WATER-4113, 4114 Aug,1994 Gr. Deta 1.6210.61 1.8310.64 1.7310.44 MILK-4168,4169 Aug,1994 K-40 1,300.00 1 140.00 1,390.00 1 140.00 1,345.00 1 98.99 WATER-4284,4285 Aug,1994 Gr. Beta 5.42 0.92 5.1710.89 5.30 i 0.64 WATER-4504, 4505 Aug,1994 H3 378.00 99.00 428.00 1 100.00 403.00 1 70.36 WATER-4259, 4260 Aug,1994 Gr. Deta 2.9210.53 2.4810.50 2.7010.36 WAThR-4308, 4309 Aug,1994 Gr. Beta 2.07 i 0.49 2.05 i 0.50 2.0610.35 WATER-4308, 4309 Aug,1994 H-3 172.74 i 88.95 148.06 1 87.97 160.40 1 62.55 WATER-4333, 4334 Aug,1994 Gr. Beta 5.1312.14 4.0712.03 4.6011.47 WATER-4333, 4334 Aug,1994 H-3 161.29 1 87.44 ~97.95 1 84.86 129.62 1 60.92 VEGETATION-4402,4403 Aug,1994 K-40 2.7310.12 2.9510.96 2.8410.48 MILK-4459, 4460 Aug,1994 K-40 1,528.00 i l70.00 1,481.00 1 151.00 1,504.50 1 113.69 WATER-4475, 4476 Aug,1994 Gr. Deta 2.8010.28 2.85 i 0.27 2.8310.19 WATER-4475, 4476 Aug,1994 H-3 51.05 i 80.26 56.34 i 80.50 53.70 i 56.84 MILK-4423,4424 Sep,1994 CMO -0.96 5.00 -0.8814.05 -0.9213.22 MILK-4423, 4424 Sep,1994 Cs-137 0.70 4.06 -0.6412.83 0.0312.47 MILK-4423,4424 Sep,1994 1-131 0.21 0.23 0.22 0.23 0.22 i 0.16 i WATER-4446, 4447 Sep,1944 H-3 186.23 88.96 223.36 i 90.42 204.80 i 63.42 , I l l 178 l
1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report j l Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged ; Codes
- Date Analysis Result Result Result i MILK-4525,4526 Sep,1994 Co-60 2.8013.47 1.2312.86 2.0212.25 MILK-4525,4526 Sep,1994 Cs-137 0.39 i 3.22 1.2712.36 0.83 i 2.00 MILK-4525, 4526 Sep,1994 I-131 0.16 i 0.26 -0.05 i 0.25 0.% 1 0.18 WATER-4571, 4572 Sep,1994 Gr. Deta 0.09 i 0.22 0.12 i 0.23 0.1110.16 WATER-4571, 4572 Sep,1994 K-40 7.20 i 1.00 7.20 i 1.00 7.20 i 0.71 WATER-3636, 3637 Sep,1994 11-3 445.19 i 99.02 529.66 i 101.98 487.43 1 71.07 MILK-4550, 4551 Sep,1994 I131 -0.0110.24 0.2510.28 0.1210.18 MILK-4550,4551 Sep,1994 K-40 1,410.90 1 109.00 1,398.10 i l55.00 1,404.50 1 94.74 SLUDGE-4613, 4614 Sep,1994 Ra-226 1.38 i 0.04 1.39 i 0.05 1.3910.03 WATER-4810,4811 Sep,1994 11-3 36,966.34 1 557.20 37,782.99 1 563.06 37,374.67 1 396.08 WATER-4688, 4689 Sep,1994 11-3 62.771 82.11 -9.391 78.95 26.69 1 56.95 MILK-4886, 4887 Sep,1994 1-131 -0.0410.25 -0.0610.24 -0.0510.17 MILK-4886, 4887 Sep,1994 K-40 1,397.90 i 152.00 1,319.00 i 171.00 1,358.45 i 114.40 WATER-4744, 4745 Sep,1994 Gr. Alpha 7.1012.30 7.6012.20 7.35 i 1.59 WATER.4744, 4745 Sep,1994 Gr. Beta 16.401 1.70 16.00 1 1.70 16.20 i 1.20 SEDIMENE-6570, 6571 Sep,1994 K-40 7.8010.59 7.6810.56 7.7410.41 MILK-4934,4935 Sep,1994 K-40 1,519.50 i 170.00 1,421.30 i 190.00 1,470.40 i 127.48 SEDIMENT-5000, 5001 Sep,1994 Gr. Deta 8.5712.00 8.57 i 2.00 8.571141 MILK-5022, 5023 Sep,1994 1-131 0.1710.19 0.2910.33 0.2310.19 VEGETATION-5253,5254 Sep,1994 Sr-89 0.0010.00 0.00 i 0.00 0.00 0.00 VEGETATION 5253,5254 Sep,1994 Sr-90 0.0010.00 0.0010.00 0.0010.00 WATER-5952, 5953 Sep,1994 Co-60 1.7312.46 1.1512.36 1.44 i 1.70 WATER-5952, 5953 Sep,1994 Cs-137 1.7512.38 0.32 i 2.24 1.0311.63 AIR FILTER-5348,5349 Sep,1994 Sr-89 420.10 1 11.40 439.40 1 22.00 429.75 i 12.39 F1LTER-5348,5349 Sep,1994 Sr-89 420.101 11.40 439.40 1 22.00 429.75 1 12.39 AIR FILTER-5348,5349 Sep,1994 Sr-90 5.6011.20 7.1012.00 6.35 i 1.17 F1LTER-5728, 5729 Sep,1994 Gr. Alpha -0.83 2.56 1.9012.63 0.5411.84 FILTER-5728,5729 Sep,1994 Gr. Alpha -0.8312.56 1.9012.63 0.5411.84 FILTER-5728,5729 Sep,1994 Sr-89 2.0216.30 -3.02 3.57 -0.5013.62 FILTER-5728, 5729 Sep,1994 Sr-90 0.8611.94 1.6611.26 1.26 i 1.16 WATER-5373, 5374 Sep,1994 1-I-3 565.00 1 96.00 561.00 i 96.00 563.00 i 67.88 MILK-5274, 5275 Oct,1994 1-131 0.1610.21 0.18 i 0.25 0.1710.16 SOIL-5394, 5395 Oct,1994 Bc-7 0.6610.36 0.8710.52 0.77 i 0.32 SOIL-5394, 5395 Oct,1994 Cs-137 0.24 i 0.06 0.2010.05 0.2210.04 SOIL-5394, 5395 Oct.1994 Cs-137 0.24 i 0.06 0.2010.05 0.2210.04 SOIL-5394, 5395 Oct,1994 Gr. Alpha 8.8912.52 9.72 i 2.71 9.3011.85 SOIL-5394, 5395 Oct,1994 Gr. Beta 27.15 i 2.36 27.83 1 2.24 27.49 1 1.63 SOlL-5394, 5395 Oct,1994 K-40 22.93 i 1.20 22.40 i 1.36 22.67 i 0.91 SOlL-5394, 5395 Oct,1994 Sr-89 0.0010.03 0.0210.03 0.0110.02
- OIL-5394, 5395 Oct,1994 Sr-90 0.0910.01 0.0810.01 0.0810.01 WATER-5421, 5422 Oct,1994 Gr. Beta 2.5610.53 3.54 i 0.51 3.0510.37 .
179
1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result WATER-5421, 5422 Oct,1994 K-40 0.87 i 0.09 0.9510.10 0.91 i 0.06 MILK-5527,5528 Oct,1994 Co-60 -1.11 i 3.26 0.89 i 3.88 -0.11 t 2.53 M1LK-5527,5528 Oct,1994 Cs-137 3.2112.44 -0.5513.51 1.3312.14 MILK-5527,5528 Oct,1994 I-131 0.0010.18 -0.0310.20 -0.02i 0.13 VEGETATION-5573,5574 Oct,1994 K-40 3.0010.30 2.82 i 0.37 2.9110.24 MILK-5552,5553 Oct,1994 Co-60 2.04 i 3.26 1.32 i 4.10 1.6812.62 MILK-5552, 5553 Oct,1994 Cs-134 -0.79 i 2.79 0.25 i 2.99 -0.2712.04 MILK-5552,5553 Oct,1994 Cs-137 1.0312.58 -0.5313.59 0.2512.21 MILK-5552,5553 Oct,1994 I-131 0.1010.22 -0.09 i 0.21 0.0110.15 MILK-5552,5553 Oct,1994 1-131 0.10 0.22 -0.0910.21 0.0110.15 MILK-5552,5553 Oct,1994 K-40 1,468.10 i 122.00 1,322.00 1 146.00 1,395.05 1 95.13 MILK-5552, 5553 Oct,1994 Sr-89 0.69 i 1.06 -0.08 i 0.88 0.31 i 0.69 MILK-5552,5553 Oct,1994 Sr-90 1.7310.45 1.37i o.39 1.55i o.29 WATER-5595, 5596 Oct,1994 1131 0.1310.21 0.1210.26 0.1210.17 FISH-5637, 5638 Oct,1994 Co-60 -0.06 i 1.28 -0.82 i 1.92 -0.44 i 1.15 FISII-5637, 5638 Oct,1994 Cs-137 0.27 i 1.25 2.0211.65 1.15 i 1.04 SEDIMENT-5850,5851 Oct,1994 Cs-137 0.2210.04 0.2210.05 0.2210.03 SEDIMENT-5850,5851 Oct,1994 K-40 13.53 1 0.85 12.20 1 0.85 12.871 0.60 WATER-5658, 5659 Oct,1994 Gr. Beta 7.42 i 1.07 7.9711.03 7.7010.74 WATER-5682, 5683 Oct,1994 Co-60 0.16 i 3.36 2.0113.54 1.09 i 2.44 WATER-5682, 5683 Oct,1994 Cs-137 0.23 i 3.07 0.70 i 3.68 0.47 i 2.40 WATER-5682, 5683 Oct,1994 H-3 78.63 i 76.44 -41.76 i 71.13 18.44 1 52.21 WATER-5707, 5708 Oct,1994 H-3 12,727.10 i 1,756.35 12,799.14 i 1,766.14 12,763.12 1 1,245.39 SEDIMENTS-5829,5830 Oct,1994 Co-60 0.4011.51 -0.58 i 1.68 -0.09 1.13 SEDIMENTS-5829, 5830 Oct,1994 Cs-137 0.19 i 0.04 0.1910.05 0.1910.03 GRASS-5879, 5880 Oct,1994 Uc-7 2.4010.12 2.4010.13 2.4010.09 GRASS-5879,5880 Oct,1994 K-40 6.55 i 0.22 6.5810.25 6.5610.17 VEGETATION 5903,5904 Oct,1994 K-40 3.4010.38 3.13 i 0.29 3.2610.24 VEGETATlON-5903,5904 Oct,1994 Sr-89 0.00 i 0.00 0.0010.00 0.00 i 0.00 VEGETATION-5903,5904 Oct,1994 Sr-90 0.0010.00 0.0010.00 0.0010.00 WATER-5928,5929 Oct,1994 H-3 402.89 1 94.65 446.30 i 96.23 424.59 1 67.49 WATER-6018, 6019 Oct,1994 Gr. Deta 2.4010.69 1.59 i 0.44 1.99i0.41 SEDIMENTS.6301, 6302 Oct,1994 Co-60 1.07 0.06 1.0710.06 1.07 i 0.04 SEDIMENTS-6301, 6302 Oct,1994 Cs-137 1.64 i 0.10 1.57 i 0.08 1.60 i 0.06 SEDIMENTS-6301,6302 Oct,1994 C r. Beta 11.82 i 1.72 8.28 i 1.83 10.05 i 1.26 SEDIMENTS-6301,6302 Oct,1994 Mn-54 0.7410.06 0.79 i 0.08 0.7710.05 WATER-6070, 6071 Oct,1994 1-131 0.07 i 0.22 -0.17 i 0.21 -0.05 i 0.15 WATER-6116, 6117 Oct,1994 H-3 -7.55 1 76.85 -21.48 1 76.21 -14.51 i 54.12 SEDIMENT-6256,6257 Oct,1994 Gr. Deta 5.4711.69 7.44 i 1.37 6.4611.09 SEDIMENT-6256, 6257 Oct,1994 K-40 9.34 i 0.27 9.34 i 0.29 9.3410.19 SEDIM ENT-6256, 6257 Oct,1994 Ra-226 0.1310.02 0.11 i 0.02 0.1210.01 ,
180
1994 Davis-Besse Nuclear Power Station 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
- SEDIMENT-6256,6257 Oct,1994 Ra-228 0.06 i 0.01 0.0510.01 0.0510.01 MILK-6091, 6092 Oct,1994 I-131 0.2210.24 0.0310.22 0.1210.16 WATER-6139, 6140 Oct,1994 11-3 23,478.00 i 782.00 23,509.00 1 782.00 23,493.50 i S52.96 FISII-6162, 6163 Oct,1994 Co-60 0.0010.01 0.0110.02 0.0110.01 FISII-6162, 6163 Oct,1994 Co-60 0.09 i 0.03 0.08i C.m 0.09 i 0.02 WATER-6635, 6636 Oct,1994 Co-60 1.8312.42 -0.2011.66 0.81 i 1.47 WATER-6635, 6636 Oct,1994 Cs-137 1.07 i 3.38 0.6812.25 0.8812.03 GRASS-6235, 6236 Oct,1994 De-7 1.89 i 0.14 1.9310.12 1.91 i 0.09 CRASS-6235, 6236 Oct,1994 K-40 7.0310.28 6.8010.24 6.9110.19 WATER-6277, 6278 Oct,1994 Gr. Beta 2.3810.56 2.37 i 0.56 2.3810.40 WATER-6277, 6278 Oct,1994 11-3 -4.11 79.62 66.30 1 89.86 31.10 1 60.03 WATER-6489, 6490 Oct,1994 Gr. Beta 1.9810.49 2.04 i 0.46 2.0110.34 WATER-6489, 6490 Oct,1994 11-3 742.19 106.47 763.16 i 107.15 752.68 1 75.53 WATER-6214, 6215 Oct,1994 H-3 4,466.00 1 189.00 4,595.00 i 191.00 4,530.50 i 134.35 WATER-6327, 6328 Oct,1994 11-3 131.64 1 82.83 147.29 i 83.49 139.46 i 58.80 SOIL-6447, 6448 Oct,1994 AC-228 0.7210.06 0.6810.05 0.70 i 0.04 SOIL-6447, 6448 Oct,1994 BI-212 0.6710.17 0.6710.10 0.67 i 0.10 SOIL-6447,6448 Oct,1994 BI-214 0.5210.02 0.5310.02 0.5310.02 SOIL-6447, 6448 Oct,1994 Gr. Alpha 6.54 2.67 6.62 i 2.51 6.58 i 1.83 SOIL-6447,6448 Oct,1994 Gr. Beta 21.52 i 2.41 20.61 1 2.42 21.06 1 1.71 SOIL-6447, 6448 Oct,1994 K-40 18.07 i 0.37 18.72 1 0.31 18.401 0.24 S01L-6447, 644S Oct,1994 PB-212 0.71 0.02 0.6810.02 0.7010.02 SO!L-M47, 6448 Oct,1994 PB-214 0.58 i 0.03 0.6010.03 0.59 i 0.02 SOIL-6447, 6448 Oct,1994 RA-226 1.15 i 0.17 0.9610.16 1.0610.11 SO!L-6447, 6448 Oct,1994 TL-208 0.2410.02 0.25 i 0.01 0.24 i 0.01 FISH-6372, 6373 Oct,1994 Co-60 0.00 i 0.02 0.0110.02 0.0010.01 FISI1-6372, 6373 Oct,1994 Cs-137 0.0010.01 0.0010.01 0.0010.01 WATER-6468, 6469 Oct,1994 Gr. Beta 1.7610.47 1.7910.49 1.7810.34 WATER-6468, 6469 Oct,1994 H-3 137.58 1 84.56 90.36 1 82.58 113.971 59.10 WATER-6401, 6402 Nov,1994 Gr. Beta 1.78 i 0.47 1.67 i 0.64 1.7210.40 SEDIMENTS-6422, 6423 Nov,1994 Gr. Beta 6.0610.61 6.4410.59 6.2510.42 SEDIMENTS-6422, 6423 Nov,1994 K-40 8.18 i 0.49 7.18 i 0.56 7.6810.37 SEDIMENTS-6422, 6423 Nov,1994 Sr-89 0.01 i 0.01 0.0010.02 0.0010.01 SEDIMENTS-6422, 6423 Nov,1994 Sr-90 0.00 i 0.00 0.0010.01 0.0010.00 ,
WATER-6534, 6535 Nov,1994 11-3 67.94 i 82.60 36.31 1 81.24 52.131 57.93 WATER 6614,6615 Nov,1994 Gr. Beta 4.9712.01 3.94 i 1.82 4.45 i 1.35 WATER-6614, 6615 Nov,1994 H-3 30.681 81.46 -4.05 1 79.96 13.31 1 57.07 WATER-6746, 6747 Nov,1994 II-3 2,734.00 1 176.00 2,851.00 1 178.00 2,792.50 1 125.16 WATER-6767, 676S Nov,1994 Il-3 107.00 1 83.00 95.00 1 82.00 101.00 1 58.34 WATER-6788, 6789 Nov,1994 Co-60 -1.87 2.17 -0.1613.22 -1.01 i 1.94 WATER-6788, 6789 Nov,1994 Cs-137 1.60 3 68 -1.8113.04 -0.11 2.39 . I81
}
l
- i 1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report l
]
Table A-5. In-house " duplicate" samples. l t Concentration in pCi/L' l I Lab Sample First Second ' Averaged i Codes
- Date Analysis Result Result Result j WATER-6788, 6789 Nov,1994 Gr. Beta 5.2011.30 3.0010.90 .
