ML20073H069
| ML20073H069 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/31/1990 |
| From: | CENTERIOR ENERGY, TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20073H050 | List: |
| References | |
| NUDOCS 9105060158 | |
| Download: ML20073H069 (280) | |
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I 1 l ANNUAL ENVIRONMENTAL OPERATING REPORT: l l for DAVIS - BESSE NUCLEAR POWER STATION l January 1,1990 to December 31,1990 Prepared by: Radiological Environmental Davls Besse Nuclear Power Station Toledo Edison Company Toledo, Ohio April 1991
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Stat 6cn Table of Contents Title Page List of Tables sill List of Figures x Summary xill Introduction 11 e Fundamentals 11 The Atom 11 Isotopes 12 e Radiation and Radioactivity 12 Radionuclides 12 Radiation 13 Radioactive Decay 1-4 Half Ufc l-4 e Interaction with Matter 1-4 fonization 1-4 Range and Shielding 15 e Quantities and Units of Measurement 17 Activity: Curie 17 Exposure: Roentgen 18 Absorbed Dose: Rad 18 Dose Equivalent: Rem 19 e Sources of Radiation 19 Background Radiation 19 l i
Annual Environmental Operating Report 1903 Davis Besse Nuclear Power Station Table of Contents (continued) Title Page e Sources of Radiation (continued) Man Made Radiation 1 13 e llealth Effects of Radiation 1 14 Studies 1 14 1-lealth Risks 1 14 e Benefits of Nuclear Power 1 17 e Where Does Electricity Come From? 1-18 The Use of Steam to Produce Electricity 1 19 e Nuclear Power Production 1 20 What is Fission? 1 20 Nuclear Fuel 1 21 The Reactor Core 1 22 Fission Control 1-22 Reactor Types 1 23 e Station Systems 1 24 Containment Building and Fission Product 1 26 Release Barriers The Steam Generators 1 27
%e Tbrbine Generator 1-27 The Condenser 1 28 The Cooling'Ibwer 1 28 Miscellaneous Safety Systems 1 29 e Reactor Safety Summary 1-30 Description of the Davis Besse Site 1 32 The 1990 Radioactive Liquid and Gaseous Emuents Summary 1 35
- Protection Standards 1-35
- Limits 1 35 e Sources 1 36
- Noble Gas 1 37 e lodine and Particulates 1 37 i
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L Annual Environtnental Operating Report 1990 Davis Besse Nuclear Power Station f' Thble of Contents (continued) Title _ Page : e Tritit:m 1 38 e Pror.t.ssing and Monitoring 1 38 . e E:posure Pathways 1 39 e Dose Assessment 1-41 e Results 1-41 References 1-43 . Radiological Environmental Monitoring Program 21 e introduction 2-1 e PreoperationalSurveillance Program 22 ; e Operational Surveillance Program Objectives 2-3 e Ouality Assurance 23-e Program Description 25 Overview 24 ' Sampling Locations' 27 Sample Analyses 2 28 e Sample History Comparison 2 29 ~ Atmospheric Monitoring 2 31 Terrestrial Monitoring- 2-32
-Aquatic Monitoring .2 33 Direct Radiation Monitoring 2 33 1990 Sampling Program - 2 34 e :1990 Program Deviations 2 36 e- Atmospheric Monitoring 2 37 Airborne Particulates 2 38-2 39 Airborne lodine 131 Snow 240 e- Terrestrial Monitoring 2-40 Groundwater 2 43 Milk - 2 41 Meat 2-44 i
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~ Annual Environmental Opereting Report 1990 Davis Besse Nuclear Power Station Thble of Contents (continued) Title Page Broad Leaf Vegetation and Fruit 2-45 Animal / Wildlife Feed 2-46 Soil 2-47 e Aquatic Monitoring- 2-49 Treated Surface Water 2-49 Untreated Surface Water 2 50 : Fist 2 53 - Shoteline Sediments 2 54 e Direct Radiation Monitoring 2-54 Thermoluminescent Dosirneters 2 55 Quality Control TLDs 2 56 NRC TLD-Monitoring 2 56 e Conclusion 2 58 References 2 59 Land use Census 3 1. e : Program Design 3-1 i e Methodology 32 , e Results 32 Meteorological Monitoring : '41 e Introduction 41
- e. Onsite Meteorological Monitoring 42 System Description 42 ;
MeteorologicalInstrumentation . 4-2 Meteorological System Maintenance and Calibration . 4-4
- Meteorological Data Handling and Reduction 45 Meteorological Data Recovery 4-5~
e Meteorological Data Summaries . . 4 6l
- Wind Speed and Wind Direction 47
. AmbientTemperature 47 ,
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Armual Environmental Operating Report 1990 Davls Besse Nuclear Power Station Table of Contents (continued) Title _ Page Dew Point Temperature 47 Precipitation 4 20 Atmospheric Stability
- 4 20 e Local Wind Patterns ' 4 20 Lake / Land Breeze 4 21 Lake Level Monitoring 4 23 Remote Sensing 4 25 Marsh Management 51 e' Navarre Marsh 51 e SpecialProjectsin 1990 56 References - 58 Zebra Mussel Control 61 e Introductiot 61 o Monitoring- 62 o Research 63 Water Treatment 71 i e Water Treatment Plant Operation 71 Description - 71 Clarifier Operation- 72 ;
Flow Measurements 72 e Wastewater Treatment Plant Operation 73 Summary of 1990 Wastewater Treatment 75 Plant Operations National Pollutant Discharge Elimination 75 System (NPDES) Reporting _ e 1990 NPDES Summary 77 Outfall 001 7 7-Outfall 002 77
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l i Annual Environmental Operating Report 1990 Davis-Besse Nuclear Power Station Table of Contents (continued) Title Page Outfall 003 77 Outfall 601 77 Outfall 602 78 Sampling Point 801 78 Chemical Waste Management Program 81 e Regulations Governing Chemical Materials 81 Resource Conservation and Recovery Act (RCRA) 81 Hazardous and Solid Waste Amendment (HWSA) 82 Comprehensive Emironmental Response, Compensation and Liability Act (CERCLA) 82 Superfund Amendment and Reauthorization Act (SARA) 83 Toxic Substances Control Act (TSCA) 8-3 Transportation Safety Act 83 Clean Air Act 83 e Compliance with Chemical Materials Regulations 84 Compliance with RCRA and HWSA 8-4 Weekly inspections of Chemical 84 Waste Storage Accumulation Areas identification of Unknown Chemicals 85 Written Inspection Reports 85 Waste Minimization 85 Compliance with CERCLA and SARA 8-6 Compliance with TSCA 87 Compliance with the Transportation Safety Act 88 Compliance with the Clean Air 88 Audits and Inspections 88 e Other Programs 89 Underground Storage Tanks 89 Fuel Storage Thnk Service Bldg #4 8 10 100,000 Gallon Diesel Fuel Oil Storage Tank 8 10 i Fire Training Area Modification 8 10 Burn Permits 8 10 vi
I Annual Environmental Operating Report 1500 Davis Besse Nuclear Power Station l Table of Contents (continued) i I Title Page Spill Control Kits 8 11 Testing of Wa!!c Oil 8 11 Waste Inventery Forms 8 11 Chemical Approval 8 11 Appendices e Appendix A: Glossary A1 e Appendix B:Interlaboratory Comparison Program B-1 e Appendix C: Data Reporting Conventions C1 e Appendix D: Maximum Permissible Concentrations of D1 l Radioactivity in Air and Water Above Natural Background in Unrestricted Areas e Appendix E: REMP Sampling Summary E1 vil
Annual Env6tonmental Operating Report ifKC Davis Besse Nuclear Power Station List of'Ihbles Table No. Page No. Title 11 13 Isotopes of Uranium 12 1 16 Risk Factors 13 1 36 Dose Limits to a Member of the Public 14 1 42 19X) Offsite Doses to Ibe Public due to kadioactivity Released in Gaseous and Liquid Elliuents 21 26 Sarnple Codes and Collection Frequencies 22 2 19 Description of REMP Sampling Locations and *I) pes of Samples Collected at Each 23 2 30 Radiochemical Analyses Performed on REMP Samples 24 2 35 Sample Collection Summary 2! 2 38 Average Concentration of Beta Emitting Radionuclides in Airtorne Particulate Samples 31 3-6 Closest Exposure Pathways Present 190 32 3-9 Pathway Locations and Corresponding Atmospheric Dispersion (X/0) and Deposition Parameters (D/0) 41 4 28 Summary of Meteorological Data Recovery for DBNPS,19A) vill
Annual Environmental OperatinJ Report 1990 Davis Besse Nuc. ear Power Station List of Tables (continued) Table No. Page No. Title 42 4 29 Summary of hieteorological Data hicasured at DBNPS,19X) 41 4 27 Summary of hieteorologicalInstrumentation at DBNPS 4-1 4 31 Classification of hieteorological Data and Pasquill Stability 4-4 4 32 hionthly and Annual Stability Class Frequency Distributions Based on Delta T (100m 10m),19X) 4-5 4-33 hionthly and Annual Stability Class Frequency Distributions Based on Delta T (75m 10m),1W 4-6 4-M DBNPS Stability Classes by llour of Day for 19X), Based on 100m 10m Delta T 4-7 4-35 DBNPS Stability Classes by Hour of Day for 1990, Based on 75m 10m Delta T l lx
1 I y Annual Environmental Operating Report 1990 Dav!s Besse Nuclear Power Station I j List ofFigures ! 1 l Figure No. Page No. - Title 11 12 The Atom 12 15 Half lifeDiagram of Cobalt 60 J 13 16 Range and Shielding of Radiation 14 17 The Curie, a Measure of ActMty 1.$ 1 10 - Sources of Radiation 16 1 17 Comparison of Nuclear with Other Energy Sources 1980 and 1989 - 17 1 19 Eleetrical Geocration 18 1 20 Fiulon Diagram - 19 1 22 Fuel Rod, Fuel Anembly and Reactor Veuel
.1 10 1 25 - Schematic of the Davis Besse Nuclear Power Station
- 1 11 : 1 26 - Finion Product Release Barriers 1 12 - 1 32 Map of Area Surrounding Davis Besse 1 13- 1 40 - External Exposure Ps:hways 1 14 : 140 = Intesnal Exposure Pathways 21 ~ 2 8.: Sampling Locations on the Davis Beue Site 22 29 ; Sampling Locations within a Five Mile Radius X
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Annual Environmental Operating Report 1 930 Davis Besse Nuclear Power Station List of Figures (continued) Figure No. Page No. Title 23 2 10 Sarnpling Locations within a Ten Mile Radius 2-4 2 11 Sarnpling L.ocations s '.:hin Lake Erie , 25 2M REMP Samples Collected and Analyses Performed since 1987 26 2 39 Air Samples: Grou Beta 27 2 42 Milk Samples: Concentration of St 90 28 2 48 Soil Samples: Concentration of Cs 137 29 2 50 Treated Surface Water Samples: Grou Beta 2 10 2-51 Untreated Surface Water Samples: Grou Beta 2 11 2 53 Fish Samples: Gross Beta,lndicator vr. Control Locations 2 12 2 55 TLD Samples: Comparison of Doses Measured Since 1987 2 13 2 57 Comparison of NRC vs Davis Besse TLD since 1987 3-1 35 Land Use Census Map
&1 43 Color Satelhte it.nage of the Globe 4-2 43 Color Satellite image of North America during Hurricane Hugo 43 44 Transmission of Meteorolcgical Data from Met Towers 4-4 48 100 Meter %d Rose A$ 4 12 75 Meter Wind Rose 4-6 4 16 10 Meter Wind Rose List of Figures (continued) xi
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Annual Environrnental Operating Report 1930 Davis Besse Nuclear Power Station l'igure No. Page No. Title 47 4 22 Local W'md Patterns Over Lake Eric: Lake Brecte Effect 48 4 22 Local Wind Patterns Over Lake Erie: Land Urcere Effect 51 52 Use of Dike to Retain Water 52 52 Use of Revetment to Encourage !)each Formation 53 54 Water Levels and Corresponding Plant Communities in the Navarre hlarsh , 5-4 55 Beach Formed at the Base of Revetment 41 41 Zebra htuuel G2 44 Zebta htussel(Graph) 43 45 hiussel Study Device 71 7-4 Moor Plan of the Wastewater heatment Plant 723 73 Latoratory Analyses Performed Daily at Wastewater Deatment Plant 8-1 8-4 Inspection of the Chemical Waste Storage Area 8-2 87 VisualInspection of PCil hansformer I I l l xil l
, Annual Environmental Operating Report 1990 DaAs Ber4e Nuclear Power Station Summary The Annual Emironmental Operating Report is a detailed report on the Emi-ronmental hionitoring Programs conducted at the Davis Besse Nuclear Power Station from January 1 through December 31,1990. Reports included are the Radiological Emironmental hionitoring, Land Use Census, hieteorological hionitoring, hiarsh hinnagement, Zebra hiussel Control, Water Treatment, and Chemical Waste hinnagement Programs. Radiological Environmental Monitoring Program The operation of a nuclear power station results in the release of small amounts of radioactisity to the surrounding emironment. However, the releases must comply with stringent regulations imposed by the Nuclear Regulatory Commis-sion (NRC). Radiological Emironmental hionitoring Program ( REhtP) has been established to monitor the radiological conditions in the environment around Davis Besse, This program includes the sampling and analysis of emiron-mental samples, and the evaluation of the effects of releases of radioactivity on the emironment. Radiation and radioactivity are monitored around Davis Besse within a 25 mile radius. The environment around Davis Besse has been monitored for radiation and radioactivity for approximately 19 years. REhiP was established at Davis. Besse about five years before the Station became operational. This program pro-vided data on background radiation and radioactivity which is normally present in the area. Davis Besse has continued to monitor the emironment by sampling air, groundwater, milk, edible meat, fruits and vegetables, animal feed, soil, drinking water, surface water, fish, and shoreline sediments, as well as by measur-ing radiation directly. Samples are collected from both indicator and control locations. Indicator loca-tions are within approximately 5 miles of the site, and are expected to show any increases or buildup of radioactivity that might occur due to the operation of Davis Besse. Controllocations are farther away from the Station, and are i xill
Annual Environmental Operating Report HOO Davis Besse Nuclear Power Station expected to indicate the presence of only naturally occurring radioactivity. The results obtained from the samples collected frorn indicator locations are com-pared with the results from those collected from control locations and with the concentrations present in the emironment before Davis Besse became opera-tional. This allows for the assessment of any impact the operation of Davis-Besse might have had on the surrounding environment. in 1990, over 2700 radiological environmental samples were collected, and over 3200 analyses for radioactivity were performed. Radionuclide concentrations measured at indicator locations were compared with concentrations measured at control locations, as well as those measured in previous studies. The results of the REMP indicate the adequacy of the control of the release of radioactivity in effluents at Davis Besse. These results also indicate that Davis-Besse complies with all applicable federal regulations. These results are divided into four sections: atmospheric monitoring, terrestrial monitoring, aquatic moni-toring and direct radiation monitoring, e Samples of air and snow are collected to monitor the atmosphere. The 1990 results are similar to those observed in preoperational and previous operational programs. Only background radioactivity normally present in the em*ironment was detected, and only at normal concentrations. e Terrestrial monitoring includes analysis of milk, groundwater, meat, fruits, vegetables, animal feed and soil samples. The results of the sample analyses compare favorably with those of previous years. For example, cesium 137 radioactisity in soil was at an average concentration of 0.39 picoeuries per gram dry weight (pCi/g) in 1990, which is at the low end of the range of 0.014 to 3.44 pCi/g dry weight observed over the past 12 years of Station operation. The results of the analyses of the other terrestrial samples also indicate concentrations of radioactivity similar to previous years, and indicate no buildup of radioactivity attributable to the operation of Davis Besse.
- Aquatic monitoringincludes the collection and analysis of drinking water, untreated surface water, fish, and shoreline sediments. The 1990 results of these analyses indicate normal background concentrations of radionuclides, and show no increase or buildup in radioactivity due to the operation of Dasis Besse.
- Direct radiation measurements averaged 15.6 mrem /91 days at indicator locations and 16.6 mrem /91 days at control locations, showing that, in 1990, radiation in the area of Davis Besse was similiar to radiation at locations greater than 5 miles away from the Station.
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' Annual Environmental Operating Report 1500 Davis Besse Nuclear Power Station The 1990 operation of Davis Besse caused no measurable increase in the concen-trations of radionuclides in the emironment and no significant change in the quality of the emironment. All radioactivity released in the Station's ef0uents was well below the applicable federal regulatory limits. The estimated radiation dose to the general public due to the operation of Davis Besse in 1990 was also well below all applicable regulatory limits, in order to estimate this radiation dose, the pathways through which public expo-sure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the REhtP. During the census, Davis-Besse personnel travel every public road within a five trile radius of the Station vent to locate the radiological exposure pathways. One pathway of particular con-cern is the pathway that, for a specific radionuclide, provides the greatest dose to a sector of the population, and is called the critical pathway. In 1990, the critical pathway changed from the child / vegetation pathway at 980 meters in the west sec-tor to an infant / milk pathway at 4270 meters in the west southwest sector.The garden at 980 meters in the west was present in 1989, but was not present during the 1990 Land Use Census. Meteorological Monitoring The hieteorological hionitoring Program at Davis Besse is part of a program for evaluating the effects of the routine operation of Davis Besse on the surrounding emironment. hieteorological monitoring began in October 1968. hieteorologi-calinstrurnents measure continuously and are monitored daily by meteorological monitoring personnel, hieteorological data recorded at Davis Besse include wind speed, wind direction, sigma theta (standard deviation of wind direction), ambient (outside air) temper. ature, differential temperature (air temperature at one height minus air tempera-ture at another height), dew point temperature (air temperature where moisture begins to condense out cf 6 or 100% relative humidity) and precipitation. Two instrument equipped meteorological towers are used to collect data. Data recovery for 1990 was 90% or greater for all measured parameters. In 1990, the data recovery for the six instruments required to be operational by Davis Besse Technical Specifications was greater than 90%. xy
Annual Environmor.tsi Operating Qeport IVJO Davls Besse Nuclear Power Station Marsh Managenent 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 man-ages it as part of the Ottawa National Wildlife Refuge. At Davis Besse, Environ-mental Compliance personnel are responsible for inspecting the marsh and reporting on its status monthly. Special projects conducted in 1990 included song bird, duck, and Canada goose banding, as well as studies of yellow warblers, Canada geese and wood ducks, in 1990, over 8011 individual birds were banded. In addition, unwanted and dinup-tive plant species, such as purple loosestrife (Lythrum salicaria) and the giant reed (Phragmites custrallr), were controlled in order to enhance the ability of the marsh to support the resident wildlife. Zebra Mussel Control The zebra mussel control program was implemented in 1990 to study the extent of musselinfestation at Davis Besse. Routine sampling and analyses of water from various location at the station provides estimates of the number of zebra mussels which might enter the plant. In addition to the sampling, Davis Besse and the Electric Power Research institute are conducting experiments to determine alternate methods for control-ling the zebra mussel for use here and thoughout the range of the mussel. Water Treatment Davis Besse uses Lake Erie as a source of water for the Water'neatment Plant. The water is treated at the site to provide drinking water for site personnel and to produce high purity water for use in the Station's cooling systems. Notable activities in 1990 included the replacement of domestic flow measurement ' desices. Wastewater generated by site personnelis treated onsite at the Davis Besse Wastewater Treatment Plant. The wastermter is processed and then pumped to holding basins where further reduction in solid content takes place. Following many days in the basin, the wastewater is discharged, along with other Station xyl
d 1 l Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station ' waste waters, back to Lake Erie. Por 19vd, Waste \Wter "Deatment Plant Num-
- ber 1 was out of service d1e to damage to an interior tank. The installation of supports have correct the ,doHem and the plant should be back in operation .
earlyin 1991. Current plans are to remove Wastewater Treatment Plant Num-ber 2 from service for cleaning and maintenance in 1991. Chemical Waste Management The Chemical Waste Manarment Program at Davis Besse was developed to en-sure that the offsite dispon ; nf nonradioactive chemical, hazardous, and non. hazardous wr.stes is performed in accordance with all applicable state and federal regulations. Davir Be,se uses the best available technology, such as incineration or treatment to redun t Mcity, for offsite disposing of its chemical wastes in
, order to protect human, : alth and the environment.
In 1990, as a result of waste minimization efforts,414 gallons of hazardous waste (used solvents),19,640 gallons of waste oil and 129 lead acid battery cells were sent to recycling firms and fuel blenders for thermal energy recovery, in 1990, Davis Desse generated 26% less hazardous waste (by vo.lume) than in 1989. As required by SARA, Davis Besse had ten haurdous products and chemicis on site in sufficient quantities to report to local and state agencies.'lko of the chemi-cal wer--xt w.ely hazardous substances, hydrazine and sulfuric acid. , As part of the ; rogram to remove PCB Ould from Davis Besse, ten PCB trans-formers were retrofilled the fifth (final) time in 1990,These will be sampled and analyzed in 1991 and possibly re classified to non PCD. One of these transform- , ers , DF-4, was re . "' id as non.PCB in 1990. Appendices Appendix A contains a Glossary of terms used throughout this report, it is not 1,icant to be a comprehensive reference source for interpreting any documents other than this 1990 Annual Emironmental Operating Report for the Davis-
. Besse Nuclear Pcwer Station.
Appendix B contains results from the interlaboratory Comparison Program re' t quired by Davis Besse Technical SpecificationL Samples with known concentra-L tions of radioisotopes are prepared by the Emironmenta! Protection Agency L (EPA), and then sent (with information on sample type and date of collection j only) to the laboratory contracted by the Davis Desse Nuclear Power Station to
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l Annual Environmental Operahno Report 19Ts Davis Besse Nuclear Power Station 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 labora-tory and the EPA are provided in Appendix B. Appendix C contains data reporting conventions used in the REMP at Davis-Besse.The appendix prosides an explanation of the format and computational methods used in reporting REMP data. Information on counting uncertainties, and computation of averages and standard deviations is also provided. Appendix D lists the maximum permissible concentrations of alpha and beta emitting radioisotoes and of certain other radioisotopes in air and water samples. These concents atioru are taken directly from the Code of Federal Regulations, and provide comparison values for actual REMP sampling results for 1990. Appendix E provides a REMP sampling summary for 1990.The appendix pro-vides a listing of the following for each sample type; e the number and types of analyses performed e the lower limit of detection for caen analysis e the mean and range of results for control and Indicator locations e the mearu range, and location description for the location with the highest annu.tl mean e the number of non toutine results For detailed studies, Appendix E will provide more specific information than that listed in Chapter 2 of this report. Additionally, more specific information is submitted to the NRC in Attachment 1.This attachment is not distributed with the rest of the Annual Erwironmental Operating Report due to itslarge size and technical nature.The information presented in Appendices B through E were provided by Teledyne Isotopes Midwest Laboratories in their Annual Report to Toledo Edison (Part 1, Feb.1991). xvill i
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Annual Environmental Operating Report 1990 Csvis-Besse Nuclear Power Station Introduction Coal, oil, natural gas, and hydropower have been used to run the nation's elec-tric generating stations; however, each method has its drawbacks. Coal fired power can affect the emironment through mining, acid rain, and airborne dis-charges. Oil and natural gas are in limited supply and are therefore costly, and hydropower is limited due to the environmentalimpact of damming our water-ways and the scarcity of suitable sites in our country. Nuclear energy provides an alternate source of energy which is readily available. The operation of nuclear power stations has a very small impact on the emiron-ment. 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 Ref-uge, the only national refuge in the State of Ohio. In order to more fully understand this unique source of energy, background infor-mation on basic radiation characteristics, risk assessment, reactor operation, and effluent control,is provided in this chapter. Fundamentals The Atom All matter consists 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 1-1). The rela-tively large protons and neut'rons are packed tightly together in a cluster at the center of the atom, called the nucleus. Orbiting around this nucleus are one or more of the 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 enarges, the protons and electrons have a strong attraction for each other, which helps to hold the atom together. I 1 11
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j,_ to.or. tis si orbYt Figure 1 1: An atom consists of two parts: a nucleus containing posi-tively charged protons and electrically neutral neutrons and one or more negatively charged electrons orbiting the nucleus. Protons and neutrons are nearly identical in size and weight, while each is about 2000 times heavier than an electron. Other attractive forces between the protons and neutrons keep the densely packed protons from repelling each other, preventing the nucleus from breaking apart. Isotopes A group of identical atoms, contair.ing the same number of protons, make up an element. In fact, . number of protons an atom contains determines its chemi-cal 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 a different number of neutrons, are called isotopes. As an example, Table 1-1 lists some of the isotopes of uranium. Different isotopes of the same element have the same chemical properties, and many are stable, or nonradioactive. A ra. dioactive isotope of an element is called a radioisotope. Radiation and Radioactivity Radionucr, des The parts of an atom are normally in a balanced, or stable state. If the nucleus of an atom contains an excess of energy, it is called a radioisotope, radioactive atom or a radionuclide. The excess energy is usually due to an excess riumber of neu-trons in the nucleus of the atom. 12
Annual Environmental Operating Report 1990 Davis Besso Nuclear Power Station Radionuclides can be naturally occurring, st.ch as uranium 238, beryllium 7, and _d potassium-40, or man made, such as iodine 131, cesium 137, and cobalt 60. Table 1 1: Isotopes of Uranium Isotope Symbol #of Protons #of Neutrons U ra ni u m 23 5 ... . . . . . . .. ... . . .. . ....
- U . . . ... . . . . .. . . . . . . . . . .. . . . .. . ... . . 92 .. .. . . . . . . .. . . . .
Uranium-23 6 . . . . . . . . . . . . . . . . . . . . . . . % . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 2 . . . . . . . . . . , U ra ni u m 23 7. ... . . . . . .. . . .. . .. . .. . .
- U . . . . . .. .. .. . .. . . . . . . .. . . . . . . . . . . .. , 9 2 . . .. . . . . . . .. . . . . . . . 14 5 U r ani u m 23 8 . .. . . . . . . . . . .. . . . . . . . . .
- U . . . . . . . . . . . .. .. . . . . . .. . . . . . . . .. . . . 9 2 . . .. . . . . . . ..
U ranium 239....................... #U . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 2 . . . . . . . . . . . . . . . . . . . 14 7 Uranium-2 4 0 . . . . . . . . . . . . . . . . . . . . . . . % . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 2 . . . . . . . . . . . . . Radiation Radiation is simply the conveyance of energy through space. For instance, heat i emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves, lonizing radiation is another type of radiation and has similar prop-erties to those of the examples listed above. Ionizing radiation consists of both electromagnetic radiation and particulate ra-diation. Electromagnetic radiation consists of rays of energy with no measur-able mass, that travel with a wave like motion through space. Included in this category are gam.ma rays and X rays. Particulate radiation consists of tiny, fast-moving particles which, if uninhibited, 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 sectica on page 15. Radioactive Decay Radioactive atoms attempt to reach a stable, non radioactive state through a pro-cess known as radioactive decay. Radioactive decay is the release of energy from 1-3
l Davis.Sesse Nuclear Power Station 1990 Annual Environmental Operating Report an atom through the emission of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daughter products which eventu-ally result in a stable atom. The loss of energy (gamma and X rays) and/or mat-ter (alpha or beta particles, or neutrons) through radioactive decay may transform the atom into a chemically different element. For example, when an atom of uranium 238 decays, it emits an alpha particle and, as a result, loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom determines its chemicalidentity. Therefore, when the ura-nium 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 sta-ble 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. Hati-Ufe Most radionuclides greatly in the frequency with which their atoms release radia-tion. Some radioactive materials in which there are only infrequent emissions, tend to have a very long life, while those which are very active, emitting radiation more frequently, tend to have a comparatively short life.The length of time an atom remains radioactive is defined in terms of half lives (Figure 12). Half life is the amount of time required for a radioactive substance to lose half of its activ-ity through the process of radioactive decay. Half lives vary from millionths of a second to millions of years. Interaction With Matter Ionization Through interactions with atoms, alpha, beta and gamma radiation lose their en-ergy. When these forms of radiation interact with any form of material, the en-ergy they impart may cause atoms in that material to become ions, or charged particles. Normally, an atom has the same number of electrons as protons. Thus, the number of negative and positive charges cancel, and the atom is electri-cally neutral. When one or niore electrons are removed, an ion pair is formed. For example, if an electron is removed from an oxygen atom, the electron (nega-tively charged)is one half of the ion pair and the rest of the atom (positively charged)is the other half of the ion pair. Ionization is one of the processes which may result in damage to biological systems. 1-4
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station DECAY OF COBALT-80 (HALF l.lFE
- 5.272 YE ARS)
PtHCtHT or enioiNAL Activity 60 - to-40-to' 0" - M" 0 $ to 16 20 26 40 36 40 YEARS Figure 12: Cobalt 60 has a half life of 5,272 years, After one half life, about half of the cobalt-60 atoms originally present have decayed and become different ele-ments; after an additional half life, half of the remaining cobalt 60 atoms, or a total of about 75% of the atoms originally present, have decayed. Range and Shielding Particulate and electromagnetic radiation each travel through matter differently because of their different properties. Alpha particles contain 2 protons and 2 neu-trons, are relatively large, and carry an electrical charge of + 2, Alpha particles are ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its 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 1-3). Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed oflight (186,000 miles per second). Beta particles have an electrical charge of either + 1 or 1. Because they are 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. 1-5
Davis Besse Nuclear Power Stalk:in 1990 Annual Environmental Operating Report R*lh0l$'. -
^ '
g ,,, u e'2"u g' . .y J ' Mdk8 g% 'T. 1 f f ', ' a a%%" Mf '
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y , " ___ ~~ Gamrta :: = = u y,g
..".a." .
a........ .g E r....... 9 hk"-499heutron . tu e n' %'% Radioactive Paper Aluminum Lead Cencrete Waterial Figure 13: As radiation travels,it collides and interacts with other atoms and loses energy. Alpha particles can be stopped by a sheet of paper, and beta particles by a thin sheet of aluminum. Gamma radiation is shielded by highly dense materials such as lead, while hydrogenous materials (those containing hy- , drogen atoms), such as water and concrete, are used to absorb neutrons. Gamma rays are pure energy that travel at the speed of light. They have no mea-surable charge or mass, and generally travel much further than alpha or beta particles before being absorbed. When the gamma ray finally loses all of its en. ergy after repeated interactions,it is gone. The range of a gamma ray in air var-ies, depending on the ray's energy and its interactions. Very high energy gamma radiation can travel a considerable distance, whereas low energy gamma radia-tion may travel only a few feet in air. Lead is used as a shielding material for gamma radiation because ofits density. Severalinches of lead or concrete may be needed to effectively shield gamma rays. Neutrons come from several sources, including the interactions of cosmic radia-tion with the earth's atmosphere, and nuclear reactions within nuclear power re-actors. However, neutrons are generally not of environmental concern since nuclear power stations are designed to keep neutrens within the containment building. Because neutrons have no charge, they are able to pass verv close to the nuclei (plura' of nucleus) of the material through which they are traveling. As a result, neutrons may be captured by one of these nuclei, or they may be deflected, much in the way that a rolling billiard ballis deflected when it strikes another. When deflected, the neutron loses some ifits energy. After a series of these defice-tions, the neutron has lost much ofits energy. At this point, the neutron is mov- . 1-6
Annual Environrnental Operating Report 1990 Davis Besse Nucloat Power Station ing 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 ener-getic than thermal neutrons, and thus, have greater potential for causing damage to tne material through which they travel. Fast neutrons can have from 200 thou-sand to 200 million times the energy of thermal neutrons. Neutron shielding is designed to slow down fast neutrons and absorb thermal neutrons. Often, neutron shielding material consists of several components, in-cluding a highly dense material, such as lead to slow down the fast neutrons, fol-lowed by a material such as water or polyethylene, to further slow the neutrons. The shield is then completed with a material such as cadmium, to absorb the now thermal neutrons. At Davis Besse, lead and concrete are combined to form an effective neutron shield. Concrete is used because it contains water molecules and is can be easily molded around odd shapes.The resulting combination of the lead to slow neutrons and the concrete to further slow and absorb neutrons has proven to be an effective neutron shield at Dasis Besse. Quantitles and Units of Measurement There are several 1 curie quantities and um.ts used to describe radio. activity and its effects. Four terms of particu- ffffffff, f77, lar usefulness are ac. ,,' ;. .' '.' ' ' ' ;.;. ' ' f thity, exposure, ffffff/cfff/7 6 absorbed dose, and ''''''':l N dose equivalent. % %
> $ 1 Curie ActMty: Curie g s -
Acthity is the number s s of nucleiin a sample that disintegrate f g (decay) every second. 10 Tens of- 1 Gram of thorium-232 Rsdium.226 Each time a nucleus disintegrates, radia-tion is emitted. The Figure 1-4: One gram of radium 226 and 10 tons of thorium 232 are both approximately equivalent curie (Ci)is the unit used to describe the to 1 curie. 1 1 l 1 1-7
Davls-Besse Nuclear Power Station 1990 Annual Environrnental Operatirig Report 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 mate-rial required to produce one curie varies. For example, one gram 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 (Figure 1-4 on previous page). Smaller units of the curie are often used, especially when discussing the low con-centrations of radioactivity detected in emironmental samples. For instance, the microcurie (uCi) is equal to one millionth of a curie, while the picoeurie (pCi) represents one trillionth of a curie. Exposure: Roentgen Exposure is a term used to describe the ability of ionizing radiation from gamma or X rays to produce ion pairs in a certain volume of air. Exposure measures the energy of the radiation and is expressed in units called roentgens (R). One roent-gen is the quantity of exposure that causes approximately two billion ionizing events (i.e., creation of ion pairs) per cubic centimeter of air. A common way to describe the rate of exposure to gamma radiation is in roent-gens per hour (R/hr). Often a smaller unit used is milliroentgens per hour _l (mR/hr), which is 1000 times less. The roentgen applies only to radiation associated with gamma or X rays, and is not used to describe exposure to alpha, beta or neutron radiation. In addition, the roentgen applies only to the energy of the radiation in air, and does not ac-count for the fact that different substances absorb different amounts of energy. Thus, another unit is necessary to describe the amount of energy absorbed by any ) meterial. Absorbed Dose: Rad
' Absorbed dose is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation. The rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the energy ofionizing radiation deposited per gram of absorbing material (rad = 100 erg /gm). The rate of ab-sorbed dose is usually given in rad /hr.
