ML20095K062
| ML20095K062 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/31/1991 |
| From: | Shelton D CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2040, NUDOCS 9205040303 | |
| Download: ML20095K062 (597) | |
Text
{{#Wiki_filter:__._._.;,__- _ . . t 9 CENTER ENERGY00R Otm C. SW 300 Maison Avenue Vce Presdent Nuclea' Toledo, OH 436524001 Mb (411r,26230n Docket Number 50-346 License Number NPF-3 Serial Number 2040 April 28, 1992 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
1991 Annual Radiological Environmental Oparating Report Gentlemen: Enclosed are two (2) copies of the 1991 Annual Radiological Environmental Operating Report for the Davis-Besse Nuclear Pover Station, Unit Number 1. This report was prepared in accordance with Section 6.9.1.10_of the Davis-Besse Operating License, Appendix A, Technical Specifications. Also enclosed are two (2) copies of Attachment I to the annual report, c'ntaining results from the analysis of radiological environmental samples and of environmental tr.diation measurements taken during the 1991 reporting period. For your reference, the enclosed Table 1 provides a listing of the specific requirements and the location of the portion of the Annual Radiological Environmental Operating Report which was prepared to meet that requirement. Should 'u have any questiona, please contact Mr. R. V. Schrauder, Managt< Nuclear Licensing, at (419' 249-2366. Very ir yours,
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. Docket Number 50-346 e License Number NPP-3 Setial Number 2040 Enclosure Table 1 Index to Report Sections Prepared to Meet Requirements of T. S. 6.9.1.10 Description of requirement Location /page number (s}
Summaries, interpretations, and analyses of trends of the radiological environmental surveillance activities, and an assessment of the observed 2-14 through 2-58 impacts of the plant and Appendix E Results of the Annual Land Use Census 3-1 through 3-8 Results of the analysis of all radiological environmental samples and of all environmental radiation measurements Attachment 1 Summary description of the radiological environmental monitoring program 2-4 through 2-58 At least 2 legible maps, covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor 2-17 through 2 19 and . 2-30 thro &c 2-32 and 2-42 throug., 2-44 and ~ 2-55 through 2-57 The results of licensee participation in the Interlaboratory Comparison Program (required by Specification 3.12.3) Appendix B Discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable 2-14 through 2-58 Discussion of casts in which specimens vere unobtainable due to hazardous conditions, seasonable unavailability, malfunction of automatic sampling equipment and other legitimate reasons (as required by Specification 3.12.1.d) 2-13 through 2-14 k _ - . . - .. .. .
i i l l l r l ANNUAL ENVIRONMENTAL OPERATING REPORT: for Davis-Besse Nuclear Power Station January 1,1991 to December 31,1991 Prepared by: Radiological Environmental Davis-Besse Nuclear Power Station Toledo Edison Company Toledo, Oblo Apr01992
s TABLE OF CONTENTS a l b Title' Page , L!st of Tables vil List of Figures lx Summary xil Introduction 1-1
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Fundamentals 1-1 The Atom 1-1 Isotopes 12
- Radiation and Radioactivity 1-3 ,
Radionuclides 1-3 Radiation- 3 Radioactive Decay 1-4 Half life - 1-4 Interaction with Matter - 1-5 . Ionization 1-5 Range and Shielding 1-5 Quantities and Units of Measurement 1-7 Activity: Curie 1-7 Exposure: Roentgen 17 Absorbed Dose: Rad 1-8 Dose Equivalent: Rem 1-8 i M.i . . . . _ . ,_ . - . _ . . . _ _ . . _ _ . . _ _ . . . . .
- -)
. Sources of Radiation 1-9 Background Radiation 1-9 Man-made Radiation 1-13 Health Effects of Radiation 1-13 Studies 1-13 Health Risks 1-14 Benefits of Nuclear Power 1-16
. Nuclear Power Production 1-17 What is Fission? 1 17 Nuclear Fuel 1-18 The Reactor Core 1-19 Fission Control 1-20 Reactor Types 1-21 Future Reactor Types 1-21 Advanced Pressurized Water Reactor 1-21 Advanced Boiling Water Reactor 1-22 Simplified Boiling Water Reactor 1 23 Liquid Metal Reactor 1-24 Modular High Temperature Gas-Cooled Reactor 1-24 Station Systems 1-26 Containment Building and Fission Product Release Barriers 1-28 The Steam Generators 1-28 The Turbine-Generator 1-29
. The Condenser 1-29 The Cooling Tower 1-30 Miscellaneous Station Safety Systems 1-31
- Reactor Safety and Summary 1-32 Description of the Davis Besse Site 1 33 ii A _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . _ __ . . . . _ _ _ _ _ . _ _ . _ . _ _ ._
The 1991 Radioactive Liquid and Gaseous . Effluents Summary 1-36 Protection Standards 1-36 Limits 1-36 Sources of Radioactivity Released 1-37 Noble Gas 1-38
. lodine and Particulates 1-38 Tritium 1-39 Processing and Monitoring 1-39 Exposure Pathways 1-40 Dose Assessment 1 42 Results 1-43 References 1-44 Radiological Environmental Monitoring Program 2-1
- Introduction 2-1 Preoperational Surveillance Program 2-2 Operational Surveillance Program Objectives 2-2 Quality Assurance 2-3 Program Description 2-4 Overview 2-4 Sample Analysis 2-6 Sample History Comparison 27 Atmospheric Monitoring 2-9 Terrestrial Monitoring 2-10 Aquatic Monitoring 2-10
- Direct Radiation Monitoring 2-11 iii L- __ _ _____ _ __________ ________________ _______ _________ _ _____ _ _ _ __ _ _ ___
a
-- 1991 Sampling Program 2-11
-1991 Program Deviations 2-13 Sampling Locations 2 Atmospheric Monitoring 2-14 Air Samples 2-14 Airborne Particulates 2 15 Airborne lodine-131 2-16 '
- Terrestrial Monitoring 2-20 Milk - 2 ' :
Groundwater 1~' ! Broadleaf Vegetation and Fruit . Samples . 2-24
- Animal / Wildlife Feed Samples 2 25 Domestic / Wild Mcat Samples 2-26 Goil Samples- 2-27
' Aquatic Monitoring 2 33 Treated Surface Water 2 33
- Untreated Surface Water 2 35 Shoreline Sediment - 2 39 Fish 2-40 Direct Radiation Monitoring 2-45 Thennoluminescent Dosimeters 2-45
. TLD Collection 2-45 ,
- Quality Control TLDs - 2-46 NRC TLD Monitoring 2-47.
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-- Conclusion - '2 58
-- References 2 59
-Land Use Census 31 Program Design - 3-1 Methodology . 32 ,
? ~ Results 3-2 iv a
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Meteorological Monitoring 4-1 IntrcJuction 4-1 Onsite hieteorological Monitoring 42 System Description 4-2 Meteorological Instrumentation 4-2 Meteorological System Maintenance and Calibration 4-3 Meteorological Data Handling and Reduction 4-3 Meteorological Data Recovery 4-* Marsh Management 5-1
- Navarre Marsh 5-1 Special Projects in 1991 5-3
- References 5-5 Zebra Mussel Control 6-1
- Introduction 6-1 Monitoring 61 Research 6-2 Water Treatment 7-1
- Water Treatment Plant Operation 7-1 Description 7-1 Clarifier Operation 7-2
. New Drinking Water Rules 7-2 ._
Wastewater Plant Operation 73
- Summary of 1991 Wastewater Treatment Plant Operations 7-3 l -- - National Pollutant Discharge Elimination Systerns (NPDES) Reporting 7-5
- 1991 NPDES Summary 7-6 Outfall 001 7-6 Outfall 002 7-6 v
I Outfall 003 7-6 Outfall 601 7-6 Outfall 602 7-7
. Sampling Point 801 77
- Storm Water Monitoring 77 Chemical Waste Management Program 8-1 Introduction 8-1 Waste Management 8-1 Resource Conservation and Recovery Act(RCRA) 8-1 Hazardous and Solid Waste Arr ndment(HSWA) 82 Emergency Response Planning 8-3 Comprehensive Environmental Response, Compensation, and Liability Act(CERCLA) 8-3 Superfund Amendment and Reauthorization Act (SARA) 8-4 Other Regulating Acts 8-5 i Clean Air Act 8-6 Transportation Safety Act 8-6 Other Programs 8-7 Underground Storage Tanks 8-7 Bum Permits 8-7 Summary 8-7 Appendix A: Glossary A1 Appendix B: Interlaboratory Comparison Program B-1 Appendix C: Data Reporting Conventions C-1 Appendix D: Maximum Permissible Concentration:..
of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas D1 Appendix E: REMP Sampling Summary E-1 vi J
LIST OF TABLES Table No. Page No. Title 1-1 1-3 Isotopes of Uranium 1-2 1-15 Risk Factors 1-3 1-37 Dose Limits to a Member of the Public l-4 1-43 Annual Doses to the Public Due to Radioactivity Released in Gaseous and Liquid Effluents 2-1 25 Sample Codes & Collection Frequencies 22 28 Radiochemical Analysis Per-formed on REMP Samples 2-3 2-12 Sampic Collection Summary 2-4 2 16 Air Monitoring i_ocations . 2-5 2-22 Milk Monitoring Locations 2-6 2-23 Groundwater Monitoring Locations 2-7 2 25 Broadleaf Vegetation and Fruit Locations 2-8 2-26 Animal / Wildlife Feed Locations 2-9 2-27 Wild / Domestic Meat Locations 2-10 2 29 Soil Locations 2 11 2-35 Treated Surface Water Locations 2-12 2-38 Untreated Surface Water Locations 2-13 2-40 Shoreline Sediment Locations 2-14 2-41 Fish Locations 2-15 2-48 Thermoluminescent Dosimeter Locations 3-1 3-5 Closest Exposurc Pathways Present in 1991 3-2 38 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters vii l l (
l Tsble No. Page No. Tl!!e 41 48 Summary of Meteorological Data Recove.ry for DBNPS 1991 42 49 Summary of Meteorological Data Measured at DBNPS for 1991 42 4 10 Summary of Meteorological Data Measured at DBNPS for 1991 (Con't) i I viii
List of Figures!* Figure No. Page No. Title 1-1 1-2 The Atom 1-2 1-6 Range and Shielding of Radiation 1-3 1-10 Sources of Radiation 1-4 1-17 Comparison of Nucicar with Other Energy Sources 1980 and 1991 1-5 1-18 Fission Diagram
- 1. - 1-20 Fuel Rod, Fuel Assembly, Reactor Vessel 1, 7 1-22 Advanced Pressurized Water Reactor 1-8 1-23 Simplified Boiling Water Reactor 1-9 1-25 High Temperature Gas-Cooled Reactor _
1-10 1-27 Schematic of Davis-Besse 1-11 1-33 Map of the Area Surrounding Davis-Besse 1-12 1-41 External Exposure Pathway 1-13 1-42 Internal Exposure Pathway 2-1 2 15 Air Samples: Gross Beta 2-2 2 17 Sampling Locations on the Davis-Besse Site ix 1 t_____________________.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ .._ _
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. . , _ . . . . . _ _ _ . . _ _ _ . _ . . _ . ..,....c. Figure No. Page No. Title 2-3 2 18 Sampling Location within a Five Mile Radius 2-4 2-19 Sampling Locations within a Twenty-five Mile Radius 2-5 2-22 Milk Samples: Strontium-90 2-6 2-28 Soil: Cesium-137 2-7 2-30 Sampling Locations on the Davis Besse Site 2-8 2-31 Sampling Locations within a Five Mile Radius 2-9 2-32 Sampling Locations within a Twenty-Five Mile Radius 2-10 2-34 Treated Water: Grost. Beta 2-11 2-37 Untreated Water: Gross Beta 2-12 2-41 Fish: Gross Beta 2-13 2-42 Sampling Locations on the Davis-Besse Site 2-14 2-43 Sampling Locations within a Five Mile Radius 2-15 2-44 Sampling Locations within a Twenty-Five mile Radius 2-16 2-46 TLD Samples: Comparison of Doses Measured Since 1987 2 17 2-47 Comparison of NRC vs Davis-Besse TLDs Since 1987 2 18 2-55 Sampling Locations on the Davis-Besse Site X
Figure No. Page No. Title 2-19 2-56 Sampling locations within a Five Mile Radius 2 20 2 57 Sampling locations within a Twenty-Five Mile Radius 3-1 3-4 Land Use Census Map 4-1 43 Transmission of Meteorological Data from Towers 4-2 4-5 10 Meter Wind Rose 4-3 4-6 75 Meter Wind Rose 4-4 4-7 100 Meter Wind Rose 6-1 6-2 Zebra Mussel Graph 6-2 6-3 Mussel Study Device 7-1 7-4 Floor Plan Waste Wate.r Treatment Plant s 1
Davis-Besse Nuc1 car Power Station tnt Annual Environmental Operating Report Summary The Annual Environmental Operating Report is a detailed report of the Envi-ronmental Monitoring Programs conducted at the Davis Besse Nuclear Pow-ei Station from January 1 through December 31,1991. Reports included are the Radiological Environmental Monitoring, Land Use Census. Meteorologi-cal Monitoring, Marsh Management, Zebra Mussel Control, Water Treat-ment, and Chemical Waste Management Programs. Radiological Environmental Monitoring Program The operation of a nuclear power station results in the release of small amounts of radioactivity to the surrounding environment. These releases must comply with stringent regulations imposed by the Nuclear Reguireory Commission (NRC). The Radiological Environmental Monitoring Propa-(REMP) has been established to monitor the radiological condition of the e... vironment around Davis-Besse. This program includes the sampling and analysis of environmental samples, and the evaluation of the effects of re-leases of radioactivity on the environment. Radiation levels and radioactivity are monitored within a 25 mile radius around Davis-Besse.ne environment around Davis-Besse has been moni-tored for approximately 20 years. The REMP was established about five years before Davis-Besse became operational, his program provided data on background radiation and radioactivity which is normally present in the area. Davis-Besse has continued to monitor the environment by sampling air, groundwater, milk, edible meat, fruits and vegetables, animal feed, soil, drinking water, surface water, fish, and shoreline sediments, as well as by measuring radiation directly. Samples are collected from both indicator and control locations. Indicator locations are within approximately five miles of Davis-Besse and are ex. pected to show naturally occuring radioactivity plus any increases of radioa:- tivity that might occur due to the operation of Davis-Besse. Control location are greater than five miles away from Davis-Besse, and are expected to indi-cate the presence of only naturally occurring radioa:tivity. The results ob-tained at the samples collected from indicator locations are compared with xii
m - 1 Davis Desse Nuclear Power Station 1991 Annual Environmental Operating Reprt the results from those collected at control locations and with the concentra-tions present in the enviromnent before Davis Besse became operational. This allows for the assessment of any impact the operation of Davis-Besse might have had on the surrounding environment. In 1991, over 2600 radiological environmental samples were collected, and over 3600 analyses for radioactivity were performed. Radionuclide con-centrations measured at indicator locations were compared with concentra-tions 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 af 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 monitoring and direct radiation monitoring.
- Atmospheric Monitoring Samples of air are collected to monitor the atmosphere. The 1991 results are similar to those observed in preoperational and previous operational programs. Only background radioactivity normally present in the environ-ment was detected.
- Terrestrial monitoring This includes analysis of milk, groundwater, meat, fruits, vegetables, animal feed and soil ssmples. The results of the sample analyses compare favorably with those of previous years. For example, cesium 137 radioactivity in soil was at an average concentration of 0.30 picoeurie per gram dry weight (pCi/g)in 1991, 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 he results of the analyses of the other terrestrial samples also indicate concentrations of radioactivity similar to previous years, and indicate no buildup of radioactiv-ity attributable to the operation of Davis Besse.
- Aquatic monitoring This includes the collection and analysis of drinking water, untreated surface uater, fish and shoreline sediments. The 1991 results of analyses for fish, i drinking water, and shoreline sediment indicate normal background con-
! centrations of radionuclides and show no increase or buildup of radioactivity i due to station operation. In untreated water, a trace amount of tritium (884 l pi'i/l) chat could be attributed to station operation was detected in only one l xiii l
l Davis-Besse Nuclea: Power Station 1991 Annual Environmental Operating Report sample, his had no impact on the nearby residents or the surrounding envi-ronment.
- Direct F.adiation Direct radiatica measurements averaged 15.0 mrem /91 days at indicator loca-tions and 16J. mrem /91 days at control locations, showing that, in 1991, radi-ation in the area of Davis-Besse was similar to radiation at lo::ations greater than 5 miles away from the Station ,
he 1991 operation of Davis Besse caused no significant increase in the con-centrations of radionuclides in the environment and no significant change in - the quali'.y of the environment. All radioactivity released in the Station's effluents was well below the applicable federal regulatory limits. The esti-mated radiation dose to the general public due to the operation of Davis-Besse in 1991 was also well below all applicable regulatory limits. In order to estimate this radiation dose, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the REMP. During the cen-sus, Davis-Besse personnel travel every public road within a five mile radius of the Station vent to locate the radiological exposure pathways. The one pathway of particular concern is the pathway that, for a specific radionuclide, provides the greatest dose to a sector of the population, and is called the criti-cal pathway. The critical pathway for 1991 remained unchanged from the 1990 Land Use Census, which is an infant / milk pathway at 4270 meters in the west southwest sector. Meteorological Monitoring The Meteorological Monitoring Program at Davis-Besse is part of a program for evaluating the effects of the routine operation of the station on the sur-row. ding environment. Meteorological Monitoring began in october 1968. Meteorological instruments measure continuously and are monitored daily by meteorological monitoring personnel. Meteorological data recorded at Davis-Besse include wind speed, wind direc-tion, sigma theta (standard deviation of wind direction), ambient temperature, differential temperature, dew point and precipitation. Two instrument equipped meteorological towers are used to ccilect data. Data recovery for 1991 was 90% or greater for all measured parameters. In 1991, the data xiv
I L Davis-Besse Nuclear Power Statko 1991 Annual Em ironmental Operating Report recovery for the six instruments required to be operational by Davis-Besse Technical Specifications was greater than 901 Marsh Management Toledo Edison and the Cleveland Electric Illuminating Company co-own the Navarre Marsh which they lease to the U.S. Fish and Wildlife Service, who manage it as pan of the Ottawa National Wildlife Refuge. Davis-Besse Envi- , ronmental Compliance personnel are responsible for inspecting the marsh and reporting its status monthly. Special projects conducted in 1991 included song bird and Canada goose banding. In 1991,6432 birds were banded. In addition, unwanted and dis-ruptive plant species, such as purple loosestrife (Lythrum salicaria) and the giant reed (Phragmities australisi), were controlled in order to enhance the ability of the marsh to support the resident wildlife. , Zebra Mussel Control The Zebra Mussel Control Program was implemented in 1990 to study the extent of mussel infestation at Davis-Besse. Routine sampling and analyses of water from various locations at the station provide estimates of the number
- of zebra mussels which might enter the plan..
In addition to the sampling, Davis-Besse and the Electric Power Research In-stitute are conducting experiments to determine alternate methods for con-trolling the zebra mussel. Water Treatrnent Davis-Besse uses Lake Erie as a source of water for the site Water Treatment Plant. The water is treated onsite to provide domestic water and to produce high prity water for use in the Station's cooling systems. Principal activities in 1991 included the removal of precipitator number one from service for cleaning and maintenance and the implementation of the new Ohio Envirar mental Protection Agency' Drinking Water Standards which placed more stringant restrictions on turbity and anaitional bacteriological requirement, , xv
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Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Report Wastewater generated onsite is treated at the Davis-Besse Wastewater Treat-ment Plant. The was:ewater 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 waste wa-ters, back into Lake Erie. During 1991, Waste Water Treatment Plant Num-ber 1 was out of service due to damage to an interior tank. The installation of supports has corrected the problem and the plant should be back in opera-tion early in 1992. Current plans are to remove Wastewater Treatment Plant Number 2 from service for cleaning and maintenance in 1992. Chemical Waste Management The Chemical Waste Management Program at Davis-Besse was developed to ensure that the offsite disposal of nonradioactive hazardous and -on-hazardous chemical wastes is performed in accordance with all applicable state and federal regulations. Davis Besse uses the best available technology, such as incineration or treatment to reduce toxicity, for offsite disposal of its chemical wastes in order to protect human health and the environment. In 1991, as a result of waste minimization effons,648 pounds of hazardous . waste (used solvents),7,355 gallons of waste oil and 24 nickel cadmium battery cells were sent to recycling Orms or a fuel blenders for thermal ener-gy purposes. As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse reported eight hazardous products and chemicals to local and state agencies. Two of the chemicals, hydrazine and su:furic acid, are classi-fied as " extremely hazardous" substances. As part of the program to remove polycharinated biphenyls (PCB) Ouid from Davis-Besse, ten previously filled PCB transformers were retrofilled for the ! final time in 1990. These were sampled and analyzed in 1991 and re-( classi0ed to non-PCB. The last identified PCB transformer at Davis-Besse ! received the final'retrofillin 1991. This transformer will be analyzed in 1992 and is expected to be re<lassified as non PCB . I Appendices l Appendix A contains a Glossary of terms used throughout this report, it is l nat meant to be a comprehensive reference source for interpreting any docu-ments other than this 1992 Annual Environmental Operating Report. xvi l
Davts.Besse Nuclear Power Station 1991 Annual Environmental Operating Reprt Appendix B contains results from the laterlaboratory Comparison Program requited by Davis-Besw Technical Specifications. Samples with known con-centrations of radioisotopes are prepared by the Environmental Protection Agency (EPA), and then sent (with information on sample type and date of collection only) to the laboratory contracted by the Centerior Energy Corpo. ration to analyze the REMP samples. The results are then checked by the EPA to ensure consistency with the know values. The results from both the contracted laboratory and the EPA are provided in Appendix B. Appendix C contains data reporting conventior.s used in the REMP at Davis-Besse. The appendix provides an explanation of the format and computation- , al methods used in reporting REMP data. Information on counting uncer-tainties, and computation of averages and standard deviations is also provided. n Appendix D lists the maximum permissible concentrations of alpha and beta emitting radioisotopes and of certain other radioisotopes in air and water samples. These concentrations are taken directly from the Code of Federal Rcgulations, and provide comparison values for actual REMP sampling re. sults for 1991. Appendix E provides a REMP sampling summary from 1991. The appendix provides a listing of the following for each sample type:
- the number and types of analyses pcrformed
- the lower limit of detection for each analysis
- the mean and range of results for control and indicator locations the mean, range, and location description for the location with the highest annua! mean the number of non-routine results For detaile6 studies, Appendix F will provide more specific information than that listed in Chapter 2 of this report. Additionally, more specific information is submitted to the NRC in Annual Environmental Monitoring Report Attach- ,
ment 1 This document is not distributed with the rest of the Annual Envi-ronmental Operating Report due to its large size and technical nature. The information presented in Appendices B through E were provided by Tele-dyne Isotopes Midwest Laboratories in their Annual Report to Toledo Edison i (Part 1, Feb.1992). i i I xvii ! l
Annual Envirtmmental Operating Repon 1991 Davis.Desse Nuclear Power Station Introduction Coal, oil, natural gas, and hydropower htye been used to run this nation's electric generating stations; however, each method has its drawbacks. Coal fired power can affect the environment through mining, acid rain, and airborne discharges. Oil and natural gas are in limited supply and are therefore costly, and hydropower is limited due to the environmental impact of damming our waterways and the scarcity of suitable sites in our country. Nuclear energy provides an attemate source of energy which is readily available. The operation of nuclear power stations has a very small impact on the environment. In fact, the Davis.Besse Nuclear Power Station is surrounded by hundreds of acres of marshland which makes up part of the Ottawa National Wildlife Refuge, the only national refuge in Ohio. In order to more fully understand this unique source of energy, background information on basic radiation characteristics, risk assessment, reactor operation, and effluent control, is provided in this chapter. Fundamentals The Atom All matter consist of atoms. Simply described, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, respectively (Figure 1 1). The relatively large protons and neutrons are packed tightly together in a cluster at the center of the atom, called the. nucleus. Orbiting around this nucleus are one or more smaller electrons. In an electrically neutral atom, the negative charges of the electrons are balanced by the positive charges of the, protons. Due to their dissimilar charges, the protors and electrons have a strong attraction for each other, which helps hold the atom together. Other attractive forces between the protons and neutrons keep the densely packed protons from repelling each other, preventing the nucleus from breaking apart. 1-1
l Annus! Environmente! Operating Repo:t 1991 Davis-Benne Nuclear Power Station I O raoluN I gd
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Figure 1-t: An atom comists of two pans: a nucleus n =L L 3 poskively c%ed pnxons and elec:rically netcal neuunns and one or enore negatively durBed electrons orbiting the nucleus. Protoos ar,4 neu:rons are nearly identical in size and weight, while cart is about 2000 times besvier than an cJectron. l Isotopes A group of identical atoms, containing the same number of protons, make up an element. In fact, the number of protons an atoms contains determines its chemical identity. For instance, all atoms with one proton tre hydrogen atoms and all the atoms with eight protons are oxygen atoms. However, the number of neutrons in the nucleus of an element may vary. Atoms with the same number of protons, but different number of neutrons, are called isotopes. As an example, Table 1-1 list some of the isotopes of uranium. Different isotopes of the same element have the ss.ne chemical properties, and many are stable, or nonradioactive. An unstable or radioactive isotope of an element is called a radioisotope. l-L l 1-2
Annual Environmental Operating Report 1991 Davis-Desse Nuclear Power Statkin Radiation and Radioactivity Radionuclides The parts of an atom are normally in a balanced, stable state. If the nucleus of an atom contains an excess of energy, it is called a radioisotope, radioactive atom, or radionuclide. The excess energy is usually due to excess number of neutrons in the nucleus of the atom. Radionuclides can be naturally occurring such as uranium 238, beryllium-7 and potassium-40, or man-made, such as iodine-131, cesium 137, and cobalt-60. Table 1-1: Isotopes of Uranium Isotope Symbol # of Protons # of Neutrons Uranium -23 5...............U-23 5.................... . 92........ ................ 14 3 Ura nium.23 6.... ......... U. 23 6.............. ...... 92........ ....... ....... 144 Uranium -23 7.... ......... U-23 7...................... 92..... . ................ 145 Uran i um -23 8........ .......U 23 8..... ........ ..... 92.... ...................... 146 Ura nium -23 9........ ....... U-23 9..... .. . ..... ....... 92........................... I 4 7 Ura n i um -24 0....... .. . ..U-24 0. ....... ... ............ 92............ .... ... ... .. . . 148 Radiation Radiation is simply the conveyance of energy through space. For instance, ! heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation is another type of radiation and has similar properties to those of the examples listed above. Ionizing radiation consists of both electromagnetic rullation and particulate radiation. Electromagnetic radiation consis:s of rays of energy
- with no measurable mass that travel with a wave-like motion through space.
Included in this category are gamma rays and X-rays. Paniculate radiation l 1-3
l Annual Environmental Operating Repon 1991 Davis.Besse Nuclear Power Station 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 af 2 protons and 2 neutrons; beta particles, which are essentially free electrons (electrons not attached to an atom); and neutrons. The properties of these types of radiation will be described more fully in the Range and Shielding section on page 1-5. Radioactive Decay Radioactive atoms anempt to reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of _ energy from an atom through the emission of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daughter products which eventually result in a stable atom. De loss of energy and/or matter through radioactive decay may transform the atom into a chemically different element. For example, when uranium 238 decays, it , emits an alpha particle and, as a result, the atom loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom determines its chemical identity. Therefore, when the uranium 238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of thorium-234. Thorium 234 is one of the 14 successive daughter prot . cts of uranium-238. Radon is another daughter product, and the series ends with stable lead-206. His example is part of a known radioactive decay series, called the uranin.n series, which begins with uranium-238 and ends with j lead-206. Half-life Most radionuclides vary greatly in the frequency with which their atoms release radiation. Some radioactive materials, in which there are only infrequent emissions, tend to have a very long half-lives. Those radioactive ; materials that are very active, emitting radiation more frequently, tend to have a comparably short half-lives. The length of time an atoms remains radioactive is defined in terms of half-lives. Half-life is the amount of time required for a radioactive substance to lose half its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years. 1-4 I , 1 l
Annual Environmental Operating Repon 1991 Davis-Desse Nuclear Power Station Interaction With Matter Ionization Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When these forms of radiation interact with any form of material, the energy they impart may cause atoms in that material to become ions, or charged particles. Normally, an atom has the same number of protons as electrons. Thus, the number of positive and negative charges cancel, and the atom is electrically neutral. When one or more electrons are removed an ion is formed. Ionization is one of the processes which may result in damage to biological systems. Range and Shielding Particulate and electromagnetic radiation each travel through matter differently because of their different properties Alpha particles contain 2 - protons and 2 neutrons, are relatively large, and carry an 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 12).
Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed oflight (186,000 miles per second). Beta perticles have an electrical charge of either +1 or -1. Because they are so small and have a low charge, they do not collide and interact as often as alpha particles, so they can travel farther. Beta particles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood. Gamma rays are pure energy that 1:2 vel at the speed oflight. They have no measurable charge or mass, and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray finally loses all ofits energy it and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high energy gamma radiation can travel a considerable distance, whereas low energy gamma radiation may travel only a few feet in air. lead is used as shielding material for gamma radiation because of its density. Several inches of lead or concrete may be needed to effectively shield gamma rays. 1-5
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Radioactive Paper Atuatnua Lead Cencrote Material i Figure 12: As radiation travels, it collidcs and interacts with other atoms and loses energy. Alpha panicles can be stopped by a sheet of paper, and beta particles by a thin sheet of aluminum. Gamma radiation is shicided by highly dense materials such as lead, while byWenous materials (t!xsc containing hydrogen atomsk such as water and concre.te, are used to stop neutroas Neutrons come from several sources. including the interactions of cosmic i radiation with the earth's atmosphere and nuclear reactions within nuclear power reactors. However, neutrons are generally not of environmental concern since nuclear power stations are designed to keep neutrons within the containment building. Because neutrons have no charge, they are able to pass very close to the nuclei of the mate:ial 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 ball is deflected when it strikes another. When deDected, the neutron loses some if its energy. After a series of these deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal neutron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for l causing damage to the material through which they travel. Fast neutrons can ! have from 200 thousand to 200 million times the energy of thermal neutrons. l l-6 l
1 Annual Environmental Operating Repon twt Davis.Besse Nuclear Power Station Neutron shielding is designed to slow down fast neutrons and absorb thermal neutrons. Often neutron shielding material consists of several components, including a highly dense 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 themial neutrons. At Davis-Besse, concrete is used to form an effective neutron shield. Concrete is used because it contains water molecules and can be easily molded around odd shapes. Quantities and Units of Measurement There are several quantities and units of measurement used to describe radioactivity and its effects. Four terms of particular usefulness are activity, exposure, absorbed dose, and dose equivalent. Activity: Curie Activity is the number of nuclei in a sample that disintegrate (decay) per unit of time. Each time a nucleus disintegra'es, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms of a radioactive substance are decaying. One curie indicates the disintegration of 37 billion atoms per second. A curie is a unit of activity, not a quantity of il. Thus, the amount of material required to produce one curie varies. .u mmple, one gram of radium 226 is the equivalent of one curie of activi.y, but it would take 9,170,000 grams (about 10 tons) of thorium-232 to equal one curie. Smaller units of the curie are often used, especially when discussing the low concentrations of radioactivity detected in environmental samples. For - instance, the microcurie (uCi) is equal to one millionth of a curie, while the 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 roentgen is the quantity of exposure that causes approximately two billion ionizing events (i.e., creation of ion pairs) per cubic centimeter of air. 1-7
l' l 1 Annual Envimnmental Operating Report 1991 Davis Besse Nuclear Power Station A common way to describe the rate of exposure to gamma radiation is in roentgens per hour (R/hr). Often a smaller unit used is milliroentgens per l hour (mR/br), which is 1000 times less. l The roentgen applies only to radiation associated with gamma or X rays, and l 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 l does not account for the fact that different substances absorb different i amounts of energy. Thus, another unit is necestary to describe the amount of 1 energy absorbed by any material. il Absorbed Dose: Rad i Absorbed dose is s term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation. 'the rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the ' energy of ionizing radiatien deposited per gram of absorbing material (I rad
= 100 erg /gm). The rate of absorbed dose is usually given in rad /hr.