4.1010.79-WATER-6985,6986 - Nov,1994 Gr. Beta 2.0210.46 1.9910.48 2.0010.33 : WATER-7059,7060 Nov,1994 Gr. Beta 8.6211.30 7.6811.70 8.15 i 1.07 i WATER-7059, 7060 Nov,1994 11-3 0.001 100.12 0.00 i 100.12 0.00 1 70.79 WATER-7615, 7616 Nov,1994 Co40 1.3312.68 1.4313.14 1.38 i 2.06 'f WATER-7615,7616 Nov,1994 Cs-137 -1.6413.77 1.05 i 3.01 -0.3012.41 ! MILK-7144,7145 Nov,1994 1-131 0.24 i 0.28 0.27 i 0.32 0.2610.21 -l MILK-7144,7145 Nov,1994 K-40 1,226.80 i 161.00 1,298.20 1 152.00 1,262.50 1 110.71 ; MILK-7144,7145 Nov,1994 Sr-89 0.5210.73 -0.4710.75 0.0310.52 j MILK-7144,7145 Nov,1994 Sr-90 0.7910.40 1.12 i 0.46 0.96 i 0.30 ! f SOIL-7193,7194 Nov,1994 Cs-137 0.08 0.04 0.09 i 0.03 0.09 i 0.02 SO!L-7193, 7194 Nov,1994 Gr. Alpha 11.65 4.05 8.15 i 3.44 9.9012.66 SOIL-7193, 7194 Nov,1994 Gr. Beta 2L9612.80 18.00 1 2.63 19.98 1 1.92 SOIL-7193, 7194 Nov,1994 K-40 15.93 1 0.83 17.12 i 0.78 16.53 1 0.57 l WATER-7594, 7595 Nov,1994 Co-60 2.3813.00 -2.7113.15 -0.1712.18 l WATER-7594,7595 Nov,1994 - Cs-137 1.5212.62 1.5512.89 1.5411.95 l GRASS-7246, 7247 Nov,1994 Be-7 5.2510.19 5.3010.21 5.2710.14 i GRASS-7246,7247 Nov,1994 K-40 5.7610.29 5.9610.35 5.8610.23 , WATER-7367, 7368 Nov,1994 Gr. Beta 6.0010.61 4.9310.51 .5.46i 0.40 } WATER-7367, 7368 Nov,1994 11-3 -67.81 i 80.94 -98.69 79.54 -83.25 i 56.74 ! WATER-7288, 7289 Dec,1994 Gr. Beta 2.2110.72 2.5710.73 2.3910.52 { WATER-7330, 7331 Dec,1994 Co-60 -0.2912.79 -0.97 i 2.68 -0.63 i l.93 [ WATER-7330,7331 Dec,1994 Cs-137 1.37 i 2.82 1.2212.44 1.3011.86 l WATER-7330,7331 Dec,1994 Gr. Beta 2.55 i 0.75 2.3810.77 2.4610.54 MILK-7391,7392 Dec,1994 1-131(G) 1.57 1.2.82 -2.9614.55 -0.7012.68 WATER-7536,7537 Dec,1994 H-3 142.34 i 83.52 61.00 1 79.84 101.67 1 57.77 ) WATER 7639,7640 Dec,1994 Gr. Beta 5.52 i 0.83 4.8310.77 5.18 i 0.57 ! WATER-7639, 7640 Dec,1994 H3 60.871 82.65 23.60 1 80.95 42.241 57.84 WATER-7691, 7692 Dec,1994 11 3 117.13 1 84.51 89.901 83.26 103.51 1 59.32 WATER-7838, 7839 Dec,1994 Co-60 3.8112.82 -0.32 i 2.18 1.74 i 1.78 ; WATER-7838,7839 Dec,1994 Cs-137 1.16 i 2.94 -0.2412.72 0.4612.00 ; WATER-7838, 7839 Dec,1994 Gr. Beta 2.6810.83 3.8810.96 3.28 i 0.63 WATER-7940,7941 Dec,1994 Gr. Deta 1.9610.42 2.3910.46 2.1810.31 f MILK-7889, 7890 Dec,1994 K-40 1,468.10 i 191.00 1,373.20 1 160.00 1,420.65 1 124.58 l WATER-7961, 7962 Dec,1994 Gr.Deta 2.01 i 1.06 2.5711.06 2.29 i 0.75 -i WATER-7961, 7962 Dec,1994 11-3 49.77 1 82.72 -9.951 79.98 19,91 1 57.53 j WATER-8107, 8108 Dec,1994 Gr. Alpha 0.2610.77 0.5910.82 0.4310.56 ! WA'ITR-8107, 8108 Dec,1994 Gr. Beta 1.21 i 0.69 1.54 0.69 1.3810.49 I WATER-8086, 6087 Dec,1994 Gr. Beta 3.3010.64 2.511037 2.9110.43 WATER.8009, 6010 Dec,1994 11-3 71.38 1 82.32 11.79 1 79.58 -41.59 1 57.25 l l i 182 !
1994 Davis-Besse Nuclear Power Station Annual Radio!ogical Emironmental Operating Report f t 1 i l' 1 APPENDIX B Data Reporting Conventions i 1 l l i I f 183
L 1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report Data Reporting Conventions 1.0 All activities except gross alpha and gross beta are decay corrected to collection time or the end of the collection period. 2.0 Single Measurements Each single measurement is reported as follows: xts where x = value of the measurement; ; s = 2a counting uncertainty (corresponding to the 95% confidence level). In cases where the activity is found to be below the lower limit of detection L it is reported as
<L where L = the lower limit of detection based on 4.66a uncertainty for a background sample.
3.0 Duplicate analyses 3.1 Individual results: xi i st x1 i s2 Eeported result: xis where x = (1/2)(xi ix2) 2 2 s = (1/2) s3 + s2 3.2 individual results: <Li
<L2 Reported result: <L where L = lower of Li and L2 3.3 Individual results: x s
<L Esported result: xi s if x 2 L;
<L otherwise -
184
1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report 4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation (s) of a set of n numbers x1, x2. . . xn are defined as follows: 1 R=5 T,x f (I- x,)'
,,) n-1 4.2 Values below the highest lower limit of detection are not included in ,
the average. 4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported. , t 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 off to 11.44. 4.5.2. If the figure following those to be retained is greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example,11.446 is rounded off to 11.45. 4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure five is dropped, and the last-place figure retained is increased by one if it is an odd number or it is kept unchanged if an even number. As an example,11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42. e*-
1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report P i l APPENDIX C c Emuent Concentration Limit of . f Radioactivity in Air and Water Above Natural i Background in Unrestricted Areas ! l i I k L l t i 186 i
1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Repoh Table C-1 Effluent Concentration Limit of Radioactivity in Air and Water . l Above Natural Background in Unrestricted Areas' t Air Water Gross Alpha 1E-03 pCi/m' Strontium-89 8,000 pCi/l Gross Beta i pCi/m' Strontium-90 500 pCi/l e lodine-131 6 2.86E-01 pCi/m' Cesium-137 1,000 pCi/l Barium-140 8,000 pCi/l lodine-131 1,000 pCi/l Potassium-40' 4,000 pCi/l Gross Alpha 2 pCi/l Gross Beta 100 pCi/l Tritium 1x10' pCi/l a Taken from Code of Fedecral Regulation Title 10 Part 20, Table Il and appropriate footnotes. Concentrations may be averaged over a period not greater than one year. b From 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting from the air grass-cow child pathway. c A natural radionuclide. , f t 187
e , li < 7:- , -- { , t . . i
' 1994 Davis-Besse Nuclear Power Station Annual Ra&ological Environmental Operating Report i i
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Appendix D -! j REMP Sampling Summary i
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1994 Divis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Report , Table 4.5 Radiological F.nvironmental Morutonng Prograin Summary. Name of Taoisty Davis-Besse Nudear Power Station Dxket No. 50-346 Locationof Faalsty Ortawa, Ohio Reportmg Period January - December 1994 (County, State)
~
Indicator location with linghest Control Number ' Sample Type and locations Quarterly Mean locations Non-
~
Type Number of LLob Mean (F)C Mean (F)C Mean (F)c Routine : (Unsts) Analyws' Rang,c locationd Rangec Range Results' Airtome CB 520 0 005 0.020 (312/312) T-8,9,11 0.021 (156/156) 0 021 (208/208) O particulates (0 008 4 040) Alllocations had (0 009 4 039) (0.00&.0.041) (pCi/m3) identical means Sr49 0 0009 <LLD - -
<tLD 0 St-90 0 0005 <LLD - - <LLD 0 GS 40 ,
Uc-7 0015 0 075 (24/24) T-9,12 0 084 (8/8) 0 082 (16/16) 0 (0 064 4 095) Both hwations had (0 075 4 094) (0 067 4 094) i identical means D40 0.058 <LLD - - <LLD 0 Nt>95 0 0023 <LLD - - <LLD 0 Zr-95 0.0039 <LLD - - <LLD 0 i Ru 103 0.0023 <LLD - - <LLD 0 Ru.106 0.016 <LLD - - < LID 0 Cs 134 0.0023 <LLD - - <LLD 0 Cs-137 0 0024 <LLD - - <LLD 0 Cc 141 0.0026 <LLD - - <LLD 0 Cc-144 0 0094 <LLD - - <LLD 0 Airtorne hune I-131 520 0 07 <LLD - - <LLD 0 ([<i/m 3) ILD (Quarterly) Camma 298 1.0 135 (254/254) T-8 Farm. 18.7 (4/4) 143(44/44) 0 (mR/91 days) (5 0-20.4) 2.7 mi WSW (18.1 20.3) (9.2-18 6) TLD(Quarterly) Camma 4 to 54(4/4) - - None 0 (mR/91 days) (4.7-5.7) (Shield) TLD (Annual) Gamma 71 1.0 49.8 ((4 /60) T-8 Farm, 74 6 (1/1) 52.0 (1I/11) 0 (mR/365 days) (281746) 2.7 mi WSW (400430) 11.D (Annual) Gamma 1 10 230(t/1) - - None 0 (mR/365 days) (%cid) mA 189
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1994 Dovis-Desse Nuclear Pover Station . Annual Radiological Environmental Operating Report i Table 4.5 Radiological Environrnental Monitonng Program Summary. Nameof Facility Davis-Besse Nudear Power Station Dochet No. 50-346 location of Fac21ity Ottawa, Ohio Reporting Period January December 1994 (County, State) s Indacator Location with Rghest Control Number l Sample Type and Locations Quarterly Mean locations Non-Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c Routine , (Units) Analyus' hnge c Locationd RangeC Fange ResultsC f Milk (pCi/L) I.131 13 05 none - - <LLD 0 Sr + < 13 07 none - -
<tLD 0 Sr 40 13 0.5 none T-24, Sandusky, 1.4 (13/13) 1.4 (13/13) 0 21.0 mi SE (0.7-3.2) (0.7-3.2) !
t GS 13 i K-40 100 none T-24, Sandusky, 1360 (13/13) 1360 (13/13) 0 21O mise (1100-1460) (1100-1460) Cs-137 10 none - -
<LLD 0 Ba-La.140 10 none - -
<LLD 0 (g/L) Ca 13 050 none T-24, Sandusky, 0.86 (13/13) 0.86 (13/13) 0 21.0 mi SE (9.78-0.97) (0.78497)
(g/L) K (stable) 13 0 04 none T-24, Sandusky, 157(13/13) 157(13/13) 0 21.0 mi SE (1.27-1.69) (1.27-1.69) (pCi/g) St-90/Ca 13 036 none T-24,Sandusky, 1.68 (13/13) 1.68 (13/13) 0 21.0 mi SE (0.79-3.60) (0.79-3.60) (pCi/g) Cs 137/K 13 7.87 none - - <LLD 0 Ground Water GB (SS) 3 0.7 (LLD - - <LLD 0 (pCi/L) GB (DS) 3 15 3.2 (2/2) T-54, Farm, 3.2 (1/1) <tLD 0 (3.1 3.2) 4.8 mi SW CB (TR) 12 L8 33(8/8) T-54, Farm 4.2 (4/4) 4.0 (2/4) 0 (2.2-6.6) 4.8 mi SW (3.2-6.6) (2.7-53) 11 3 12 330 (LLD - -
<LLD 0 St89 12 1.1 (LLD - - (LLD 0 Sr-90 12 0.7 0.8 (1/8) T-7, Sand Beach, 0.8 (1/4) <LLD 0 09 mi NW CS 12 Mn 54 15 < tI D - - <LLD 0 f e-59 30 <LLD
- - <tLD 0 Co66 15 <tLD - - <LLD 0 c
Co44 15 <LLD - - <LLD 0 Zn46 30 <t t D - -
<tLD 0 ,
7245 15 <!!D - - <LLD 0 190
1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report Table 45 Radological Envuonmental Morutonng Program Summary. Davis-Besse Nudcar Power Station Docket No. 50-346 Name of Facilsty locabon of Facility ottawa, Ohio Reporting Period January - December 1994 (County, State) Indicator 1.ocation with Highest Control Number locations Quarterly Mean Locations Non-Sample Type and Routine Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c (Units) Analyws' Rangec locationd Rangec Range Results'
<LLD - - <LLD 0 C&134 10 Ground Water (pC6/L) <LLD 0 (amtmurd) C>l37 10 <LLD - -
<LLD - <LLD 0 Ba-La 140 15 Edible Meat CS 3
(;C/g wet) T 31,Onsite Rovmg 2.74 (1/1) 2 04 (1/1) 0 K-40 01 2.70 (2/2) (2 67-2.74) location
<LI D - - <LLD 0 Cs137 0 012
<LLD - - <tLD 0 Fruits and Sr.49 4 0 0020 Vegetables 0 0014 (t /2) 0 4 0 0008 OtoM (1/2) T-23, S. Bass istand. 0 0014 (1/1)
(pCi/g wet) Sr-90 143 mi ENE
<LLD - - <LLD 0 l131 4 0 017 GS 4 T-23,S. Bass Island, 2.47 (1/1) 2.22 (2/2) 0 K-40 030 136(2/2)
(1311.40) 143 mi ENE (I.97-2.47)
- <LLD 0 Nb-95 0.010 <LLD -
<LLD 0 Zr-95 0.017 <tLD - -
<LLD - - <LLD 0 Cs.137 0 010
- <LLD 0 Cc-141 0 025 <LLD -
- <LLD 0 Ce-144 0.10 <LLD -
<LLD 0 11 mad leaf Sr49 20 0 0067 <tLD - -
Vegetation 0 0041 (3/3) <LLD 0 (pC /g wet) Sr-90 20 0 0026 0 0037 (S/16) T-17, Site boundary, (0.0027 4 0047) 0.7mi SW (0.0028 4 0047)
- <LLD 0 1 131 20 0.028 <LLD -
CS 20 T-17, Site taandary, 336(4/4) 2.61 (4/4) 0 K40 0.1 3 34 (16/16) 0.7 mi SW (3.054 05) (1 98-2.75) (2.234 47)
- <LLD 0 Nb 95 0 034 <LLD -
- <LLD 0 Zs 95 00'l3 <LLD -
- <LLD 0 Cs 137 0 024 <LLD -
- <LLD 0 Ce 141 00% <LLD -
mn' 191
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1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Repri i i Table 4.5 Radx> logical Environrnental Monitonng Program Summary. l Name of facihty Davis-Besse Nuclear Power Station Docket No. 50-346 i locationof facility Ottawa, Ohio Reputting Period January - December 1994 3 (County, State) l 1 Indicator location voth Highest Contro! Number Sample Type and locations Quarterly Mean Locations Non-
' }
Type - Number of tipb ge,n (y)c Mean (F)C Mean (F)c Routine (Umts) a Analyses Ranger locaticad Rangec Range Results' ; i l Broad traf Ce-144 0.16 <LLD - -
<LLD 0 i Vegetation '!
(pCi/g wet) i (contmunt) . i Fr;;s CS 2 i (pCi/g wet) ; K 40 0.01 136(1/1) r 34, Offsite Roving 1 56 (1/1) 1.56 (1/1) 0 ; location, >10 mi l Nb-95 0.012 <LLD - -
<LLD 0 i
Zr45 0.026 <LLD - -
<LLD 0 I
Ru-103 0.013 <LLD - -
<LLD 0 l Ru-106 0.12 <LLD - -
<LLD 0 1 Cs-137 0.012 (LLD - -
<LLD 0 l t
Cc-141 0.024 <LLD - -
<LLD 0 j i
Cc-144 0.056 <LLD - - <LLD 0 } Arumal CS 4 i Wildide Fei i (pCi/g wet) Be-7 0.14 <LLD - -
<LLD 0 j K-40 0.1 3.08 (3/3) T-34, Offsite Roving 5.67 (1/1) 5 67 (1/1) 0 ,
(01.61-5.05) location, >10 mL Nb-95 0 011 <LLD - -
<LLD 0 I
Zr-95 0.020 <LLD - -
<LLD 0 -l Ru 103 0.019 <LLD - - <LLD 0 f Ru-106 0 05' ; <LLD - -
<LLD 0 Cs-137 0 016 <LLD - -
<LLD 0 Cc-141 0.026 <LLD - -- <LLD 0 i Cc-144 0.066 <LLD - - <LLD 0 l t
Soil CS 11 Be 7 0.45 0.59 (1/6) T-27, Crane Creek. 1.18 (1/1) 0.95 (3/5) 0 53 mi WNW (0.70-1.18) K-40 1.0 1530(6/6) T-8, I artr, 28.70 (l/1) 2122(5/5) 0 (s 98 28 70) 2.7 mi WSW (8 95-26.50) a 192
. . . . . m..w..,,. . . _ _ . _ , _ -.m___... , . ~ ~ . , . - . . . _ . , , . , , , , . . . . . _ . , , , . , _ , . ,
4 I 1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report Table 45 Radiological Environmental Monitonng Prograrn Summary. Nameof Fanlity Davis-Besse Nudear Power Station Dockt No. 50-346 tocation of Taolity Ottawa, Ohio Reportmg Period January - December 1994 (County, State) Indicator Location with Highest Control Number Sample Type and Locations Quarterly Mean locations Non-Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analyws' Ranre c locationd Range t Range Results* Soil Nb-95 0 067 <tLD - -
<LLD 0 (pCi/g dry)
(contmurd) Zr-95 0 076 <LLD - -
<LLD 0 Ru-103 0 043 <tLD - -
<LLD 0 Ru-106 0.32 <tLD - -
<LLD 0 Cs-137 0 043 0 24 (5/6) T 9, Oak I{ arbor, 0.85 (1/1) 0 48 (5/5) 0 (0050049) 6 8 rru SW (022-065)
Ce-141 O wl <LLD - - (LLD 0 Cc-144 0.24 <LLD - -
<LLD 0 Treated CB (SS) 12 04 <LLD - -
<LLD 0 Surface Water (pCi/L) GB (US) 12 1.0 25(6/6) T-144, Creon Cove 2.6 (2/2) 2.1 (6/6) 0 (2.2 2.7) Cond.,0.9 mi NNW (2.6-2.7) (15-2.8)
GB (TR) 63 1.0 2.1 (36/36) T-11, Port Clinton 2.4 (12/12) 2.1 (27/27) 0 (1.1-2.8) Water Treatment (1.9 4.6) (I M 6) Plant,95 mise l{-3 21 330 336 (1/12) T 11, Port Cinton 898 (1/4) 898 (1/9) 0 Water Treatment Plant,95 mi. SE Sr49 21 1.6 <LLD - -
<LLD 0 Sr-90 21 0.7 0.8 (1/12) T 144, Green Cove 0.8 (1/4) <LLD 0 Cond,0.9 mi NNW CS 21 Mn-54 15 <LLD - - <LLD 0 T+59 30 <LLD - -
<LLD 0 Co.58 15 <LLD - -
<LLD 0 Co-60 15 <LLD - - <LLD 0 Zn-65 30 <LLD - - <LLD 0 Zr-95 15 <!LD - - <LLD 0 Cs-134 10 <tLD - - <tLD 0 Cs-137 10 <llD - -
<LLD 0 Ita-La.140 15 < t LD - -
<LLD 0 oE 193
c 1994 Davis-Besse Nuclear Power Station Annual Radiological Emironmental Operating Repott , I Table 45 Radiological Envuunmental Monitoting Program Suminary. j Name of racility - Davis-Besse Nudear Power Station Docket No. 50-346 locatx>n of radlity Ottawa, Ohio f Reporting Period January December 1994 (County, State) l todgator Location with Highest Control I Number Sample Type and locations Quarterl Mean 1 Locations Non- i T Number of LLob Mean (F)C Routine Mean (F)C Mean (F)c ; (U tS) Analyses
- locationd hg
_ Rangec %f h ge Untreated CB (SS) 12 04 <LLD T-12, Intake , 08(1/2) 0.8 (1/6) 0 Surface Water 11.25 mi NW t (pCi/L) j GB (DS) 12 10 2.6 (6/6) T-12, Intake , 3.4 (2/2) 2.7 (6/6) 0 - (23-3.4) 11.25 mi NW (2.4-4.5) (1.9-4 3) GB (TR) 123 1.0 2.6 (72/72) T-152, 3.1 (6/6) 2 3 (51/51) 0 (15-43) Canal Entrance to (23-43) (15-5.3) Maumee Bay S.P-15 6 mi. WNW H.3 123 130 633 (14/72) T 135, Lake Ene, 1256 (1/6) 417 (3/51) 0 (342-1256) 2.5 mi WNW (338-524)
!ir.89 21 1.2 <LLD - -
<LLD 0 Lir-90 21 0.7 0.7 (1/12) T-11,50 0.7 (2/8) 0.7 (1/9) O Both locations had identical means Gi 123 Mn-54 15 <LLD - -
<LLD 0 Fe-59 30 <LLD - -
<tLD 0 Co-58 15 <LLD - -
<LLD 0 Co-60 15 <LLD - -
<LLD 0 Zn-65 30 <LLD - -
<LLD 0 Zr-95 15 <LLD - -
<LLD 0 Cs-134 10 <LLD - -
<LLD 0 Cs-137 10 <LLD - -
<LLD 0 Ba-12 140 15 <LLD - -
<LLD 0 lish GB 6 0.1 335(3/3) T-35, Lake Ene, 3 44 (3/3) 3.44 (3/3) 0 (pCi/g wet) (2.454 08) > 10 mi. radius (2.90-3.94) (2.90-3.94)
GS- 6 K-40 0.1 2.87 (3/3) T 33,33 2.87 (6/6) 2.87 (3/3) 0 (2.33-3 45) Both locations had (233345) (2.59-3 42) identical means Mn 54 0 012 <LLD - -
<LLD 0 fe-59 0 049 <LLD - -
<LLD 0 Co-58 0 019 <LLD - -
<LLD 0 con) 0 018 <LLD - -
<LLD 0 194
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1994 Davis-Besse Nuclear Power Station Annual Radiological Environmental Operating Report Table 45 Radiological Environmental Morutonng Program Summary. Name of Fac Isty Davis-Besse Nuclear Power Station Docket No. 50 346 l taation of Fachty Ottawa, Ohio Reportmg Penod ' January - December 1994 ! I (County, State) Indicator location with Highest Control Number , Sample Type and locations Quarterly Mean locations Non- J Type Number of Ltob Mean (F)C Mean (F)C Mean (F)c Routine l (Units) Analyses a RangeC locatWnd Rangec Range Results' j Fish Zn-65 0.037 <tLD - - <LLD 0 l (pCi/g wet) e tcontmurd) l Cs-134 0 020 <LLD - - <LLD 0 [ Cs 137 0 025 <LLD - -
<LLD 0 i
Shorchne G 8 Sediments . 0 (pCi/g dry) E-40 01 16.93 (6/6) T-4, Site Boundary, 19 33(2/2) 13% (2/2) l 14 72-23 45) 0.8 mi S (l5 21-2345) (13.25-14.66)
<LLD <LLD 0 Mn-54 0 050 - -
( Co-58 ' "
<LLD 0 !