1-8 l
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station if the biological effect of radiation was directly proportional to the energy depos. ited by radiation in an organism, the rad would be a suitable measurement of the biological effect. However, biological effects depend not only on the total energy deposited per gram of tissue, but on how this energy is distributed along its path. Experiments have shown that some types of radiation are more damaging per unit path of travel than others.Thus, another unit is needed to quantify the bio-logical damage caused by ionizing radiations. Dose Equivalent: Rom Biological damage due to alpha, beta, gamma and neutron radiation may result from the ionization caused by these radiations. Some types of radiation, espe-cially alpha particles which cause dense local ionization, can result in up to 20 times the arnount 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 equiva-lent, which is a estimate of the possible biological damage resulting from expo-sure to a particular type of ionizing radiation. The dose equivalent is measured in rem (roentgen equivalent man), As an example of this conversion from absorbed dose to dose equivalent, the quality factor for alpha radiation is 20. Hence,1 rad of alpha radiation is approxi-mately 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. Thermal neutrons have a quality factor of 3, and fast neutrons have a quality factor of 10. One tem produces the same amount of biological damage, regardless of the source, in terms of erwironmental radiation, the rem is a large unit. Therefore, a smaller unit, the millirem,is often used. One millirem (mrem)is equal to 1/1000 of a rem. Sources of Radiation Background Radiation Radiation is not a new creation of the nuclear power industry; it is a natural oc-currence on the earth. Mankind has always lived with radiation and always will. In fact, during every second of life, over 7,000 atoms undergo radioactive decay in the body of the average adult. In addition to that which normally occurs in our 1-9
l Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report bodies, radioactivity also exists naturally in the soil, water, air and space. All these common sources of radiation contribute to the natural background radia-Sources of Exposure to the Public Natural Ba ck gr ot,nd Nuclear Industry Radon 0.05% 5$% Others less than LOX
'Censumer Products s 3.0 %
) Nuclear Medicine
/ 4.0%
Rocks and Soll Medical X rtys ,, 6.0% 11% _l Cosmic Radiation Radioactivity g'gg Inside the Body 11% Note: Shaded pertion Indicates rnaninde radiation. Source: National Council on Radiation Protection and Measurements. NCRP Report No,93. Figure 15: A very small annual dose to the public results from the nuclear power industry. Actually, the most significant annual dose the average individual re-ceives is that from naturally occurring radon. tion to which everyone is exposed (Figure 1-5). 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 out most of this radiation, but everyone still receives about 20 to 50 mrem each year from this source. The thinner air at higher altitudes pro-vides less protection against cosmic radiation. Therefore, people living at higher altitudes or even flying in an airplane are exposed to more cosmic radiation. For example, the dose due to cosmic radiation in Denver, Colorado (elevation 5280 feet above sea level) is approximately 47 mrem per year, whereas, in Toledo, Ohio (maximum elevation 630 feet above sea level), the dose attributed to cos-1 10
Annual Environrnental Operating Report 1990 Davis-Besse Nuclear Power Station mic radiation is approximately 26 mrem per year. Radionuclides commonly found in the atmosphere as a result of cosmic ray interactions include beryllium 7, carbon 14, tritium, and sodium 22. Other natural sources of radiation include the radionuclides naturally found in soil, water, food, building materials and even people. People have always been radioactive,in part because the carbon found in their bodies is a mixture of all carbon isotopes, both non radioactive and radioactive. In fact, because radioactive carbon 14 has a known half life of 5730 years and ex-ists in all living things, archaeologists can use carbon dating to determine the age of a fossil or other artifact. After an organism dies,it no longer takes up carbon, and the radioactive carbon 14 present in its body continues to decay. Thus, ar-chaeologists can compare the percentage of radioactive carbon to stable carbon present in a fossil or artifact to estimate the point at which it no longer assimi-lated radioactive carbon in its tissues (i.e., the point of death). Another common naturally occ'urring radionuclide is potassium 40. About one-third of the external terrestrial and internal whole body dose from natural sources is attributable to this natural radioactive isotope of potassium. Recently, concern has been expressed over another source of background radia-tion -radon. According to the National Council on Radiation Protection (NCRP), over half of the radiation dose the average American receives is attrib-uted to radon. Radon is a colorless, odorless, radioactive gas that results from the decay of radium 226, a member of the uranium 238 decay series. Radon atoms are produced in the soil and migrate through air filled pores in the soil to reach the atmosphere. Radon occurs in all soils, but, because it is a daugh-ter product of uranium, it occurs in higher concentrations in rocks (and soils de-rived from rocks) with high concentrations of uranium, such as black shales, granites, phosphate rocks and carbonate rocks. Radon occurs indoors as a result oi radon in the soil or rock under the building, or radon in building materials, water supplies, natural gas or outdoor air. Groundwater supplies can become contaminated with radon migrating through the soil. In addition, the unvented combustion of natural gas can also contribute to indoor radon concentrations. However, the primary source of indoor radon is that which diffuses into the building from the underlying soil or rock, Radon may enter buildings through the walls, floors, vents and other openings. Although radon can migrate through uncracked concrete slabs, cracked slabs, 1-11
. . .- - . - - - .- - . . . . - ~- -.- Davis-Besse Nuclear Power Stat}on 1990 Annual Environmental Operating Report and those with openings for piping, sumps, etc. may considerably increase the transmission of radon into a building. Although there is no reliable method of predicting which buildings will have greater indoor concentrations of radon, the following factors directly impact radon uptake and accumulation: e uranium content of the soil e weather conditions e construction methods e presence (or absence) of any cracks or openings in the foundation. Some weather conditions, such as low pressure systems or increased rainfall, act to force radon out of the soll at anincreased 9te,In addition, construction meth-ods affect indoor radon concentrations. Buildn.gs built on a slab with no crawl space, buildings sealed to prevent energy loss, those with basements, and those without fully ventilated crawl spaces tend to be linked to higher radon concentra-tions. Because uranium naturally occurs in all soils and rocks, everyone is continuously exposed to radon and its daughter products. However, radon does not typically pose a health hazard unless it is allowed to concentrate in a confined area, such as a building.
' Radon related health concerns stem from the exposure of the lungs to this radio-active gas. Radon emits alpha radiation when it decays, Alpha radiation can eas.
ily be stopped by a person's dead skin layer. However, alpha radiation can cause damage to internal tissues when ingested or inhaled, As a result, expcsure to the lungs is of greatest concern, and the only recognized health effect associated with - exposure to radon is an increased risk oflung cancer.- Radon can be' detected in one of several ways.Three common methods used presently to detect radon in homes and other buildings are as follows: e - Charcoal canister method: Charcoal canisters, which adsorb radon, are placed in a building, and after approximately 1 to 5 days are removed and sent to a laboratory where the radon decay products are detected. From this information,
- the laboratory can determine the approximate concentration of radon gas required to produce the decay products measured, t
1-12
Annual Environmental Operating Report 1990 DavisIBesse Nuclear Power Station e Alpha track method Alpha track detectors utilize a radiation sensitive film. When the alpha emissions from radon strike the film, they make a track. The alpha track detector is usually placed in a building for 2 weeks to several months, and, like the charcoal canister, is sent to a labaratory j for analysis. At the laboratory, the number of tracks on the film are counted, and this information is used to estimate the average concentration of radon in the building during the period that the film was exposed. e Electronic monitoring method: Electronic monitors are available which continuously detect the number of negative ions produced by decaying radon and provide instantaneous information on the concentration of radon in the air. The United States Environmental Protection Agency has provided guidelines for
- radon monitoring in homes and other buildings, and has developed recommenda.
tions for concentrations at which to take corrective actions. Further information ' on radon,its detection, and actions to reduce the radon concentration in build-ings can be obtained by contacting the state radon program office at the follow-ing addresst 4 Radiological Health Program Ohio Department of Health 1224 Kinnear Road, Suite 120 Columbus, Ohio 43212 (614)481-5800-
,(800) 523-4439 (in Ohio only)-
Man-Made Radiation : In addition to naturally occurring radiation and radioactivity, people are also ex-
- posed to man-made radiation. The largest sources of exposure include medical X rays and radioactive pharmaceuticals. Small doses are also received from con-sumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man made exposure. Fallout radionu-clides include strontium-90, cesium 137, carbon-14, and tritium. As shown in Fig -
ure 1-5, a very small percent of the annual dose a member of the public receives is due to the production of nuclear power. In fact, the maximum whole body doses to the public due to radioactivity released in liquid and gaseous effluents
. from Davis Besse in 1990 were only 0.22 and 0.04 mrem, respectively. Each of 1-13
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Rtport these doses is less than the dose an individual would receive from one coast to-coast jet flight (3 mrem). Health Effects of Radiation stu a . 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 of laboratory animals that were exposed to radiation under extremely controlled conditions. However,it has proven difficult to relate the biological ef-fects of irradiated laboratory animals to the potential health effects on humans. Hence, much study has been done with human populations that were irradiated under various circumstances. These groups include the survivors of the atomic bomb; persons undergoing medical radiation treatment; radium dial painters, who ingested large amounts of radioactivity by " tipping" the paint brushes with their lips; uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (uranium ore); and early radiologists, who accumulated large doses of radiation while unaware of the potential hazards. The studies performed on these groups have increased our knowledge of the health effects from large doses of radiation. However,less is known about the ef-fects of low doses of radiation. To be on the conservative side, we assume that 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 overestimates the risks associated with low level radiation expo-sure. The effects predicted in this manner have not been actually observed in in-dividuals exposed to low level radiation. However, this assumption provides a highly conservative model of radiation-induced health effects, and most probably overestimates the risks associated with receiving low doses of radiation. Health Risks Since the actual effects of exposure to low level radiation are difficult to assess, scientists often refer to the risk involved. The problem is one of evaluating alter- ' natives, of comparing risks and weighing them against benefits. People make de-cisions involving risks every day, such as whether to wear seatbelts or smoke cigarettes. Risks are a part of everyday life. The question is one of determining how great the risks are. We accept the inevitability of automobile accidents. Chances are that several people reading this report will be seriously injured this year as a result of auto-mobile accidents. By building safer cars or wearing seat belts, this risk can be re-1-14
l 1 I Annual Environrnental Operating Report 1990 Davis Besse Nuclear Power Station l l l duced, however, even a parked car is not risk free. You could choose not to drive, but even pedestrians and bicyclists may be injured by cars. Reducing the l risk of injury from automobiles to zero requires moving to a place where there are no automobiles. l While most people accept the risks inherent in such activities as smoking and l driving to work each day, some people seem to feel that their energy needs should be met on an essentially risk free basis. However, this is impossible, no l matter what the energy source. The burning of fossil fuels can have a negative im- ; pact on the environment, and even the use of hydropower entails risks, including that of a ruptured dam, and the habitat destruction that can result from damming waterways. 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 perspective. One of the most widely distorted perceptions of risk is that associated with radiation exposure. Because some people do not understand ionizing radiation and its associated risks, they may fear it. This fear is compounded by the fact that we cannot hear, smell, taste or feelionizing radiation. Sometimes,if we have no other source of information, we may believe the widespread myths about ionizing radiation and its health effects. But this is not true of other potentially hazardous things for which we have the same lack of sensory perception, such as radio waves, carbon monoxide, and small concentrations of numerous cancer causing substances. Al-though these risks are just as real as the risks associated with ionizing radiation, they do not generate the same degree of concern. Most risks are with us through-out our lives, and their effects can be added up over a lifetime to obtain a total ef-feet on our lives. Table 12 shows a number of different factors that decrease the average life expectancy of mdividuals in the United States. The American Cancer Society estimates that about 30 percent of all Americans will develop cancer at some time in their lives from all possible causes. Thus, in a group of 10,000 people, it is expected that 3,000 of them will develop cancer. If each person in that group of 10,000 people were to receive 100 millirem in addi-tion to the natural and man-made sources of radiation they are normally exposed to then there is an increased probability that would indicate one additional per-son from that group may develop cancer during his/her lifetime. This increases the risk from 30 percent to 30.01 percent. For comparison, the average offsite dose to indisiduals in the population due to the operation of the the Dasis Besse Nuclear Power Station is significantly less than one millirem (0.0011 millirem in 1990). If it is considered that the Davis Besse Nuclear Power Station will operate for the remainder ofits license at this rate, the probability of even one person :n 1 15
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report the population developing a cancer due to the presence of the Davis-Besse Nu-clear Power Station is extremely small. The preceding table should provide you with an idea of the risks associated with nuclear power with respect to other, more significant risks that we accept as a part of our daily lives. Only when one is presented with a basis for comparison, can he or she make the decision that the benefits derived from a particular activ-ity (e.g., driving an automobile) outweigh the costs associated with that actisity (e.g., possibility of an automobile accident). By comparing the risks associated with familiar activities, this provides people with a means to put the risks associ-ated with malear power in perspective. Table 12: Risk Factors Factors Estimated Decrease in Average Life Expectancy
- Male rathe r than female............................................. 5.0 years Ove rwe igh t by 30% ..................................................... 3.6 ye ars Cigarette smoking:
1 pack / day ..................... 7.0 years 2 packs / day..................10.0 years 1 H e art dise as e s ............................. ....... ............... ......... .. 5.8 ye ars Can c e r .. . .. . .. . . . .. .. .. . .......... . .. . ... . . . .. . .. . . . ... . .. . . . .. . . . . ... . . . .... . . . . 2.7 ye ars City living (not rural) .................................................. 5.0 years 125 operating nuclear power stations..... less than 12 minutes
- The typical life span in the Urtited States is now 76 years for women and 71 years for men.
1 16
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Benefits of Nuclear Power Nuclear power plays an important part in meeting today's electricity needs, and will continue to serve as an important source of electric energy well into the fu-ture, in 1980, nuclear power accounted for only eleven percent of the electricity produced in the United States (Figure 16). By the end of 1989, however, this number had grown to nineteen percent. At the same time, dependence on oil as an energy source decreased by almost half. By decreasing the nation's depen-dence on oil, dependence on foreign oil supplies also decreases, thereby ensuring the nation can continue to be self sufficient in meeting the energy needs of its private and business sectors. 1980 & 1990 NET GENERATION OF ELECTRICITY "T&*' "ifeT
*iM**' ,. oi .,
io n
. l **i;;*l,oa -
- Us "
io h d'ti 1980 1990
?.*EI."E.*I$Iii WNnI(?Ah Figure 1-6: During the past decade, the nation's dependence on nuclear power has increased dramatically.This has led to decreased dependence on foreign oil supplies, thus enabling the U.S. to become more self sufficient in meeting its electricity needs, i
l 1-17 l 1
l Davls Besse Nuclear Power Station 1990 Annual Environmental Operating Report Nuclear power offers several advantages over alternative sources of electric en-ergy: e nuclear power stations have an excellent safety record dating back to 1957 when the first commercial nuclear power station began operating, e uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States, and e nuclear power is the cleanest energy source for power stations that use steam to produce electricity. The following sections provide information on the fundamentals of electrical gen-eration, and on how Davis Besse uses nuclear fuel and the fission process to pro-duce electricity. Where Does Electricity Come From? The flow of electrons through a wire is called an electric current, or electricity.
. Voltage is the force that pushes the current along the wire,just as pressure pushes water through pipes. Extra electrons are needed to start and maintain an - electric current.- One way to add these extra electrons is by using a battery; how-ever, batteries are not an efficient source for large amounts of electricity. An-other method of generating electricity is by rotating a magnet inside a coil of wire. Large amounts of high voltage electricity can be produced in this manner, The two ends of a magnet are called poles. The power of a magnet extends be- . yond these poles in invisible lines of force. If a loop of wire passes through a magnet's line of force, electrons start racing through the wire.
Figure 1-7 provides a simplified illustration of the basic steps involved in produc-
. ing an electrical current. Fuel, such as coal, is burned in a furnace and heats -water in the boiler to produce steam.The steam drives the turbine generator. An electric generator is basically a magnet and coils of wire. It has an engine that is called a turbine. The turbine converts the heat energy of the steam into mechan .
ical energy. When steamis forced against the blades of the turbine, the turbine rotates, turning a long shaft. At the end of the shaft is a huge magnet inside the - generator. The generator converts mechanical energy into electrical energy. As the shaft turns, the magnet spins inside a ring wrapped with a long coil of wire, This starts a current flowing in each section of wire that it passes. Before the electric current leaves the power station, a transformer steps up the voltage so that it can travel long distances to consumers. Dansmission lines 1-18
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cutfent. Figure 1-7: Electricity is produced in a fossil fueled power station much in the way it is produced at Davis Besse. Steam is forced against the blades of a turbine which wrns a magnet inside the generator, and produces an electric current, carry the current from the power station to other transmission lines many miles away or to local substations equipped with transformers that lower the voltage of the current. Distribution lines then carry the lower voltage current to pole trans-formers where the voltage is again stepped down for safe use by electrical con-sumers. The Use of Stoem To Produce Electricity There are several sources of steam used by power stations to generate electricity, including the burning of fossil fuels such as coal, oil, or natural gas; the earth's natural steam, called geothermal energy; and steam produced inside a nuclear re-actor from the heat released when atoms of uranium are split or fissioned. Be-sides steam, water power (hydropower) and wind power can be used to turn turbines to produce electricity. 1-19
Davis Besse NucJoar Power Station 1990 AnnuJ Environmental Operating Report Nuclear Power Production Electricity is produced in a nuclear power station in essentially the same way as in a fossil fueled station. Heat changes water to steam that turns a turbine. In a fossil fueled station, the fuel is burned in a furnace. Inside the boiler, water is turned into steam. In a nuclear station, the furnace is replaced by a reactor con-taining a core of nuclear fuel, primarily uraniurn. Heat is produced when the atoms of uranium are split, or fissioned, inside the reactor. What is Fission? A special attractive force called the binding force holds the protons and neutrons together in the nucleus of the atom. The strength of this binding force varies from atom to atom. If it is weak enough, the nucleus can be split if it is bom-barded by a free neutron (Figure 1-8). This causes the entire atom to split, pro-ducing smaller atoms, more free neutrons, and heat. In a nuclear reactor, a chain reaction of fission events provides the heat necessary to boil the water to produce steam.
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Qo >o 1 - + e j NO s' O NEUIRON O pac!ON l w utu w a l Figure 1-8: When a heavy atom, such as uranium 235 is split, or fissioned, heat, free neutrons, and fission fragments result. The free neutrons can then strike neighboring atoms causing them to fission also. In the proper environment, this process can continue indefinitely in e chain reaction. l l l 1-20 l l
l Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station l 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 pel-let can release an extremely large amount of energy. Tne 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: e using fuel that is free ofimpurities that might absorb the freed neutrons; e increasing the concentration of the rarer fissionable isotope of uranium (U 235) relative to the concentration of U 238, a more common isotope that does not fission easily; and e slowing neutrons down to increase the probability of fission by providing a " moderator"such as water. Natural uranium contains less than one percent U 235 when it is mined. Before it can be economically used in a nuclear reactor, it is enriched to approximately three percent U 235 relative to U 238. In contrast, the nuclear material used in nuclear weapons has been enriched to over 97 percent. Because of the low levels of U-235 in nuclear fuel, a nuclear power station cannot explode like a bomb. Nor could the fuel, as it exists at a power station, be used to make a bomb. After the uranium is separated from the earth and rock in the ore, it is concen-trated by a milling process. After milling the ore to a granular form and dissolv-ing out the uranium with acid, the uranium is converted to uranium hexafluoride (UF6), a chemical form of uranium that exists as a gas at temperatures slightly above room temperature. The uranium is then highly purified and shipped to an enrichment facility where gaseous diffusion converters increase the concentra-tion of U 235 in the fuel.The enriched gaseous UF6 is then converted into pow-dered uranium dioxide (UO2), 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 (refer to Figure 19) 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. 1 1 21
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a, U I ;;; N Fuel Rod Fwel Assembly Reactor tessel Figure 1-9: The reactor core at Davis-Besse antains 177 fuel assemblies. Each assembly contains 208 fuel rods. Each fuel rod is filled with approximately five pounds of fuel pellets, each pellet approximately 3/8 inch in diameter and 5/8 inch long. The Reactor Core 1 l TWo hundred eight fuel rods comprise a single fuel assembly. The reactor core l 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 neu-tron levels in the fuel assembly. The Davis Besse reactor core weighs approxi- i mately 207,486 pounds, while the reactor vessel itself weighs 833,000 pounds,
' has a diameter of 14 feet, is 39 feet high, and has 81/2 inch thick steel walls.
Fission Control The fission rate inside the reactor core is controlled by raising or lowering con-trol rod assemblies into the reactor core. Each assembly consists of 16 " fingers" containing silver, Indium and cadmium metals that absorb free neutrons, thus dis-rupting the fission chain reaction. When control rod assemblies are slowly with-drawn from the core, fissioning begins and heat is produced. If the control rod assemblies are inserted rapidly into the reactor core, as during a plant " trip," the
- chain reaction ceases. A slower acting (but more evenly distributed) method of fission controlis achieved by the addition of a neutron poison to the reactor cool-1-22
Annual Environmental Operating Report 1990 Davis Besso Nuclear Power Station ant water. At Davis Besse, boric acid can be concentrated or diluted as neces-sary in the coolant to achieve the desired level of fission. After boric acid is added to the coolant water, the acid turns into boron 10. Boron 10 readily ab. sorbs free neutrons (hence the term " neutron poison"), forming boron-11. The boron 11 in turn decays to nonradioactive lithium 7 by the emission of an alpha particle. Reactor Types Virtually all of the commercial reactors in this country are eithe r boiling water reactors (BWRs) or pressurized water reactors (PWRs). Both types are also called light water reactors (UVRs) because their coolant, or medium to transfer heat, is ordinary water, containing the light isotope of hydrogen. Some reactors use the heavy isotope of hydrogen (deuterium) in the reactor coolant. Such reac-tors are called heavy water reactors, or HWRs. In BWRs, made by the General Electric Company, water boils to steam directly in the reactor vessel. In PWRs, made by the Babcock & Wilcox Company, Com-bustion Engineering, Inc., anil the Westinghouse Electric Corporation, the reac-tor water or coolant is pressurized to prevent it from boiling. Instead, the hot water is pumped to a steam generator, where its heat is transferred to a separate supply of water. The water inside the steam generator boils into steam. Davis. Besse uses a PWR, while the Perry Nuclear Power Plant, owned by Toledo Edison's sister company, Cleveland Electric Illuminating, uses a BWR. The Davis Besse and Perry Nuclear Power Stations are the only two commercial reac-tors in the State of Ohio. I 1 1-23
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report Station Systems The following paragraphs describe the various systems illustrated in Figure 1 10 on page 125. Major systems in the Davis Besse Station are assigned a different color in the figure. FIGURE 1 10 LEGEND GREEN . Reactor Coolant System (Primary Coolant Water) RED Main Steam System BLUE - Condensate / Main Feedwater System (Secondary Coolant Water) YELLOW - Circulating Water System (Tertiary Coolant Water) 1 GOLD - Emergency Core Cooling System SCARLET - Auxiliary Feedwater System GREY - Pressurizer and Associated Structures 1-24
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Davis Besse Nuclear Power S:stion 1990 Annual Environmental Operating Report Containment Bulkling std Fission Product Release Barriers The containment building at Davis Besse houses the reactor vessel, the pre-ssurizer and two steam generators. The building is constructed of an inner 1 inch thick steel liner or containment vessel, and the shield building with steel rein-forced concrete walls 2 feet thick. The shield building protects the containment vessel from a variety of environmental factors, and provides an area for a nega. tive pressure boundary around the steel containment vessel. In the event that the integrity of the shield building is compromised (e.g., a crack develops), this negative ptessure boundary ensures that any airborne radioactive contamination present in the containment vessel ls prevented from lea' king out into the environ-ment. It accomplishes this 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 frec+ standing containment vessel is the third in a series of barriers (refer to [ _. FIS$10N PRODIJCT RELEASE BARRIERS:
- 1. Fuel Ctacding
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V N j Figure 1-11: There are three isolation barriers that would prevent the release of fission products to the environment in the event of an accident at Davis Besse in addition to these barriers, a negative pressure boundary maintained between the containmem vessel and concrete shield building is designed to contain airborne radioactive contaminants. 1-26 l
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l Annual EmtonmenW Openating Aeport 19GO Davls-Besse Nuclear Power Station i Figure bli) that prevent the release of fission products in the unlikely event of an uccidem, The first barrier to the release of fission products is the fuel clad- l ding itself. The second barrier is the walls of the primary system,i.e. the reactor i vessd steam generator and associated piping. The Stoam Gamestors j 1 The steam generators at Davis Besse perform the same function as a boiler at a j 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 l (secondary coolant) surrounding the tubes on the outside. Fission heat must be transferred from the reactor core to the steam generator in order to provide the , steam necessary to drive the turbine. However, beat must also be removed from 1 the core even after reactor shutdown in order to prevent damage to the fuel clad-ding. Therefore, pumps maintain a contirmous flow of coolant through the reac- i tot and steam generator. Primary loiop water (green in Figure i 10) exits the l reactor at approximately 606"F, passes through the steam generator, transferring some ofits heat energy to the secondary hop water (blue in Figure 1-10) without ever actual.ly coming in contact with:it, Primary coolant water exitrahe steam 0 generator at approximately 558 F to be circulated back into the reactor whexe it is again heated to 6%"F as it passes up through the fuel assemblies. Under ordi-nary condidons, water inside the primary system would boil long before it reached such temperatures. However,,it is kept under a pressure of approxi-mately 2,200 pounds-per. square inch (psi) at n!! times. This prevents the water from boiling and is the reason the reactor at " avis Besse is called a Pressurized Water Reactor. Secondary loop water ente- the base of the steam generator at U approximately 400 F and under 1100 psi pressure. At this pressure, the water can casily 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 sys. tems. This means they are designed not to come in physical contact with one an-other. Rather, the coolant (i.e., water) contained in each loop transfers heat energy'oy the process of convection. Convection is a method of heat transfer that can occur between two fluid media. It is the same process by which radiators are used to heat homes. The water circulating inside the radiator is separated from the air (a " fluid" medium) by the metal piping. The TuttAne-Generator The turbine, main generator, and the condenser are all housed in what is com-monly referred to as the 1brbine Building. 1 27
Davis Besse Nucinar Power Stat on 1W Annual Environmen'.ai Operating Report The purpose of the turbine is to convert the thermal energy of the steam pro-duced in the steam generator (referred to as main steam, red in Figure 1 10) to rotational energy of the turbine geneator 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 tenter of each turbine and fiows outward along the shaft in opposite directions through each successive stage of blading. As the steam passes over the turbine blades,it ioses 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 thaft 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 se. ties of transformers for transmission and use throughout northern Ohio. The Condenser After the spent steam in the secondary loop (blue in Figure 1 10) passes through the high and low pressure turbines,it is collected in a cavernous condenser sev-eral stories tall and containing more than 70,000 small tubes. Circulating (cire) water (yellow in Figure 1 10) from the cool!ng tower passes through the tubes in-side 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 inte the steam generator again in a cloted loop system. Cire water forms the third (or tertiary) and finalloop of cooling water used at the Davis Besse Station. As with the primary to secondary interface, the secondary to tertiary ime rface is based on a closed loop design. In other words, the circulating water is able to cool the steam in the condenser, without evu 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 radioac-tive. Closed loops are an integral part of the design of any nuclear power facility, to greatly reduce the chance of emironmentalimpact from station operation. The Cooling Tower The cooling tower at Davis Besse is easily the most noticeable, and often the most misunderstood, feature of the plant. The tower stands 493 feet high and the diameter of the base is 411 feet. The two pipes circulating water to the
- i 1 28
I l Annual Environmental Operating Report 1990 Davis Cet,t.e Nuclear Power Station tower are 9 feet in diameter. Theycirculate 480,000 gallons of water per min. ute; enough water to fill a swimming pool the size of a football field 32 feet deep, n purpose e of the tower is to recyclc water from the condenser by cooling it. Aftgr passing through the condenser, the cire water has warmed to approximately 100 F. In order to cool the water back down to around 70 0F, the cire water en-ters the cooling tower about 40 feet above the ground. The water is sprayed evenly over a series of baffles called fillsheets which are suspended vertically in the base of the tower. A natural draft of air blowing up through these baffles cools the water through the process of evaporation. The evaporated water exits the top of the cooling tower in the form of water vapor. As much as 10,000 gallons of water per minute are lost to the atmosphere via the cooling tower. Even so, approximately 98 percent of the water drawn from Lake Erie for stadon operation can be recycled through the cooling tower for reuse. A smell portion of the cire water is discharged back to Lake Erie at essentially the same temperature it was withdrawn earlier, in 1990, the average, difference be-tween the intake and discharge water temperatures was only 3,8" F. The slightly warmer discharge water had no adverse environmentalimpact on the area of the lake surrounding the discharge point. Many power stations, both nuclear and fossil fueled, utilize cooling towers to cool station discharge water. Federal regulations governing the water tempera-ture of ritcs, lakes, and bays require that power station operation introduce rela-tively small changes in water tensperature. An increase in water temperature is not necessarily detrimental to aquatic life. Fishermen usually find that the best fishing areas are in the vicinity of warm water effluents from power stations. Warm water has also been found to accelerate the growth and increase the size of oysters and shrimp harvested by commercial fishermen. Unfortunately, the same warm water may also attract undesirable aquatic organisms such as the zebra mussel. In additon, an ir.trease in water temperature during the summet months could decrease the water's oxygen content and could therefore precipitate a fish kill. Miscellaneous Station Safety SyWems The gold system in Figure 1 10 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 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, 1 29 l
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report 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 grey systern illustrated in Figure 1 101s responsible for maintaining the pri-mary coolant water in a liquid state. it accomplishes this by adjusting the pres. sure inside the primary system Heaters inside the pressurizer turn water into steam. This steam takes up more space inside the pressurizer, therefore increas-ing the overall pressure inside the primary system. The pressurizer is also equipped with spray heads that shower cool water over the stearn in the pre-ssurizer. In this case, the steam condenses and the overall pressure inside the pri-mary system drops. The quench tank pictured in Figure 1 10 is sitnply where execss steam is :litected and condensed for storage. The scarlet system in Figure 1 101s part of the Auxillary Feedwater System, a key safety system in the event the main feedwater supply (blue in Figure 1 10) to the steam generator is inadequate. Following a reactor shutdown, the Auxiliary Feedwater System can supply water to the steam generators from the Conden. sate Storage Tanks. The Auxiliary Feedwater System is housed in the 7brbine 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 concentra-tion of fissionable material is far less than is necessary for such a nuclear explo-sion. Just as the battery of a flashlight provides enough energy to produce light, the amount of energy produced by the battery is not enough to cause un electri-cal shock to a person handling the flashlight Many safety features (such as the Auxiliary Feedwater System) are also equipped with several backup systems to ensure that any possible accident would be pre-vented from causing a serious health or safety threat to the public, or serious im-pact on the local emironment. The Davis Besse Station,like all U.S. nuclear units, has many overlapping, or redundant safety features. If one system should fail, there would still be back up systems to assure the safe operation of the Sta-tion; During normal operation, the Reactor Control System regulates the power outptit by adjusting the positicn of the control rods. The reactor can be automati-cally 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 1.oss Of 1 30
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Annual Environmental Operating Report 1990 Davis Besse Nuclear Pcwer Station ) Coolant Accident, the Emergency Core Cooling System is designed to pump re-serve water into the reactor cutomatically if the reactor coolant pressure drops below a predetermined level. The preceding pages should provide basics on electrical generation, and more specifically, how the Davis Besse Nttricar Power Station op; rates to produce a reliable, safe, and erwironmentally sound source of electricity. l 1 1 31
Annual Environmental Operating Report 1990 Davis Besso Nuclear Power Station 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 1.ake Erie,just north of the mouth of the Toussaint River. The site lies north and cast of Ohio State Route 2, approxi-mately 10 miles northwest of Port Clinton,7 miles north of Oak Harbor, and 25 miles east of Toledo, Ohio (Figure 1 12). 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 settiment and farming. During the nineteenth century, the land was cleared and drained,'and has been farmed 8 9.e g 8
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Annua! Environmental Operating Report 1990 Davis Besse Nuclear Pow Station successfully since. Today, the terrain consists of farmland with marshes extend-ing in some places for up to two miles inland from the Sandusky Lake Shore Ridge. More than half of the Davis Beste site area is marshland. A small portion of the site was farmland. The marshes are part of a valuable ecological resource, pro-viding a breeding ground for a variety of wildlife, and a refuge for migratory birds. Major species of birds using this portion of the 1.2ke Erie marshes include mallards, black ducks, widgeon, egrets, great blue herons, blue winged teal, and Canada geese, in fact, there are hundreds of geese living right on the site. Bald eagles, osprey, swans, great horned owls, and a large number of hawks are also seen in the area. The site includes a tract known as Navarre Marsh, which was ac-quired 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 sec-tion of the Ottawa National Wildlife Refuge. Most of the remaining marshes in the area have been maintained by private hunt-ing clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natu-ral Resources, Division of Wildlife. There are some residences along the lake shore used mainly as summer homes.1-lowever, the major resort area of the county is farther east, around Port Clinton, Sandusky, and the Bass Islands. The immediate area near Davis Besse is sparsely populated; Ottawa County had a population of only 40,076 in the 1980 census. The nearest incorporated com-munities are: e Port Clinton - 10 miles southeast, population 7,223 e Oak Harbor 7 miles south, population 2,678 e Rocky Ridge 7 miles west southwest, population 457 e Toledo (the nearest major city)- 25 miles west, population 354,650. The non marsh areas around the Davis Besse site are used 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 in-dustries within five miles of the site are located in Erie Industrial Park, about four miles southeast of the Station. The State of Ohio Department of Natural Resources operates many wildlife and recreational areas within 10 miles of the Station. These include Magee Marsh, hrtle Creek, Crane Creek State Park, and the Ottawa National Wildlife Refuge. Magee Marsh and %rtle Creek lie between three and six miles WNW of the 1-33
i 1 , Annual Environmental Operating Report 1990 Davis Desso Nuclear Power Station 4 Station. hiagee hiarsh is a wildlife preserve allowing public fishing, nature study, and controlled hunting in season. Turtle Creek, a wooded area at the southern end of hiagee hiarsh, offers boating and fishing. Crane Creek State Park is adja. cent to hiagee hiarsh and is a popular picnicking, swimming, and fishing area. The Ottawa National Wildlife Refuge lies four to nine miles WNW of the site, immediately west of hiagee hlarsh. 1 34
l Annual Environmental Operating Report 17)0 Davis Besse Nuclear Power Station The 1990 Summary of Radioactivity Released in Liquid and Gaseous Efiluents 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 hicasurements (NCRP). hiany of these recommendations have been given legis-lative authority through publication in the Code of Federal Regulations (CFR) by the Nuclear Regulatory Commission (NRC). The main objectives in the control of radiation exposure are to ensure that any necessary exposures are kept as low as is reasonably achievable (AIARA). The ALARA principles in a practical sense, means redcing and maintaining exposure to radiation and radioactive materials both to the individual working at Davis-Besse and the general public. This is based on sound economic decisions and op-erating practices. By practicing ALARA. Davis Besse and Centerior Energy minimizes the health risk and emironmental detriment and ensures that doses do not exceed certain specified limits. Limits To protect the general public, guidelines and limits have been established govern-ing the release of radioactivity in liquid and gaseous Station efnuents. The Code of Federal Regulations, Title 10, Part 50, Appendix !(10CFR50, App.1) pro-vides guidelines for the Technical Speelf1 cations which are part of the license au. thorizing nuclear reactor operation. Davis Besse's Technical Specifications place restrictions on the release of radioactivity to the environment and the resulting dose to the public. Table 13 presents these limits. 1 35
l Annual Environmental Operating Report 1>00 Davis Besse Nuclear Power Station Table 13: Dose Limits to a Member of the Public NRC Limits for i Source Davis 11 esse i j Unuld Emuents j leu than or equal to 3 mrem' year to the whole txxjy
! leu than or equal to 10 mrem / year to any organ Gaseous Emuents Noble Gases:
gamma (mit dose) leu than or equal to 10 mrad' year beta (air dos,e) leu than or equal to 20 mrad' year lodine 131, tritium and particulates with halblives greater i than 8 days leu than or equal to 15 mrem' year to any organ l I The Davis Besse limits are only a small fracti,n of the dose limits established by the Emironmental Protectior. Mency (EPA). In its emitonmental dose standard of 40CFR190, the EPA established environmental radiation protection standards for nuclear power operations. The standards for normal operation pro-vide that the dose from all discharges of radioactivity should not exceed: e 25 mrem / year to the whole body e 75 mrem / year to the thyroid e 25 mrem / year to any other organ. Sources Through the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. Ilowever, 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. Many of these particles art removed through demineralizers in a processing sys. tem. 1 36 __ ___ - _-_ _ _M
Annual Environmental Operating Report 1990 Davls Betse Nuclear Power Station 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 de- ; signed for gas collection and storage for radioactive decay prior to release. l Small releases of radioactivity in liquids may occur from valves, piping or equip- t ment associated with the primary coolant system. These liquids are collected through a series of floor and equipment drains and sumps. Allliquids of this na-ture are processed and carefully monitored prior to release. Noble Gas Some of the radionuclides 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 exposure by being a source of external whole body exposure, 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. In 1990, approximately 1090 cu-ries of noble gases were released. The calculated offsite gamma and beta air doses due to the release of this activity were 0.024 mrad and 0.068 mrad, respec-tively and are less than 1.0% of their respective Technical Specifications limits. Additional dose information is provided in Table 14 on page 1-42. lodine and Particulates Annual releases of radioisotopes oflodine and radioactive particulates (with half-lives greater than eight days)in gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing systems, minimize their dis-charge. The predominar.t radiolodine released is iodine 131 with a half life of approximately eight days. The principal radioactive particulates released are radioactive fission products (cesium 134 and cesium 437) and activation products (cobalt 58 and cobalt 60). During 1990, the amount of radioactive iodine and particulates (excluding tri-tium) released was approximately 3.82 3 curie in gaseous effluents and 0.14 curie in liquid effluents. These releases were v. ell below all applicable regula-tory limits. Additional dose information is provided in Table 1-4 on page 1-42, 1 37
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Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station i i Tritium Tritium, a radioactive isotope of hydrogen,is the predominant radionuclide in lig-uid ef0uents, and is also present in gaseous e(Guents. Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydro-gen isotope) present in the water and with the boron in the primary coolant used for reactivity control of the reactor. The amount of tritium released in 1990 was approximately 28.9 curies in gaseous ef0uents and 127 curies in liquid effluents. The associated doses were well below all regulatory limits, and additional dose information is provided in Table 1-4, page 1-42. Processing and Monitoring Effluents are strictly controlled to ensure radioactivity released to the environ-ment is minimal and does not exceed release limits. Effluent controlincludes the operation of monitoring systems,in plant and environmental sampling and analysis programs, quality assurance programs for effluent and environmental programs, and procedures covering all aspects of ef0uent and environmental monitoring. The radioactive waste treatment systems at Davis Besse are designed to collect and process the liquid and gaseous wastes which contain radioactivity. For exam-plc, the Waste Gas Decay Tanks are holding tanks which allow radioactivity in gases to decay prior to release via the station vent. All wastes are sampled prior to release and an offsite dose evaluation is performed to assure that the dose from the release will be as low as reasonably achievable (ALARA). Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits. These instruments provide a continuous indication of the ra-dioactivity present and are sensitive enough to measure 100 to 1000 times lower than the release limits. Each instrument is equipped with alarms with indicators in the control room. The alarm set points are low to ensure the limits will not be exceeded, if a monitor alarms, a release from a tank is automatically stopped. Additionally, effluent samples are collected and analyzed in a laboratory to iden-tify the spccific concentrations of radionuclides being released. Sampling and analysis provides a more sensitive and precise method of determining efnuent composition than with monitoring instruments alone. 1 38
Annual Environmental Operating Report 1990 Davis Best,e Nuclear Power Station i A meteorological tower is located in the southwest sector of the Station, it is linked to a computer which records the meteorological data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public. Beyond the plant, devices maintained in conjunction with the Radio- I logical Emitonmental Monitoring Program constantly sample the air in the sur-rounding emironment. Frequent samples of other emironmental media, such as water and vegetation, are also taken to determine if buildup of deposited radioae. ! tivity has occurred in the area. l l l Exposure Pathways l Radiological exposure pathways define the methods by w hich people may be-come exposed to radioactivity. The major pathways of concern are those which j could cause the highest calculated radiation dose. These pathwnys are deter- ! mined from the type and amount of radioacthity released, the emironmental transport mechanism, and the use of the em>ironment. The emironmental trans- I port mechanism includes consideration of physleal fnetors, such as the hydrologi-cal (water) and meteorological (weather) characteristics.af the a.rea. This provides information on the water flow, wind speed and wind direction at the time of a gaseous or liquid release. This information is used to evaluate how the radionuclides will be distributed in the area. The tumt important factor in evalu-ating the exposure pathways is the use of the envhunment. Many factors are con-sidered such as dietary intake of residents, recreational use of the area, and the location of homes and farms in the area. The external and internal exposure pathways considered are shown in
- Figure 1 11 and 1 12. The release of radioactivity in gaseous effluents involves pathways such as direct radiation, deposition on plants, deposition on soil, inhala-tion by ardmals destined for human consumption, and inhalation by humans.