If the biological effect of radiation was directly proportional to the energy deposited by radiation in an organism, the rad would be a suitable measurement of the biological effect. However, biological effects depend not only on the total energy deposited per gram of tisc.ue, but on how this energy is distributed along its path. Experiments have shown that some types of radiation are more damaging per unit path of travel than others. Thus, another unit is needed to quantify the biological damage caused by ionizing radiation. Dose Equivalent: Rem Biological damage due to alpha, beut, gamma and neutron radiation may result from the ionization caused by these radiations. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological camage for the same energy imparted as do gamma or X rau. Therefore, a quality factor must be applied to account for tTe & ent ionizing capabilities of various types of ionizing radiation. When tk (Mty factor is multiplied by the absorbed dose, the result is the dose 9. svalent, which is an estimate of the possible biological damage resulting from exposure to a particular type of ionizing radiation. The dose equivalent is measured in rem (radiation equivalent man). l-8
_ . _ - _ - .- . _ . - . ~ . _ . - - - - . - ~ ~ Annual l:nvironmental Operating Repon twi Davis.Ibc Nuclear Power Staten As an example of this conversion from absorb:d dose to dose equivalent, the ' quality factor for alpha radiation is 20. Hence, I rad of alpha radiation is approximately equal to 20 rem. Bete and gamma radiation each have a quality factor of 1, therefore one r:1 of either beta or gamma radiation is apptcximately 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. t In terms of environmental radiation, the tem is a large unit. Therefore, a smaller unit, the rnillirem,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 j occurrence on the earth Mankind has always lived with radiation and always will. In fact, during every second of life, over 7,000 atoms undergo rat.ioactive decay in the body of the average adult. In addition to that which ; normally occurs in our bodies, it also occurs naturally in the soil, water, sir, and space. All these common sources of radiation contribute to the natural background radiation to which everyone is exposed (Figure 13). The earth is constantly showered by a stesdy stream of high energy gamma ; rays and particulate radiation that come from space, known as cosmic rediation.The atmosphere shields out most of this radiation, but everyone still receives about 20 to 50 mrem each year from this source. 'Ihe thinner air at higher altitudes provides less pre. ction age. inst cosmic radiation. Therefore, people living et higher altitudes or eve:n flying in an airplane are exposed to more cosmic radiation. For example, the dose due to cosmic radiation in Dent s Colorado (elevation 5280 feet above sea level) is approximately 4*/ mrem per year, whereas, in Toledo, Ohio (maximum elevation 630 feet above sea level), the dose attrit wed to cosmic radiation is approximately 26 mrera per year. Radionuclides commonly found in the atmosphere as a result o. osmic ray in'eractions include berylliam.7, carbon.14, tritium, and sodium 22. t l.9
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I Annual Environmental Operating Report 1991 Davis Ikme Nuckar P<wer Statk n Sources of Exposure to ahe Puhtle Natural
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it! tote: Shades portten indicates sammade radietton. Source: National Couned on Radiation Protestion I sad Wessurements. NORP Report No.93. Figure 13: A very Srnall annual dose to the public results from the nuclear power industry. Actually, the most significant annual dose the average indivkiual receives is that from naturally occurnng radon.
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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 tncir bodies is a mixture I' of all carbon isotopes, both non radioactive and radioactive. , In fact, because radioactive carbon 14 has a known half life of 5730 years ' and exists in all living things, archaeologists can use carbon dating to determine the age of a fossil or other anifact. After an organism dies, it no longer takes up carbon, and the radioactive carbon 14 present in its body continues to decay. Thus, archaeologists can estimate the point at which it no longer assimilated radioactive carbon in its tissues (i.e., the point of death). Another common naturally occurring 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 rad!ation radon. According to the National Council on Radiation Protection (NCRP), over half of the radiation dose the average American receives is 1-10
1 Annual Envimnmentat Operating Repon 1991 Davh.lkue Nuclear Power Staten attributed to r, don. 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 at2d migrete through air filled pores in the soil to reach the atmosphere. Radon occurs in all soils, but because it is a daughter product of uranium, it occurs in higher concentrations in rocks (and soils derived from rocks) with high concentrations of uranium, such t.s black shales, granites, phosphate rocks and carbonate rocks. Radon occurs indoors as a result of radon in the soil or rock under the building or radon in building materials, water suppeles, 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. Ilowever, the primary source of indoor radon !s that which diffuses into the building from the underlying soil or rock. Radon inay en'er buildings through the walls, floors vents and other openings. Although radon can migrate through .icracked slabs, slabs with cracks or 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 of uranium content of the soil:
. weather conditions constructions methods
- presence / absence of any cracks or openings in the foundations Some weather conditions, such as low pressure systems or increased rain fall, act to force radon out of the soil at an increased rate. In addition, construction methods affect indoor ,adon concentrations. Buildings built on a slab with no crawl space, scaled to prevent energy loss, those with basements, and those without fully ventilated crawl spaces tend to be linked to higher radon concentrations.
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. 1 11
l Annual Environmental Operating Repon 1991 Davh llesse Nucicar Power Statkin i Radon related health concerns stem from the exposure of the lungs to this j radioactive gas. Radon emits alpha radiation when it decays. Alpha ) radiation can easily be stopped by a person's dead &. layer. Ilowever, alpha radiation can cause damage to internal tissues when ingested or I inhaled. As a result, exposure to the lungs is of greatest concern, especially ' as the only recognized health effect associated with exposure to radon is an increased risk of lung cancer. Radoa can be detected in one of several ways. 'Ihree common methods used presently to detect radon in homes and other buildings are as follows:
. Chareaal canister method:
Charcoal canisters, which absorb 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 analyzed. From this information, the laboratory can determine the approximate eta:entration of radon gas required to produce the decay prod-ucts measured.
. Alpha track method:
Alpha track detectors utilize a radiation sensitive film When the alpha ensissions 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 laberatory for analys!s. At the laboratory the number of tracks on the film are counted. This information is used to estimate the average concentration of radon in the building dur-ing the period that the film was exposed.
- Electronle monitoring method:
Elect.onic monitors are available which continuously detect the number of negative ions produced by decaying radon and pro-vide instantaneous l' formation on the concentration of radon in the air. The United States Environmental Protectior Agency has provided guidelines for radon monitoring in homes and other buildings, and has developed recommendations for concentrations at which to take corrective actions. Further information on radon, its detection , and actions to reduce the radon concentration in buildings can be obtained by contacting the state radon program office at the following address: 1-12
on Annual Environmental Operating Report 1991 Davis Ikme Nuclear Power Station Ohio Department of llealth P.O. BOX 118 . _ Columbus, Onio 43266-0118 (614) 481-5800 (800) 523-4439 (in Ohio Only) Man-Made Radiation in addition to naturally occurring radiation and radioactivity, people are also exposed to man made radiation. The largest sources of exposure include medical x rays and radioactive pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium 90, cesium 137, carbon 14, and tritium. As shown in Figure 13, 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 maximurn whole body doses to the public due to radioactivity released in liquid and gaseous effluents from Davis-Besse in 1991 were only 0 07 and 0.04 mrem, respectively. Each of these doses is less than the dose an Individual would neceivt. from one coast-to-coast jet flight (3 mrem). Health Effects Of Radiation Studies The effects of ionizing radiation on human health have been under study for more than eighty years. Scientists have obtained valuable knowledge through the study oflaboratory animals that were exposed to radiation under e stremely controlled conditions. However, it has proven difficult to relate the biological effects of irradiated laboratory animals to the potential health effects on humans. llence, much study has been done with human populations that were radiated 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 "tipp'ng" the paint brushes with their lips; uranium miners, who inhaled large amounis of radioactive dust while mining pitchblende (uranium ore); and early radiologists, who a: cumulated large doses of radiation while unaware of the potential hazards. 1-13
- I Annual Enytronmental Operating Repin 1991 Davis-Desse Nuc! car Power Station i . The studies performed on these groups have increased our knowledge of the 7
- health effects from large doses of radiation. Ilowever, less is known about the effects 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 a low level radiation exposure. The effects predicted in this manner have never been actually observed in individuals exposed to low level radiation. Ilowever, this assumption provides a highly conservative model of radiation induced health effects, because it most probably overestimates the risks associated with receiving low doses of radiation.
Health Risks Since the actual effects of exposure to low radiation are difDeult to assess, scientists often refer to the risk involved. The problem is one of evaluating alternatives, of comparing risks and weighing them against benefits. People make decisions involving risks every day, such as whether to(not to) wear seat belts; or whether to (not to) smoke cigarettes. Risks are a part of everyday life. He 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 automobile accidents, By building safer cars or wearing seat belts, this risk can be reduced, however, even a parked car is not risk free. 'You could choose not to drive, but even as a pedestrian or a bicyclist you may be injured by cars. Reducing the risk ofinjury from automobiles to zero requires moving to a place where there are no automobiles. While most people accept the risks inherent in such activities as smoking and j driving to work each day, some people seem to feel that their energy needs should be met on a risk-free basis. Ilowever, this is impossible , no matter what the energy source. The buming of fossil fuels can have a negative impact on the environment, and even the use of hydropower entails risks, including that of a mptured dam and 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 y hear, smell, taste or feel ionizing radiation. Sometimes, if we have another source of information, we may believe the widespread myths about ionit;ng l { l-14 L__ _ .-- - - . -- _ , -_-
Annual Environmental Operating Report 199t Davis llene Nuc!rar Power Station radiation and its health effects. But this is not true of other potentially harardous things for which we have the same lack of sensory perception such as radio waves, carbon monoxide, and small concentrations of numerous caticer causing substances. Although these risks are just as real as the risks concerning in radiation. Most risks are with us throughout our lives, and their effects can be added up over a lifetime to obtain a total effect on our liws. Table 12 shows a number of different factors that decrease the avenge life expectancy of individuals in the United States. Table 1-2: Risk Factors Factors Estimated Decrease in Average Life Expectancy
- Male rather than female 5.0 years Overweight by 30% 3.6 years Cigarette smoking: 1 pack / day 7.0 years 2 packs / day 10.0 years Heart diseases 5.8 years Cancer 2.7 years City Living(not rural) 5.0 years 125 operating nuclear power stations less than 12 minutes
- The typical life span in the United States is now 76 years for women and 71 years for men.
The American Cancer Saciety estimates that about 30 percent of all Americans will develop cancer at some time in their lives from all possit le causes. Thus, in a grog 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 millitem in addition to the natural and man-made sources of radiation they are normally exposed to then there is an increased probability q that would indicate one additional person from that group mr; develop cancer during his/her lifetime. This increases the risk from 30 percent to 30.01 percent. For comparison, the average offsite dose to individuals in the population due to the operation of the Davis-Besse Nuclear Power Station is significantly less than one millirem (0.001 millirem in 1991). If it is 1-15 ,
l Annual Environmentat Operating Report 1991 Davis Ikne Nuclear Power Statkm considered that the Davis-Besse Nuclear Power Station will operate for the remainder of its license at this rate, the probability of even one person in the population developing a cancer due to the presence of the, Davis Besse Nuclear Power Station is extremely small. The preceding table should provide you with an idea of the risks asscciated 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 decisions that ha benefits derived from a particular activity (e.g., driving an automobile) outweigh the costs associated with that activity (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 associated with nuclear power in perspective. 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 future. In 1980, nuclear power accounted for only eleven percent of the electricity produced in the United States (Figure 1-4). By the end of 1991, however, this number was greater than twenty percent. At the same time, dependence on oil as an energy source decreased by more than half. By decreasing the nations' degndence on oil. dependence on foreign oil supplies also decreases, thereby ensuring the nation can continue to be self sufficient in meeting the enetdy needs ofit's private and business sectors. Nuclear power offers several advantages over alternative sources of electric energy: nuclear power has an excellent safety record dating back to 1957 when the first commercial nuclear power station began operat-ing, uranium, the fuel for nuclear power stations, is a relatively inex-pensive fuel that is renoily available in the United States, 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 and how Davis Besse uses nuclear fuel and the fission process to produce electricity. 1-16 j
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- COAL nuou An in o 1980 19 91 mm m mm m.m .u,m, Figure 1-4 : Since 1980, the nations dependence on nuclear power for supplying electricity has almost doubled. This has led to the decrutsed dependence tm Ihe amoun' of oil and natural gas needed to pr(m.tuce electncity. The advantaFe to this is less cmtui(m to the atmosphere which may cause acid rain.
Nuclear Power Prr.Netion Electricity is produced in a nuclear power station in essentially the same way as in a fossil. fueled statien. Ileat changes water to steam that turns a turbine. In a fossil-fueled station, the fuel is burned in a furnace, which is also a boiler. Inside the boiler, water 1s turned into steam, in a nuclear station, the furnace is replaced by a reactor containing a core of nuclear fuel, primarily uranium, lient is produced when the atoms of uranium are split, or fissioned, inside the reactor.
- WI... 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 the bond is weak enough, the nucleus can be split when bombarded by a free neutron (Figure 15). This causes the entire atom to split, producing smaller atoms, more free neutrotis, and heat. In a nuclear reactor, a chain reaction of fission events provides the heat necessary to boil the water to produce steam. 1 17 t l l l
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O nurm / O PROTON w HEAT Figure 15: Whcn a heavy atom, sucn 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 petxas can continue indefinitely in a chain reaction. Nuclear Fuel The fissioning of one uranium atom releases approximately 50 million times more e+.rgy that tne combustion of a single carbon atom common to all fossil fuels. Since a single small reactor fuel pellet contains trillions of atomr., each pellet can release an extremely large amount of energy. The amount of electricity tha: can be generated from three small fuel pellets would require about 3.5 tons of coal or 12 barrels of oil to generate. Nue' ear fission occurs spontaneously in nature, but these natural occurrences cannot sustain themselves because the freed nuetrcns either are absorbed by non fissionable atoms or quickly decay, in contrast, a nuclear reactor minimized neutron losses, thus sustaining the fission process by several means: using fuel that is free of impurities thtt might absorb the freed neutrons; l-18
Annual Environmental Operating Report 1991 Davis 13 case Ntclear Power Station
- increasing the concentration of the rarer fissionable isotope of uranium (U 2My rt!6tive to the concentration of U 238, a more common iwtope that does not fission easily;
- and 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 compared to the more abundant U-238 when it is mined. Before it can be economically used in a nuclear reactor, it is enriched to approximately three percent U 235 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. After the uranium is separated from the earth and rock in the ore, it is concentrated by a milling process. After milling the ore to a granular form and dissolving out the uranium with acid, the uranium is converted to uranium hexalluoride (UF6). A chemical form of uranium that exists as a gas at temperatures slightly above room temperaNre. The uranium is then highly purified and shipped ;o an enrichment facility where gaseous diffusion converters increase the concentration of U-235 in the fuel. The enriched gaseous UF6 is then converted into powdered uranimn dioxide (UO 3), a highly stable ceramic materia!. The UO 2powder is put under high pressure to form fuel pellets, each about 5/8 inch long and 3/8 inch in diameter (refer to Figure 1-6). Approximately five pounds of these pellet 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 of heat, radiation and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods. The Reactor Core Two hundrta eight fuel rods comprise a single fuel assembly. The reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fuel rods, the fuel assembly also contains 16 vacant holes for the insertion of control rods, and one vacant hole for an incore monitoring probe. This probe monitors temperature and neutron levels in the fuel assembly. The Davis Besse reactor vessel weighs 838,000 pounds, has a diameter of 14 feet, is 30 feet high, and has 81/2 inch thick steel walls. 1-19
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Fuel Red Fuel Assembly Reacter Vessel Figure 16: Tbc reactor core at Davis Besse contains 177 fuel assemblics. Each assembly contains 208 fuel rods. Each fuel rod is filled with approximately five pounds of fuel penets, each pettet approximately 3/8 inch in diameter and 5/8 inch long. Fission Control The fission rate ins'de the reactor core is controlled by raising or lowering control rod assemblies into the reactor core. Each assembly consist of " fingers" containing silver. Indium, and cadmium metals that absorb free neutrons, thus disrupting the fission chain reaction. When control rod assemblies are slowly withdrawn from the core, fissioning begins and heat is produced. If the control rod assemblies are inserted rapidly into the reactor core, as during a plant " trip," the chain reaction ceases. A slower acting (but more evenly distributed) method of fission control is achieved by the addition of a neutron poison to the reactor coolant water. At Davis Besse, boric acid can be concentrated or diluted as necessary, in the coolant to achieve the desired level of fission. After boric acid is added to the coolant water, the acid turns into baron 10. Boron-10 readily absorbs free neutrons, hence the term " neutron poison," forming boron-11. The boron 11 in turn decays to non-radioactive lithium by the emission of an alpha particle. Reactor Types Virtually all of the commercial reactors in this country are either bolling water reactors (BWRs) or pressurized water reactors (PWRs). Both 1-20
Annual Environmental Operating Repan 1991 Davis Dease Nuc! car Power Statkr types are also called light water reactors (LWRs) 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 reactions are called heavy water reactors, or IIWRs. In BWRs, water passes through the core and boils into steam. The steam passes through separators which removes water droplets. The steam then travels to dryers before entering the turbine. After passing though the turbine the water returns to the core to repeat the cycle. In PWRs, the reactor water or coolant is pressurized to prevent it from boiling. The hot water is pumped to a steam generator (heat exchanger) where its heat is transferred to a separate water supply. The water inside the generator boils into steam which is used to turn the turbine. Davis Besse uses a PWR, while the Perry Nuclear Power Plant, owned by Toledo Edison's sister company, Cleveland Electric illuminating, tues a BWR. The Davis Besse and Perry Nuclear Power Stations are the only two commercial reactors in the State of Ohio. Future Reactor Types In the future, the BWRs and PWRs may not be the only types of commercial reactors in operation in the United States. Presently, several reactor types are being designed or developed which would be licensed by design or class. The new reactors will be smaller and nare snodular units, approximately 80-600 Megawatts electric (MWe) in size. These proposed reactors would have more passive systems relying on gravity, natural air flow (convection) and evatrration cooling systems in the event of a loss of coolant situation. Also, these reactors could be fabricated at the manufacturers and shipped to a plant for installation. This would save money and time during construction. The following paragraphs discuss five reactors that may be licensed in this country. Advanced Pressurized Water Reactors The Advanced Pressurized Water Reactor (APWR) or passive water-cooled reactor by Westinghouse Electric Corporaticn is a 600 MWe reactor which replaces many active systems with more passive ones. The AP-600, Westinghouse's version, is similar to current PWRs with the following exceptions. The containment buildmg is larger than usual. Safety features 1-21
I Annual & dronmental Operating Report 1991 Davis Besse Nuclear Power Station that aid 'n the maintenance of the building pressure and the prevention of a reactor vessel rupture include cool.ng sprioklers located above the. reactor vessel and air baffles that allow natural convection cooling. Gravity Feed Emergency Flood Tanks located above the core allow water to free-flow down in case of a joss of coolant situation. The reactor uses a uranium dioxide pelle: as fuel and operates at 60TF. Construction of the AP-600 is estimated to take five years. Since prefabricated modules (. reactors) can be purchased and installed, construction time and cost would be considerably less than building a reactor at a site. ! Figure 17:De AP600.shown bere,is fabricated at the snknufacturers' and shipped to a site for instadlation. his t: duces both ( V yy construction time and cost without - L)nA M P compmmising plant safety. ""*" /, NMan g N.- 1
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O , in the reactor vessel. This reduces the amount of shielding required and the number of welds in the system. Also, the control systems are driven electromechanically rather than hydraulically, thereby reducing maintenance. Safety systems are more redundant, requiring less operator intervention. The ABWR would be capable of producing 1350 MWe and would use uranium dioxide as a fuel. Tokyo Electric Power Company in Japan has plans to build the first ABWR once pre-approved certification is completed. The plant construction time is estimated to take five to six yeats. 1-22
_ _ .._. _ . . _ _ _ _ ._ _ _ _ .. . - .- _.._______--___.__m__._.. _ t i Annual Environmental Operating Report 1991 Davis Beene Nuclear Power Station i l Simplified Boiling Water Reactor (SBWR) , The General Electric Company is also developing a second type of BWR ;
. called the Simplified Boiling Water Reactor. This design focuses on safety l and simplicity, relying on gravity and natural circulation for cooling during a ;
loss of coolant situation. The reactor core is at the bottom of the containment building. A Gravity Feed Cooling Tank, located above the core, is used to ' flood the core during a loss of coolant situation. This reactor is considered an inherently safe design which means reactor operator would have 72 hours to respond to a loss of coolant situation instead of 20 minutes like current i reactors. Also, this response time can be lengthened by adding more water to the core. The SBWR would produce 600 MWe and use a uranium dioxide fuel. Pre approval certification is targeted for 1995, with construction time - being 30 months. t
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t l Annual Envimamental Operating Report 1991 Davis Besse Nuclear Power Stat 6on Liquid Metal Reactor Presently, Os 'eral Electric Company is designing their version of a Liquid Metal Ret ctor (LMR) called PRISM (Power Reactor Inherently Safe Module). The PRISM is considered walk away safe because the reactor coolant surround the core is liquid (molten) sodium. Theoreticelly, the sodium would never reach its boiling point where it would boil into vapor and uncover the reactor core. De PRISM uses a three loop system to produce steam for the turbine. De first loop has liquia sodium passing I through the core to be heated. The sodium from the first loop goes to a heat exchanger and heats the liquid sodium in the second loop. This sodium then travels to a second best exchanger where it converts water to steam, for running the turbine. By using sodium as the coolant the primary system can operate at higher temperatures without being pressurized. Since the reactor operates at a higher temperature (1156T), a thermal efficiency of 40% is achievable compared to 33% for current BWRs and PWRs. A group of nine LMRs with a capacity of 155 MWe cach, would form a 1345 I MWe plant. He reactors are fueled with uranium plutonium zirconium alloy. The PRISM is a breeder reactor, which means it converts uranium-238 to plutonium 239. The Pu.239 would later be used to fuel another nuclear plant. One major draw back of the PRISM is that sodium is highly reactive with air and water, but design features eliminate most of the problems. I Modular 11igh Temperature Gas-Cooled Reactor The last reactor being considered in the United States is the Modular High Temperature Gas-Cooled Reactor (HTGR) which uses helium as the reactor coolant, it is being designed under the cooperation of General Atomics, Gas Cooled Reactor Associates, and Electric Power Research InstitWe (EPRI). In , the HTGR, helium hested in the reactor core passes to a heat exchanger, tk a ' back to the reactor again. In the heat exchanger, water is converted to steam to run the turbine,just as in PWRs. Since there is no possibility of phase change of reactor coolant, the system can operate at a high temperature (12684) without pressurization, allowing thermal efficiency of 40% The core of the HTGR is made of graphite blocks with vertical and horizontal holes drilled through the blocks. In the vertical holes fuel rods, containing carbon and silicon carbide coated uranium pellets and control rods are inserted. He horizontal holes allow helium to pass through and be heated before going to the heat exchangers. This design is considered walk 1-24
Annual Emironmental Operating Report 1991 Davis-Ikane Nuclear Power Station
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I Annual Environmental Operating Report 1991 Davis Benac Nuclear Power Station Station Systems The following paragraphs describe the various sys: ems illustrated in Figure 1-10. 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) GOLD < Emergency Core Cooling System SCARLET - Auxillary Feedwater System GREY - Pressurizer and Associated Structures , 1 o '-m Davis-Besse Nuclear Power Station Unit No.1 _ m. - : m e, f
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l l Annual tvironmentat Operating Report twt Davn.Deze Nuclear Power Station Containment Building and Fission Product Release Barriers , he conteloment building at Davis Besse houses the reactor vessel, the pressurizer niid two steam generators. He building is constructed of an inner 1 inch thld steel liner or containment vessel, and the shield building with steel reinfxced concrete walls 2 feet thicL The shield building protects the conia'nment vessel from a variety of environmental factors, and provides an area for a nep,ative pressure boundary around the steel containment vesse!. In the evera that the integrity of the shield building is compromised (e.g., a crack develops), this negative pressure boundary ensures that any airborne raabacthe contamiration present in the conbinment vessel is prevented from lesking out into the environment. It accomplishes this by maintaining the pressure inside the shield building lower than that outdoors, tnus forcing clean outside air to leak in, while making it impossibic for the contaminated air inside the containment vessel to leak out. He free standing containment vessel is the third in a series of barriers that prevent the release of Ussion products in the unlikely event of an accident. The first barrier to the release of Ussion products is the fuel cladding itself. He second barrier is the walls r4 the primary system, i.e. the reactor vessel, steam generator and associated piping. The Steam Generators The steam generators at Davis Besse perform the same function as a boiler at a fossildueled power station. He steam generator uses the heat of the primary coolant inside the steam generator tubes to boil the secondary side feedwater (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, heat must also be removed from the core even after reactor shutdown in order to prevent damage to the fuel cladding. Herefore, pumps maintain a continuous flow of coolant through the reactor and steam generator. Primary loop water (green in Figure 1-10) exits the reactor at approximately 606aF, passes through the steam generator, transferring some of its heat energy to the secondary loop water (blue in Figure 1 10) without ever actually coming it.
- contact with it. Primary coolant water exits the steam generator at approximately 5580F to be circulated back into the reactor where it is again heated to 606oF as it passes up through the fuel assemblies. Urider ordinary ,
conditions, water inside the primary system would boil long before it reached such temperatures. However, it is kept under a pressure of approximately 2,200 pounds per-square inch (psi) at all times. This prevents the water from 1 28 l l
I Annual Environmentel Operating Repon 199t Davis Desse Nuclear Power Statkin boiling and is the reason the reactor at Davis Besse is called a Pressurized Water Reactor. Secondary loop water enters the base of the steam generator at approximately 40Cyr ad under 1100 psi pressure. At this pressure, the water can easily boil into steam as it pa:ses over the tubes containing the primary coolant water. Both the primary and the secondary coolant water are considered closed loop systems. This means they are designed not to come in physical contact with one another. Rather, the coolant (i.e., water) contained in each loop transfers beat energy by the procens of conveetjon. Convection is a method of heat i s transfer that can occur between two fluid media. it is the same process by v hich radiators are used to heat homes. The water circulating inside the raGla:o* is Fyrsted from the air (a 'iluid* mediam) by the metal piping. The Turbine Generatur The turbine, main generator, and the condenser are all housed in what is commonly referred to as the Turbine Building. The purpose of the turb!ne is to convert the thermal energy of the steam produced in the steam generator (referred to as main steam, red in Figure 1-10) to rotational energy of the turbine -generator shaft. The turbine at Davis Besse is actually composed of one six. stage high pressure turbine erid two seven stage low pressure turbines aligned on a common shaft. A turbine stage refers to a set of blades. Steam enters at the center of each turbine and flows outward along the shaft in opposite directions through each successive stage of blading. As the steam passes over the turbine blades, it loses presscre. Thus, the blades must be proportionally larger in successive stages to extuct enough energy from the steam to rotate the shaft at the correct speed. The purpose of the main generator is to convert the rotational energy of the shaft to electrical energy for commercial usage and support of station systems. The main generator is composed of two par *s, a stationary stator that contains coils of copper conductors, and a rotor that supplies a rotating magnetic field within the coils of the stator. Electrical current is generated in the stator portion of the main generator. From this point, the electric current passes through a series of transformers for transmission and use throughout northern Ohio. The Condenser After the spent steam in the secondary loop (blue in Figure 1-10) passes through the high and low pressure turbines, it is collected in a cavemous 1 29 I (
i Annual Environmental Operating Report 1991 Davis. Deme Nuc1 car Power Statice condenser several stories tall and containing more than 70,000 small tubes. Circulatlog (elre) water (yellow in Figure 1 10) goes to the coollag tower after passing through the tubes inside the condenser. As the steam from the low pressure turbines passes over these tubes, it is cooled and condensed. The condensed water is then purified and reheated before being circulated back into the steam generator again in a closed loop system. Cire water forms the third (or tertiary) and final loop of cooling water used at the Davis Besse Station. As the primary to secondary interface, the secondary to tertiary interface is based on a closed loop design. In other words, the circulating water is able to cool the steam in the condenser, without ever actually coming in contact with it, by the process of convection. Even in the event of a primary to secondary leak, the water vapor exiting the Davis.Besse cooling tower would remain non radioactive. Closed loops are an integral part of the design of any nuclear facility. his design feature greatly reduce the chance of environmental impact from station operation. The Cooling Tower The cooling tower at Davis-Besse is easily the most noticeable and the most misunderstood, feature of the plant. %e tower stands 493 feet high and the diameter of the base is 411 feet. The two pipes circulating 480,000 gallons of - water per minute to the tower are 9 feet in diameter. This is enough water to fill a swimming pool the size of a football fictd 32 f s deep. The purpose of the tower is to recycle water from the condenser by cooling it. Aftc passing through the condenser, the circulating water has warmed te - approximately 1000F. In order to cool the water back down to around 70* F, the circulating water er.ters the cooling tower about 40 feet above the ground. The water is sprayed evenly over a series of baffles called Hllsbeets 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 cocdng tower. Even so, approximately 98 percent of the water drawn from Lake Eric for station operation can be recycled through the cooling tower for reuse. A small portion of the circulating water is discharged back to lake Erie at es:entially the same temperature it was withdrawn earlier, in 1991, the average difference between the intake and discharge water temperatures was only 6.20F, The slightly warmer discharge water had no 1 30 l
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I Annual Environmentat Operating Report 1991 Davis-Besse Nuclear Power Station ; adverse environmental impact on the area of lake surrounding the discharge point. ; Many power stations, both nuclear and fossil. fueled, utilize cooling towers to l cool station discharge water. Federal regulations governing the water temperature of rivers, lakes, and bays require that power station operation introduce relatively small changes in water temperature. 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 i1 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 addition, an increase in water temperature during the summer months could decrease the , water's oxygen content and could therefore precipitate a fish kill. Miscellaneous Station Safety Systems 6 The gold system in Figure 1 10 is part of the Emergency Core Cooling System (ECCS) housed in the Aux 1111ary 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 g* reactor by either high pressure igjection pumps, a core flood tank, or low , pressure igjection pumps. Borated water can also be sprayed from the l ceiling of the containment ver.sel to cool and condense an'y steam that may escape from the primary system. The grey system illustrated in Figure 1-10 is responsible for maintaining the primary coolant water in a liquid state. It accomplishes this by adjusting the , pressure inside the primary system. Heaters inside the pressurizer turn water into steam. 'Ihis steam takes up more space inside the pressurizer, therefore increasing the overall pressure inside the primary system. The pressurizer is also equipped with spray heads that shower cool water over the steam in the pressurizer. In this case, the steam condenses and the overall pressure inside the primary system drops. The quench tank pictured in Figure 1-10 is
- simply where excess steam is directed and condensed for storege.
The scarlet system in Figure 1-10 is part of the Auxilliary Feedwater System, a key safety system in event the main feedwater supply (blue in 1 31
Annual !!nvirunmental Operating Repon 1991 Davis.tkme Nuclear Power Station 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 Condensate storage Tanks. He Auxiliary Feedwater System is housed in the Turbine Building along with the turbine, main generator, and the a.ondenser. Reactor Safety and Summary Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. 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 an electrical shock to a p:rson handling the flashlight. Many safety features are also squipped with several backup systems to ensure that any possitie accident would be prevented from causing a serious health s. or safety threat to the pubhe, or serious impact on the local environment, Davis-Besse, like all U.S. nuclear units, has many overlapping, or redundant !$ safety features. If one system should fail, there would still be back up 4
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systems to assure the safe operatian of the Station. During normal operation, the Reactor Control System regulates the power output by adjusting the position of the control rods ' Die reactor can be automatically shut down by a separate Reactor Protection System that causes all the control rod assemblies to be quickly and completely inserted into the. reactor core, stopping the chain reaction. To guard against the possibility of a loss Of Coolant Accident, the Emergency Core Cooling System is designed to pump reserve water into the reactor automatically if the reactor coolant pressure drops below a predetermined level. The Davis-Besse Nuclear Power Station wcs designed, constructed and operates to produce a reliable, safe, and environmemally sound source of , electricity. 1-32
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1 l l l l Davis-Bene Nucicar Power Station 1991 Annual Environrnental Operating Reprt
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Description of the Davis-Besse Site l The Dr.vis Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the southwestern shore of Lake Ele,just north of the mouth of the Tcussaint River. The site lies north and east of Ohio State Route 2, approxi- i mately 10 miles northwest of Port Clinton,7 miles north of Oak liarbor, and 25 miles east of Toledo, Ohio (Figure 1-11). This section of Ohio is flat and marshy, with maximum elevations of only a few feet above the level of Lake Erie. The area originally consisted of swamp forest and marshland, rich in wildlife but unsuitable for settlement ' and farming. _During the nineteenth century, the land was cleared and drained, and has been farmed successfully since. Today, the terrain consists , of farmland with marshes extending in some places for up to two miles in-land from the Sandusky lake Shore Ridge.