0 073 <LLD I Co-60 0.070 <LLD - - <LLD 0 l Cs.134 0.089 <LLD - - <LLD 0 { l Cs-137 0.074 0.14 (1/6) T-132,IAc Erie, 0 14 (1/1) <LLD 0 l 1.0 mi E f a GB = gnus teta, CS = gamma scan, SS = suspended solids, DS = dissolved solids,TR = total residue. j b LLD = nominallower hmit of detection based on 4.66 sigma counting error for background sample. l C Mean based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in ! r parentheses (F). d locatmns are specified by station code (Table 4.1) and distance (miles) and direct 2on relative to reactor site. l
' Non-routine results are those which excm3 ten times the control station value. {
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l l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Radiological linvironmental Monitoring Program Sample Analysis Results for Davis-Besse Nuclear Power Station January 1,1994 to December 31,1994 Prepared by: Radiation Protection Section Davis-Besse Nuclear Power Station Toledo Edison Company Toledo, Ohio April 1995 ;
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IDLEDQ ; i 4 LIST OF TABLES l I i
' N2. Ii11e East !
1 Airbome particulates and iodine collected at Location T-1, analysis for ! gross beta and lodine-131. . .... ... .. ... .... .. .. .... . ........... . . . . . . . ... . .. . .. . .. .. . . . . . .. ...... 5 2 Airborne pa.3culates and iodine collected at Location T-2, analysis for [ gross beta and iodine- 131....... .. . . ... . .... .. ... . ... .. . . . .. ... . . . ...... .. . . . .............. . .. 6 i 3 Airbome particulates and iodine collected at Location T-3, at:alysis for t gross beta and iodine- 131.... .. ... . .. ... ....... . .. . . . .. . .. .. .... .. . .. .. ... ..... . .... ...... .... . 7 l 4 i Airbome particulates and iodine collected at Location T-4, analysis for j gross beta and lodine- 131. .. ... . . .. ... .. .. . .. . .... .. ... . . . .. .... . . .. . . ... . ... .... ... . . . . . . .... .. 8 5 Airbome particulates and iodine collected at Location T-7, analysis for gross beta and iodine- 131... . . . .. ... . .... ... ........ .. .. . .... ... ... ...... ........ .. .. ......... ... . 9 f i 5 Airbome particulates and iodine collected at Location T-8, analysis for j gross beta and lodine-131....... .. .. .. ... .. .............. .... ...... ....... .. .... . . . ... ....... 10 ; 7 Airbome particulates and iodine collected at Location T-9, analysis for l gross beta and iodme-131........... ...... ............... . . ...... . .... ..... . .... ... .... . ....... 11 : i b 8 Airbome particulates and iodine collected at Location T-11, analysis for l gross beta and iodine-131........... . ....... ...... ................ ........ .. . ... .. ............. 12 i 9 Airbome particulates and iodine collected at location T-12, analysis for . > gross beta and iodine- 131....... .. .......... ........... .. ................. .. ..... .... ........ ... 13 . 10 Airbome particulates and lodine collected 'ocation T-27, analysis for l gross beta and iodine-131. ...... .. . . . . ... . . .. .............. . ... ... .. . .. ..... . .. .. . .. . . . . .... .... 14 ji 11 Airbome particulate data, gross beta analyses, monthly averages, mmima and maxima, 1994................................................................................15 i i 12 Airbome particulate samples, quarterly composites by location, analyses ! for strontium-89, strontium-90 and gamma-emitting isotopes,1994.......... 21 14 Area monitors (T1.D), quarterly, 1994................................................................25 h i 15 Area monitors (TLD), annual, 1994.....................................................................28 l i I i l 16 Milk .xuples, analysis for strontium-89, strontium-90, lodine-131 and j gamma-emitting isotopes . ......... ... ............. .... .... .... ..... .......... . .. ........ ...... 31 ! 17 Milk samples, analysis for calcium, stable potassium, and ratios of strontium.90 (pCi) per gram of calcium and cesium-137 (pCi) per gram of potassium .... ..... . .... ..... .... . . ....... ...... .......... . .. ..... ...... ..... ........... .. 33
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r _ ., _ __ TOLEDO LIST OF TABLES (continued) No. Title page 18 Ground water samples, analyses for gross beta, tritium, strontium-89 and strontium-90 and gamma-emitting isotopes, quarterly collections, 199 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
.........................35 19 Domestic meat samples, analyses for gamma-emitting isotopes ....................... .. 38 20 Wild meat samples, analyses for gamma-emitting isotopes.......... ... ..... ......... 39 21 Green leafy vegetable samples, analyses for strontium-89, strontium-90, aodine-131 and gamma. emitting isotopes... ... .... . ... .... . . . . . . . . . . . .. .40 22 Fruit samples, analyses for strontium-89, strontium-90, iodine-131 and gamma-emitting isotopes . .... .. .... ..... ...... ................................42 23 Animal-wildlife feed samples, analyses for gamma-emitting isotopes...... ........ 43 24 Soil samples, analyses for gamma-emitting isotopes .... ... ..........................~....... 44 25 Treated surface water samples, monthly composites of weekly grab samples analysis for gross beta, 1994....................................................46 26 Treated surface water sampics, monthly composites of weekly grab samp!cs, analysis for gross beta, 1994..................................................52 27 Treated surface water samples, quarterly composites of weekly grab samples, analysis for tritium, strontium-89, strontium-90 and gamma-emitting isotopes, 1994.......................................................53 28 Untreated surface water samples, monthly composites of weekly grab samples, analysis for gross beta, tritium and gamma-emitting isotopes,1994..... ..... .. .. ... . . . . ... . . . . . . . . . . . . ............................55 29 Untreated surface water samples, monthly composites of weekly grab samples, analysis for gross beta, tritium and gamma-emitting isotopes, 1994..........................................................................61 30 Untreated surface water samples, quarterly composites of weekly grab samples, analysis for strontium-89 and strontium-90,1994........... . . . . . . . 62 31 Untreated surface water samples, monthly composites of weekly grab samples, analysis for gross beta, tritium, strontium-89, strontium-90 and gamma-emitting isotopes, 1994...............................................64 32 Fish samples, analyses for gross beta and gamma-emitting isotopes........... .. ..... 68 33 Shoreline sediment samples, analyses for gamma-emitting isotopes.... ........... . 70 34 Egg samples, analyses for gamma <mitting isotopes...... . . ............................72 iv
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, 1994 Davis-Besee Nuclear Power Station Annual Ra&ologmal Environmental Operating Report , 5 i Introduction l Attachment 1 to the Davis.Besse Nuclear Power Station 1994 Annual Radiological Environmental Operaating Report (AREOR) includes the results of analyses of the radiological environmenta , radiation samples taken as part of the 1994 Radiological Environmental Monitoring
. (REMP). The summaries provided in the 1994 AREOR are based on the data presented in the following tables.
i Data tabulation and sample analyses results were provided by Teledyne Brown Engineering, .-.
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Environmental Services, Midwest Laboratory in their Final Progress Report to Toledo Edison, March ! 17,1995. l
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Tor rno 2.0 LISTING OF MISSED SAMPI F4 l Expected Collection Sample Type Location Date Reason f TLD T-119 1st Qtr.,1994 TLD lost in the field. i TLD T-150 1st Qtr.,1994 TLD lost in the field. f TLD T-204 3rd Qtr.,1994 TLD lost in the field. ! 1 TLD T-150 Annual,1994 TLD lost in the field. TLD T-206 Annual,1994 TLD not placed in the field. ILD T-207 Annual,1994 TLD not placed in the field. TLD T-208 Annual,1994 TLD not placed in the field. i NOTE: Page 3 is intentionally left out. h i I l l i t I s-1 i t 2 I
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eswegeemgespy_ sage s ws wwwwo- .or.w . _ 4 4 TOI.EDO 9 3.0 DATA TABULATIONS i l 1 i i 1
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.~. ~ TOLEDO Tcble 1. Air particulate filters and charcoal canisters. Analyses: Gross beta and iodine-131 ' Location: T1 Units: pCi/m 8 Collection: Continuous, weekly exchange. Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Ecquired LLD E E 01-10-94 283 0.020 1 0.004 07-04-94 292 0.011 1 0.003 01-17-94 279 0.032 i 0.004 07-11-94 287 0.017 1 0.003 01-24-94 283 0.031 1 0.004 07-18-94 293 0.016 i 0.002 01 31-94 284 0.024 1 0.003 07-25-94 283 0.017 1 0.003 02-07-94 283 0.019 1 0.003 08-01-94 291 0.018 i 0.002 02-14-94 284 0.019 0.003 08-08-94 290 0.021 1 0.003 02-21-94 281 0.028 i 0.004 08-15-94 287 0.014 1 0.002 02-28-94 281 0.018 i 0.003 08-22-94 287 0.016 i 0.003 03-07-94 283 0.022 1 0.003 08-29-94 291 0.026 i 0.003 03.14-94 281 0.023 1 0.003 09-05-94 292 0.014 1 0.003 03-21-94 279 0.019 i 0.003 09-12-94 290 0.023 1 0.003 03-28-94 283 0.019 i 0.003 09-19-94 287 0.032 1 0.003 09-26-94 289 0.016 i 0.003 10-03-94 285 0.012 i 0.002 1st Qtr. Meants.d. 0.023 i 0.005 3rd Qtr. Meanis.d. 0.018 1 0.006 04-04-94 282 0.019 i 0.003 10-10-94 286 0.016 1 0.003 04 11-94 284 0.014 1 0.002 10-17-94 285 0.020 i 0.003 04-18-94 2 74 0.012 1 0.002 10-24-94 285 0.023 1 0.003 04-25-94 283 0.019 i 0.003 10-31-94 286 0.021 1 0.003 05-02-94 284 0.012 i 0.003 11-07-94 2eJ 0.016 i 0.003 05-09-94 281 0.017 1 0.003 11-14-94 278 0.027 1 0.004 05 16-94 284 0.012 i 0.002 11-21-94 285 0.019 i 0.003 05-23-94 283 0.009 i 0.002 11-28-94 285 0.014 0.003 05-30-94 273 0.017 i 0.003 12-04-94 284 0.029 i 0.003 06-06-94 285 0.014 1 0.002 12-12-94 285 0.018 i 0.003 06-13-94 287 0.015 1 0.003 12-19-94 269 0.024 i 0.003 06-20-94 283 0.020 i 0.003 12-26-94 262 0.040 1 0.004 06-27-94 283 0.012 i 0.003 01-02-95 257 0.028 1 0.004 2nd Qtr. Meanis.d. 0.015 1 0.003 4th Qtr. Meanis.d. 0.023 1 0.007 Cumulative Average: 0.020 Previous Annual Average: 0.020
- Iodine-131 concentrations are <0.07 pCi/m8 unless otherwise noted in Appendix C.
5
___3... - - ___._._ _ ~ _ _ . _ .__ TOLEDO Table 2 Airbome particulates and charcoal canisters . Analyses: Gross beta and iodine-131
- Location: T-2 Units: pCi/m' Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Required LLD E E 01-10-94 296 0.015 i 0.003 07-04-94 289 0.011 1 0.003 01-17-94 298 0.026 i 0.003 07-11-94 286 0.018 1 0.003 01-24-94 297 0.031 1 0.003 07-18-94 291 0.016 1 0.003 01-31-94 299 0.021 1 0.003 07-25-94 286 0.021 1 0.003 02-07-94 296 0.022 1 0.003 08-01-94 282 0.018 1 0.003 02-14-94 340 0.020 1 0.003 08-08-94 290 0.019 0.003 02-21-94 255 0.023 1 0.004 08-15-94 287 0.018 1 0.002 02-28-94 309 0.022 i 0.003 08-22-94 282 0.024 i 0.003 03-07-94 287 0.025 i 0.003 08-29-94 286 0.030 1 0.003 < 03-14-94 298 0.022 i 0.003 09-05-94 286 0.015 1 0.003 03-21-94 297 0.020 1 0.003 09-12-94 289 0.024 i 0.003 03-28-94 297 0.015 1 0.003 09-19-94 286 0.035 1 0.003 09-26-94 286 0.022 1 0.003 10-03-94 293 0.013 i 0.002 1st Qtr. Meanis.d. 0.022 i 0.004 3rd Qtr. Meanis.d. 0.020 i 0.006 04-04-94 296 0.016 1 0.003 10-10-94 288 0.017 1 0.003 04-11-94 298 0.014 i 0.002 10-17-94 286 0.022 i 0.003 04-18-94 301 0.012 1 0.002 10-24-94 285 0.022 1 0.003 04-25-94 293 0.019 i 0.003 10-31-94 279 0.021 i 0.003 05-02-94 289 0.009 i 0.003 11-07-94 284 0.020 i 0.003 05-09-94 305 0.013 1 0.002 11-14-94 280 0.025 1 0.003 05-16-94 298 0.013 i 0.002 11-21-94 286 0.018 1 0.003 05-23-94 301 0.009 i 0.002 11-28-94 287 0.020 i 0.003 05-30-94 297 0.016 1 0.003 1241-94 279 0.028 0.003 06-06-94 296 0.012 1 0.002 12-12-94 287 0.018 1 0.003 06-13-94 294 0.013 i 0.002 12-19-94 286 0.028 1 0.003 06-20-94 277 0.020 1 0.003 12-26-94 287 0.036 1 0.004 06-27-94 286 0.010 1 0.002 01-02-95 279 0.022 i 0.003 2nd Qtr. Meanis.d. 0.014 1 0.003 4th Qtr. Meanis.d. 0.023 i 0.005 Cumulative Average: 0.020 Previous Annual Average: 0.021
- 8 Iodine-131 concentrations are <0.07 pCi/m wdess otherwise noted in Appendix C.
6
TOLEDO Table 3. Air particulate filters and charcoal canisters. Analyses: Gross beta and iodine 131 *. Location: T-3 Units: pCi/m' Collection: Continuous, weekly exchange. Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Reauired LLD 041 (LQ1 01-10-94 281 0.021 1 0.004 07-04-94 280 0.010 1 0.003 01-17-94 298 0.026 i 0.003 07-11-94 285 0.015 i 0.002 01-24-94 277 0.036 i 0.904 07-18-94 285 0.016 i 0.003 01-31-94 404 0.027 i 0.003 07-25-94 285 0.019 i 0.003 02-07-94 157 0.020 i 0.005 08-01-94 308 0.017 i 0.002 02-14-94 318 0.022 i 0.003 08-08-94 283 0.017 i 0.003 02-21-94 242 0.023 i 0.004 08-15-94 285 0.016 1 0.002 02-28-94 282 0.023 i 0.003 08-22-94 285 0.015 i 0.003 03-07-94 281 0.021 i 0.003 08-29-94 308 0.028 i 0.003 03-14-94 280 0.024 i 0.003 09-05-94 285 0.015 1 0.003 03-21-94 278 0.021 1 0.003 09-12-94 292 0.022 i 0.003 03-28-94 282 0.014 1 0.003 09-19-94 294 0.032 i 0.003 09-26-94 279 0.020 1 0.003 10-03-94 288 0.015 i 0.003 1st Qtr. Meanis.d. 0.023 1 0.005 3rd Qtr. Meanis.d. 0.018 i 0.006 04-04-94 271 0.018 i 0.003 10-10-94 285 0.014 i 0.003 04-11-94 283 0.015 1 0.003 10-17-94 284 0.023 i 0.003 04-18-94 283 0.015 i 0.003 10-24-94 282 0.023 i 0.003 04-25-94 283 0.018 i 0.003 10-31-94 290 0.020 1 0.003 05-02-94 278 0.010 1 0.003 11-07-94 282 0.021 i 0.003 05-09 94 285 0.017 i 0.003 11-14-94 279 0.025 i 0.003 05-16-94 285 0.016 i 0.003 11-21-94 286 0.019 i 0.003 05-23-94 284 0.011 1 0.003 11-28-94 289 0.018 i 0.003 05-30-94 284 0.018 1 0.003 12-04-94 280 0.026 1 0.003 06-06-94 285 0.015 i 0.003 12-12-94 286 0.016 i 0.003 06-13-94 285 0.015 i 0.003 12-19-94 283 0.028 i 0.003 06-20-94 289 0.021 1 0.003 12-26-94 297 0.031 i 0.003 06-27-94 317 0.015 1 0.003 01-02-95 287 0.024 i 0.003 2nd Qtr. Meanis.d. 0.016 i 0.003 4th Qtr. Meanis.d. 0.022 1 0.005 Cumulative Average: 0.020 Previous Annual Average: 0.021
- Iodine-131 concentrations are <0.07 pCi/m' unless otherwise noted in Appendix C.