The release of radioactivity in liquid effluents involves pathways such as drinking water, fish consumption, and direct exposure from the lake, both shoreline and immersion bi the lake (swimming). Although radionuclides can reach humans by many different pathways, some are more important than others. The pathway of concern is termed the critical path. way, Tne critical pathway is the exposure pathway which will provide, for a spe-cific radionuclide, the greatest dose to a population, or to a specific group of the population, called the critical' group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, or othe cultural fac-tors The dose may be delivered to the whole body or to a specific organ. The organ recching the greatest fraction of the dose is called the critical organ. 1 39
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l i Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station l Dose Assessment L Dose is the energy deposited by radiation in an exposed individual. Whole body i radiation exposure involves the exposure of all organs. Most background expo- l sures are of this form. Both non radioactive and radioactive elements can enter l the body through i.nhalation (breathing) or ingestion (eating, drinkirig). When they do, the.y are usually not distributed evenly. For example, radioactive lodine selectively concentrates in the thyroid gland, while radioactive cesium collects in muscle and liver tissue, and radioactive strontium collects in bone tissue. 4 The total dose to organs from a given radionuclide depends on the radioactivity present in the organ and the amount of time that the radionuclide remains in the organ. Some radionuclides remain for very short times due to their rapid radio-active decay and/or elimination rate from the body, while other radionuclides may remain in our bodies for longer periods of time. The dose to people in the area surrounding Davis Besse is calculated for each lig-uld or gaseous release.The dose due to radioactivity released in gaseous efflu-a ents is calculated using factors such as the amount of radioactivity released, the concentration of radioactivity beyond the site boundary, the weather conditions present at the time of the release, the locations ofimportant pathways (cow milk, goat milk, vegetable gardens, and residences), and usage factors (inhalation, food consumption). The dose due to radioactivity released in liquid efiluents is calcu. i lated using factors such as the amount of radioactivity released, the total volume of radioactive liquid, the total volume of dilution water, near field dilution, and useage factors (water and fish consumption, shoreline and swimming factors). These calculations produce a conservative estimation of the dose. RESULTS The results of the effluent monitoring program are reported to the Nuclear Regu-latory Commission in the Semiannual Effluent and Waste Disposal Report For 1990, the doses from radioactivity released in gaseous and liquid effluents were a small fraction of the Davis Besse Technical Specifications limits. The offsite whole body dose due to radioactivity released in liquid effluents was approxi - mately 7.3% of the annual Technical Specifications limits, The offsite gamma and beta air doses due to radioactivity released in gaseous effluents were smaller; each was less than 0.4% of the annual Technical Specifications limits. Table 1-4 summarizes the dose due to radioactivity released in effluents in 1990. n 1 41
Annual Environmental Operating Report WX) Davis Besse Nuclear Power Station Table 1.-8: 1990 Offsite Doses to the Public due to Radioactivity Released in i Gasecutand Liould Emuents . 1990 Annual Percent Dose Limit of Limi Liquid Emuents Whole Body 0.22 mrem 3 mtem 7.3% Organ (liter) 0.31 mrem 10 mrem 3.1% Gaseous Emuents ; Noble Gas Gamma (air dose) 0.024 mrad 10 mrad 0.24 % j Beta (air dose) 0.%8 mrad 20 mrad 0.34 % ! lodine 131, tritium and ; particulates with hair. ! lives greater than 8 days 0.053 mrem 15 mrem 0.36 % l l l Prior te January 1,1990, a smallleak appeared in one of the steam generators wh'ch allowed a small fraction of the radioactivity present in the primary coolant to be transferred to the secondary loop. Although the steam generator leak has contributed to the radioactidty released in effluents and to the dose to the public during 1990, the ofsite doses have remained less than 8% of the annualTechni. cal Specifications dose limits. 1 42
Annual Environmental Operating P # port 19X) Davis Ber.so Nuclear Powor Stat 6on References
- 1. "A Citizen's Guide to Radon: What it is and What to do About it," United States Emironmental Protection Agency, United States Departrnent of flealth Services, Centers for Disease Control (August 1986).
- 2. " Basic Radiation Protection Criteria," Report No. 39, National Council on Ra-diation Protection and hicasurements, Washington, D.C. (January 1971).
- 3. Cesium 137 from the Emironment to hian: hietabolism and Dose," Report No. 52, National Council on Radiation Protection and hicasurements, Washing-ton, D.C. (January 1977).
- 4. Deutsch, R.," Nuclear Power, A Rational Approach," fourth edition, GP Courseware, Inc., Columbia, hiD. (1987).
- 5. Eisenbud, hi.,"Emironmental Radioactivity," Academic Press, Inc., Orlando, FL (1987).
- 6. " Environmental Radiation hieasurements," Report No. 50, National Council on Radiation Protection and hicasurements, 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 Protec-tion and hicasurements, Washington, D.C. (December 1987).
- 8. "licalth Effects of Exposure to Low Levels of ionizing Radiation: BEIR V,"
Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects Research Commission on Life Sciences, National Research Council, Na-tional Academy Press, Washington, D.C. (1090).
- 9. liendee, William R., and Doege, Theodore C.," Origin and licalth Risks of in-door Radon," Seminars in Nuclear hiedicine, Vol. XVill, No.1, American hiedi-cal Association, Chicago,IL (January 1987),
iC 14urley, P.,"Living with Nuclear Radiation," University of hiichigan Press, Ann Arbor, hil. (14R2). 1 43
Annual Environmental 0perating Report 1 990 Davis Besse Nuclear Power Station
- 11. " Indoor Air Quality Emironmental Information Handbook: Radon," pre-pared for the United States Depar: ment of Energy, Assistant Secretary for Emi-ronment. Safety and Health, by hiueller Associates,Inc., Baltimore, MD.
(January 1986). 12."lonizing Radiation Exposure of the Population of the United States," Re-port No. 93, National Council on Radiation Protection and Measurements, Wash-ington, D.C. (September 1987). 13 " Natural Background Radiation in the United States, Report No. 45, Na-tional Council on Radiation Protection and Measurements, Washington, D.C. (November 1975).
- 14. " Nuclear Energy Emerges from 1980's Poised for New Growth," U.S. Council
- for Energy Awareness, Washington, D.C. (1989).
- 15. " Nuclear Power: Answers to Your Questions," Edison Electric Institute, Wash-ington, D.C. (1981).
- 16. " Nuclear Power: Answers to Your Questions," Edison Electric Institute, Wash-ington, D.C. (1987).
- 17. "Public Radiation Exposure From Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measure-ments, Washington, D.C. (December 1987).
- 18. " Radiation Protection Standards," Department of Emironmental Science and Physiology and the Office of Continuing Education, Harvard School of Pubile Health, Boston, MA. (1986).
- 19. "hadon in Buildings: Sources, Biological Effects, Monitoring and Control,"
course notes from the Advanced Workshop on Occupational and Emironmental Radiation Protection, Office of Continuing Education, Harvard School of Public Health, Boston, MA. (July 19,89).
- 20. " Removal of Radon from Household Water," United States Emironmental Protection Agency, Washington, D.C. (September 1987).
- 21. "1985 Radiological Emironmental Monitoring Report for Three Mile Island Station," GPU Nuclear Corporation, Middletown, PA (1985).
l 1 44 l
Annual Environmental Operating Report 1900 Davis Besse Nuclear Power Station
- 22. " Sources, Effects and Risks of ionizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation 1988 Report to the General As-sembly, United Nations, New York (1988),
- 23. " Standards for Protection Against Radiation," Title 10, Part 20, Code of Fed-eral Regulations, Washington, D.C. (1988).
- 24. " Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50, Code of Federal Regulations, Washington, D.C. (1988).
- 25. " Environmental Radiation Protection Standard for Nuclear Power Opera-tions," Title 40, Part 190, Code of Federal Regulations, Washington, D.C. (1988).
- 26. 'Titium in the Environment," Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979).
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Davis Besse Nuclear Power Station 1930 Annual 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 ade-quacy of containment and effluent controls, to assess the radiologicalimpact,if any, that Station operation has on the surrounding area, and to determine compil-ance with applicable radiation protection guides and standards. Environmental surveillance at Davis Besse has been a part of the radiological programs con. ducted at the Station for approximately 19 years. The Radiological Environmen-tal Monitoring Program was established in 1972, five years before the Station became operational. 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 operationalin 1977, the REMP continued to measure radiation and radioactivity in the surrounding arec. The operational surveillance program has been collecting environmental data for over 13 years now. A wide variety of emironmental samples are collected as part of the REMP at Davis Desse. The selection of sample types is based on the established critical pathways for the transfer of radionuclides through the environment to humans. The selection of sampling locations is based on sample availability, local meteo. rological and hydrological characteristics, local population characteristics, and land usage in the area of interest, The selection of sampling frequencies for the various emironmental media is based on the radionuclides of interest, their re-spective half lives, and their behavior in both the biological and physical environ-ment. A description of the Radiological Emironmental Monitoring Program at Davis-Besse is provided in the following section, in addition, a brief history of analyti-cal results for each sample type collected since 1972, and a more detailed summary of the analyses performed in 1990, are also provided. 21 4
Annual Environmental Operating Report 1930 Davis Besse Nuclear Power Station Preoperational Surveillance Program All nuclear facilities are required by the federal government to conduct radiologi-cal emironmental monitoring prior to constructing the facility. This preoperatio-nal surveillance program should be 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 emironmen-tal samples should include not only those nuclides expected to be released during facility operation, but should also include typical fallout radionuclides and natu-ral background radioactivity. All environmental media with a potential to be af-fected by facility operation, as well as those media directly in the critical pathways, should be sampled on at least an annual basis during the preoperatio-nal phase of the environtnental surveillance program. The preoperational surveillance program design, including nuclide/ media combi-nations, sampling frequencies and locations, collection techniques, and radioanalyses performed, should be carefully considered and incorporated in the design of the operational surveillance program. In this manner, data can be com-pared in a variety of ways (for example: from year to year, location to location, etc.),in order to detect any radiological impact the facility has on the surround-ing emironment. 'Ibtal data collection during the preoperational phase should be planned to provide a comprehensive database for evaluating any future changes in the environment surrounding the nuclear facility. Davis Besse began its preoperational environmental surveillance program five years before the Station began producing power for commercial use in 1977. Data accumulated during those early years provide an extensive database from which Station personnel are able to identify trends in the radiological characteris-tics of the local environment. The emironmental surveillance program at Davis-Besse will continue well after the Station has reached the end of its economically usefullife and decommissioning has begun. Such a rigorous,long-term emiron-mental surveillance program provides a sort ofinsurance that any radiologicalim. pact the operation of Davis Besse has had on the surrounding environment, since its design conception through its productive years to its eventual shutdown, is detected to preserve the integrity ef the local environment. 22 _ __- - - -__ A
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report Operational Surveillance Program Ob,ectives , The operational phase of the emironmental surveillance program at Davis Besse was designed with the following objectives in mind: e to fulfill the obligations of the radiological surveillance sections of the Station's Technical specifications, e to determine whether any significant increase occurs in the concentration of radionuclides in critical pathways, e to identify and evaluate the buildup,if any, of radioactivity in the local emironment, or any changes in normal background radioactivity, and e to verify the adequacy of Station controls for the release of radioactisity. Quality Assurance ' An important part of the environmental monitoring program at Davis Besse is Quality Assurance (QA). QA consists of all the planned and systematic actions that are necessary to provide adequate confidence in the results of an acti ity such as the REhiP. QA is a program which checks the adequacy and validity of the monitoring program through routine audits, strict adherence to written poll-cies and procedures, and attention to good record keeping practices. The QA program at Davis Besse is conducted in accordance with the guidelines specified in NRC Regulatory Guide 4.15," Quality Assurance for Radiological hionitoring Programs." The QA program is designed to identify possible defi-ciencies in the REhiP so that corrective actions can be initiated promptly. Davis-Besse's Quality Assurance program also provides confidence in the results of the REhiP through: e performing regular audits (investigations) of the REhtP, including a careful examination of sample collection techniques and record keeping, e performing audits of contractor laboratories which analyze the emironmental samples, e requiring analytical contractor laboratories to participate in - the United States Emironmental Protection Agency Cross Check Program, 23
Annual Enwonmental Operating Report 1990 Davis Besse Nuclear Power Station e Requiring analytical contractor laboratories to split samples for separate analysis followed by a comparison of results. e splitting samples prior to analysis by independent . laboratories, and then comparing the results for agreement, and, finally, e requiring analytical contractor laboratories to perform in house spiked sample analyses. OA audits and inspections of the Davis Besse REMP are performed by groups such as Davis Besse's OA department and representatives from the NRC. In ad. dition, the NRC and the Ohio Department of Health (ODil) also perform inde-pendent emironmental monitoring in the vicinity of Davis Besse. The types of samples collected and the sampling locations used by the NRC and ODH were incorporated in Davis Besse's REMP. Hence, the analytical results from the dif-ferent programs can be compared. This practice of comparing results from iden-tical samples, collected and analyzed by different parties, provides a valuable OA tool to verify the quality of both the laboratories' analytical procedures and the data generated, in 1987, environmental sampling personnel at Davis Besse incorporated their own Quality Assurance program into the REMP Duplicate samples, called qual-ity 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 the analyticallaboratory would not know the sam-pies were identical. The laboratory results from analysis of the quality control samples and the routine samples could then be compared for agreement. Qual-ity control sampling has become an important part of the REMP since 1987, pro-viding a check on the quality of analyses performed at the contracted analytical laboratory. 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 rou- < tine sample couterpart. Program Description m.u The Radiological Environmental Monitoring Program at Davis Besse consists of the collection ~and analysis of a wide variety of emironmental samples. Samples i are collected on a routine basis either weekly, monthly, quarterly, semiannually, 2-4
Oavis Berse Nuclear Power Station 1990 Annual Environtnental Operating Report or annually, depending upon the sample type and nature of the radionuclides of interest. Environmental samples collected by Davis Besse personnel are disided into four general categories: e atmospheric -including samples of airborne particulates, airborne radiciodine, and snow, e terrestrial including samples of milk, groundwater, broad leaf vegetation and fruits, animal / wildlife feed, soll, and wild and domestic meat, e aquatie including samples of treated and untreated surface water, fish, and shoreline sediments, and e direct radiation - measured by thermoluminescent dosimeters. All erwironmental samples are tabled using a sampling code. Table 21 provides the sample codes and collection frequency for each sample type, 25
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Annual Environmental Operating Report i990 Davis Besso Nuclear Power Station jable 23: Sarnple Codes and Collection Frequencies Sampic Type Sample Code Collection Frequency Airl>orne Particulate AP Weekly Airborne lodine Al Weekly Thermoluninescent Dosimeter TLD Quartert,s, Annually Snow SNO When Available Stilk Nill $1onthly (semi monthly during grazing season) Groundwater GW Quarterly Broad Leaf Vegetation and Fruits BLY/FRU hionthly (July September) Surface Water 'IYeated SWT Weekly Surface Water Untreated SWU Weekly Fish FIS Semiannually Shoreline Sediments SED Semlannually_ Soil Sol Semiannually Animal / Wildlife Feed AF Semlannually hicat Domestic hie (D) Annually hient Wild hie (W) Annually 2-6
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his.Bem Nuclear Power Stauon 1993 Annual Environmental Operating Report l I Samplitvg Locations REMP samples are collected at numerous locations, both onsite and 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. Gener-ally, they are located within five miles of the station. Controllocations are those which should be unaffected by Station operations. Typteally, thesc are more than five miles away from the Station. Data obtained from the indicator locations are compared with data from the controllocations. This comparison allows REMP personnel to take into accoutit naturally occurring background radiation, includ-ing nuclear fallout from weapons testing, in evaluating any radiological impact Davis.Hesse has on the surrounding environment. Data from indicater and con. trol locatiorts are also compared with preoperational data to determine whether significant variations or trends exist. Beginning on page 2-8 through 211 Figures 21 through 2 4 identify the REMP sampling locations on the Davis Besse site, within a five mile radius,within a sen mile radius, and in Lake Erie, respectively Table 2 2 provides a more detailed listing of the locations of all sampling sites and the types of samples collected at each site. I 27
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Figure 2-4
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and 'Iypes of Samples Collected at Each Site Wpq of Location Description %pe(s) of Number Location Samples" (1,C or OC)* T1 1 Site boundary,0.6 mile ENE of Station. AI, AllTLD SOI, SNO T2 i Site boundary,0.9 mile E of AI, AP, TLD, Station. SOI l T.3 i Site boundary,1.4 miles ESE of AI, AP, TLD, Station. SOI, SWU, SED T-4 i Site boundary,0.8 mile S of AI, AP, TLD, 4
' Station. SOI, SED, SNO T 5_ l Site boundary,0.5 mile W ofTLD TLD Station.
T6 I Site boundary,0.5 mile NNE TLD of Station. T7 i Sand Beach, main entrance,0.9 AI, AP, TLD,' mile NW of Station. SOI, GW - T8_ I Farm,2.7 miles WSW of Station. AI, AP, TLD, MIL, SOI, AF, BLV, FRU, SNO
- * - I = Indicator C = Control QC = Quality Control
" Refer to Samp'e Codes in Table 21, page 2 6.
s L 2-12 1
l I Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and Types of Samples Collected at Each Site Type of laation Description Type (s) of Number Location Samples" (1,C or OC)* T9 C Oak Harbor Substation,6.8 miles AI, AP, TLD, miles SW of Station. SOI, SNO T 10 1 Site boundary,0.5 mile SSW of TLD Station. T ll C Port Clinton Water Treatment Plant AI, AP, TLD, 9.5 miles SE of Station. SOI, SNO S%T, SWU T 12 C Toledo Water Treatment Plant. AI, AI, AP, TLD, AP, TLD, and SOI collected 23.5 SOI, SWU, SWT q miles WNW of Station, SWU and SWT. l samples taken from Intake Crib 11.25 l miles NW of Station. T.23 C -South Bass Island,14.3 miles ENE of TLD, SOI, SED Station. SWU, S%T, GW FRU T.24 C- Sandusky,21.0 miles SE of Station. TLD, MIL-T 25 I Farm,3.7 miles S of Station. BLV, FRU '
- I= Indicator C = Control - QC = Quality Control
" Refer to Sample Codes in Table 21, page 24, 2-13
Annual Environmental Operating Report 1 990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and Types of Samples Collected at Each Site Typei.f Location Description Type (s) of Number Location Samples" (I,C or OC)* T 27 C Crane Creek State Park,53 miles Al, AP, TLD, WNW of Station. sol, GW, SED T 28 1 Treated and untreated water supply, SWU, SWT at the Davis Besse site. T 31 I Onsite roving location. Me(W), AF T 33 I Lake Erie, within 5 mile radius FIS of Station. T34 C Offsite roving location, land greater. Me(W), AF than 10 mile radius of Station. T 35 C Lake Erie, greater than 10 mile FIS radius of Station. T 37 C Farm,13.0 miles SW of Station. BLV, FRU T 38 i Site boundary,0.6 mile ENE of TLD Station. T 39 I Site boundary,1.2 miles ESE of TLD Station.
- I= Indicator C = Control QC = Quality Control
" Refer to Sample Codes in Table 21, page 2-6, 2-14
_ . - . _ . _ . - _ _ . _ . .__.._-m._ ... _ . _ . _ , y
- Annual Environmental Operating Report 1990 Davis-Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and 'lypes of -
Samples Collected at Each Site Type of Location Description Type (s) of
- Number Location Samples" (l,C or OC)*
T40 1 Site boundary,0.7 mile SE of TLD Station. T41 I Site boundary,0.6 mile SSE of TLD Station. T-42 1. Site boundary,0.8 mile SW of TLD Station. T-43 I- Site boundary,0.5 mile SW of TLD , Station. T44- I Site boundary,0.5 mile WSW of TLD Station. l _- T 45 I- Site boundary,0.5 mile WNW of TLD Station. l
. T46-. I- Site boundary,0.5 mile NW of ' TLD Station. '.
T-47 I Site boundary,0.5 mile N of Station. TLD T48 -I Site boundary,0.5 mile NE of Station. TLD T 49_ l' Site boundary,0.5 mile'NE Of Station. TLD
* ! = Indicator C = Control .
QC = Quality Control
~ " Refer to Sample Codes in . Table 21, page 2-6. j 1
2-15 ' 1
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station E 'Ihble 2 2: Description of REMP Sampling Locations and 'lypes of Samples Collected at Each Site Type of Location Description Type (s) of Number Location Samples" (I,C or OC)* T 50 I Erie Industrial Park, Port Clinton, TLD, SWU, SWT 4.5 miles SE of Station. T 51 C Farm,5.5 miles SSE of Station. TLD T 52 I Farm,3.7 miles S of Station. TLD T 53 1 Farm,,4.5 miles S of Station. TLD T.54 ! Farm,4.8 miles SW of Station. TLD, GW T 55 1 Farm,5.0 miles W of Station. TLD T.57 C Farm,22.0 miles SSE of Station. MIIAF T40 1 Site boundary,03 mile S'of Station. TLD T41 1 Site boundan,0.6 mile SE of Station. TLD T42 1 Site boundary,1.0 mile SE of Station. TLD T63 I Site. boundary,1.1 miles ESE of TLD Station. T-64 I Site boundary,0.9 mile E of Station. TLD
* ! = Indicator C = Control QC = Quality Control
" Refer to Sample Codes in Table 21, page 24.
1 1 2-16
- .. . - .. . . . . . . - - . . - - . . - _ _ . . - . - . . . _ _ - . ~ . . . . . . . . - - -
~ Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and Types of
-Samples Collected at Each Site- Type of - Location Description . Type (s) of Nttmber Location Samples" (l,C or OC)*
T45 I Site boundary,0.3 mile E of Station. TLD T46 1 Site boundary,03 mile ENE of Station. TLD T47 I Site boundary,03 mile NNW of Station. TLD T48 I Site boundary,0.5 mile WNW of Station. TLD T49 I Site boundary,0.4 mile W of Station. TLD T 70 I Site boundary,03 mile NNW of Station. TLD- 1 T 71 I . Site boundary,0.1 mile NNW of Station. TLD 1 4 1 T 73 - I Site boundan,0.1 mile WSW of Station. TLD n T 74 - I: Site boundary,0.1 mile SSW of Station. TLD l T 75 I~ Site boundary,0.2 mile SSE of Station. TLD
- T 76 I Site boundary,0.1 mile SE of Station. TLD T 77. I Site boundary,0.1 mile ENE of Station. TLD
* != Indicator C = Control - QC = Quality Control
" Refer to Sample Codes in Table 21, page 24, 2-17
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and lypes of Samples Collected at Each Site Type of Location Description lype(s) of Number Location Samples" (l C or OC)* T 78 C West Sister Island,10.0 miles N of TLD, SWU Station. T 79 QC Quality Control site. TLD T 80 QC Quality Control site. TLD T 82 QC Quality Control site. TLD T-83 QC Quality Control site. TLD T84 QC Quality Control site. TLD T-85 QC Quality Control site. TLD T 86 QC Quality Control site. TLD T-88 QC Quality Control site. TLD T 89 QC Quality Control site. TLD T 90 I Toussaint East and Leutz Roads, TLD 2.0 miles SSW of Station.
* != Indicator C = Control QC = Quality Control
" Refer to Sample Codes in Table 21, page 2 6.
i 2 18
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station l Table 2 2: Description of REMP Sampling Locations and Types of Samples Collected at Each
- Site Type of Location Description Type (s) of Number Location Samples" (l.C or OC)*
T 91 i State Route 2 and Rankle Road. TLD 2.5 miles SSE of Station. T 92 i Locust Point Road,2.7 miles TLD i WNW of Station. T 93 I Twelfth Street, Sand Beach,0.6 mile TLD NNE of Station. T 94 ' i State Route 2,1.8 miles WNW or Station. TLD ' T.95 C State Route 579,9.3 miles W of Station. TLD 1 T.% C State Route 2 and Howard Road, TLD 10.5 miles WNW of Station. T 97 - I Duff Washa and Zetzer. Road, TLD 1.5 miles W of Station. T 98 C Toussaint Portage and Bier Road, TLD 6.0 miles SW of Station. T 99 - I Behlman Road,4.7 miles SSW. TLD of Station.
- ImIndicator C = Control QC = Quality Control
" Refer to Sample Codes in Table 21, page 2-6.
2-19
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and Types of ] Samples Collected at Each Site T,9e of Location Description Type (s) of Number Location Samples" 0,C or QC)* T 100 C Ottawa County liighway Garage, TLD Oak,llarbor,6.0 miles S of Station. T 101 C Finke Street, Oak liarbor,6.5 ralles TLD g of Station. T 102 C Oak Street, Oak liarbor,6.5 miles TLD SSW of Station. T 103 C Lickert Ilarder Road,8.5 miles SW TLD of Station. T 104 C Salem Carroll Road,7 3 miles SW TLD of Station. T 105 C Lake Shore Drive, Port Clinton, TLD 6.0 miles SE of Station. T 106 C Third Street, Port Clinton,8.9 TLD miles SE of Station. T 107 C Little Portage East Road,8.5 TLD miles SSE of Station. T 108 C Boysen Road,9.0 miks S of Station. TLD
- l = Indicator C = Control QC = Quality Control
" Refer to Sample Codes in Table 21, page 2-6, 2-20
. . . . . . . . . .- - . . . .. . - - . ~ . - . - - - ~ . . - - . . - . - -
f f Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and Types of Samples Collected at Each: Site- lype of . Location Description. Type (s) of . Number Location Samplos" 0,C or QC)* T 109 - C Stange Road,8.0 miles W of Station. : TLD T 110 - C- Toussaint Nort.h and Graytown Road, TLD 10.0 miles WSW of Station. T 111 C- Tc6ssaint North Road. 8.3 miles TLD WSW of Station. iT 112 I iThompson Road,1.5 miles SSW of TLD Station. 4 T 113 ~ QC- Quality Control site. TLD 1 T 114 -QC; ; Quality Control site. . TLD . - T l'15 QC- .' Quality Control site.- TLD T 116. . QCL ; Quality Control site. . TLD T 117 QC Quality Control site. TLD-T l'18 . QC Quality C6ntrol site.;z TLD-- T119 QC - - Quality Control site. -TLD:
- I= Indicator C = Control . QC = Quality Control
" Refer to Sample Codes in Table 21, page 2 6.
21
Annual Environmental Operating Report 1990 Davis Bense Nuclear Power Station l Table 2-2: Debeription of REMP Sampling Ucations and '1) pes of Samples Collected at Each Site Type of Location Description hpe(s) of Number Location Samples * * (1,C or QC)* T.120 QC Quality Control site. TLD T 121 i State Route 19,2.0 miles W of TLD Station. T.122 1 Duff Washa and llumphrey Road, TLD 1.7 miles W of Station. T 123 1 Zetzer Road,1.6 miles WSW of TLD Station. T.124 C Church and Walnut Street, Oak TLD Ilarbor,6.5 miles SSW of Station. T.125 I Behlman and Bier Roads,4.4 miles TLD SSW of Station. T.126 I Camp Perry Western and Toussaint - -TLD South Road,3.7 miles S of Station. T.127 I Camp Perr/ Western and Rymers TLD Road,4.0 miles SSE of Station. T.128 1 Erie Industrial Park, Port TLD Clinton,4.0 miles SE of Station.
* != Indicator C = Control QC = Quality ConErol
** Refer to Sample Codes in Table 21, page 2-6. i i
2-22 _- .- . . , g .,
Anrmal Environmental Operating Report 1990 Dav!s Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and 'I) pes of Samples Collected at Each Site Type of Location Description Type (s) of Number Location Samples" 0.C or QC)* y, T 130 I Lake Erie,1.7 miles ESE of SWU , i Station. T 131 i Lake Erie,0.8 mile NE Of Station. SWU T 132 i Lake Erie,1.0 milt E of Station. SWU T 133 i Lake Erie,0.8 mile N of Station. SWU T134 I Lake Erie,1.4 miles NW of Station. S%U T 135 .I Lake Erie,2.5 miles WNW of S%U Station. T 136 i Lake Erie,3.8 miles WNW of SWU l Station. T137. C Lake Erie,7.0 miles WNW of SWU Station. T 138 C Lake Erie,11.0 miles NW of SWU. Station.
'T 141 - QC Quality Control site. GW
* != Indicator
- C = Control- QC = Quality Control
** Refer to Sample Codes in Table 2-1, page 2 6.
2 23
r-Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and lypes of Samples Collected at Each Site Type of Location Description Type (s) of Number Location Samples" (1,C or QC)* T 143 QC Quality Control site. SwT T 144 1 Green Cove Condominiums,0.9 SWT mile NNW of Station. T145 QC Quality Control site. SWU T147 C Farm,5.7 miles WSW of Station. Me(D), AF T 150 1 Ilumphrey and fiollywood Road, TLD 2.1 miles NW of Station. T 151 1 State Route 2 and llumphrey Road, TLD 1.8 miles WNW of Station. T 153 i Leutz Road,1.4 miles SSW of TLD Station. T 154 1 State Route 2,0.7 mile SW of TLD Station. T 155 C Fourth and Madison Street, Port TLD Clinton,9.5 miles SE of Station. T 156 C Lake Erie,8.0 miles WNW of Station. SWU
* != Indicator C = Control QC = Quality Control
" Refer to Sample Codes in Table 21, page 2-6, 2-24
Annual Enykonmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sarnpling Locations and lypes of Samples Collected at Each Site hpe of Location Description hpe(s) of Numbr Location Samples" 0.C or QCP T.157 C Lake Erie,8.9 miles WNW of Station. SWU T 158 C Lake Erie,10.0 miles WNW of SWU Station. T.159 C Lake Erie,10.2 miles WNW of Station. S%t T.160 i Lake Erie,3.5 miles ESE of Station. SWU T 161 1 Lake Erie,4.7 miles SE of Station. SWU T 162 C Lake Erie,5.4 miles SE of Station. SWT T.163 C Lake Erie,8.5 miles SE of Station. SWU T164 C Lake Erie,9.5 miles ESE of Station. SWU T.165 C Lake Eric,10.2 miles ESE of Station. SWU T 166 C Lake Erie,12.0 miles ESE of Station. SWT T 167 C Lake Erie,11.5 milmes E of Station. SWT T 168 C Lake Erie,12.5 miles ENE of Station. SWU
- I= Indicator C = Control QC = Quality Control
" Refer to Sample Codes in Table 21, page 2-6.
2-25
Annual Environmental Operating Report 1990 Davls Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and Types of Samples Collected at Each Site Type of location Description Type (s) of Number Location Samples" (1,C or QC)* T 169 C Lake Erie,14.0 miles ENE of Station. SWU T 170 C Lake Erie,15.0 miles ENE of Station. SWU T 171 C Lake Erie,15.5 miles ENE of Station. SWU T 172 C Lake Erie,17.0 miles ENE of Station. S%1) T 173 C Firelands Winery, Sandusky, FRU 20.0 miles SE of Station. T 173A C Firelands Vineyard, North Bass Island, FRU 16.3 miles ENE of Station. T 197 I Farm,1.7 miles W cf Station. Me(D), AF T 198 I Toussaint Creek Wildlife Area,4.0 AF miles WSW of Station. T 199 C Farm,8.5 miles SW of Station. MIL T 200 QC Quality Control site. TLD T 201 I Sand Beach,1.1 miles NNW TLD of Station.