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I m Davis Besse Nuclear Power Station 1991 Annuallhwironmental Operating Repwt More than half of the Davis Besse site area is marshland. A small portion of the site was farmland. The marshes are part of a valuable ecological re- ) source, p~'viding a breeding ground for e variety of wildlife, and a refuge for i i migratory o., M. Major species of birds using this portion of the Lake Erie marshes include mallards, black ducks, widgeon, egrets, great blue herons, blue winged teal, and Canada geese. In fact, there are hundreds of geese liv-ing right on site. Bald eagles, osprey, swans, great horned owls, and a large j number of hawks are also seen in the area. The site includes a tract known as Navarre Marsh, which was acquired for the U.S. Bureau of Sport Fisheries . ! and Wildlife, Department of the Interior. In 1971, Toledo Editon purchased l the 188 acre Toussaint River Marsh. De Toussaint River Marsh is contigu-ous with the 610 acre Navarre Marsh section of the Ottawa National Wildlife Refuge. t Most of the remaining marshes in the area have been maintained by private ' hunting clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife. There are some residences along the take shore used mainly as summer homes. However, the major reson , area of the county is farther cast, around Pon Clinton, Lakeside, and the Bass Islands. The immediate area near Davis Besse is sparsely populated; Ottawa County had a population of only 40,029 in the 1990 census. He nearest incorpo- ' rated communities are:
- Port Clinton - 10 miles southeast, population 7,106
- Oak Harbor - 7 miles south, population 2,637-
- Rocky Ridge . 7 miles west southwest, population 425
- Toledo (the nearest major city)- 25 miles west, population 322,943 .
-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 ofincome in the area. He main industries within five miles of the site ere located in Eric In- ,
dustrial 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. Rese include Magee Marsh, Turtle Creek, Crane Creek State Park, and the Ottawa National Wildlife Refuge. Magee Marsh and Turtle Creek lie between three and six 1-34
Davis-11csse Nuclear ikwer Station IW1 Annual Environrnental Operating itepwt l i miles WNW of the Station. Magee Marsh is a wildlife preserve allowing , i public fishing, nature study, and controlled hunting in season. Turtle Creek, a wooded area at the southern end of Magee Marsh, offers boating and fish- i ing. Crane Creek State Park is adjacent to Mager Marsh and is a popular pic-nicking, swimming, and fishing area. The Ottawa National Wildlife Refuge ; lies four to nine miles WNW of the site,immediately west of Magee Marsh. I I { l 1-35 i i
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Davis Incue Nucicar Ibwer Station 1991 Arnuat Envirmmental Operaung Repyt t The 1991 Sununary of Radioactivit Released in Liquid and Gaseous Effluents Protection Standards Soon after the discovery of x tays in 1895 by Wilhelm Roentgen, the poten-tial hazards of ionizing radiation were reognized and efforts were rnade to establish radiation protection standards. The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protecthn and Wasurements (NCRP). Many of these recommendations have been given legislative authority through publication in the Code of Federal Regulations (G E) by the Nuclear Regulatory Commission (NRC). The main objective in the control of radiation c~,posure is to ensure that any necessary exposures are kept as low as is reasonably achievable (ALARA). The ALARA principle tpplies to reducing radiation exposure both to the in. dividual working at Davis Besse and the general public. " Reasonably achie-vable" means that exposure reduction is based on sound economic decisions and operating practices. By practicing ALARA, Davis-Besse and Cet>terior Energy minimize health risk and environmental detriment and ensure tha doses do not exceed certain specified limits. Limits To protect the general public, guidelines and limits have been established governing the release of radioactivity in liquid and gaseous Station effluents. The Code of Federal Regulations, Title 10, Part 50, Appendix I(10CFR50, App.I) provides guidelines for the Technical Specifications which are part of the license authorizing nuclear reactor operation. Davis-Besse's Technical Specifications restrict the release of radioactivity to the environment and the resulting dose to the public. Table 1-3 presents these limits. MT l-36
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Davis Besse Nuc1 car Power Sta'tlan 1991 Annual Envuunmental Opurating Repon . Table 13: Dose Limits to a Member of the Public-Source NRC Limits for Davis-Besse Liquid Emuents _ Whole body less than or equal to 3 mrem / year l Organ less than or equal to 10 mrem / year i l Gaseous Emuents Noble Gases t- gamma air dose less than or equal to 10 mrad / year beta air dose less than or equal to 20 mrad / year Iodine 131, tritium and . particulates with half-lives greater than 8 days . less than or equal to 15 mrem /yr The Davis Besse limits are only a small fraction of the dose limits estab-lished by the Environmental Protection Agency (EPA). In its environmental dose standard,40 CFR 190, the EPA established euvironmental radiation protection standards for nuclear power operations. These standards for nor-mal operation provide that the dose from all discharges of radioactivity , should not exceed: 4 25 mrem / year to the whole body,
. 75 mrem / year to the thyroid, and
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Sources of Radioactivity Released E Through the normal operation of a nuclear power station, most of the fission
- products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component--
and structure surfaces which have been activated are present in the primary-coolant water. The three types of radioactive material released are noble g gases, iodine and particulates, and tritium. The noble gas fission products m the primary coolant are given off as a gas E when the coolant is depressurized. These gases are then collected by a sys : , i, L 1-37 i __ . ._
Davis-Besse Nuclear Ibwer Station 1991 Annuallinviructnental Operating Report tem designed for gas collection and storage for radioactive decay prior to re-lease. Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primaty coolant system. These liquids are col-lected through a series of floor and equipment drains and sumps. All liquids of this nature are processed and carefully monitored prior to release. Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologi-cally and chemically nonreactive. They do not concentrate in humans or oth-er organisms. They contribute to human radiation exposure by being a source of extemal 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 at-mosphere. In 1991, approximately 1160 curies of noble gases were released in gaseous effluents. The calculated offsite gamma and beta air doses due to the release of this activity were 0.015 mrad and 0.047 mrad, respectively, and are less than 0.25% of their respective Technical Specification limits. Additional dose information is provided in Table 1-4 and page 1-43. Iodine and Particulates Annual releases of radioisotopes of iodine and 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 discht.rge. Se predominant radioindine released is iodine-131 with a half-life of approximately eight days. 'Ihe main contribution of radioactive iodine to human exposure is internal exposure of the thyroid gland, where the body concentrates iodine. The principal radioactive particulates released are fission products (cesium-134 and cesium-137) and activation products (cobalt-58 and cobalt-60). Radioactive cesiums and cobalts contribute to internal radiation exposure of tissues such as the muscle, liver, and intestines. These particu-lates are also a source of external exposure if deposited on the ground. l-38 l l 1
I Davis-Besse Nuclear Power Station 1991 Annual Environmental 0; crating Repcrt During 1991, the amount of radioactive iodine and particulotes (excluding tritium) released was approximately 0.01 curie in gaseous effluents and 0.17 curie in liquid effluents. These releases were well below all applicable regu-latory limits. Additional dose information is provided in Table 1-4 on page 1-43. Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide ; in liquid effluents. It is also present in gaseous effluents. Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) present in the water and with the boron in the primary coolant used foi reactivity control of the reactor. When tritium is ingested or inhaled it disperses throughout the body and exposes all tissues until it is eliminated. The amount of tritium released in 1991 was approximately 64.6 curies in gas-eous effluents and 325.6 curies in liquid effluents. The associated doses were well below all regulatory limits, and additional dose information is provided in Table 1-4. Processing and Monitoring Effluents are strictly controlled to ensure radioactivity released to the envi-ronment is minimal and dNs not exceed release limits. Effluent control in-cludes 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 effluent and environmental monitoring. The radioactive waste treatment systems at Davin-Besse are designed to col-lect and process the liquid and gaseous wastes which contain radioactivity. For example, the Waste Gas Decay Tanks are holding tanks which allow ra. dioactivity in gases to decay prior to release via the station vent. Radioactivity monitoring systems are used to ensure that all relesr.es are be-low regulatory limits. These instruments provide a continuous indication of the radioactivity 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 setpoints are low to ensure the limits will not be exceeded. If a monitor alarms, a release from a tank is automatically stopped. 1-39
Davis-Desse Nuclear Power Station 1991 Annual Environmental Operating Report All wastes are sampled prior to release and analyzed in a laboratory to identi. fy the specific concentrations of radionuclides being released. Sampling and analysis provide a more sensitive and precise method of determining effluent composition than with monitoring instruments alone. A meteorological tower is located in the southwest sector of the Station. It is linked to computers which record the meteorological data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public. Beyond the plant, devices maintained in conjuction with the Radiological En. viromnental Monitoring Program constantly sample the air in the surround-ing environment. Frequent samples of other environmental media, such as water and vegetation, are also taken to determine if buildup of deposited ra-dioactivity has occurred in the area. Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to radioactivity. The major pathways of concern are those which could cause the highest calculated radiation dose. These pathways are determined from the type and amount of rarticactivity released, the envimn-mental transport mechanism, and the use of the environment. The environ-mental transport mechanism includes consideration of physical factors, such as the hydrological (watei) and meteorological (weather) characteristics of the area. Information on the water flow, wind speed and wind direction at the time of a gaseous or liquid release is used to evaluate how the radionu-clides will be distributed in the area. An important factor in evaluating the exposure pathways is the use of the environment. Many factors are consid-ered such as dietary intake of residents, recreational use of the area, and the location of homes and farms in the area. The externsi and internal exposure pathways considered are shown in Figures 1-12 and 1-13. The release of radioactive gaseous effluents involves path-ways such as external whole body exposure, deposition of radioactive materi-al on plants, deposition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radioactive in liquid 1 l-40
I Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Repcrt eftluents involves pathways such as drinking water, fish consumption, and direct exposure from the lake at the shoreline and while swimming. Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure path-way which will provice, for a specific nadionuclide, 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 other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest frac. tion of the dose is called the critical organ. h.".I_ $ $ U Y . l . 4
/ . nN<c NEE W tumme N.
o (~ .
\
nnIErs , {AJ ((oEEYisTv ma h :, [ ""Wrh / x l l Figure 1 12 he external exposure pathways shown here, are monitened thmugh the Radi-ological Environmental Monitoring Program (REMP), and are considered when calculating doses to the public. 1-41
Davis-Desse Nucicar Power Station 1991 Annual Envirurunental Operating Report on. 2632Z 1" m eeuurm m _ N
))
evMu"Y ub wrm, a i g fg g i w
</ m2xaw A
sE M
- AwaP7A Q o ym
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$ 7 Figure 1-13: Intemal exposure pathways include the methods by whid1 radioactivity could reach peopic amund the Station viathte foods they cat, the milk they drink, and the air they breathe.
Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body radiation exposure involves the exp( r tre of all organs. Most back-ground exposures are of this form. Both non-radioactive and radioactive ele-ments can enter the body through inhalation or ingestion. When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium col-tects in bone tissue. The total dose to organs from a given radionuclide depends on the amount of radioactivity present in the organ and the amount of time that the radionu-clide remains in the organ. some radionuclides remain for very short times due to their rapid radioactive decay and/or elimination rate from the body, while other radionuclides may remain in the body for longer periods of time. 1-42
I Davis.Besse Nuclear Power Statino 1991 Annual Dwirotuncatal Operating Report The dose to people in the area surrounding Davis-Besse is calculated for each liquid or gaseous release. The dose due to radioactivity released in gaseous effluents is calculated using factors such as the amount of radioactivity re-leased, the concentration of radioactivity beyond the site boundary, the weather conditions at the time of the release, the locations of exposure path-ways (cow milk, goat milk, vegetable gardens, and residences), and usage factors (inhalation, food consumption). The dose due to radioactivity re-leased in liquid effluents is calculated using factors such as the total volume of radioactive liquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption, shoreline and swimming fac- i tors). These calculations produce a conservative estimation of the dose. ReSultS The results of the effluent monitoring program are repo-ted to the Nuclear Regulato.y Commission in the Semiannual Radioactive Effluent and Waste Dispcsal Repo-t. For 1991, the doses from radioactivity released in gaseous 4 and liquid effluents were a small fraction of the Davis-Besse Technical l Specifications limits. The offsite whole body dose due to radioactivity re-l leased in liquid effluents was approximately 2.3% of the annual Technical Specifications limits. The offsite gamms and beta air doses due to radioac-tivity released in gaseous effluents were smaller; each was less than 0.39% of the annual Technical Specifications limits. Table 1-4 summarizes the dose due to radioactivity released in effluents in 1991. I Table 1-4 Annual Doses to the Public Due to Radioactivity Released in Gaseous and Liquid Emuents
~
1991 Annual Percent Dose Limit of Limit Liquid Effluents Whole Body 0.07 mrem 3 mrem 2.3% Organ (GI-LLI) 0.11 mrem 10 mrem 1.1% Gaseous Emuents Gamma air dose 0.015 mrad 10 mrad 0.15 % Beta air dose 0.047 mrad 20 mrad 0.24 % g Iodine-131, tritium and particulates with half-lives greater than 8 days 0.06 mrem 15 mrem 0.40 % l 1-43
Davis.Besse Nuclear Power Station t99t Annual Envimnmental Operating Report References
- l. "A Citizen's Guide to ' Radon: What it is and What to do About It", United States Environmental Protection Agency, United States Department of Health Services, Centers for Disease Control (August 1986).
- 2. " Basic Radiation Protection Criteria", Report No. 39, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1971).
- 3. " Cesium-137 from the Environment to Man: Metabolism and Dose", Re-port No. 52, National Council on Radiation Protection and Measurements, Washington D.C. (January 1977).
- 4. Deutch, R., " Nuclear Power, A Rational Approach", fourth edition, GP Courseware, Inc., Columbia, MD. (1987).
- 5. Eisenbud. al., " Environmental Radioactivity" Academic Press, Inc., Or-lando, FL (1987).
- 6. " Environmental Radiation Measurements", Report No. 50, National Coun-cil on Radiation Protection and Measurements, Washington, D.C. (December 1976).
- 7. " Exposure of the Population in the United States and Canada from Natural Background Radiation", Report No. 94, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1987).
- 8. Fisher, Arthur, "New Generation Nuclear Reactors; Dare We Build Them?," Popular Science, (April 1990) pp. 68-77,112-114.
- 9. Golay, Micheal W., and Todreas, Neil E., " Advanced Light-Water Reac-tors," Scientific American,(April 1990) pp. 82-89.
- 10. " Health Effects of Exposure to Low Levels of Ionizing Radiation: BEIR V", Committee on the Biological Effects of lonizing Radiations, Board on Radiation Effects Research Commission on Life Sciences, National Research Council, National Academy Press. Washington, D.C. (1990).
1-44
I L Davis-Desse Nuclear Power Station 1991 Annual Environmental 0;mradng Report
- 11. Hendee, William R., and Doege, Theodor: C., " Origin and Heahh Risks of Indoor Radon", Seminars in Nuclear Medicine, Vo r VIII, No.1, Ameri-canMedical Association, Oilcago, IL (January 1987).
- 12. Hurley, P., "Living with Nuclear Radiation", University of Michigan Press, Ann Arbor, MI. (1982).
- 13. " Indoor Air Quality Environmental Infonnation Handbook: Raden". pre-I pared for the United States Department of Energy, Asdstant Secretary for .
i Environment, Safety and Health, by Mueller Associates, Inc., Baltimi ee, MD. (January 1986). 14: "lonizing Radiation Exposure of the Population of the United States", Re- : port No. 93, National Council on Radiation Protection and Measurements, Washington, D.C. (September 1987).
- 15. Miller, Peter. "Our Electric Future," Nationnal Geographic, Vol.180, I
(August 1991) pp. 60-89.
- 16. " Natural Background Radiation in the United States", Report No. 45, Na-tional Council on Radiation Protection and Measurements, Washington, D.C.
(November 1975).
- 17. " Nuclear E'lergy Emerges from 1930's Poised for New Growth", U.S.
Council for Energy Awareness, Washington, D.C. (1989).
- 18. " Nuclear Power: Answers to Your Questions", Edison Elect.-ic Institute, Washington, D.C. (1981).
- 19. " Nuclear Power: Answers to Your Questions, "Elison Electi institute, Washington, D.C. (1987).
- 20. "Public Radiation Exposure From Nuclear Power Generation in the United States", Report No. 92, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1987).
- 21. " Radiation Protection Standards", Department of Environmental Science and Physiology and the Office of Continuing Education, Harvard School of Public Health, Boston, MA. (July 1984).
- 22. " Radon in Buildings: Sources, Diological Effects, Monitoring and Con-trol", course notes form the Advanced Workshop on Occupational and Envi-1-45
Davis-Ik:sse Nuclear Power Station 1991 Annual Envuonmental Operating Report ronmental Radiation Protection, Office of Continuing Education, Harvard School of Public Health, Boston, MA. (July 1989).
- 23. " Removal of Radon from Household Water", United States Environmen-tal Protection Agency, Washington, D.C. (September 1987).
- 24. "1985 Radiological Environmental Monitoring Report for Three Mile Is.
land Station", GPU Nuclear Corporation, Middletown, PA (1985).
- 15. " Sources, Effects and Risks of Ionizing Radiation", United Nations Scientific Committee on the Effects of Atomic Radiation,1988 Report to the General Assembly, United Nations, New York (1988).
- 26. " Standards for Protection Against Radiation", Title 10, Part 20, Code of Federal Regulation, Washington, D.C. (1988).
- 27. " Domestic Licensing of Production and Utilization Facilities", Title 10, Part 50, Code of Federal Regulations, Washington, D.C. (1988)
- 28. " Environmental Radiation Protection Standard for Nuclear Power Opera-tions", Title 40, Part 190, Code of Federal Regulations, Washington, D.C.
(1988).
- 29. " Tritium in the Environment", Report No. 62, National Council on Radi-ation Protection and Measurement, Washington, D.C. (March 1979).
I 1-46 W- -- - -- --.--._-- - __-- _ ----- ~ _--- - - - _ _ - _ _ _ - - - - _ _ _ _ . - - _ - _ _ _ _ - - _ - - _--- -
Davis-Besse Nuclear Power Station 1991 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 adequacy of containment and effluent controls, to assess the radi-ological impact, if any, that Station operation has on the surrounding area, and to determine compliance with applicable radiation protection guides and stan-dards. Environmental surveillance has been a part of the radiological pro-grams for approximately 20 years. The Radiological Environmental Monitoring Program was established in 1972, Sve years befoce the Station be-came operational. This preoperational surveillance program was estab-lished to describe and quantify the radioactivity, and its variability, in the area prior to commerical operation. When Davis-Besse became operational in 1977, the REMP continued to measure radiation and radioactivity in the sur-rounding areas. The operational surveillance program has been collecting environmentai data for over 14 years. A wide variety of environmental samples are collected as part of the REMP. The selection of sample types is based on the established critical pathways for the transfer of radionuclides through the environment to humans. The selec-tion of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population characteristics, and land usage in the area ofinterest. He selection of sampling frequencies for the various environmental media is based on the radionuclides of interest, their re-spective half-lives, and their behavior in both the biological and physical envi. ronments. A description of the Radiological Environmental Monitoring Program is pro-vided in the following section. In addition, a brief history of analytical results for each sample type collected since 1972, and a more detailed summary of the analy es performed in 1991, are also provided. 2-1
I Davis-Desse Nuclear Power Station 1Wt Annual Environmental Operating Report Preoperational Surveillance Program All nuclear facilities are required by the federal govemment to conduct radi-ological environmental monitoring prior to constructing the facility. This pre-operational surveillance program should be aimed at collecting the data needed to identify critical pathways, incluGing selection of the radioisotope and sam-pie media combinations to be included in the surveillance program conducted after facility operation begins. Radiochemical analyses performed on the envi-ronmental samples should include not only those nuclides expected to be re-leased during facility operation, but should also include typical fallout radionuclides and natural background radioactivity. All environm:ntal media with a potential to be affected by facility operation, as well as those media di-rectly in the critical pathways, should be sampled on at least an annual basis during the preoperational phase 01 me environmental surveillance program. The preoperational surveillance design, including nuclide/mecia combinations, 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 compared in a variety of ways (for example: from year to year, location to location, etc.), in order to detect any radiological impact the facility has on the surrounding en-vironment. Total data collection during the preoperational phase s%uld 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 charac-teristics of the local environment. The environmental surveillance program at Davis-Besse will continue well after the Station has reached the end of its eco-nomically useful life and decommissioning has begun. Such a rigorous, long term environmental surveillance program provides a measure of insurance that any radiological impact the operation of Davis Besse has had on the surround-ing environment, is detected to preserve the integrity of the local environment. Operational Surveillance Program Objectives The operational phase of the environmental surveillance pregram at Davis-Besse was designed with the following objectives in mind: 2-2
i Davis Besse Nuclear Power Station 1991 Annual Environmentat Operating Repo,t to fulfill the obligations of the radiological surveillance sections of the Stations Technical Specifications, to determine whether any significant increase occurs in the concentration of radionuclides in critical pathways, -
- to identify and evaluate the buildup, if any, of radioactivity in the local environment, or any changes in normal background radioactivity, and
- to verify the adequacy of Station controls for the release of radioactivity.
Quality Assurance An important part of the environmental monitoring program at Davis Besse is the Quality Assurance (QA) Program. QA consists of all the planned and systematic actions that are necessary to provide ad,:quate confidence in the re-suits of an activity such as the REMP. QA is a program which checks the ade-quacy and validity of the monitoring program through routine audits, strict adherence to written policies and procedures, and attention to good record-keeping practices. The QA program at Davis-Besse is conducted in accordance with the guide-lines specified in NRC Regulatory Guide 4.15. " Quality Assurance for Radi-ological Monitoring Programs." The QA program is designed to identify pos-sible deficiencies in the REMP so that corrective actions can be initiated promptly. Davis-Besse's Quality Assurance program also provides confidence in the results of the REMP through: ;
- performing regular audits (investigations) of the REMP, including a care-ful examination of sample collection techniques and record keeping, performing audits of contractor laboratories which analyze the environ-mental samples, requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross-Check Program, requiring analytical contractor laboratories to split samples for separate analysis followed by a comparison of results, splitting samples prior to analysis by independent laboratories, and then comparing the results for agreement, and finally, requiring analytical contractor laboratories to perform in house spiked sample analyses.
GA audits and inspections of the Davis-Besse REMP are performed by groups such as Davis-Besse's QA department and representatives from the NRC. In 2-3 l -
I Davis-Desse Nuclear Power Station 1991 Annual Environmental Operating Report r addition, the NRC and the Ohio Department of Health (ODH) also perform independent environmental monitoring in the vicinity of Davis-Besse. The types of samples collected and the sampling locations used by the NRC and ODH were incorporated in Davis Besse's REMP. Hence, the analytical results from the different programs can - compared. This practice of comparing re-sults from identical samples, collected and analyzed by different parties, pro-vides a valuable OA tool to verify the quality of both the laboratories' analytical procedures and the data generated. In 1987, environmental sampl%g personnel at Davis Besse incorporated their . own Quality Assurance program into the REMP. Duplicate samples, called quality control samples, were collected at severallocations. These duplicate samples were assigned different identification numbers than the numbers as-signed to the routine samples. This ensured the analyticallaboratory would not know the samples were identical. The laboratory results from analyses of the quality control samples and the routine samples could then be compared for agreement. Quality control sampling has become an important part of the REMP since 1987, providing 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 lorations as possi-ble, and to ensure the contractor laboratory has no way of correctly pairing a quality control sample with its routine sample counterpart. Program Description Overview , The Radiological Environmental Monitoring Program at Davis-Besse consists of the collection and analysis of a wide variety of environmental samples. Samples are collected on a routine basis either weekly, monthly, quarterly, semiannually, or annually, depending upon the sample type and nature of the radionuclides of interest. Environmental samples collected by Davis-Besse personnel are divided into four general categories: atmospheric -- including samples of airborne particulates and airborne
- radiciodine, terrestrial -- including samples of milk, groundwater, broad leaf vegeta-tion, fruit, animal / wildlife feed, soil, and wild and domestic meat, aquatic --including samples of treated and untreated surface water, fish, and suoreline sediments, 2-4
Davis-Desse Nuclear Power Station 1991 Annual Environmental Oprating Report direct radiation -- measured by thermoluminescent dosimeters. All envi-ronmental samples are labeled using a sampling code. Table 2-1 provides the sample codes and collection frequency for each sample type. Table 2-1: Sample Codes and Collection Frequencies Sample Type Sample Collection Code Frequency Airborne Particulate AP Weekly Airborne lodine Al Weekly Thermoluminescent TLD Ouarterly, Annually Dosimeter Milk MIL Monthly (semi monthly during grazing season) Groundwater GW Quarterly Broad Leaf Vegetation BLV/ Monthly (July-September) and Fruits FRU Surface Water - Treated SWT Weekly Surface Water - Untreated SWU Weekly Fish FIS Semiannually Shoreline Sediments SED Semiannually Soil SOI Semiannually Animal / Wildlife Feed AF Semiannually
' Meat-Domestic Me(D) Annually Meat-Wild Me(W) Annually 2-5
I
. Davis Besse Nuclear Power Station 1991 Annual Environrnental Operating Report Sample Analysis When environmental samples are analyzed for radioactivity, several types of measurements may be performed to provide information about the types of radiation and radionuclides present. De major analyses that are performed on environnaental samples collect:d for the Davis-Besse REMP include:
Gross beta analysis Gamma spectral analysis Tritium analysis Strontium analysis Gamma dose (TLDs only) Gross beta analysis measures the total amount of beta emitting radioactivity q present in a sample. Beta radiation may be released by many different radio-nuclides. Since beta decay gives a continuous energy spectrum rather than the discrete lines or " peaks" associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal con. centrations of beta emitting radioactivity; it does not identify specific radionu-clides. Gross beta analysis rnerely 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 etch. Each radionuclide has a very specific " fingerprint" that allows for swift and accurate identification. For example, gamma spectral analysis can be used to identity the presence and amount ofiodine-131 in a sample. Iodine-131 is a man-made radioactive isotope of iodine that may be present in the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power sta-tions. Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the amount of radioactivity present as a result. As discussed in Chapter One, tritium is an isotope of hydrogen that emits low energy beta par-ticles. Strontium analysis identifies the presence and amount of strontium-89 and strontium-90 in a sample. Tnese man made radionuclides are found in the en-2-6
Davis-Besse Nuclear Power Station 1991. Annual Environmental Operating Report vironment as a result of fallout from nuclear weapons testing. Strontium is usually incorporated into th calcium pool of the biosphere. In other words, strontium tends to replace calcium in living organisms and becomes incorpo-rated in bone tissue. The principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from gaseous re-leases. Gamma Doses received by thermoluminescent dosimeters while in the field are read by a speciallaboratory procedure that is more thoroughly discussed on page 211 Table 2-2 provides a listing of the types of analyses performed on environmen-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 sample activity which can be detected with a reasonable degree of confi. dence at a predetermined level. When a measurement of radioactivity is re-
. ported as less than LLD (<LLD), it means that the radioactivity is so low that
;it cannot be accurately measured by th9t particular method for an individual 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 analysis are compared with results from other locations and from earlier years. Generally, the results of sample analyses are compared with preoperational and eterational data.-
- Additionally, the results of indicator and control locations are also compared This allows REMP personnel to track and trend the radioactivity presem in the environment, to assess whether a buildup of radionuclides is' occurring and to determine the effects,if any, the aperation of Davis Besse is having on the en-vironment. If any unusual radioactivity is detected, it is investigated tc deter-mine whether it is attributable to the operation of Davis Besse, et to scme other source such as nuclear weapons testing. - A summary of the REMP sam-
. ple analyses performed from 1972 to 1991 is provided in the following sec-tion.
2-7
, ,d w ., - , , e ., . . , - , . ,- ,n
I Davis-Besse Nuclear Power St. tion 1991 Annual Environmental Operating Repan _ _ _ Table 2-2 kadiocherrical Analyses Performed on REMP Samples Sample Type Analyses Performed ATMOSPIERIC MONITORING Airborne Paniculates Gross Beta Gamma Spectral 3 Strontium-89 Strentium 90 Airborne Radiciodine lodine 131 TERRESTRIAL MONITORING Milk Gamma Spectral , lodine-131 Strontium.89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectral Tritium Strontium-89 Strontium-90 Broad Leaf Vegetation and Fruits Gemma Spectral lodine-131 Strontium-89 Strontium-90 Aniinal/ Wildlife Feed Gamma Spectral Scil Gamma Spectral l Wild and Domestic Meat Gamma Spectral 2-8
Davis.Besse Nuclear Power Station 1991 Annual Environmental Operating Report Table 2-2: Radiochemical Analyses Performed On REMP Samples
. Sample Type Analyses Performed AQUATIC MONITORING Untreated Surface Water Gross Beta ,
Gamma Spectral Tritinm Strontium-89 Strontium 90 Treated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium 90 Iodine 131 Fish Gross Beta Gamma Spectral Shoreline Sediments Gamma Spectral DIRECT RADIATION MONITORING Thermoluminescent Dosimeters Gamma Dose Atmospheric Monitoring
- Airborne Particulates: No radioactive particr. ites have been detected as a result of Davis Besse's operation. Only natural and fallout radioa:tivity from nuclear weapons testing and the 1986 nuclear accident at Chernobyl have been detected.
- Airborne Radiolodine: Radioactive iodine-131 fallout was detected in 1976,1977, and 1978 from nuclear weapons testing, and in 1986 (0.12 to 1.2 picocuries per cubic meter) from tbc nuclear accident at Chernobyl.
2-9
l l Davis Besse Nclear Power S;ation IWt Annual Erwironn.cntal Operating Repon Terrestrial Monitoring: Groundwater: On;f naturally occurring backgiound radioactivity has been detected in groundwate . Milk lodine 131 from nuclear weapons testing fallout was detected in 1976 and 1977 at concentrations of 1.36 and 23.9 picoeuries/ liter respec-tively. In 1986, concentrations of 8.5 picoeuries/ liter were detected from the nuclear tecident at Chemobyl. No iodine 131 detected has been at-tributable to the operation of Davis.Besse. Domestic and Wild Meat: Only naturally occurring potassium-40 and very low cesium-137 setivity have 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 nu-clear weapons testing.
- Broad Leaf Vegetation and Fruits: Only natural background radioactiv-ity and radioactivity from nuclear weapons testing have been detected.
Soll: Only natural background radioactivity and radioactivity from nu-clear weapons testing and the 1986 nuclear accident at Chernobyl have been detected. Animal / Wildlife Feed: Only natural background radioactivity and radio-activity from weapons testing have been detected. Aquatic Monitoring
- Surface Water (Treated and Untreated): In 1979 and 1980, the tritium -
concentrations at location T-7 were above nonnal background. Location T-7 is a beach well fed directly by Lake Erie. The fourth quarter sample in 1979 read 590 picocuries per liter, and the first quarter sample. in 199 had a concentration of 510 picoeuries per liter compared with the normal background concentration of 450 picoeuries per liter. A follow up sam-ple was collected in L Erie between T 7 and the Davis-Besse liquid discharge point. This sample contained tritium at a concentration of 2737 picocuries per liter. These concentrations could be attributed to the op-eration of Davis Besse. Even so, the reselts at T-7 were more than 39 times lower that 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 of 3,000,000 picocuries per liter) for tritium in unrestricted areas. The follow-up sample was less than 0.1% of the MPC. None of the subse-4 2-10
Davis.Desse Nelear Pcwcr Station 1991 Ancual Environmental Operating Repm quent samples indicate any significant difference between the background tritium concentration and the concentration at T-7.
- Fish: Only natural background radioactivity and radioactivity from nu- -
clear testing have been detected.
. Shoreline Sediments: Only natural background radioactivity and radio-activity from nuclear testing and the 1986 nuclear accident at Chernobyl have been detected.
D rect Radiauon Monitoring:
- Thermoluminescent Dos 1 meters (TLDs): he annual average gamma ,
dose rates recorded by TLDs have ranged from 42 to 87 millirems per year at control locations and between 36.8 and 86.1 millirems per year at indicator locations. No increase above natural background radiation at-tributable to the operation of Davis Besse has been observed. 1991 Sampling Program The Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the Dasis Besse Nuclear Power Station Operating License, Appendix A, Technical Specifications. The program includes the collection
< and analysis of airborne particulates, airborne radiciodine, grcundwater, milk, eggs, domestic and wild meat, fruits and broad leaf vegetation, soil, treated and untreated surface water, fish, shoreline sediments, and measurements of direct radiation (refer to Table 2 3). All samples are sent to en independent laboratory for analysis.