7
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IRLERQ Table 4. Air particulate filters and charcoal canisters . Analyses: Gross beta and iodine-131 *. Location: T-4 Units: pCi/m' Collection: Continuous, weekly exchange. ! Date Volume Date Volume Collected (m.3) Gross Beta Collected (m3) Gross Beta Ecquired.LLD Dal 041 01-10-94 282 0.020 1 0.004 07-04-94 289 0.012 1 0.003 01-17-94 283 0.032 i 0.004 07-11-94 291 0.016 1 0.002 01-24-94 282 0.035 1 0.004 07-18-94 288 0.014 i 0.002 01-31-94 326 0.024 i 0.003 07-25-94 286 0.016 1 0.003 02-07-94 240 0.021 1 0.004 08-01-94 288 0.017 1 0.002 02-14-94 284 0.023 i 0 004 08-08-94 287 0.020 1 0.003 02-21-94 282 0.027 1 0.004 08-15-94 287 0.017 i 0.002 02-28-94 282 0.024 i 0.003 08-22-94 288 0.023 1 0.003 03-07-94 282 0.026 1 0.003 08-29-94 288 0.028 t 0.003 03-14-94 283 0.022 1 0.003 09-05-94 288 0.014 i 0.003 03-21 94 283 0.019 i 0.003 09-12-94 291 0.020 i 0.003 03-28-94 282 0.017 1 0.003 09-19-94 288 0.032 1 0.003 09-26-94 290 0.022 t 0.003 10-03-94 290 0.009 i 0.002 l 1st Qtr. Meants.d. 0.024 i 0.005 3rd Qtr. Meanis.d. 0.019 1 0.006 04-04-94 281 0.016 1 0.003 10-10-94 295 0.017 1 0.003 04-11-94 283 0.016 1 0.003 10-17-94 284 0.025 1 0.003 04-18-94 282 0.016 i 0.003 10-24-94 284 0.025 i 0.003 04 25-94 278 0.017 i 0.003 10-31-94 284 0.021 1 0.003 05-02-94 284 0.010 i 0.003 11-07-94 286 0.022 i 0.003 05-09-94 291 0.015 1 0.003 11-14-94 283 0.028 i 0.004 05-16-94 289 0.012 1 0.002 11-21-94 204 0.020 0.003 i 05-23-94 285 0.008 1 0.002 11-28-94 284 0.016 i 0.003
- 05-30-94 288 0.018 1 0.003 12-04-94 285 0.027 1 0.003 06-06-94 288 0.014 1 0.002 12-12-94 294 0.014 1 0.003 06-13-94 289 0.015 I 0.003 12-19-94 283 0.027 1 0.003 06-20-94 288 0.021 1 0.003 12-26-94 302 0.034 1 0.003 06-27-94 288 0.010 i 0.002 01-02-95 303 0.024 1 0.003 2nd Qtr. Meas is.d. 0.014 i 0.003 4th Qtr. Meanis.d. 0.023 1 0.005 l
l l Cumulative Average: 0.020 Previous Annual Average: 0.021 8
- Iodine-131 concentrations are <0.07 pCi/m unless otherwise noted in Appendix C.
l 8
TOLEDO Table 5. Air particulate filters and charcoal canisters. Analyses: Gross beta and iodine-131 * . Location: T-7 Units: pCi/m' Collection: Continuous, weekly exchange. Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Ecquired I LD E E 01 10-94 280 0.019 i 0.004 07-04-94 269 0.014 0.003 01-17-94 274 0.028 i 0.004 07-11-94 336 0.016 0.002 01 24-94 272 0.037.i 0.004 07-18-94 285 0.013 i 0.002 01-31-94 259 0.019 i 0.003 07-25-94 280 0.016 i 0.003 02-07-94 289 0.023 i 0.003 08-01-94 290 0.016 i 0.002 02-14-94 280 0.022 i 0.004 08-08-94 299 0.021 i 0.003 02-21-94 286 0.028 i 0.004 08-15-94 284 0.017 i 0.002 02-28-94 284 0.021 1 0.003 08-22-94 280 0.021 1 0.003 03-07-94 285 0.024 1 0.003 08-29-94 285 0.028 i 0.003 03-14-94 285 0.026 i 0.003 09-05-94 285 0.011 i 0.002 03-21-94 285 0.020 1 0.003 09-12-94 285 0.024 0.003 03-28-94 285 0.021 i 0.003 09-19-94 285 0.032 i 0.003 09-26-94 285 0.016 i 0.003 10-03-94 286 0.013 i 0.003 1st Qtr. Meanis.d. 0.024 i 0.005 3rd Qtr. Meanis.d. 0.018 i 0.006 04-04-94 284 0.022 1 0.003 10-10-94 286 0.012 1 0.003 04-11-94 286 0.016 1 0.003 10-17-94 285 0.022 1 0.003 04-18-94 285 0.013 1 0.002 10-24-94 303 0.024 1 0.003 04-25-94 286 0.019 1 0.003 10-31-94 276 0.017 1 0.003 05-02-94 288 0.009 i 0.003 11-07-94 300 0.020 1 0.003 05-09-94 283 0.014 1 0.003 11-14-94 269 0.027 i 0.004 05-16-94 246 0.014 1 0.003 11-21-94 285 0.023 i 0.003 05-23-94 263 0.010 i 0 003 11-28-94 290 0.019 i 0.003 05-30-94 262 0.024 1 0.003 12-04-94 284 0.028 i 0.003 1 06-06-94 263 0.022 1 0.003 12-12-94 291 0.017 i 0.003 06-13-94 263 0.020 i 0.003 12-19-94 284 0.025 i 0.003 06-20-94 263 0.023 1 0.003 12-26-94 285 0.033 1 0.004 06-27-94 257 0.017 1 0.003 01-02-95 277 0.025 i 0.003 2nd Qtr. Meants.d. 0.017 i 0.005 4th Qtr. Meants.d. 0.022 1 0.005 Cumulative Average: 0.020 i Previous Annual Average: 0.021 l
' lodine-131 concentrations are <0.07 pCi/m' unless otherwise noted in Appendix C. I I
9 ; I
TOLEDO Tcble 6. Air particulate filters and charcoal canisters. Analyses: Gross beta and iodine-131' . Location: T-8 Units: pCi/m' Collection: Continuous, weekly exchange. Date Volume Date Volume Collected (m 3) Gross Beta Collected Gross Beta (m3) Eequired LL.Q 041 Dal 01-10-94 290 0.018 1 0.003 07 04-94 277 0.013 1 0.003 01-17-94 283 0.026 1 0.003 07-11-94 277 0.017 i 0.003 01-24-94 294 0.035 1 0.004 07-18-94 275 0.019 1 0.003 01-31-94 307 0.023 1 0.003 07-25-94 279 0.020 1 0.003 02-07-94 310 0.022 1 0.003 08-01-94 295 0.022 i 0.003 02-14-94 278 0.025 i 0.004 08-08-94 297 0.021 1 0.003 02-21-94 277 0.030 1 0.004 08-15-94 288 0.015 i 0.002 02-28-94 278 0.024 1 0.003 08-22-94 289 0.020 i 0.003 03-07-94 277 0.030 1 0.004 08-29-94 288 0.030 i 0.003 03-14-94 277 0.028 1 0.004 09-05-94 288 0.014 i 0.003 03-21-94 277 0.020 1 0.003 09-12-94 290 0.021 i 0.003 03-28-94 277 0.020 1 0.003 09-19-94 286 0.032 1 0.003 09-26-94 288 0.012 i 0.002 10-03-94 292 0.013 i 0.002 1st Qtr. Meanis.d. 0.025 1 0.005 3rd Qtr. Meands.d. 0.019 i 0.006 04-04-94 276 0.019 i 0.003 10-10-94 293 0.019 i 0.003 04-11-94 278 0.020 1 0.003 10-17-94 288 0.022 1 0.003 04-18-94 277 0.015 1 0.003 10-24-94 298 0.025 1 0.003 04-25-94 274 0.021 i 0.003 10-31-94 288 0.022 1 0.003 05-02-94 278 0.011 1 0.003 11-07-94 290 0.019 i 0.003 05-09-94 277 0.018 1 0.003 11-14-94 275 0.025 i 0.003 05-16-94 308 0.013 1 0.002 11-21-94 288 0.018 1 0.003 05-23-94 277 0.010 1 0.003 11-28-94 291 0.016 1 0.003 05-30-94 277 0.020 1 0.003 12-04-94 287 0.025 i 0.003 06-06-94 277 0.016 i 0.003 12-12-94 296 0.015 t 0.003 06-13 94 280 0.021 1 0.003 12-19-94 287 0.027 i 0.003 06-20-94 278 0.025 1 0.003 12-26-94 286 0.032 1 0.004 06-27-94 277 0.015 i 0.003 01-02-95 284 0.024 1 0.003 2nd Qtr. Meants.d. 0.017 1 0.004 4th Qtr. Meanis.d. 0.022 0.005 Cumulative Average: 0.021 j Previous Annual Average: 0.021 Iodine-131 concentrations arc <0.07 pCi/m8 unless otherwise noted in Appendix C. in
~-%_,w.. . .- -
m
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TOLEDO ~ Table 7. Air particulate filters and charcoal canisters- [ Analyses: Gross beta and iodine-131 *. ' Location: 'T-9 Units: pCi/m' Collection: Continuous, weekly exchange.
- Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Reauired r i n Q01 201 01-10-94 278 0.020 1 0.004 07-04-94 295 0.010 1 0.002 I 01-17-94 277' O.027 i 0.004 07-11-94 285 0.017 i 0.003 I 01-24-94 277 0.037 1 0.004 07-18-94 300 0.020 i 0.003 I-01-31-94 278 0.027 0.003 07-25-94 275 0.021 i 0.003 02-07-94 313 0.019 i 0.003 08-01-94 314 0.021 1 0.003 i 02-14-94 240 0.023 i 0.004 08-08-94 281 0.021 i 0.003 02-21-94 282 0.027 i 0.004 08-15-94 283 0.018 i 0.002 , .
02-28-94 283 0.023 i 0.003 08-22-94 284 0.024 i 0.003 . 03-07-94 282 0.026 i 0.003 08-29-94 284 0.031 1 0.003 ' 03-14-94 280 0.024 i 0.003 09-05-94 284 0.017 i 0.003 03-21-94 282 0.022 i 0.003 09-12-94 286 0.024 i 0.003 . 03-28-94 282 0.019 i 0.003 09-19-94 286 0.036 1 0 003 09-26-94 284 0.024 i 0.003 10-03-94 283 0.015 i 0.003 1st Qtr. Meanis.d. 0.025 i 0.005 , 3rd Qtr. Meanis.d. 0.021 1 0.006 l t 04-04-94 281 0.021 i 0.003 10-10-94 284 0.017 i 0.003 04-11-94 283 0.018 i 0.003 10-17-94 282 0.024 i 0.003 . 04-18-94 284 ' 0.014 1 0.002 10-24-94 290 0.027 i 0.003 04-25-94 284 0.021 i 0.003 10-31-94 284 0.023 i 0.003 L 05-02-94 283 0.011 i 0.003 11-07-94 285 0.023 i 0.003 05-09-94 283 0.015 i 0.003 11-14-94 273 0.015 i 0.003 , 05-16-94 288 0.013 i 0.002 11-21-94 284 0.019 i 0.003 05-23-94 300 0.013 i 0.003 11-28-94 284 0.019 1 0.003 05-30-94 ' 285 0.018 i 0.003 12-04-94 283 0.028 1 0.003 06-06-94 299 0.016 i 0.002 12-12-94 297 0.013 i 0.003 , 06-13-94 266 0.021 1 0.003 12-19-94 280 0.026 i 0.003 06-20-94 334 0.023 i 0.003 12-26-94 281 0.035 i 0.004 06-27 94 248 0.012 i 0.003 01-02-95 284 0.021 1 0.003 2nd Qtr. Meants.d. 0.017 i 0.034 4di Qtr. Meanis.d. 0 022 1 0.006 i i Cumulative Average: 0.021 Previous Annual Average: 0.022 i
- Iodine-131 concentrations are <0.07 pCi/m8 unless otherwise noted in Appendix C.
1 11 I
TOLEDO' Table 8. Air particulate filters and charcoal canisters. Analyses: Gross beta and iodine-131 *. location: T-11 Units: pCi/m' Collection: Continuous, weekly exchange. Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Ecquired t.tn 0.01 Dal 01-10-94 289 0.016 i 0.003 07-04-94 272 0.012 1 0.003 01-17-94 288 0.030 1 0.004 07-11-94 282 0.015 i 0.002 01-24-94 280 0.039 i 0.004 07 18-94 283 0.020 1 0.003 01-31-94 281 0.020 1 0.003 07-25-94 284 0.018 i 0.003 02-07-94 280 0.026 i 0.004 08-01-94 280 0.018 1 0.003 02-14-94 283 0.024 i 0.004 08-08-94 281 0.019 i 0.003 02-21-94 282 0.027 i 0.004 08 15-94 283 0.018 i 0.002 02-28-94 279 0.024 i 0.003 08-22-94 284 0.024 1 0.003 03-07-94 281 0.024 1 0.003 08-29-94 284 0.033 i 0.003 03-14-94 280 0.022 i 0.003 09-05-94 285 0.016 i 0.003 03-21 94 281 0.020 1 0.003 09-12-94 280 0.026 i 0.003 03-28-94 281 0.015 1 0.003 09-19-94 282 0.037 1 0.004 09-26-94 282 0.021 1 0.003 10-03-94 285 0.011 1 0.002 1st Qtr. Meanis.d. 0.024 i 0.006 3rd Qtr. Meanis.d. 0.021 1 0.007 04-04 94 279 0.021 i 0.003 10-10-94 289 0.017 1 0.003 04 11-94 282 0.018 1 0.003 10-17-94 287 0.026 i 0.003 t 04-18-94 280 0.012 1 0.002 10-24-94 275 0.026 i 0.003 04-25-94 284 0.019 1 0.003 10-31-94 289 0.022 1 0.003 05-02-94 281 0.010 i 0.003 11 07-94 287 0.024 1 0.003 05-09-94 275 0.016 1 0.003 11-14-94 281 0.027 i 0.003 05 16-94 282 0.013 i 0.002 11-21-94 286 0.020 1 0.003 05-23-94 287 0.009 i 0.002 11-28-94 285 0.013 1 0.003 05-30-94 285 0.018 1 0.003 12-04-94 285 0.027 1 0.003 06-06-94 278 0.016 1 0.003 12-12-94 288 0.015 1 0.003 06-13-94 269 0.015 1 0.003 12-19-94 289 0.031 1 0.004 06-20-94 276 0.018 1 0.003 12-26-94 288 0.035 i 0.004 06-27-94 276 0.011 1 0.003 01-02-95 285 0.021 1 0.003 2nd Qtr. Meanis.d. 0.015 i 0.004 4th Qtr. Meanis.d. 0.023 1 0.006 Cumulative Average: 0.021 Previous Annual Average: 0.023 8
- Iodine-131 concentrations are <0.07 pCi/m unless otherwise noted in Appendix C.
l l { 12 l
e IOLEDO Table 9. Air particulate filters and charcoal canisters. Analyses: Gross beta and iodine-131' . Location: T-12 Units: pCi/m 2 Collection: Continuous, weeldy exchange. Date Volume Date Volume Collected (m 3) Gross Beta Collected (m3) Gross Beta Required LLD DE OR 01-10-94 284 0.020 1 0.004 07-04-94 286 0.012 1 0.003 01-17-94 282 0.033 1 0.004 07-11-94 285 0.012 1 0.002 01-24 94 282 0.041 1 0.004 07-18-94 280 0.015 1 0.003 01-31-94 283 0.022 1 0.003 07-25-94 310 0.017 1 0.003 02-07-94 281 0.021 1 0.003 08-01-94 276 0.021 1 0.003 02-14-94 280 0.021 1 0.004 08-08-94 284 0.019 i 0.003 02-21-94 301 0.026 1 0.003 08-15-94 285 0.016 i 0.002 02-28-94 283 0.022 1 0.003 08-22-94 280 0.022 i 0.003 03-07-94 282 0.022 i 0.003 08-29-94 285 0.033 1 0.003 03-14-94 282 0.024 i 0.003 09-05-94 283 0.015 1 0.003 03-21-94 282 0.020 i 0.003 09-12-94 283 0.023 i 0.003 03-28-94 282 0.015 i 0.003 09-19-94 285 0.035 i 0.003 - 09-26-94 285 0.024 i 0.003 10-03-94 288 0.014 i 0.003 1st Qtr. Meanis.d. 0.024 i 0.007 3rd Qtr. Meanis.d. 0.020 1 0.007 04-04-94 281 0.019 1 0.003 10-10-94 282 0.017 i 0.003 04-11 94 284 0.017 1 0.003 10-17-94 282 0.023 1 0.003 04-18-94 282 0.016 i 0.003 10-24-94 282 0.025 i 0.003 04-25-94 284 0.019 i 0.003 10-31-94 275 0.018 i 0.003 05-02-94 283 0.009 i 0.003 11-07-94 281 0.021 1 0.003 05-09-94 283 0.015 i 0.003 11-14-94 277 0.023 1 0.003 05-16-94 304 0.013 1 0.002 11-21-94 280 0.021 1 0.003 05-23-94 285 0.008 1 0.002 11-28-94 285 0.020 1 0.003 05-30-94 286 0.018 1 0.003 12-04-94 279 0.027 1 0.003 06-06-94 281 0.017 i 0.003 12-12-94 286 0.017 i 0.003 06-13-94 283 0.016 i 0.003 12-19-94 279 0.026 i 0.003 1 06-20-94 286 0.023 1 0.003 12-26-94 278 0.035 1 0.004 06-27-94 284 0.012 1 0.003 01-02-95 289 0.025 1 0.003 2nd Qtr. Meanis.d. 0.016 1 0.004 4th Qtr. Meanis.d. 0.023 1 0.005
)
)
{ Cumulative Average: 0.020 Previous Annual Average: 0.021 8
- Iodine 131 concentrations are <0.07 pCi/m unless otherwise noted in Appendix C.
1 13 l
_g . .- - . . . ... [ b TOLEDO ' Table 10. Air particulate filters and charcoal canisters . Analyses: Gross beta and iodine-131 *. !* Location: T-27 ' Units: pCi/m' Collection: Continuous, weekly exchange. 5 Date Volume Date Volume r Collected (m 3) Gross Beta Collected (m3) Gross Beta f Reauired i 1 n QQ1 i QQ1 01 10-94 288 0.020 1 0.004 07-04-94 306 0.012 1 0.002 ! 01 17-94 287 0.033 1 0.004 07-11-94 285 0.015 1 0.002 01 24-94 266 i 0.036 1 0.004 07-18-94 278 0.017 1 0.003 01 31 94 284 0.018 1 0.003 07-25-94 286 0.019 i 0.003 [ 02-07-94 282 0.022 1 0.003 08-01-94 288 0.018 i 0.003 i 02-14-94 285 0.022 1 0.004 08-08-94 284 0.018 1 0.003 02-21-94 285 0.025 1 0.003 08-15-94 285 0.016 i 0.002 02-28-94 282 0.023 1 0.003 [ 08-22-94 272 0.024 1 0.003 ' 03-07-94 278 0.031 1 0.004 08-29-94 286 0.026 i 0.003 03 14-94 283 0.026 1 0.003 09-05-94 292 0.013 1 0.002 l 03-21-94 274 0.017 1 0.003 09-12-94 279 0.021 1 0.003 03-28-94 281 { 0.016 i 0.003 09 19-94 280 0.034 i 0.003 ; 09-26-94 280 0.017 1 0.003 10-03-94 284 [ 0.013 1 0.003
- 1st Qtr. Meants.d. 0.024 1 0.006 3rd Qtr. Meants.d. 0.019 1 0.006 !
i 04-04-94 282 0.020 1 0.003 10-10-94 281 0.018 i 0.003 04-11-94 285 i 0.017 1 0.003 10-17-94 285 0.020 1 0.003 04-18-94 282 0.014 i 0.002 I 10-24-94 284 0.021 i 0.003 04-25-94 285 l 0.019 1 0.003 10-31-94 286 0.020 i 0.003 05-02-94 279 0.009 i 0.003 11-07-94 277 0.020 1 0.003 ' 05-09-94 284 0.016 1 0.003 11-14-94 284 0.022 1 0.003 ' 05 16-94 284 0.013 1 0.003 11-21-94 285 0.020 i 0.003 05-23-94 283 0.010 1 0.003 11-28-94 285 0.013 i 0.003 ; 05-30-94 285 0.020 0.003 12-04-94 284 0.027 i 0.003 06-06 277 0.015 1 0.003 12-12-94 286 0.014 i 0.003 06-13-94 283 0.015 1 0.003 12-19-94 275 0.026 i 0.003 06-20 94 285 l 0.020 1 0.003 12-26-94 281 0.035 1 0.004 06-27-94 288 0.011 1 0.003 01-02-95 285 0.024 1 0.003
- 2nd Qtr. Meants.d. 0.015 i 0.004 4th Qtr. Meants.d. 0.022i 0.005 !
t Cumulative Average: 0.020 i Previous Annual Average: 0.021
- Iodine-131 concentrations are <0.07 pCi/m'unless otherwise noted in Appendix C.
f' i t 14 '
_ . , ~ . - TOLEDO l Table 11. i Airborne particulate data, gross beta analysis, monthly averages, minima, and I maxima,1994. l i Gross Beta (pCi/m3) l Month Location Number of Samples a Average Minimum Maximum l January T-1 4 0.027 0.020 0.032 T-2 4 0.023 0.015 0.031 ; T-3 4 0.028 0.021 0.036 T-4 4 0.028 0.020 0.035 : T-7 4 0.026 ' 0.019 0.037 T-8 A 026 , DES 025 ! All Indicators 24 0.026 0.015 0.037 T-9 4 0.028 0.020 0.037 T-11 4 0.026 0.016 0.039 T-12 4 0.029 0.020 0.041 i T-27 1 042Z 0 018 ,0436 ' All Controls 16 0.028 0.016 0.041 i February T-1 4 0.021 0.018 0.028 T-2 4 0.022 0.020 0.023 ; T-3 4 0.022 0.020 0.023 : T-4 4 0.024 0.021 0.027 ? T-7 4 0.024 0.021 0.028 > T-8 1 0E25 0322 0E0 All Indicators 24 0.023 0.018 0.030 T-9 4 0.023 0.019 0.027 T-11 4 0.025 0.024 0.027 i T-12 4 0.022 0.021 0.026 T-27 A 023 l 0422 0425 ; All Controls 16 0.023 0.019 0.027 i i Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. ' 15 _ . ~ _ _ _ _ .