- I= Indicator C = Control QC = Quality Control
" Refer to Sample Codes in Table 21, page 2 6.
l. 2-26
- ._. - ._ _. . . __. . . _ . _ . _ . _ . . _ . . ~ -
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 2 2: Description of REMP Sampling Locations and Types of Samples Collected at Each Site Type of Location Description Type (s) of Number Location Samples" 6 C or QC)* ~ T.202 I Sand Beach. 0.8 miles NNW of Station. TLD T 203 1 Sand Beach,0.7 miles N of Station. ' TLD T 204 I Sand Beach,0.7 miles N of Station. TLD T 205 I Sand Beach,0.5 miles NNE of Station. TLD T 206 I Site bounday,0.6 miles NW of Station. .TLD T.207 - I- Site boundary,0.5 miles N of Station. TLD T.208 I Site boundary,0.5 miles NNE of Station. TLD l i i i: 1 1
- I = Indicator C = Control . QC = Quality Control l
- " Refer to Sample Ccdes in Table 21, page 2-6. I 2-27 l
{ l l
l Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Sample Analysis When emironmental samples are analyzed for radioactisity, several types of measurements may be performed to provide information about the types of radi-ation and radionuclides present. The major analyses that are performed on envi-ronmental samples collected for the Davis Besse REMP include: e Gross beta analysis e Gamma spectral analysis e Tritium analysis
- Strontium analysis e) Gamma dose (TLDs only)
Gross beta analysis measures the total amount of beta emitting radioactivity present in a sample. Beta radiation may be released by many different radionu-clides. Since beta decay gives a continuous energy spectrum rather than the dis-crete 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 radioactivity; 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 radionuclide present in the sample that emits gamma radiation, and the amount of radioactivity emitted by each. No two radionuclides emit the same energy gamma rays. Therefore, each radionuclide has a very specific" fingerprint" that allows for swift and accu-rate identification. For example, gamma spectral analysis can be used to identify the presence and amount ofiodine-131 in a sample, lodine 131 is a man made radioactive isotope ofiodine that may be present in the emironment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power stations. Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the amount of radioactivity present as a result. As discussed in Chap-ter One, tritium is a natural or man made isotope of hydrogen 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 emi-2 28
^
i Davis-Besso Nuclear Power Station 1990 Annual Environmental Operating Report ronment as a result of fallout from nuclear weapons testing. Strontium is usually incorporated into the calcium pool of the biosphere. In other words, strontium tends to replace calcium in living organisms and becomes incorporated in bone tissue. The principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from gaseous releases. Gamma De es received by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure that is more thoroughly discussed on page 2 55. Table 2 3 provides a listing of the type (s) of analyses performed on em>ironmen-tal 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 (LLD) is the smallest amount of sam-ple activity that will give a net count for which there is confidence, at a predeter-mined level, that radioactivity is present. When a measurement of radioactivity is reported as less than the LLD ( < LLD), it meanz hat the radioactivity is so low that it cannot be accurately measured by that particular method for an indi-vidual analysis, with any degree of confidence. Sample History Comparison The concentration of radioactivity present in the environment will vary due to factors such as weather or variations in sample collection techniques or sample analysis. This is one reason why the results of sample analyses are compared with results from other locations and from earlier years. Generally, the results of sample analyses are compared with preoperational and operational data. Addi-tionally, the results of indicator and control locations are also compared. This al-lows REMP personnel to track and trend the radioactivity present in the environment, to assess whether a buildup of radionuclides is occurring, and to de-termine the effects,if any, the operation of Davis-Besse is having on the envbon-ment. If any unusual radioactivity is detected, it is investigated to determine whether it is attributable to the operation of Davis-Besse, or to some other . source such as nuclear weapons testing. A summary of the REMP sample analy-ses performed from 1972 to 1990 is provided in the following section. a 2 29
Annual Environmental Operating Report 1990 Davis Besse Nuclear Fower Station Table 2 3: Radlochemical Analyses Performed on REMP Samples Sample Type _ Analyses Performed , ATMOSPHERIC MONITORING Airborne Particulates Gross Beta Gamma Spectral Strontium 89 Strontium 90 Airborne Radioiodine lodine-131 Snow Gross Beta Gamma Spectral Tritium TERRESTRIAL MONITORING Milk Gamma Spectral Iodine 131 Strontium 89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectral Tritium Strontium 89 Strontium 90 Broad Leaf Vegetation and Fruits Gamma Spectral
. Iodine 131 Strontium 89 Strontium-90 Animal / Wildlife Feed Gamma Spectral Soil Gamma Spectral Wild and Domestic Meat Gamma Spectral 2 30
s a Davis Besse Nuclear Power Station . 1990 Annual Environmental Operating Report t Table 2 3: Radiochemical Analyses Performed on REMP Samples (continued)'- l Sample Type Analyses Performed AQUATIC MONITORING Untreated Surface Water Gross Beta Gamma Spectral Tritium Strontium 89 ; Strontium 90 .; Treated Surface Water Gross Beta Gamma Spectral L Tritium Strontium 89 Strontium 90 lodine 131 . Fish Gross Beta j Gamma Spectral -! Shoreline Sediments Gamma Spectral i DIRECT RADIATION MONITORING Thermoluminescent Dosimeters Gamma Dose ? Atmospheric Monitoring:- i e Airborne Particulates: , i LNo radioactive particulates have been detected as a result of g . Davis Besse's operation. Only natural and fallout radioactivity from
' nuclear weapons testing and the 1986 nuclear accident at Chernobyl K ~ have been detected.
l fI 2 31
.+,_a_ -_
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station 1 e Airborne Radiolodine: [ Radioactive iodine 131 fallout was detected in 1976,1977, and 1978 l from nuclear weapons testing, and in 1986 (0.12 to 1.2 picoeuries per l cubic meter) from the nuclear accident at Chernobyl. e Snow:- Only normal background and fallout radioactivity from nuclear weapons testing have been detected. l Terrestrial Monitoring: i e Groundwater: Only naturally occurring background radioactivity has been detected in groundwater. e Milk: Iodine 131 from nuclear weapons testing fallout was detected in 1976 R ' and 1977 at concentrations of 1.36 and 23.9 picoeuries/ liter, respectively. In 1986, 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 Davis Besse. , e Domestic and Wild Meat:- Only naturally occurring potassium 40 and very low cesium 137 activity has been detected in meat samples. Potassium-40 has ranged from 1.1 to 4.6 picoeuries/ gram wet weight. Cesium 137 was detected in 1974,1975, and 1981 due to fallout from nuclear weapons testing, e Broad Leaf Vegetation and Fruits:. , Only natural background radioactivity and radioactivity from nuclear l weapons testing has been detected, e Soil: 1 Only natural background radioactivity and radioactivity from nuclear , weapons testing and the 1986 nuclear accident at Chernobyl has been 'i detected. e Animal / Wildlife Feed:
- Only natural background radioactivity and radioactivity from weapons testing has been detected.
2-32
--l_--_---__------__ .--- -_ -- ---__ - w
Davis Bosso Nuclear Power Station 1990 Annual Environmental Operating Report Aquatic Monitoring: e Surface Water (Treated and Untreated): In 1979 and 1980, th tritium concentrations at location T 7 were above normal background. Location T-7 is a beach well fed directly by 1.2ke Erie.The fourth quarter sample in 1979 read 590 picoeuries per liter, and the first quarter sample in 1980 had a concentration of 510 picoeuries per liter above the normal background concentration of 450 picoeuries 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. Howeser, the results at T-7 were more than 39 times lower than the annual average concentration allowed by the EPA National Interim Primary Drinking Water Regulations (40CFR141), and were only 0.018% of the Maximum Permissible Concentration (MPC)(3,000,000 picoeuries per liter) for tritium in unrestricted areas. The follow up sample was less than 0.1% of the MPC. None of the subsequent samples indicate any significant difference between the background tritium concentration and the concentration at T 7. e Fish: Only natural background radioactivity and radioactivity from nuclear testing has been detected, e Shoreline Sediments: Only natural background radioactivity and radioactivity from nuclear testing and the 1986 nuclear accident at Chernobyl has been detected. Diroct Radiation Monitoring: e Thermoluminescent Dosimeters (TLDs): The annual average gamma dose rates recorded by TLDs have ranged from 49 to 87 millirem per year at controllocations, and between 44 and 63 millirem per year at indicator locations. No increase above natural background radiation attributable to the operation of Davis-Besse has been observed. L l l l l l 2 33
Annual Environmental Operating Report 1990 Davis Besso Nuclear Power Station 1990 Sampling Program The Radiological Environmental hionitoring Program (REMP) is conducted in accordance with the Davis Besse Nuclear Power Station Operating License, Ap-pendix A, Technical Specifications. The program includes the collection and analysis of airborne particulates, airborne radiciodine, snow, groundwater, milk, domestic and wild meat, fruits and broa6 leaf vegetation, soil, treateo and un-treated surface water, fish, shoreline sediments, and measurements of direct ra-diation (refer to Table 2-4). All samples are sent to an independent laboratory for analysis. Although previous years' sampling programs satisfied all regulatory require-ments, in 1987, a REMP Enhancement Program was initiated. In an effort to im-p!ement a more comprehensive REMP, the number of samples collected and analyzed was selectively increased during 1987 and 1988. Expansion of the REMP was achieved by increasing the number of sampling locations and types of samples collected, and by collecting duplicate, or quality control samples. As a result of the REMP Enhancement effort,1990 REMP included over 1700 more samples than required by the Technical Specifications. During 1990, only 29% of the samples collected for REMP were required to satisfy regulatory re-quirements. In addition, of the 138 sampling locations utilized in 1990,23 of these, or 16% of the total were quality. control locations. REMP SAMPLES COLLECTED sonow. coucted v Aname periorm.o
.m --
~
t
' io m s, n c .m. 'm u r--
Figure 2 5 : In 1987, the number of samples collected and analyses performed were selectively increased. Since 1986, the number of samples collected have only increased slightly. The number of analyses performed varied because of the types of samples missed and the analyses varied with each sample type. I 2-34
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report Table 2-4: Sample Collection Summary Sample Collection Number Number of Number of
'Iype _
Type'/ of Samples Samples (Remarks) Frequency" 1Acations Collected Missed ATMOSPHERIC Airborne Particulates C/W 10 520 2"' , Airborne Radiciodine C/W 10 520 2"' Snow G/AQ 5 5 0 TERRESTRIAL Milk (May.0ct.) O/SM 4 46 3 (Nov Apr.) G/M 4 20 3 Groundwater G/O 4 20 0 Edible Meat
- a. wild ' GIA 1 3 0
- b. domestic G/A 2 1 ten
- Broad Leaf Vegetation / Fruit (July Sep.) G/M S 20 0 Soil G/S 11 22 0 Ammal/ Wildlife feed G/A 6 5 1""
AQUATIC Treated Surface Water G/WM 7 327 2"" Untreated Surface Water G/WM 29 436 3"" Comp /WM 5- 208 2" " Fish (3 species) G/SA 2 11 1"" Shore!ine Sediments - G/SA 4 9 0 DIRECT RADIATION Thermoluminescent C/M 0 0 0 Dosimeters C/O 115 445 15"" C/A 115 109 6""
- hye of collection:l C/ = Continuous; G/ = Grab; Comp / = Composite.
" Frequency of collection:
!WM = Weeklycomposited Monthly;/W = Weekly; >
/SM = Semimonthly;/M = Monthly;
/0 = Quarterly;/SA = Semiannually;/A = Annually;
/AQ = When available composited Quarterly.
"* Airborne particulate and radiolodine samples were collected but declared invalid due to low volume during sampling period.
*"* The reasons for missed samples is discussed on pages 2 36 and 2-37.
l i l 1 2 35
Annual EnAronmental Operating Report 1990 Davis Besse Nuclear Power Station 1990 Program Deviations Provided below is a description and explanation of all environmental samples which were not collected in 1990. e U ntrs :d surface water from T-3 was unavailable the weeks of January 2,8, and 15 because the Toussaint River was frozen.
- h1 ilk was not collected from the dairy cow at T-199 the weeks of January 8, February 12, March 13, April 9, July 24, and August 13,1990 because oflow milk production from the cow.
e Airborne radiciodine and particulate sample from T-11(Port Clinton) for week of January 22,1990 were considered invalid samples because of low sample volume caused by a pump malfunction. The LLD for this 3 airborne radiciodine sample was < 0.24 pCi/m instead of < 0.07 3 pCi/m .
- A composite sample of untreated ;urface water at T-28 was unavailable for the weeks of February 5 and 13,1990 because the water compositor malfunctioned.
- Treated water sample was not collected at T-144 the week of February 26,1990 due to frozen faucet. .
- There were no TLD data for locations T-122 and T-203 for first quarter 1990, because TLDs were lost due to vandalism.
- There were no TLD data for location T-78 and T-79 for 1990 because TLDs are located on an island in Lake Erie and lake conditions did not permit collection.
e There were no TLD data for location T-109, T-93, T-114, and T-202 during second quarter 1990, because TLDs were lost due to vandalism.
- A composite untreated surface water sample at T-12 for week of September 4,1990 was not available, from personnel contracted to collect the sample. A grab sample was collected as a substitute, e A chicken, eggs and animal feed samples were not collected during 1990 at T-147 because the person no longer raised chickens.
- A treated surface water sample was unavailable at T-23 from February through September 1990 due to policy changes at the Water Treatment Facility. Therefore, a new contract was written. A suitable substitute was unavailable.
e The February 1990 composite of untreated surface water for T 23 was lost in transit to the analyticallaboratory. 2 36
^ aDesuegut.9 Davie B:sse Nuclear Power Station 1990 Annel Environm:ntal Op; rating Report e A carp sample was unavailable at T 33 during November because this species was rot in the nets at the time of collection.
- The airborne iodine and particulate sample at T 7 collected on September 10,1990 wLs considered an invalid sample because of low sample volunge. The Ll.D for the airbope iodine (I 131) sample was
< 0.34 pCi/m instead of < 0.07 pCi/m .
e There was no TLD data for location T 150 during fourth quarter of 1990. because TLD was lost due to vandalism o There were no TLD data for locations T-114,T-122, T 202, and T.203 for the Annual 1990 TLD sites because TLDs were lost due to vandalism. In 1990, the major deviation from the REhiP scheduled activities were losses of TLDs due to vandalism and not being able to collect milk sample because low milk production of the dairy cow. A summary of the major deviation is provided in the following paragraphs. Every year, a small percentage of the TLDs placed in the field by REhiP person-net are vanda'ized. However, the lost data can usually be estimated from calcula-tions using data from other nerby locations or from other TLDs (quality control, quarterly, annual) at the same site. He increased number of sampling locations brought on by the REhiP Enhancement Program has provided greater TLD cov-erage over the area monitored by the REhiP, and has helped to reduce the im-pact of lost TLDs on the REhiP database. In 1990,3% of allTLDs in the field - were lost, however, these lost data did not have a significant effect on the quality of the 1990 REhiP. 1 The second major program deviation experienced in 1990 was the loss of milk ' samples at T 199. The sample could not be obtained because the cow's dpy milk production was too low. The low milk production was a result of the cow being pregnant and the newborn calf consuming all the milk. Atmospheric Monttoring Air samples Emironmental air sampling is conducted to detect any increase in the concentra-tion of airborne radionuclides that may be inhaled by humans, or serve as an ex-ternal radiation source. Inhaled radionuclides may be absorbed from the lung, gastrointestinal tract, or from the skin. Air samples collected by the Davis Besse REhiP include both airborne partleulates and airborne radiolodine. Air sam-pling pumps are used to draw continuous samples through particulate membrane 2 37
Annual Environmental Operating Report 1990 Davis.Besse Nuclear Power Station filters and charcoal cartridges at a rate of approximately one cubic foot per min-ute. The samples are collected on a weekly basis,52 weeks a year. Airborne particulate samples are collected on 47 mm diameter membrane filters which are carefully handled so as not to disturb or lose any deposited particu. lates. Charcoal cartridges are miled downstream of the particulate tilters to sample for the presence of airborne radiolodine. The airborne particulate and airborne radiolodine samples are sent to an offsite contractar laboratory for anal-ysis. At the laboratory, the altborne particulate filters are stored for 72 hours be-fore they are analyzed to allow for the decay of naturally occurring short lived radionuclides. However, due to the short half life oflodine 131 (approximately i eight days), the airborne radiciodine cartridges are analyzed upon receipt by the i contractor laboratory. l l Airborne Particulates
- Davis Besse samples air for altborne radioactkity continuously at ten locations, i 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 Magee Marsh (T 27). Gross beta analydis is performed on each of the weekly samples. Each quarter, , the filters from each location are combined (composited) and analyzed for t , gamma emitting radionuclides. The gross beta analyses yielded an annual aver-age of.019 pCi/m3 at both control and indicator location for 1990. Evidence of Average Concentratlon of Bets Emhting Rad 6onuclidee in Airborne Partleunate Sample - Year Concentration Year Concentration
- 1972 0.041 pCVm3 1981 0.090 pCym3*
1973 0.025 pCVm3 1982 0.023 pCVm3 1974 0.190 pCVm3' 1983 0.021 pCVm3 1975 0.096 pCVm3' 1984 0.025 pCVm3 1976 0.089 pCVm3' 1985 0.023 pCVm3 . 1977 0.166 pCVm3* 1986 0.033 pCym3 1978 0.096 pCVm3' 1987 0.022 pCVm3 1979 0.039 pCVm3 1988 0.031 pCVm3 i 1980 0.030 pCVm3 1989 0.024 pCym3 1990 0.019 pCVm3
' Averages were influenced by nuclear fallout from weapons testing.
2 38
Davis Bet $e Nuclear Power Station 1990 Annual Environm:ntd Operating R: port Air Particulates Gross Beta c.os A A
- e. , -
y euu o.i e "L e u., w u., a., o.. YEAR
~ ~ . ,~
l'igure 24 Concentrations of teta emitting radionuclides in airtorne particulate samples were almost identical at indicator and contron locations. the similarity of the results of the control and indicator locations may be seen in similarity of the average monthly results shown in Fig 2 6 (pg 2 39). The highest annual average (.020 pCi/m3) was detected at T-1, T 8, and T 12. The 1990 an. nual average is in good agreement with previous years. The results of the past 18 years are shown on page 2 38. Berylilum 7 was the only gamma emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites. Beryllium 7 is a naturally oc-curring radionuclide produced in the upper atmosphere by cosmic radiation. The average concentration of beryllium 7 was 0.051 pCi/m3 for indicator loca. tions and 0.050 pCi/m3 for controllocations. These values are similar to those observed in the previous preoperational and operational years. No other radio-nuclides were detected above their respective LLDs. Altt>orne lodine 131 Airborne iodine 131 samples are collected at the same ten locations and with the same samplers as the airborne particulates. Charcoal cartridges are installed downstream of the particulate filters to sample for the presence of airborne ra-diciodine. These cartridges are collected weekly, sealed in separate collection bags and sent to the laboratory for gamma spectral analysis, in all of the sample ollected in 1990, there was no detectable iodine-131 above the LLD of 0.07 pCi/m3 In two samples, the LLD of 0.07 pCi/m3 could not be reached due to 2 39
1 1 3 l_ Annual Environmental Operating Report 1F Davis Besse Nuclear Power Station 4
. low sample volume caused by the loss of power to the pumps. These samples in.
~dicated less than the LLD of 0.24 and 0.34 pCl/m3 ofiodine 131.
Snow l l Snow provides a mechanism to sample for radionuclide deposition from the at- ! , mosphere. Since snow is solid,it provides a surface which airborne radionuclides l can be deposited. The radionuclides may be man-made (frorn nuclear weapons i test fallout or nuclear power pl.m: operation) or naturally occurring. Following a fresh snowfall, approximately 10 pounds of snow are collected from ) the surface and packed into a container. Once the snow melts,it is transferred to l
! a one gallon container. At the end of the_ quarter, a one gallon composite is i made for each sampling location. 1 During 1990, snow samples were collected when available from three indicator !
locations (T 1. T 4 and T 8) and 2 control locations (T 9 and T 11). The samples - were anz!yzed for beta emitting radionuclides, tritium, and gamma emitting ra- t dionuclides. In all snow samples collected in 1990, there were no detectable beta emitting ra-dionuclides above the LLD of 0,6 pCi/lin suspended solids. The concentration ' of dissolved solids averaged 0.8 pCi/l at indicator locations and 1.4 pCi/l at con-trollocations. Tritium was not deteeted above the LLD of 330 pCi/lin all sam- L
. ples.1There was no detectable cesium 137 'above the LLD of 10 pCi/l in any of the samples.- !
1 TERRESTRIAL MONITORING-The collection and analysis of groundwater, milk, rneat, fruits and broad leaf veg-etation provides data to assess the buildup of radionuclides that may be ingested by humans. Animal and wildlife feed samples provide additionalinformation on , radionuclides that may be present in the food chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere. Many radionuclides are present in the erwironment due to sources such as cos-mic radiation and fallout from nuclear weapons testing. Some of the radionu-clides normally present are: 2-40
. _ __ _ _ _ _ _ _ _ . _ . . . _ _ . . _ u_ -._..._._.._.___._.-.--._:
l Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report l e tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere, e beryllium 7, present as a result of the interaction of cosmic radiation with the upper atmosphere. e cesium 137, a man made radionuclide which has been deposited in the emironment, (for example, in surface soils), as a result of fallout from nuclear weapons testing and routine releases from nuclear facilities, e potassium-40, a naturally eccurring radionuclide normally found in humans and throughout the erwironment, and e fallout radionuclides from nuclear weapons testing, including strontium 89, strontium 90, cesium 134, cerium 141, cerium 144, ruthenium 103 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 environ. mental samples collected in the vicinity of the Davis Besse Station. The contri-bution of radionuclides from the operation of Davis Besse is assessed by comparing sample results with preoperational data, operational data from previ-ous years, controllocation data, and the types and amounts of radioactivity nor-mally released from the Station in liquid and gaseous effluents. Davis Besse monitors the terrestrial em'ironment through the collection and analysis of samples of groundwater, milk, meat, broad leaf vegetation, fruits, ani-mal feed, and soil. Milk Samples Milk sampling is very important in environmental surveillance because it pro-vides a direct basis for assessing the buildup of radionuclides in the emironment that may be ingested by humans. Milk is particularly important because it is one of the few foods commonly consumed soon after productior,. The milk pathway involves the deposition of radionuclides from atmospheric releases onto forage l consumed by cows. The radionuclides present in the forage can become incorpo-l rated into the milk which is then consumed by humans. Samples of milk are collected at three farms and a commercial dairy store once a month from November through April, and twice a month from May through Oc-tober. Sampling is increased in the summer when the herds are usually outside 2 41
1 Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station l 1 on pasture and not on stored feed. The sample locations consist of one indicator (T 8) and three control locations (T 24, T 57, and T 199). l MILK CONCENTRATION OF SR-90
,ocus 77 78 7e 80 81 82 as 64 as se er as og so YEAR M Indicator ll E control Figure 2 7: Strontium 90 is normally detected in milk samples from both control and indicator locaations. The 1990 average cmcentrations of strontium.90 in milk samples were simillu at control and indicator locations, a trend exhibited in presious years. l l
The milk samples are analyzed for strontium 89, strontium 90, iodine 131 and other gamma emitting radionuclides, stable calcium and potassium. A total of 66 milk samples were collected in 1990. The results obtained were similar to those of the previous years. Strontium-89 was not detected above the LLD of 2.1 pCl/l in any of the samples. ! Strontium 90 activity was detected in 64 of the 66 samples collected and ranged l from 0.6 to 3.1 pCf/l. The annual average concentration cf strontium 90 was 1.02 l pCi/l at the indicator locations and 1.25 pCi/l at the control locations. The loca- l tion with the highest annual average concentration was indicator location T 199 ! with an average of 1.81 pCi/1. For all sample sites, the annual average concentra-tions were similar to those measured in the previous years (Fig 2 7). l l 2-42
- . - _ . - . _. . - . _-_ _ _ ~_ . _ _ - _ - o \ Davis 3csse Nuclear Power Station 1990 Annual Environmental Operating Report l A total of 66 analyses for iodine 131 in milk were performed during 1990. Iodine 131 was not detected in milk samples above the LLD of 0.5 pCi/l. The concentratiora of barium 140 and cesium 137 were below their respective LLDs in all samples collected. The results for potassium-40, a naturally occur-ring radionuclide, were similar at indicator and control locations (1229 and 1225 pCi/l, respectively). Since the chemistries of calcium and strontium, and potassium and cesium are similar, organisms tend to deposit cesium radioisotopes in muscle tissue, and strontium radicisotopes in bones. In order to detect the potential emironmental accumulation of these radionuclides, the ratio of the strontium radioisotopes radioactivity (pCi/l) to the concentration of calcium (g/l), and cesium radioisotpes radioactivity (pCi/l) to the concentration of potassium (g/l) were monitored in milk. Tnese ratios are compared to standard values to determine if build up is occurring. No statistically significant variations in the ratios were ob-served. The results of the analy,ses performed on the milk samples collected in 1990 indicate no effect due to the operation of Davis Besse. Groundwater Samples It is unlikely that groundwater will accumulate radioactivity from nuclear facili-ties, 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 ex-change medium for most radionuclides. However, tritium and other radiant'- clides such as ruthenium-106 have a potential to seep through the soil into the groundwater. Although Davis-Besse does not discharge its liquid effluents di-w 'ly to the ground, REMP personnel sample local wells on a quarterly basis to asure the detection of any adverse impact on the local groundwater supplies due to Station operation. The four wells sampled include two indicator locations (T 7, T 54), and two control locations (T 23 and T 27), in addition, a quality con-trol sample is collected at one of the four wells each quarter. The groundwater samples are analyzed for beta emitting radioactivity in dis-solved and susper.ded solids, tritium, strontium 89, strontium 90 and gamma emitting radionuclides. Beta emitting radionuclide concentrations in suspended solids were not detected above the LLD of 0.4 pCi/lin any samples, in dissolved solids, the concentra-tions averaged 3.1 pCi/l at indicator locations and 2.1 pCi/l at control locations. The location with the highest annual average was T 54, a control location. The concentration of beta emitting radionuclides at T 54 averaged 3.6 pCi/1. 2-13
j Annual Environmental Operating Roport 1990 Davis Besse Nuclear Power Station Tritium was not detected in any sample above the LLD of 330 pCV1. Also, Stron-tium 89 was not detected above the LLD of 1.6 pCi/1. Strontium 90 was detected at T 7. The average concentration of Strontium 90 was 0.6 pCi/l which is similar to concentrations observed in past years. Additionally, no gamma emitting radio-nuclides were detected in any of the samples collected. Wind and Domestic Meet Samples Sampling of meat, both domestic and wild, provides information on environmen-tal nuclide concentrations that humans may be exposed to through an ingestion pathway. The principle pathways for radionuclide contamination of meat animals include: atmospheric deposition from airborne releases on their food, contamination of their drinking water through atmospheric deposition, or contamination of their drinking water from radionuclides released in liquid effluents. Wild animals commonly consumed by residents in the vicinity of Davis Desse in-clude waterfowl, deer, and muskrat. The REMP generally collects wild meat samples and domestic meat samples (chickens) and eggs on an annual basa. Analyses from animals whose meat is eaten by humans provides general informa-tion on radionuclide concentratiore in the food chain. When evaluating the re-suits from analyses performed on meat animals, it is important to consider the age, diet, and relative mobility of the animal before drawing conclusions on ra-dionuclide concentrations in the local emironment or in the species as a whole. For instance, a meat sample taken from a deer killed by an automobile near Davis Besse might not provide as much information as a meat sample taken from a muskrat living in the Navarre Marsh, because the deer probably foraged in areas well beyond those that could be affected by Station operation. Both wild and domestic meat sample and eggs were sampled in 1990 as follows: e Wild Meat: One Canada goose was collected from on site One woodchuck was obtained on site Four muskrats were collected from the marsh on site 2-44
)
l l Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report e Domestic Meat: A Domestic Meat sample (chicken) was collected at one indicator (T 197) in July. The Domestic Meat sample at control site T 147 was unavailable. All meat samples were analyzed for gamma emitting radionuclides, e Eggs: Eggs were collected at T 197 in July. The sample was analyzed for gamma emitting radionuclides. In the edible meat samples, the mean potassium-40 concentration was 2.47 pCi/g wet sveight for the indicator locations. No edible meat sample was available dur-ing 1990 for the controllocation. This value is well within the range of the pre-operational and operational values. Potassium 40 is a naturally occurring radionuclide and is not produced by nuclear power stations. Cesium 137 was not detected in meat samples above the LLD of 0.025 pCi/g. In the ergs, the only detectable gamma emitting radionuclide was potassium 40 which was detected at a concene. cation of 0.97 pCi/g weight. This is similar to concentrations observed in previous years. l l Broad t.eet Vegetation and Fruit Samples l Fruits and broad leaf vegetation also represent a direct pathway to humans from ingestion. Fruits and broad leaf vegetation may become contaminated from at-mospheric deposition from air' arne sources (nuclear weapons fallout or gaseous releases from nuclear facilities) or from irrigation water drawn from lake wcter receiving liquid effluents (from hospitals, nuclear facilities, etc.) Also, radionu- , clides from the soil may be absorbed by the roots of the plants and become it.cor-porated into the edible portions. During the growing season (July through l September), broad leaved edible vegetation such as cabbage or lettuce, and fruits, are collected from farms in the vicinity of Davis Besse. l In 1990 broad leaf vegetation samples were collected at two indicator locations (T 8 and T 25) and one control location (T-37). Fruit samples were collected l 2-45 i
Annum Environmental Operating Report 1990 Davis Besse Nuclear Power Station from two indicator (T 8 and T 25) and three control (T 23, T 37, and T 173) loca-tions. Samples were collected once a month during the growing / harvest season, from July through September. All samples were analyzed for gamma emitting ra-dionuclides, strontium 89, strontium 90, and iodine 131. In all the samples, strontium 89 was not detected above the LLD of 0.028 pCUp wet weight. Strontium 90 was detected at one indicator site in a broad leaf vege-tation sample at a concentration of 0.007 pCUg wet weight. This is well within the normal range. Broad leaf vegetation (cabbage, squash leaves, Kohlrabi leaves, Swiss chard, let-tuce and horseradish leaves) and fruit (apples, pears, and grapes) collected during the growing season were analyzed for 1 131 by gamma spectral analysis. Broad leaf vegetation is an excellent source for accessing the deposition of radio-nuclides from atmosphere on the leaves. Iodine 131 was not detected above the LLD of 0.043 pCUg wet weight. No gamma emitting radionuclides, except naturally occuring potassium 40 were detected. In fruits, the average potassium 40 concentrations were 1.01 pCUg wet weight and 1.93 pCUg wet weight for indicator and control locations, respectively. In vegatation, the concentrations of potassium-40 were 4.35 pCUg wet weight for indicator locations and 1.53 pCilg wet weight for control locations. i Although the average concentration of potassium-40 at indicator locations was approximately twice that at controllucations in 1990, this radionuclide is not pro-duced by nuclear power stations, and, thus could not be attributable to the opera-tion of Davis Besse. The disparity between control and indicator potassium-40 averages may be due to the fact that different types of vegetation (e.g., cabbage versus squash leaves) were sampled at control and indicator locations, and differ-ent types of plants accumulate different concentrations of potassium 40. Animal / Wildlife Food Samples As with broad leaf vegetation and fruit samples, samples of domestic animal feed, as well as vegetation consumed by wildlife, provide an indication of air-borne radionuclides deposited in the vicinity of the Station. Analyses from ani-mal / wildlife feed samples also provide data for determining radionuclide concentrations in the food chain. Domestic animal feed samples are collected annually at both the milk and domestic meat sampling locations. Wildlife feed samples are collected from the Navarre Marsh onsite and from a local marsh within five miles of the Station. As in all terrestrial samples, naturally occurring potassium 40, cosmic ray produced radionuclides such as beryllium 7, and fallout ; radionuclides from nuclear weapons testing may be present in the feed samples. 2-46
Duvis Bosse Nuclear Power Station 1990 Annual Environmental Operating Report e Domestic Animal Feed: Domestic animal feed was collected at two indicator (T 8 and T 197) and one control (T 57) locations. The feed collected consisted of hay, silage, corn, and chicken feed. The samples were analyzed for gamma emitting radionuclides. e Wildlife Feed: , Wildlife feed was collected at 2 sites (T 31 and T 198 Toussaint Wild-life Area) and consisted of cattails, coontall, millets and smartweed. The samples were analyzed for gamma emitting radionuclides. In cattle feed, chicken feed, and wildlife feed, the only gamma emitting radionu-clides detected were beryllium 7 and potassium-40: both are naturally occurring radionuclides not produced at nuclear plants. Beryllium 7 was detected in two indicator locations at an average concentration of 0.50 pCi/g wet weight. The. an-nual average potassium 40 concentration for control location was 1.48 pCi/g wet weight compared to the average value of 5.39 pCi/g for the indicator locations. The type of plants collected for animal feed will influence the potassium 40 con-centrations found. For instance, hay samples collect more potassium than other i crops or wild feed. Also, crops that are fertilized possess more potassium be-cause it is readily available in fertilizer and therefore, more available for the plants to absorb it. l The normal range of berryllium 7 concentrations is 0.15 to 1.61 pC1/g wet weight. The normal range for potassium 40 is 1.17 to 14.4 pCilg wet weight. Thus, the concentrations of these radionuclides measured in 1990 were typical for the
- types of feed sampled. in addition to being analyzed for gamma emitting radio-j nuclides, all grass amples were analyzed for iodine 131; however, iodine 131 was not detected in any of these samples. No other radionuclides were detected.
l Soil Samples Soil samples are generally collected twice a year at all sites equipped with air samplers. Only the top layer of soil is sampled in an effort to identify possible trends in the local environmental nuclide concentrations caused by atmospheric deposition of fallout and Station released radionuclides. Generally, the sites se-lected are relatively undisturbed, so that the sample will be representative of the 2-47
Annual Environmental Operating Report 1990 Davis Besse Nuclear Pcwer S'ation actual deposition in the area. Ideally, there should be little or no vegetation present, because the vegetation rould affect the results of the analyses. Approxi. mately five pounds of soil are taken from the top two inches at each site. Many naturally occurring radionuclides (e.g., berryllium 7, potassium-40) and fallout radionuclides from nuclear weapons testing are usually detected. Fallout radio-nuclides which are often detected include strontium 90, cesium 137, cerium 141, cerium-144, and ruthenium 106. During 1990 soil was collected at 11 sites in June and October. The indicator 10-cations included T 1, T 2, T 3, T 4, T 7, and T 8. The control locations included: T 9, T 11, T 12, T 23, and T 27. The predominant activity was attributable to the presence of potassium-40 which had an average concentration of 11.93 pCi/g dry weight at the indicator locations and 15.59 pCi/g dry weight at control locations. Potassium 40 is part of the natu-ral emironment and is expected to be found in soil. The typical potassium 40 concentrations for the locations range from 9.70 pCl/g dry weight to 25.82 pCi/g dry weight. Cesium 137 is a man made radionuclide that is normally present in top few inches of soil as a result of fallout from nuclear weapons testing. Cesium 137 was detected at both indicator and control locations. The average concentration for the indicator locations was 0.40 pCi/g dry weight and 0.38 pCi/g dry weight at controllocations. The concentrations and distribution patterns were similar to those observed in previous years. No other radionuclides were detected above the respective ll.Ds. SOIL Cs-137 Concentration
, .cv. es 1.5 - -
- ,. ., ~
Figure 2 8: ne concentration of cesium 137 in soil has remained fairly constant over the years the REMP has conducted sampling. The peak observed in 1978 was due to fatlout from nuclear weap-ons testing. 2 48
1 l Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station l AQUATIC MONITORING Radionuelides may be present in Lake Erie from many sources including atm> spheric deposition. run off/ soil erosion, and releases of radioacthity in liquid ef-fluents from hospitals or nuclear facilities. These sources provide two forms of potential radiation exposure, external and internal. Enternal exposure can occur 1 from the surface of the water, shoreline sediments aM from the immersion (swimming) in the water. Internal exposure can occur from ingestion of radionu-clides, either directly from drinking water, or as a results of the transfer of radio-nuclides through aquatic food chain with eventual consumption of aquatic organism, such as fish. To monitor these pathways, Davis Besse samples treated ' surface water (drinking water), untreated surface water (lake or river water), fish !' and shoreline sediments. Trested Surtees 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 drinkin. ter. l Samples of treated surface water were collected from three indicator (T 28, l T 50, and T 144) and three control locations (T 11 T 12, and T 23). These loca-l tions include the water treatment facilities for Davis Besse, Erie Industrial park, ~ Port Clinton,'Ibledo and Put In Bay. Samples were collected weekly and com-posited monthly. The monthly composites were analyzed for beta emitting radio-activity. The samples were also composited into a quarterly sample and analyzed for strontium 89, strontium 90igamma emitting radionuclides and tritium. One QC sample was collected from a routine location which was changed each month.- In treated water samples, beta emitting radionuclides were detected at one site (T 11) in suspended solids at a concentration of 0.7 pCl/l. The average concentra. tion was similar in dissolved solids for indicator and control (2.2 and 2,1 pCi/1. re-spectively). The annual average beta emitting radionuclides was similar to concentration observed in previous years (Fig. 2 9). All tritium analysis results were less than the LLD of 330 pCi/1. All strontium 89 , and strontium 90 analysis results were less than their respective LLDs of 2.4 pCi/l and 1.0 pCi/l. Additionally, all cesium 137 results were less than the LLD of 10.0 pCi/1 These resuhs are similar to those of previous years and indicate no measurable effect resulting from the operation of Davis Besse. 2 49 4
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0- , , , ,,,, , , , , , , 72 73 74 75 76 77 78 79 60 01 82 63 84 e5 66 87 to 80 00 Year Figure 2 9: The awrage. concentration of beta emitting radionuclides in treated surface water samples collected during 1990 was similiar to concentrations detected in predous years. l-A quality control sample (T 143) was collected from a routine sample site each week and composited each month, and the location was varied on a monthly basis. The results of the analyses were consistent with the results obtained at the routine sampling locations. 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 im - mersion in the water. It also provides information on the radionuclides present . which may affect drinking water, fish and irrigated crops. Routine Program:. The routine program is the basic sampling program which is performed year-
. round. Untreated water samples are collected in the areas of the Station intake -
and discharge, and at the water intakes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo, Davis Besse, Eric L , L L 1 L 2 50
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v,, Annual Environmental Operating Report MOO Davis Bosso Nuclear Power Station ; Industrial Park, and Put In Bay Water Treatment Plants. A sample is also col-lected 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, tritiunt and gamma emitting radionuclides. The samples are further cornposited quarterly and analyzed for strontium 89 and strontium 90. A QC sample was colleleted weekly at a different location each month. Surnmer 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. l These samples are obtained in areas along the shoreline of Lake Erie and around the islands (see Figure 210). The samples are collected weekly and composited monthly. The monthly com-posites are analyzed for beta emitting radioactivity, tritium, strontlutn 89, stron-tium 90, and gamma emitting radionuclides.