Although previous years' sampling programs satisfied all regulat--y require-ments, in 1987, a REMP Enhancement Program was initiated, in an effort to implement a more comprehensive REMP, the number of samples collected and analyzed was selectively increased. 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 ti.e REMP Enhancement efforts, over 2600 samples were col-tected during 1991. Of these samples collected, only 33% were required to satisfy regulatory requirements or Technical Specification. In addition, of the 143 sampling locations utilized in 1991,14% were quality control locations. 2-11 l P _ _ ______ _______
i l Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Repon Table 2-3: Sample Collection Summary j Sampic Collection Number Number of Number of Type Type */ of Samples Samples (Remarks) Freq: ency" Locations Collected Missed ATMOSPIP RIC Airbome Pm ticulates C/W 10 520 0 Airborne Rauoiodine C/W 10 520 0 s TERRESTRLE Milk (May-Oct.) G/GM 4 36 0 (Nov. Apc.) G/M 4 19 0 Groundwater G 'O 5 19 1 Edible Meat wild G/A 1 0 comestic GIA 2 2 0 Broad Leaf Vegetation' Fruit G/M 5 22 0 Soil G/S 11 22 0 Animal /Wildhfe Feed G!A 6 10 0 AQUNTIC Treated Surface Water G/W 7 362 2 Uctreated Surface Water G/Wm 16 CompM M 5 260 0 Fish (3 species) G/S A 2 6 6 Shoreline Sediments G/SA 7 15 0 DIRECT RADIATION Thermo!uminescent Dosimeters C/O 111 435 9 C/A 111 105 6
- Type of Couection:
C/ = Continuous; G/ = Grab; Comp / = Composite.
" Fnquency of CoUection:
/WM = Weekly composited Monthly;!W = Weekly y /SM = Semimonthly; /M = Monthly;
/Q = Quanerly; /SA = Semiannually; /A = Annually 2 12 I
=. -
Devis.Besse Nuclear Power Station 1991 Annual Environmental Operaung Report 1991 Program Deviations Provided below is a description and explanation of 1991 environmental sample collection deviations.
- A composite sample of T-12 untreated surface water could not be col-lected on 1-14-91 because lines leading to compositor were frozen. A grab sample was substituted in place of the composite sample.
- Treated surface water samples at T 144 were unavailable on January 28, and March 14,1991 because the waterliae to that faucet was frozen.
- There were no data for TLD locations T-91, T-114, T-203 and T 204 for first quarter 1991. TLDs were lost due to vandalism.
- TLD locations, T-78 and T-79 were eliminated from the sampling pro-gram.
- The T-23 groundwater sample for first Quarter 1991 was unavailable from the Put-In Bay Water Treatment Plant because their well is sealed up during the winter months.
- Precipitation / snow samples were eliminated from the 1991 sampling program.
- The treated surface water sample at T-28 for week of March 19,1991 was inadvertently discarded. A grab sample was collected as a substitute for the lost sample.
- There was no TLD for location T-116 second quarter 1991. The TLD was lost due to vandalism.
- T-12 composite of untreated surface water for week of May 20,1991 was not collected. The water sample container was damaged after collection of composite, the sample leaked out of the container while in transit from the intake crib back to the Toledo Water Treatment Plant Lab. A grab sample was collected as a substitute.
- There were no data for TLD locations T-93,T-203, and T-204 for third quarter 1991. TLDs lost due to vandalism.
- No fish samples were collected during October 1991 because desired fish species were unavailable.
- There were no data for TLD locations T-202 and T-204 for fourth quarter 1991. TLDs lost due to vandalism.
- The annual 1991 TLD for T-108 was lost in transit from field to laboratory.
2-13
I Davis-Besse Nuclear Power Station lo91 Annual Ermronmental Operating Repon The annual 1991 TLD for T 108 was lost in transit from field to laboratory.
- There were no data for Annual TLDs at T-6, T-91, T 97, T-Il4, T 202, and T-203, these being TLDs lost due to vandalism.
Sampling Locations REMP samples are collected at numerous locations, bo h 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. Generally, they are located within five miles of the station. Control locations are those which should be unaffected by Station operations and are typically, more than five miles away. Data obtained from the indicator loca- , tions are compted with data from the control locations. This comparison al-lows REMP personnel to take into account naturally occurring background radiation, or fallout from weapons testing. in evaluating any radiological im-pact Davis-Besse has on the surrounding environment. Data from indicator and control locations are also compared with preoperational data to de; ermine whether significant variations or trends exist. Atmospheric Monitoring Air Samples Environmental air sampling is conducted to detect any increase in the con-centration of airborne radionuclides that may be inhaled by humans, or serve as an external radiation source. Inhaled radionuclides may be absorbed from the lung, gastrointestinal tract, or from the skin. Air samples collected by the REMP include both airborne particulates and airborne radiolodine. Air sampling pumps are used to draw continuous samples through paniculate membrane filters and charcoal cartridges at a rate of approximately one cubic foot per minute. The samples are collected on a weekly basis. l Airborne particulate samples are collected on 47 mm diameter membrane fil-f ters. Charcoal cartridges are installed downstream of the particulate filters to sample for the presence of airborne radioiodine. 'Ihe airborne samples are sent to a contractor laboratory for analysis. At the laboratory, the airborne par-ticulate filters are stored for 72 hours before they are analyzed to allow for the
- decuy of naturally occurring short lived radionuclides. However, due to the short half-life of iodine-131 (approximately eight days), the airborne radicio-l dine cartridges are analyzed upon receipt by the contractor laboratory.
2-14 l l l
l Davis.Besse Nuclear Power Station 1991 Annual Environmental Operating Report Airborne Particulates i
- Davis Besse samples air for airborne radioactivity continuously at ten loca-tions. There are six indicator locations including four around the site bound-ary, one at Sand Beach, and another at a local farm. There are four control
- locations, Oak Harbor, Port Clinton, Toledo and Magee Marsh. ,
Gross beta analysis is performed on each of the weekly samples. Each quarter, . the filters from each location are combined (composited) and analyzed for gamma emitting radionuclides. The gross beta analyses yield an annual aver-age of.021 pCi/m5at indicator locations and .022 pCi/m5 at control locations for 1991. Evidence of the similarity of results of control and indicator loca. tions may be seen _in the average monthly results shown in Fig 21, The high-est annual average (.023 pCi/mS) was detected at the Toledo location. The . 199.1 annual average was .021 pCi/m5 which is similar to previous years, i Beryl'ium 7 was the only gamma emitting radionuclide detected by the gamma-spectroscopic analyses of the quarterly composites. Beryllium-7 is a naturally occurring radionuclide produced in the upper atmosphere by cosmic radiation. No other radionuclides were detected above their respective LLDs. 1991 Air Particulates Gross Beta DCi/m3 0.03 - - - - - -- - - k+ [
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-=-~~--~-f' s 0.01 - - - - - - - - - - -
0 Jan Feb- Mar Apr May Jun Jul Aug Sep Oct Nov - Dec
-*- Indic ator -+- Control Figure 2-1: Concec: ration of Beta emitting radionuclides in aibrne particulate samples were essentially identical at indicator and control locations. t 2-15 i ..~..,h5..- ..ie',.w,, . . - - , - - - rw , -- -
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Davis-Besse Nuclear Power Statwn 1991 Annual Environmental Operating Report Airborne lodine-131 Airborne iodine-131 samples are collected at the same ten locations and with the same samplers as the airborne particulate filters to sample for the presence of airbome radiciodine. These cartridges are collected weekly, sealed in separate collection bags and sent to the laboratory for gamma spectral analysis. In all of the samples collected in 1991, there was no detectable iodine 131 above the LLD of 0.07 pCi/m2 6 Table 2-4: Air Monitoring Locations - Sample Location Type of Location Description Number Location T-1 I Site boundary. 0.6 mile ENE of Station T-2 I Site boundary,0.9 mile E of Siation T3 I Site boundary,1.4 miles ESE of Station T-4 I Site boundary,0.8 mile S of Station T-7 I Sand Beach, main entrance,0.9 mile NW of Station T-8 I Earl Moore Farm,2.7 miles WSW of Station , T-9 C Oak Harbor Substation,6.8 miles SW of _ Station T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-27 C Crar.e Creek State Park,5.3 miles WNW of Station.
'I = Indicator C = Control 2 16
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Davis-Besse Wctcar Power Station 1991 Annual Envuonmental Operatmp Heron TERRESTRIAL MONITORING The collection and analyses of groundwater, milk, meat, fruits and broad leaf vegetation provides data to asses the buildup of radionut les that may be in-gested by humans. Animal and v.ildlife feed samples provide additional in-formation on radionuclides that m.v be present in the focxl chain. The data from soil sampling provides informa*lon on the deposition of radionuclides from the atmosphere. Many radionuclides are present in the ensirorrnent due to sources such as cos. mic radiation and fallout ' rom nuclear wetpons testing. Some of the radionu-clides present are: tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere ano as a result of routine releases from nuclear facill-ties.
. beryllium 7, present as a result of the interaction of cosmic radiation with the upper atmosphere.
. cesium 137, a man made radionuclide which has been deposited in the environment, (for example, in surface soils), as a result of fallout from nuclear weapons testing and routine releases from nuclet* facilities
. potassium 40, a naturally occurring radionuclide normally found in hu.
mans and throughout the environment.,
- fallout radionuclides which come from nuclear weapons testing, including strontium 89, strontium.90, cesium 134, cerium 141, cerium 144, ruthenium 103. nese radionuclides may also be released in minute amounts from nuclear facilities.
The radionuclides listed above are expected to be present in many of the envi-ronmental samples collected in the vicinity of Davis Besse. The contribution of radionuclides from the plant operation is assessed by comparing sample re-sults with preoperational data, operational data from previous years, control location data, and the types and amour.ts of radioactivity normally released from the Station in liquid and gaseous effluents. 2 20
I Dava-Dew Nuclear Pow ct Station 1W1 Annual Enttronmentat Operant;g Repon Milk sampling is very irportant in environmental surveillance because it pro-vides a direct basis for assessing the build up of radionuclides in the environ-ment that may be ingested by human. Milk is particularly important because it is one of the few foods commonly consumed soon after production. De milk pathway involves the deposition of radionuclides from atmospheric releases onto forage consumed by cows. De radionuclides piesent in the forage eating cow become incorporated into the milk. which is then consumed by humans. Samples of milk are collected at three farms and a coaimercial dairy store once a month from November through April, and twice a month from May through October. Sampling is increased in the summer when the herds are usually out-side on pasture and not on stored feed. The sample locations consist of one indicator and three control locations. The milk samples are analyzed for strontium 89, strontium 90, iodine 131 and other gamma emitting radionuclides, stable calcium and potassium. A total of 55 milk saraples Jere collected in 1991. Strontium 89 was not detected above the LLD of 1.1 pCi/lin any of the sam-ples. Strontium-90 activity was detected in 54 of the 55 samples collected and ranged from 0.5 to 2.1 pC/1. The annual average concentration of strontium 90 was 0.99 pCill at the indicator locations and 1.21 pCi/l at the control locations. For all sample sites, the annual average concentration were similar to those measured in the previous years (Fig 2 5). A total of 55 analyses for iodine 131 in milk were performed during 1991. lodine 131 was not detected in milk samples above the LLD of 0.4 pCill. The concentrations of barium 140 and cesium-137 were below their respective LLDs in all samples collected. The results for potassium 40, a naturally oc. curring radionuclide, were similar at indicator and controllocations, as is to be expected. Since the chemistries of calcit a and strontium, and potassium and cesiums are similar, organisms tend to deposit strontium radioisotopes in bones, and ce-sium radioisotopes in muscle tissue. In order to detect the potential environ-mental accumulation of these radionuclides, the ratios of the strontium radioisotopes radioactivity (pCi/1) to the concentration of calcium (g/l), and cesium radioisotopes radioactivity (pCi/l) to the concentration of potassium (g/1) were monitored in milk. These ratios are compared to standard values to determine if build up is occurring. No statistically significant variations in the ratios were observed. The results of the analyses performed on he milk sam-pies coilected in 1991 indicate no effect due to the operation of Davis-Besse. 2-21
Davis tku Nuclear Iw er Statkm 1991 Annual Environmceal Operating Repri ratios were observed. The results of the analyses performed on he milk sam-ples collected in 1991 indicate no effect due to the operation of Davis Desse. MILK CONCENTRATION OF SR-90 pct /l , I g- .
.m - -. . .-- - - - - . - - -
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o -- . I_ E -- - ~. - 77 78 79 80 21 82 83 84 85 86 87 88 89 90 91 YEAR A * [D indicator M contret Figure 2 5:'the 1991 averege concentratkm of strtotium.00 detected, in milk sampics, were similar at indicator and (Untrol krations, a trend exhibhr4 in prevmus years. Table 2 5: Milk Monitoring Locations Sample Location Type of Location Description Number Location T-8 I Moore Farm. 2.7 miles WSW of Station T-24 C Toft Dairy, Sandusky,21.0 miles SE of Station T-57 C Meek Farm,22.0 miles SSE of Station T-199 C Ewing Farm 6.5 miles SW of Station
' I = indicator C = control 2 22
I Davis.llene Nuc1 car Pow er Stanon 1W1 Annual Environmeraal Operanng Repn Groundw ater Samples it is unlikely that groundwater will accumulate radioactivity from nuclear faci-lities, except for those facilities which discharge liquid effluents to the ground via cribs, pits, or trenches. 'Diis is because the soil acts as a filter and an ion exchange medium for m:,st radionuclides. Ilowever, tritium and other radio-auclides such as ruthenium 106 heve a potential to seep through the soil into the groundwater. /Jthough Davis Besse does not discharge its liquid ef0uents directly to the ground, samples from local vells are collected on a quanerly basis to ensure the detection of any adverse impact on the local groundwater , supplies due to Station operation. The four wells sampled include two indica-tor locations, and two control locations. In additiott, a quality control sample is collected at one of the four weils each quarter. The groundwater samples are analyzed for beta emitting radioactivity in dis-solved and suspended solids, tritium, strontium-89, strontium 90 and gamma emitting radionuclides. Beta emitting radionuclides concentration in suspended solids were not de-tected above LLD of 0.8 pCi/1. In dissolved solids, the concenti.iiion averaged 3.0 pCi/l at indicator locations and 2.0 pCi/l at control locations. Tritium was not detected in any sample above the LLD of 330 pCi/1. Also, strontium 89 was not detected above the LLD of 1.5 pCi/1. Strontium.90 was detected in two indicator samples at an average of 0.8 pCi/1. There were no gamma emitting radionuclides detected in any of the samples collected. All sample analyses were within normal ranges and were similar to results of pre-vious years. Table 2-6: Groundwater Monitoring Locations Sample Location Type of Location Description Number Location T7 I Sand Beach,0.9 mile NW of Station T 23 C Put in Bay Waterworks,14.3 miles ENE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station l t l 2 23 t l l
. . _. -_ -. ~ - . - . _ _ _ _ .
l Duvts-Desse Nuclear Ibwcr Station 1991 Annual Envirtomental Operating Repon J Table 2 6: Groundwater Monitodng Locations con't Sample Location Type of location Description i Number Location i T 54 i Weis Farm,4.8 miles SW of Station T 141 OC Roving Site
- I = indicator C e control QC = quality control ,
Broad Lear Vegetation and Fruit Samples Fruits and broad leaf vegetation also represent a direct pathway to humans from ingestion. Fruits and broad leaf vegetation may become contaminated frorn atmospheric deposition from airborne sources (nuclear weapons fallout or gaseous releases form nuclear facilities) or form irrigation water drawn from lake water receiving liquid effluents (from hospitals, nuclear facilities, etc.). Also, radionuclides from the soil may be absorbed by the roots of the plants and become incorporated into the edible portions. During the growing season (July through September) edible broad leaf vegetation and fruits are collected from farms in the vicinity of Davis Besse. In 1991, broad leaf vegetation samples were collected at two indicator loca-tions and one control location. Fruit samples were collected at tv o indicator locations and three control locations. Broad leaf vegetation was collected once a month during the growing season and consisted oflettuce, cabbage, spinach, kale, parsley, pepper leafs, broccoli and horse radish leaves. The fruits col-lected were apples, and grapes. All samples were analyzed for gamma emit-ting radionuclides, strontium-89, strontiem 90, and iodine 131. Iodine 131 was not detected above the LLD of 0.047 pCi/g wet in any broad leaf vegetation samples. He LLD for iodine 131 could not be reached in two samples collected (T-25 and T-37) on 07-16 91 because of a delay in counting. Iodine 131 was not detected above the LLD of 0.041 pCi/g wet in fruit. The only gamma emitting radionuclide detected in the fruit and broad leaf ve-getation samples was potassium-40 which is naturally occurring. In both fruit and oroad leaf vegetation, strontium 89 was not detected above LLD of 0.010 pCi/g wet. Strontium 90 was detected at a concentration of 0.005 pCi/g wet at control location T-173 for fruit samples. In broad leaf vegetation, strontium-90 averaged 0.004 pClig wet for indicator locations. All results of analyses were similar to results observed in previous years. 2 24
i 1991 Annual Envimnmental Ope ating Report I Davis-Desee Nuclear Ibwer Station Table 2 7: Broad Leaf Vegetation and Fruit Locations ; Sample Number Type of Location Description location location T-8 1 Moore Farm,2.7 miles WSW of Station T-23 C Heineman Winery, Put IN Bay,14.3 , miles ENE of Station. ! T-25 I Miller Farm,3.7 miles S of Station , T-37 C Bench Farm,13.0 miles SW of Station T-173 C Firelands Winery, Sandusky, 20.0 , rniles SE of station. I = indicator C = control Animal / Wildlife Feed Samples As with broad leaf vegetation and fruit samples, samples of domestic animal , feed, as well as vegetation consumed by wildlife, provide and indication of air. ' borne radionuclides depasited in the vicinity of the Station. Analyses from anima!/ wildlife feed samples also provide data for determining radionuclide concentration in the food chain. Domestic animal feed samples are collected < both at the milk and domestic meat sampling locations. Wildlife feed samples 3 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 fal-4 lout radionuclides from nuclear weapons testing may be present in the feed ,
samples.' Domestic Animal Feed - Domestic animal feed was collet:ted semi-
- annually at dairy farms and annually at chicken sampling locations.
There are aws indicator locations and two control locations. The feed col-
- lected consiste( of hay, haylage, mixed feed, chicken feed and corn. All l t
samples were analyzed for gamma emitting radionuclides.
. - Wildlife Feed - Wildlife feed was collected annually at two _ indicator. _ 3 locations. The samples consisted of edible portions of cottails and L smartweed. Samples were analyzed for gamma emitting radionuclides.
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Devts !kse Nuclear Power Stathm 1991 Annuat Envirtnmental Operating Repan in both the animal and wildlife feed only naturally occurring Be 7 and 040 were detected. All other radionuclides were below the respective LLDs. Table 2 8: Animal / Wildlife Feed Locations Sample Location Type of Location Description Number Loca:lon T-8 i Moore farm,2.7 miles WSW of Station T 31 1 Davis Besse, onsite reving location l T 34 C Bertsch farm, Sandust y,20.0 miles SE of Station ; T.57 C Meek Farm,22.0 miles SSE of Station ) T-197 1 Peisman Farm 1.7 miles W of Station T 198 I Toussaint Creek Wildlife Aria .; 4.0 miles WSW of Station ,
- I = indicator C = control Wild and Domestic Meat Samples Sampling of domestic and wild moat provides mformation on environmental radionuclide concentration that humans may be exposed to through an in- ;
gestion 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 atmospherie deposition or contamination of their drinking water from radionuclides released in liquid effluents. >
The REMP generally collects wild meat, domestic meat, (chickens) and eggs on an annual basis. Wild animals commonly consumed by residents in the vi- , einity of Davis Besse include water fowl, deer, and muskrats. Analyses from
- animals whose meat is eaten by humans provides general information on ra- :
dionuclide concentration in the food chain. When evaluating the results from analyses performed on meat animals, it is important. to consider the age, dies - and mobility of the animal before drawing conclusions'on radionuclide con-centration in the local ensironment or in a species as a whole, 2 26
I Davis.Bewe Nuclear Pow cr Maton IW1 Annual Em ironmental Operating Repin Both wild and domestic meat samples and eggs were sampled in 1991 as fol-lows: Domestic Meat: Chickens were collected at cae indicator location and one comrol location. Wild Meat: One Canada goose was collected from onsite. Four muskrats wrie collected from the marsh on site. All meat samples were analyzed for gamma emitting radionuclides. Eggs: Eggs were collected from one indicator location and one control , lxation. The samples were analyzed for gamma emitting radionuclides. The only radionuclide detected in both the meat and eggs samples was K 40 which is naturally occurring and not produced by nuclear power plants. Cs 137 was not detected above LLD of 0.029 pCi/g wet, nese results are similar to previous years. 6 Table 2 9: Wild and Domestic Meat Locations Sample location Type of location Description Number location T-31 1 Oncite roving location g T 34 C Bertsch Egg Farm, Sandusky,20.0 miles SE of Station T-197 I Priesman Farm,1.7 miles W of Station.
- 1 = indicator C = control 1
Soll Samples During June and October of 1991, soil samples were collected at all sites which are equipped with air samplers and Put in Bay, the top layer of soil is sampled in an effort to identify possible trends in the local environmental nu. clide consentiation caused by atmospheric deposition of fallout and station re. leased radionuclides. Generally, the sites are relatively undisturbed, so that the sample will be representative of the actual deposition in the area. Ideally, 2 27
Davis-Iksse Nuclear Ibwer Station 1991 Annual Envinvunental Operating Report there thould be little er na vegetation present, because the vegetation could af. feet the results of analyses. Approximately five pounds of soll are taken from the top two inches at each site. Many nr,turally occuning radionuclides (e.g. beryllium .7 and potassium-40) and fallout radionuclides from nuclear weap. ons testing are detected. Fallout radionuclides which are often detected in. clude strontium 90, cesium 137, cerium 141 and ruthenium 106. All soil samples were analyzed for gamma emitting radionuclides. The results show that the only gamma emitter detected in addition to naturally occurring Be 7 and K-40, was Cs 137. Cs 137 was found in both indicator and control location at a concentration of 0.21 and 0.40 pCi/g dry, respectively. The con-centrations were similar to that observed in previous year (Figure 2-6). SOIL Cs-137 Concentration DCl/9 dry 1.5 g 0.5 - - - - - - - - 0 . i- - - 77 78 79 80 81 82 83 84 85 88 87 88 89 90 91 YEAR incicator E Control Figure 2 6:"Ihe conantratioa of cesiu:n-137 in soil has remained fairly constant over the years the REMP has been conduced. The peak seen in 1978 was due to fallout fonn nuclear weapons testing. 2-28 l
I Davis-Desse Nuclear Power Station 1W1 Annual Envimnmental Operating Reput Table 210: Soll Locations Sample Location Type of location Description Number location T-1 I Site boundary,0.6 miles ENE of Station T2 I Site boundary,0.9 miles E of Station 9 T-3 I Site boundary I.4 miles ESE of Station T-4 1 Site boundary 0.8 miles S of Station T7 I Sand Beach, main entrance,0.9 miles NW of Station 6 T-8 I Moore Farm,2.7 miles WSW of S>ation T-9 C Oak Harbor substation,6.8 miles SW of Station T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles l WNW of Station i T-23 C South Bass Island,14.3 miles ENE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station l
- I = indicator C = control l
2 29
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Davis Besse Nuclear Power Station 1991 Annual Envirtxunental Operating Report AQUATIC MONITORING Radionuclides may be present in Lske Erie from many sources including at-mospheric deposition, run-off/ soil erosion, and releases of radioactivity in l liquid effluents from hospitals or nuclear facilities. These sources provide two forms of potential radiation exposure, external and internal. External ex. posure can occur from the surface of the water, shoreline sediments, and the immersion (swimming)la the water. Internal exposure can occur from in-gestion of radionuclides, either directly from drinking water, or as a result of the transfer of radionuclides through the aquatic food chain with eventual consumption of an aquatic organism, such as fish. To monitor these path-ways, treated surface water (drinking water), untreated surface water (lake or river water), fish, and shoreline sediments are sampled and analyzed. Treated Surface Water Treated surface water is water from Lake Erie which has been processed for l human consumption. Radiochemical analysis of this processed water provides a direct basis for assessing the dose to humans from ingestion of drinking wa-ter. Samples of treated surface water were collected form three indicator and three control locations. These locations include the water treatment facilities for Davis-Besse, Erie Incustrial Park, Port Clinton, Toledo and Put In Bay. Sam-pies were collected weekly and composited monthly. The monthly composites were analyzed for beta emitting radioactivity. The samples were also compos-ited in a quarterly sample and analyzed for strontium-89, strontium 90, gamma emi: ting radionuclides and tritium. One Quality Control (OC) sar gle was col-lected f om a routine location which was changed each month. In treated water samples, beta emitting radionuclides were not detected above the LLD of 0.9 pCi/l for suspended solids. The average concentration was similar in dissolved solids for indicator and control locations (2.3 and 2.2 pCi/1, respectively). The annual average for beta emitting radionuclides for all locations was similar to previous years as shown on the following page: l l 2-33
l Davis Besse Nuclear Power Station 1991 Annual Enviroruncatal Operating Report 1972 3.4 pCiA 1982 2.5 pCiA 1973 2.9 pCi/l 1983 3.1 pC/l 1974 2.3 pCi/l 1984 2.4 pCill 1975 2.3 pCi/l 1985 2.2 pCi/l 1976 2.3 pCi/l 1986 2.2 pCi/l 1977 2.8 pCi/l 1987 1.9 pG/1 1978 3.1 pCi/l 1988 2.7 pG/1 1979 2.6 pCi/l 1989 2.5 pCi/l 1980 2.5 pCi/l 1990 2.2 pCi/l 19812.9 pCi/l 1991 2.2 pCi/l i All quarterly tritium analyser results were less than the LLD of 330 pCi/l for all routine sites. One monthly tritium analysis on a OC sample showed some detectable concentration of tritium (3931108 pCi/l). The OC sample was col. lected from T-11 Port Ginton water treatment plant (a control location) and is attributed to a natural source because tritium con:entrations of this level were detected during the preoperational monitoring period. 6 TREATED SURFACE WATER Gross Beta Analyses pCl/l _ 3 l i 4 3 - 91:!l:l:N-111:ll: 77 78 79 80 81 82 83 84 85 88 87 88 89 90 91 Year
^* Indicator Mean -- Control Mean Figure 210: Over the pas 15 years, the annual mncentrations of beta emnting rrdionuclides in treated surface water samples os!!ccted from indicator locations have been consistant with l
those from mntrollocations. This shows that Davis-Desse has had no meas.trable radiologi. cal impact on surfad water used to make drinking water. j 2 34 m - ~ ~- my ,
- - - - . . - - - - - - . _ - . . ~ . - -
Davis-11csse Nuclear Power Statke 1991 Annual Envwonmental Operating RcPn All cesium 137 results were less than the 11D of 10.0 pCi/1. Strontium 89 was not detected above 1.6 pCi/lin any samples. Strontium 90 was detected at an average concentration of 0.6 at both indicator and control location. Rese results are similar to those of previous years and indicate no significant impact on the environment resulting from the operation of Davis Besse. Table 2 11 Treated Surface Water Locations Sample Location Type of location Description Number location T 11 C Port Clinton Water Treatment Plant 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant 23.5 miles WNW of Station T 23 C Put in-Bay water Treatment Plant 14.3 miles ENE of Station. T-28 1 Treated water supply from Davis Besse site T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE of Station T-143 OC Ouality Control Site T-144 1 Green Cove Condominiums,0.9 miles NNW of ' Station
- 1 indicator C= control OC = quality control Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assess-ing the dose to humans from external exposure from the lake surface as well as immersion in the water. It also provides information on the radionuclides i
present which may affect drinking water, fish, and irrigated crops, 2 35
I Davis-Desse Nuc1 car Power Station 1991 Annua 1 Envrunmental Operating Report Routine Program: The routine prograra is the basic sampling program which is performed year round. Untreated water samples a:e collected in the areas of the station intake and discharge and at the wa'.er intakes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo, Davis.Besse, Erie in. dustrial 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 ana-lyzed for beta emitting radiormclides, tritium, and gamma emitting radionu-clides. The samples are further composited quarterly and analyzed for strontium-89 and strontium 90. A OC sample was collected weekly at a dif-ferent location each month. Summer Program : he 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 late recreational activity, such as boating, fishing, and swim-ming. These samples are obtained in areas along the shoreline of Lake Erie and around the islands The samples are collected weekly and composited monthly. The monthly composites are analyzed for beta emitting radioactivity, tritium, strontium.89, strontium 90 and gamma emitting radionuclides, in 2ntreated water samples, beta emitting radionuclides in suspended solids ranged from 0.3 to 6.8 pCiA, with and average concentiation of 0.5 and 2.8 pCia at indicator and controllocations, respectively. In dissolved solids, the average concentration was 2.5 pCill at indicator and 2.4 pCiA at control loca. tions. Of the 182 tritium analyses performed on the untreated water,176 were less than the LLD of 330 pCiA. The concentration of tritium detected in samples ranged form 333 to 884 pCi/l with an average concentration 531 and 333 pCiA at indicator and control locations, respectively. Only the August composite for tritium at T 130 (mouth Toussaint River) could be attributed to the routine operation of the station. The tritium concentration for that composite was 884 pCiA. This is only .03% of the maximum permis-sible concentration of 3,000,000 pCia for tritium in an unrestricted area, as. stated in 10 CFR 20, Appendix B, Part 20, Table 2. Subsequent samples 2 36 l
1 I Davis-Desse Nuclear Power Station 1991 Annual Environmental Operat tog Repon Subsequent samples collected during September and October showed that the tritium concentration has retumed to below LLD of 330 pCiA. Cesium-137 and strontium-89 were not detectable in samples of untreated wa-ter above their LLDs of 10 pCia and 1.9 pCi/1, respectively. Strontlutn 90 was detected at both indicator and control locations and had an average concentra. tion of 0.7 pCiA and 0.9 pCia, respectively. The analysis results from un-treated water samples show that the operation of Davis-Besse has not had significant impact on nearby residents or on the environment. Each month, weekly quality control samples were collected at different loca. tion. The results of the analyses from the quality control samples were consis-tent with those from the routine samples. Some of the samples collected during the summer rr.onths in Lake Eric were close to the collection points of some of the routine untreated surface water samples. Thus, they served as quality control samples and helped to verify the accurney of the measurements performed. A comparison of their results from the routine sites and nearby summer collection sites illustrates the value of using quality control samples to check the accuracy of analyses performed by the laboratory. The average concentrations of beta ernitting radionuclides for these samples were 2.6 pCia for routine sites and 2.2 pCiA for Lake Eric sample. Untreated Surface 'Nater Control vs. Indicator pCL/L 4 Jan Feb Mar Apr Hey Jun Jul Aug Sept Oct Nov Dec 1991 M contro C andicator Figure 211: The average concentration of beta emining radionucides in untreated water was simitin between control and indicator locations. This dernonstrates that Davis Besu had no impact on the surrounding environment. 2-37
I Davts-Besse Nuclear Power Statkin 1991 Annual Envimnmental Operating Report Table 212: Untreated Surface Water Locations Sample Location Type of Location Description Number Location T-3 I Site boundary,1.4 miles ESE of Station T-11 C Port Clinton Water Treatment Plant 9.5 mues . SE of Station 6 T-12 C Toledo Water Treatment Plant, sample taken form in take crib 11.25 miles NW of Station T 23 C Put in Bay Treatment Plant,14.3 miles ENE of Station T 28 I Davis Besse Water Treatment Plant i T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE of Station T-130 I bke Erie,1.7 miles ESE of Station T-131 I Lake Erie,0.8 mile NE of Station T-132 I Lake Erie,1.0 mile E of Station T-133 I Lake Erie,0.8 mile N of Station T-134 I Lake Erie,1.4 miles NW of Station T-135 I Lake Erie,2.5 miles WNW of Station T-137 C Lake Erie,5.8 miles WNW of Station T-138 C Lake Erie,11.0 miles NW of Station T-145 OC Roving Quality Control Site T-152 C Lake Erie,15.6 ruiles WNW of Station T 158 C Lake Erie,10.0 miles WNW of Station 2 38 I - _ _ - -
l Davis-Iksse Nuclear Pow er Station 1991 Annual Environmental Operating Rc port Table 2-12: Untreated Surface Water Iecation continued Sample Location Type of Location Description Number Location T-162 C Lake Erie,5.4 miles SE of Station T-164 C Lake Erie,9.5 miles ESE of Station T 167 C Lake Erie,11.5 miles E of Station T-168 C Lake Erie,15.5 miles ENE of Station
- I = indicator C = control Shoreline Sediment The sampling of shoreline sediments can provide an indication of the accumulation of undissolved radionuclides which may lead to internal dose to humans through the ingestion of fish, through resuspension into drinking water supplies, or as an external radiation source from shoreline dow to fishermen and swimmers.