.l_,.-.-------:.- . - . - TOLEDO Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and maxima,1994 (continued). Gross Beta (pCi/m3) Month Location Number of Samples a Average Minimum Maximum March T1 4 0.021 0.019 0.023 T-2 4 0.020 0.015 0.025 ; T-3 4 0.020 0.014 " 0.024 T-4 4 0.021 0.019 0.026 T7 4 0.023 0.020 0.026 T-8 1 0A21 0320 DA30 All Indicators 24 0.022 0.014 0.030 T-9 4 0.023 0.019 0.026 T-11 4 0.020 0.015 0.024 T-12 4 0.020 0.015 0.024 T-27 1 0A22 DAlfi - 0A31 All Controls 16 0.021 0.015 0.031 April T-1 5 0.015 0.012 0.019 T-2 5 0.014 0.009 0.019 T-3 5 0.015 0.010 0.018 T-4 5 0.015 0.010 ' 0.017 T7 5 0.016 0.009 0.022 T-8 5 OA12 DAll 0321 All Indicators 30 0.015 0.009 0.022 T9 5 0.017 0.011 0.021 T-11 5 0.016 0.010 0.021 T-12 5 0.016 0.009 0.019 T-27 5 DAlfi 0A02 0320 All Controls 20 0.016 0.009 0.021 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parenthms indicate the number of e samples with unreliable and less than value results which are excludeo from the average. 16
TOfFDO Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and maxima,1994 (continued). Gross Beta (pCi/m3) Month Location Number of Samples a Average Minimum Maximum May T-1 4 0.014 0.009 0.017 T-2 4 0.013 0.009 0.016 T-3 4 0.016 0.011 0.018 T-4 4 0.013 0.008 0.018 T-7 4 0.016 0.010 0.024 T-8 4 025 020 0.02Q All Indicators 24 0.014 0.008 0.024 T-9 4 0.015 0.013 0.018 T-11 4 0.014 0.009 0.018 T-12 4 0.014 0.008 0.018 T-27 A 0.015 020 DA20 All Controls 16 0.014 0.008 0.020 June T-1 4 0.015 0.012 0.020 T-2 4 0.014 0.010 0.020 T3 4 0.016 0.015 0.020 T-4 4 0.015 0.010 0.021 T-7 4 0.020 0.017 0.023 T-8 4 0312 025 0425 All Indicators 24 0.016 0.010 0.025 T-9 4 0.018 0.016 0.023 T-11 4 0.018 0.011 0.018 T-12 4 0.017 0.012 0.023 T-27 4 QA15 021 0.020 All Controls 16 0.017 0.011 0.023 a Unless otherwise specified, data ior samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. 17 l
, m-,_ m -- - - - - ~ ~ ~ ~ ~ ~ ~ ~ ~ * ~
~ l f
TOLEDO i Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and l maxima,1994 (continued). I I Gross Beta (pCi/m3) ( Month Location Number of Samplesa Average Muumum Maximum l ! July T-1 5 0.016 0.011 0.018 T-2 5 0.017 0.011 0.021 i T-3 5 0.015 ' O.010 0.019 ! T-4 5 0.015 0.012 ' O.017 T-7 5 0.015 0.013 0.016 T-8 5 0A18 0A13 0.022 i All Indicators 30 0.016 0.010 0.022 ! T-9 5 0.018 0.010 0.021 T-11 .', 5 0.017 0.012 0.020 i T-12 5 0.015 0.012 . 0.021 T-27 5 0.016 Qa12 DA12 g All Controls 20 0.016 0.010 0.021 i August T-1 4 0.020 0.014 0.029 T-2 ! 4 0.023 0.018 0.030 T-3 i 4 0.019 0.015 0.028 i T-4 4 0.022 0.017 0.028 f
.T-7 4 0.022 0.017 0.028 !
T-8 1 0.022 0415 0430 i All Indicators 24 0.021 0.014 0.030 , T-9 4 0.024 0.018 0.031 T-11 4 0.024 0.017 0.033 r T-12 4 0.023 0.016 0.034 ! T-27 1 0,021 0 016 0426 : All Controls 16 0.023 0.016 0.034 ! I a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of -- t samples with unreliable and less than value results which are excluded from the average. ;I i i i l 18
- ._ _., .-. _ __ _ ~.
..w.., . _ ... ._. _. .,..1- ._ m. . . , , m.-..- - - ~ . - . . _ . .
o.y u
-4 TOLEDO Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and maxima,1994 (continued).
Gross Beta (pCi/m3) Month Location Number of Samples a Average Mmunum Maximum September T-1 5 0.019 0.012 0.032 T-2 5 0.022 0.013 0.035 T-3 5 0.021 0.015 0.032 T-4 5 0.019 0.009 0.032 T-7 5 0.019 0.011 0.032 T-8 5 Da18 0412 DA32 All Indicators 30 0.020 0.009 0.035 T-9 5 0.023 0.015 0.036 T-11 5 0.022 0.011 0.037 T-12 5 0.022 0.014 0.035 T-27 5 Da22 0413 0431 All Controls 20 0.022 0.011 0.037 October T-1 4 0.020 0.016 0.023 T-2 4 0.021 0.017 0.022 T-3 4 0.020 0.014 0.023 T-4 4 0.022 0.017 0.025 T-7 4 0.019 0.012 0.024 T-8 4 0A22 Dal2 0425 All Indicators 24 0.021 0.012 0.025 T-9 4 0.023 0.017 0.027 T-11 4 0.023 0.017 0.026 T-12 4 0.021 0.017 0.025 T-27 4 0420 0418 QA21 All Controls 16 0.022 0.017 0.027 a Unless otherwise specified, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. 19
IOLEDO Table 11. Airborne particulate data, gross beta analysis, monthly averages, minima, and maxima,1994 (continued). Cross Beta (pCi/m3) Month Location Number of Samples a Average Minunum Maximum November T-1 4 0.019 0.014 0.027 T-2 4 0.021 0.018 0.025 T-3 4 0.021 0.018 0.025 T-4 4 0.022 0.016 0.028 T-7 4 0.022 0.019 0.027 T-8 4 0420 0A16 0.025 All Indicators 24 0.021 0.014 0.028 T-9 4 0.019 0.015 0.023 T-11 4 0.021 0.013 0.027 T-12 4 0.021 0.020 .d.023 T-27 1 DAl2 DA13 0422 All Controls 16 0.020 0.013 0.027 December T-1 5 0.028 0.018 0.040 T-2 5 0.026 0.018 0.036 T-3 5 0.025 0.016 0.031 T-4 5 0.025 0.014 0.034 T7 5 0.026 0.017 0.033 T-8 .5 0A25 0A15 0432 All Indicators 30 0.026 0.014 0.040 T-9 5 0.025 0.013 0.035 T-11 5 0.026 0.015 0.035 T-12 5 0.026 0.017 0.035 T-27 _5 0A25 DAll 0,035 All Controls 20 0.026 0.013 0.035 8 Unless otherwise specified, data for samples colixted on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. 20
m- - 10J.EDQ Table 12. Airborne particulates, quarterly composite of all indicator and all control locations, analyses for strontium and gamma-emitting isotopes,1994. Sample Description and Activity (pCi/m3) January - March Lab Code TAP-3927 TAP-3928 TAP-3929 TAP-3930 TAP-3931
!.ocation T-1 T2 T-3 T4 T-7 Volume (m3) 3384 3569 3380 3391 3364 Sr 89 <0.0005 <0.0009 <0.0005 <0.0004 <0.0007 St-90 <0.0003 <0.0004 <0.0003 <0.0002 <0.0004 EeJ 0.07610.015 0.07110.016 0.070t0.013 0.079 0.016 0.06810.018 K-4 ) G "M <0.034 <0.041 <0.036 <0.036 Nie 15 w.ca>5 <0.0007 <0.0010 <0.0004 <0.0007 Zr-95 <0.0006 <0.0005 <0.0008 <0.0010 <0.0006 Ru-103 <0.0006 <0.0005 <0.0006 <0.0007 <0.0010 Ru-106 <0.0040 <0.0051 <0.0032 <0.0036 <0.0042 Cs-134 <0.0003 <0.0004 <0.0003 <0.0007 <0.0003 Cs-137 <0.0005 <0.0004 <0.0008 <0.0003 <0.0005 Ce-141 <0.0014 <0.0013 <0.0016 <0.0017 <0.0014 Cc-144 <0.0031 <0.0031 <0.0057 <0.0037 <0.0048 lab Code TAP-3932 TAP-3933 TAP-2934 TAP-3935 TAP-3936 Location T-8 T-9 (C) T-11 (C) T-12 (C) T-27 (C)
Volume (m3) 3425 3354 3385 3404 3375 Sr-89 <0.0005 <0.0006 <0.0006 <0.0005 <0.0006 St-90 <0.0003 <0.0004 <0.0004 <0.0003 <0.0004 Be-7 0.08110.015 0.08510.015 0.08510.014 0.09410.016 0.08710.017 K-40 <0.036 <0.036 <C.036 <0.036 <0.034 Nb-95 <0.0007 <0.0004 <0.0006 <0.0014 <0.0009 Zr-95 <0.0006 <0.0016 <0.0006 <0.0009 <0.0005 Ru-103 <0.0003 <0.0008 <0.0005 <0.0005 <0.0009 Ru-106 <0.0025 <0.0032 <0.0045 <0.0062 <0.0055 Cs-134 <0.0009 <0.0005 <0.0003 <0.0004 <0.0004 Cs-137 <0.0004 <0.0004 <0.0008 <0.0003 <0.0004 Cc-141 <0.0016 <0.0016 <0.0015 <0.0017 <0.0009 Cc-144 <0.0032 <0.0036 <0.0030 <0.0033 <0.0041 21
;~ ._._ ._
~ - ' -' - ' - - - - -
4 . . tor Fi1O i Table 12. Airborne particulates, quarterly composite of all indicator t.nd all control locations, analyses for strontium and gamma emitting isotopes,1994 (continued). ! Sample Description and Activity (pCi/m3) - ! April- June { lab Code TAP-4042 TAP-4043 TAP-4044 TAP-4045 TAP-4046 ! Location T-1 T-2 T-3 T-4 T-7 i Volume (m3) 3666 3831 3712 3714 3529 Sr-89 <0.0005 <0.0007 <0.0006 <0.0004 <0.0006 '! Sr-90 <0.0003 <0.0004 <0.0004 <0.0004 <0.0003 Be-7 0.06410.021 0.07110.023 0.08310.024 0.07110.016 0.07410.023 K-40 <0.049 <0.056 <0.051 <0.040 <0.058 Nb-95 l
<0.0012 <0.0009 <0.0014 <0.0014 <0.0011 i Zr-95 <0.0026 <0.0028 <C.0034 <0.0009 <0.0030 '
Ru 103 <0.0013 <0.0006 <0.0010 <0.0007 <0.0023 j Ru 106 <0.0079 <0.0055 <0.013 <0.013 <0.0066 ; Cs-134 <0.0006 <0.0008 <0.0006 <0.0015 <0.0007 ; Cs-137 <0.0008 <0.0016 <0.0009 <0.0014 <0.0011 Ce-141 <0.0026 <0.0024 <0.0021 <0.0020 '
<0.0018 Cc-144 <0.0033 <0.0049 <0.0064 <0.0056 <0.0051 Lab Code TAP-4047 TAP-4048 TAP-4049 TAP-4050 TAP 4051 Locati.n T-8 T-9(C) T-11(C) T-12(C) T-27(C)
Volume (m3) 3634 3718 3634 3706 3948 i Sr89 <0.0006 <0.0005 <0.0007 <0.0006 <0.0005 Sr-90 <0.0004 <0.0003 <0.0005 <0.0004 <0.0004 i i Be-7 0.08010.025 0.08810.019 0.06710.023 0.08510.021 0.07910.022 ! K-40 <0.048 <0.044 <0.053 <0.054 <0.046 ; Nb-95 <0.0014 <0.0008 <0.0014 <0.0011 <0.0023 t Zr-95 <0.0019 <0.0015 <0.0018 <0.0012 <0.0012 i Ru-103 <0.0020 <0.0014 <0.0009 <0.0013 <0.0012 ! Ru-106 <0.0083 <0.0059 <0.0079 <0.0050 <0.010 l Cs-134 <0.0011 <0.0013 <0.0007 <0.0005 <0.0008 ! Cs-137 <0.0015 <0.0006 <0.0006 <0.0007 <0.0010 Cc-141 <0.0026 <0.0013 <0.0026 <0.0023 <0.0026 : Ce-144 <0.0069 <0.0033 <0.0094 <0.0076 i
<0.0070 P
t i
?
22
._L
2/ TOLEDO
-l e
- Table 12.' Airborne particulates, quarterly composite of all indicator and all control locations, I analyses for strontium and gamma-emitting isotopes,1994 (continued).
l
- l Sample Description and Activity (pCi/m3)
July-September f I Lab Code TAP-4158 TAP-4159 TAP-4160 TAP-4161 TAP-4162 !
' location T-1 T-2 T-3 T-4 T-7
Volume (m3) 4044 4019 4042 4039 4034 l
\
Sr-89 <0.0005 <0.0005 <0.0006 <0.0004 <0.0006 Sr-90 <0.0003 <0.0003 <0.0004 <0.0003 <0.0004 l Be-7 0.068i0.013 0.06710.020 0.073i0.014 0.066t0.018 0.070f0.019 , K-40 <0.019 <0.057 <0.033 <0.057 <0.053 i Nb-95 <0.0003 <0.0012 <0.0016 <0.0007 <0.0010 t Zr-95 <0.0008 <0.0011 <0.0039 <0.0011 <0.0020 Ru-103 <0.0006 <0.0013 <0.0012 <0.0009 - <0.0017 ; Ru 106 <0.0021 <0.0098 <0.0050 <0.0044 <0.0038 ; Cs 134 <0.0004 <0.0014 <0.0016 (0.0006 <0.0007 ~ Cs-137 <0.0008
<0.0014 <0.0009 <0.0024 .<0.0014 i Ce-141 - <0.0007- <0.0019 <0.0012 <0.0020 <0.0018 !
Ce-144 <0.0042 <0.0093 <0.0053 <0.0041 <0.0065 i
<0.0042 ,
tab Code TAP-4163 TAP-4164 TAP-4165 TAP-4166 TAP-4167 ! Iocation T-8 T-9 T-11 T-12 T-27 Volume (m3) 4009 4024 3947 3995 3985 ! Sr-89 <0.0007 <0.0007 <0.0005 <0.0004 <0.0005 . Sr-90 <0.0004 <0.0004 <0.0003 <0.0003 <0.0003 i Be-7 0.07010.012 0.08810.022 0.084t0.020 0.077t0.022 0.073i0.018 K-40 <0.017 <0.058 <0.057 <0.056 <0.054 ; Nb-95 <0.0003 <0.0007 <0.0013 <0.0007 <0.0010 l Zr-95 <0.0012 <0.0010 <0.0015 <0.0010 <0.0025 Ru-103 <0.0004 <0.0014 <0.0013 <0.0010 <0.0007 i Ru 106 <0.0035 <0.016 <0.0082 <0.0042 <0.013 ,
. Cs-134 <0.0007 <0.0006 <0.0023 <0.0006 <0.0016 ,
Cs-137 <0.0009 <0.0018 <0.0017 <0.0013 <0.0019 i Cc-141 <0.0006 <0.0025 <0.0021 <0.0016 <0.0020 l Ce-144 <0.0020 <0.0039 <0.0057 <0.0079 <0.0080 l l 23 ! L
TOLEDO Table 12. Airborne particulates, quarterly composite of all indicator and all control locations, analyses for strontium and gamma-emitting isotopes,1994 (continued). Sample Description and Activity (pCi/m3) October- December i Lab Code TAP-8130 TAP-8131 TAP-8132 TAP-8133 TAP-8134 Location T1 T-2 T-3 T-4 T-7 Volume (m3) 3375 3414 3423 3448 3438 St 89 <0.0006 <0.0005 <0.0005 <0.0005 <0.0006 St-90 <0.0005 <0.0004 <0.0005 0.00310.001 <0.0005 Be-7 0.07910.015 0.08810.013 0.081i0.016 0.095i0.016 0.08410.017 K-40 <0.037 0.037 <0.037 <0.037 <0.037 Nb-95 <0.0007 '.0004 <0.0005 <0.0006 <0.0004 Zr-95 <0.0013 <0.0006 <0.0006 <0.0006 <0.0006 Ru-103 <0.0004 <0.0003 <0.0005 <0.0005 <0.0004 Ru-106 <0.0041 <0.0026 <0.0034 <0.0055 <0.0069 Cs-134 <0.0004 <0.0004 <0.0007 <0.0005 <0.0004 Cs-137 <0.0006 <0.0003 <0.0006 <0.0005 <0.0007 Cc-141 <0.0010 <0.0013 <0.0016 <0.0017 <0.0009 Cc-144 <0.0064 <0.0045 <0.0050 <0.0085 <0.0048 Lab Code TAP-8135 TAP-8136 TAP-8137 TAP-8138 TAP-8139 i Location T-8 T-9 (C) T-11 (C) T-12 (C) T-27 (C) Volume (m3) 3467 3407 3429 3366 3393 i Sr-89 <0.0005 <0.0005 <0.0005 <0.0006 <0.0007 ! Sr-90 <0.0003 <0.0003 <0.0003 <0.0004 <0.0005 Be-7 0.07510.013 0.07510.015 0.07710.013 0.08010.015 0.089i0.015 K-40 <0.036 <0.038 <0.037 <0.038 <0.037 Nb-95 <0.0008 <0.0004 <0.0005 <0.0008 <0.0004 Zr-95 <0.0006 <0.0006 <0.0012 <0.0008 <0.0012 Ru-103 <0.0005 <0.0004 <0.0005 <0.0005 <0.0007 ; Ru-106 <0.0044 <0.0028 <0.0027 <0.006d <0.0084 ! Cs-134 <0.0005 <0.0008 <0.0006 <0.0004 <0.0006 l Cs-137 <0.0007 <0.0005 <0.0005 <0.0010 <0.0009 i Ce-141 <0.0017 <0.0014 <0.0012 <0.0014 <0.0015 i Cc-144 <0.0042 <0.0028 <0.0045 <0.0061 <0.0030 i 74
__ _~_ a - u ---- - -~ ~ l TOLEDO Table 14. Area monitors (TLD), quarterly,1994. I i mR/91Ihvs Location 1st Quarter 2 rid Quader 3rd Quarter 4th Quarter Indirator T-1 10.710.2 10.4f0.2 i 9.9i0.3 10.810.3 ; T-2 12310.3 10.SiO.2 12.1103 10.9i0.3 f T-3 '12.110.2 11.0i0.2 11.Si0.3 11.010.2- { T-4 14.li0.2 12.8i0.4 13.510.3 12.9i0.4 T-5 14.lio.2 [ 11.2io.4 12.8i0.2 11.110 3 T-6 10.910.3 10.610.2 ( 11.6t0.3 10.4t0.3 T-7 10.9i0.3 13.9i0.4 l 13.810.5 14.910.3 T-8 18.9f0.4 17.4i0.3 ! 20.310.3 18.110.7 T-10 14.2i0.2 13.5103 14.910.2 14.110.2 T-38 11.2i0.3 11.610.2 11.7i0.3 10.9i0.3 ! T-39 12.1i0 3 13310.4 14.1103 13.lio.3 - T-40 11.9i0.2 13.2io.2 13.3i0.3- 12.9i0.3 , T-41 11.610.2 10.9i0.2 ' 11.410.4 11.8i0.2 T-42 10.1i0.2 9.4i0.2 9.7iO3 9.810.2
- T-43 !