- UNTREATED SURFACE WATER Gross Beta Analyses
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4 * ' ~ ~ ~ ~ i 11110llI11llll 7: 7s 74 rs to r7 7s to oc si at ss 64 sa se at es se so Year M inatestorueen M controi wean Figure 2 t0: Over the past 19 years, the annual average concentrations of beta emitting radionu-clides in untreated surface water samples couected from indicalor locations have been consistent w4th those concentraions in samples collected from controllocations. This shows that Davis Besse has had no measurable radiological impact on the surrounding surface water. l l- 2 51
l Annual Environmental Operating Report 1990 Davis Besse Nuclear Power StWon i 1 in untreated water samples, beta emitting radionuclides in suspended Solids were detected at an average concentration of 0.5 pCi/l for indicator and 0.4 pCi/l at control location. In dissolved solids, the average concentrations were 2.5 pCi/l and 2.3 pCi/l for indicator and control sites. 1 Of the 208 tritium analyses performed on untreated surface water,206 results were less than the LLD of 330 pCi/l. The concentrations in these two samples l with tritium results greater than LLD were 437 pCi/l and 768 pCi/1. It is sus-pected that these two samples may have been cross contaminated with non envi-ronmental sample when the sample was composited or analyzed at the i laboratory. No other samples collected at the same time from nearby locations showed elevated tritium results, and all other samle collected frorn T 134 and T-162 during 1990 showed tritium results less than the LLD. I Cesium 137 and strontium 89 were not detected in samples of untreated water above their LLDs of 10 pCi/l and 2.3 pCi/1, respectively. Strontium 90 was de-tected at both indicator and control and an average concentration of 0.7 pCi/l and 0.8 pCi/1, respectively. These concentrations are similar to concentrations observed in previous years. Each month, weekly quality control samples were collected at different locations. The results of the analyses from the quality control samples were consistent with those from the routine samples. Some of the samples collected during the sum- , mer months in Lake Erie were close to the collection points of some of the rou-tine untreated surface water samples. Thus, they served as quality control samples and helped to verify the accuracy of the measurements performed. A comparison of their results from the routine sites and nearby summer collection sites illustrates the value of using quality controlsamples to check the accuracy of analyses performed by the laboratory. The average concentrations of beta emitting radionuclides for these samples are provided below: T 12 - 2.62 pCi/l vs. T 138 2.44 pCi/l T 3 3.00 pCi/l vs. T 130 2.62 pCi/l T 11 2.30 pCi/l vs. T 164 2.60 pCi/l T 23 1.92 pCi/l vs. T 168 2.25 pCi/l T 28 2.22 pCi/l vs. T 131 2.60 pCi/l 2 52
Annual Environmental operating P.eport 1990 Devis Besse Nuclear Power Station Fish Samples Fish are analyzed primarily to quantify the dietary radionuclide intake by hu-mans, and secondarily to serve as indicators of radioactivity in the aquatic ecosys-tem. The principal nuclides which may be detected in fish include naturally occurring potasrium-40, as well as cesium 137 and strontium 90. Depending upon the feeding habit of the species (e.g., bottom feeder versus predator), re-suits from sampic analyses may vary. With the aid of a local commercial fisherman, Davis Besse routinely collects three species of fish (walleye, white bass and carp) twice a year from sampling lo-cations 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 bass because they are an important commercial fish. Carp are col-lected because they are botton1f eeders and thus would be more likely to be af-fected by radionuclides deposited in lake sediments. Only one carp sample could be obtained at T 33 during 1990. The edible portions of fish were analyzed for beta and gamma emitting radionuclides. Fish Samples l Indicator vs. Control Mean Gross Beta j , cc /o aet l111nllld___h 77 70 70 80 81 82 83 84 85 80 of 88 80 00 su E L no cator EM comro Figure 211: Average concentrations of beta emitting radionuclides in fish samples were similiar at indicator and control locations and were within the range of results from previous years. 1 2 53
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Fig.211 shows that the average concentration of beta emitting radionuclides in fish muscle was similar for indicator and controllocations (3.04 and 2.98 pei/g wet weight,respectively). The predominant gamma emitting radionuclide de-tected was the naturally occurring potassium-40. The average concentration at the indicator location was 2.77 pCilg wet weight and 2.80 pCi/g wet weight for controllocations. Cesium 137 was detected in one indicator location (T 33, wall-cye sample), at a concentration of 0.13 pCi/g wet weight. All the sample analysis results were within normal ranges compared to previous years. Shoreline Sodiments The sampling of shoreline sediments can provide an indication of the accumula-tion of undissolved radionuclides which may lead to internal exposure to humans through the ingestion of fish, through respension into drinking water supplies, or as an external radiation source from shoreline exposure to fisherman and swim-mers. Samples of deposited sediments in water were collected in May and October from two indicator locations (T 3 and T-4) and two control locations (T 23 and T 27). The samples were analyzed for gamma emitting radionuclides. Naturally occurring potassium-40 averaged 12.8 and 11.6 pCi/g dry weight at indi-cator and controllocations. Cesium 137 was detected at one controllocation T 23 at a concentration of 0.49 pCi/g dry weight. Atmospheric testing of nuclear weapons has been the principal source of cesium. 137 in the emironment to da:e. Although no atmospheric nuclear weapons tests have been reported since 1980, cesium 137 is still present in shoreline sediment samples because of its long half (approximately 30 years). No other gamma emit-ting radionuclides wen ictected in any of the samples, and the concentrations of those detected were consistent with normal concentrations for this area. DIRECT RADIATION MONITORING Populations may be exposed to extremely small amounts of external radiation from nuclear facilities by several pathways, including airborne radioactivity or ra-dionuclide deposition in soil, vegetation or lake bottom sediments. Some radia-tion will always be present from background sources, both man made and natural. The amount of normal background radiation can be determined by 2 54
;- Annual Environmental Operating Fleport Davis Besse Nuclear Power Station 1990 I
examining preoperational measurements or data collected at control locations. Dasis-Besse measures direct radiation at 95 locations. These lccations include indicator and controllocations. Additionally, there are 20 duplicate or QC sites. Thermoluminescent Dostmeters Radiation at and around Davis Besse is constantly monitored by a network of thermoluminescent dosimeters (TLDs). TLDs are small devices which store adiation dose information. The TLDs used at Davis Besse contain a calcium sul-fats: dysprosium (CaSO.t: Dy) card with four main readout areas. Multiple reados:' areas are used to ensure the precision of the measurements. i Thermoluminescence is a process by which ionizing radiation interacts with the sensitive materialin the TLD the phosphor. Energy is trapped in the TLD mate-rial 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 amount of energy that was stored in the TLD as a result of interaction with radiation is re. l moved and measured by a controlled heating process in a calibrated reading sys-tem. As the TLD is heated, the phosphor releases the stored energy as light. l The amount of light detected is directly proportional to the amount of radiation to which the TI.D was exposed. The reading process rezeros the TLD and pre-L - pares it for reuse, i TLD Collection Davis Besse has 95 TLD locations (71 indicator and 24 contrci) which are col-lected and replaced on a quarterly and annual basis. Twenty QC TLDs are also I collected on a quarterly and annual basis or at any given time. There are a total COMPARISON OF TLD DOSES CONTROL vs INDICATOR
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YEAR M inosc. aron W CONih0L Figure 2.t2: The similiarity of the indicator and control results demonstrate that the operation of I Davis.Besse has not caused any abnormal gamma dose. 2 55 ,
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station of 230 TLDs in the environment surrounding Davis Besse. By collecting TLDs on a quarterly and annual basis from a single site, the two measurements serve as a quality control check on each other. In 1990, the annual average value for all indicator locations was 15.1 mR/91 days, and for all control locations was 16.2 mR/91 days. The annual average value for all TLDs in 1990 was 15.4 mrem /91 days. This average value is slightly lower than 1989 and within normal range of the previous years as shown below: 1972 22.4 mrem 91 days 1981 14.8 mrem 91 days 1973 14.3 mrem 91 days 1982 14.5 mrem 91 days 1974 11.7 mrem 91 days 1983 13.2 mrem 91 days 1975 12.8 mrem 91 days 1954 13.2 mrem 91 days 1976 15.6 mrem 91 days 1985 14.4 mrem 91 dap 1977 16.5 miem91 days 1986 14.8 miem91 days 1978 16.7 mrem 91 days 1987 14.5 mrem 91 days 1979 13.4 mrem /91 days 1988 14.5 mrem 91 days 1980 14.5 mrem /91 days 1989 15.9 mrerrv91 days 1990 15.4 mremSt days Quanty ControlTLDs Duplicate TLDs have been established at 17 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 same 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 at the rou-tine TLDs averaged 14.3 miem whi!e the quality control TLDs yielded ar. aver-age dose of 15.3 mrem. All the quality control and routine sample results were similar, demonstrating the accuracy of both the TLDs and the laboratory's mea-surements. NRC TLD Monitoring The NRC has 22 TLDs located around Davis Besse as part of their Direct Moni-toring Network Program. Davis Besse maintains TLDs at all the NRC TLD mon-itoring 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 prosid-ing a quality control check on both laboratories. 2 56
. . i Annual Environmental Operating Report 1990 Davis Besso Nuclear Power Station The NRC uses the Panasonic Model UD801 TLD, which has two elements oflith-ium borate: copper (Li:B407: Cu) and two elements of calcium sulfate: thulium (CaSO4: Tm).The difference in TLD material used by the NRC and Davis Besse causes some variation in results.
The results of TLD monitoring at these 22 locations show good consistency for the NRC TLDs and the Davis Besse TLDs. The average of the quarterly results are 16.4 mrem /91 days for the Davis Besse TLDs and 16.5 mrem /91 days for the NRC TLDs (data from first and third quarters only). The variance in these mea-surements is most likely due to the differences in the TLD rnaterials. _D CON 3ARISO\ NRC vs Davis-Besse mrem /91 days MH 1987 1988 M DD Year U NRC 1989 1990 Figure 213 compares NRC and Davis Besse's TLDs for the last four years. 2 57 I
l Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station ; CONCLUSION The Radiological Emironmental Monitoring Program at Davis Besse is con-ducted to determine the radiologicalimpact the Station's operation on the envi- l ronment. Radionuclide concentrations measured at controllocations,in previous operational studies and in the preoperational surveillance program. These comparisons indicate normal concentrations of radioactivity in all en-vironmetnat samples collected in 1990. No adverse effects attributable to the op-eration of Davis Besse were detected in any of the sampling media collected and analyzed during 1990. In fact, the dose to local residents from exposure to nor-mal sources of radiation, both natural and man made, is much more significant than the dose associated with the operation of Davis Besse. The results of the sample analyses performed during the period of January t through December 1990 are summarized in Appendix E of this report. i i 1 l l 2 58 I
Annual Environmental Operating Report 1990 Davis 86sse Nuclear Power Station 2 References 1." Cesium 137 from the Emironment to Man: Metabolism and Dose," Report No. 52, National Council on Radiation Protection and Measurements, Washing-ton, DC (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 Measurements, Washington, DC (December 1976). 4." Exposure of the Population in the United States and Canada from Natural Background Radiation," Report No._94, National Council on Radiation Protec-tion cnd Measurements, Washington, DC (December 1987), 5."A Guide for Emironmental Radiological Surveillance at U.S. Department of Energy Installations," DOE /EP-0023, Department of Energy. Washington, DC '
'(July 1981).
6."lonizing Radiation Exposure of the Population of the United States." Report . No. 93, National Council on Radiation Protection and Measurements, Washing-ton, DC (September 1987).
- 7. Kirk, TJ, and G.N. Midkiff, Health Physics Fundamentals. General Physics Corporation (1980).
1 "8." Natural Background Radiation in the United States," Report No. 45, National Council on Radiation Pro:nction and Measurements, Washington, DC (Novem-ber 19_75). 9." Numerical Guides for Design Objectives and Limiting Conditions for Opera-tion to meet the Criterion 'As Low As Reasonably Achievable' for Radioactive 4 Materialin Light Water Cooled Nuclear Power Reactor Effluents." Code of Fed. > eral Regulations, Title 10 Energy, Part 50 " Domestic Licensing of Production and Utilization Facilities," Appendix I (1988). 2 59
Annual ErMronmental Operating Report 1990 Davis Ber4e Nuclear Power Station 10. Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," American National Standards Institute, Inc., ANSI N545 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 Measure-ments, Washington, DC (December 1987). 12."Radic, logical Assessment: Predicting the Transport, Bioaccumulation, and Uptake by Man of Radionuclides Released to the Environment," Report No. 76, National Council on Radiation Protection and Measurements, Washington, DC (March 1984).
- 13. Regulatory Guide 4.1," Programs for Monitoring Radioactivity in the Erwi-rons of Nuclear Power Plants," US NRC (April 1975).
- 14. Regulatory Guide 4.13, " Performance, Testing, and Procedural Specifications for Thermoluminescent Dosimetry: Erwironmental Applications." US NRC (July 1977),
15 Regulatory Guide 4.15," Quality Assurance for Radiological Monitoring Pro-grams (Normal Operations) Effluent Streams and the Environment," US NRC (February 1979).
- 16. Regulatory Guide 0475," Radiological Emironmental Monitoring by NRC Li-censees for Routine Operations of Nuclear Facilities," US NRC (September 1978).
- 17. Regulatory Guide 0837 "NRCTLD Direct Radiation Monitoring Network,"
US NRC (1988), t 18." Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, Part 20 (1988), 19.Teledyne Isotopes hildwest Laboratory," Operational Radiological Monitor-ing for the Davis Besse Nuclear Power Station Unit No.1, Oak Harbor, OH," An-nual Report, Parts I and II (1977 through 1990). 20.Teledyne Isotopes Midwest Laboratory,"Preoperational Environmental Ra-diological Monitoring for the Davis Besse Nuc! car Power Station Unit No.1 Oak Hvbor, OH (1972 through 1977). 2 60
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station i
- 21. Toledo Edison Company," Davis Besse: Nuclear Energy for Northem Ohio." j
- 22. , Davis Besse Nuclear Power Station, Unit No.1, Radiological Efauent l Technical Specifications," Volume 1, Appendix A to License No. NPF 3.
l 23, , Final Em'ironmental Statement Related to the Construction of Davis Besse .4uclear Power Station," Docket #50 346 (1973). 1 24, "
, Performance Specifications for Radiological Emironmental Monitor-ing Program," S 720, Revision 2 (1988),
- 25. , Radiological Environmental hionitoring Program," DB HP 00015, Re. I vision 0, (1990),
{ l
- 26. , Radiological Monitoring Quarterly, Semiannual, and Annual Sam-pling," DB.HP 03004, Revision 0, (1990),
- 27. . " Radiological Monitoring Weekly. Semimonthly, and hionthly Sam- .
pling," DB HP 03005, Revision 0, (1990), !
- 28. , REMP Enhancement Sampling," DB HP 10101. Revision 0,(1990), ;
- 29. , Semiannual Effluent and Waste Disposal Report," January 1 June 30 (1978 through 1990).
l 30, , Semiannual Efauent and Waste Disposal Report," July 1 December 31 (1977 through 1990).
- 31. , Updated Safety Analysis for the Offsite Radiological hionitoring Pro-gram," USAR 11.6, Revision 9, (1989).
32._ , Annual Radiological Emironmental Operating Report Preparation and Submittal," DB HP-00014, Revision 0,(1990). 33l Tritium in the Emironment," Report No. 62, National Council on Radiation Protection and Measurements, Washington, DC (March 1979). 2-61
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s Davis Besse Nuclear Power Station Ifric Annual Environmental Operating Report I Land Use Census c Program Design Each year a Land Use Census is conducted by Davis Besse in order to gather in-formation necessary to sample media representative of conservative radioactivity exposure pathways in the environment. The Land Use Census is required by Title 10 of the Code of Federal Regulations, Part 50, Appendix 1, and the Davis-Besse Technical Specifications, Section 3/4.12.2. Radiological exposure path-ways, as discussed in Chapter 1 of this report, indicate the methods by which people may become exposed to radioactivity. The Land Use Census identifies the various pathways by which radioactivity may reach the population around Davis Desse. These pathways include: e Inhalation Pathway Internal exposure as a result of breathing radioactivity carried in the air. e Ground Exposure Pathway. External exposure from radioactivity deposited on the ground, e Plume Exposure Pathway- External exposure directly from a plume or cloud of radioactive rnaterial. e Ytgetation Pathway. Internal exposure as a result of eating vegetables, fruit, etc. which have a build up of deposited radioactivity or which have absorbed radionuclides through the soil. i e Milk Pathway Internal exposure as a result of drinking milk which may contain radioactivity as a result of a cow or goat grazing on a pasture contaminated by radionuclides. The information gathered during the Land Use Census for dose assessment and input into the Radiological Environmental Monitoring Program ensures that these programs are as current as possible, For instance,if the Land Use Census iden.ifies the presence of a dairy animal closer to the Station than was previously t i L____ ___ -..
Annual Environmental Operating Report 1990 Davis Bessa Nuclear Power Station identified, then information from this new location can be used to estimate the potential dose to the surrounding population. Also, the milk at this location can be sought as a new sample for the Radiological Emironmental Monitoring Pro-gram. 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 1990 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.1-lowever, only the residences. vegetable gardens (greater than 500 square feet), and milk animals are used in the dose assessment program. The Ottawa County Cooperative Extension Agency confirmed the presence of dairy cattle and goats reported within the five mile radius. Each residence is tabulated as having an inhalation pathway, as well as ground anc plume exposure pathways. Each garden is tabulated as a vegetation pathway. Each milk animal is tabulated as a milk pathway. All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 minute series of the relevant quadrangles) which has been divided into 16 equal sectors corresponding to the 16 cardinal compass points (Figure 3-1). The closest residence, milk animal, and vegetable garden in each sector are determined by measuring the distance from each to the station vem at Davis-Besse. Results The following changes in the pathways were recorded in the 1990 census: e SSE Sector - A milk goat deleted at 3467 meter. The residence and vegetation pathways at 2030 and 2830 meters were changed to 2010 and 2900 meters. These changes were due to an increased accuracy in measurement. 32
Davis Bes4e Nudoar Power Station 1990 Annual Environmental Operating Report e S Sector The vegetation pathway at 2560 meters was deleted in favor of a closer garden at 1450 meters. The residence at 1090 meters is changed to 1070 meters. The actuallocation of residence is the same as 1989 census. e SSW Sector The residence and garden located at 960 and 980 meters changed to 980 and 2180 meters. The residence was changed due to measurement improvement and the garden at 980 meters was not present in 1990. e SW Sector-A garden at 1340 meters was added. The garden at 1220 meters was not present in 1990, e WSW Sector.The residence, garden and milk cow changed to 1620,2640, and 4270 meters. The changes are due to improvement in measuring accuracy. The actual grour.d locations remained the same, e W Sector - The garden at 1050 meters was added because the garden at 980 meters was not present in 1990. e WNW Sector - The residence and vegetation pathway at 1310 and 2900 meters. r-spectively, were changed to 1730 and 3290 meters, respse.tvely.
- NW Sector -The residence and vegetation pathway at 1730 and 2290 meters, respectively, were changed to 1980 and 2040 meters, respectively.
e NNW Sector The residence and vegetation pathway at 1250 and 1490 meters were deleted in favor of a closer location at 1210 meters, e Critical Pathway - The critical pathway for 1989 was west sector 9 980 meters for child / vegetation. The critical pathway for 1990 changed to WSW at 4270 meters for infant / milk pathway. The detailed pathway list in Table 3-1 was used to update the database of the ef-fluent dispersion model used in dose calculations. Tab!e 31 is e ided by sectors and lists the distance (in meters) of the closest pathway in each meteorological sector. 3-3 1
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station There were a number of changes in the 1990 Annual Land Use Census. The ma-jority of these changes were due to improvements in measuring the distance from the station vent. The actual ground location in these sectors were the same as last year only the distance measureci changed (see Table 3-1). Table 3 2 provided information on the pathways, critic- age group, atmospheric dispersion (X/Q) and deposition (D/0) parameters for each sector. This infor-mation is used to update the Offsite Dose Calciclation Manual (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous ef0uents, and in calculat-ing liquid and gaseous ef0uent monitoring instrumentation alarm / trip setpoints, i 3-4
DAVIS-BESSE NUCLEAR POWER STATION LAND USE CENSUS 1990 PRIMARY. PATHWAYS WITHIN 5 MILE RADIUS
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i i Annual Environmental Operating Report 1990 Davis 86sse Nuclear Power Stat lon ! l
. Table 3-1: Closest Exposure Pathways Present in 1990 l l
1
- Sector Distance from Station Closest l (meters) Pathways 1 1
*N &% Inhalation I Ground Exposure Plume Exposure 1
1 NNE 870 inhalation Ground Exposur: Plume Exposure NE 900 Inhalation Ground Exposure Plume Exposure l ENE, E. ESE, SE N/A Located over Lake Erie
?SSE 2010 Inhalation .
Ground Exposure ) Plume Exposure l
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Ground Exposure _
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-1
*S 1070 Inhalation. I Ground Exposure l Plume Exposure l
*S 1450 Inhalation Ground Exposure ,
Plume Exposure ! Vegetation 1 1 1
- Changes stoce 1989, 1
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3-6 1 1
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report Table 31: Closest Exposure Pathways Present in 1990 (continued) Sector Distance from Station Closest (meters) Pathways
*SSW 980 inhalation Ground Exposure Plume Exposure
*SSW 2180 inhalation Ground Exposure Plume Exposure Vegetation SW 1050 inhalation Ground Exposure Plume Exposure
*SW 1340 Inhalation Ground Exposure Plume Exposure Vegetation
*WSW 1620 inhalation Ground Exposure Plume Exposure
*WSW 2M0 inhalation Ground Exposure Plume Exposure
%getation
*WSW 4270 Ithalation Ground Exposure Plume Exposure Vegetation Cow Milk W 980 inhalation Ground Exposure Plume Exposure
' Changes since 1989.
3-7
_ . _ , . . . . . . , _ . _ _ . ~ . . . . . _ _ . - . Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Table 3-1: Closest Exposure Psthways Present In 1990 (continued) Sector Distance from Station Closest (meters) Pathways
'W 1050 inhalation Ground Exposure Plume Exposure Vegetation
'WMV 1730 inhalation Ground Exposure Plume Exposure
*WNW 3290 inhalation i
, Ground Exposure Plume Exposure Vegetation
*NW : 1980 inhalation
- Ground Exposure Plume Exposure l *NW 2040 inhalation l Ground Exposure Plume Exposure
. Vegetation -
*NNW 1210- Inhalation Ground Exposure Plume Exposure Vegetation
- Changes since 1989, 38
. . . - . - .. .- . - .- - - . ~ . - . - . - _ . - _ . - . - -
n. Davis Bene Nuclear Power Sta3c1 1990 Annual Environmental Operating Report hble 3 - 2: Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters SECTOR METERS CRITICAL AGE X/Q PATHWAY GROUP (uc/mh D/g' (m ) N'" 880 inhalation child 9.15E-07 8.40E-09 NNE 870 inhalation child 1.27E-06 1.47E 08 NE 900 inhalation child 1.26E-06 1.58E 08 ENE' --- --- --- --- --- E' --- -- --- --- --- ESE' --- -- --- -- --- SE* --- -- --- --- --- t SSE"
- 2900 vegetation child 6.80E-08 7.90E 10 ,
S" 1450 vegetation child 1.21E-07 2.46E 09 ; SSW" - 2180 vegetation child 6.45E 08 1.19E-09 j SW"' . 1340 vegetation child 2.10E-07 3.94E 09 WSW'" 4270- cow / milk infant 5.71E-08 5.31E 10 W" 1050 . vegetation child 5.72E-07 8.87E 09
'WNW" 3290 vegetation child 6.28E-08 5.18E 10 i
NW" 2(M0' vegetation child 8.25E-08 7.28E 10
'NNW" 1210' vegetation child 2.70E-07 1.92E 09
- Since these sectors are located over marsh areas and Lake Erie, no ingestion pathways are present.
" Changes since 1989. j
'" Changes in measurement but not actual ground location. ;
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Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station I MeteorologicalMonitoring i introduction 1 The Meteorological Monitoring Program at Davis Besse is required by the Nu-clear Regulatory Commission (NRC) as part of the program for evaluating the ef. fects of routine operation of nuclear power stations on the surrounding environment. Both NRC regulations and Davis Besse Technical Speci6 cations provide guidelines for the Meteorological Monitoring Program. These guide-lines ensure that Davis Besse has the proper equipment,in good working order, to support the Radiological Emironmental Monitoring Program. Meteorological observations at Davis Besse began in October 1968.The Meteo- l rological Monitoring Program at Davis Besse has provided data, with very little I data loss, since the Station began operation in 1977. - This has provided an exten-sive record of meteorologicalinformation that can be used by many programs at Davis Besse. The Radiological Environmental Monitoring Program uses the me- I teorological data to evaluate the effects of radioactidty released in Station efflu- ) ents. The meteorological conditions at the time of these releases are used to calculate doses to the general public. Meteorological data are also used to evalu-ate where new radiological environmental monitoring sites should be located. The meteorological monitoring system is also valuable in toonitoring weather conditions and predicting the development of adverse weather trends, such as flood'ag or high winds. This provides an early warning system. so precaununs can be taken to protect the facilities and personnel at Davis Besse, as well as local residents. Onsite meteorological data would also be a valuable tool in the unlikely event of an emergency at Davis Besse. Atmospheric dispersion charac-teristics necessary for evaluating conditions, distribution, and doses to the public could be readily obtained. 41
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station Onsite Meteorological Monitoring This section describes the onsite Meteorological Monitoring Program at Dasis. Besse. A description of the meteorological system at Davis Besse, and data han-dling and analysis procedures, as well as a table and discussion of the annual data recovery are also provided.
System Description
Meteorological data collection at Davis Besse consists of wind speed, wind direc-tion, sigma theta (standard deviation of wind direction), ambient (outside air at 10 m) temperature, dinerential temperature (air temperature at 100 or 75 m minus air temperature 10 m), dew point temperature (the air temperature where inoisture begins to condense out of the air, and precipitation. Two towers equipped with a variety of meteorological instruments are used to gather this data. , Meteorologicat instrumentation The meteorological system consists of one monitoring site located at a grade level of 577 feet above mean sea level. A 340 ft (100 m) free standing tower to-cated about 3000 feet SSW of the cooling tower, and an auxiliary 35 ft (10m) foot tower located 100 feet west of the 340 ft tower, are used to gather the meteo-rological data. The 340 ft tower is instrumented for wind speed and wind direc-tion at 340 ft (100 m) and 250 ft (75 m). The 35 ft (10 meter) tower is instrumented for wind speed and wind direction. The 350 ft tower also measures two dinerential temperatures (delta T's) : 340-35 ft and 25435 ft (100-10 m and
. 75 10 m, respectively). Differential temperatures are used to determine stability of the lower atmosphere. This gives an indication of how fast airborne effluents can mix and disperse. Precipitation is measured by.a tipping bucket rain gauge located near the base of the 35 ft (10 m) tower. According to the Davis Besse Nuclear Power Station, Operating License, Appendix A, Technical Specifica-tions, 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.
The signals from each meteorologicalinstrument are translated by modules lo-cated inside the meteorological shelter.These signals are then transmitted to var-ious places (refer to Figure 4 2): to an ADAC System-1000 computer (PDP 11/03) located in the meteorological shelter, to a computer in the Control Room.
- and to four Esterline Angus strip chart recorders located in the meteorological shelter which are used if the PDP 11/03 and Control Room data are not avail-able. The PDP 11/03 also communicates data to a PDP 11/34 computer located 42
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Annual Environrnental Operating Report 1990 Davis Besso Nuck.tr Power Station Additional data losses during the year were as follows: o January: Ice stom freezes 340 foot (100 meter) 250 foot l (75 meter sensors temporary sensor failure). High winds break 35 foot (10m ) windspeed sensor. e February: Ice storm freezes all sensors temporarily, e August: Lightning strike, temporary computer failure. ; 1 1 METEOROLOGICAL SYSTEM RECOVERY STATISTICS PERCENT
/
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65 l, , , l JAN FEB MkR APR MkY JbNJUL AbGShP ObiNbV DhC MONTH M icu ws CG icu wo O 75u ws s nu wo ( E tcua iou O rrup tsu 1 Fig. 4-4: Davis- Besse Technical Specification requires six sensors to be to be op-etable on site during plant operation. Data loss from these six sensors were mini-mal resulting in a data recovery of greater than 90% for 1990. See table 41. Meteorological Data Summaries This section presents summaries of the meteorological data collected from the onsite monitoring program at Davis-Besse during 1990. Tables 4-2 through 4-7, discused in this section, can be found on pages 4-27 through 4-34. Table 4 2 sum-46
h --. Annual Environmental'Operat!ng bport 1990 Davis Besse Nuclear Power Station In the area surrounding Davis Besse, the lake breezes are deflected clockwise 12 degrees each hour until about midnight. As the land cools, a land breeze from late evening to mid morning develops, resulting in winds from the SSW and WSW. In general,laktdland breezes occur at Davis Besse from April through September, with a peak in May. Otrrent and reliable information on local weather patterns (such as the lake / land breeze effe et) and global weather patterns is crucial for Davit-Besse persomiel responsible for monitoring atmospheric disparsion characteristics in the unlikely event of a radiological emergency at the Station. Wind Sper,i rind V&nd Dir2ction The maximum hourly average wind speeds for 1990 were 54.49 mph for the 100m level >on January 25,30.6 mph for the 75m level on January 25, and 37.14 mph for the 10tn level on January 25. Figure 4-5 gives an annual and monthly wind rose of average wind speed and per-cent frequency by direction mezsured at the 100 m level in 1990. Wind roses get their name because the circular pattern of each graph resembles a flowering rose. Each wind sector has ruo radial bars, the darker bar represents the percent of t,ime the wind blew from that direction.Tu hatched bar represents the aver-age speed of the wind from that direction. Wind direction sectors are classified usiny, Pasquill Stabilities (Tah?e 4-3, page 4-31). Calms (less than or equal to 1.0 mph) are shown in percent in the middle of the wind rose.The 75 m wind rose is given in Figure 4-6 :and the 10 m wind rose in Figure 4-7. Ambient Ternperature Monthly minimum and maximum temperatures for 1990 are given in Table 4-2. These data are mgasured0 at the 10m level. The maximum monthly average tem-perature was 72.3 F(22.4 C) for July.The extreme maximum was 97.90 F(36.6 C) 0 on July 4, and the extreme minimum was 4.43 F(-15.4 C) on December 24. Osnr L41ru Temperature Menthly average and extreme dew point te'mperatures for 1990 are also provided
-in Thble 4-2. These data are measured althe 10m level. The maximum daily c average dew point temperature was 63.0T(17.2 C) for August. The extreme 0
maximum was 75.5 F(24.2 C) on August 27, and the extreme minimum was - 0 6.7 F(-21.5 C )cn Februrary 25. k i l 4-7
Fig. 4-4: 100 Meter hd Rose for January through December 1990. N -N -
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- Fig. 4-4 (continued): 100 Meter Wind Nsc for January through Decernber 19T.
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Annual Environmental Operating Report 1990 DQvis-Bene Nucisar Per,vor Station I _ l Precipantion 1 Monthly totals and extremes of precipitation at Davis Besse for 1990 are given in Table 4-2. Total precipitation for the year was 36.76 inches (93.37 cm). The maxi- _Y-mum monthly precipitation total was 5.50 inches (13.97 cm) in December, it is e-likely that precipitation totals recorded in colder months are somewhat less than _i the actual amounts received at the site due to periods of freezing precipitation 4 coupled with strong winds. 1 Atmospherie Stability g, __r 4-The atmospheric stability is categorized by delta T (100m 10m) and delta T [ J-(75m - 10m) using the information provided in Table 4 3 (pege 4 18). Unstable conditions (classes A C) mix and disperse effluents better than stable conditions # (classes E-G). Table 4-4 (page 4-19) gives the monthly and annual stability class % frequency distributions for 1990, based on delta T (100m 10m). The table i shows that neutral and slightly stable conditions (classes D and E) were the most _- ~ common during the year, ;- For comparison purposes, the delta T (75m - 10m) tability class frequency distri- - bution is given in Table 4-5 (page 4 20). The delta T (75m 10m) shows an in-crease of extreme classes (A and G), and a decrease of neutral class D relative to -; the delta T (100m 10m) distribution. This was expected due to the small height i separation. , i
) =
Tables 4-6 and 4-7 (pages 4 21 and 4 22, respectively) give the distributions of e bility classes by hour of day for delta T (100m - 10m) and delta T (75m 10m), re- I m spectively, for 1990. They show, as expected, that unstable classes occurred primarily during the daytime hours and stable classes generally occurred at night. j The neutral class occurred throughout the day and night, but showed a peak fre- - quency for morning and afternoon transition periods. Local Wind Patterns ( Y Heating and cooling cycles that develop from solar heating of the atmosphere can create a variety of localized wind systems. One example common in areas O bordering the Great Lakes is sometimes referred to as the " lake / land breeze ef- - fect." Unfortunately, this term is also used in other parts of the country to de-scribe localized wind systems not at all related to tne wind patterns in the Lake g Erie area. For purposes of this report, the term " lake / land breeze effect" will be E used to describe the harmless wind patterns that occur over areas adjacent to Lake Erie, including the Davis Besse site.These wind patterns arise because of f i 4 20 1 I
=
' i .. -.iii..........,_
Annual ErMronrnental Operating Report 1990 Davis.Besse Nuclear Power Station the different thermal characteristics of land and water, a difference that is magni-fled when the body of water has a large surface area, such as Lake Erie. The large surface area of Lake Erie causes the temperature of the air over the water to be quite different from the air temperattve over the land. This difference in temperature is not seen over smaller bodies of water such as man made reser-voirs. Lake Erie acts as a giant " heat sink"; i.e., it takes a long time for water tem-peratures to rise in the spring, but once the lake has warmed, it also takes a long time to cool back down in the autumn. In contrast, landforms experience signifi-cant temperature changes over short periods of time. In the case of the lake / land breeze effect along the Lake Erie shoreline, during the daytime, 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 ris-ing 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 "laks breeze effect (Figure 4-7). At night time, this process is reversed, ne water retains its heat as the land cools rapidly. This results in warmer, less dense air over the lake, with colder air over the land. This causes the local winds to shift from the land to the water, creating a " land breeze" effect (Figure 4-8). The lake / land breeze circulation at Davis Besse ts generally not present during the late fall, winter, early spring, or when skies are cloudy. At these times, there is no significant solar heating of the land. The lake / land breeze is also not pres-ent when the difference between the lake temperature and land temperature is too small, or when wind speeds become faster than 12 mph (19.2 km/L ). Such wind speeds tend to minimize the effect of local wind circulation patterns and allow large scale weather features (e.g., fronts, lows, highs, etc.) to dominate. If conditions are such that a lake breeze develops in the area around Davis-Besse, the winds usually start out from the SSW and the WSW during midmorn-ing. As the land becomes warmer during the day, the lake breeze develops and the wind shifts to the NNE and NE. Once the lake breeze develops, the Coriolis Force begins to act on the wind direction. He Coriolis Force develops due to the earth's rotation. When any mass travels above the earth's surface in an appar-ently linear path (as viewed from its point of origin), its path is actually deflected to the right or left, depending upon the object's position relative to the equator. His deflection is easily observed from the earth's surface at some point in the initial trajectory of the mass. However, when viewed from some fixed point in outer space, or from the initial point of origin, the mass appears to travel a straight path. The deflection seen by earthbound observers arises from the fact 4 21
Annual Errvitcomental Operating Report 1 goo Davis Besse NudestPower Station 1 Late creeze Cumulus cloucs covelop and migrate lakewera A I F A A v gng ? . 50uncery of Inf f ew (wem, d@
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- A R R NT Figure 4-7: During the daytime, warmer air over the land rises faster than the !
detae cool air over Lake Erie. The resulting " lake breeze " draws cool air from . the lake towards the land.