Samples of deposited sediments in water were collected in May and October from four indicator locations and four control locations. All samples were analyzed for gamma emitting radionuclides. Naturally occurring potassium-40 was detected at both controls and indicator locations. Cesium 137 was detected at a concentration of 0.12 pCi/g at indicator locations and 0.41 pC1/g at control locations. Atmospheric testing of nuclear weapons has been the principal source of cesium-137 in the environment to date. Although no atmospheric nuclear weapons tests have been reported since 1980, cesium 137 is still present in shoreline sediment samples because of its long half life (approxiraately 30 years). No other gamma emitting radionuclides were detected in any of the samples, and the concentrations of those detected were consistent with normal l concentrations for this area.- 2-39 l l
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Davis Besse NucicJr Power Station 199t Annual Environmental Operating Report Table 213: Shoreline Sediment lecation Sample locaticn Type of Location Description Number lecation T-3 I Site boundary,1.4 miles ESE of Station T-4 I Site boundary,0.8 mile S of Station T-23 C South Bass inland,14.3 miles ENE of Station f i T-27 C Crane Creek State Park,5.3 miles WNW of Station T-130 I Lake Erie,1.7 miles ESE of Station T-132 I Lake Erie,1.0 m;le E of Station Lake Erie,11.0 miles NW of Station ' T-138 C T-164 C Lake Erie, 9.5 miles ESE of Station I 1 = indicator C = control Fish Samples Fish are analyzed primarily to quantify the dietary radionuclide intake by hu. mans, and secondary to serve as indicators of radioactivity in the aquatic eco-system. The principle nuclides which may be detected in fish include naturally occurring potassium-40, as well as cesium-137, and strontium 90. Depending upon the feeding habit of the species (e.g., bottom-feeder versus predator), re-sults from sample analyses may vary. With the aid of local commercial fishermen, Davis Besse routinely collects three species of fish (walleye, white bass and carp) twice a year from sampling locatMn near the Station's liquid discharge point and more than ten miles away irem the Station where fish populations would not be expected to be im-pacted by the Station operation. Walleye are collected because they are a pop-ular sport fish, white bass because they are an important commercial fish. Carp age collected because they are bottom feeders and the would be more likely to be affected by radionuclides deposited in lake sediments. Due to sea-sonal unavailability no fish samples were obtained for the second half of 1991.The edible portion of fish were analyzed for beta and gamma emitting ref Gelides. 2-40
-4
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Davis-Iksse Nuclear Power Station 1991 Annual Etwonrnentat Operating Report Fish Samples Indicator vs. Control Mean Gross Beta pCi/g met 4 . - - _ 1 3- - - - - - - - - - - - - - - - - - - - - - - --
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77 78 79 80 81 82 83 84 85 88 87 80 89 90 91
%st E inc estor M contrei Figure 212: Average concentrations of beta emitting radionuclides in fish sampics were similar at indicator and controllocations and were within the range of results of previous years.
The average conecntration of beta emitting radionuclides in fish muscle was similar for indicator and control location (2.46 and 2.76 pCi/g wet weight, re-spectively). Cesium 137 was detected in one indicator location (T-33, white bass sample) at a concentration of 0.026 pCi/g wet weight. All sample analy-sis results were within normal ranges compared to previous years. Table 2 14. Fish locations Sample location Type of Location Description Number Location T-33 1 Lake Erie, within 5 miles radN of Station T-35 C Lake Frie, greater than 10 mile radius of Station
' I = indicator C= control 2-41
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Davh 13csse Nuclear Power Station twt Annual Environmental Operating Report DIRECT RADIATION MONITORING Populations may be exposed to extremely small amounts of extemal radiation
%m nu-lear facilities by several pathways, including airborne radioactivity or radionuclide deposition in soll, vegetation, or lake bottom sediments. Some radiation will always be present from background sources, both man made and natural, he amount of normal background radiation can be determined by examining preoperational measurements or data collected at control locations.
Thermoluminescent Dosimeters Radiation at and around Davis Besse is constantly monitored by a network of thermoluminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information. He TLDs used at Davis Besse contr:n a calcium sulfate: dysprosium (CaSO.: Dy) card with four main readout areas. Multiple readout areas are used to ensure the precision of the measurements. Thermoluminescence is a process by which lonizing radiation interacts with the sensitive material in the TLD, the phosphor. Energy is trapped in the TLD material and can be stored for several months or years. This provides an ex-cellent method to measure the dose received over long periods of t'me. The amount of energy that was stored in the TLD as a result of interaction with radiation is removed and measured by a controlled heating process in a cali-brated reading system. As the TLD is heated, the phosphor re':ases the stored energ) as light. The amount oflight detected is directly p. tional to the amount of radiation to which the TLD was exposed. D' u: process re-zeros the TLD and prepares it for reuse. TLD Collection Davis Besse has 94 TLD locations (71 indicator and 23 control) which are col-lected and replaced on a quarterly and annual basis. An additional seventeen OC TLDs are also collected on a quarterly and annual basis or at any given time. There are a total of 222 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 1991, the annual average dose for all indicator locations was 15.0 mR/91 days, and for all contro! locations was 16.2 mR/91 days. The annual average dose equivalent for all TLDs in 1991 was 15.3 mrem days. These averages are similar to those observed in previous years as shown on the next page: 2-45
l, l i Davis Desse Nuclear Power Station 1991 Annu 6 Environmentr.: Operating Repx1 1972 - 22.4 mremS1 days 1982 - 14.5 mremS1 days 19',J - 14.3 mremN1 days 1983 - 13.2 mremS1 days 1974 - 11.7 mremS1 days 1984 - 13.2 mremS1 days 1975 - 12.8 mremS1 days 1985 14.4 mremS1 days 1976 15.6 mremN1 dgs 1986 - 14.8 mremS1 days 1977 16.5 miemS1 days 1987 14.5 mremB1 days 1978 16.7 mremS1 days 1988 - 14.5 mtemS1 days 1979 - 13.4 mremS1 days 1989 - 15.9 mremS1 days 1980 - 14.5 mremS1 days 1990 - 15.4 mremS1 days 1981 14.8 mremS1 days 1991 - 15.3 mremS1 days i COMPARISON OF TLD DOSES CONTROL vs INDICATOR mrem /91 days 15- j ' -E - f
- I 3 ~1 E - 8
^ m *
, R I'](I '
10- - - 4 l 6- ~ - O ~ ~ ~ 0-' i ~i . i 1 i . i i 'i ' i . i i i -i 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 l 1987 l 1988 l 1989 l 1990 l 1991 l l YEAR ED INDICATOR E CONTROL Figure 216: similarity between indicator and mntrol results from the last five years demon-strated that the operation of Davis-Desse has not caused any abnormal gamma dose. Quality Control TLDs Duplicate TLDs have been established at 17 sites. These TLDt were placed in the field at the same time and at the same location as some of the routine TLDs, but were assigned quality control site numbers. This allows us to take several measurements at the location without the laboratory being aware that they are the same. A comparison of the quality control and routine results pro-vides a method to check the accuracy of the measurements. The average dose equivalent at the routine TLDs averaged 14.4 mremS1 days while the quality control TLDs yielded an average dose equivalent of 15.2 mrem /91 days. All 2 46
Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Report the quality control and routine sample results were similar demonstrating the accuracy of both the TLDs and the laboratory's measurements. NRC TLD Monitoring The NRC has 22 TLDs located around Davis Besse as part of their Direct Monitoring Network Program. Davis Besse maintains TLDs at all the NRC TLD monitoring sites. The NRC collects their TLDs on a quarterly basis, whereas Davis-Besse collects TLDe quanerly and annually at the.se locations. The NRC TLDs are collected and read independently of Davis Besse's TLDs, thus providing a quality control check on both laboratories. { The NRC uses Panasonic Model UD801 TLDs, which have two elements of lithium borate: copper (LIAO,: Cu) and No elements of calcium sulfate: thu-lium (CaSO,: 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 16.2 mrem /91 days for the Davis Besse TLDs and 16.3 mrem /91 days for the NRC TLDs (data from first, second, and third quarter). The vari-ance in these measurements is most likely due to the differences in the TLD materials. TLD COMPARISON NRC vs Davis-Besse mrem /91 days I n'
- 5
~~
r- ] db r$_ h 1 1987 1988 1989 1990 19 91 Year M os E3 NRC Figure 217: Compares NRC and Davis-Desse TUs for last fivu years. 2-47
j. L 1 3 Davis-Besse Nuclear 19 uct Station 1991- - Annual Environmental Operating Report Table 215: Thermoluminescent Doshneters Locations Sample twation : Type of Location Description Number Location T-1 I- Site boundary,0.6 mile ENE of Station -
-T2 I Site boundary,0.9 mile E of Station T-3 I Site boundary,1.4 miles ESE of Station
. 1 T-4 I Site boundary,0.8 mile S of Station T-5 I Site boundary,0.5 mile W of Station T-6 I Site boundary,0.5 mile NNE of Station T-7 I Sand Beach, main entrance,0.9 mile NW of , Station ' T-8_ I Earl Moore Farm,' 2.7 miles WSW of Station
; T-9 C Oak Harbor Substation,6.8 miles SW of .
I Station f _ T-10 I Site boundary,0.5 mile SSW of Station near ;- j warehouse T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station - T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station - ,
-T-23 C South Bass Island,' 14.3 miles ENE of Station, nearlighthouse T-24 C Sandusky,21.0 miles SE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station =
T-38 I Site boundary,0.6 mile ENE of Station 2-48
. , - -_ _ _ , _ , _ _- . - _ . . , . ~ _-_ _ _ __ _- . . ..___ _ _ _ -_ _
[ i Davis.Besse Nuc1 car Power Station -1991 Ancual Environmental Operating Repon _ Taole 215: Thermoluminescent Dostmeters IAcations continued Sample location Type of lecation Description
- Number - Location
-T 39 .I Site boundary 1,2 miles ENE of Station i
T 1 Site boundary,0.7 mile SE of Station T-41 1 Site boundary,0.6 mile SSE of Station T-42 I Site boundary,0.8 mile SW of Station T-43 I Site boundary,0.5 mile SW of Station T 1 Site boundary,0.5 mile WSW of Station T-45 I Site boundary,0.5 mile WNW of Station T-46 I Site boundary,0.5 mile NW of Station T-47 211 Site boundary,0.5 mile N of Station . , T-48-- =I Site boundary,0.5 mile NE of Station
- T.49 I Site boundary,0.5 mile NE of Station T-50 I Erie Industrial Park, Port Clinton,4.5 miles SE
, of Station -- t T-51 C Daup Farm,5.5 miles SSE of Station e T-52 I Miller Farm,3,7 miles S of Station
-T 53 I- Nixon Farm,4.5 miles S of Station T ~I Weis Farm,4.8 miles SW of Station L: T-55 I- King Farm,4.5 miles W of Station
- T-60 I- Site boundary,0.3 mile S of Station ,
1 T-61-- I Site boundary. 0.6 mile SE of Station l 2-49 l l l- .
I l Dsvis-Besse Nuclear Powt nation 1991 Annual Environmental Operating Repan Table 215: Thermoluminescent Dosimeters locations continued Sample Location Type of Location Description Number Location T-62 I Site boundary,1.0 mile SE of Station T-63 1 Site boundary,1.1 miles ESE of Station T-64 I Site boundary,0.9 rc.ile E of Station g T-65 I Site bcundary,0.3 mi!c E of Station T-66 I Site boundary,0.3 mile ENE of Station T-67 1 Site boundary,0.3 mile NNW of Station T-68 I Site boundary,0.5 mile WNW of Station , t T-69 I Site boundary,0.4 mile W of Station T-70 1 Site boundary,0.3 mile WNW of Station T-71 I Site boundary,0.1 mile NNW of Station T-73 I Site boundary,0.1 mile WSW of Station T-74 I Site boundary,0.1 mile SSW of Station T-75 I Site boundary,0.2 mile SSE of Station T-76 I Site boundary,0.1 miie SE of Stadon T-77 I Site boundary,0.1 mile ENE of Station T-80 OC Ouality Control Site T-82 QC Ouality Control Site l T-83 OC Ouality Control Site T-84 QC Quality Control Site l l 2-50
-e
- n. , . ..+. . _ . . - . - . _- . ..- ,,n... - - . -. . .. . . . . _ . - ~. - . .- . .-
Davis-Desse Nuclear Power Siation 1991 Annual Environmental Operating Report
. Table 215: Thermoluminescent Doslmeters location continued -
Sample Location Type of Location Number Number - Location
. -T-85 . OC Ouality control Site T-86 QC Ouality Control Site i T-88 OC Quality Control Site o
- T OC Quality Control Site T-90 I Toussaint East and Leutz Roads,2.0 miles ,
l - SSW of Station T-91 -I State Route 2 and Rankie Road,2.5 miles SSE of Station T-92 I Locust Point Road,2.7 miles WNW of Station Twelfth Street, Sand Berch 0.6 mile NNE of - ~ T-93 I Station T-94 I State Route 2,1,8 miles WNW of Station
- T-95 : C' State Route 579,9.3 miles W of Station
- T-% C State Route 2 and floward Road 10.5 miles -
WNW of Station T-97 I Duff Washa and Zetzer Road,1.5 miles W of Station -
-T-98 C- Toussaint Portage and Bier Road,6.0 miles SW
-of Station T-99 .I Behlman Road,4.7 miles SSW of Station I . T-100 C Ottawa County Highway Garage, Oak Harbor, 6.0 miles S of Station 2-51 y- r,nah-m y . y4 -y91r .9.-- g
l Davu-Iksse Nuc! car Power Station 1991 Annual Environmental Operating Report Tabic 215:Thermoluminescent Dostmeters Locations continued Sample Location - Type of Location Description Number Location T-101 C Finke Street, Oak Harbor,6.5 miles SSW of Station T-102 C Oak Street, Oak Harbor,6.5 miles SSW of Station , T-103 C Licker-Harder Road,8.5 miles SW of Station T-104 C Salem-Carroll Road,73 miles SW of Station T 105 C Lake Shore Drive Port Clinton,6.0 miles SE of Station T-106 C Third Street, Port Clinton,8.9 miles SE of Station T-107 C Little Portage East Road,8.5 miles SSE of Station T-108 C Boysen Road,9.0 miles S of Station T-109 C Stange Road,8.0 miles W of Station T-110 C Toussaint North and Graytown Road,10.0 miles WSW of Station T-111 C Toussaint North Road,8.3 miles WSW of Station T-112 I Thompson Road,1.5 miles SSW of Station T-113 OC Ouality Control Site T-114 OC Ouality Control Site T-115 OC 0,ality control Site 2-52
Davis Besse Nuclear Power Station 1991 Annual Environmental Operating Repon Table 215: Thermoluminescent Dostmeters Locations continued Sample locatien Type of Location Description Number Location T-116 OC Ouality Control Site T-117 OC Ouality Control Site T-11S OC Ouality Contr01 Site T-119 OC Ouality Control Site T-120 OC Ouality Control Site T-121 I State Route 19,2.0 miles W of Station T-122 I Duff Washa and Humphrey Road,1.7 miles W of Station T-123 I Zetzer Road,1.6 miles WSW of Station T-124 C Church and Walnut Street, Oak Harbor,6.5 miles SSW of S;ation T-125 I Behlman and Bier Roads,4.4 miles SSW of Station T-126 I Camp Perry Western and Toussaint South Road,3.7 miles S of Station l T-127 I Camp Perry Western and Rymers Road,4.0 miles SSE of Station T-128 I Erie Industrial Park, Port Clinton Road, 4.0 miles SE of Station T-150 I liumphrey and Hollywood Road,2.1 miles NW of Station T 151 I State Route 2 and Humphrey Road,1.8 miles WNW of Station 2 53
_ . . . _ _ . - . . . _ . . _ _ - _ . . . . _ _ . . . . . , _ m_. ,_.. . . l.
! Davis Besse Nuclear Power Statkm L1991 Annual Environmental Operating Report Table 215: Thennoluminescent Desimeters Locations continued Sample Location Type of Location Description-Number 1.ocation
-T-153 . I Leutz Road,1.4 miles SSW of Station T 154 I State Route 2,0,7 mile SW of Station T-155 C Fourth and Madison Street, Port Clinton,9.5 e miles SE of Sation T-203 GC Quality Control Site T-201 I Sand Beach,1.1 miles NNW of Station
-T-202- I Sand Beach 0.8 mile NNW of Station f
T-203 I Sand Beach,0.7 mile N of Station iT-204 I- Sand Beach. 0.7 mile N of Station 1
.T 205- Ig Sand Beach,0.5 mile NNE of Station T-206 I Site Boundary,0.6 mile NW of Station
- T-207.. I Site Boundary,0.5 mile N of Station e-- T-208 = I Site boundary,0.5 mile NNE of Station.
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DAVIS-BESSE NUCLEAR-POWER STATION
. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TLD SAMPLES: 5-25 MILE RADIUS
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Davis-Besse Nuclear Power Station IW1 Annual Environmcatal Operating Repon Conclusion Tha. Radiological Environmental Monitoring Program at Davis-Besse is conducted to determine the radiological impact of the Station's operation on the environment. Radionuclide concentrations measured at indicator locations were compared with concentrations measured at control locations, in previous operational studies and in the preoperational surveillance program. These comparisons indicate normal concentrations of radioactivity in all environmen-tal samples collected in 1991. Davis Besse's operation in 1991 had no adverse impact on the residence and environment surrounding the station. In fact, the dose to local residence from exposure to normal sourcer 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 through December 1991 are summarized in Appendix E of this report. 2-58
Davis.Besse Nuclear Power Station 1991 Annual Envirmmental Operating Report References 1." Cesium-137 from the Environment to Man: Metabolism and Dose," Report No.52, National Co ancil on Radiation Protection and Measure-ments, Washington, D.C (January 1977). 2.Eisenbud,M., Environmental Radioactivity, Academic Press, Ir.c., Or-lando, FL (1987). 3." Environmental Radiation Measurements " Report No.50, National Council on Radiation Protection and Measurements, Washington, D.C (December 19'/6). 4."Expositte of the Population in the United States and Canada from Natural Background Radiation," Report No.94, National Council on Radiation Protection and Measurements, Washington, D.C (December 1987).
- 5. "A Guide for Environmental Radiological Surveillance at U.S. Depart.
ment of Energy Installations," DOE /EP-0023, Department of Energy, Washir.gton, D.C (July 1o81). 6." Ionizing Radiation Exposure of the Population of the United States " Report No.93, National Council on Radiation Protection and Measure-ments, Washington, D.C (September 1987).
- 7. Kirk, T.J. and G.N. Midkiff, " Health Physics Fundamentals," General Physics Corporation (1980).
8." Natural Background Radiation in tne United States," Report No.45, National Council on Radiation Protection and Measurements,
' Washington, D.C (November 1975).
i 9." Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion 'As Low As Reasonably Achievable' for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents," Code of Federal Regulations, Title 10 Energy, Part 50 " Domestic Licensing of Production and Utilization Facilities," Appen- ! dix I(1988). l 2-59 l I l l
. . . .. . - -. ~ - - - - . . _- .
I-Davis Besse Nuclear Power Station 1991 Annual Environrnental Operating Report . <
- 10 " Performance, Testing, and Procedural Specifications for Thermolumi-nescent Dosimetry," American National Standards Institute, Inc., ANSI N451975, New York, New York (1975).
11."Public Radiation Exposure from Nuclear Power Generation in the United States," Report No.92, National Council on Radiation Protectica and Measurement, Washington, D.C. (December 1987). 12." Radiological Assessment: Predicting the Transport , Bioaccumulation and Uptake by Man of Radionuclides Released to the Environment." Re- . I port No.76, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1984),
- 13. Regulatory Guide 4.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," US NRC (April 1975).
- 14. Regulatory Guide 4.13, " Performance, Testing, and Procedural Speci-fications fo Thermoluminescent Dosimetry; Environmental Applica-I tions," US NRC (July 1977).
- 15. Regulatory Guide 4.15, " Quality Assurance for Radiological Monitor. -
ing Programs (Normal Operations)- Efnuent Streams and the Environ-ment," US NRC(February 1979).
- 16. Regulatory Guide 0475, " Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities," US NRC (September 1978). h 1~7. Regulatory Guide 0837. "NRC TLD Direct Radiation Monitoring Net-
- work," US NRC(1988) 18." Standards for Protection Against Radiation," Code of Federal
- Regulations, Title 10, Energy, Part 20 (1988).
i
= 19. Teledyne Isotopes Midwest Laboratory, " Operational Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No.1, Oak Harbor, OH," ' Annual Report, Parts I and II (1977 through 1990).
20.Teledyne Isotopes Midwest Laboratory, Preoperational Environmen-tal Radiological Monitoring for the Davis-Besse Power Station Unit No. c i, Oak Harbor, OH (1972 through 1977). 2-60
Davts-Besse Nuclear Power Station 1991 Annual Environtnental Operating Reinn
- 21. Toledo Edison Company," Davis Besse: Nuclear Energy for Northern Ohio."
- 22. . " Davis Besse Nuclear Power Station, Unit No.1, Radiologi-cal Effluent Technical Specifications," Volume 1, Appendix A to License No. NPF 3.
- 23. . " Final Environmental Statement Related to the Construction of Davis-Besse Nuclear Power Station," Docket #50-346 (1987).
- 24. , Performance Specifications for Radiological Environmental Monitoring Program,' S-720, Revision 2 (1988).
- 25. , Radiological Environmental Monitoring Program,"
DP HP-00015, Revision 0,(1990).
- 26. , .
, " Radiological Environmental Monitoring Quanerly, Semi-annual, and Annual Sampling " DB.HP 03004, Revision 0,(1990).
- 27. , Radiological Monitoring Weekly, Semimonthly, and Monthly Sampling " DB-HP-03005, Revision 0, (1990).
- 28. , REMP Enhancement Sampling," DB-ilP 10101, Revision 0, (1990).
- 29. , Semiannual Effluent and Waste Disposal Report,"
January 1. June 30 (1978 through 1990).
- 30. , " Semiannual Effluent and Waste Disposal Report," July 1 -
December 31 (1977 through 1990).
- 31. , Updated Safety Analysis for the Offsite Radiological Moni-toring Program," USAR 11.6, Revision 9. (1989).
- 32. , Annual Radiological Environmental Operating Report Prepar-tion and Submittal," DB-HP-00014, Revision 0,(1990).
- 33. " Tritium in the Environment, " Report No. 62, National Council on Radiation Protection and Measurements," Washington, D.C. (March 1979).
2-61
Annual Environmental Operating Repon 1991 Davs-Desse Nuclear Power Station Land Use Census Program Design Each year a Land Use Census is conducted by Davis-Besse in order to gather information necessary to sample media representative of conservative radio-activity exposure pathways in the environment. The Land Use Census is re-quired by Title 10 of the Code of Federal Regulation, Part 50, Appendix ! and the Davis-Besse Technical Specifications, Section 3/4.12.2. Radiological exposure pathways, 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 populatio 1 around Davis-Besse. These pathways include:
- Inhalation Pathway- Intemal exposure as a result of breathing radio-activity carried in the air.
- Ground Exposure Pathway- Extemal exposure from radioactivity deposited on the ground.
- Plume Exposure Pathway- Extemal exposure directly from a plume or cloud of radioactive material.
- Vegetation Pathway-Intemal exposure as a result of eating vegeta-bles, fruit, etc. which have a build up of deposited radioactivity or which have absorbed radionuclides through the soil.
- Milk Pathway- Intemal 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 identifies the presence of a dairy animal closer to the Station than was previously 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 En-vironmental Monitoring Program. 3-1 a
I Antmal Environmental Operating Report 1991 Davis-Besse Nuclear Power Station Methodology The 12nd Use Census consists of recording and mapping the locations of all residences, dairy cattle and goats, and broad leaf vegetable gardens (greater then 500 square feet) within a five mile radius of Davis-Besse. The surveillance portion of the 1991 Land Use Census was performed during the month of July. In order to gather as much information as possible, the , location of residences, dairy cows, dairy goats, vegetable gardens, beef cattle, fowl, fruit trees, grapes, sheep, and swine were recorded. However, only the , residences, vegetable gardens (greater than 500 square feet), and milk ani-mais are used in the dose assessment program. The Ottawa County Coopera-tive Extension Agency confirmed the presence of dairy cattle and goats re-ported within the five mile radius. Each residence is tabulated as having an inhalation pathway, as well as , ground and plume exposure pathways. Each garden is tabulated as a vegetat-ion pathway. Each milk anima; is tabulated as a milk pathway. All of the locations identified are plotted on a map (based on the U.S. Geo. i, logical 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 gar-den in each sector are determined by measuring the distance from each to the station vent at Davis-Besse. ReSultS The following changes in me pathways were recorded in the 1991 census:
- SSW Sector The vegetation pathway at 2180 meters was deleted in favor of a closer garden at 1560 meters.
- SW Sdtor- The vegetation pathway at 1340 meters was deleted in favor of a closer garden at 1050 meters.
- W Seetor - The garden at 1050 meters was not present during the 1990 census. The vegetation pathway has changed to 1750 meters.
- WNW Sector- The vegetation pathway at 3290 meters was deleted in favor of a closer garden at 1750 meters.
3-2 l i
Annual Environmental Operating Report 1991 Dava-Besse Nuclear Power Statkm
- NW Sector The garden at 2040 meters was not present during 1990.
The vegetation pathway has moved to 2630 meters. Tce detailed list in Table 31 was used to update the database of the effluent dispersion model used in dose calculations. Table 31 is divided by sectors and lists the distance ( m meters) of the closest pathway in each meteorologi-cal sector. Table 3-2 provided information on pathways, critical age group, atmospheric dispersion (X/0) and deposition (D/Q) parameters for each sector. This in-formation is used to update the Offsite Dose Calculations Manual (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents, and in calculating liquid and gaseous eftluent monitoring instru-mentation alarm / trip setpoints. 3-3
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Annual Environmental Operating Report 1991 Deva Besse Nuclear Power Statkm Table 3-1: Closest Exposure Pathways Present in 1991 Sector Distance from Station Closest (meters) Pathways N 880 Inhalation Ground Exposure Plume Expesure NNE 870 Inhalation Ground Exposure Plume Exposure NE RO Inhalation Ground Exposure Plume Expesure ENE,E,ESE,SE N/A Located over 12ke Eric SSE 2010 inhalation Ground Exposure Plume Exposure SSE 2900 Inhalation Ground Exposure Plume Exposure Vegetation S 1070 Inhalation Ground Exposure Plume Exposure S 1450 Inhalation
. Ground Exposure Plume Exposure Vegetation SSW 980 Inhalation Ground Exposure Plume Exposure 3-5
. _ _ . _ . . _. _ . _ _ - ... . . _ . . - - . - . . . . . ~ _ _ . . - . - - . . . . _ ~ . , . . . _ . . _ _ [ l Annual Envimamental Operating Repon 1991 Davis-Benee Nuclear Power Suulon Table 3-1: Closest Exposure Pathways Present in 1991-- ; (continued)r LSector Distance from Station Gosest (meters) Pathways SSW 980- Inhalation Ground Exposure Plume Exposure -
- *SSW 1560 Inhalation '
Ground Exposure - Plume Exposure .
- Vegetation
- SW - 1050 -Inhalation Ground Exposure Plume Exposure Vegetation ,
WSW 1620 Inhalation Ground Exposure Plume Exposure
- WSW 2640 Inhalation _
Ground Exposure Plume Exposure Vegetation - WSW 4270 Inhalation - Ground Exposure - Plume Exposure - Vegetation Cow Milk ,< W 980 Inhalation Ground Exposure Plume Exposure
'Changcs Since 1990 -
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- Annual Envuonmental Operating Report -1991' Davis Benne Nuckar Power Statkx o
Table 3-1: Closest Exposure Pathways Present-in 1991
-(continued)
- Sector Distance from Station Closest (meters) Pathways
*W 1720 Inhalation Ground Exposure Plume Exposure Vegetation WNW 1730 Inhalation Ground Exposure Plume Exposure
*WNW. 1750 Inhalation Ground Exposure Plume Exposure Vegetation
- NW 1980 Inhalation Ground Exposure Plume Exposure
- NW . 2630 Inhaiation Ground Exposure Plume Exposure Vegetation-
- l0 NNW 1210 Inhalation -
- Ground Exposure Plume Exposure Vegetation -
-
- Changes since 1990 i
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- Ancaal Environmental Operating Report -1991 Davw-Beane Nuclear Power Station Table 3-2: Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters SECTOR METERS CRITICAL AGE X/Q D/O PADIWAY GROUP (SEC/MS (M 9 N 880 inhalation chlW - 9.15E-07 8.40E ,
NNE 870 inhalation ch1W 1.27E E 1.47EW ,; NE 900 inhalation diiW 126E 06 158E418 ENE' --- - - - - --- - - - - E' - - - - -- ESE'- - - - -- - SE' - - - - -- SSE 2900 vtgetation child 6.80E-08 7.90E 10
.S '1450 vrgetstion _ chijJ 1.21E-07 2.46E-09
. SSW" 1560 vegetation chiW 1.03E-07 2 28E-09 SW" 1050. vegetation child 2.92E-07 533E-09 ,
t WSW '4270. cow / milk infant 5.71E-08 531E 10 W" , 172C vegetation chiW 2.47E 07 - 3.81E-09
.WNW" x1750 vegetation chiW 1.46E 07 - - 1.72E NW" 2630 vegetation chiW 5.%E-08 - 4.50E 10 L NNW - 1210 . vegetation driW 2.70E.07 1.92E-09 l.
- Since these sectors are located over marsh areas and Lake Erie, no ingestion pathways are present. !
" Changes since 1990.
p l. 3-8 1 1
Davia.Beu.c Nuclear Power Statico 1991 Annual Environment Operating Report Meteorological Monitoring Introduction The Meteorological Monitoring Program at Davis-Besse is tequired by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nuclear power stations on the surrounding environment. Both NRC regulations and Davis-Besse Technical Specifica-tions provide guidelines for the Meteorological Monitoring Program. These guidelines ensure that Davis Besse has the proper equipment, in good work-ing order, to support the Radiological Environmental Monitoring Program. Meteorological observations at began in October 1968. The Meteorological Monitoring Program at has provided data and records of meteorological in-formation that can be used by many other programs. The Radiological Envi-ronmental Monitoring Prcgram uses the meteorological data to evaluate the effects of radioactivity released in Station effluents. The meteorological conditions at the time of these releases are used to calculate doses to the gen-eral public. Meteorological data are also used to evaluate where new radiolo-gical environmental monitoring sites should be located. The meteorological monitoring system is also valuable in monitoring weather conditions, predicting the development of adverse weather conditions, and predicting the development of adverse weather trends, such as flooding or high winds. This provides an early warning system so precautions can be taken to protect the facilities and personnel at Davis-Besse. Onsite meteoro. l logical data would also be a valuable tool in the unlikely event of an emer-gency. Atmospheric dispersion characteristics necessary for evaluatic, conditions, distribution, and doses to the public could be readily obtained. p 4-1 l l
I q Davis-Besse Nuclear Power Station 1991 Annual Envimnment Operating Report OnSite Meteorological Monitoring This section describes the onsite Meteorological Monitoring Program at Davis Besse. A description of the meteorological system , and data handling and analysis procedures, as well as a table and discussion of the annual data recovery are also provided.