12.1*0 3 14.210.5 13.6i0.5 13.0fo.3 ; T 13.910.2 14.2iO3 15.8i03 13.4i0.2 T-45 16.110.2 17.7f0.3 19.7i0.2 { 16.710.3 ! T-46 12.710 3 12.7t03 13.8f0.2 12.6i0.4 T-47 9.710.2 9.5i0.2 9.210.3 8.9i0.3 T-48 15.910.2 ! 16.2iO3 15.4f03 14.0f0.2 i T-49 10.6i0.2 9.910.2 11.510.3 9.110.2 -i T-50 16.810.2 19.Si0.7 18.lf03 18.8i0.4 T-51 14.8io.3 14.810.3 15.9i03 13.4i0.4 + T-52 18.2iO3 18.6i0.3 18.710.2 18.8i0.6 T-53 16.9i0.3 20.1*0.2 17.2103 19.2i0.6 T-54 16.8103 18.4f0.4 18.510.3 17.2f0.8 ' T-55 13.810.2 13 A+0.4 15.1M.2 12Mo.3 Mean i s.d. 13.512.7 13.713.2 14.2i3.0 i 13.313.0 'i Control r T-9 11.4to.2 11.710.2 11.4103 12.0to.4 T-11 14.010.2 12.610.4 13.9io.3 12.310.4 T-12 18.6i0.2 17.2103 l 17.9iO3 18.6i0.4 i T-23 14.910 3 13.4t0.2 18.2io.4 11.610.4 T-24 16.7103 i 15.6i0.2 18.0103 15.4f0.2 ; T-27 16.110.2 16.010 3 17.710.2 16.6+0.4 , Mean i s.d. 153123 14.412.2 16.212.6 f 14.412.6 - [ i 25 ,
,, v -. - - . -. --- - .-s-
, , _ .. _ . . ~ - - - -- -
d
- l
- 1 TOLEDO I
Tab!e 14. Area monitors (TLD), quarterly,1994. i l mTU9mm - Location 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Indicater . T-60 10.310.3 10.4i0.2 11.1*0.2 9.6f0.4 T-61 9.6f0.4 8.8i0.5 10.3i0.2 8.9f0.4 i T-62 9.2103 9.010.2 9.4f0.3 10.0f0.3 : T-65 13.7i0.2 15.1f0.2 20.3i0.2 14.9i0.4 T 66 17.610.3 17.7i0.5 203i0.2 18.6i0.3 i T-67 173103 16.6f0.2 20.4i0 3 16.310.2 T-68 13.210.2 14.810.4 15.210.2 15.010.3 ! T-69 15.510.2 17.lio.4 17.210.3 16.210.4 T-71 15.610.4 16.010 3 15.210.2 15.010.4.
- T-73 12.210.2 11.210.2 12.8103 12.110.4 l T-74 10.210.3 8.210.3 10.210.2 7.4i0.3 !
T-75 13.010 3 13.0i0.2 15.010.2 11:710.4 . T-76 9.910.3 8.810.4 9.9i0.2 8.8i0.2 t T-91 14.010.2 163103 143fD.2 16.410.2 - T-92 10.010.3 6.110.4 11.Si0.2 5.0t0.3 T-93 10.5103 10.010.3 12.510.2 10.6i0.3 T 94 15.410.4 10.1103 16.110.3 11.2f0.4 T-112 15.410.3 12.9i0.3 14.0f0.2 12.4to.4 l T-121 13.410.2 17.4103 16.8iO3 16.8AO.3 T 122 12.710 3 13.710.2 15.910.2 13.810.4 T 123 13.110.3 14.310.2 14.0io.2 14.710.3 .I T-125 12.910.4 15.910.3 14.8i0.2 15.4103 i T 126 14.210 3 12.910.4 14.8103 12.310.3 T-127 17.010.2 17.0103 19.210.2 17.210.4 ; T-128 14.810.3 15.110.3 16.610.2 13.910.4 T-150 NDa 9.810.2 14.810.2 9.610.3 ! T 151 16.110.2 15.710.4 17.410.6 15.210.3 ! T-153 17.1f0.3 17.710.4 18.SiO.2 17.210.4 T-154 14.010.3 14.810 3 14.7f0.3 14.7t03 T-201 12.910.4 12.810.3 12.310.2 11 +0.4 T-202 12.710 3 12.6i0 3 12.210 3 11310.4 T-203 , 12.1103 12.6103 13.5f03 11.610.4 - T 204 12.9103 13.410.2 NDa 11.210.5 T-205 14.610.2 17.310.3 14.610.4 16.810.4 - T-206 11.8103 11.410 3 10.9f0.2 10.6i0.4 T-207 11.110 3 -11.010 3 i 10.110.2 10.liOJ T 208 11.810.2 11. m 3 11.6+0.2 10.2iO3 Meani s d. 13312.3 13.213.1 14.513.1 12.813.1 aND - No data;'ILD lost in field. I i l 26 5
-. - _ ~ . . - - - - . - - . - - . - - - - . - - ~ - . . - - -. TOLEDO Table 14. Area monitors (TLD), quarterly,1994 (continued) mR/91 thvs Location 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Contr21 T-95 15.410.3 15.0i0.2 18.110.3 14.110.2 T-100 15.710.3 10.7i0.3 16.910.2 9.2i0.3 T-111 12.810.3 15.210.3 14.5i0.2 14.410.3 T-124 10.810.5 12.510.4 11.810.3 11.1t0.3 T-155 15.3 0.4 12.910.3 15.3i0.3 13.1 0.2 Mean i s.d. 14.0il.9 13.311.9 15.312.2 12.412.0 QC T-80 9.910.3 10.210.3 11.9fD.2 9.910.3 T-81 18.110.3 20.2i0.2 20.610.3 18.610.3 T-82 9.610.3 10.610.2 9.210.2 9.6.10.2 T-83 12.310.2 11.710.3 13.Di0.2 9.4i0.2 T-84 13.110.3 12.7i0.4 13.710.3 11.910.3 T-85 14.810.3 14.310.2 13.8i0.5 14.4i0.4 T-86 17.210.2 17.6i0.3 18.2i0.3 17.5i0.3 T-88 16.910.2 17.410.2 19.210.2 16.910.2 T-89 17.510.3 17.4i0.2 19.210.2 16.410.4 T-113 13.210.2 7.810.3 14.310.2 6.710.5 T-114 11.7i0.5 13.410.6 12.810.3 12.210.5 T-115 14.310.2 15.210.2 15.310.2 14.li0.2 T-116 16.410.2 17.3i0.3 18.810.7 15.3i0.4 T-117 11.410.2 14.710.2 14.810.2 14.610.3 T-118 15.410.4 20.910.3 20.0i0.2 17.9 0.3 T-119 NDa 12.7i0.4 14.5i0.2 13.010.2 T-120 14.110.3 15.010.3 15.0i0.3 14.210.3 T-200 14.lio.3 17.4 0.2 15.6+0.2 16.2+0.4 Mcan i s.d. 14.112.5 14.813.5 15.6i3.0 13.813.2 Shteld T-87 5.710.3 5.210.2 6.010.2 4.710.2 27 i l
r_ - _.
~ __ _
TOLEDO
- Table 15. Area monitors (TLD), Annual,1994.
Location ~mR/365 days Annud indicator T-1 38.210.8 T-2 39.8il.0 T-3 38.Si0.7 T-4 47.610 9 T-5 0.4fo.7 T-6 34.0 0.8 T-7 48.811.3 T-8 74.611.2
. T-10 48.0f0.7 T-38 38.510.8 T-39 38.810.6 T-40 47.211.0 T-41 42.910.7 .
T-42 28.lio.7 T-43 48.611.1 T-44 57.4i0.7 T-45 66.510.8 T-46 43.8i0.8 T-47 29.0i0.7 T-48 49.211.6 T-49 37.2i0.7 T-50 68.8to.7 T-51 51.610.8 T-52 71.811.0 T-53 59.410.6' T-54 56.911.4 - T-55 45.510 6 Mean s.d. 47.9112.3 Control T-9 43.6i0.2 T-11 43.210.4 . T-12 60.710.3 T-23 46.7i0.2 T-24 56.410.2 T-27 62.0+7 3 ; Mean i s.d. 52.118.6 l l
.i l
l 28 :
F _ ... TOLEDO Table 15. Area rnonitors (TLD), Annual,1994 (continued). Location mR/365 days Annual Indicator T-60 42.0i0.7 T-61 41.0i0.6 T-62 41.4 0.6 T-65 49.812.8 T-66 67.7i0.8 T-67 60.210.6 T-68 58.910.7 T-69 58.410.7 T-71 57.910.8 T-73 49.li0.6 T-74 39.710.8 T-75 58.010.8 T-76 38.112.1 T-91 58.011.4 T-92 40.310.8 T-93 29.910.9 T-94 57.6i0.9 T-112 52.210.6 T-121 52.911.0 T-122 39.212.2 T-123 54.110.8 T-125 53.710.8 T-126 48.111.2 T-127 56.611.6 T-128 61.8i0.6 T-150 NDa T-151 53.610.8 T-153 67.310.9 T-154 58.5i0.8 T 201 46.011.0 T-202 46.310.8 T 203 38.810.8 T-204 41.710.8 T-205 50.8i0.8 T-206 NPb T-207 NPb T-208 NE.b Mean i s.d. 51.419.4 8 ND - No data; TLD lost in the field. b NP - Not placed in the field. 29
. . . . ~ . _ -- . . . . . - - . . - - - - .. -- -- TOLEDO Table 15. Area monitors (TLD), Annual,1994 (continued). Location mR/3r6 days Annual Control T-95 63.010.6 T-100 52.5il.5 T-111 55.810.7 T-124 40.010.6 T-155 48.9 0.7 Mean i s.d. 52.018.5 QC T-80 38.911.0 T-81 68.010.9 T-82 39.710.8 T-83 44.510.8 T-84 49.010.8 T-85 49.010.7 T-86 72.110.7 T-88 67.410.7 T-89 58.010.8 T-113 48.911.0 T-114 43.910.8 l T-115 45.611.0 T-116 55.5i0.8 T-117 43.510.6 T-118 58.710.7 T-119 NDa ' T-120 56.411.5 T-200 57.2 1.3 Mcan i s.d. 52.7i10.0 Shield T-87 23.010.ti , a ND - No data; TLD lost in the field. 30
'.--,. . . . _ -. _ _z -~. . - - - . - - - TOLEDO Table 16. Milk samples, analyses for strontium-89, strontium-90, iodine-131 and gamma-emitting isotopes. Collection: Monthly Date Lab Adivitv(oCi/D Collected Code Sr-89 Sr-90 1-131 Ba-La-140 Cs-137 K-40 T-8 Farm. 2.7 mi WSW of Station 01-06-94 NSa .. .. .. .. .. .. aNS = Sample not available; location dropped from program. 31
, --- . . - .. . - . - - .~- . - - - -
i ,g-4
. TOtrno !
Table 16. Milk samples, analyses for strontium-89, strontium-90, iodine 131 and gamma-emitting isotopes (continued). y i Date 1/b Activitv(oCi/L) Collected Code Sr-89 St-90 1131 Ba La 140 Cs-137 K-40 ' t T-24 (C) Sandusky 21.0 mi SE of Station 01-06-94 TM1-0180 <0. 1.410.4 <0.3 <10 <10 13201160-02-04-94 -0261 <0.6 0.710.3 <0.4
<10 <10 1430i160 02-23-94 -0286 < 0.6 1.910.4 !
<0.3 <10 <10 11001170 03 22 94 -0353 <0.5 I 1.710.4 < 0.5 <10 <10 04-13 94 13701150 I 0457 < 0. 6 1.2i0.4 <0.4 <10 <10 1400150 05-24 94 -1389 <0.4 1.0i0.3 < 0.4 <10 <10 14501150 06-28-94 -2731 <0.7 3.210.6 <0.2 <10 <10 13801100 07-14-94 -3039 <0.7 1.7i0.5 <0.5 <10 <10 1450f130 08-30 94 -4305 <0.4 1.210.4 <0.1 :
<10 <10 14601120 09-27-94 -5109 ;
<0.7 1.310.5 <0.1 <10 <10 10-28-94 12901160 i
-6473 <0.6 1.110.3 <0.5 <10 <10 14101120 11 29-94 -7144,5 <0.6 1.010.3 <0.4 <10 <10 12601110 t 12-20 -7777 <0.5 1.510.4 <0.3 <10 <10 13101130 !
t h [ i t i l i i
?
4 [ t 1
}.
32
__ . - - ~ .. r TOIA O , Table 17. - Milk samples, analyses for calcium, stable potassium, and ratios of strontium-90 (pCi) per gram of calcium and cesium-137 (pCi) per gram of potassium. Collection: Monthly Sr-90 (pCi) Cs-137 (pCi) Date Lab Calcium Potassium , per gram per gram Collected Code (g/L) (g/L) i of Calcium of Potassium T-8 Farm. 2.7 mi WSW of Station
.01-06-94 NSa .. ..
T a NS = Sample not available; location dropped from program. t 6 i l o i i+,,
TOLFnO Table 18. Ground water samples, analyses for gross beta, tritium, strontium-89, strontium-90 and gamma-emitting isotopes,1994 (continued). Sample Description and Activity (pCi/L) Annual Meant s.d. l I-23 (C) ' i Lab Code NSa NSa NSa NSa Collection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Cross Beta Suspended Solids -- -- -- -- -- Dissolved Solids -- -- -- -- -- Total Residue -- -- -- -- -- 13 3 .. -. -. -. .. Sr-89 -- -- -- -- -- Sr-90 -- -- -- -- -- ' Cs-137 -- -- -- -- -- T-27 (C) Lab Code TWW-4799 TWW-0453 TWW 3060 TWW 5898 Collection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Gross Bria Suspended Solids <0.4 NAC NAC NAc <0.4 Dissolved Solids < 1.5b NA NA NA < 1.5 Total Residue <1.5b <1.7 5.311.3 2.711.3 4.0il.8 11 3 <330 <330 <330 <330 <330 St-89 < 1.0 <0.8 <0.5 < 1.1 <1.1 Sr-90 <0.6 <0.5 <0.4 <0.7 <0.7 Cs-137 <10 <10 <10 <10 <10 aNS - Sample not available. bSample counted longer; corrected data. cNA - Not applicable; speciGcations changed, deleting analysis. v
*We-*--he- ,,
e . tor SnD l Table 18. Ground water samples, analyses for gross beta, tritium, strontium-89, strontium-90 and gamma-emitting isotopes,1994 (continued). l Sample Description and Activity (pCi/L) Annual Meant s.d. T-141 (OC) Lab Code TWW-4801 TWW-0456 TWW-3062 TWW-5900 Collection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Gross Beta Suspended Solids <0.7 NAa NAa NAa <0.7 ~ Dissolved Solids 1.8i0.5 NA NA NA 1.8i0.5 Total Residue 1.8i0.5 4.3i2.1 7.612.0 4.2i2.3 4.5i2.4 H3 <330 <330 <330 <330
<330 Sr-89 <1.4 <0.5 <0.7
<0.7 ' <1.4 '
Sr-90 <0.6 <0.3 0.510.3 <0.3 <0.6 Cs-137 <10 <10 <10 <10 <10 aNA - Not applicable; specifications changed, deleting analysis. ' D L 37 I
TOLEDO Table 19. Domestic meat samples, analysis for gamma-emitting isotopes. Date Lab Sample Activity (pCi/g wet) Location Collected Code Type K-40 Cs-137 T-34 (C) 10-06-94 TME-5605 Chicken 2.04f0.41 <0.012 T-197 10-06-94 BIE-5606 Chicken 2.6710.31 <0.005
TOLEDO Table 20. Wild meat samples, analysis for gamma-emitting isotopes. Date Lab Sample Activity (oCi/g wet) Location Collected Code Type K-40 Cs-137 T-31 09-30-94 TME-5607 Muskrat 2.7410.33 <0.012 o 39 t
i 4 6 IDLEDO - Table 21. Green leafy vegetables, analyses for strontium " ,trontium-90, iodine-131, and other gamma-emitting isotopes. Collection: Monthly i s ;. son, Sample Description and Activity l Location T-17 T-17 T-19 T-19
!ab Code TVE-3999 TVE-4000 TVE-4001 TVE-4002 Collection Date 08-11 94 08 11-94 08-12-94 08-12-94 Type lettuce Kohlrabi Swiss Chard Cabbage Sr-89 <0.0008 <0.0017 <0.0040 <0.0008 Sr-90
<0.0005 0.0011i0.0006 <0.0026 0.000710.0003 1131 <0.022 <0.010 <0.012 <0.017 K-40 3.0510.31 3.07i0.27 4.46M.37 2.2310.28 Nb-95 <0.009 <0.005 <0.013 <0.013 Zr-95 <0.017 <0.011 <0.023 <0.014 Cs-137 <0.007 <0.010 <0.006 <0.012 Ce-141 <0.011 <0.025 <0.022 <0.018 Cc-144 <0.079 <0.074 <0.068 <0.076 Location T-37 (C) T-17 T-17 T-19 lab Code TVE-4003 TVE-4756 TVE-4757 TVE-4758 Collection Date 08-11 94 09 13-94 09-13-94 09-13-94 Type Cabbage Cabbage Kale Cabbage i Sr-89 <0.0011 <0.0046 <0.0067 <0.0024 Sr-90 0.001410.0005 0.004710.0015 0.0047IO.0024 0.002210.0010 1-131 <0.016 <0.026 <0.024 (0.011 K-40 1.9810.21 3.1710.36 3.56fD.39 3.42i0.26 Nb-95 <0.005 <0.014 <0.014 <0.010 Zr-95 <0.013 <0.013 <0.010 <0.019 Cs 137 <0.009 <0.015 <0.014 <0.009 l Ce-141 <0.018 <0.013 <0.034 <0.016 Cc-144 <0.054 <0.047 <0.10 <0.078 Location T-19 T-37 (C) T-17 T-17 Lab Code TVE-4759 TVE-4760 TVE-5901 TVE-5902 Collection Date 09-13-94 09-13-94 10-13-94 10-13-94 Type Swiss Chard Cabbage Purple Cabbage Kale Sr-89 <0.0018 <0.0013 <0.0016 <0.0026 Sr-90 <0.0012 0.000910.0005 0.001910.0007 0.0019io.0009 I-131 <0.028 <0.014 <0.012 <0.020 K-40 4.4710.42 2.57i0.46 4.05i0.46 3.3110.38 Nb-95 <0.013 <0.024 <0.019 <0.013 Zr-95 <0.013 <0.016 <0.017 <0.024 Cs-137 <0.013 <0.019 <0.015 <0.011 ;
Cc-141 <0.026 <0.021 <0.025 <0.027
- r Cc-144 <0.073 <0.069 <0.080 <0.10 l
r -- ._._ .._ _ _ . _.-.. - - - TOLEDO Table 21. Green leafy vegetables, analyses for strontium-89, strontium-90, iodine-131, and other gamma-emitting isotopes. Collection: Monthly in season. Sample Description and Activity (pCi/g wet) Location T-19 T-19 T-37 (C) T-17 Lab Code TVE-5903,4 TVE-5905 TVE-5906 TVE-6898 Collection Date 10-13-94 10-13-94 10-13-94 11-15-94 Type Cabbage Kale Cabbage Cabbage Sr-89 <0.0021 <0.0028 <0.0019 <0.0017 Sr 90 0.002710.0008 0.003810.0012 0.0024 0.0008 0.001610.0006 I131 <0.014 <0.015 <0.009 <0.024 K-40 3.2610.24 3.4110.32 2.75i0.32 3.3910.53 Nb-95 <0.005 <0.012 <0.005 <0.011 7r 95 <0.013 <0.021 <0.016 <0.031 Cs-137 <0.012 <0.006 <0.013 <0.020 Ce-141 <0.021 <0.014 <0.014 <0.022 Cc-144 <0.087 <0.096 <0.11 <0.055 Location T-17 T-19 T-19 Lab Code T-37 (C) TVE-6899 TVE-6900 TVE-6901 TVE-6902 Collection Date 11-15-94 11-15-94 11-15-94 11-15-94 Type Kale Cabbage Kohlrabi Cabbage Sr-89 <0.0033 <0.0010 <0.0016 <0.0012 Sr-90 0.002810.0011 0.000710.0004 0.0016io.0007 0.000810.0004 I-131 <0.026 <0.019 <0.018 <0.023 K-40 3.2510.59 2.3310.44 3.0810.42 2.69i0.48 Nb-95 <0.014 <0.022 <0.013 <0.034 Zr-95 <0.017 <0.033 <0.024 <0.021 Cs-137 <0 020 <0.019 <0.011 <0.024 Ce-141 <0.031 <0.031 <0.029 <0.036 Cc-144 <0.13 <0.097 <0.072 <0.16 Location Lab Code Collection Date Type Sr-89 Sr-90 1-131 K-40 Nb-95 Zr-95 Cs-137 Cc-141 Cc-144 41
TOfIDO Table 22. Fruit Samples, analyses for strontium-89, strontium-90, iodine-131, and other gamma-emitting isotopes. ' Collection: Monthly in season. Sample Description and Activity (pCi/g wet) Location T-8 T-23 (C) T-25 lab Code TVE-5251 TVE-5745 TVE-5252 Collection Date 09-26-94 09-26-94 09-26-94 Type Apples Grapes Apples Sr-89 <0.0013 <0.0020 <0.0011 Sr-90 <0.0008 0.001410.0007 0.000910.0005 I131 <0.009 <0.017 <0.011 K-40 1.3110.17 2.4710.019 1.4010.20 Nb-95 <0.607 <0.004 <0.010 Zr-95 <0.009 <0.014 <0.017 Cs-137 <0.008 <0.006 <0.010 Cc-141 <0.025 <0.020 <0.022 Ce-144 <0.10 <0.031 <0.052 location T-173 (C) lab Code TVE-5253,4 Collection Date 09-26-94 Type Grapes Sr-89 <0.0004 Sr-90 <0.0004 I131 <0.007 K-40 1.9710.90 Nb-95 <0.007 Zr-95 <0.012 Cs-137 <0.007 Ce-141 <0.014 Cc 144 <0.040 l t 42
~ . ~ _ . _ _ _ - . . ~ . , . . . . _ _ _ _ _ . ._... _ _ . _ . tot Sno f i Table 23. Animal - wildlife feed samples, analysis for gamma-emitting isotopes. Collection: Semiannually. l Sample Description and Activity (pCi/g wet) i Location T-31 v T-34 (C) T-197 Collection Date 10-05-94 10-06-94 i 10-06-94 Lab Code TCF-5601 TCF 5602 l Type TCF-5603 Cattails Chicken Feed Chicken Feed t Be-7 <0.14 i
<0.059 <0.042 '
K-40 1.61i0.21 5.6710.32 5.05i0.21 ' Nb-95 <0.011 <0.010 Zr-95 <0.005
<0.013 <0.020 :
Ru-103 <0.008 -
<0.012 <0.010 .!