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- Annual Environmental Operating Report 1990- Davis Besse Nuclear Power Station that their frame of reference changes as the mass travels along its path due to the earth's rotation beneath the mass, In essence, the earth actually " moves out" from under the traveling mass, in the Northern Hemisphere, objects (or air masses)
- are denected to the right of their path of motion;in the Southern Hemisphere, they are de0eced to the left.
In the area surrounding Davis Besse, the lake breezes are denected clockwise 12 degrees each hour imtil about midnight. As the land cools, a land breeze from late evening to mid morning develops, resulting in wmds from the SSW and WSW. In general, lake / land breezes occur at Davis Besse from April through September, with a peak in May. Current and reliable information on local weather patterns (such as the lake / land breeze effect) and global weather patterns is crucial for Davis Besse personnel responsible for monitoring atmospheric dispersion characteristics in the unlikely event of a radiological emergency at the Station. The Meteorological Monitor-ing Program at Davis Besse has provided such information, with very little data loss, since the Station began operation in 1977. L.ake Level Monitoring Lake and forebay levels are monitored at Davis Besse to observe, evaluate, pre-dict and disseminste high or low lake levelinformation. Long term Lake Eric water levels are controlled by the amount of precipitation and evaporation in the Great Lakes drainage basin. As well as diversion of water for irrigation. indus-try and domestic use, short term changes are controlled by the current meterological conditions daily. Davis Besse personnel gather national weather service information and satellite imagery data to evaluate Lake Erie ductuations. Figure 4 9 shows lake level data for Lake Erie during 1980 to 1990 from four sites: Toledo, Davis Besse, Cleveland, and Buffalo.- As expected, all four sites track each other for the ten year period.
. The increase or decrease in lake level is sometimes due to high winds creating a seiche. Specifically, a seiche is an oscillation in water level from one end of a lake to the other due to rapid changes in winds and atmospheric pressure. The ~
seiche may last as long as thirty six hours and cause flooding at one end of the lake and anti flooding at the other Close monitoring of these events allow time to prepare for low or high water events and take appropriate action. 4 23
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Annual Erwironmental Operating Qeport 1990 Davis Bene Nuclear Power Station Forobey Temperature MonitortN Forebay temperature at Davi . Besse are rnonitored and compared with Lake Eric temperatures. Figure 410 show Forebay temperature averages for 1989, 1990 and the ten year average, FOREBAY TEMPERATURES 1989 AND 1990 WITH 10 YR. AVG ftMPF
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REMOTE SENSING Remote sensing is the scanning of the earth from remote observation stations; manned or unmanned. Satellite imagery can provide information on tempera-tures of the earth and its atmosphere, snowfall and rainfall, geologic activity, land use and vegetation cover Radar is also used for detecting precipitation and geo-graphic features. Aerial photography is used for land use, mapping, water use and vegetation cover. Satellite, radar imagery and aerial photography are used by meteorological per-sonnel on a daily basis to monitor global and local weather systems, lunar tidal gravitational effects, seismic activity, solar radiation fluctuations and magnetic fields and land use. All of these have an impact on the weather. Monitoring these events allow for careful analysis of weather conditions that could impact the operation of Davis Besse and surrouding area. Figures 4-12 and 4-13 shows sample applications of remote sensing. 4 25
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1990 Davis-Besse iJudear Power Station Annual Environmental Operating Report Table 4-1 Summary of Meteorological Instrumentation used at Davis-Besse Nucicar Power Station lewis Inur- = .:IA) Th rnhnto f m'd) Aren ncr (mA) %ft Parameser f mrtm) 06 mph 11% or 015 enph 100 and 75 (main) Osmet rmalet 0]l-1, trammetter Mem and Aun Wand SpecD which ewr is Gemet nwuse1025-2, translator 10(aus) greaser (Nerime Angus Recorder, model Eil102R) 100 and 75 (main) Gemet enodel 012-10, transmpter 0 75 mph 13.0* Mam and Aun Wmd threetson 10(sea) Gemet im del -025-2. tramlator (!!sserfine Angus Recorder, model til102R) 100,75 and to t eledyne Geocc4 Aspirated N/A 109*P Mam lemperature 1hermal Rad 2ation Shecid, nwx5cl 327 with I'latiniem R111(T-200) (listertme Angus Mais pant Recor$er, model El124D) Tcledyne Geotech Platmum RIB T/ N/A 1018*F thfferential 100-10 Main Temperature 75-10 delta T prucessor, t del 2135 (Esterime Angus Mufttpomt Recorder model Ell 24fi) 100,10 Cambridge nww3cl1135 M N!A 10.5*F Mann Dew Point Temperature (literime Angus Multipoent Recorder model E*12411) I!cifort tippeg flocket Ram Gauge N/A 11% st a m.1ir em%r Aes Precupttation 1 Cat. ,W 5 *1511 14% at 3 in.tr 16% at 6 sa,tr Tcledyne Geotetis Processor, mtmiet 2152
.35 foot tower ( A) Recordmg equipnent endrated m parentheses NOlli Mam = 340 foos tower Aux 4-27 i
i 1990 Davis-Besse Nuclear Power Station Annual Environmental Operating Report \ Table 4-1 Summary of , Meteorological Data Recovery (expressed in percentages of operabic tirne)* for the Davis-Besse Nuclear Power Station January 1,1990 through December 31,1990 AUG SEP OCT NOV DEC ANNUAL JAN FEH MAR APR MAY JUN JUI, W.17 100m 98I,4 100m Wind Speed 9435 95 2 99E7 99.72 99.73 97 S) 100 m W33 100m 98I4 84.72 91.73 97 S) 100D) W.19 1001X) 99.19 W.17 10)l6 98.18 1(X)m %d Direction 98.79 99.85 99E7 99.73 97.50 100m 82.12 100.00 98th W.17 10010 97.28 75m %d Speed 95Si 95D> 9937 99.72 981M 88E4 100n) 99.19 ?>.17 100fX) 98.79 99.85 99.87 93I;1 99.73 9530 10010 75m %d Direction W.17 100 3) 9831 10m Wind Speed %IA 95M 99E7 99.44 99.73 97 3) 100H) W33 1(MD) 9814 98.92 W.17 100fC 99.27 W.85 WE7 98 61 99.73 9730 1003 0 W.19 1009) 10m %d Direction 9839 W.25 W.73 95,50 1001H W33 100m W33 W.17 110.00 10m Ambient Temperaturc 9939 9935 WE7 97.78 98.89 1(Om V728 10m Ocw Point Temperature 81.59 W.85 WE7 W.17 W.73 97 S) 100u) WM 191m W.19 W.17 1001X) 99.14 9 7.'72 99E5 99E7 97.22 99.73 97 3) 100.00 W33 99.72 Wm Delta T (100m - 10m) 99.72 99.60 99.17 1001X) W.22 Delta T (75m - 10m) 98.52 99ES 99E7 9736 99.73 97 S) 100 m 9933 100 m Precipitation 100DJ 100.00 100R) 100D) 100m 10000 100AM) 100fM 100m 1919) HUD) 100fX) 97.10 Joint 100m winds 93.41 95m 99E7 8230 99.73 97 S) 10010 99.19 99.72 9832 99.17 100110 and Delta T (100m - 10m) 98.52 99.17 100 m 96.47 97 S) 100R) 81.85 W.72 Joint 75m winds and 9442 95 2 99E7 9133 99.73 Dc!ta T (100m-1(nn) 99.72 9832 W.17 100.00 96.48 94I2 95M 99.87 9 1 I27 99.73 97.50 10010 81.85 Joint 75m winds and Delta T (75m - 10m) W.19 99.72 98.25 99.17 100 #) WE) Joint 10m winds and 95S> 95M 99.87 % 39 99.73 9730 100 m Dcita T (75m - 10m)
- Values for individual * .10NTIIS = percent of time instrument was operable during the month,divkled by the number of hours in that month that the instrument was operable.
Values for ANNUAL data recoveries = percent of time instrument was operabic during the year, divided by the number of hours i year that the instrument was operabic. 4-28
! -3 l Annual Environmental Operating Report 1990 Davis.Besse Nuclear Power Station l l
. 'Ihble 4-2 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station
- l. ForJanuary 1,1990 through December 31,1990 i l
JAN FER MAR APR MAY JUN idL AUG SEP (X'r ' N(W DEC ; 100m WIND 21.4 17.0 18.4 17.5 16 9 173 15.1 11.7 13.4 17.9 19.9 179 Max Speed (mph) 54.49 5239 4033 3539 46.24 433 MJ6 28.18 30.46 42.13 44.10 47.78 Date of Max. Speed : 25 24 17 5 10 3 12 28 25 18 5 3 , Min. Speed (mph) 360 1.56 2.09 2.18 1.13 239 1.70 130 2.15 1.56 1.60 224 Date of Min. Speed 31 4 31 1 23 14 20 10 13 23 18 27 75m WIND 19.4- 15.6 16.8 16.2 15.6 15.8 14.1 10.9 13D 16.5 17E 16.9 . Max. Speed (mph) 5040 49.74 '38.59 34.44 4432 4030 33.06 26.45 3021 40.02 41.47 45.23 Date of Max. Speed 25 24 17 10 10 3 12 28 15 18 5 3 Min. Speed (mph) 330 '135 1.85 2.43 1.17 138 2.12 136 229 2.11 1.55 3D4 i Date of Min Speed 31 4 .3 1 23 14 20 10 26 23 18 19 10m WIND 12.1 1C ,' 11.1 103 10.6 9.7 9.2 7.2 7.9 10.1 103 11.1 . Max _ Speed (mph) 37.14 36E7 30.88 30D4 35.47. 31.0 22.62 18.59 21.89 31.23 3228 31.91 Date of Max. Speed 25 24 17 12 10 26 12 28 16 18 5 4 Min. Speed (mph) E8 130 1.55 1.85 1.02 1.74 135 133 133 194 1.02 1.47 ff Date of Min. Speed 27 11 11 23 22 12 25 2 26 24 19 27 10m Ambient Temp. 35 33.1 40E 50.2 57.1 68 3 723 70B 64.2 53.4 45.2 43.4 Max. (*F) 5639 63.19 76.05 8590 76E5 9132 9731 89A8 90.58 92.03 72.43 57.56 Date of Max. 17 13 14 25 8 17 4 28 6 3 1 3. Min (*F) 16.55 8.72 21.67 23.70 40.73 45.01 6039 54.51 4134 34.21 26J9 437 Date of Min. 30 26 4 3 11 5 7 8 24 29 30 24 i 4 4-29 !
Davis-Besse Nuclear Power Station 1990 Annual Environmental Operating Report Thble 4-2 Sumniary of Meteorological Data Measured at Davis-Besse Nucicar Power Station ForJanuary 1,1990 through December 31,1990 (Continued) AUG SEP OCT NOV DEC FEB MAR APR MAY JUN JUL JAN 10m DEW POINTTEMPERATURE 57.7 613 63.0 56 3 43.4 %0 28.0 283 243 313 373 46.6 Mean( F) 753 74.6 633 62.2 54E 51.8 61.2 61.6 633 723 74.7 53.5 27 6 4 27 3 Max. ( F) 25 15 !8 5 17 22 11 24.0 18B -23 Date of Max. 20.1 38.7 44.6 46.1 32.6 10.6 -6.7 236 10 6 26 8 24 Min.( F) 25 6 7 11 5 6 1 17 Dateof Min. 30 PRECIPITAITON 4.73 2.44 3.05 IES 5.50 141 2.00 4.76 1.92 2.50 2.53 3E7 40 38 .12 .23 Total (inches) .11 .57 41 31 .65 Max. in oce Day IDJ 36 .15 19 14 4 5 23 10 10 16 13 22 23 15 Date 4-30
Annual Environmental Operating Report . 1990 Davis-Besse Nuclear Power Station
%ble 4-3 Classification of Meteorological Data
' Wind Direction
. Wind Sector Wind Direction (Degrees)
N 348.75 TO 11.25 NNE 1123 TO 3335 NE 3335 TO 56.25-ENE 56.25 TO 78.75 E 78.75 TO 10125 ESE 101.25 TO 173.75 SE 12335 TO 14635 SSE 146.25 TO 16835 S 16835 TO 191.25 SSW 19125 TO 213.75 [ SW' 21335 TO 23625 WSW 23625 TO 25835 i W 25835 TO 28115 ! WNW 28125 TO 30335 NW 30335 TO 32615 ! NNW 32625 TO 34835 Pasquill Stability l DeHa T (100mm - 10m) 340ft -35 R Delta T(75m - 10m) 250 ft -35 n ; i (340 ft -35 ft) *F ("C)
- F (' C) i Stability Class A (extremely unstable) T < -3.13 T < -2.18
, B (moderately unstable) -3.13 < =T < -2.80 . -2.18 < = T < -1.95 C (slightly unstable) . -2.80 < = T < -2.47 -1.95 < =T <-132 D (neutral) -2.47 < = T < -032 -1.72 < = T < -0.57 E(slightlystabic) -0 82 < =T < 2.47 -0.57 < = T < 1.72 F(moderately stable) 2.47 < =T < 639 1.72 < =T < 439 i G (extremely stable) 6S) <=T 4.59 <=T I l 4-31
Annual Environmental Operating Report - 1990 Davis-Besse Nuclear Power Station 1hble 4-4 Monthly and Annual Stability Class Frequency Distributions liased On Delta T 340FT -35Fr (100m - 10m) For January 1,1990 Through December 31,1990 (in percent) 100m .am A B' C D E F G f 0.00 0.00 0.00 54.9 37.1 6.10 1.90 JAN FEB 0.90- 1.20 330 60.8 29.4 4.20 030 MAR 0.00 0.80 2.70 61.9 27.2 5.40 2.00 0.40 1.10 4.60 49.0 28.7 12.40 3 ?G APR ' MAY 0.50 2.40 4.70 57.8 263 7.70 0.50 JUN -0.10 0.60 1.90 563 33.2 6.40 1.60 3UL 1.20 0.80 2.00 60.5 -27.8 7 10 0.50 AUG 0.10 030 3.00 583 20.2 15.0 3.10 i SEP 0.00 0.40 1.00 52.8 29.7 13.1 3.10
-0.10 0.40 4.00 52.9 25.1 15.0 2.40 OCT .
0.70 0.70 48.2 373 10.9 2.20 I NOV 0.00 030 030 58.6 34.8 5.10 0.00 DEC 0.90 0 230 56.0 29.7 9.10 1.80 ANNUAL 0.40 0.70 5 4-32 ___
h w I I w dW 1990 Davb-Besss Nodear Power Statbn Annual Environmental Oparating Report
'Pable 4-5 -
Monthly and Annual Stability Class Fruguency Distributions Based on Delta T 250FT-35FT (75m - 10m) For January 1,1990 'Ihrough December 31,1990 (in percent) C D E F G 75m-10m A B 51.8 39.0 6.40 1.90 JAN 0.00 0.00 0.80 5.20 565 313 430 030 FEB 0.40 1.90 3.50 58.5 27.2 5.90 2.70 MAR 0.40 1.70 7.60 44.2 26.4 14.4 4.10 APR 130 2.00 4.90 58.5 25.5 6.50 2.00 ' MAY 1.20 1.50 503 34.8 5.40 1.90 JUN 0.60 1.00 6.10 53.2 28.5 7.10 0.90 JUL 0.10 1.90 8.20 8.90 52.0 18.8 12.2 6.50 AUG 0.10 1.50 5.70 47.4 28.6 13.4 3.80 l SEP 030 1.00 49.9 25.4 14.0 3.50 OCT 0.70 230 4.20 1.70 40.8 42.4 11.2 2.70 ; NOV 0.80 0.40 0.50 57.7 36.4 5.10 030 DEC 0.00 0.00 l 4.80 51.8 303 8.80 2.60 ANNUAL 0.50 130 I f 4-33 _ _ _ _ _ .a
l~ Annua! Environmental Operating Report 1990 Davi>Besse Nuclear Power Station . j Table 44 Davis-Besse Nuclear 1%werStation Stability Classes by Hour of Day for 1990, Based on 340FT-35FT (100m-10m) Delta T l Stability Index ! Ilour of Day A B C D E F G TOTAL FG EFG [
.1 0 1 0 125 162 64 ~ 12 361 76 238 2 0 0 0 129 157 66 13 365 79 236 0 1' 127 152 66 18 365 84 236 3 1
- 4 1 0 2 130 146' 70 16 365 86 232 5 1 3 1 144 131 62 20 362 82 213 6 2 2 3 141 137 .59 20 361 79 216 7 4- 1 2 153 137 58 10 365 68 205 8 5 2. I 179 139 28 6- 360 34 173 i 9 -3 1 5 251 89 11 'I 361 12' 101 l 6 358 7 42 ;
10 3 2 13 298 35 1 11 3 4 23 205 17 3 1 356 4 21 3 7 29 299 20 0 1 359 1 21 , 12
- 2 10 39 293 12 0 1 357 1 13 13 14 2 11 35 297 14 1 1 361 2 16 15 0 8 26 302 22 3 0 361 3 25 l 13 - 305 33 4 1 362 5 38 l 16 1 5 17 0 2 5 290 57 6 2 362 8 65 18 0 1 2 249 101 9 1 363 10 til 2 363 20 158 i 19 . 0 2 1 202 138 18 20 1 0 1 141 185 32 3 363 35 220 ;
' i i
21 1 0- 0 122 191 42 5 361 47 238 0- 0 122 179 55 5 362 60 239 l 22 1 l- 0 0 130 165 61 6 363 67 232 23 1 24 0 0 1 132 159 62 9 363 71 230-l l l Tbtal 32 65 203 4866 2578 786 155 8685 '941 3519 l l 9.4 0,7 2.3 50.0 29.7 9.1 13 100.00 10.8 40.5 [ l Percent l l l 1 4 a . _ _ _ . Annual Environmental Operating Report 1990 D vis-Besse Nudear Power Station Table 4-7 Davis-Besse Nuclear Ibwer Station Stability Classes by Hour of Day for 1990, Based on 250FT-35FT( 75m-10m) Delta T Stability Index D E F G TOTAL FG EFG Ilour of Day A B C 166 64 17 %5 81 247 1 0 0 1 117 159 56 28 %5 84 243 2 0 0 2 120 155 55 30 365 85 240 3 0 1 0 124 149 61 28 M5 89 238 4 0 0 2 125 145 56 26 362 82 227 5 0 0 0 135 139 56 23 M4 71 218 6 0 0 1 145 144 51 11 365 62 206 7 0 0 1 158 122 28 2 360 30 152 8 1 0 2 205 2I,4 82 7 2 361 9 91 9 0 0 6 42 4 358 5 47 10 0 1 32 278 1 24 3 1 357 4 28 11 5 10 58 256 73 238 20 0 1 359 : 21 12 8 19 18 0 1 357 1 19 13 11 27 68 232 M1 2 24 14 7 25 69 2% 22 1 1 2 %1 3 24 15 .4 17 54 M) 23 1 288 32 4 1 %2 5 37 16 3 8 26 276 58 9 2 M2 11 69 17 2 2 13 101 9 2 %3 11 112 18 1 0 3 247 148 21 2 %3 23 171 19 0 0 1 191 0 0 138 181 40 4 V4 44 225 20 1 245 116 188 50 7 362 57 21 0 0 1 176 67 6 M3 73 249 22 0 0 0 114 170 63 12 3M 75 245 23 0 0 0 119 0 0 1 119 170 61 13 X4 74 244 24 414 4501 26M 768 222 N#2 y>9 M24 Total 43 110 303 8E 2.6 100 9) 11.4 41E Percent 0.5 13 4E SIE t 4-35
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Annual Environmental Operating Repon 1990 Davis Besse Nuclear Power Station Marsh Management Navarre Marsh The Navarre hlarsh is approximately 733 acres of low lying wetland which sur-rounds the Davis Besse Nuclear Power Station, located on the southwestern shore of Lake Erie The Toledo Edison and Cleveland Electric illuminating Companies co-own the marsh which is leased to the U.S. Fish and Wildlife Ser-vice (USFWS), who manage it as part of the Ottawa National Wildlife Refuge. , Protective dikes and access roads in the marsh are maintained by the Toledo Edi-son Company. Emironmental Compliance (EC) personnel at Davis Besse are responsible for conducting marsh inspections and generating monthly status re-ports, recommending management actions, and actively controlling undesirable plant species such as purple loosestrife. Results from the marsh inspections are compared to the activity levels expected by the USFWS for each seasonal period, and from this comparison an evaluation of the marsh progress is made. The Navarre hiarsh is completely enclosed by a system of dikes (refer to Figure 5 1) and a revetment (Figurc5 2) to protect it from flooding and the wave action of Lake Erie. A dike is a retaining structure designed to hold back water for pur-poses of flood control and to aid in managing a marsh for waterfowl and wildlife. Dikes are also routinely used to convert wetlands into land suitable for farming. A dike generally consists of rock laid over a clay base at a slope of approximately a one to-one or a two to-one ratio, When used as a marsh management tool, dikes aid in controlling the water levels required to obtain the desired vegetation beneficial to wildlife hianipulating water levels is one of the most important management tools used in the Navare Marsh Simply by lowering or raising water levels within the marsh, certain plant species can be encouraged or discour-aged to grow. From a wildlife management standpoint, plant species that provide either food (e.g.,smartweed) or shelter (e.g., cattails) for native wildlife, are more desirable that plant species that serve no useful purpose (e.g., purple loosestrife.) 5-1
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Figure 5 2:The gently sloping sides of a revetment actually encourage beach formation by dissipating wave energy and allowing particulate matter to settle out at the base of the structure, Revetments are an ideal method of flood control for areas subject to a great deal of wave action, such as the Lake Erie shoreline. 52
1 Annual Environmental Operating Report 1FJO Davis Besse Nuclear Power Station l A revelment is also a retaining structure designed to hold back water for pur- i poses of erosion control and/or to encourage beach fromation. Unlike a dike, a ! revetment consists of rocks laid over a nylon mesh mat atop a clay base, Revet-ments are also built at a gentler slope ( E.g., a ratio of three to-one). As waves l strike the gradual slope of a revetment, their energy dissipates, allowing the sedi-ment load to drop out at the base of the revetment. At the same time, the under- { lying mat allows the water to percolate through slowly. This helps maintain the ; integrity of the clay base beneath the mat. Because a revetment extends well out i into the water, it actually encourages beach formation by this passive deposition of particulate matter. Particularly along the southern shores of Lake Erie, where wave action has literaly eroded away large areas of shoreline, a revetment is a logical choice to both protect the inland areas and to encourage beach formation. Due to the ! steeper slopes of dikes, when waves strike, they are denected laterally down the l shoreline. This tends to scour out the base of the dike and will eventually cause the dike to slump or collapse, allowing Gooding, in contrast, when waves strike the gently sloping sides of a revetment, they are de0ected up and their energy is dissipated. As the water slowly passes back down the reverment, any silt or sedi-ment drops out, gradually forming a beach along the base of the revetment. ; Beaches themselves provide a natural form of Good control, and are therefore ; desirable in areas with a great deal of wave action (such as Lake Erie). ! hiarshes are generally found in low lying flat areas, and are chacterized by a wide divesity of plant life as the elevation changes. In the Navarre hiarsh , elevations ; I throughout rarely differ by more than two feet (refer to Figure 5 3). As one trav-els to higher elevations and the land gets dryer, woody plants such as shrubs and trees replace the plants more commonly associated with wetlands. The Navarre hiarsh has a varied landscape with different plants found in each. The majority of vegetation is found in the fresh water marsh. Three kinds of vegetation grow l here: emergents, submergents, and floating plants. Emergents grow in wet soil or out of the water and include cattails, smartweed and arrowhead. Sub. mergents, such as pond uced and water milfoil, thrive beneath the water's sur- l face. Floating on the water are greater and lesser duckweed, and water lilies. l All these plants provide faod, cover, and nesting area essential to wildlife. The Navarre hiarsh is bordered by a narrow, dry beach ridge along the lake front. The beach supports a limited number of woody plants and has many stand-1 ing dead treed, frequently occupied by birds of prey such as bald eagles. Extend-ing out from the beach is a sandbar which formed over the last few years after the revetment was constructed in early 1988. As discussed earlier, the revetment helps dissipate lake wave action , allowing suspended particles in the water to 53 l l
Davis.Besse Nuclear Power Station 1990 Annual Environmental Operaung Report ELEVATION ABOVE-SEA LEVEL SHAUSS ANo TREES I + oMSS ; I il SECGE l ll 571.5 _ sunutaseur mo n.c.mno pwis I i 570.5 AVERAGE WATER LEVEL IN THE NAVARRE MARSH t
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l l t i I i 0 FEET 1000 Figure 5 3:If one travels 1,000 feet in any direction in the Navarre Marsh, eleva-tions will rarely differ by more than two feet. As elevation increases, the ground gets dryer and plant communities change. l i settle out and accumulate, eventually forming a sandbar. The sandbar then acts l as a natural barrier, protecting the shore from storms and wave action. In addi. ! tion to protecting the shoreline, the sandbar also benefits local wildlife. Shore birds and waterfowl are often seen resting and feeding in this area. Figure 5 4, taken in early 1990, shows the beach that has formed within the last year after the revetment was completed in 1988. Lower lake levels in 1989 also exposed shorelines that were underwater during previous years. These lower levels also
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- l. - contributed to the beach at the base of the revetment pictured in Figure 5-4 The Navarre Marsh also supports a variety of other habitats, including a swamp forest and wet meadows. Bluejoint grass and rice cut grass are the major wet L 5-4 l
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\ l s l i I l l ! I 1 Figure 5 4:The revetment encouraged this beach to form within the first two years. While encouraging beach formation, the revetment also provides a means 3 of flood control and protects the marsh against the wave action of Lake Erie, i i rneadow plants. In the swamp forest, the soil is poorly drained or underwater for i part of the growing season. The swamp forest supports woody plants such as cot-tonwood, willows and buttonbush, and several understory plants such as poison ivy, sumaciand swamp loosestrife. Navarre Marsh is unique to this area because of the buttonbush found in the swamp forest. Buttonbush is becoming rare along Lake Erie and so it is becoming increasingly important to protect those i habitats that support the buttonbush population. Studies have shown that 90% of Navarre Marsh's black crowned night heron use the buttonbush swamp for feeding and resting. Green herons have also been observed nesting in the area (Meeks and Hoffman,1979). i A wide variety of birds utilize Navarre Marsh. The best known resident is the Canada goose, abundant throughout the marsh and around the Station site. . Besides natural nesting site, several artificial necting areas, such as wood duck boxes and goose tubs, are provided. The boxes and tubs represent a collective ef-fort of both U.S. Fish and Wildlife Service, Ohio Department of Natural Re-sources (ODNR), and Davis Besse personnel. The marsh also provides waterfowl with a feeding and resting place during their migration. Besides water-fowl, raptors such as owls, hawks and eagles also frequent the marsh. In the , spring and fall, warblers, vircos, kinglets and a bariety of other songbirds stop 55
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i Davis Bosse Nuclear Power Station 1990 Annual Environmental Operating Report here during their migration. Great blue herons and great egrets use the marsh as a feeding and resting area during the breeding season, Gulls, rails, killdeer, and a wide variety of other wading birds can be observed throughout the year in the Navarre Marsh. Mammals also use the Navarre Marsh throughout the year. The most noticeable resident is the muskrat. The marsh is dotted with muskrat houses which serve a dual purpose: they provide homes for muskrats and nesting places for waterfowl. The muskrat population in Navarre Marsh is kept in balance by trappers who are supervised by personnel from the Ottawa National Wildlife Refuge. Other mam-mais inhabiting the Navarre Marsh include raccoon, red fox, mink, and whitetail j deer. Special projects in 1990 Toledo Edison and Davis Besse are committed to protecting the Navarre Marsh and have gone to great lengths to preserve this valuable resource. This is best illustrated by the extensive dike system built to protect the area from flooding, and by the many special projects conducted in the marsh each year. In 1990, these special projects included controlling undesirable plant species, songbird banding, Canada goose banding and nesting surveys. and wood duck banding and , nesting box relocation. A brieidescription of each of these projects is provided in the following paragraphs. ' Not all of the plants found in Navarre March are beneficial to wildlife, Purple loosestrife (lphmm salicaria) is one such undesirable species. This exotic plant, introduced from Europe, is an aggressive species which tends to crowd out the valuable plants. Each summer, Environmental Compliance personnel record and map the locations of all purple loosestrife plants found within the marsh. Once sighted, the staff attempts to control the spread of the species through the use of approved herbicides, and by removing smaller individual plants. One other undesirable plant species found in Navarre Marsh is the giant reed (Phragmites australis). These tall plants often grow thick, dense stands which crowd out more beneficial plant species. Environmental Compliance personnel attempt to control the giant reed through limited herbicide spraying under the di-rection of the U.S. Fish and Wildlife Service. In controlling these undesirable plant sp:cies, the rich plant diversity in the Navarre Marsh is maintained 5-6 l
Annual Erwironmental Operating Report 1990 Davis Besse Nucioar Power Station The songbird banding project was conducted in cooperation with the ODNR from April through August 1990. The project involved capturing and banding songbirds migrating through the area. From April through June,8,011 individual birds were banded. The yellow warbler, a resident species of the Navarre hiarsh during the summer months, was studied in further detail from June through Au-gust. The study provided information on nesting and feeding habits of the yellow warbler. The data collected during the banding project provides and extensive database so that the migratory movements of the warblers may be better under-stood, and to aid in tracking the population levels of the different warbler species over time. A Canada goose nest survey was performed in the Navarre Marsh and in the sur-rounding marsh area in 1990 by the ODNR. The survey was performed using a helicopter from the ODNR. This allowed the nests to be located more quickly and easily. Sixty five goose nest were identified in Navarre Marsh. This was the highest concentration of Canada goose nest in this area. Environmental Compliance students assisted the ODNR in capturing and band-ing ducks at Ottawwa National Wildlife Refuge in December. Mallards and black ducks were aged, sexed, and banded. Six of the black ducks were fitted with radio collars for tracking. Prior to the 1990 nesting season,19 wood duck boxes were installed at several lo-cations throughout the Navarre Marsh. These boxes will be examined for use and reconditioned with fresh sawdust prior to the 1991 breeding season. 5-7
Annual Environmental Operating Report 1990 Davis Boss,e Nuclear Pcw:r Station References 1."The Audubon Society Nature Guides: Wetlands," National Audubon Society,Inc. (Marsh 1985).
- 2. 'The Ecology of Coastal Mathes of Western Lake Erie: A Community Profile,
" Biological 85(7.9), U.S. Fish and Wildlife Service, Dept. of Interior and Corps of Engineers, U.S. Department of Army ( February 1987).
- 3. Meeks and Hoffman," Bird Populations Common to the Sister Islands, the Role of the Navarre Marsh",(1979).
58
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Annual Environmental Operating Report 1990 Davis Bosso Nuclear Power Station ZEBRA MUSSELCONTROL introduction Dreissenapolymorpha,more commonly known as the zebra mussel because of its striated shell,is a native European bivalve that was accidentally introducted into North American waters in 1988 and was discovered in Lake Eric 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 like this, they may form layers several inenes 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 were found attached to the intake crib (the structure that allows water to be pulled in from the lake) and the first section of the intake conduit (the pipe that connects the crib to the intake canal). However, mussels have not attached to tne latter portion of the conduit of the intake canal which supplies water to the plant. The mussels were removed from the crib with high pressure water which destroys the mussels as well. M 5/e" W Fig. 6-t : Named after its distinctive black striping. the zebra mussel (Dreissena polymorpha) is equipped with a tuft of fibers that protrude through the hinged area of its shell. These, known as byssal threads, attach to hard surfaces with an adhesive secretion which anchors the mussel firmly in place. l 6-1
i Annual Environmental Operating Report 1990 Davis-Besse Nuclear Power Station
.At Davis Besse, zebra mussels are monitored to estimate their population den-sity, which will determine the severity of the problems they may cause. The life cycle of the mussel and the effects of certain variables (wind, temperature, and chemicals) on mussels or veligers, the larvae stage of the mussel, are being stud-ied to determine a means of controlling mussel pcpulation.
Monitoring The Zebra Mussel Monitoring Program, implemented by the Environmental Compliance Unit, 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 det' anined by lake water temperature. Samples are only taken when the lake temperature is above 12 C because this is the temperature at which spawning may occur. At temperatures above 18 C, when spawning condi-tions are most favorable, more frequent samples are taken. The most frequent sample type is the raw water sample collected daily from the water treatment plant. Other water samples are taken weekly from the Toussaint River and semi weekly from two different locations along the forebay (the canal that provides lake water for plant intake). These samples are collected using a plankton net sampler: a net support system with a straining bucket used for plankton size (microscopic) organisms which include veligers. One milliliter from each sample is observed under a microscope to check for the presence by using the. sample volume and the number of veligers observed to determine the average number of veligers per liter. The average number of veligers per liter is deta.rmined so that a standard comparison may be made from water samples of different volumes, One other type of sample is collected, but it is observed for the presence of adult mussels rather than the veliger stage, This sample is taken from the bottom of the screenwash basin which collects debris from the water intake traveling screen. It is collected by using a device (an Eckman Dredge) which has a pair of spring loaded jaws that close to trap a sediment sample. The sample is then dumped onto a screen and sifted through to count the number of adult mussels. Another method used by the Environmental Compliance Unit to monitor adult mussels is the observation of mussels that attach to objects placed in the forebay. These objects include a cement block and a "veliger tree" (two levels of crossed boards separted by a metal support), wh ch has large graduated slides that allow attached mussels to be counted easily. Once a week the block and the tree are pulled out of the forebay and the mussels are counted. 6-2
Annual Environmental Operating Report 19X) Davis Besse Nuclear Power Station Foreboy Veliger Sample Comparisons y f $D0 - i - p t L 100 - r 0- i i , , &,% , I i i Ah i i i i i Emeib i i 1
- A A J J J J J J A A A A A A A 9 9 9 9 9 9 9 9 1 1 1 2 2 3 2 7 9 1 1 2 2 2 3 2 6 9 3 6 1 3 6 0 3 8 0 Dates M wear towe M w.or into6e l Fig. 6 2: The graph (above) sh -'.the peaks in veliger population during July and August 1990 and that the wuger population is less dense in the intake near the station compared to the veligers near the lake.