System Description
i Meteorological data collection at Davis-Besse consists of wind speed, wind direction, sigma theta (standard deviation of wind direction), ambient (out-side air at 10 m) temperature, differential temperature (the air tempera-ture at 100 or 75 m minus air temperature at 10m), dew point temperature (the air temperature where moisture begins to condense out of the air), and precipitatien. Two towers equipped with a variety of meteorological instru-I ments are used to gather these data. Meteoritical Instrumentation The meteorological system consirts of one monitoring site located at a grade l j level of 577 feet above mean sea level. A 100 m free-standing tower located I about 3,000 feet SSW of the cooling tower, and an auxiliary 10 m tower j located 100 feet west of the 100 m tower, are used to gather the meteorologi-cal data. The 100 m tower has instruments for wind speed and wind direc-tion at 100 m and 75 m. The 10 m tower is instrumented for wind speed and ! wind direction. The 100 m tower also measures two differential tempera-tures (della T's) : 100-10m and 75-10m. Differential temperatures are used to determine staN!ity of the lower atmosphere. This gives an indication of how fast airborne effluents can mix and disperse. Precipitation is measured g by a tipping bucket rain gauge located near the base of the 10m tower. Ac-l ! cording to the Davis-Besse Nuclear Power Station Operating License, Ap-pendix A, Technical Specification, a minimm of six instruments are required to be operable at the two lower les els (75 m and 10 m) to measure temperature, wind speed and wind direction. The signals from each meteorological instrument are translated by modules i located inside the meteorological shelter. These signals are then transmitted to various places as shown in Figure 4-1. 4-2
1 1 l Davis Besse Nuclear Power Station 1991 Annual Envuonment Operating Report Meteorological Systern Maintenance and Calibration l Personnel at Davis-Besse in-spect the meteo-rological site and i instrumentation l regularly. Tow-er instrumenta-tion maintenance and semi-annual nr 1 i calibrations are
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Figure 4-1: De sig-nals from the two n. meteorological tow- [ ers are tracsmitted umW " " " ' " * " to many computers located onsite. De information from these towers aid in calculating popula- . tion dmes. - Meteorological Data Handling and Reduction The Campbell Datalogger 21X in the meteorological shelter communicates data to the PDP 11/84. The PDP 11/84 take 900 averages and stores them for l each hour in a disk files. This information is then transferred to the vax sys-tem. The data are processed and analyzed by several computer programs. Computer listings of the data are generated and values are compared to speci-f:ed range and rate-of-chance criteria in order to identify anomalies. 4-3
I Davis-Desse Nuclear Power Stmion 1991 Annual Envuunrnent Operating Report Summary statistics and Joint Frequency Distributions (JFDs) of wind and sta-bility data are generated and the results are reviewed for consistency in terms of known site characteristic and regional climatology The end result of the review process is a validated final database suitable for use by atmospheric dispersion models and for site meteorological characterizations. Meteorological Data Recovery , The monthly and annual data recovery statistics for all parameters measured during 1991 are provided in Table 4-1. Data recoveries in Table 4-1 repre-sent the percentage of time a given instrument was operable for the month / year divided by the t..aximum number of hours in that month / year that the instrument could be operable . Data recovery for 1991 was above 90 per-cent for all measured parameters. Data recovery for 1991 for the six instru- , ments required by Technical Specification to be operable was also above 90 percent. Table 4-1 also gives monthly and annual recovery rates for joint operability of wind measurements and delta T (differential temperature) for 1991. Annualjoint recovery rates were above 90 percent for all combina-tions of wind and stability data, and above 90 percent for the six instruments required to be operable . Minor losses of data occurred during routine instrument maintenance and calibration and data validation. I I l i 1
1 Figure 4 2: 10 m:ter Wind Rose for January through December 1991 1 N Mt ME M . W eat . m
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1 l l Table 4-1 l Summan Of Metec% logical Data Recovery For The Davis-Besse Nuclear Power Station I Jainuary 1,1991 Througn December 31,1991* ( JAM D21 MAR AIT, MAY JEi jl!L ACQ ff;f M EQM DEC A N N LFAl, j 10(.vn Wirm1 Speed 9933 8239 100.fo 100ft) 9536 10010 9631 M12 97.72 1001X) W in3 99E7 9736 10th Wum1 Directum M73 9)*5 Ifofo 1(010 9536 1001H 10010 9tl39 9).72 10010 97.50 9)E7 M21 75m Wa! Speed M73 9925 1(x)10 10010 95.56 100fX) 10000 9725 97.72 M66 99fD M87 9tt.09 75m Ward Drectkm 99.73 WE5 1001X) 10010 9536 1[c1X) 100lX) 97.85 M72 99.06 99.03 99.87 99.22 10m W alSpea! 99.73 8839 100ft) 1001X) 95.56 10010 100D0 M12 99.72 1001D 99.03 99E7 99.20 10m Wind Drectkm M73 M85 la)1X) 1(MD0 4536 IUO1X) 1001D 9t!39 99.72 1001X) 9736 99E7 M20 10m Ambient AsrTcmp 10011) 97.11 9387 9931 95.43 1001x) Mtd M 25 99.58 99.06 97.92 99E7 99 02 10m Dew Nat Temp 100D0 9930 1(111H 9938 95.43 1001x) 10010 9ts.25 99.58 1(X11X) 77.92 05.24 91.13 Delta T (luku-10in) 100fX) 99.40 9)E7 M58 9523 1001N) M60 9tl39 M44 M06 (77.9 2 M87 99.06 a)cita T p5m-10m) Ifx110 M s5 WL78 99.58 9523 100fX) 9MO 9tt39 99.58 9A06 97.92 99E7 9tt.26 Joint IfDm wn!s md Delta T(100m-10m) 9tJ3 82.14 99.87 9738 93.28 Ifu.00 96.10 98.12 9A44 99.06 97.50 99E7 97.16 Joint 75m wi.% ar 1 Delta T(100m.10) M73 K5.27 99.87 M58 94.62 100.00 Mto 97.72 M 44 97.18 97.50 M87 97.16 Joint 75m winds and 893!' M58 94.62 100D0 9)fo 4' 72 97.58 97.18 97.50 9)E7 96.ig) DeltaTp5m 10m) M73 8531 Joint 1(kn wi.% and Deha T p5m.icm) 9333 8839 W)E7 9338 94.62 10000 Mto 9t1.12 M58 M06 95.83 99E7 97.07
- All data for indsvhar.1 monthes expressed as percent of time katrument was openshic during the month, divided b; the maximum number of tours in that month that the irbtrument could be speraMe. Values for annual data reawcries = pearnt of time insinsnent wm operabic during tre year, divided by the number of twxars in the year that the anurument was operabic.
4-8
Tabic 4-2 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1,1991 through December 31,1991 JAN FEH MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 100m Wind Max Speed (mph) 42.9 34.0 51.4 38.7 35.8 27.1 51.2 33.7 30.8 38.1 45.1 45.1 , Date of Max Speed 23 71 28 15 18 3 7 20 16 5 30 14 Min Speed (mph) 1.7 2.4 13 2.1 13 13 2.1 1.6 1.8 1.4 0.5 1.7 Date of Min Speed 6 28 11 28 21 8 10 2 5 30 8 19 75m Wind ' Max Speed (mph) 40.7 31.3 49.7 56.6 33.8 24.8 23.4 29.8 29 5 36.7 44.1 42.5 Date of Max Speed 23 22 28 15 18 15 7 3 16 5 30 14 . Min Speed (mph) 1.0 2.6 13 2.6 1.8 1.0 2.1 1.1 1.4 0.8 0.2 1.8 Date of Min Speed 29 28 11 24 21 8 16 20 21 26 8 11 10m Wind Max Speed (mph) 33.2 21.8 39.1 42.4 27.1 20.7 15.9 25.6 223 27.6 39.2 32.2 Date of Max speed 23 22 28 15 7 3 5 8 16 5 12 14 Min Speed (mph) 13 1.4 1.1 1.1 1.1 13 1.2 1.1 1.4 1.9 0.5 0.7 Date of Min Speed 5 1 10 25 21 8 15 12 6 12 9 14 r 10m AmbientTemp Max ('F) 45.6 55.6 713 80.9 88.0 91.5 91.9 88.0 90.8 NA 63.8 60.4 Date of Max 15 4 21 7 16 15 20 1 15 NA 20 8 Min (SF) 6.7 6.0 23.6 30.7 44.2 59.3 60.2 57.4 39.7 33.0 15.7 10.1 Date of Min 22 16 12 2 3 14 25 21 27 20 8 5 ! 4-9 - l
Table 4-2 Summary of Meteorological Data Measured at Davis-Besse Nucicar Power Station January 1,1991 through December 31,1991 (con't) JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 10m Dew Point Temp Mean (F) 203 24.5 31.1 42 8 56.6 60.9 62.7 62.1 523 44.4 31.7 263 Max ('F) 40.9 47.5 60.0 67.4 78.8 733 75.4 73.5 72.9 63.9 59.5 32.6 Date of Max 16 19 27 29 9 15 22 28 9 25 19 1 Min ('F) -3.5 -1.5 11.2 13.6 33.1 42.0 513 45.6 27.0 213 6.7 17.1 Date of Min 21 1 30 2 2 13 28 11 23 16 6 2 Precipitation Total (inches) 2.79 1.15 1.08 3.74 3.61 2.07 1.36 10.54 1.63 6.19 3.10 NA NA-Not Available , 4-10
l Davo.Ilcue Nuclear Power Station 1WI Annual Ennronmental Operating Report l Marsh Management ! 1 l Navarre Marsh ; The Navarre Marsh is approximately 733 acres of low lying wetland which surrounds the Davis Besse Nuclear Power Station, located on the south-western shore of Lake Erie. The Toledo Edison and Cleveland Electric illu-minating Comp ** ^ m own the marsh. It is leased to the U.S. Fish and Wildlife Servic {USi ~' eu ,anages it as part of the Ottawa National Wildlife Refugt Fnce u W, eccess roads in the marsh are main-tained by the To&*Dto ~s,g ny Environmental Compliance (EC) personnel at Davis Lex c. . wspensibic for conductirig raarsh inspections l and generating monthly stAus reports, recummending management actions, and actively controlling unMrable plant species. Re:;ults from the marsh in-spections are compared to tae activity levels expected by the USFWS for each seasonal period, and from this comparison an evaluation of the marsh progress is made. The Navarre Marsh i.e completely enclosed by a system of dikes and revet-ments to protect it from flooding and the wave action of Lake Die. A dike is a retaining structure designed to hold back water for purposes of flood con-trol and to aid in managing a marsh for waterfowl and wildlife. Dikes are also routinely used to convert wetlands into land suitable for farming. When used as a marsh management tool, dikes aid in controlling the water levels required to obtain the desired vegetation beneficial to wildlife, Mar.ipulating water levels is one of the most important management tools used in the Na-varte Marsh. Simply by lowering or raising water levels within the marsh, certain plant spcies can be encouraged or discouraged 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 than serve do not provide these (e.g. purple loosestrife). A revetrnent is also a retaining structure designed to hold back water for purposes of erosion control and to encourage beach formation. Revelments are built at a gentler slope (e.g. a ratio of three to one). As waves strike the gradual slope of a revetment, their energy dissipates, allowing the sediment load to drop out at the base of the revetment. Because a revetment extends 5-1 l l
l DavwBeac Nuclear Power Station tWl Annual Envirmmental Operanng Reput well out into the water, it actuaay encourages beach formation by this pas. sive deposition of sediment. A marsh is generally found in low lying flat areas and are characterized by a wide diversity of plant life as the elevation changes. The Navarre Marsh has a varied landscape with different plants found in each elevation. The major. ity of vegetation is found in the fresh
- ater marsh. Three kinds of vegeta-tion grow here: emergents, submergents, and floating plants. Emergents grow in wet soil or out of the water and include cattails, smartweed, and ar-towhead Submergents, such as pondweed and water milfoil, thrive beneath the water's surface. Floating on the water are greater and lesser duckweed ,
and water lilies. All these plants provide food, cover and nesting areas essen-tial to wildlife. The Navarre Marsh is bordered by a narrow, dry beach ridge along the lake front. The beach supports a limited number of weedy plants and has many standing dead trees, frequently occupied by birds of prey such as bald eagles. Extending out from the beach is a sandbar which formed over the last several years after the revetment was constructed in early 1988. As discuued earlier, the revetment helps dissipate lake wave action, allowing suspended particles in the water to settle out and accumulate, eventually forming a sandbar. The sandbar then acts as a natural barrier, protecting the shore from storms and wave action. In addition to protecting the shoreline, the sandbar also benefits local wildlife. Shorebirds and waterfowl are often seen resting and feeding in this area. Lower lake levels in 1989 also exposed shorelines that were un-derwater during previous years. These lower levels also contributed to the formation of the beach at the base of the revetment. 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 meadow plants. In ;he swamp forest, the soilis poorly drained or underwater for part of the growing season. The swamp forest supports woody plants such as cottonwood, willows, buttonbush and several understo-ry plants such as poison ivy, sumac, and swamp loosestrife. Navarre Marsh is unique to this area because of the buttonbush found in the swamp forest. Buttonbush (Cephalanthus Occidentalis) is becorning rare along Lake Die and so it is becoming h.creasingly important to protect those habitats that support the buttonbush population. Studies have shown that 90% of Navarre Marsh's black-crowned night heron use the buttonbush swamp for feedi.1g and resting. Green herons have also been observed resting in the area (Meeks and Hoffman,1979). l l l 52 y_. -
- _ _ - _ .- . . -- - . - - - ~ - - . .-- - -- -
l l Dava Ilesse Nuclear Power Station IW1 Annuall'nvitcuunental Operaung Repri l l A wide variety of birds utilize Navane Marsh. The best known resident is the Canada goose, abundant throughout the marsh and around the site. Be. I sides natural nesting sites, several artificial nesting structures, such as wood , duck boxes and goose tubs, are provided. De boxes and tubs represent a colle:tive effort of U.S. Fish and Wildlife Service, Ohio Department of Natural Resources (ODNR), and Davis Besse personnel. ne marsh also provides waterfowl with a feeding and resting place during their migration. Besides waterfowl, raptors such as owls, hawks, and eagles also frequent the marsh. In the spring and fall, warblers, vircos, kinglets and a variety of other songbirds stop 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 Navstre Marsh. M mmals also use the Navarre Marsh throughout the year. The most notice. able resident is the muskrat. De 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 mammals inhabiting the Navarre Marsh include raccoon, red fox, mink, and whitetail deer. Special Projects in 1991 Toledo Edison is committed to protecting the Navarre Marsh and has gone to great lengths to preserve this valuable resource. This is best illustrated by the extensive dike system built to protect the area from flood!ng, and by the many special projects conducted in the marsh each year. In 1991, these spe-cial projects included controlling undesirable plant species, songbird band. ing, Canada goose banding and nesting surveys, wood duck banding and nesting box relocation. A brief description of each of these projects is pro-vided in the following paragrap..s. Not all of the plants found in Navarre Marsh are beneficial to wildlife. Pur. ple loosestrife (Lythrum salicaria) is one such undesirable sp:cies. His ex. otic plant, introduced from Europe, is an aggressive species which tends to crowd out valuable plants. Each summer, Environmental Compliance per-sonnel 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. 53
l Davis.Besse Nucicw I'ower Station 1991 Annul Environmental Operating itervin One other undesirable plant species found in Navarte hiarsh is the giant reed (Phragmites australis). These tall plants often grow thick, dense stand which crowd out more beneficial plant species. Environmental Compliance personnel attempt to control the giant reed through limited herbicide spraying under the direction of the U.S. Fish and Wildlife Service. In controlling these undesirable plant species, the rich plant diversity in the Navarre Marsh is maintained. The songbird banding project was conducted in cooperation with the ODNR from March through June 1991. The project involved capturing and banding song birds migrating through the area. A total of 6,932 individual birds were banded. Many of the wood duck boxes installed in 1990 were used in 1991. Several of the boxes housed families of wood ducks. Other boxes were utilized by a hooded merganser, starlings and screech owls. Similar efforts for providing nest structures will be taken in 1992. Potential species for which artificial structures will be provided include: wood duck, black duck, mallards, mar. tins, and bats. 5-4 l l
_ . _ . - . . ._ . . _ . _ __. .._-.______._._.-___.m _______m l Dam. Bene Nuc1 car Power Station 1991 Annual Envinomente10perating RcFat ! References ; i i
- 1. "The Audubon Society Nature Guides: Wetlands," National Audubon Society, Inc. (Marsh 1985). .
- 2. "The Ecology of Coastal Marshes of Western Lake Erie: A Commu. ,
nity 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, "13 tid Populations Common to the Sister Islands, .
the Role of the Navarie Marsh",(1979). l t i p i f r t 1
?
5-5
Annual Imtronmtntal Operating Repmt IW1 Davis ikue Nuclear 1% er station l Zebra M~ussel Control Introduction (Dreissena polymorpha), is trote commoniy known as the zebra mussel be- i cause of its striated shell, is a native European blvalve that was accidentally i introduced into North American waters in 1988 and was discovered in Lake ! Erie in 1989. Zebra musselr 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 inches deep. This poses a problem to facilities that rely on wa. ter intakes from Lake Erie because mussels may attach to the intake struc-tures and restrict water flow. Zebra mussels have not yet caused 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 fint section of the intake conduit (the pipe that connects the crib to the intake canal). However, mussels have not attached to the latter portion of the con-duit of the intake canal which supplies water to the plant. The mussel were removed from the crib with high pressure water which also destroys the mus-seis as well. In 1991, zebra mussels were found covering approximately 80cc of the trash racks (moving screens which filter out large debris),however, this did not affect plant operations. At Davis Besse, zebra mussels are (nonitored to estimate their population density, which will determine the severity of the problems they may :ause. The life cycle of the mussel and the effects of certain variables (wind, tem-perature, and chemicals) on mussels and veligers, the larvae stage of the mus-sel, are being studied to determine a means of controlling mussel population. 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 pres-ence of adult zebra mussels or the free swimming larval forms, veligers. The frequency of sampling is determined by take water temperature. Samples are only taken when the lake temperature is above 12 0 C because this is the 6-1 l
i 1 Annual Environmenta10peredng Report 1991 Davis.Iksse Nuclear Pow er Station Perceer venger somsde campertsons sw 60
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temperature at which spawning may occur. At temperatures above 18'C, when spawning conditions are most favorable, more frequent samples are taken. Weather data and water temperatures are also recorded to determine their effects on mussel population. Water samples are collected rnonthly in the Toussaint River and bi weekly in the station's intake forebay. These samples are collected using a plankton net sampler: a net support system with a straining bucket used for plankton sire (microscopic) organisms which include veligers. One milliliter from each sample is observed under a microscope to check for the presence of veligers to determine the average number of veligers per liter.Then a standard com-parison may be made from water samples of different volumes (Figure 61). One other type of sample is collected, but it is observed for the presence of adult mussels rather than ior veliger stages. 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 called an Eckman Dredge. The dredge has a pair of spring loaded jaws that close to trap a sediment sam-ple. The sample is then dumped onto a screen and sifted through to count the number of adult mussels. Research The Environmental Compliance Unit is involved with the Electric Power Re-search Institute (EPRI)in studying the effects of proprietary and commercial 62 I
Annual Environmentat Operating Repvt 1991 Davis-llesse Nuclear Power Station i a I cals on zebra mussels. %c purpose of the study is to determine what may
- influence mussel mortality and/or detachment. Figure 6-2, shows a skid de-signed by EPRI to roughly simulate an in plant water system was con-structed for use at Davis Besse. The skid consists of four different sizeri cells, ranging from 1-1/2" to 3" in diameter with a valve connected to each that allows the water flow to be adjusted. Mussels air placed inside the cells then water is pumped from the forebay through the system. A chemical feed pump is connected to the system so that chemicals can be introduced into three of the cells, he fourth is the control cell that enables comparisons to be made with different chemical conditions in the other cells.
The Skid was used in the summer and fall of 1991 to test the efficiency of a Union Carbide molluscide. The chemical was shown to be very effective against rebra mussels in higher water temperatures (approximately 230C). However, the chemical was found to be rather ineffective in lower water temperatures below 15 eC. Present plans for 1992 are continuing exper-imentation with molluscides to determine the effectiveness on controlling ze-bra mussels. fP ? .p{ p,W . .
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Davis-Deue Nuclear Powcr Station 1991 Annual Environmental Operating Reprt l Water Treatment Water Treatment Plant Operation Description ne Davis Besse Nuclear Power Station uses Lake Eric as a water source for its water treatment plant. He lake water is treated with chlorine, llme, so- _ dium aluminate, and coagulant aid to make the water clean and safe for con- 1 sumption. This water may also be further treated by a demineralizing process i 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 integrity. Operation of the water treatment plant falls under the purview of the Ohio Environmental Protection Agency (OEPA) and the Ohio Department of Health. He operation of the facility is reviewed by a certified operator, Pub. lic Water Supply. Activities at the water treatment plant are conducted in compliance with the Safe Drinking Water Act, and the regulations for public water supply as set forth by the OEPA. Monthly operational reports, required by the OEPA, are completed and sub-mitted to the agency. Rese reports include the Drinking Water Operation Report (OEPA form 5002) and the Drinking Water Contaminant Report (OEPA form 5001). Rese reports contain sample dates and analytical re. ) sults, which are compared to standards established by the OEPA. Operation of the water treatment plant is maintained by the Chemistry Department and monitored by the Environmental Compliance (EC) Unit through weekly in-spections. Operational data are also reviewed for compliance with the limits set by the OEPA. As a further means of monitoring water quality, drinking watu is sampled annually for pesticides, herbicides, and heavy metals (such as chromium, arsenic, mercury, lead) and quarterly for radioactivity and cer. tain organic chemicals. The health and safety of the water treatment plant operators and other site personnel are ensured through weekly housekeeping j inspection of the facility. 71
l l Davis-Besse Nuclear Power Station 1991 Annual Environmental Operaung Repxt Clarifier Operation The water treatment plant at Davis Besse uses upflow clarifiers, or precipita-tors, to remove sediment, organic debris and dissolved agents from the raw water prior to filtration. Clarifiers combine the convent'.onal treatment steps of coagulation, flocculation, and sedimentation into a single unit. Coagula-tion is the process by which a chemical, called a coagulant, is added, causing the small particles in the water to adhere to each other and form larger par-8 ticles. During flocculation, the water is gently circulated, allowing these conglomerate particles to mass together further. Finally, during sedimenta-tion,large conglomerate particles settle to the bottom of the clarifier. These processes normally require large separate tanks. Ilowever, the use of clarifi-ers saves both space and the manpower needed to operate the treatment plant. The sediment removed during clarification is routed to settling basins. The sediment settles to the bottom of the basin, allowing the clear supernatant to be discharged to the lake. The water treatment plant has two precipitators with separate chemical addi-tion systems, allowing for operstion of one or both of the units. Throughout 1991, precipitator number two was operational while precipitator number one was out of service for cleaning and maintenance. New Drinidng Water Rules , The OEPA has issued several new rules for water treatment plants t*tilizing surface water sources, which includes Davis-Besse. More rigid tuitidity standards and additional bacteriological monitoring requirements are among those new rules which took effect in 1991. The OEPA has also issued additional rules concerning disinfection require - ments and turbidity standards which will take effect in June 1993. These additional requirements are more stringent than current rules. Some modifi-cations to thi, water treatment plant will be required. For example., the new distnfection requirements may require baffling of the clearwell in order to Mcrease the amount of tiine the water remains in the treatment system. Also,
~
rew continuous monitoring equipment and additional computer access to data are being considered in order to better comply with tbtse requirements, as well as those of the future. t 7-2 l l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _m __
Davis-flesse Nuc1 car Power Station 1991 Annual Envimnrnental Operating Rerxwt Wastewater Treatment Plant Operation The wastewater treatment plant (WWTP) operation is supervised by a state 1 certified Wastewater Operator. Wastewater generated by site personnel is treated at an onsite extended aeration package treatment facility designed to accommodate a flow of 38,000 gallons per day (gpd). This facility (Figure
- 71) consists of two units, W%TP Number 1 is a 15,000 gpd plant, and WWTP Number 2 is a 23,000 gpd plant. In the treatment process, wastewa-ter from the various collection points around the site, called lift stations, en- ,
ters the facility at the equalization chamber. This structure is simply a l chamber which collects raw wastewater and distributes it to the surge tanks ! of the treatment plants. The wastewater is then pumped into the aeration tanks. Here, organic materi-als are digested by microorganisms which must be provided with a source of oxygen. This is accomplished through the use of blowers. De mixture of organics, microorganisms, and decomposed wastes are called activated sludge. The treated wastewater settles in a clarifier, and the clear liquid (su. pernatant) passes over a welr, leaving the plant by an effluent trough. The activated sludge contain the organisms necessary for continued treatment, and is pumped back to the front of the plant to digest more incoming waste-water. The effluent leaving the plant is disinfected with chlorine and is pumped to the wastewater treatment basin (NPDES Outfall 601) where fur-ther reduction in solids cor. tent and in Biochemical Oxygen Demand (BOD) takes place. Summary of 1991 Wastewater Treatment Plant Operations WWTP Number 1 was taken out of service in early May 1989 after operators observ:d that the walls separating two of the plant's treatment tanks were bowing several inches. The plant was completely drained and supports were installed to alleviate this problem. The plant was also painted at that time. The plant was originally scheduled to be returned to service in 1991, but due to deiays caused by .ae refueling outage and other activities, work was not completed until the end of 1991. Current plans are to place WWTP Number 1 back into service early in 1992. Later that year WWTP Number 2 will be removed from service for cleaning and maintenance. The domestic water supply for the wastewater treatment facility was dis-rupted for most of 1991. The first time this occurred was in March when a ruptured pipe was discovered. The pipe was repaired and the domestic water supply was retumed in August. The water supply was disrupted again in l l 7-3 i l
I DavisBesse Nuclear Power Station 199t Annual Envirtnmental Orcrating Report October, when another ruptured water pipe was discovered. Repair to the line is currently in progress. Biochemical Oxygen Demand (BOD) is an analytical procedure designed to determine how polluted the wr.ter is. 'Ihe rnore organically active the waste-water is, the more oxygen it vill consume. Hence, BOD measures the de-mand for this oxygen; the higher the BOD, the greater the treatment required. In 1991, water entering the treatment system had an average BOD of 163 mg/L, while water leaving the system averaged only 5 mg/L This represents a total BOD reduction of 97E WASTEWATER TREATMENT PLANT
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7-4 1
Davis llessc Nuclear Power Station 1Wt Annual Enytronmental Operating Rep et National Pollutant Discharge Elimination System (NPDES) Re-porting The OEPA has established limits on the amount of pollutants that Davis. Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) per-mit. number 21B0011
- ED. Parameters such as chlorine, suspended solids and pH are monitored under the NPDES permit. Davis Besse personnel pre-pare the NPDES Reports and submit them to the OEPA by the fifteenth day of each month.
Davis-Besse has six sampling points described in the NPDES permit. Ene of these locations are discharged points, or ourfalls, and one is a temperature monitoring location. Descriptions of these sampling points follow: Outfall 001 Collection Box: At a point representative of discharge to Lake Erie. Source of Wastes: lew volume wastes (Outfalls 601 and 602), circulation system blow down and occasional service wr.ter (sample collected at Davis-Besse Beach Sampling Station). Outfall 002 Area Runoff: Discharge to Toussaint River. Source of Wastes: Storm water runoff, turbine building drains, circulating pump house sumps (sample collected at discharge of Training 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 Treatment Basin: Discharge from wastewater treatment system. , Sources of Wastes: Wastewater Treatment Facility. 7-5
.. . . . _ _ - _ ...._.m . . - ._. ._ . - . _ _ . . _ _ _ _ _ _ - _ _ . _ _ _ . _ _ _ . . . _ _ _ _ . _ . _ , _
l-; Davis Heue Nuclear Powcr Station 1991 Annual Environmental Opending Rt pvt , Outfall 662 i Low Volume Wastes: Discharge from settling basins. . Sources of Wastes: Water treatment residues, condensate polishmg resms (sample collected at overflow number 2 basin),and condensate pit sumps. Sampling Point 801 Intake Temperature: Intake water prior to cooling operation (temper:.ture taken at the east end of the in'.ake forebay). ;; 1991 NPDES Summary 4 Outfall 001 nrough conscientious operation and careful monitoring of discharges, chlo-rine levels at the outfall were consistently well below established limits, while pli values remained within the required range. Outfall 002 The discharge gate was isolated from March until August due to station drainage to the pool 3 via the station storm water system. He gate was opened in late August due to high flow condition resulting from heavy rains. The discharge was again isolated at the end of October due to station drain- , age, but it was opened in November 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 significant problems oc. curred at this outfall in 1991. ,
,Outfall 601 Algae populations thrive on the nutrient rich wates in the wastewater treat-ment basin. Although algae play an important role In tertiary, or final clean-up, excessive numbers can adversely impact effluent quality. Algae- . ,
concentrations in 1991.were surprisingly moderate.: A single algicide treat- J
- ment and isolatica of the basin stabilized conditions. De established limits for outfall 601 were not exceeded in 1991, t
7-6 -
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Davis Besse Nuclear Power Stadon 1991 Annual Envirtnmental Operating Repxt ment and isolation of the basin stabilized conditions.
- Die established limits for outfall 601 were not exceeded in 1991.
Outfall 602 The established limits for Outfall 602 were not exceeded in 1991. No sig-nificant problems occurred at this outfall. Sarnpling Point 801 The intake temperature is monitored continuously. Temperature variations between intake and discharge temperatures only itnged as high as 1200. An average difference of 6.20F was recorded for the year. Storm Water Monitoring In 1991, the United States Environmental Protection Agency (USEPA)is-sued new requirements for storm water discharges. These requirements have been part of tne NPDES program for several years, but no formal require-ments for monitoring were issued until 1991. In this new program, the USEPA requires all industrie., who discharge storm water to waterways of the state to monitor all such outfalls and submit appil-cations to the OSEPA for the issuance of a permit to discharge. Davis-Besse has three required discharge points which are currently being monitored. The parameters monitored vary at each discharge location according to what is expected to be discharged, but these parameters are very similar to those in the NPDES program. Sampling of these discharge points is conducted during storm events with av-erage duration and quantity of rain fall. Sampling consists of collecting a grab sample of water during the first thirty minutes of discharge and grab snriples every twenty minutes thereafter up to four hours. All samples are c-.nbined to make a single composite sample. Flow measures are taken si-multaneously with each grab samples in order to get a flow weighted com-posite. Only one set of data for each discharge point is required for the permit application, but sampling may be conducted as often as time permits. All applications must be submitted to the USEPA by November 1992. After that time, the USEPA will evaluate the information and provide additional guidance as to what is required for each industry and each discharge location on a case by<ase basis. 7 ^1 l l
Davwllev.c Nuclear Power Statko IW1 Annual Envirtoment Operating Repw CHEMICAL WASTE MANAGEMENT PROGRAM Introduction The Chemical Wastr Management Program for chemical, harardous and non hazardous wastes generated at the Davis Besse Nuclear Power Station was developed to ensure wastes are managed and disposed of off site in accordance with all applicable state and federal regulations. The Chemical Waste Management Program is regulated by the United States Environmental Protection Agency (USEPA) under the Resource Conserva-tion and Recovery Act (RCRA); the Hazardous and Solid Waste Amendment (HSWA); the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA or Superfund); the Toxic Substance Control Act (TSCA); and the Clean Air Act. He waste transported from Davis Besse is also regulated by Ohio Department of Transportation (DOT) under the Transportation Safety Act. A brief description of these programs is provided in the following paragraphs. Waste Management Resource Conservation and Recoverv Act The Resource Conservation and Recovery Act (RCRA)is tne federal law which regulates solid hazardous waste. Solid waste is defined as a solid, liq. uld, semisolid or contained gaseous material. The major goals of RCRA are to estabhsh a hazardous waste regulatory program to protect human health and the environment and to encourage the establishment of solid waste man-ageinent, resource recovery, and resource conservation systems. The intent of the hazardous waste management program is to control hazardous wastes from the time they are generated until they are properly disposed of, com-monly referred to as " cradle to grave" management. Anyone who generates, transporta, stores, treats or disposes of hazardous waste is subject to regu-lation under RCRA. 81 L-1
I l Davis-Desse Nuclear Pow cr Station 1991 Annual Enviruntnent Operating Repc Ilazardous and Solid Waste Arnendment The llazardous and Solid Waste Amendment (11SWA)is an important addi-tion to the RCRA. He goals of ilSWA are to significantly increase federal regulation of hazardous waste management and to ban the land disposal of most hazardous wastes. In cases where it is not possible to entirely ban haz. ardous waste from landfills, the regulations state that the waste should be treated according to guidelines and stored or disposed of in a manner that minimizes the present and future threat to human health and the environment. This amendment also promotes the recycling, recovery, or reuse of waste by .' sending it to waste-to-encrgy facilities, distillation facilities, and fuel blend-ing facilities. These activities would result in a reduction of waste being dis-posed of in our nation's dwindling landfill space. An additional llSWA goal is to mitJmize the generation of waste through such methods as source reduc-tion, product substitution, technology / process modification and raw material modification. The Davis Besse Nuclear Power Station has Men designated as a large quan-tity generator of hazardous waste. His limits the Station to a maximum stor-age period of 90 days for hazardous waste. RCRA also mandates other re-quirements for large quantity generators, such as the use of proper storage and shipping containers, labels, manifests, reports, personnel training, spill control pl n and an accident contingency plan, all of which are part of the Chemical Management Program at Davis Besse. In 1991,7,533 gallons of hazardous waste were transported off site for disposal. An additional 323 gallons of non hazardous waste were disposed of in 1991. he following are completed as part of the hazardous war.te management program to ensure compliance with the RCRA regulations
- Insprtions Chemical Waste Storage and Accumulation Areas are designed throughout the site to ensure proper handling and disposal of chemical waste. The Chemical Waste Accumulation and Storage Areas are routinely patrolled by security personnel and inspected weekly by Environmental Compl!ance per-sonnel. Inspection log sheets, inspection reports and maintenar.ce work re-quests are completed as needed after each inspection. The log sheets and in spection reports are retained for three years. All areas used for storage or accumulation of hazardous waste are posted as such with warning signs, and drums are color-coded for easy identification of waste categories by Davis-Besse employees. EC personnel also periodically inspect the llazardous Waste Emergency Equipment and areas throughout the Station and site to en-sure wastes are not stored in unapproved areas.