Ru-106 <0.007 '
<0.051 <0.045 Cs-137 ' <0.041
<0.015 <0.010 Ce-141 <0.007
<0.026 <0.017 Ce-144 <0.018
<0.065 <0.066 :
<0.032 '
i Location T-198 ' Collection Date 10-05-94 Lab Code TCF-5604 " Type Cattalls Be-7 <0.13 l K-40 2.5910.29 Nb-95 <0.011 : Zr-95 <0.012 ! Ru-103 <0.019 ! Ru-106 <0.055 Cs-137 <0.016 l , Ce-141 <0.023 Ce-144 <0.063 !" f i I f f i h l 43
- TOLEDO Table 24. Soil samples, analysis for gamma-emitting isotopes. -
Sample Description and Activity (pCi/g dry) I.ocation T-1 T-2 T-3 T-4 T-7 Collection Date 04-25-94 04-25-94 04-25-94 04-25-94 04-25-94 lab Code TSO-0636 TSO-0637 T50-0638 15 0-0639 5 0-0640 Be-7 0.4210.19 <0.25 <0.38 <0.45 0.5810.22 K-40 5.9810.40 10.5810.55 8.8810.90 25.0211.00 12.6610.55 Nb-95 <0.008 <0.012 <0.050 <0.057 <0.017 Zr-95 <0.027 <0.032 <0.032 <0.076 <0.038 Ru-103 <0.019 <0.027 <0.043 <0.024 <0.028 Ru-106 <0.10 <0.17 <0.32 <0.17 <0.16 Cs-137 0.2310.02 0.1910.03 <0.043 0.22i0.04 0.05i0.02 Cc-141 <0.042 <0.044 <0.064 <0.091a <0.036 Ce-144 <0.091 <0.16 <0.14 <0.16 <0.066 Location T-8 T-9 (C) T-11 (C) T-12 (C) 'T-27 (C) Collection Date 04-25-94 04-25-94 04-25-94 04-25-9? 04-25-94 lab Code TSO-0641 TSO-0642 75 0-0643 750-0644 150-0645 i Be-7 <0.30 <0.27 0.97i0.29 0.7010.25 1.1810.38 K-40 28.7010.87 26.50i0.92 24.0310.77 23.2310.89 23.37i0.79 Nb-95 <0.067 <0.024 <0.026 <0.048 <0.054 l Zr-95 <0.052 <0.036 <0.043 <0.038 <0.064 I Ru-103 <0.030 <0.028 <0.022 <0.026
<0.023 Ru-106 <0.20 <0.19 <0.087 <0.10 <0.21 i Cs-137 0.4910.04 0.8510.05 0.2210.04 0.44i0.04 0.3210.03 Ce-141 <0.079 <0.077 <0.041 <0.030 <0.078 Ce-144 <0.16 <0.12 <0.091 <0.091 <0.24 Location T-23 (C)
Collection Date 09-26-94 i lab Code T50-5746 Be-7 <0.28 l K-40 8.9510.55 , Nb-95 <0.044 l Zr-95 <0.040 Ru-103 <0.027 l Ru-106 <0.17 l Cs-137 0.5810.04 Ce-141 <0.048 Ce-144 <0.16 a Corr (ded data Note: Page 45 is intentionally left out. 44
i' l i J TOLFOO i Table 25. , Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1994. . Cmss Beta Activity (nCi/L) Collection Lab Suspended Dissolved Total j Period Code Solids Solids Residue ; i T-11 (C) January TSWT-5039 <0.3 1.810.5 l February 1.810.5 !
-5231 <0.4 2.7i0.6 2.7i0.6 I March -5561 gga NAa 1,9i0.5 '
Ist Qtr. mean i s.d. <0.4 2.2i0.6 2.li0.5 i r April TSWT-0605 NAa NAa May 3.010.5
-1734 -- {
June 2.liO.6 .
-2732 --
2.2i0.5 , 2nd Qtr. mean i s.d. 2.4i0.5 July '13WT-3352 NA* NAa - 2.7t0.5 i August -4322 NA NA 2.1*0.5 September -5137 NA NA 4.6*06 l 3rd Qtr. mean is.d NA NA 3.111.3 ! i October TSWT-6475 NAa l NAa 2.410.5 l November -7146 NA NA December 2.0i0.5 ,
-7928 NA NA 2.2f0.4 4th Qtr. ;:nean i s.d. NA NA 2.2i0.2
- aNA - Not applicable; specifications changed, deleting analysis.
6 s ( I i ( 1 i 46 _ _ _ _ _ _ __ __ . _ . _ _ .i
< I l
TOLEDO i s Table 25. Treated surface water samples, monthly composites of weekly grab samples, analyses for ! gross beta,1994 (continued). ' { 1 Cross Beta Activity (oCi/L) ! Collection Lab Suspended Dissolved' Tota! Period Code Solids ! Solids Residue ! T-12 (C) !- i
- January TSWT-5040 <0.3 1.7f0.5 1.710.5 February -5232 <0.4 2.810.5 2.8io.5 1 March -5562 NAa NAa 2.910.5 ;
1st Qtr. mean i s.d. <0.4 2.210.8 i 2.510.7 y i April TSWT-0606 NA" NAa May 1.710.4 1735 .. .- 1.810 5 i June 2733,4 .. .. 1.810$3 '! 2nd Qtr. mean i s.d. .. .. 1.8i0.1 i f, July TSWT-3353 NAa s
.NAa 1.3i0.4 August -4323 NA NA 1.910.4 September -5138 NA ;
NA Leio.5 l 3rd Qtr. mean i s.d. NA NA 1.710.4 l October TSWT-6476 NAa 1.7i0.4 NAa November -7147 NA l NA 1.5i0.5 December -7929 i NA NA 1.610.4 j 4th Qtr. mean i s.d. NA NA 1.6i0.1 aNA - Not applicable; specifications changed, deleting analysis. I 1 l 1 I I I i 47 ' _ -- _ . - _. _ - _. - =_
W TOLEDO Table 25. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1994 (continued). 1 Cross Beta Activity (pCi/L) Collection Lab Suspended Dissolved Total Period Code Solids Solids Residue T-23 (C) January TSWT-4988 <0. 4 1.510.5 1.510.5 February -5302 <0.2 1.910.6 1.910.6 , March -0072,3 NAa gga 1.50.3 1st Qtr. mean i s.d. <0.4 1.7i0.3 1.610.2 April NSb .. .. .. May June 2nd Qtr. mean 1 s.d. - July August September 3rd Qtr. mean i s.d. October November December 4th Qtr. mean i s.d. aNA - Not applicable; specifications changed, deleting analysis. b NS - Sample not available; location has been dropped from the program. I 1 1 48
a__. - - i Tor 1:no ! i i Table 25. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1994 (continued). ! Gross Beta Actiylty(oCi/U Collection Lab' Suspended Dissolved Total ; Period Code Solids Solids Residue I:28 January TSWT-5041 <0.3 2.Si0.5 2.510.5 February -5233 <0.4 ! 2.210.5 2.210.5
- March -5563 NAa NAa 2.6 0.3 .
1st Qtr. mean i s.d. <0.4 2.410.2 2.410.2 $ t, Aptil TSWT-0607 NAa NAa May 1.810.5 !
-1736 -- --
2.210.5 June -2735 -- -- 1.810.5 , 2nd Qtr. mean i s.d. -- --
~1.9i0.2 July 15WT-3354 NAa NAa 1.110.4 August -4324 NA .
NA 1.414.4 l September -5139 NA NA 1.610.5 : 3rd Qtr. mean i s.d. NA NA 1.410.3 i October TSWT-6477 NAa 1.810.4 NAa > November -7148 NA- NA 2.010.5 December -7930 NA NA 1.910.4 ! 4th Qtr. mean i s.d. NA NA 1.910.1 aNA - Not applicable; specifications changed, deleting analysis. ! i 7 1 t 40 I
1 TOLEDO Table 25. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1994 (continued). Collection Cross Beta Activity (pCi/L) Lab Suspended Period Dissolved Total Code Solids Solids Residue I-50 January TSWT-5042 <0.3 2.310.5 2.3i0.5 February -5234 <0.4 2.6io.6 2.610.6 March -5564 NAa gga 2.4iA3 1st Qtr. mean i s.d. <0.4 2.410.2 2.410.2 April TSWT-0608 NAa May NAa 2.410.5
-1737 -- --
June 2.110.5
-2736 -- --
2.2f0.5 2nd Qtr. mean i s.d. -- --
. 2.210.2 July TSWT-3355 NAa August NAa 2.810.5
-4325 NA NA September -5140 2.li0.5 NA NA 2.110.5 3rd Qtr. mean i s.d. NA NA 2.3t0.4 October TSWT-6478 NAa November NAa 2.110.5
-7149 NA NA December 1.710.5
-7931 NA NA 2.2io.5 4th Qtr. mean i s.d. NA NA 2.010.3 i
aNA - Not applicable; specifications changed, deleting analysis. 50
N' 'Totrrr) Table 25. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1994 (continued).
~
i Cross Beta Activity (oCi/D Collection Lab Suspended. Dissolved' Total Period Code Solids Solids Residue T-144 ' January TSWT-5044 <0.3 2.6*0.5 2.6i0.3 February -5236 <0.4 2.7f0.5 2.710.5-l March -5566,7 NA* NA* 2.5fo.3 ; 1st Qtr. mean i s.d. <0.4 2.610.1 2.6i0.1 April TSWT-0610 NAa NAa 2.710.5 ' May -1739,40 -- -- 2.3i0.4 ,
. June -2738 -- --
2.0i0.5 2nd Qtr. mean i s.d. -- -- 2.310.4 .- 1 I July 13WT-3358 NAa NAa 2.li0.5 ; August -4327 NA NA 2.0i0.5 t
- September -5142 NA NA 1.8to.5 lt 3rd Qtr. mean i s.d. NA NA 2.0iO.2 .
t October . TSWT-6480 NAa NAa 2.410.5 , November -7151 NA NA 2.0io.5 [ December -7933 NA NA 1.910.4 4th Qtr. mean i s.d. NA NA 2.110.3 [ aNA - Not applicable; specifications changed, deleting analysis. L 8 0 t I 51 4
Totrno Table 26. Treated surface water samples, monthly composites of weekly grab samples, analyses for gross beta,1994. Cross Beta Activity (oCi/L) Collection Lab Suspended Dissolved Total Period Code Solids Solids Residue T-143 (OC) January TSWT-5043 <0.3 1.410.5 1.410.5 February -5235 (0.4 2.510.5 2.510.5 March -5565 NAa gga 1,9 0.5 1st Qtr. mean i s.d. <0.4 2.010.8 1.910.6 April TSWT-0609 NAL NAa 3.010.5 May -1738 -- -- 2.010.5 June -2737 -- - 1.70.4 2nd Qtr. mean i s.d. -- -- 2.210.7 July TSWT-3356,7 NAa NAa 2.510.4 August -4326 NA NA 1.810.5 September -5141 NA NA 2.1 0.5 3rd Qtr. mean i s.d. NA NA 2.110.4 October TShT-6479 NAa NAa 2.010.5 November -7150 NA NA 1.710.5 December -7932 NA NA 2.30.4 4th Qtr. mean i s.d. IJA NA 2.010.3 aNA - Not applicable; specifications changed, deleting analysis. 52
TOLEDO { Table 27. Treated surface water samples, quarterly composites of weekly grab samples, analysis for tritium, strontium-89, strontium-90 and gamma-emitting isotopes,1994. Collection Lab Activitv(oCi/D Location Period Code H-3 Sr-89 Sr-90 Cs-137 Contral Tal 1st Quarter TSWT-0374 <330 <1.0 <0.6 <10 2nd Quarter -2884 <330 <0.9 <0.4 <10 3rd Quarter -5815 <330 <1.0 <0.6 <10 4th Quarter -8093 s330 sQ,2 504 s10 Annual mean i s.d. <330 <1.0 <0.6 <10 I-12 1st Quarter TSWT-0375 <330 <0.9 <0.6 <10 2nd Quader -2885 <330 <1.0 <0.5 <10 3rd Quarter -5816 <330 <1.6 <0.5 <10 4th Quarter -8094 s330 s04 s03 s10 Annual mean i s.d. <1.0 <0.6 <10 I-23 1st Quarter TSWT-0376 <330 <0.9 <0.5 <10 2nd Quader -NSa .. .. .. .. 3rd Quarter -NS -- -- -. -- 4th Quarter -NS = = = = Annual mean i s.d. <330 <0.9 <0.5 <:0 aNS Sample not avellable; location has been dropped from the program. 53
_o___.. 2
. I Tormo r Table 27. Treated surface water samples, quarterly composites of weekly grab samples, analysis for tritium, strontium-89, strontium-90 and gamma-emitting isotopes,1994 (continued). !
j Collection Lab Activity (oCi/D i Location Period Code H-3 Sr 89 ~' Sr-90 Cs-137 Indicator
- I-28 1st Quarter TSWT-0377 <330 <1.1 0.6f0.4 <10 2nd Quarter -2886 <330 <1.0 <0.5 <10 '
3rd Quarter -5817 <330 <1.2 <0.6 <10 4th Quarter -8095 s330 s03 sol s1D Annual mean t s.d. <330 <1.2 0.6i0.4 <10 { I-50 1st Quarter TSWT-0378 <330 <0.8 <0.5 <10 2nd Quarter -2887 <330 <0.9 0.6i0.3 <10 3rd Quarter -5818 <330 <1.2 0.6t0.4 <10 ; 4th Quarter -8096 5330 s02 s04 s1D Annual meani s.d. <330 <1.2 0.6f0.0 <10 ! T-144 1st Quarter TSWT-0379 <330 <0.9 - 0.8i0.4 <10 i 2nd Quarter -2888 <330 <0.8 <0.4 <10-3rd Quarter '5819
<330 <1.0 <0.6 <10 !
4th Quarter -8097 336194 s02 s03 s10 ! i Annual meanis.d. 336194 <1.0 0.8i0.4 <10 i t i i t 4 b l a _ _ _ .. . __ ._. - ~ _
.~ .-. . . .
..~
~
l e TDIFnO $ l i Table 28. : Untreated surface water samples, monthly composites of weekly samples, analyses for gross ! beta, tritium and gamma-emitting isotopes,1994. i Gross Beta Activity (oCi/L)
' Collection Lab . Suspended Dissolved Total Period Activity (pC1/L) !
Code Solids Solids Residue H-3 Cs-137 . T-11 (C) ,
)
January TSWU 5047 <0.2 2.8i0.5 2.8i0.5
'i
<330 <10-February -5239 <0.2 2.510.6 2.Si0.6 <330 <10 March -5570 NAa gga 3.010.5 s330 s1Q !
1st Qtr. mean i s.d. <0.2 2.610.2 2.8i0.3 <330
<10 :
April TSWU 0613 NAa NAa 2.7i0.5 <330- <10 May -1728 -- -- 2.3f0.5 <330 <10 ;
- Jme -2741 -- --
2.110.5 s33Q s10 - 2nd Qtr. mean i s.d. -- -- 2.410.3 <330 <10 ! r July TSWU-3361 NAa NAa ! 1.710.5 5241103b <to August . -4331 NA NA 1.8f0.5 <330 <10 { September -5147 NA NA 1.810.5 s330 s10 -! 3rd Qtr. mean i s.d. NA NA 1.810.1 5241103 <10 ! October TSWU-6483 ' NAa NAa 2.2io.5 <330 <10 November -7154 NA NA l 1.810.4. <330 <10 i December -7936 NA NA 1.810,3 s330 s1D l 4th Qtr. mean i s.d. NA NA 1.910.2 <330 <10 t aNA - Not applicable; specifications cf.anged, deleting analysis. b I Sample was reanalyzed; result of reanalysis is 4891100 pCi/L l f I i i 5 [ t f i i 55 t 1 r . - - - - - -, ...c- . . , m ,- , - - --- _
., . . . . ...- . .. ,. - . . .. . -. ~ .