The date, time, location, and number of adult mussels or veligers are recorded for every sample or observation. Weather data and water temperatures are also recorded to determine their effects on veliger/ mussel population. Research The emironmental Compliance Unit is involved with the Electric Power Re. search Institute (EPRI) in studying the effects of water velocity and chemicals on zebra mussels. The purpose of the study is to determine what may influence mus-sel mortality and/or detachment. An apparatus, Fig. 6-3, designed by EPRI to roughly simulate an in plant water system was constructed for use at Davis-Besse. The apparatus consists of four different sized cells, ranging from 11/2" to 3"in diameter, with a valve connected to each that allows the water flow to be ad-Justed. Mussels are placed inside the cells then water is pumped from the forebay through the system. A chemical feed pump is connected to the syste:: so that chemicals can be introduced into three of the cells. The fourth is the control cell that enables comparisons to be made with different chemical conditions in the other cells. 6*3
Annual Env6ronmental Operating Report 1930 Davis-Besse Nuclear Power Station The results of the first chemical study are inconclusive due to the low tempera-tures that occurred during the experiment. Research has been halted but will re-same once water temperatures increase with the coming of Spring. V ; _ .,. . : .ca . 9 :' _ .. 4
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Annual Environmental Operating Report 1100 Davis Besse Nuclear Power Station WATERTREATMENT WATER TREATMENT PLANT OPERATION Deuriptk>n 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, sodium alu-minate, and a coagulant aid to make the water clean and safe for consumption. This water may also be further treated by a demineralization process to produce water which is used by much of the Station's equipment, including the turbine. This process is used to produce high purity water to maintain plant system integ. rity. Operation of the water treatment plant falls under the pursiew of the Ohio Envi-ronmental Protection Agency (OEPA) and the Ohio Department of Health. The operation of the facility is reviewed by certified operation, Public Water Supply. Activities at the water treatrnent 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 submitte.d to the agency. These reports are submitted monthly, and include the Drinking Water Operation Report (OEPA form 5002) and the Drinking Water Contaminant Report (OEPA form 5001). Timse reports contain sample dates and analytical results, which are compared to standards es-tablished by the OEPA. Operation of the water treatment plant is maintained by the Chemistry Department and monitored by the Emironmental Compliance (EC) Unit through weekly inspections. 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, and heavy metals (such as chromium, aresenic, mercury, lead) and quarterly for radio-activity and certain organic chemicah. The health and safety of the water treat-ment plant operators and other site personrael are ensured through weekly housekeeping inspections of the facility. 71
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- wU% sm Davis 4 esse Nuclear Power Station 1990 Annual Ee gywnseparaw wet. s Ciertner Operation The water treatment plant at Davis Besse uses upuow clarifiers, or precipitators, to remove sediment, organic debris and dissolved agents fre'n the raw water I
prior to filtration. Clarifiers combine the conventional treatn.mt steps of coagu. lation, nocculation, and sedimentation into a single unit. Coagulation is the pro-cess 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 Doccula-tion, 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 clarifer.These processes normally require large sepa-rate tanks. However, the use of clarifiers saves both space and the manpower needed to operate the treatment plant. The sediment removed during clarification is routed to settling basins. The sedi-ment settles to the bottom of the basin, allowing the clear supernatant to be dis-charged to the lake. The water treatment plant has two precipitators with separate chemical addition l systems, allowing for operation of one or both of the units. Throughout 1990, precipitator number two was operational while precipitator number one was taken out of service for cleaning and maintenance, now Measurement The OEPA requires daily domestic water production now measurement for the i Drinking Water Operation Report. This Dow is normally recorded from the Do- , mestic Water integrator in the water treatment plant, however, this integrator I was out of service throughout the year, As a result, flow values had to be calcu-lated using precipitator and secondary demineralizer flow measurements, in De- , cember 1990, the integrator was replaced by a new flow measuring device making plant production Gow values more accurate and easily obtainable. l 4 7-2
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l l , i i Wastewater Treatment Plant Operation I i The wastewater (sewage) treatment plant operation is supervised by a state l certified Wastewater Operator. Wastewater generated by site personnel is j treated at an onsite extended aeration package treatment facility designed to , l accomodate a flow of 38,000 gallons per day (gpd). This facility (Figure 71) con- ; sists of two units, and the second is a 23,000 gpd plant, WWTP Number 2. In the treatment process, w astewater from the various collection points around the site,
- called lift stations, enters the facility at the equalization chamber. This structure i is simply a chamber which collects raw wastewater and distributes it to the surge 1
( tanks of the treatment plants. l l The wastewater is then pumped into the aeration tanks. Ilece, organic materials are digested by microorganisms which must be provided with a source of oxygen. This is accomplished through the use of blowers. The mhture of organics, micro-organisms, and decomposed wastes is called activated sludge. The treated
- wastewater settles in a clarifier, and the clear liquid (Supernatant) passes over a i i weir, leaving the plant by an effluent trough. The activated sludge contains the j organisms necessary for continued treatment, and is pumped back to the front of I i
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Annual Environmental Operating Report 1100 Davis Besse Nuclear Power Stat on 4 1 the plant to digest more incoming wastewater. The effluent leasing the plant is 3" dainfected with chlorine and is pumped to the wastewater treatment basin (NPDES Outfall 601) where further reduction in solids content and the Blochemical Oxygen Demand (BOD) takes place. 4 To provide for optimun wastewater treatment, Emironmental Compliance added , a laboratory to the wastewater treatment facility in 1988. The laboratory is used to run daily tests (refer to Figure 7 2) on the plant processes including pil, total suspended solids, dissolved solids, percent settleability, chlorine and dissolved , oxygen tests. By analyzing the test results, an operator may make adjustments to treat the wastes more effecively.
SUMMARY
OF 1m WASTEWATER TREATMENT PLANT OPERATIONS WWTP Number 1 was taken out of service in early May 1989 after operators ob-se ved that the wall separating two of the plant's treatment tanks was bowing l several inches. The plant was completely drained and suupports were installed to alleviate this problem. Current plans are to place the Number one WWrP back into service early in 1991. Later that year WWTP2 will be removed from service for cleaning and maintenance in 1991. Biochemical Oxygen Demand (BOD) is an analytical procedure designed to determine how polluted the water is. The more organically active the wastewa-ter is, the more oxygen it will consume. IIence BOD measures the demand for this oxygen; the higher the BOD the greater the treatment required, in 1990, water entering the treatment system had an average BOD of 230mgt while water leaving the system averaged only 5 mg/L This represents a total BOD re-duction of 98E National Pollutant Discharge Elimination System (NPDES) Reporting The OEPA has established limits on the amount of pollutants the Dav!s Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 21B0011'ED. Parameters such as chlorine, suspended solids, and pH are monitored under the NPDES permit. In June 1990, the NPDES permit was renewed, with Ohio EPA issuing a new permit with some new requirements. For example, the permit was expanded to include increased sampling frequencies for suspended solids and BOD at the wastewater basin. 75
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v e _ 1990 Annual Environmental Operating Report Davis Besse Nuclear Power Station i Davis Besse personnel prepare and submit the Monthly Ohio EPA NPDES Reports.These reports are complied, typed, reviewed, approved, and submitted 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 discharged points, or outfalls, and one is a temperature monitoringlocation. Descriptions of these sampling points follow. Outrail 001 Collection Box: At a point representative of discharge to Lake Erie. Source of Wastes: Low volume wastes (Outfalls 601 and 602) circulation system blowdown and occasional service water (sample collected at Davis-Besse Beach Sampling Station). Outfall 002 Area Runom Discharge to Toussaint River. Source of Wastes: Storm water runoff, condensate pit sumps, turbine building drains, boiler drains, circulating pump house sumps (sample collected at discharge of Daining Center Pond) . 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 Wastewater Plant Tertiary Tireatment Basin: Discharge from wastewater treatment system. Sources Of Wastes: Wastewater Beatment Facility. Outfall 602 Low volume Wastes: Discharge from settling basins. Source of Wastes: Water treatment residues, condensate polishing resins (sample collected at overflow number 2 basin). 76
l Annual ErMronment2J Opertthg Report 1990 Davis Desse Nudoar Power St: tion Sampling Point 801 Intake Teraperature: Intake water prior to cooling operation (values obtained computer point at east end of forebay). 1990 NPDES Summary Ouifall 001 The Davis Besse NPDS permit limits the amount of chlorine that can be dis-charged to Lake Erie, in order to protect the lake's divene aquatic life. Chlorine discharge is restrictd to only two hours per day for this purpose. On two occa-sfons, in 1990 this requirement was not met. The fint incident occured on Au. gust 31 as a result of an equipment malfunction. The second took place on _ October 4. It was attributed to design and equipment deficiencies. Neither oc- Q curance resulted resulted in an exceedance of the 0.5 mg/l free available chlorine p (FAC) daily maximum concentration limitation , and no impact to the lake was observed. Outfall 002 Various conditions resulted in the isolation of Outfal 002 for much of 1990, in February of 1990, the discharge gate was closed due to feedwater drainage into the 'I1 raining Center pond via the station stormwater system. The discharge of the pond (Outfall 002) was again isolated in May 1990 as a result of condensate drainage in the station which contained small quantities of a treatment chemical; hydrazine, The gate remained closed throughout the summer as evaporation eliminated the need to discharge stormwater. The gate was opened in November 1990, in preparation for the winter months. Outfall 003 The screenwash catch basin overflow requires a single total suspended solids analysis each month and has no set limitations. No signifigant problems occured at this outfallin 1990. Outfall 601 Algac populations thrive on the nutrient rich water in the wastewater treatment basin. Although algae play an important role in tertiary, or final cleanup, 77
Davis Bosso Nuclear Power Station 19x) Annual Env6ronmental Operating Report excessive numbers can adversely impact effluent quality. Algae concentrations in 1990 were suprisingly moderate. A single algicide treatment and cool temper-atures stabilized the basin. The established limits for Outfall 601 were not ex-ceeded in 1990. Outfall 602 The established limits for Outfall 602 were not exceeded in 1990. No signigicant p"hlems occured at this outfall in 1990. Sampl!ng Point 801 The intake ternperature is obtained from o computer point and is monitored con-tinuously. Temperaturg variations between intake and discharge temperatures car' range as high as 15 F was recorded for the year. An average differentiation ) of 3.8" F was recorded for the year. ( l $'l i._ ' 78
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Figure 8-2: Visual mspecuons of all PCl3 transformers are conducted to detect l l leakage and avoid potential problems which may arise. l 1 and avoid potential problems which may arise. There are eleven PCB transform-i ers located in the Auxiliary Building, Water Treatment Plant, near Service Build- , ing 2 and the Personnel Processing Facility. Environmental Compliance personnel are currently sampling all fluid filled transformers at Davis Besse and
; submitting the samples to an offsite lab for analysis to ensure ihat there are no l
! other PCB or PCB-contaminated transformers onsite. ! The eventual phase out and elimination of PCBs is recommended due to the ! high cost of PCB spill cleanup. Although no time lim t has been set on this plan, ) in 1990, Davis Besse continued an aggressive program of reducing the number i of PCB transformers onsite. i Ten PCB transformers underwent the fifth and final retronll cycle during 1900. A l retrofill cycle involves flushing the PCB fluid out of the transformer, refilling it i with a PCB leaching solvent, and allowing the solvent to circulate in the trans-F l 87
Davis 4 esse Nuclear Power Station 1990 Annual ErMronmental Operating Report ) former during operation. For the entire retrofill process, the transformers are ' retrofilled three times Wth a leaching solvent and twice with silicone fluid.The entire process will take two to three years and will extract almost all of the PCBs. The transformers will be tested in 1991 for PCB levels, and if less than 50 parts per million (ppm), the transformers can be reclassified as non PCB. One trans- 1 former, BF 4, was reclassified as non PCB in 1990. Compilence WRh the Transportation Safety Act - Before any wastes are transported offsite, Davis Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations. Also, the transportation vehicle is checked to ensure DOT placards are on all sides and it is in good operating condition (for example, brake lights and turn signals func. tion properly). Hazardous wastes are transported for disposal within 90 days from the date accu-mulation and storage began, as required by the USEPA waste generator permit issued to Davis Besse. Before shipping the waste, approval for disposalis re-ceived from the Treatment, Storage and Disposal Facility (TSDF). Prior to transportation, a Uniform liarardous Waste Manifest is completed and signed by both the generator and the transporter, if the TSDF does not return a signed copy of the manifest within 35 days, Davis Besse personnel contact the facility to determine the status of the waste, in 1990, all manifests were returned from the TSDF to Davis Besse within the required 35 days. Compliance With the Clean Air Act In 1990, a notification letter was prepared and submitted to the EPA concerning the removal and disposal of asbestos conta!ning material from Davis Besse. The Davis Besse cooling tower was renovated and (amount) of nonfriable asbestos cement board was removed and replaced with a non asbestos cement board. As-i bestos is not considered an RCRA hazardous waste, but the EPA does require special handling and disposal of this waste under the Clean Air Act. Audhs and Inspections The above programs, as well as Davis D sse's commitments to various regulatory agencies, are audited and inspected by various groups and individuals including the following: e Davis Besse Quality Assurance Department e Nuclear Regulatory Commission e Institute of Nuclear Power Operations 88
Annual Environmental Operating Report 1930 Davis Besse Nuclear Power Station e Emironmental Protection Agency e Private Consultants These inspections and audits are performed to ensure Davis Besse maintains the commitment to meet the reqairements of local, state and federal regulations. As a measure to ensure compliance with applicable regulations Environmental Compliance and Quality Assurance personnel have been conducting surveys of all the vendors utilized for disposal of Davis Besse chemical wastes. This in-cludes the analytical laboratories, transporters, and TSDFs The surveys include a checklist of applicable federal RCRA, HSWA, and DOT regulations. If the vendor or TSDF has a deficiency in complying with an item of the regulation or program enhancement, a Recommendation or Observation, respectively, is is-sued to the vendor or TSDE For an Observation, the facility is requested to re-spond within thirty days with corrective actions. A Recommendation is issued to suggest a good business practice and does not requite the facility to respond with any corrective actions. Only three Recommendations were issued to the one fa-cility surveyed in 1990. Other Programs Underground Storage Tanks According to RCRA, facilities with Underground Storage Tanks (USTs) are re-quired to notify the State. This regulation was implemented in order to provide protection from tank contents leaking and causing damage to the emironment. An UST includes the tank system and its piping. It must have at least 10% of its volume underground. Additional standards require leak detection systems and performance standards for new tanks. At Davis Besse the two 40,0W gallon and one 8,000 gallon diesel fuel storage tanks, and the one 2,000 gallon waste oil tank are regulated as USB. UST regulations also provide the following timeline for revamping tank systems:
- By January 31,1992 all tanks must have permit renewals completed and submitted.
e Tank tightness testing capable of detecting a 0.1 gal /hr :eak rate or monthly tank gauging with inventories within 13 gallons must be conducted on the 2,000 gallon waste oil tank by December 22,1993. e Line tightness tests must be performed every three years by December 22,1996. 89
Davis Besse Nuclear Fower Station 1WX Annual Environmental Operating Report a e There must be corrosion protection, monthly release detection, and overfill prevention for the 2,000 gallon waste oil tank by December 22, 1998. In 1990, the two 40,000 gallon and the 8,000 gallon diesel fuel storage tanks be-came exempt from these regulations by virtue of being part of an emergency gen-erating system at a nuclear power station. Ilowever, there are regulations that do apply for responding to a tank or piping leak greater than 25 gallons and for corrective action to clean up such a spill. Fuel Storage T6nks At Serv 6ce BuMing #4 Permanent gasoline storage tanks were constructed at Service Building #4, Mc-bile Central at Senice Building #4 provides vehicle repair and senice. Having a fuel supply at this location eliminates the inconveniences of the previous tempo-rary fuel storage facility at the station warehouse. l The gasoline storage tanks are constructed inside a diked concrete structure to collect any spilled fuels and to reduce any emironmenlealimpact should a spill occur. 100,000 Gallon Diesel oel Oil Storage Tank A spill control dike was constructed in front of the pump house for the 100,000 gallon diesel fuel oil storage tank. This dike was constructed to ensure contain-ment of drips, leaks and small spills during refueling operations. Fire Training Area Modification in response to an independent Chemical Risk Assessment Audit performed at the Davis Besse site, Emironmental Compliance recommended that the fire protection training area be upgraded to reduce the potential of adverse environ-mental impact due to training activities or potential spills. Enviror. mental Compliance recommended that a diked concrete pad with a catch basin be installed. The catch basin would collect wastes preventing contam. ination of surrounding soils and possibly groundwater supplies. Wastes are peri-odically pumped out of the catch basin and properly disposed of. When the training area is not in use, a waterproof cover prevents accumulation of rairvsnow thereby minimizing the amount of contarninated wastes. Bum Permits As required by the EPA under the Clean Air Act, burn permits for Davis Besse were submitted for approval. The Station has a small area onsite for training em-8 10
i l 1 Annual Environmentat operating Report 1990 Davis Besse Nuclear Power Station ployees on proper fire fighting techniques. Most instruction is on the proper use of a fire extinguisher. A burn permit is submitted every three months to re. l
- main in compliance with the Ohio EPA regulations.
Split contiof Kits l i Fifty five gallon drums containing protective equipment and spill control equip-ment are maintained throughout the Station at chemical storage areas. Equip-ment in the kits includes such items as waterproof coveralls, gloves, absorbent , cloth, goggles and warning signs. The spill kits are strategically placed through-out the Station to allow for fast and easy response in the event of a chemical or
- oil spill.
Testing of Weste Oil The majority of waste oil generated at Davis Besse is not disposed of, but is re-moved to a recycling facility for thermal energy recovery. Before removal for re-cycling. the oil is tested to determine that it is nonhazardous. Waste oil that contains less than 1000 parts per million of halogens and has a flash point above U 140 F is considered to be nonhazardous waste. This testing minimizes waste due to the fact that the nonhazardous waste oil is recyclable. Also, disposal cost is I minimized due to the lower cost of waste oil recycling than hazardous waste dis. . posal. Weste inwrtory Forme Inventory forms placed on waste accumulation drums allow employees to record l the waste type and amount as it is added to the drum. This ensures that in-compatible wastes are not mixed and also identifies the drum contents for proper disposal. It also ensures that nonhazardous waste is not mixed with hazardous waste. This eliminates the possibility ofincreasing the volume and number of containers of hazardous waste and increasing disposal costs, Chemical Approwl The Controlled Materials Program at Davis Besse was developed to review and approve chemicals and products before they are put to use at the Station. Chem-
' icals and products that cannot be disposed of easily are either deleted or re-placed with a less hazardous substitute to eliminate the problem of waste disposal at a later date.
8 11
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Annual Environmental Operating Report 17X) Davis Besse Nuclear Power Station APPENDIX A - GLOSSARY A-1
Annual Environmental Operating Report 1990 Davis Besso Nuclear Power Station a Glossary A absorbed dose The amount of radiation energy absorbed by any material exposed to ionizing radiation. activation products Radioactivity that is created when stable substances are bombarded by ionizing radiation. AIARA Acronym for "As Low As Reasonably Achievable," a basic concept of radiation protection that specifies radioactive discharges from nuclear plants and radiation exposure to personnel be kept as far below regulatory limits as possible. alpha particle A positively charged particle ejected from the nuclei of some radioactive elements,it is identical to a helium nucleus, and has a mass number of 4 and a charge of + 2. It has low penetrating power and short range. Alpha particles are easily stopped by a thin layer of paper or fabric, or the dead outer layer of skin cells, atom The smallest portion of an element that shares the general characteristics of that element and cannot be divided or broken up by chemical means. An atom has a nucleus, composed of positively charged protons and electrically neutral neutrons, around which orbit negatively charged electrons. L atomic number The number of protons in the nucleus of an atom. A2
Davis Besse Nuclear Power Station 1930 Annual Environmental Operating Peport i atomic weight The number of neutrons and protons in the nucleus of an atom. For example, a carbon atom has 6 neutrons and o protons, so its atomic w eight is 12. B background radiation The radiation in man's environment, including cosmic rays from space and radiation that exists everywhere in the air,in the earth, and in man made materials that surround us, in the United States, most people receive 100 to 250 millitem of background radiation per year. Common sources of man made background radiation include consumer products such as color televisions, radium dials on watches or clocks, smoke detectors, ccast to coast jet fllghts, construction material 3 and certain foods, beta particle A charged particle emitted from a nucleus during radioactive decay, with a mass equal to 1/1837 that of a proton. A negatively charged beta particle is identical to an electron. A positively charged beta particle is called a positron. Deta particles are easily stopped by a thin sheet of metal, plastic or wood. borated water Water containing the element baron, used to cool the reactor core in the event of a Loss Of Coolant Accident. Borated water can be sprayed inside the containment building, thus protecting the stnicture from overpressurization by condensing any steam released through any leaks in tM Reactor Coolant System. Borated water can also be flushed into the reactor vessel.The baron in the water actually absorbs free neutrons, thus removing the catalysts required to drive the nuclear fission process. A3
Annual Enwonmental Operating Report 1990 Daws.Besse Nuclear Power Station C calibrate To standardize a measuring instrument, such as the anemometer used to measure wind speed, by determining its deviation from a standard. Tl.e deviation determined allows one to apply a correction factor to a measured value, to yield the true value, chain reaction A reaction that stimulates its own repetition. In a fission chain reaction, a fissionable nucleus absorbs a neutron and fissions, releasing additional neutrons which perpetuate the fission reaction in the nuclei of neighboring atoms. charged particle An ion. An elementary particle carrying a positive or negative electric charge. cladding The thin walled tube of zirconium alloy that forms the outer Jacket of a fuel rod. The claddirg is highly resistant to heat, corrosion and radiation, and comprises the first barrier to the release of fission products, composite sample A sample made of grab or continuous samples combined to represent a particular location or a set period of time. (e.g., four weekly water samples combined to make one monthly composite sample), containment A steelliner inside the concrete shield building. Designed vessel to isolate the primary system from the environment and other station systems. , continuous sample A continuous sample is one that collects samples non stop and is used to evaluate conditions over a specific period of time.The typical continuous sarnples collected at Davis Besse include TLDs and air samples. control location A sample collection location generally more than 5 miles away from Davis Besse. Analyses of samples collected at control locations provide information on A4
Davis Besse Nuclear Power Station : 1990 Annual Environrnental Operating Report , normally occurring background radiation and radioactivity, control rod ' A rod containing material such as hafnium or boron, used to control the power of a nuclear reactor. By absorbing neutrons, control rods slow down andi eventually stop the fission process.
.: coolant : A Guid, usually water, used to cool the nuclear ,
reactor core by transferring the heat energy emitted . ; l during the fission process into the Guid medium. cooling tower - Essentially a chimney, designed to create a natural draft. Cool air enters the base of the tower,is drawn upward , through the hollow tower interior and exits the top. At the same time, warm water used to cool the turbine is showered on to a series of bafnes inside the cooling tower. As the water strikes the bafiles,it is cooled by the process of evaporation. coriolis force ' An apparent denective force that develops due to the , earth's rotation.When any mass travels above the earth's , surface, the coriolis force appears to deneet the mass L to the right in the Northern Hemisphere and to the left in the Southern Hemisphere. cosmic radiation Penetrating ionizing radiation, both particulate and
- electromagnetic, that originates in space. >
critical group The segment of the population that could receive -
'I
-the greatest radiation dose,
" critical organ The body organ receiving a radiation dose that could result l in the greatest overall effect.
l} ' critical pathway The exposure pathway that will provide, for a given 4
- radionuclide, the greatest radiation dose to a population,-
- or to a specific segment of the population.- ,
. curie (Cl) The basic unit used to describe the intensity of radioactivity in a sample or material. One curie is equal to 37 billion disintegrations per second, which l
A5
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station is approximately the rate of decay of one gram of radium. A curie is also a quantity of any radionuclide that decays at a rate of 37 billion disintegrations per second. D daughter products isotopes that are formed by the radioactive decay of other radionuclides. In the case of radium 226, there are 10 successive daughter products, ending in the stable isotope lead 206. decay series A radioactive sequence which an unstable element goes through before reaching a stable state; it usually involves the loss or gain of energy and/or matter. decommissioning The process of dismantling a nuclear power station, e decontaminating any radioactive parts, and storing or disposing of these parts.This process will begin at the end of the reactors' usefullife, normally after 40 years of operation. difTerential Air temperature at one level, minus air temperature temperature at another level. Also called delta T. dike A retaining structure designed to hold back water for flood control. dissolved solids Solids incapable of removal through physical means, e.g., via filtration. An example of a dissolved solid is a small amount of table salt dissolved in a glass of water. dose A quantity (total or accumulated) of ionizing radiation received, dose rate The radiation dose delivered per unit of time. Measured, for example, in rem per hour. 4 A6
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report 1 1 E ellluent in general, a waste material, such as smoke, liquid, industrial refuse, or sewage discharged into the environment. Effluents discharged from the Davis Besse Nuclear Power Station include liquid and gaseous media containing extremely small concentrations of radionuclides. The concentrations released are well below the limits established by the NRC. electromagnetic A travelling wave motion resulting from radiation changing electric or magnetic fields. Familiar electromagnetic radiations range from X rays (and gamma rays) of short wavelength, through the ultraviMet, visible, and infrared regions, to radar and radiowaves of relatively long wavelength, electron An elementary particle with a negative charge and a mass 1/1837 that of the proton. Electrons orbit arround the positively charged nucleus. In an electrically neutral atom, the negative charges of the electrons are balanced by the positive charges of the protons. element One of the 103 known chemical substances that cannot be broken down further without changing its chemical properties. Some examples include carbon, hydrogen, nitrogen, gold, lead, and uranium, enrichment The process ofincreasing the concentration of the fissionable isotope uranium 235 relative to concentrations present in natural uranium ore. Eariched fuelis more capable of sustaining a chain reaction, and is therefore a more economical fuel source for a nuclear power station. The uranium fuel used at Davis-Besse has been enriched approximately 3%. In comparison, the uranium fuel used in nuclear weaponry has been enriched over 90%. exposure The absorption of radiation or ingestion of a radionuclide. Acute exposure is generally accepted to be a large exposure received over a short A7
Annual Snvironmental Operatng Report 1990 Davis Besse Nuclear Power Station I period of time. Chronic exposure is low level exposure received during a lifetime or over a long period of time, external radiation Exposure to ionizing radiation when the radiation source is located outside of the body. F nssion The splitting or breaking apart of a hean atom into two or more fragments. When a heavy atom such as uranium is split,large amounts of energy in the form of heat, radiation, and one or more neutrons are released. fission gases Those fission products that exist in the gaseous state. Primarily the noble gases (krypton, xenon, radon, etc.), fission products The nuclei (fission fragments) formed by the fission of heavy elements, plus the nuclides formed by the fragments' radioactive decay, fuel assembly A cluster of fuel rods. Also called a fuel element. Many fuel assemblies make up a reactor core. The reactor core at the Davis Besse Station contains 177 fuel assemblies, each assembly containing 208 fuel rods. The combined weight of the reactor core is 207,486 pounds. fuel pellet A small ceramic capsule containing fissionable material, generally powdered uranium dioxide (UO2), fuel rod Contains approximately five pounds of nuclear fuel pellets stacked inside a thin walled tube (cladding) of zirconium alloy. l A8
Davis Besse Nuclear Power Station 1990 Annual Environmental Operating Report lr G gamma ray High energy, short wavelength electromagnetic radiation emitted from the nucleus of a radioactive atom. Gamma radiation frequently accompanies alpha and beta emissions and always accompanies fission, Gamma rays are very penetrating but may be shielded by dense materials, such as lead or concrete, Gamma rays are similiar to X rays, but are usually more energetic, grab samples A grab sample represents a single sample collected in finite period of time. H half life The time in which half the atoms of a particular radioactive substance disintegrate to another nuclear form. Measured half lives vary from millionths of a second to billions of years. I indicator location A sample collection location generally within 5 miles of Davis Besse Analyses from samples collected at indicator locations provide information on the radiological impact,if any, Davis Besse has on the surrounding environment, internal radiation Nuclear radiation resulting from radioactive substances in the body. Some examples are iodine 131 deposited in the thyroid gland, and strontium 90 and plutonium 239 deposited in bone tissue. A9
Annual Enwonmental Operating Report 1990 Davis Besse Nuclear Power Station ion An atom that carries a positive or negative electric charge as a result of having lost or gained one or more electrons. May also refer to a free electron, i.e., an electron that is not associated (in orbit) with a nucleus. ionization The process of adding one or more electrons to, or removing one or more electrons from, atoms or molecules, thereby creating ions. High temperatures, ! electrical discharges, or ionizing (atomic) radiation may cause ionization, ionizing radiation Any radiation capable of displacing electrons from atoms or molecules, thereby producing ions. l For example, alpha and beta particles, gamma and X rap, l neutrons, and ultraviolet light. . 1 isotope One o.f two or more atoms with the same number of l protons, but different numbers of neutrons in their nuclei. Thus, carbon 12, carbon 13, and carbon 14 are isotopes of the element carbon; the numbers denoting their approximate atomic weights. Isotopes have the same chemical properties, but often different physical properties (for example, carbon-12 and carbon 13 are stable, while carbon-14 is radioactive). JKL lower limit The smallest amount of sample activity that will give of detection a net count, for which there is a confidence at a (LLD) predetermined level, that the activity is present. The LLD is actually a measure of the ability of an individual analysis to detect extremely minute amounts of radioactivity in a sample.
- l A 10
Davis Besse Nuclea' Power Station 1990 Annual Environmental Operating Repon M mean Arithmetic average in a series of 3 or more numbers, the mean is calculated by the equation: x = x 1 + x2 + . . xn n where n is the number of observations in a data set,and x1, x2, ... xn are the various observations, micro. A prefix that divides a basic unit by one million. microcurie One millionth of a curie. milli- A prefix that divides a basic unit by one thousand, millirem One thousandth of a rem. N 'l neutron An uncharged elementary particle with a mass slightly greater than that of a proton, and found in the nucleus of every atom heavier than hydrogen l. noble gas A gaseous chemical element that does not readily enter into chemical combination with other elements. An inert gas such as krypton, xenon, neon or argon. nucleus The central, positively charged region of an atom that nuclei (plural) contains essentially all of the mass of that atom. Except for the nucleus of ordinary hydrogen, which has a single proton, all atomic nuclei contain both protons and neutrons. The number of protons determines the total positive charge, or atomic number; this is the same for all the isotopes of a given chemical element. The total number of neutrons and protons is called the mass number. 4 A 11
' Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station nuclide A general term referring to all known isotopes, both stable (279) and unstable (about 5000), of the chemical elements. OP pico. A prefix that divides a basic unit by one trillion. picoeurie One trillionth of a curie. primary loop A closed system of piping which provides cooling water to the reactor and transfers heat energy to a second closed system, the secondary loop. proton An elementary particle that, carries a positive charge and has a mass of 1.67 x 10 " gram. QR , quality assurance All the planned and systematic actions that are necessary (QA) to provide adequate confidence in the results of an activity. quality control The field check or verification of work while it is being (QC) performed to assure that the task is properly done. quality factor The factor by which the absorbed dose is multiplied to obtain a quantity that expresses, on a common scale for all ionizing radiation (rem), the potential for biological damage to exposed persons. rad An acronym for" radiation absorbed dose". The basic unit of absorbed dose of radiation. One rad equals s' absorption of 100 ergs (a small but measureabl; mount of energy) per gram of absorbing material. A-12
m . . .. . . . .. Davis Besse Nuclear Power Station 1990 Anr aa! Environmental Operating Report I radiation The conveyance of energy through space, for example, the radiation of heat from a stove, lonizing radiation is the emission of particles or gamma rays from the nucleus of an unstable (radioactive) atom as a result of radioactive decay, radioactise Radioactive materialin an undesirable location. contamination Contamination can be loose on surfaces, fixed on surfaces (soaked or ground into), or airborne, radioactive decay The decrease in the amount of radioactivity with the passage of time due to the spontaneous emission of particulate or gamma radiation from the atomic nuclei, radioactivity The spontaneous emission of radiation from the nucleus of an unstable isotope, Radioactivity is a process and radiation is the product. radiolodine A radioactive isotope of iodine.The radioisotopes of iodine are among the most abundant of the fission products. All told,27 isotopes of iodine are known to exist , but only the naturally-occurring iodine 127 is stable. Of the remaining 26 radioisotopes.12 are produced during fission and these have half lives ranging from 1.5 seconds to 16 million years. radioisotope The term " radioisotope" is used to specifically describe the relationship between an element and a radioactive isotope of that element. For instance,in describing Cs-137, one could state that Cs 137 is a radioisotope of cesium (stable). radionuclide A radioactive isotope, reaction Any process involving a chemical or nuclear change. reactor trip A sudden shutting down of a nuclear reactor, usually by rapid insertion of control rods, either automatically or manually by the reactor operator, sometimes called a scram. A 13
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station rem Acronym for " roentgen equivalent man". The unit of dose of any ionizing radiation that produces the same biological effect as a unit of absorbed dose of X-rays. revetment A retaining structure designed to hold back water for purposes of erosion control. Inherent in the design a layer of rocks, concrete blocks, etc., laid over a nylon mesh mat to form a gradual slope that extends wellinto the water revetments actually encourage beach fctmation by passive deposition of particulate matter along the base of the structure, roentgen A unit of exposure to ionizing radiation. It is that amount of gamma or X rays required to produce ions carrying one electrostatic unit of electrical charge in one cubic meter of dry air at standard temperature and pressure. S, secondary A closed piping system that absorbs heat from water in loop the primary loop via convection through the steam generator tubes. As water in the secondary loop heats, it boils and becomes the steam used to spin the turbines to produce an electric current. shield building A specially designed concrete building which surrounds the containment vessel. Its purpose is to protect the containment vessel from environmental extremes, and to provide a negative pressure boundary between the containment vessel and the environment. shielding Any material or obstruction that absorbs radiation and thus tends to protect personnel or materials from the effects of ionizing radiation, spent fuel Nuclear reactor fuel that has been used to the extent that it can no longer effectively sustain a chain reaction. l I A 14
- d. .I..... . . , , . . . , , , , . .. . . . , , . .