8-2
Davis-Iksse Nuclear Power Station 1991 Annual Envimnment Operat!ng Report
- WasteInventory Fomis Inventory forms are placed on waste accumulation drums or pasted in the ac-cumulation area to allow employees to record the waste type and amount as it is added to the drum. This ensures that incompatible wastes are not mixed and also identifies the drum contents for proper disposal. It also ensures that nonhazardous waste is not mixed with hazardous waste. His eliminates the i possibility of unnecessarily increasing the volume and number of containers of hazardous waste and increasing disposal costs.
- Testing of Waste Oil The majority of waste oil generated at Davis Besse is not disposed of, but is removed to a recycling facility for thermal energy recovery. Before removal for recycling, the oil is tested to determined that it is nonhazardous. Waste oil that contains less than 1,000 parts per million of halogens and has a flash point above 1400 F is considered to be nonhazardous waste. This testing minimizes waste due to the fact that the nonhazar , us waste oil is recyclable.
Also, disposal cost is minimized due to the lower est of waste oil recycling than hazardous waste disposal.
- Waste Minimizatko Davis Besse reduced the volume of waste sent to disposal facilities by send-ing 648 pounds of hazardous waste (used solvents),7,355 gallons of waste oil and 24 nickel cadmium battery cells to recycling firms and fuel blenders for thermal energy recovery purposes.
Other measures in waste minimization include the return of polystyrene res-ins to a plastic manufacturer for reuse, drum recycling and return, and inven-torying unused materials being sent to the Centerior Investment Program. Emergency Response Planning Comprehensive Environmental Response, Compensation and Liability Act The Comprehensive Environmental Response, Compensation and Liability Act (CERCLA, sometimes referred to as Superfund) established a federal au. thority and source of funding for responding to spills and other releases of hazardous materials, pollutants, and contaminants into the environment. Su-perfund establishes " reportable quantities" for several hundred hazardous ma. terial, and regulates the cleanup of abandoned hazardous waste disposal sites. 8-3
1 1' l Davis.Desse Nuclear Power Station 1991 Annual Erwironment Operating Report {
- Superfund Amendment and Reauthorization Act (SARA) i Superfund was amended in October 1986 to establish new reporting pro- !
grams dealing with emergency preparedness and community right to know laws. As part of this program, CERCLA is enhanced by ensuring that the po-tential for release of hazardous substances is minimized and adequate end timely responses are made to protect surrounding populations. Also, the : regulation required the USEPA to develop a list of extremely hazardous sub-stances (Ells), and to established threshold planning quantitles (TPO) for , each chemical. Any facility that has these EHS at or greater than the TPO 4 must submit reports to the State Emergency Response Commission (SERC). The SERC will in turn provide this information to local emergency planning committees to aid in the implementation of emergency response plans. Davis Besse conducts site wide inspections to identify and record all hazard- , ous products and chemicals onsite as required by SARA. Determinations , 1 were made as to which products and chemicals were in sufficient quantitles to report and, in 1991, the following list was: ;
- dieselfuel
-* hydrazine
- lubricating (petroleum) oils
* . Nalco Surecool 1332 (aqueous mixture of organophosphomus compound and ;
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acrylic polymer)
- sodium hydroxide
- sodium hypochk?3
- sulfuric acid
-* ' unleadedgasoline Wese chemicals are found onsite in quantitles greater than or equal to 10,000
,unds. Two of these chemicals, hydrazine ar.d sulfuric acid, are extremely
. hazardous substances (Ells and exceed the TPO of 500 lbs). Any new
~
chemicals found to be present in sufficient quantities to report or at threshold planning quantities prior to the next reportic.g year (1992), must be reported l within 90 days of discovery. 'Ihe TPQ is simply a limit at which certain re- L porting is required. This allows for the appropriate regulation and tracking of these chemicals. In 1992, the required reporting quantity was the same pound limits as in 1991. Annual SARA reports are submitted by March I for the preceding calendar year, i 8-4 ,
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l l Davis Desse Nacicar Power Station 1991 Annual Envimnment Operating Report Fifty five gallon drums containing protective equipment and spill control equipment are maintained shroughout the Station at chemical storage areas and at appropriate hazardous chemical and oil use points. Equipment in the kits includes such items as waterproof coveralls, gloves, absorbent cloth, goggles, and warning signs. He spill kits are strategically placed throughout the Station and inspected on a periodic basis to allow for fast and easy re-sponse in the event of a chemical or oil spill. Other Regulating Acts The To.nc Substance Control Act (TSCA) was enacted to provide the USEPA with the authority to require testing of new chemical substances for potential health effects before they are introduced into the environment, aad to regulate them where necessary. His law would have little impact on utili-ties except for the fact that one family of chemicals, polychlorinated biphe-nyls (PCBs), has been singled out by TSCA. His has resulted in an extensive PCB management system, very similar to the hazardc.us waste management system established under RQlA. A1 hough TSCA requires inspections every three months, the Davis-Besse PCB Program requires that PCB transformers are inspected on a weekly basis to ensure effective management of PCBa. Visualinspection of the transformers are conducted to detect leakage and avoid potential problems which may arise. In 1991, Davis-Be.sse continued an aggressive program of reducing the number of PCB transformers on site. There were originally eleven PCB transformers located in the Auxiliary Building, Water Treatment Plant, near Service Building Two and the Personnel Processing Facility. In 1991, tea of these PCB transformers undenvent the final retrofill cycle and were reclassified as "non-PCB". A retrofill cycle involves flushing the PCB fluid out of the transformer, refilling it with PCB-leaching solvents and ale lowing ?he solvent to circulate in the transformer during operation. The trans. formers are retrofilled three times with a leaching solvent and twice with silicone fluid. He entire process takes two to three years and will extract al-most all of the PCBs. De transformers were tested in 1991 for PCB levels, and were less than 50 pans per million (ppm), allowing the transformers to be reclassified as non-PCB. The eleventh PCB transformer has received the final retrofill and will be analyzed for non-PCB status in 1992. In 1991, 4,708 kilograms of PCB waste were dbpovd of. 8-5
1: 1 i Davis Dess.c W; lear Power Station 1991 Annual Environment Operst rig Report Clean Air Act i The Clean Air Act identifies several substances which are conai..! .Jard-ous air pollutants. Of particular significance is asbestos removal from reno-l vation and demolition projects for which USEPA has outlined specinc regulations concerning handling, removal, envirorimental protection and dis-posal. Also the Occupational Safety and Health Protection Administration (OSilA) strictly regulates asbestos with a concern for worker protection. Re-moval teams must meet medical surveillance, respirator fit tests, and training l requirements prior to removing asbestos-containing material. In 1991, a notification letter was prepared and submitted to the EPA concern-ing the removal and disposal of asbestos-containing material from Davis. Besse. The Davis Besse cooling wwer was renovated and approximately 180 cubic yards of cement boards containing nonfriable asbestos were removed and replaced with non asbestos cement boards. Asbestos is not considered an RCRA hazardous waste, but the EPA does require special handling and dis-posal of this waste under the Clean Air Act. Transportation Safety Act The transportation of hazardous chemicals, including chemical waste, is regulated by the Transportation Safety Act of 1976. Dese regulations are enforced by the United States Department of Transportation (DOT) and cov-er all aspects of transporting hazardous materials, including packing, han-diing, labeling, marking, and placarding. For DOT purpose.s, the term
" hazardous material" encompasses a wide range of materials including explo-sives, compressed gases, poisonous materials, inhalation hazards, Hammab;e materials, oxidizing materials, irritants, corrosive materials, radioactive mate-rials, and hazardous wastes. Before any wastes are transported off site, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations, including verification that the vehicle has ap-propriate placards and it is in good operating condition.
As stated under RCRA, hazardous wastes are transported for disposal within 90 days from the date accumulation and storage began. Before shipping the waste, approval for disposal is received from the Treatment, Storage and Dis-posal Facility (TSDF). Prior to transportation, a Uniform Hazardous Waste Manifest is completed and signed by both the generator and the transporter. Once the transporter has delivered the waste to the designated TSDF, the TSDF p ns g he manifest for shipment receipt and returns the completed manifest to DB. 8-6
- . - .-_ _ . . . . - - _ - . -- -. _ - . . - - . - - - _ _ _ - . . - . ~ _ - I Davis-Besse Nuclear Power Station 1991 Annual Envimnment Operating Repcwt , i Oth.:r Programs Underground Storage Tanks According to RCRA, facilities with Underground Storage Tanks (USTs) are required to notify the State. This regulation was implemented in order to provided protection from tank contents leaking and causing damage to the environment. An UST includes the tank system and its piping which has at least 10% of its volume underground. Additional standards require leak detection systems and performance standards for new tanks. At Davis Besse ' the two 40,000. gallon and one 8,000 gallon diesel fuel riorage tanks, and the one 2,000-gallon waste oil tank are regulated as USTs. Burn Permits As required by the EPA under the Clean Air Act, burn permits for Davis-Besse were submitted for approval. The Station has a smal1 area on site for _ training employees on proper fire fighting techniques. Most instruction is on the proper use of a fire extinguishcr, A burn permit is submitted every three months to remain in compliance with the Ohio EPA regulations. Summary Davis-Besse will continue to remain dedicated to protecting the environment and human health through the use aggressive chemical waste management practices. 'Ihese practices include recycling of waste oil and batteries and thermal energy recovery for waste solvents. Also, Davis-Besse will continue training employees on the proper handling, storage and disposal of chemical waste. 8-7
f Davis-llesse Nuclear Power Sation 1991 Annual Environrnental Operating Repet Glossary A I absorbed dose The amount of radiation energy absorbed by any material exposed to ionizing radiation. ALARA Acronym for "As Low As Reasonably Achievable," a basic concept of radiation protection that specifies ra-dioactive 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. atom The smallest portion of an element that shares the gencial characteristics of that element and cannot be divided or broken up by chemical means, atomic number The number of pretons in the nucleus of an atom, atomic weight The numbe: of neutrcns and protons in the nucleus of an atom. 3 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 matericts that surround us. A-1
l l Davis Besse Nuclear Power SatW 1991 Annual Environmental Operating Report beta particle A charged particle emittcd from a nucleus during ra. diaactiv- decay, with a mass equal to 1/1837 that of a proton. A negatively charged beta particle is identical to an electror,. A positively charged beta particle is called a positron. Beta particie ; are easily stopped by a thin shee! of metal, plastic, or wood. borated water Wate containing the element boron used to cool the reactor core in the event of a Loss Of Coolant Acci-dent. Borated water can be sprayed inside the contain-ment building, thus protecting the Reactor Coolant 6 System. Borated water can also be flushed into the reactor vessel. The boron in the water actually absorbs free neutrons, thus removing the catalysts required to drive the nuclear fission process. __J i calibrate To standardize a measuring itwument by determin. ing its deviation from a standed. The deviation deter-mined allows one to apply n correction factor b a measured value to yield the true value, chain reaction A reaction that stimulates its own repetition. In a fis-sion chain reaction. s fissionable nucle absorbs a neutron and splits, relea;;ing 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 Tne thin-walled tube of zirconiuim alloy that forms the outer jacket of a fuel rod. He cladding is highly resistant to heat, corrosicn and radiation, and com- $ f prises the first br.rrier to the release of fission products, w A-2 g 1
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Day.s-Desse Noelcar Power Sation 1991 Annual Envimame.atal Operating Report composite sample A sample made cf grab or continuous samples combined to represent a particular locaban or a set period of time. containment A steel liner inside the concrete shir:a b 'ilding. De-vessel signed to isolate the primary syster.: 9w 'he environment and other systems, continuous sample A sample that is collected non-stop and is used to evaluate conditior.s over a specific period of time, control location A sample collection location generally more than 5 miles away from Davis-Besse. It is used to measure the normal background radiation levels. ,
, control rod A rod containing material such as hafnium or boron, used to control the power of a nuclear reactor. By ab-sorbing neutrons, control rods slow down and eventu-ally stop the fission process. r; 9
coolant A fluid, usually water, used to cool the nuclear reactor a core by transferring the heat energy emitted during the fission process into the fluid medium, cooling tower A heat exchanger designed to a.id in the coolin.g of wa-ter that was used to cool ensurt steam exiting the tur-bines of the power plaret 't at cooling tower transfers exhaust heat into the air instead of inta a body of - water. cosmic radiation Peneuating ionizing radiation, both particuir.te and electromagnetic, that origin:es in space. critical group The segment of the population that cw.d receive the greatest radiation dose. . citical organ The body organ receiving a tsd ation dose that could result in the greatest overall effect. i A-3
l L Davis Besse Nuclear Power Sation 1991 Annual Environroental Operating Report critical pathway The exposure pathway that will provide, for a given radionuclide, the greatest radiation dose to a popula-tion, or to a specific segment of ti:e population. The basic unit used to describe the intensity of radio-curie (Ci) activity in a sample or material. One curie is equal to 37 billion disintegrations per second, which is approxi-mately the rate of 6ecay of one gram of radium. A cu-rie is also a quantity of any radionuclide that decays at a rate of 37 billion disintegrations per second. {
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daughter products Isotopes that are formed by the radioactive decay of other radionuclides. A radioactive sequence which an unstable element 6 decay series goes through before reaching a stable state; it usually involves the loss or gain of energy and/or matter, dike A t etaining structure designed to hold back water for flood control dissolved solids Solids incapable of removal through physical means, , I e.g., via filtration. dos! A quantity (total or accumulated) of ionizing radiation received in tissue. dose rate The radiation dose delivered per unit of time. Mea-l sured, for example, in rem per hour IIP L% effluent In general, a waste material, such as smoke, liquid, industrial refuse, or sewage discharged into the envi-L ronment. A-4
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Davis-Besse Nuclear Pover Saton 1991 Anoual Environmental Operating Report electromagnetic A travelling wave motion resulting from simultaneous changes electric and magnetic fields. Familiar electromagnetic waves range from X rays and gamma rays of short wavelength, through the ultra-violet, visible, and infrared regions, to radar anff radio. waves of relatively long wavelength. electron An elementary particle with a negative charge and a mass 1/1837 that of the proton. Electrons orbit around the positively charged nucleus and can determine the chemical property of the atom. element One of the 103 known chemical substances that cannot i be brohen down further without changireg its chemical properties. Some examples include carbon. hydrogen, nitrogen, gold, lead, and uranium, extemal radiation Irradiation by a source located outside the body. 7 fission The splitting or breaking apart of a heavy 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 trore neutrons are re-leased. fission products The nuclei (fission fragments) formed by the fission of heavy elements, plus the nuclides formed by the ra-dioactive decay of the fragments. fuel assembly A cluster of fuel rods or plates. Also called a fuel element. Many fuel assemblies make up a reactor core.
' fuel rod A long, slender tube that holds fissionable material (fuel) for nuclear reactor use. Fuel rods are assembled into bundles called fuel elements or fuel assemblies, which are loaded individually into the reactor core.
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I Davis Besse Nuclear Power Sation 1991 Annul Environmer.uj Operating Report G gamma ray High energy, short wavelength electromagnetic radi-ation emitted from the nucleus of a radioactive atom. Gamma radiation frequently accompanies alpha and beta emissions and always accompanies fission. Gam-ma rays are very penetrating but may be shielded by dense materials, such as lead or concrete. Gamma rays are similar to X rays, but are usually more energetic. 6 grab samples A grab sample represents a single samt,le collected in a finite period of time. i t half-life The time in which half the atoms of a particular radio-active substance disintegrate to another nuclear form. F 1 red half-lives vary from millionths of a second to or ions of years. I indicator location A sample collection location generally within 5 miles of Davis-Besse. It is used to measure the effects of Davis-Besse 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. A-6
Davis-Besse Nuclear Power Sation 1991 Annual Environmental Operating Rewt 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 or removing one ore more elec-trons to from atoms or molecules, thereby creating ions. High temperatures, electrical discharges, or io nizing (atomic) radiation may cause ionization. ionizing radiation Any radiation capable of displacing electrons from atoms or molecules, thereby producing lons. isotope One of two or more atoms with the sa:re number of protons, but different numbers of neutrons in their nuclei. t . J lower limit The smallest amount of sample activity that will give a of detection net count, for which there is a confidence at a predeter-mined level that the activity is present. micro- A prefix that divides a basic unit by one million. milli. A prefix that divides a basic unit by one thousand, 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 1. A-7
i Davis-Besse Nuclear Power Sation 1991 Annual Environmental Operating Report noble gas A gaseous chemical element thct does not readily enter into chemical combi.. tion with other elements. An in-ert 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. Ex-cept 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. i The total number of neutrons and protons is called the mass number. nuclide A general term referring to all known isotopes, both stable (279) ar.d unstable (about 5000), of the chemical elements. 03 pico. A prefix that divides a basic unit by one trillion, proton An elementary particle that carries a positive charge and has a mass of 1,67 x 10 2* gram. I Q quality factor The factor by which the absorbed dose is multiplied to obtain a quantity (rem) that expresses, on a common scale the potential for biological 6 mage to exposes persons. rad An acronym for " radiation absorbed dose". The basic unit of absorbed dose of radiation. One rad equals the absorption of 100 ergs ( a small but measurable amount of energy) per gram of absorbing material. radiation The conveyance of energy through space, for example, the radiation of heat from a stove. Ionizing radiation A-8
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i Davis-Besse Nuclear Power Sation 1991 Annual Environmental Operating Report is 'the emission of particles or gamma rays from the nucleus of an tmstable (radioactive) atom as a result of radioactive decay. ; radioactive- Radioactive material in an undesirable location. Con- 1 contamination tamination can be loose on surfaces, fixed on surfaces (soaked or ground into the surface) or airborne. radioactive decay The decrease in the amount of radioactivity with the . passage of ti'ne due to the spontaneous emission of particulate or electromagnetic radiation from the atom .
- nuclei.
radioactivity - The spontaneous emission of radiation from the nucleus of an unstable isotope. Radioactivity is a pro-cess and radiation is the product. radionuclide A radioactive isotope of an element. [ reactor trip ' A sudden shutting down of a nuclear reacto;, usually by rapid insertion of control rods, either t.utomatically . or manually by the reactor operator. A reactor trip is . sometimes called a scram, rem _ Acronym for (" roentgen equivalent man") . The unit of
' dose of any ionizing radiation that produces the same biological effec; as a unit of absorbed dose of x rays.
revetic > 3.t A retaining structure designed to hold back water for >
. purposes of erosion control.~
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 centimeter of dry air at standard temperature and pressure. S - shielding . Any material or obstruction that absorbs radiation and thus tends to protect personnel or materials from the effects ofionizing radiation. A-9
I Davis-Besse Nucicar Power Sation 1991 Annual Envirmmental Operating Report spent fuel Nuclear reactor fuel that has been used to the extent that it can no longer effectively sustain a chain reac-tion. 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. Solids capable of removal through a filter such as a i suspended solids Screen, r1 I Technical Specifications (Tech Specs) A part of the operating license for any nuclear facility insured by the Nuclear Regulatory Commission (NRC), the Tech Specs delineate the requirements the facility must meet in order to maintain its operating license. terrestrial radiation The portion of natural radiation (background) that is ' emitted by naturally occurring radioactive materials in the earth. 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 12-1/2 years. EVW whole-body .An exposure of the body to radiation in which the en-dose tire body rather than an isolated part is irradiated. A - 10
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ws , Davis-Bene Nuclear Powi er Setion 1991 - Annual Environmental Operating Repcwt , XYZ Xrays Penetrating electromagnetic radiation (photon)hav. ing a wavelength that is much shorter than that of vis-ible 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. s 4 2 a d S 4 Y A - 11 1 e e m-- = * , 3
Davis Besse Nuclear Power Station 1991 Annual Environmental Operating Report APPENDIX B Interlaboratory Comparison program O B1
Appendix B Interlaboratory Comparison 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 purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and speciries control limits. Results consistently higher or lower than the known valu2s 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 environmental umple crosscheck program for milk, water, air filters, and food samples during the period January 1988 tarough November 1991. This program has been conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support laboratory, Las Vegas, Nevada. The results in Table B-2 were obtained for thermoluminescent dosimeters (TLDs) during the period 1976, 1977,1979,1980,1984, and 1985-86 through participation 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. B2
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l . Table B-1 U.S.= Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Isotopes Midwest bboratory results for milk, water, air filters, and food samples,1988 through 1991.a Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 12cc Is, N=1 Limits STW-521 Water Jan 1988 Sr-89 27.315.0 3C 015.0 21.3-38.7 Sr 15311.2 15.011.5 12A-17.6 STW-523 Water Jan 1988 Gr. alpha 23il.2 1 015.0 0.0-12.7 Gr. beta 7.711.2 w015.0 0.0-16.7 STW-524 Food Jan 1988 Sr 89 44.0i4.0 46L15.0 37 3-54.7 Sr-90 53.012.0 55.012.8 50.2-59.8 I-131 102314.2 102.0i10.2 84 3-119.7 Cs-137 95.716.4 91.015.0 82.3-99.7 K 1011i158 1230162 1124-1336 . STW-525 Water Feb 1988 Co-60 69.3123 U.0i5.0 60 3-77.7-Zn-65 99.013.4 94.019.4 77.7-1103 Ru 106 92.7114.4 105.0110.5 86.8-123.2 Cs-134 61.7i8.0 64.015.0 55.3-72.7 Cs437- 99.7 3.0 94.015.0 853-102.7 STW-526 Water - Feb 1988 H-3 3453i103 3327i362 2700-3954 STW _527 Water. Feh 1988 . Uranium 3.010.0 3.016.0 0.0-13.4 - STW-528 Milk Feb 1988 1-131 4.711.2 4.0 0.4 33-4.7
- STW-529 Water Mar 1988 Ra-226 7.110.6 7.611.1 ' 5.6-9.6 Ra-228 nae 7.711.2 5.7-9.7 STW-530 Water Mar 1988 Gr. alpha 43 1.2 6.0t5.0 0.0-14.7 Gr. beta 133113 13.015.0 4 3-21.7
- STAF-531 Air Filter . Mar 1988 Gr. alpha 21.0i2.0 20.015.0 11.3 28.7 Gr. beta 48.0i0.0 50.015.0 41.3-58.7 , Sr-90 16.7i1.2 17.011.5 14.4-19.6. Cs-137 18.7i1 3 16.015.0 7 3-24.7 STW-532 Water Apr 1988 I-131 9.012.0 7.5-10.8 6.2-8.8 B-3