Torrno i i h Table 28. Untreated surface water samples, monthly composites of weekly samples, analysis for gross I' beta, tritium and gamma-emitting isotopes,1994 (continued). t i Gross Beta Activity (oCi/D i Collection Lab Suspended Dissolved Total _. Activity (pci/L) t Period Code Solids Solids Residue H-3 Cs-137 l 5 T-12 (C)
- January E W U-5048 <0.2 2.410.6 2.410.6
<330 <10 !
February -5240 0.8i0.1 4.5i0.7 5.3i0.4 <330 <10 March gga m
-5571 NAa 3.3f0.5 s10 ,
1st Qtr. mean i s.d. 0.810.1 3.411.5 3.711.5 <330 <10 April TSWU-0614 NAa NAa 1.9i0.5 <330 <10 i May -1729 -- -- 2.4i0.6 <330 <10 m June -2742 -- -- 3.110.5 $10 2nd Qtr. mean i s.d. -- -- 2.510.6 <330 <10 ! July EWU-3362 NAa NAa 1.810.5 <330 l
<10 August -4332 NA NA 2.0f0.5 <330 <10 September -5148 NA NA 2.3fo.5 s330 ~s10 i 3rd Qtr. mean i s.d. NA NA 2.010.3 <330 <10 ,
October TSWU-6484 NAa NAa 2.910.5 <330 <10 November -7155 NA NA 2.210.5 <330 <10 December -7937 NA NA 20 0.3 s33Q s10 i 4th Qtr. mean i s.d. NA NA 2.410.5 <330 <10 i - 1 aNA - Not applicable; specifications changed, deleting analysis. I l i i l l I r 56
Totroo Table 28. Untreated surface water samples, monthly composites of weekly samples, analysis for gross beta, tritium and gamma <mitting isotopes,1994 (continued). Cross Beta Activity (oCi/L) Collection Lab Suspended Dissolved Total _ Activity (pCi/L) Period Code Solids Solids Residue H-3 Cs-137 T-23 (C) January TSWU-4987 <0.3 2.010.4 2.010.4 <330 <10 February -5303 <0.2 1.910.6 1.910.6 <330 <10 March -0074 NAa gga 2.3i0.5 s3310 s1D 1st Qtr. mean i s.d. <0.3 2.010.1 2.110.2 4 30 <10 April NSb .. .. .. .. .. May June 2nd Qtr. mean i s.d. July August September 3rd Qtr. mean i s.d. October November December 4th Qtr. mean i s.d. aNA - Not applicable; specifications changed, deleting analysis. b NS - Sample not available; location dropped from program. l l i l 57
1 TOfFno i Table 28. Untreated surface water samples, monthly composites of weekly samples, analysis for gross beta, tritium and gammt emitting isotopes,1994 (continued). j Gross Beta Activity (oCi/D Co!!ection Lab Suspended. Dissolved Total . Activity {pCi/L) Period Code Solids Solids Residue H-3
. Cs-137 '
i I:3 i january TSWU-5045 <0.2 2.710.6 <330 _2.710.6 <10 February -5237 <0.4 2.310.5 2.3i0.5 - <330 <10 ' March -5568 NAa NAa 10104 s330 s1D 1st Qtr. mean i s.d. <0.4 2.510.3 3.010.9 <330 <10 6 April TSWU-0611 NAa NAa 2.910.6 <330 <10 t May -1726 -- -- 3.4f0.5 <330 <10 June -2739 -- -- 2.90.5 567f100b gig l t 2nd Qtr. mean i s.d. 3.110.3 567i100 <10 i July TSWU-3359 NAa NAa 2.9i0.6 342i92C <10 'i August -4329 NA NA 2.5i0.5 5411103 <10 : September. -5144,5 NA NA 2.3f0.4 s330 s10 t 3rd Qtr. mean i s.d.- NA NA 2.6i0.3 4421140 <10 . t. October 15WU-6481 NAa NAa 2.510.5 621i103 <10 ,
' November -7152 NA NA 2.9i0.5 <330 <10 ;
December -7934 NA NA 2.8f0.5 <330 sia , 4th Qtr. mean i s.d. NA NA 2.710.2 621i103' <10 i aNA - Not applicable; specifications changed, deleting analysis. b , Sample was reanalyzed; result of reanalysis is 5171103 pCi/L. l CSample was reanalyzed; result of reanalysis is 386196 pCi/L 1 i i l l
-I t
i e i I 58
. ?
g-. TOI FDO Table 28. Untreated surface water samples, monthly composites of weekly samples, analysis for gross (+te, tritium and gamma-emitting isotopes,1994 (continued). Cross Beta Activity (pCi/L) Collection Lab Suspended Dissolved Total Activity (pCi/Li Period Code Solids Solids Residue H-3 Cs-137 January TSWU-5050 <0.3 2.610.6 2.610.6 <330 <10 February -5242 <0.2 3.410.6 3.410.6 <330 <10 March -5573 NAa NAa 3.510.6 m m ~ ist Qtr. mean i s.d. <0.3 3.0i0.6 3.210.5 <330 <10 April TSWU-0616,7 NAa NAa 2.810.4 <330 <10 May -1731 -- -- 2.6i0.6 <330 <10 June -2744 -- -- 2.4f0.5 m m 2nd Qtr. mean i s.d. -- -- 2.610.2 <330 <10 July TSWU-3364 NAa NAa 2.610.5 <330 <10 August -4335 NA NA 1.810.5. 390i97 <10 September -S150 NA NA 2.lio.6 m m 3rd Qtr. mean i s.d. NA NA 2.210.4 390197 <10 October TSWU-6486 NAa NAa 1.8i0.4 409195 <10. November -7157- NA NA 2.210.4 <330 <10 December -7939 NA NA 2.2iG 3 m m 4th Qtr. mean i s.d. NA NA 2.110.2 409i95 <10 aNA - Not applicable; specifications changed, deleting analysis. l 59 !
,I
v.~=... s
~. -
*r-~ * * - ^ " ~ ' ~ ' - - ~ -~~ ~ -
TOLEDO Table 28. Untreated surface water samples, monthly composites of weekly samples, analysis for gross beta, tritium and gamma-emitting isotopes,1994 (continued). ; Gmss Beta Activity (pCi/L) Collection Lab Suspended Dissolved Total Activity (pCi/L) Period Code Solids Solids Residue H-3 Cs-137 ' I-50 i
. January *ISWU-5051 <0.2 2.4i0.6 2.4 0.6 <330 <10.
February -5243 <0.4 2.4f0.5 2.410.5 <330 <10
^
March -5574 NA* NAa 3.510 6 s330 slo A ist Qtr. mean i s.d. <0.4 2.410.0 2.810.6 <330 <10 April TSWU-0618 NAa NAa 3.li0.5 <330 <10 i May -1732 -- -- 3.1f0.6 <330 <10 ! June -2745 -- -- 2.210.6 s330 s12 2nd Qtr. mean i s.d. -- -- 2.810.5 <330 <10 < July 15WU-3365 NAa NAa 2.310.5 372193b <10 August -4336 NA NA 2.5f0.7 418i97 <10 September -5151 NA NA 2.1to.5 s330 sig 3rd Qtr. mean i s.d. NA NA 2.3i0.2 395133 <10 ; October TSWU-6487 NA* NAa 1.910.5 502i99 <10 November -7158 NA NA 2.010.4 <330 <10 December -7940,1 NA NA 2.2io.3 s330 sig 4th Qtr. mean i s.d. NA .NA 2.010.2 502199 <10 I aNA - Not applicable; specifications changed, deleting analysis. bSample was reanalyzed; result of reanalysis is 290i93 pCi/L I l I l t 60 1
n l
^
~
. l i
j TOLEDO ~l l Table 29. Untreated surface water samples, monthly composites of weekly samples, analysis for gross beta, tritium and gamma. emitting isotopes,1994. i Cross Beta Activity (oCi/L) ' Collection Lab Suspended Dissolved Total Period Activity (oCi/L) ; Code Solids - Solids Residue H3 Cs-137 i T-145 (OC) ' January 15WU-5052 ,3 <0.3 2.410.4 2.410.4 <330 ;
<10 February -5244 <0.4 1.7i0.5 1.7i0.5 <330 <10 ;
March -5575 NAa gga .4.00.6 ' 5330 s.10 1st Qtr. mean i s.d. <0.4 2.0f0.5 2.711.2 <330 <10 April 15WU-0619 NAa NAa 3.010.5 ' <330 <10 May -1733 -- -- 4.lio.6 <330 <10 ; June -2746 -- -- 2Jt03 562ig9b g l 1 2nd Qtr. mean i s.d. -- -- 3.310.7 562i99. <10 ? P f July TSWU-3366 NAa NAa 2.6i0.5 <330 <10 , August -4337 NA NA 2.1i0.5 466i110 <10 September NA' i
--5152 NA 2.4*0.5 s330 m 3rd Qtr. mean i s.d. NA NA 2.4i0.3 4661110 <10 I October 'I5WU-6488 NAa NAa 2.lio.5 6371103 <10 'h November -7159 NA NA 2.Si0.5 <330 <10 !
December -7942 NA NA 2.4 0.3 s330 sia
' 4th Qtr. mean i s.d. NA NA 2.310.2 637i103 <10 aNA - Not applicable; specifications changed, deleting analysis. ;
b Sample was scanalyzed; results of reanalysis is 5361104 pCi/L. 4 e f t
,f i
t 61 !
_ ._ _ _ . ._. 1 1 ' ~ TOLEDO
)i I
i Table 30. Untreated surface water samples, quarterly composites of weekly grab samples, analysis for strontium-89 and strontium-90,1994. Collection Lab Activity (oCi/D l Location Period Code Sr-89 Sr-90 l Control l I 1st Quarter TSWU-0381 <0.9 0.7f0.3 I 2nd Quarter -3054 <1.1 <0.5 3rd Quarter -5748 <1.1 <0.5 l 4th Quarter -8125 sLQ sQl ; Annual mean is.d. <1.1 0.7i0.3 I-12 1st Quarter TSWU-0382 <0.9 <0.5 l 2nd Quarter -3055 <0.9 <0.4 3rd Quarter -5749 <1.1 <0.6 ( 4th Quarter -8126 101 0.6fD.4 l Annual mean is.d. <1.1 0.610.4 l t I-23 1st Quarter TSWU-0383 <0.8 0.Si0.3 2nd Quarter -NSa -- - 3rd Quarter -NS -- -- 4th Quarter -NS = = Annual mean i s.d. <0.8 0.5i0.3 aNS = No Sample; location dropped from program. f I
)
1
)
t I i 62 ,
IDLERO Table 30. Untreated surface water samples, quarterly composites of weeldy grab samples, analysis for strontium-89 and strontium-90,1994 (continued). Collection Lab ActiYity (DCi/I] Location Period Code St-89 Sr 90 Indicator I-3 1st Quarter TSWU-0380 <0.8 0.610.3 2nd Quarter -3053 <1.0 <0.5 3rd Quarter -5747 <1.1 <0.5 4th Quarter -8124 s01 515 Annual mean i s.d. <1.1 0.610.3 I-28 1st Quarter TSWU-0384 <0.9 <0.5 2nd Quarter -3056,7 <0.8 <0A 3rd Quarter -5750 <1.2 <0.5 4th Quarter -8127 s01 sQ,6 Annual mean i s.d. <1.2 <0.6 I:-50 1st Quarter TSWU-0385 <0.9 <0.5 2nd Quarter -3058 <0.9 0.710.3 3rd Quarter -5751 <1.1 <0.5 4th Quarter -8129 501 50.5 Annual mean 2 s.d. < 1.1 0.7i0.3 l l t I 63
9 TOLEDO Table 31. Untreated surface lake water samples, weekly grab samples, analysis for gross beta, I tritium and gamma-emitting isotopes, collected May through October,1994. Gross Beta Activity (oCi/L) Activity (pCi/L) Lab Total Location Period Code Residue H-3 Cs-137 T-131 (MAY) 15 W U-1715 2.6f0.6 <330 <10 (JUNE) -2106 2.510.5 <330 <10 OULY) -3367 1.910.6 <330 <10 (AUGUST) -4338 2.010.5 <330 <10 (SEPTEMBER) -5153 1.710.4 <330 <10 (OCTOBER) -6489,90 2.010.3 753176 <10 T-132 (MAY) TSWU-1716 2.7t0.6 <330 <10 OUNE) -2107 2.510.5 <330 <10 QULY' -3368 2.0i0.6 <330 <10 (AUGUST) -4339 2.5i0.5 <330 <10 (SEPTEMBER) -5154 1.7i0.6 <330 <10 (OCTOBER) -6491 1.6i0.5 8201109 <10 T-133 (MAY) TSWU-1717 2.510.6 <330 <10 (JUNE) -2108 2.4t3.5 <330 <10 OULY) -3369 2.0id.5 <330 <10 (AUGUST) -4340 1.810.4 <330 <10 (SEPTEMBER) -5155 2.310.5 <330 <10 (OCTOBER) -6492 2.410.5 9591113 <10 64
.. - -. - .- - _ . . . - = . - - ~ . .
t IRLERQ Table 31. Untreated surface lake water samples, weekly grab samples, analysis for gross beta, tritium and gamma-emitting isotopes, colk<ted May through October,1994 (continued). t Gross Beta Activity (oCi/L) Activity (pCi/L) Lab Total Location Period Code i Residue -' H-3 Cs 137 e T-134 (MAY) TSWU 1721 l 2.910.6 <330 <10 i 00NE) 2109 2.210.5 <330 <10
- OULY) -3370 2.lio.5 <330 <10 (AUGUST) -4341 2.210.5 <330 <10 (SEPTEMBER) 515e 2.510.5. <330 <10 (OCTOBER) -6493 2.510.5 9171112 <10 i T 135 (MAY) TSWU-1718,9 2.910.4 <330 <10 0UNE) -2110 2.410.5 <330 . <10 OULY) -3375 1.810.5 <330 <10 (AUGUST) -4342 1.9f0.5 <330 <10 (SEPTEMBER) -5157 2.710.5 <330 <10 i (OCTOBER) -6494 2.lio.5 12561123
<10.
T-137 (C) (MAY) ~I3WU-1720 2.910.6 <330 <10 GUNE) -2111 2.210.5 <330 <10
. OULY) -3371 1.510.6 <330 <10 (AUGUST) -4343 2.0i0.5 <330 <10 .
(SEPTEMBER) -5158 2.510.6 <330 <10 ; (OCTOBER) -6495 1.710.4 389194 <10 I l L I t I i
'?
b h L k r t 4 65
TOfFnO Table 31. Untreated surface lake water samples, weekly grab samples, analysis for gross beta, tritium and gamma emitting isotopes, collected May through October,1994 (continued). I Gross Beta Activity (oCi/L) Activity (oCi/Q__, Lab Total Location Period Code Residue H-3 Cs-137 i T-152 : (MAY) TSWU-1722 3.210.6 <330 <10 OUNE) -2112 3.410.6 <330
<10 GULY) -3372 4.310.8 <330
<10 (AUGUST) -4307 3.2f0.6 <330 <10 (SEPTEMBER) -5159 2.410.6 <330 <10 (OCTOBER) -6496 2.310.5 <330
<10 T-158 (C) (MAY) - TSWU-1723 2.5f0.6 <330 <10 0UNE) -2113 2.510.5 <330 <10 OULY) -3373 2.310.6 <330
<10 j (AUGUST) -4308,9 2.lf0.4 <330 <10 (SEPTEMBER) -5160 2.510.6 <330 <10 i (OCTOBER) -6497 1.810.5 338i92' ,
<10 ;
T-162 (C) (MAY) TSWU-1724 2.110.5 <330 <10 ! OUNE) -2114 2.7i0.5 <330 <10 (JULY) -3376 1.8i0.6 <330 <10 } (AUGUST) -4344 2.lio.5 <330 <10 (SEPTEMBER) -5161 1.6i0.6 <330 <10 ' (OCTOBER) -6498 2.0f0.4 <330 <10 I i
)
4
TOLEDO Table 31. Untreated surface lake water samples, weekly grab samples, analysis for gross beta, tritium and gamma-emitting isotopes, collected May through October,1994 (continued). Gross Beta Activity (oCi/L) Activity (oCi/L) Lab Total Location Period Code Residue H-3 Cs-137 T-167 (C) (MAY) T5WU-1725 2.410.5 <330 <10 OUNE) -2115 2.610.5 <330 <10 OULY) -3374 2.6i0.5 <330 <10 (AUGUST) -4345 2.210.5 <330 <10 (SEPTEMBER) -5162 2.0i0.5 <330 <10 (OCTOBER) -6499 1.610.4 <330 <10 l 67
a ; TOLEDO 1 i i Table 32. Fish samples, analyses for gross beta and gamma-emitting isotopes. Collection: Semiannually. Sample Description and Activity (pCi/g wet) IndicMnr Contml l Location T-33 (Imka Erie 1.5 ml NE of Station 1 T-E Collection Date 05-20-94 05-20-94 05-2494 05-18-94 1 05-18-94 05-18-94 lab Code TF-1386 TF-1387 T0-1388 TF-1287 TF 1288 TF-1289 Sample Type White Bass Carp Walleye White Perch Walleye Carp Gross Beta 2.4510.09 3.5310.11 4.08i0.12 2.90i0.09 3.94i0.13 3.49i0.12 > K-40 2.8310.40 2.3310.48 3.4510.32 2.59i0.22 3.4210.27 2.5910.30 Cs-137 0.020 <0.025 <0.016 <0.010 <0.014 <0.014 : Location T-33 (I mka Erie 1.5 mi NE of Station) T-E Collection Date Lab Code Sample Type Gross Beta t K-40 Cs-137 t NOTE: Page 69 is intentionally left out. i l i e 68 b
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TOfSDO , Table 33. Shoreline sediment samples, analysis for gamma-emitting isotopes. , Collection: Semiannually. Sample Description and Activity (pCi/g dry) Location T-3 T-4 T-132 T-27 (C) Collection Date 05-02-94 05-02-94 05-02-94 08-24-94 Lab Code TSS-0814 TSS-0815 TSS-0817 TSS-4306 . K-40 16.37i0.55 15.2110.57 13.2510.48- 14.7210.99 Mn-54 <0.014 <0.015 <0.013 <0.041 Co-58 <0.011 <0.026 <0.023 <0.062 Co-60 <0.021 <0.021 <0.012 <0.043 Cs 134 <0.034 <0.051 <0.039 <0.089 Cs-137 <0.015 0.05410.022 <0.014 0.135i0.059 Location T-3 T-4P T-4 T-27 (C) Collection Date 10-21-94 10-21-94 10-21-94 10-21-94 Lab Code TSS-6157 TSS-6158 TSS-6159 TSS-6160 K-40 16.711103 15.1210.99 23.45i1.68 14.66fl.00 Mn-54 <0.041 <0.042 <0.050 <0.028 Co-58 <0.073 <0.055 <0.034 <0.058 Co <0.026 <0.040 <0.070 <0.016 Ca-134 <0.074 <0.085 <0.028 <0.080 Cs-137 <0.044 <0.041 <0.074 <0.028 Location Collection Date Lab Code K-40 Mn-54
- Co-58 Co-60 Cs-134 l Cs-137 Note: Page 71 is intentionally left out. ;
1 I l ,7
y nnen. , . .n- ng . " ~ * * * * ' ( TOIFnO Table 34. I Egg samples, analysis for gamma-emitting isotopes. Collection: Annually. . Sample Description and Activity (pCi/g wet) t
' Location T-34 (C) T-197 f
Date 10-06-94 1 10-06-94 ! Lab Code TE-5599 TE-5600 c
- K-40 1.5610.31 Nb-95 1.36i0.28
<0.012 L <0.008 I Zr-95 . <0.026 <0.012 i Ru 103 <0.011 <0.013 Ru 106 <0.12 <0.059 ;
Cs-137 <0.012 <0.008 Ce-141 <0.024 <0.017 Ce-144 <0.055 <0.056 . I E t I 1
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I I 72
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