Davis Besse Nuclear Power S'stion 1990 Annual Environmental Ocerating Report spiked sample A sample that has been intentionally contaminated with a known concentration of some radionuclide. Subsequent testing of the sample should indicate concentrations at least as high as the introduced concentration. Spiked sample analyses prc, vide a quality control check on the "alidity of the analyses performed at the laboratory, steam generator A piece of equipment used to transfer heat from the primary system (reactor coolant) to the secondary (steam) system, without the water of the two systems actually touching. This design permits heat exchange with little or no contamination of the secondary system equipment. suspended solids Solids capable of removal through a filter such as a screen. An example of a suspended solid is silt present in lake or river water that giver he water a cloudy appearance. The silt is easily removed by passing the water through a filter. T Technical Specifica. tions (Tech Specs) A part of the operating license for any nuclear facility issued by the Nuclear Regulatory Commission (NRC), the Tech. Specs delineate the requirements the facility must meet in order to maintain its operating license. For example, the Tech Specs for Davis-Besse provide detailed information on the types, collection sites, frequencies, and analyses to be performed on samples collected as part of the Radiological Environmental Monitoring Program, terrestrial radiation The portion of natural radiation (background) that is emitted by naturally occurring radioactive materials in the earth, tertiary loop The steam in the secondary loop used to drive the turbine generator is condensed,i.e., cooled to a liquid form, by transferring its heat to a third loop system, the i A !5
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station tertiary loop. Also called the circulating water system, the nonradioactive water in this system carries heat from the condenser to the cooling tower; the heat is lost to the atmosphere via evaporative cooling. tritium A radioactive isotope of hydrogen (one proton, two neutrons). Because it is chemically identical to natural hydrogen, tritium can easily be taken into the body by any ingestion path. Tritium decays by beta emission. Its radioactive half life is about 121/2 years. UVW wind rose A graph representing the percent of time that the wind blew from a particular direction and the average speed of the wind from that direction, whole body exposure An exposure of the body to radiation,in which the entire body rather than an isolated part is irradiated. Where a radioisotope is uniformly distributed throughout the body tissues, rather than being concentrated in certain parts, the irradiation can be considered as a whole body exposure. XYZ X rays Penetrating electromagnetic radiation (photon) having a wavelength that is much shorter than that of visible light. In nuclear reactions,it is customary to refer to photons originating in the nucleus as gamma rays, and to those originating in the electron field of the atom as X rays. A 16
Annual Environmental Operating Report 1990 Davis Besse Nuclear Power Station APPENDIXB - Interlaboratory Comparison Program 3-1
Appendix B Interlaboratory Comoarison program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The pu provide an independent check on the laboratory,rpose of such 5 analytical a program procedures andistoto alert it to any possible problems. Participant laboratories measure the concentrttions of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. The results in Table B-1 were obtained through participation in the anviron-mental sample crosscheck program for milk, water, air filters, and food samples during the period January 1986 through December,1990. This program has been conducted by the U.S. Environmental Protection Agency Intercompari son and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada. The results in Table B-2 were obtained for thermoluminescent dosimeters (TLDs) during the period 1976,1977,1979,1980,1984, and 1985-1985 through partici-pation in the Second, Third, Fourth, Fifth, Seventh, and Eighth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table B-2. Also Teledyne testing results are listed. Table B-3 lists results of the analyses on in-house spiked samples. Table B-4 lists results of the analyses on in-house " blank" samples. Attachment B lists acceptance criteria for " spiked" samples. Addendum to Appendix B provides explanation for out-of-limit results. B-2
Table B-1 U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples,1986 through 1990.a Concentration in pCi/Lb i EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22 cc Is, N=1 Limits STF-447 Food Jan 1986 Sr-89 24.322.5 25.025.0 16.3-33.7 Sr-90 17.320.6 10.021.5 7.4-12.6 1-131 22.722.3 20.0 0.6 9.6-30.4 Cs-137 16.320.6 15.025.0 6.3-23.7 K 92746 9501144 701-1199 ST W-448 Water Feb 1986 Cr-51 45.023.6 38.025.0 29.3-46.7 Co-60 19.711.5 18.0:5.0 9.3-26.7 Zn-65 44.023.5 40.025.0 31.3-48 .7 Ru-106 (9.0 0.025.0 0.0-8.7 Cs-134 28.322.3 30.025.0 21.3-38.7 Cs-137 23.7:0.6 22.025.0 13.3-30.7 STW-449 Water Feb 1986 H-3 5176:48 5227:525 4317-6137 STW-450 Water Feb 1986 V total 8.020.0 9.026.0 0.0-19.4 STM-451 Mil k Feb 1986 1-131 7.020.0 9.026.0 0.0-19.4 STW-452 Water Mar 1986 Ra-226 3.8 0.1 4.120.6 3.0-5.2 Ra-228 11.020.5 12.421.8 9.2-15.5 STW-453 Water Mar 1986 Gr. al pha 6.720.6 15.025.0 6.3-23.7 Gr. beta 7.320.6 8.025.0 0.0-16.7 STW-454 Water Apr 1986 1-131 7.0 :0.0 9.026.0 0.0-19.4 STW-455 Wat er Apr 1986
, 456 (Blind)
Sample A Gr. alpha 15.021.0 17.025.0 8.3-25.7 Ra-226 3.120.1 2.920.4 2.1-3.7 Ra-228 1.5:0,2 2.020.3 1.5-2.5 Uranium 4.720.6 5.026.0 0.0-15.4 Sample B Gr. beta 28,721.2 35.025.0 26.3 43.7 Sr-89 5.720.6 7.025.0 0.0 15.7 Sr-90 7.020.0 7.021.5 4.4-9.6 Co-60 10.7:1.5 10.025.0 1.3-18.7 Cs-134 4.021.7 5.025.0 0.0-13.7 Cs-137 5.3 0.6 5.0:5.0 0.0-13.7 B-3
Table B-1 (continued) Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22cc Is, N=1 Limits STAF -457 Air Apr 1986 Gr. alpha 13.7:0.6 15.0:5.0 6.3-23.7 Filter Gr. beta 46.320.6 47.025.0 38.3-55.7 Sr-90 14.720.6 18.021.5 15.4-20.6 Cs-137 10.720.6 10.025.0 1.3-18.7 STU-458 Urine Apr 1986 Tritium 4313270 4423:189 4096-4750 STW-459 Water May 1986 Sr-89 4.320.6 5.015.0 0.0-13.7 Sr-90 5.020.0 5.021.5 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.320.6 8.015.0 0.0-16.7 Gr. beta 11 .311.2 15.025.0 6.3-23.7 STW-461 Water Jun 1986 Cr-51 (9.0 0.025.0 0.0-8,7 Co-60 66.021.0 66.025.0 57.3-74 .7 Zn-65 87 .3 1 .5 86.025.0 77.3-94.7 Ru-106 39.722.5 50.025.0 41.3-58.7 Cs-134 49.322.5 49.0:5.0 40.3-57.7 Cs-137 10.321.5 10.015.0 1.3-18.7-Jun 1986 Tritium 3427225 3125:361 2499-3751 STW-462 Water STM-464 Mil k Jun 1986 Sr-89 <1.0 0.0 5.0 0.0-8.7 Sr-90 15.3 0.6 16.021.5 13.4-18.6 1-131 48.312.3 41.026.0 30.5-51 .4 Cs-137 43.7 1.5 31.015.0 22.3-39.7 K 1567 114 1600280 1461-1739 STW-465 Water Jul 1986 Gr. alpha 4.720.6 6.025.0 0.0-14.7 Gr. beta 18.721.2 18.025.0 9.3-26.7 STW-467 Water Aug 1986 1-131 30.320.6 45.026.0 34.4-55.4 STW-468 Water Aug 1986 Pu-239 11.320.6 10.121.0 8.3 11.9 STW-469 Water Aug 1986 Uranium 4.020.0 4.016.0 0.0-14.4 Sep 1986 Gr. alpha 19.321.5 22.025.0 13.3-30 .7 STAF-470 Air 57.3-74 .7 471 Filter Gr. beta 64.022.6 66.025.0 Sr-90 22.021.0 22.025.0 19.4-24 .6 472 Cs-137 25.721.5 22.015.0 13 .3-3 0 .7' Sep 1986 Ra-226 6.0:0.1 6.120.9 4.5-7.7 STW-473 Water Ra-228 8.7 1.1 9.1 ' .4 6.7-11 .5 B-4
Table B-1 (cont'1ued) Concentration in pC1/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 2cc is, N=1 Limits STW-474 Water Sep 1986 Gr. alpha 16.3:3.2 15.025.0 6.3-23.7 Gr. beta 9.021.0 8.025.0 0.0-16.7 STW-475 Water Oct 1986 Cr-51 63.325.5 59.025.0 50.3-67.7 Co-60 31.0:2.0 31.025.0 22.3-39.7 Zn-657 87.315.9 85.015.0 76.3-93.7 Re-106 74.727.4 74.0:5.0 65.3-82.7 Cs-134 15.7 0.6 28.0:5.0 19.3-36.7 C -137 46.321.5 44.025.0 35.3-52.7 STW-476 Water Oct 1986 H-S 5918:60 5973 597 4938-7008 SPW-477 Water Oct 1986 (Blino) Senple A Gr. alpha 34.026.0 40.025.0 31.3-48.7 Ra-226 5.820.2 6.0:0.9 4.4-7.6 Ra-228 2.721.0 5.020.8 3.7-6.3 Uranium 11.020.0 10.026.0 0.0-20.4 Sample B Gr. beta 38.7:1.2 51.025.0 42.3-59.7 Sr-89 5.020.0 10.025.0 1.3-18.7 3r-90 3.0:0.0 4.0:1.5 1.4-6.6 Co-60 24.7:1.2 24.025.0 15.3-32.7 Cs-134 11.0:2.0 12.025.0 3.3-20.7 Cs-137 9.321.2 8.0 5.0 0.0-20.4 STM-479 Milk Nov 1986 Sr-89 7.721.2 9.025.0 0.3-17.7 Sr-90 1.0:0.0 0.0:1.5 0.0-2.6 1-131 52.3 3.1 49.026.0 38.6-59.4 Cs-137 45.7:3.1 39.0:5.0 30.3-47.7 K 14892104 1565:78 1430-1700 STU-480 Urine Nov 1986 H-3 5540:26 5257:912 4345-6169 STW-481 Water Nov 1986 Gr. alpha 12.04.0 20.0:5.0 11.3-28.7 Gr. beta 20.0:3.5 20.0 5.0 11.3-28.7 STW-482 water Dec 1986 Ra-226 6.7t0.2 6.8:1.0 5.0-8.6 Ra-228 5.2:0.2 11.121.7 8.2-14.0 STW-483 Water Jan 1987 Sr-89 19.725.0 25.0:5.0 16.3-33.7 Sr-90 21.0:2.0 25.021.5 22.4-27.6 B-5
^ --
i Table B-1 (continued) Concentration in pCi/L b EPA Resultd TIML Result Control Lab Sample Date Limits Anal ysi s 22 cc 15, Nel Code Type Collected Pu-239 17.022.3 16.721.7 13.8-19.6 STW-484 Water Jan 1987 Sr-90 36.024.0 49.0210.0 31 .7-66 .3 STF-486 Food Jan 1987 64.1-91.9 1-131 78.0 3.4 78.028.0 Cs-137 89.723.0 84.025.0 75.3-92.7 K 942:56 980249 895-1065 Jan 1987 Sr-90 2.020.0 - - - STF -487 Food - - - 1-131 <3 (Blank) C5-137 <2 K 993:102 Co-60 49.0 0.0 50.025.0 41.3-58.7 STW-488 Water Feb 1987 82.3-99.7
, Zn-65 96 ^27.2 91.0:5.0
' Ru-106 92.0:20.2 100.025.0 91.3-108.7 Cs-134 53.023.4 59.015.0 50.3-67.7 C5-137 89.324.6 87.0 5.0 78.3-95.7 4130:140 4209:420 3479 4939 Water Feb 1987 H-3 STW-489 Uranium 8.321.2 8.026.0 0.0-18 d STW-490 Water Feb 1987 1-131 10.0 0.0 9.0:0.9 7.4-10.6 STM-491 Mil k Feb 1987 Gr. alpha 3.721.2 3.0:5.0 0.0-11.7 STW-492 Water Mar 1987 4.3-21.7 Gr. beta 11 .3:1.2 13.015.0 Ra-226 7.020.1 7.321.1 5.4-9.2 STW-493 Water Mar 1987 5.5-9.5 Ra-228 7.1:2.3 7.5 1.1 1-131 8.020.0 7.0:0.7 5.8-8.2 STW-494 Water Apr 1987 Gr. alpha 15.020.0 14.025.0 5.3-22.7 STAF-495 Air Apr 1987 34.3-51.7 Gr. beta 41 .022.0 43.025.0 Filter 16.321.2 17.0 1.5 14 .4-19 .6 S r-90 7.0 0.0 8.025.0 0.0-16.7 Cs-137 STW-496 Water Apr 1987 497 (Blind)
Gr. alpha 30.7 1.2 30.028.0 16.1-43.9 Sample A 3.9:0,2 3.90.6 2.9-4.9 Ra-226 Ra-228 4.9:0.9 4.020.6 3.0-5.0 l Uranium 5.0:0.0 5.026.0 0.0-15.4 a B-6
Table B-1 (continued) Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22ec 15, N=1 L imits STW-496 Water Apr 1987 497 (Blind) Sample B Gr. beta 69.319.4 66.025.0 57.3-74.7 Sr-89 16.3:3.0 19.025.0 10.3-27.7 Sr-90 10.020.0 10.021.5 7.4-12.6 Co-60 8.323.0 8.0 5.0 0.0-16.7 Cs-134 19.0:2.0 20.015.0 11.3-28.7 Cs 137 14.721.2 15.015.0 6.3-23.7 STU-498 Urine Apr 1987 H-3 6017:494 56202795 4647-6593 STW-499 Water May 1987 S r-89 38.026.0 41.025.0 32.3-49,7 S r-90 21.022.0 20.0:1.5 17.4-22.6 STW-500 Water May 1987 Gr. alpha 9.023.4 11.0:5.0 2.3-19.7 Gr. beta 10.321.2 7.025.0 0.0-15.7 STW-501 Water Jun 1987 Cr-51 40.028.0 41.025.0 32.3-49 .7 Co-60 60.323.0 64.025.0 55.3-72.7 i Zn-65 11.325.0 10.025.0 1,3-18.7 i Ru-106 78.326.4 75.025.0 66.3-83.7 ) Cs-134 36.723.0 40.025.0 31.3-48.7 Cs-137 80.3:4.2 80.0:5.0 71 .3-88 .7 STW-502 Water Jun 1987 H-3 2906:S6 2895:357 2277-3513 STW-503 Water Jun 1987 Ra-226 6.920.1 7.3 1.1 5.4-9.2 R a-228 13.3 1.0 15.222.3 11.2-19.2 1 STM-504 Mil k Jun 1987 S r-89 57.024.3 69.025.0 60.3-77.7 l Sr-90 32.021.0 35.025.0 32.4-37.6 I-131 64.022.0 59.026.0 48.6-69.4 Cs-137 77.720.6 74.0 5.0 65.3-82.7 K 1383217 1525:76 1393-1657 STW-505 Water Jul 1987 Gr. alpha 2.320.7 5.025.0 0.0-13.7 Gr. beta 4.021.0 5.025.0 0.0-13.7 STF -506 Food Jul 1987 I-131 82.724.6 80.028.0 66.1-93.9 Cs-137 53.723.0 50.025.0 41.3-58.7 i K 1548:57 1680284 1534-1826 ' STW-507 Water Aug 1987 I-131 45.724.2 48.026.0 37.6-58.4 I B-7 l
Table B-1 (continued) Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysi s 22cc Is, N=1 Limits STW-508 Water Aug 1987 Pu-239 5.820.2 5.320.5 4.4 6.2 STW-509 Water Aug 1987 Uranium 13.3 0.3 13.026.0 2.6-23.4 STAF-510 Air Aug 1987 Gr. alpha 9.7 0.4 10.0:5.0 1.3-18.7 Filter Gr. beta 28.3 0.6 30.0 5.0 21.3-38.7 Sr-90 10.020.9 10.021.5 7.4-12.6 Cs-137 10.021.0 10.025.0 1.3-18.7 STW-511 Water Sep 1987 Ra-226 9.920.1 9.7:1.5 7.2-12.2 Ra-228 8.121.4 6.321.0 4.6-8.0 STW-512 Water Sep 1987 Gr. alpha 2.0:0.6 4.0 5.0 0.0-12.7 Gr. beta 11.3 1.3 12.0:5.0 3.3-20.7 STW-513 Water Sep 1987 H-3 44732100 4492:44 9 3714-5270 STW-514 Water Oct 1987 (811nd) Sample A Gr. alpha 29.3 2.6 28.027.0 15.9-40.1 Ra-226 4.9t0.1 4.820.7 3.6-6.1 Ra-228 4.211.0 3.6:0.5 2.7-4,5 Uranium 3.0:0.1 3.026.0 0.0-13.4 Sample B Sr-89 14.3:1.3 16.0:5.0 7.3-24.7 < Sr-90 9.7:0.4 10.021.5 7.4-12.6 Co-60 16.7:3.0 16.025.0 7.3-24.7 Cs-134 16.722.3 16.025.0 7.3-24.7 Cs-137 24.323.3 24.0:5.0 15.3-32.7 STW-516 Water Oct 1987 Cr-51 80.3:17.5 70.025.0 61.3-78.7 Co-60 16.0 2.3 15.0 5.0 6.3-23.7 Sample A Zn-65 46.3:5.6 46.025.0 37.3-54.7 Ru-106 57.3 15.4 61.025.0 52.3-69.7 Cs-134 23.722.5 25.0 5.0 16.3-33.7 Cs-137 51.723.2 51.0:5.0 42.3-59.7 STU-517 Urine Nov 1987 H-3 72672100 74322743 6145-8719 STW-518 Water Nov 1987 Gr. alpha 3.022.0 7.025.0 0.0-15.7 Gr. beta 15.722.3 19.025.0 10.3-27 .7 STW-519 Water Dec 1987 ' 131
- 26.0:3.0 25.026.0 15.6-36.4 B-8
Table B-1 (continued) Concentration in pCi/LD EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22cc Is, N=1 Limits STW-520 Wat er Dec 1987 Ra-226 5.120.8 4.820.7 3.6-6.0 Ra-228 3.4:0,1 5.310.8 3.9-6.7 STW-521 Water Jan 1988 Sr-89 27.325.0 30.015.0 21.3-38.7 Sr-90 15.3:1.2 15.021.5 12.4-17.6 STW-523 Water Jan 1988 Gr. alpha 2.321.2 4.015.0 0.0-12.7 Gr. beta 7.7:1.2 8.025.0 0.0-16.7 STF-524 Food Jan 1988 Sr-89 44 .024.0 46.015.0 37.3-54.7 Sr-90 53.012,0 55.0 2.8 50.2-59.8 1-131 102.314.2 102.0210.2 84.3-119.7 Cs-137 95.716.4 91.0 5.0 82.3-99.7 K 1011:158 1230162 1124-1336 STW-525 Water Feb 1988 Co-60 69.312.3 69.025.0 60.3-77.7 Zn-65 99.023.4 94.019.4 77.7-110.3 Ru-106 92.7:14.4 105.0:10.5 36.8-123.2 Cs-134 61.718.0 64.025.0 55.3-72.7 Cs-137 99.723.0 94.025.0 85.3-102.7 Water Feb 1988 H-3 34532103 3327:362 2700-3954 STW-526 STW-527 Water Feb 1988 Uranium 3.0:0,0 3.026.0 0.0-13.4 STM-528 Mil k Feb 1988 1-131 4.7:1.2 4.0 0.4 3.3-4.7 STW-529 Water Mar 1988 Ra-226 7.1 0.6 7.6:1.1 5.6-9.6 Ra-228 RAe 7.7:1.2 5.7-9.7 STW-530 Water Mar 1988 Gr. alpha 4.321.2 6.0:5.0 0.0-14.7 Gr. beta 13.321.3 13.025.0 4.3-21.7 STAF-531 Air Mar 1988 Gr. alpha 21.022.0 20.025.0 11.3-28.7 Filter Gr. beta ?8.020.0 50.015.0 41.3-58.7 Sr-90 16.7:1.2 17.021.5 14.4-19.6 Cs-137 18.7:1.3 16.025.0 7.3-24.7 STW-532 Water Apr 1988 1-131 9.022.0 7.5 0.8 6.2-8.8 B-9
Table B-1 (continued) Concentration in pCi/L b EPA Resultd Sample Date TlHL Result Control Lab Code Type Collected Analysis 22 cc Is, N=1 Limits STW-533 Water Apr 1988 534 (Blind) Sample A Gr. alpha NDf 46 .0 :11 .0 27.0-65.0 Ra-226 ND 6.421.0 4.7-8.1 Ra-228 ND 5.620.8 4.2-7.0 Uranium 6.0 0.0 6.026.0 0.0-16.4 Gr. beta ND 57.025.0 48.3-65.7 Sample B Sr-89 3.3 1.2 5.025.0 0.0-13.7 Sr-90 5.321.2 5.0 1.5 2.4-7.6 Co-60 63.321.3 50.0:5.0 41.3-58.7 Cs-134 7.721.2 7.025.0 0.0-15.7 Cs-137 8.3 1.2 7.0 5.0 0.0-15.7 Apr 1988 H-3 6483 155 6202 620 5128-7276 STU-535 Uri ne Apr 1988 Sr-89 14 .7 tl .3 20.0:5.0 11.3-28.7 STW-536 Water Sr-90 20.0:2.0 20.021.5 17.4-22.6 STW-538 Water Jun 1988 Cr-51 331.7 13.0 302.0230.0 250.0-354.0 Co-60 16.022.0 15.0 5.0 6.3-23.7 Zn-65 107.7211.4 101.0 10.0 83.7-118.3 Ru-106 191.3 11.0 195.0220.0 160.4-229.6 Cs-134 18.3:4.6 20.0!5.0 11.3-28.7 Cs-137 26.321.2 25.025.0 16.3-33.7 Jun 1988 H-3 5586:92 5565:557 4600-6530 STW-539 Water Jun 1988 Sr-89 33.7:11.4 40.025.0 31.3-48.7 STM-541 Mil k 54.8-65.2 Sr-90 55.325.8 60.023.0 1-131 103.7:3.1 94 .0 9.0 78.4-109.6 Cs-137 52.7t3.1 51.025.0 42.3-59.7 K 1587:23 1600:80 1461-1739 Jul 1988 Gr. al pha 8.724.2 15.025.0 6.3-23.7 STW-542 Water Gr. beta 5.321.2 4.025.0 0.0-12.7 Jul 1988 Sr-89 NDf 33.025.0 24.3-41.7 STF-543 Food 30.5-37 .5 Sr-90 ND 34.022.0 I-131 115.025.3 107.0211.0 88.0-126.0 Cs-137 52.7:6.4 49.0:5.0 40.3-57.7 K 1190266 1240262 1133-1347 6-10
l l l Table B-1 (continued) l l Concentration in pCi/Lb j EPA Resultd Lab Sample Oate- TIHL Result Cont rol Code Type Collected Analysis 22cc Is, N=1 Limits i I STW-544 Water Aug 1988 l-131 80.010.0 76.028.0 62.1-89.9 STW-545 Water Aug 1988 Pu-239 11.010.2 10.2 1.0 8.5-11.9 Uranium 6.026.0 0.0-16.4 l STW-546 Water Aug 1988 6.020.0
)
STAF-547 Air Aug 1988 Gr. alpha 8.020.0 8.0:5.0 0.0-16.7 l Gr. beta 20.3-37.7 Filter 26.321.2 29.025.0 Sr-90 8.022.0 8.011.5 5.4-10.6 Cs-137 13.022.0 12.025.0 3.3-20.7 1 STW-548 Water Sep 1988 Ra-226 9.310.5 8.422.6 6.2-10.6
, Ra-228 5.820.4 5.4!1.6 4.0-6.8 STW-549 Water Sep 1988 Gr. alpha 7.0:2.0 8.025.0 0.0-16.7 l Gr. beta 11.321.2 10.025.0 1.3-18.7 STW-550 Water Oct 1988 Cr-51 252.0214.0 251.0 25.0 207.7-294.3 i Co-60 26.022.0 25.025.0 16.3-33.7 l Zn-65 158.3210.2 151.0:15.0 125.0-177.0 '
l Ru-106 153.0 9.2 152.0215.0 126.0-178.0 Cs-134 28.725.0 25.0:5.0 16.3-33.7 Cs-137 16.321.2 15.0:5.0 6.3-2' ' STW-551 Water Oct 1988 H-3 2333:127 2316:350 1710 STW-552 Water Oct 1988 553 (Blind) Sampie A Gr, al pha 38.328.0 41.0210.0 23.7-58.3 i Ra-226 4.5:0.5 5.020.8 3.6-6.4 Ra-228 4.4:0.6 5.220.8 3.6-6.4 Uranium 4.721.2 5.026.0 0.0-15.4 Sample B Gr. beta 51.3 t3.0 54.025.0 45.3-62.7 S r-89 3.721.2 11.025.0 2.3-19.7 Sr-90 10.721.2 10.021.5 7.4-12.6 Cs-134 15.322.3 15.025.0 6.3-23.7 Cs-137 16.721.2 15.025.0 6.3-23.7 B-11
i Table B-1 (continued) Concentration in pCi/Lb EPA Resultd Sample Date TIML Result Control L ab Collected Anal ysi s 22 c< 1s, N=1 Limits Code Type Oct 1988 Sr-89 40.327.0 40.025.0 31.3-48.7 STM-554 Mil k 54.8-65.2 Sr-90 51.012.0 60.0:3.0 1-131 94.023.4 91.019.0 75.4-106.6 Cs-137 45.0 4.0 50.015.0 41.3-58.7 K 1500:45 1600:80 1461-1739 Nov 1988 A-3 30302209 30252359 2403-3647 STU-555 Urine Nov 1988 Gr. alpha 9.013.5 9.015.0 0.3-17.7 STW-556 Water Gr. beta 9.721.2 9.0:5.0 0.3-17.7 Dec 1988 1-131 108.7:3.0 115.0212 .0 94.2-135.8 STW-557 Water Jan 1989 Sr-89 40.028.7 40.025.0 31.3-48.7 STW-559 Water 24 .4-27 .6 Sr-90 24.323.1 25.021.5 Jan 1989 Pu-239 5.821.1 4.2:0.4 3.5-4.9 STW-560 Water Jan 1989 Gr. al pha 7.3:1.2 8.025.0 0.0-16.7 STW-561 Water 0.0-12.7 Gr. beta 5.3:1.2 4.025.0 Feb 1989 C r-51 245:46 235:24 193.4-276.6 STW-562 Water 1,3-18.7 Co-60 10.0 2.0 10.025.0 Zn-65 170210 159:16 139.2-186.7 Ru-106 18127.6 178:18 146.8-209.2 Cs-134 9.723.0 10.0:5.0 1,3-18.7 Cs-137 11.721.2 10.025.0 1.3-18.7 Feb 1989 l-131 109.024.0 106.0:11.0 86.9-125.1 STW-563 Water H-3 2820:20 27542356 2137-3371 STW-564 Water Feb 1989 Mar 1989 Ra-226 4.220.3 4.920.7 3.7-6.1 STN-565 Water 1.2-2.2 Ra-228 1.921.0 1.7 0.3 Mar 1989 U 5.020.0 5.0:6.0 0.0-15.4 STW-566 Water Gr. al pha 21.7:1.2 21.025.0 12.3-29.7 STW-567 Air Mar 1989 62.025.0 53.3-70.7 Filter Gr. beta 68.324.2 Sr-90 20.022.0 20.021.5 17.4-22.6 Cs-137 21.3:1.2 20.025.0 11.3-28.7 I B-12
El Table B-1 (continued) Concentration in pCi/Lb EPA Resultd L ab Sample Date TIML Result Control Code Type Collected Analysis 12 0< 1s, N=1 Limits STW-568 Water Apr 1989 569 (Blind) Sample A Gr. al pha 22.7 2.3 29.027.0 16.9-41.2 Ra-226 3.6:0.6 3.520.5 2.6-4.4 Ra-228 2.621.0 3.6 0.5 2.7-4.5 i V 3.020.0 3.026.0 0.0-13.4 Sample B Gr. beta 52.3:6.1 57.025.0 43.3-65.7 Sr-89 9.315.4 8.015.0 0.0-16.7 Sr-90 7.020.0 8.0:1.5 5.4-10.6 Cs-134 21.025.2 20.025.0 11 .3-28 .7 Cs-137 23.022.0 20.025.0 11.3-28.7 STW-570 Mil k Apr 1989 Sr-89 26.0:10.0 39.015.0 30.3-47.7 Sr-90 45.7:4.2 55.0 3.0 49.8-60.2 Cs-137 54.0.t6.9 50.025.0 41.3-58.7 K-10 15212208 1600180 1461-1739 STW-5719 Water May 1989 Sr-89 <0.7 6.025.0 0.0-14.7 Sr-90 5.021.0 6.0:1.5 3.4-8.6 STW-572 Water May 1989 Gr. al pha 24.022.0 30.028.0 16.1-43.9 Gr. beta 49.3:15.6 50.025.0 41.3-58.7 Jun 1989 Ba-133 50.7:1.2 49.0 5.0. 40.3-57.7 STW-573 Water Co-60 31 .3:2 .3 31.025.0 22.3-39.7 In-65 167210 165:17 135.6-194.4 Ru-106 12329.2 128213 105.5-150.5 Cs-134 40.321.2 39:5 30.3-47 .7 Cs-137 22.321.2 20 5 11.3-28.7 Jun 1989 H-3 4513:136 4503:450 3724-5282 STW-574 Water Water Jul 1989 Ra-226 16.813.1 17.722.7 13.0-22.4 STW-575 Ra-228 13.823.7 18.322.7 13.6-23.0 Jul 1989 U 40.321.2 41.026.0 30.6-51.4 STW-576 Water Aug 1989 I-131 84.7:5.8 83.028.0 69.1-96.9 STW-577 Water Aug 1989 Gr. alpha 6.0:0.0 6.025.0 0.0-14.7 STAF-579 Air 10.025.0 1.3-18.7 Filter Cs-137 10.312.3 B-13
Table B-1 (Continued) Concentration in pCi/LD EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 22cc is, N=1 Limits STW-580 Water Sep 1989 Sr-89 14.7 1.2 14.025.0 5.3-22.7 Sr 90 9.721.2 10.021.5 7.4-12.6 STW-581 Wate- Sep 1989 Gr. alpha 5.0:0.0 4.025.0 0.0-12.7 Gr. Beta 8.722.3 6.025.0 0.0-14.7 STW-583 Water Oct 1989 Ba-133 60.3210.0 59.026.0 48.6-69.4 Co-60 29.024.0 30.025.0 21.1-38.7 Zn-65 132.326.0 129.0213.0 106.5-151.5 Ru-106 155.326.1 161.0216.0 133.3-188.7 Cs-134 30.726.1 29.025.0 20.3-37.7 Cs-137 66.324.6 59.025.0 50.3-67.7 STW-584 Water Oct 1989 H-3 3407:150 3496 364 2866-4126 STW-585 Water Oct 1989 586 (Blind) Sample A Gr. Alpha 41.7:9.4 49.0212.0 28.2-69.8 Ra-226 7.9 0,4 8.421.3 6.2-10.6 Ra-228 4.420.8 4.1 0.6 3.1 - 5 ,1 U 12.0:0.0 12.026.0 1.5-22.4 Sample B Gr. Beta 31.7:2.3 32.0:5.0 23.3-40.7 Sr-89 13.324.2 15.025.0 6.3-23.7 Sr-90 7.022.0 7.0 3.0 4.4-9.6 Cs-134 5.0:0.0 5.025.0 0.0-13.7 Cs-137 7.020.0 5.025.0 0.0-13.7 STW-587 Water Nov 1989 Ra-226 7.9:0.4 8.721.3 6.4-11.0 Ra-228 8.921.2 9.321.2 6.9-11.7 STW-588 Water Nov 1989 U 15.020.09- 15.026.0 4.6-25.4 STW-589 Water Jan 1990 Sr-89 22.7:5.0 25.025.0 16.3-33.7 S r-90 17.321.2 20.021.5 17.4-22.6 STW-591 Water Jan 1990 Gr. Alpha 10.323.0 12.025.0 3.3-20.7 Gr. Beta 12.321.2 12.025.0 3.3-20.7 B-14
Table B-1 (continued) Concentration in pCi/Lb EPA Resultd Sample Date TlHL Result Control Lab Collected Analysis 22cc is, N.1 Limits C ode Type Water Jan 1990 Co-60 14.722.3 1525.0 6.3-23.7 STW-592 Zn-65 135.026.9 139.0 14.0 114.3-163.2 Ru-106 133.3213.4 139.0214.0 114.8-163.2 Cs-134 17 .321.2 18.0 5.0 9.3-26.7 Cs-137 19.3:1.2 18.0:5.0 9.3-26.7 Ba-133 78.020.0 74.027.0 61.9-86.1 Feb 1990 M-3 4827183 4976:498 4113-5839 STW-593 Water Mar 1990 Ra-226 5.0 0.2 4.920.7 4.1-5.7 STW-594 Water Ra-228 13.5 0.7 12.721.9 9.4-16.0 Mar 1990 0 4.0 0.0 4.026.0 0.0-14.4 STW-595 Water Mar 1990 Gr. Alpha 7.321.2 5.025.0 0.0-13.7 STW-596 Air 22.3-39.7 Filter Gr. Beta 34.020.0 31.025.0 Sr-90 10.020.0 10.021.5 7.4-12.6 Cs-137 9,3:1.2 10.0 5.0 1.3-18.' STW-597 Water Apr 1990 598 (Blinc) Gr. Alpha 81.0t3.5 90.0223.0 50.1-129.9 Sample A Ra-226 4.9 0,4 5.020.8 3.6-6.4 Ra-228 10.6 0.3 10.221.5 7.6-12.8 U 18.7 3.0 20.026.0 9.6-30 .4 Gr. Beta 51.0210.1 52 .0 5 .0 43.3-60.7 Sample B Sr-89 9.321.2 10.0:5.0 1.3-18.7 Sr-90 10.323.1 10.021.5 8.3-11.7 Cs-134 16.020.0 15.025.0 6.3-23.7 C s-137 19.022.0 15.025.0 6.3-23.7 Apr 1990 Sr-89 21.723.1 23.025.0 14 .3-31 .7 STM-599 Milk 23.025.0 14 .3- 31 .7 Sr-90 21.027.0 I-131 98.721.2 99.0210.0 81.7-116.3 Cs-137 26.016.0 24.025.0 15.3-32.7 K 1300.0:59.2 1550.0278.0 1414.7-1685.3 May 1990 S r-89 6.022.0 7.025.0 0.0-15.7 STW-600 Water 0.0-15.7 Sr-90 6.721.2 7.025.0 Gr. Alpha 11.022.0 22.026 0 11 .6-3 2 .4 STW-601 Water May 1990 Gr. Beta 12.3 1.2 15.0:5.0 6.3-23.7 B-15
Table B -_(continued)- ! Concentration in pC1/Lb EPA Resultd L ab Sample. Date TIML Result Control Code . Type Collected Analysis 22cc 15, N=1 Limits _ STW-602 Water Jun 1990 Co-60 25.322.3 24.015.0 15.3-32.7_
-Zn-65 155.0 10.6 148.0215.0 130.6-165.4 Ru-106 202.7217.2 210.0221.0 173.6-246.4 '
Cs-134 23.721.2 24.0:5.0 18.2-29.8 Cs-137 27.713.1 25.025.0 16.3-33.7 Ba-133 100.718.1 99.0210.0 81.7-116.3 STW-603 Water Jun 1390 H-3 2927:306 29332358 2312-3554 STP 504 Water Jul 1990 Ra-226 11.820.9 12.121.8 9.0-15.2 Ra-228 4.121.4 5.121.3 2.8-7.4 STW-605 Water Jul- 1990 V 20.321.7 20.823.0 15.6-26.0 STW-606 Water Aug 1990 I-131 43.021.2 39.0:6.0 28.6-49.4 STW-607 Water Aug 1900 Pu-239 10.021.7 9.120.9 7.5-10.7 Aug 1990 Gr. alpha 14.010.0 10.025.0 1,3-18.7 STW-608_ - Air Filter Gr. beta .65.321.2 62.025.0 53.3-70.7 Sr-90 19.026.9 20.025.0 11.3-28.7 Cs-137 19.022.0 20.025.0 11.3-28.7 STW-609 Water Sep 1990 S r-89 9.022.0 10.025.0 1.3-18.7 Sr-90 9.022.0 9.025.0 0.3-17.7 STM-610 Water Sep 1990 Gr. alpha 8.3:1.2 10.015.0 1.3-18.7 Gr. beta 10.321.2 10.025.0 1.3-18.7 STM-611 Mil k Sep 1990- Sr 11 713.1 16.025.0 7.3-24.7 Sr-90 15.020.0 20.025.0 11.3-28.7 1-131 63.016.0 58.026.0 47 .6-68 .4 Cs-137 20.022.0 20.025.0 11.3-28.7 K 1673.3270.2 1700,0185.0 1552.5-1847.5: L STW-612 . Water Oct 1990 Co-60 20.3 3.1 20.025.0 11.3 28.7 Zn-65 115.3112.2 115.0212.0 94.2-135.8 Ru-106 152.028.0 151.0215.0 125.0-177.0-Cs-134 11.020.0 12.0:5.0 ~ 3.3-20.7 ! Cs-137 14.022.0 12.015.0 3.3-20.7 8a-133 116.729 9 110.0211.0 90.9-129}}