' Toble B 1. (continued) Concentration in pCI/Lb EPA Resultd lab - Sample. Date TIML Result Control Code Type' Collected Analysis 120C 1s, N=1 Limits STW 533 Water Apr 1988 SM (Blind) Sample A Cr. alpha NDI 46.0i11.0 -27.0-65.0 Ra-226 ND 6.411.0 4.7-8.1 Ra-228 - ND 5.610.8 4.2-7.0 Urantum 6.016.0 6.016.0 0.0-16.4 Sample B Gr. beta ND _ 57.015.0 48 3-65.7 St-89 3311.2 5.015.0 0.0-13.7 Sr-90 53i1.2 5.011.5 - 2.4-7.6 - Cc4 63.3113 50.015.0 413 58.7 Cs-134 7.711.2 7.015.0 0.0-15.7 Cs-137 8311.2 7.015.0 0.0 15.7 STU 535 Urine Apr 1988 . H3 64831.155 62021620 5128-7276-STW 536 Water Apr 1988 Sr-89 14 7113 _20.015.0 11.3-28.7 Sr-90 20.0+ 2.0 20 011.5 17.4-22.6 STW-538 Water Jun 1988 Cr-S1 331.7113.0 302.0130.0 -250.0-354.0-Cc>-60 16.012.0 15.015.0 63 23.7 Zn-65 107.7111.4 101.0110.0 83.7-1183 Ru-106 191 3111.0 195.0t20.0 160.4-229.6: Cs-134 -18314.6 20.015.0 11 3-28.7 Cs-137 26311.2 25.015.0 163-33.7 STW-539 Water Jun 1988 H-3 5586192 55651557- 4600-6530 STW-541 Milk Jun 1988 _ Sr-89 33.7111.4- 40.015.0- 31.3-48.7 Sr 90 55315.8 60.013.0 _ 54.8-65.2 1-131 103.713.1 94.019.0 78.4-109.6 Cs-137 52.713.1 51.015.0 42.3-59.7 - K 1587i23 1600180 1461-1739 STW-542 - Water Jul1988 Gr. alpha 8.714.2 15.0 5.0- 6 3-23.7 Cr. beta 5311.2 4.015.0 0.0-12.7 STF-543 ~ Food - Jul1988 St-89 NDI 33.0i5.0 24 3-41.7 Sr-90 ND 34.012.0 30.5-37.5 I-131 115.015 3 107.0111.0 88.0-126.0 Cs-137 52.716.4 49.0i5.0 403 57.7 K 1190166 1240162 1_131-134_.Z B-4
Table B-1 ' (continued) Concentration in t>C1/Lb EPA Resultd lab Sample Date TIML Result Control Code Type. Collected Analysis i2cC 1s, N=1 Limits STW-544 Water Aug 1988 I-131 80.0 0.0 76.018.0 62.1 89.9 L 545 - Water Aug 1988 Pu-239 11.0d0.2 10.211.0 8.5-11.9 STW 546 Water Aug 1988 Uranium 6.010.0 6.016.0 0.0-16.4 STAF-547 Air Filter Aug 1988 Gr. alpha 8.0do.0 8.015.0 0.0-16.7 Gr. beta 26311.2 29.015.0 203-37.7 Sr-90 8.012.0 8.011.5 5.4-10.6 Cs-137 13.012.0 12.0 5.0 3 3-20.7 STW-548 Water Sep 1988 Ra-226 93d0.5 8.412.6 6.2 10.6 Ra-228 5.810.4 5.411.6 4.0-6.8 STW-549 Water Sep 1988 Gr. alpha 7.0i2.0 8.015.0 0.0-16.7 Gr. beta 11311.2 10.015.0 1 3-18.7 STW-550 Water Oct 1988 - Cr-51 252.0 14.0 251.0125.0 207.7-2943 Co-60 26.0i2.0 25.015.0 16 3-33.7 Zn-65 158 3110.2 151.0115.0 125.0-177.0 Ru-106 153.0d9.2 152D115.0 126.0-178.0 Cs-134 23.715.0 25.0 5.0 163-33.7 Cs-137 16.311.2 15.015.0 6.3-23.7 STW-551 Water Oct 1988 H-3 23331127 23161350 1710-2927 STW-552 Water Oct 1988 553 (Blind) Sample A Gr. alpha 38313.0 41.0110.0 23.7-58 3 Ra-226 4.5i0.5 5.010.8 3.6-6.4 Ra-228 4.410.6 5.210.8 3.6-6.4 Uranium 4.711.2 SD16.0 0.0-15.4 Sampie 11 Gr. beta 51 3 i3.0 54.015.0 45.3-62.7 Sr-89 3.711.2 11.0 5.0 2 3-19.7 Si-90 10.7il.2 10.011.5 7.4-12.6 Cs-134 153123 15.015.0 6 3-23.7 Cs-137 16.711.2 15D15.0 6 3-23.7 B-5
Table B-1. (continued) Concentration in rCl/Lb FPA Resuhd Lab Sample - Ebte TIML Result Control Code Type Collected Analysis 120C 1s, N=1 Limits STM-554 Milk - Oct 1988 Sr-89 40.317.0 40.015.0 31.3-48.7 Sr-90 51.012.0 60.0i3.0 M.8-65.2 . 1-131 94.0d3.4 - 91.019.0 75.4-1 % .6 Cs-137 45.014.0 50.015.0 413 58.7 K 1500145 1600180 1461-1739 STU-555 Urine Nov 1988 H-3 30301209 30251359 2403-3647 STW-556 Water Nov 1988 Gr. alpha 9.013.5 9.015.0 0 3-17.7 Gr. beta 9.711.2 9.015.0 0 3-17.7 - STW-557 Water Dec 1988 I-131 108.713.0 115.0112.0 94.2-135.8 STW-559 Water Jan 1989- Sr-89 40.018.7 40.015.0 31 3-48.7 Sr-90 24313.1 25.01.1.5 22.4-27.6 STW-560 ' Water Jan 1989 Pu-239 5.611.1 4.210.4 3.5-4.9 STW-561 Water - Jan 1989 Gr. alpha 7.311.2 8.015.0 0.0-16.7 Gr. beta 5.311.2 4.0i5.0 0.0-12.7 STW-562 Water Feb l989 Cr-51 245146 235124 193.4-276.6 Co40 10.0 2.0 10.015.0 1 3-18.7 Zn-65 170110 159116 139.2-186.7 Ru-106 18117.6 178118 146.8-209.2 Cs-134 9.7d3.0 ' 015.0
. 1 3-18.7 Cs-137 11.711.2 t a15.0 1 3-18.7
, STW-563 - Water Feb 1989 I-131 109.014.0 106.0111.0 86.9-125.1 STW-564 Water Feb l989 H-3 2820120 27541356 2137-3371 STW-565 Water Mar 1989 Ra-226 - 4.2iO3 4.910.7 3.7-6.1 Ra-228 1.911.0 1.7d03 1.2-2.2 STW-566 Water Mar 1989 U 5.0 10.0 5.016.0 0.0-15.4 STAF-567 Air Filter Mar 1989 Cr. aIpha .21.7il.2 21.015.0 12.3 29,7 Cr. beta 68.314.2 62.015.0 53 3-70.7 Sr-90 20.012.0 20.011.5 17.4-22.6 Cs-137 21311.2 20.015.0 11 3-28.7 B-6
3 Table B-1. (continued) Concentration in pCi/Lb EPA Resultd lab Sample - Date TIML Result Control Code Type Collected Analysis 12aC 1s, N=1 ' imits STW-568 _ Water Apr 1989 569 (Blind) Sample A Gr. alpha 22.7123 29.017.0 16.9-41.2 Ra-226 3.610.6 3.510.5 2.6-4.4 Ra-228 2.611.0 3.610.5 2.7-4.5 U 3.010.0 3 016.0 0.0-13.4 Sample B Gr. beta 52316.1 57.015.0 43.3-65.7 Sr-89 9315.4 8.015.0 0.0-16.7 Sr-90 7.0f0.0 8.011.5 5.4-10.6 C3-134 21.015.2 20.015.0 11.3-28.7 Cs-137 23.0i2.0 20.0i5.0 11328.7 STM-570 Milk Apr 1989 Sr-89 26.0110.0 39.015.0 30347.7' Sr-90 45.714.2 55.013.0 49 & 60.2 Cs-137 54.016.9 50.015.0 41358.7 K-40 1521i208 1600180 1461-1739
- STW-5718 Water May 1989 Sr-89 <0.7 6.015.0 0.0-14.7 Sr-90 5.011.0 6.011.5 3.4-8.6 STW-572 Water ' May 1989 Gr. alpha 24.012.0 30.018.0 16.1-43.9 Gr. beta 493115.6 50.015.0 41358.7
. STW-573 Water Jun 1989 Ba-133 50.711.2 49.015.0 40.3-57.7 Co.60 313123 31.015.0 22.3-39.7 Zn-65 167110 165il7 135.6-194.4 Ru-106 12319.2 128i13 105.5-150.5 Cs-1M 40311.2 3915- 30 3-47.7-Cs-137 22311.2 20i5 11.3-28.7 STW-574 Water lun 1989 H-3 45131136 45031450 3724-5282-
- STW-575 Water Jul 1P89 _ Ra-226 16.813.1 17.712.7 13.0-22.4 Ra-228 13.813.7 183i2.7 13.6-23.0 STW-576 Water Jul 1989 U 40311.2 41.016.0 30.6251.4
- STW-577 Water aug 1989 I-131 84.715.8 83.018.0 69.1 96.9-STAF-579 Air Filter Aug 1989 Gr. alpha 6.010.0 6.015.0 0.0-14.7 Cs-137 103123 10.015.0 1.3-18.7 B7
TableB 1. (continued) Conce. cation in oCi/Lb EPA Rei:ultd 12.b Sample Date TIML Rt-sult Control Code Type Collected Analysis 12aC 1s, N=1 Limits STW-580 Water Sep 1989 Sr-89 14.711.2 14.015.0 5 3-22.7 Sr 90 9.711.2 10.011.5 7.4-12.6 STW-581 Water Sep 1989 Gr. alpha S.010.0 4.015.0 0.0-12.7 Gr. beta 8.7123 6.015.0 0.0-14.7 STW-583 Water Oct 1989 Ba-133 60 3110.0 59.016.0 48.6-69.4 Co-60 29.014.0 30.015.0 21.1 38.7 Zn 65 132316.0 129.0113.0 106.5-151.5 Ru-106 155316.1 161.0116.0 133 3-188.7 Cs-134 30.716.1 29.015.0 20.3-37.7 Cs-137 66314.6 59.015.0 503167.7 STW-584 Water Oct 1989 H-3 3407i150 34961364 286614126 STW-585 Water Oct 1989 586 (Blind) Sample A Gr. alpha 41.719.4 49.0112.0 28.2-69.8 Ra-226 7.910.4 8.4113 6.2-10.6 Ra-228 4.410.8 4.110.6 3.1-5.1 U 12.0 0.0 12.016.0 1.6-22.4 Sampie B Gr. beta 31.7123 32.015.0 23340.7 Sr-89 13 3 i4.2 15.015.0 6 3-23.7 Sr-90 7.012.0 7.013.0 4.4-9.6 CrA34 5.0 10.0 5.015.0 0.0-13.7 Cs-137 7.00.0 5.015.0 0.0-13.7 STW-587 Water Nov 1989 Ra-226 7.910.4 8.7113 6.4-11.0 Ra-228 8.911.2 9.311.2 6.9-11.7 ST W-588 Water Nov 1989 U 15.010.08 15.0 6.0 4.6-25.4 STW-539 Water Jan 1990 Sr-89 22.715.0 25.015.0 16 3-33.7 Sr-90 17.311.2 20.011.5 17.4 22.6 STW-591 Water Jan 1?90 Gr. alpha 10313.0 12.015.0 3 3-20.7 Gr. beta 12.311.2 12.015.0 3 3-20.7 B8 l
~ Tcble B 1. (continued)
.__ - Concentration in oC1/Lb EPAlendid Lab Sarnple Date - TIML Result Control Code Type Collected Analysis 12oC 1s, N=1 Limits STW-592 Water Jan 1990 Co.4) 14.7123 1515.0 6 3-23.7 Zn-o5 135.016.9 139.0114.0 114.8-163.2 Ru-106 1333113.4 139.0114.0 114.8-163.2 Cs-134 173il.2 18.015.0 9 3-26.7 Cs-137 193il.2 18.015.0 9 3-26.7 -
Ba 133 78.010.0 74.017.0 61.9-86.1 STW-593 Water Feb l990 H-3 4827iS3 49761498 4113-5S39 STW-594 Water Mar 1990 Ra-226 5.010.2 4.910.7 4.1-5.7 Ra-228 13.510.7 12.711.9 9.4-16.0 STW-595 Water - Mar 1990 U 4.010.0 4.015.0 0.0-14.4 STAF-596 Air Filter Mar 1990 Gr. alpha -7311.2 5.015.0 0.0-13.7 Gr. beta 34.010.0 31.015.0 22.3-39.7 Sr 10.0f0.0 10.011.5 7.4 12.6 Cs-137 9311.2 10.015.0 1 3-18.7
- STW-597 Water Apr 1990 598 (Blind)
' Sample A Gr. alpha 81.0 3.5 90.0 23.0 50.1-129.9 Ra-226 ' 4.910.4 5.010.8 3.6-6.4 Ra-228 10.6103 10.211.5 7.6 12.8 U 18.713.0 20.016.0 9.6-30.4 Sample B Gr. beta - 51.0110.1 52.015.0 43 3-60.7 Sr-89 9311.2 10.0 5.0 1 3-18.7 Sr-90 10313.1 10.011.5- 8 3-11.7 Cs-134 '16.010.0 15.0i5.0 6 3-23.7 Cs-137 19.0i2.0 15.0i5.0 6 3-23.7 STM 599 Milk ' Apr 1990 Sr-89 21.713.1 23.0i5.0 14.3-31.7 Sr-90 21.017.0 - 231015.0 14 3-31.7 l-131 98.7il.2 99.0110.0 81.7-1163 Cs-137 26.016.0 24.0 5.0 15.3-32.7 K 1300.0169.2 1550.0178.0 1414.7-16853 STW-600 Water - May 1990 Sr-89 6.012.0 7.015.0 0.0-15.7 Sr 6.7il.2 7.015.0 0.0-15.7 STW-601 Water May 1990 Gr. alpha 11.012.0 22.016.0 - 11.6-32.4 Gr. beta 12311.2 15.015.0 63-237 B-9
3 Table B 1. (continued) Concentration in rCif.Lb EPA Resultd lab Sample Date TIML Result Control Code Type Collected Analysis 12aC 15, N=1 Limits STW-602 Water Jun 1990 Co-60 253123 24.015.0 153-32.7 Zn-65 155.0110.6 148.0115.0 130.6-165.4 Ru 106 202.7117.2 210.0i21.0 173.6 246.4 Cs-134 23.711.2 24.015.0 18.2-29.8 Cs-137 27.713.1 25.015.0 163-33.7 Ba-133 100.718.1 99.0110.0 81.7-1163 STW 603 Water Jun 1990 H-3 29271306 29331358 2312-3554 STW-604 Water Jul 1990 Ra-226 11.810,9 12.lil.8 9.0-15.2 Ra-228 4. lit.4 5.111.3 2.8-7.4 STW-605 Water Jul 1990 U 20311.7 20.813.0 13.6-26.0 STW-606 Water Aug 1990 I-131 43 011.2 39.016.0 28.6149.4 STW-607 Water Aug 1990 Pu-239 10.011.7 9.110.9 7.5-10.7 STAF-608 Air Filter Aug 1990 Cr. alpha 14.010.0 10.015.0 1 3-18.7 Gr. beta 65311.2 62.015.0 53 3-70.7 Sr-90 19.0i6.9 20.015.0 11 3-28.7 Cs-137 19.012.0 20.015.0 11 3-28.7 STW-609 Water Sep 1990 Sr-89 9.012.0 10.015.0 1 3-18.7 Sr-90 9.012.0 9.015.0 0 3-17.7 STW-610 W ater Sep 1990 Gr. alpha 8.311.2 10.015.0 1 3-18.7 Cr. beta 103tl.2 10.015.0 1 3-18.7 STM-611 Milk Sep 1990 Sr-89 11.713.1 16.0i5.0- 7 3-24.7 Sr-90 15.010.0 20.0t5.0 11 3-28.7 I-131 63.016.0 58.016.0 47.6-68.4 Cs-137 20.0i2.0 20.015.0 11 3-28.7 K 16733170.2 1700.0185.0 1552.5-1847.5 STW-612 Water Oct 1990 Co-60 20313.1 20.015.0 11 3-28.7 Zn-65 1153112.2 115.0112.0 94.2-135.8 Ru-106 152.0 8.0 151.0115.0 125.0-177.0 Cs-134 11.010.0 12.015.0- 3 3-20.7 Cs-137 14.012.0 12.015.0 3 3-20.7 Ba-123 116.719.9 110.0111.0 90.9-129. STW-613 Water Oct 1990 H-3 7167i330 72031720 5954-8452 B-10
Table B-1. (continued) Concentration in oCl/Lb EPA Resultd 1.ab Sample Date TIML Result - Control , Code Type Collected Analysis 12cc Is, N=1 Limits STW-614 Water Oct 1990 615 Sample A Cr. alpha 68.717.2 62.0 16.0 34.?-89.8 Ra-226 12.910 3 13.612.0 10.1-17.1 Ra-228 4.210.6 5.0113 2.7-73 U 10.4d0.6 10.2i3.0 5.0-15.4 Sample B Cr. beta 55.018.7 53.015.0 '44 3-61.7 Sr-89 15.712.9 20.015.0 11 3-28.7 Sr-90 12.012.0 15.015.0 6 3-23.7 Cs-134 9.011.7 7.015.0 0.0-15.7 Cs-137 7.711.2 5.015.0 0.0-13.7 STW-616 Water ' Nov 1990 Ra 226 6.811.0 7.411.1 5.5-93 Ra-228 5311.7 7.711.9 4.4-11.0 STW-6175 Water Nov 1990 U 35.0io.4 35.513.6 29.3141.7 STW-618 Water . Jan 1991 Sr-89 4311.2 5.05.0 0.0 -13.7 St-90 4.711.2 5.015.0 0.0-13.7 STW-619 Water Jan 1991 Pu-239 3.60.2 3310.3 2.8-3.8
. STW-620 Water Jan 1991 Gr. alpha 6.713.0 5.035.0 0.0-13.7 Cr. beta 6311.2 5.015.0 0.0-13.7 STW-621 Water Feb 1991 Co-60 41318.4 40.015.0 31 3-48.7
' Zn-65 166.7119.7 149.0 15.0 123.0-175.0 Ru-106 209.7118.6 186.0119.0 153.0-219.0 Cs-134 5,012.0 8.015.0 0.0-16.7 Cs-137 9.711.2 8.03 5.0 0.0-16.7 Ba-133 85.7d9.2 75.018.0 61.1-88.9 l- STW-622 Water Feb l991 1-131 81316.1 75.018.0 61.1-88.9
.STW-623 Water ' Feb l991 H-3 4310.01144.2 4418.0 442.0 3651.2-5184.8 l STW-624 Water - Mar 1991 Ra-226 31.413.2 31.814.8 23.S-40.1 Ra-228 NDh 21.1153 11.9-303 l; STW-625 Water Mar 1991 U 6.710.4 7.613.0 2.4-12.8 L
L t t L B-11 1 l
Table B-1.L (contidued)~
- Concentration in oCl/Lb _
EPA Resultd lab Sample INte TIML Result Control Code Type Collected Analysis doc 1s, N=1 Limits STAF-626 - Filter Mar 1991; Gr. alpha 38.7il.2 25.016.0 14.6-35.4-- Gr. beta 130.014.0 124.016.0 113.6-134.4i Sr-90 35.711.2 40.015.0 313-48.7 Cs-137 33.714.2 40.015.0 31 3-48.7. r STW-627- Water Apr 1991 623 Sample A ~ Gr. alpha 51.016.0 54.0114.0 29.7-783 Ra 226 7.010.8 8.011.2 5.9-10.1. , Ra.228 -9.7tl.9 15.213.8 8.6-21.8 U 27.712.4 - 29.813.0 24.6-35.0 Sampie B Gr. beta 93 3 i6.4 115.0117.0 85.5-144.5 - ,
- Sr-89 21.013.5 28.015.0 19 3-36.7 26.015.0 173 34.7?
Sr-90 23.010.0 Cs-134 27311.2- 24.015.0 153-32.7-Cs-13" 29.017"J - 25.015.0 163-33.7-STM-629 E Milk Apr 1991- S.-89 2/,0t8.7 32.015.0 - ' 23 3-40.7 - 3r 28.0i2.0 32.015.0- 23 3-40.7 141- 653i14.7- 60.016.0- - 49.6-70.4-Ce137 54.7111.0 49.015.0 40.3-57.7 t K 1591.71180.1 1650.0183.0 1506.0-1794.0
= STW-630 JWater -May 1991 Sr-89f 40.7t23 39.015.0 303-47.7 -~
S.-90 : 23.711.2 24.015.0 - 153-32.7 = - STW-631 Water - - Mr;199T Pr, alpha 27.715.8 24.016.0 13.6-34.4 Gr. beta 46.010.0 46.015.0 = 373-54.7 i STW 632 LWater Jun 1991 Co.60 - 11311.2 10.0i5.0 1 3-18.7
- Zn 11931163 108.0111.0 88.9-127.1' Ru-106 .1623119.0 149.0i15.0 - 123.0 175.0' Cs-134 :15311.2 15.0i5.01 6 3-23.7
. Cs-137 163tl.2 14.0 5.0 5 3-22.7 Ba-133 - 74.0i6.9 62.016.0 ' 51.6-72.4 = >
- STW-633 Water Jun 1991 - - H-3 13470.0i385.8 12480.011248.0 10314.8-14645.2 STW-634 - . Water- .
Jul1991 Ra-226 - 14.910.4 15.9i2.4 11.7-20.1; Ra-228 ~ 17.611.8 16.7i4.2 9.4-24.0 L i- p B-12 i4 - i
) =
4 tva g , , - - - + y- t rw ~ e
I Tabla B-1. (continued) Concentration in oCi/Lb EPA Resultd lab Sample - Date TIML Result C+ ntrol Code -Type Collected Analysis 12aC 1s, N=1 i.imits STW-635 Water - Jul 1991 U 12.810.1 14.2i3.0 9.0-19.4 STW-636 Water Aug 1991 1-131 19 3 i1.2 20.016.0 9.6-30.4 - STW-637 Water Aug 1991 Pu 239 21.410.5 19.411.9 16.1 22.7 STW-638 Filter Aug 1991 Gr. alpha 33.0i2.0 25.016.0 14.6-35.4 Gr. beta 88.711.2 92.0110.0 80.4-103.6 St-90 27.014.0 30.015.0 21 3-38.7
/ 26.311.2 30.015.0 21 3-38.7 i
STW-639 Water Sep 1991 Sr-89 47.0110.4 49.015.0 40 3-57.7-Sr-90 24.012.0 25.015..) 163-33.7 STW 640 Water Sep 1991 Gr. alpha 12.014.0 10.015.0 1 3-18.7 Gr. beta 20.311.2 20.015.0 11 3-28.7 STM-641 - Milk Sep 1991 St-89 20315.0 25.015.0 163-33.7 Sr-90 19.7 3.1 25.015.0 163-33.7 1-131 130.7116.8 108.0111.0 88.9-127.1 Cs-137 33.7i3.2 30.0 5.0 21 3-38.7 i K 1743 31340.8 1740.0187.0 1589.1-1890.9 l STW-642 Water Oct 1991 - CM0 29.711.2 29.015.0 20 3-37.7 Zn-65 75.7183 73.017.0 60.9-85.1 Ru-106 196.3115.1 199.0120.0 164 3-233.7 Cs-134 9.711.2 10.015.0 1 3-18.7 l Cs-137 11.012.0 10.015.0 13-18.7 Ba-133 94.7i3.1 98.0i10.0 80.7-1153 STW-643 Water Oct 1991 H-3 2640.01156.2 2454.01352.0 1843 3-3064.7 STW-644 Water Oct 1991 645 Sample A Gr. alpha 73.0113.1 82.0121.0 45.6-118.4 Ra-226 20.9i2.0 22.013 3 ' 163-277 Ra-228 19.6123 22.215.6 12.5-31.9-l U 13.510.6 13.513.0 8 3-18.7 Sample B Gr. beta 55313.1 65.0110.0 47.7-823 Sr 89 9.713.1 10.0i5.0 1 3-18.7 Sr-90 8.711.2 10.015.0 1 3-18.7 Co-60 20.311.2 20.015.0 113-28.7 Cs-1M 9.015 3 10.015.0 1 3-18.7 Cs-137 14.715.0 11.015.0 2 3-19.7 B-13
Tcble B-1. (continued) t Concentration in oCl/Lb EPA Resultd ~ lab Sample Ihte TIML Result Control Code. . Type- Collected Analysis 12cc Is, N=1 Limits STW-646 Water Nov 1991 Ra-226 5.611.2 6.511.0 4.8-8.2 Ra 228 9.610.5 8.li2.0 4.6-11.6 STW-647 Water Nov 1991 U 24.712.3 24.913.0 19.7 30.1 a Results obtained by Teledyne botopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. Environmental Protection Agency (EPA), Las Vegas, Nevada, b All results are in pCl/1, except for elemental potassium (K) data in milk, which are in mg/1; air filter samples, which are in pCi/ filter; and food, which is in mg/kg. c Unless otherwise indicated, the TIML results are given as tl.a mean i 2 standard deviations for three determinations. d USEPA results are presented as the known values and expected laboratory precision (1s, I determination) and control limits as dermed by EPA. e NA = Not analyzed. _ f ND = No data; not analyzed due to relocation oflab. 8 Sample was analyzed but the results not submitted to EPA because deadline was missed (all data on file). 1 h ND = No data; sample lost during analyses.
-t B 14
~n -
- , - .+ - ,
Table B 2. Crosscheck program results, thermoluminescent dosimeters (TLDs). mR Teledyne ^"erage 12cd Lab Result Known 311 Code TLD Type Measurement 12ca ValueC Participants) 2nd International Intercomnarisonb 115-2 CaF2 :Mn Field 17.011.9 17.1 16.417.7 Bulb Lab 20.814.1 21.3 18.817.6 3rd International Intercomparisone 115-3 CaF2 :Mn Field 30.713.2 34.914.8 31.513.0 Bulb lab 89.616.4 91.7114.6 86.2124.0 4th International Intercomparisonf 115-4 CaF2 :Mn Field 14.111.1 14.111.4 16.019.0 Bulb lab (Low) 93il.3 12.2i2.4 12.017.4 lab (Wgh) 40.411.4 45.819.2 43.9113.2 5th International Intercomp,a_rJ1Qn8 115-5A CaF2 :Mn Field 31.411.8 30.016.0 30.2114.6 Bulb Lab at beginning 77.415.8 75.2i7.6 75.8140.4 La'a at the end 96.6i5.8 88.418.8 90.7131.2 115-5B LiF-100 Field 30314.8 30.016.0 30.2114.6 Chips Field at beginning 81.117.4 75.217.6 75.8140.4 Lab at the end 85.4111.7 88.418.8 90.7131.2 7th International Comparison h 115-7A LiF-100 Field 75.412.6 75.816.0 75.1129.8 Chips Lab (Co-60) 80.013.5 79.914.0 77.9127.6 1.ab (Cs-137) 66.612.5 75.0 3.8 73.0122.2 B-15
Table B 2. Crosscheck program results, thermoluminescent dosimeters (TLDs). mR Teledyne Average 2cd lab Result Known (All Code TLD Type Measurement A2ca ValueC Participants) 115-7B CaF2 :Mn Field 71.512.6 75.816.0 75.1129.8 Bulbs Lab (Co40) 84.816.4 79.9 4.0 77.9127.6 lab (Cs-137) 78.8il.6 75.013.8 ' 73.0122.2 115-7C CaSO4 :Dy Field 76.812.7 75.816.0 75.1129.8 Cards lab (Co40) 82.513.7 79.914.0 77.9127.6 lab (Cs-137) 79.013.2 75.013.8 73.0122.2 8th International Intercomparisor,i 115-8t. LIF-100 - Field Site 1 29.5i1.4 29.721.5 28.9112.4 Chips - Field Site 2 11.310.8 10.410.5 10.139.06 I.ab (Cs-137) 13.7i0.9 17.210.9 16.216.8 115-8B CaF2 :Mn Field Site 1 32.311.2 29,711.5 28.9112.4
. Bulbs Field Site 2 9.011.0 10.410.5 10.139.0 Lab '.Cs-137) 15.810.9 17.2io.9 16.216.8 115-8C - CaSO4 :Dy Field Site 1 32.2i0.7 29.711.5 28.9112.4 Cards Field Site 2 10.6 0.6 10.410.5 10.1 9.0 12b (Cs-137) 18.110.8 17.210.9 16.2i6.8 Teledyne Testinej 89-1 LIF-100 Lab 21.010.4 22.4 -
Chips 89-2 Teledyne 12b 20.9 1.0 20.3 - CaSO4:Dy Cards B.16
Table B-2. (continued) mR Teledyne Average i2cd Lab Result Known (All Code TLD Type Measurement 12ca ValueC Participants) Teledyne Testinc} 90-1k Teledyne Lab 20.611.4 19.6 - CaSO4 Oy Cards 90-11 Teledyne lab 100.814.3 100.0 - CaSO4 Dy Cards 91-1m Teledyne lab 33.412.0 32.0 - CaSO4 Oy 55.214.7 58.8 - Cards 87.816.2 85.5 - a I.ab result given is the mean 2 standard deviations of three determi.nadors, b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health 'and Safety Laboratory (HASL), New York, New York, ard the School of Public Health of the University of Texas, Houston, Texas. c Value determined by sponsor of the intercomparison using cantinuously operated pressurized ion chamber, d Mean i2 standard deviations of results obtained by all laboratories participating in the program. e Third International Intercomparison of Environmental Dosimeters conducted , summer of 1977 by
. Oak Ridge National Laboratory and the School of Public Health of the Universt y of Texas, Houston,
~ Texas.
f Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas Houston, Texas. 8 Fifth International Intercomparison of Environmental Dosimeters conducted in fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and Environmental Measurements' Laboratory, New York. New York, U.S. Department of Energy.
-h Seventh' International Intercomparison of Environmental Dosimeters conducted in the spring and summer of,1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The U.S.
Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. i Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 19_85-1986 at New York, New York, and sponsored by the U.S. Departinent of Energy. j Chips were submitted in Sephmber 1989 and cards were submitted in November 1989 to Teledyne Isotopes, Inc., Westwood, NJ for irradiation. k Cards were irradiated by Teledyne Isotopes, Inc., Westwood, NJ on June 19,1990. 1 Cards were irradiated by Dosimetry Associates,'Inc., Northville, MI on October 30,1990. m Irradiated cards were provided by Teledyne Isotopes, INC , Westwood, NJ. Irradiated on October 8,1991. B-17
Table B-3. In-house spiked samples.
~
Concentration in oCi/L lab Sample Die TIML Expected Code Type rollected Analysis Result Known Precision - n=1 Activity 1s, n=l a QC-MI-16 Milk Feb 1988 Sr-89 31.&t4.7 31.716.0 8, Sr-90 25.512.7 27.8i3.5 52 1-131 26.410.5 23.2i5.0 10.4 Cs-134 23.812.3 24.216.0 8.7 Cs-137 26.510.8 25.116.0 8.7 QC-MI-17 ' Milk Feb 1988 I-131 10.611.2 14311.6 10.4 QC-W-35 Water Feb l988 I-131 9.711.1 11.611.1 10.4 QC-W-36 Water Mar 1988 1-131 10.511.3 11.611.0 10.4 QC-W-37 Water Mar 1988 Sr-89 17.li2.0 19.818.0 8.7 Sr-90 18.7i0.9 17.315.0 5.2 QC-MI 18 Milk Mar 1988 1-131 33.2i2.3 26.715.0 10.4 Cs-134 31312.1 30.215.0 8.7 Cs-137 29.911.4 2e 2 5.0 8.7 QC-W-38 Water Apr1988 I-131 17. lit.1 14.215.0 10.4 QC-W-39 Water Apr 1988 H-3 4439131 41761500 724 QC-W-40 Water Apr1988 Co40 23.710.5 26.li4.0 S.7 Cs-134 25.412.6 29.214.5 8.7 Cs-137 26.612.3 26.214.0 8.7 QC-W-41 Water Jun 1988 Gr. alpha 12310.4 13.1i5.0 8.7 Cr. beta 22.611.0 20.115.0 8.7 QC-MI-19 Milk Jul 1988 Sr-89 15.111.6 16.415.0 8.7 Sr-90 18.010.6 18315.0 5.2 1-131 88.414.9 86.618.0 10.4 Cs-137 22.710.8 20.816.0 8.7 QC-W-42 Water Sep 1988 Sr-89 48.5i3.3 50.818.0 8.7 Sr-90 10.911.0 11.413.5 5.2 QC-W-43 Water Oct 1988 Co-60 20.913.2 21.413.5 8.7 Cs-1M 38.7il.6 38.016.0 8.7 Cs-137 19.0i2.4 21.013.5 8.7 QC-W-44 Water Oct 1988 I-131 22.210.6 23313.5 10.4 i B-18
Table B 3. In house spiked samples (continued) CQattDtration in pCi/L ! Lab Sample Date TIML Expected : Code Type " >llected Analysis Result Known Precision
""I Activity 1s,n=1a QC-W 45 Water Oct !9M H3 4109143 41531500 7.'4 (p MI 20 Mlik Oct 1988 I131 59.810.9 60.619.0 10.4 Cs 134 49.611.8 48.617.5 8.7 Cs-137 25.814.6 21.714.0 8.7 QC-W-46 Water Dec 1988 Cr. alpha 11.5i2.3 15.215.0 8.7 Cr. beta 26.512.0 25.715.0 8.7 QC MI-21 Milk Jan 1589 Sr-89 25.5110.3 34.0110.0 8.7 Sr-90 28V.3.2 27.113.0 5.2 I131 540113 550120 10.4 Cs 134 24.512.6 22.615.5 8.7 Cs-137 24.010.6 20.515.0 8.7 QC-W 47 Water Mar 1989 St89 15.213.8 16.115.0 8.7-Sr90 16.411.7 16.913.0 5.2 QC-M1-22 Milk Apr 1989 I131 36.311.1 37.215.0 10.4 Cs-134 . 20.812.8 20.743.0 8.7 Cs-137 22.212.4 20.413.0 8.7 QCV Water Apr 1989 Co 60 23.512.0 25.118.0 8.7 Cs 1M 24.211.1 25.918.0 8.7 Cs-137 23.611.2 23.018.0 8.7 QC W-49 Water Apr 1989 l-131 37.2i3.7 37.225.0 10.4 QC W 50 Water Apr 1989 11-3 3011i59 30891500 724 ,
QC-W-51 Water Jun 1989 Gr. alpha 15.011.8 15.015.0 8.7 Cr. beta 26.011.2 25,518.0 8.7 i QC MM3 Milk Jul1989 Sr-89 19.416.5 22.0110.0 8.7 Sr 90 27.61*.5 a - 28.613.0. 5.2
- l-131 46.813.2 43.415.0 10.4
- . Cs-134 27.411.8 28.316.0 8.7 Cs 137 24.111.8 20.816.0 8.7
- L l QC-MI 24 Milk Aug 19'.9 Sr-89 75.412.7 27.2110.0 8.7 L Sr-90 46.011.1 47.819.6 83 QC-W 52 Water Sep 1989 1131 9.610.3 9.711.9 10.4 l -
B 19
--pi P' - -9 -- v
i Table B 3. In-houen spiked samples (continmd) ~ ~ ConcCDlD.tica in ICI/L I4 Sample Date T'M . L b p wted Code Type Collected Analysis Result Known Precision n=1 Activity 1s, n=l a QC W-53 Water Sep 1989 l131 19.020.2 20.914.2 10.4 QC W 54 Water Sep 1989 Sr 89 25.814.6 24.714.0 8.7 Sr90 26.515 3 29.715.0 5.2 QC-MI-25 Milk Oct 1989 l131 70.013.3 73.5120.0 10.4 Cs-134 22.112.6 22 613.0 8.7 C3 i37 29.411.5 27.518.0 8.7 QC-W-55 Water Oct 1989 I131 333113 353110.0 10.4 QC W-56 Water Oct 1989 Co40 15.210.9 17.415.0 8.7 C5134 22.114.4 18.918.0 8.7 Cs-137 27.211.2 22.91B.0 8.7 QC-W 57 Water Oct 1989 R3 3334122 33791500 724 QC-W 58 Water Nov 1989 Sr-89 10.911.4d 11.111.0d 3,7 St 90 10.411.0d jo31),od 5.2 QC-W-59 ' Water Nov 1989 Sr-89 101.016.0d 104.1110.5d 17.5 Sr 90 98.013.0d 95.0110.0d 17.0 QC-W-60 Water Dec 1989 Cr, alpha 10.811.1 10.6:4.0 8.7 Cr. beta 11.610.5 11.4x4.0 8.7 QC-MI-26 Milk Jan 1990 Cs-1M 19311.0 20.818.0 8.7 Cs-137 25.211.2 22.818.0 8.7 QC-MI-27 Milk Feb 1990 Sr 90 18.011.6 18.815.0 5.2 QC-MI 28 Milk Mar 1990 I-131 63.812.2 62.616.0 63 QC-MI 41 Water Apr 1990 Sr 89 17.915.5 23.11B.7 8.7 Sr-9; 19.412.5 73 515.2 53 T MI 29 Milk Apr1990 M31 90.719.2 82.518.5 10.4 Cs-1M 18311.0 19.715.0 8.7 Cs-137 20311.0 18.215.0 87 QC-W-62 Water Apr1990 CMC 8.710.4 9.415.0 8.7 Cs-134 20.010.2 19.715.0 8.7 Cs-137 28 711.4 22.715 0 8.7 B 20
i Tcble B 3. In house spiked samples (continued)
~
,_ Concentration in tCl/L lab Sample INte TIML bpected Code Type Collected Analysis Result Known Precision
""1 Activity 1s,n=ta QC W-63 Water Apr 1990 1131 63.518.0 66.016.7 6,6 QC-W44 Water Apr 1990 H-3 1941*130 1826.01350.0 724 QC-W-65 Water Jun 1990 Ra 226 6.410.2 6.9.11.0 1.0 QC-W-66 Water Jun 1990 .U 6.210.2 6.016.0 6.0 ,
QC-MI 30 Milk Jul 1990 Sr 89 12.810.4 18.4110.0 8.7 Sr 90 18.211.4 18.716.0 5.2 Cs 134 46.011.3 49.015.0 8.7 Cs-137 27.6113 25315.0 8.7 i QC-W-68 Water Jun 1990 Cr. alpha 9.810 3 10.6 6.0 8.7 Gr. beta 11.410.6 11.317.0 8.7 QC MI 31 Milk Aug 1990 1131 68.811.6 61.41123 10.4 QC W-69 Water Sep 1990 Sr 89 17.711.6 19.2110.0 8.7 Sr 90 13.911.6 17.4110.0 5.2 QC-MI-32 Milk Oct 1990 1131 34.810.2 32.416.5 8.7 Cs-134 25.811.2 27.3110.0 8.7
- Cs-137 25312.0 22.4110.0 8.7 QC-W-70 . Water Oct 1990 H-3 2355159 227614H 605 QC-W 71 Water Oct 1990 1-131 55.910.9 51.8110.4 10.4 h QC-W 73 Water Oct 1990 Cc>.60 183i2.7 16.815.0 8.7 C3134 28.3123 27.015.0 8.7 Cs 137 22.7113 22.435.0 8.7 QC W-74 Water Dec 1990 Gr. alpha 21.411.0 26.116.5 11 3 Gr. beta 25.911.0 22315.6 9.7 QC MI-33 Mlik Jan 1991 Sr-89 20.713 3 21.61S.0 5.0 Sr-90 19.011.4 23.013.0 3.0 22211.7 Cs-134 19.615.0 5.0 Cs-137 26.111.6 223 i5.0 5.0 QC Mh34 - Milk Feb l991 1-131 40.711.8 40.116.0 6.0 QC-W Water Mar 1991 Sr 89 18.811.5 23.315.0 5.0 Sr 90 16.010.8 17.213.0 3.0 D-21
Table B 3. In house spiked samples (continued)
~
Concentration in DCI/L 1.ab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision < n=1 Activity 1s, n=P QC W 76 ber Apr 1991 1 131 56.511.7 59.015.9 5.9 QC W 77 Water Apr 1991 Co60 16.412.2 15.715.0 5.0 Cs-134 23.812.5 22.615.0 5.0 Cs 137 25.012.4 21.115.0 5.0 , QC W 78 Water Apr 1991 li3 10271188 40801408 408 QC MI 35 Mlik Apr 1991 1 131 48.010.8 49.216.0 6.0 Cs 134 19.212.0 22.6d5.0 5.0 Cs-137 22.812.2 22.115.0 5.0 QC-W 79 Weter Jun 1991 Cr. alpha 7.410.7 7.815.0 5.0 Cr. beta 11.010.7 -11.015.0 5.0 QC-MI-36 Milk Jul 1991 Sr-89 28.112.1 34.0110.0 10.0 Sr-90 11.610.7 11.513.0 3.0 1131 14.411.9 18315.0 5.0 Cs-137 34313.0 35.115.0 5.0 QC W 80 Water Oct 1991 Sr-89 27.416.9 24.415.0 5.0 Sr-90 11.711.4 14.115.0 5.0 QC-W 81 Water Oct 1991 - 1-131 19.110.7 20.614.2 42 QC W-82 Water Oct 1991 Co-60 22.612.7 22.115.0 5.0 Cs 134 15.Sil.8 17.615.0 5.0 Cs-137 17.512.1 17.615.0 5.0 QC-W-83 Water Oct 1991 H-3 46391137 43821438 438 QC MI-37 Milk Oct 1991 1131 23.613.2 25.815.0 5.0 C3-134 22.712.8 22.115.0 5.0 Cs-137 38313.0 35.115.0 5.0 QC W-84 Water Dec 1991 Cr. alpha 6.210.6 7.815.0 5.0 Gr. beta 11.010.7 11.015.0 5.0 a n=3 unless noted otherwise, b n=2 unless noted otherwise. C n=1 unless noted otherwise, d Concentration in pCl/rnl. i B 22
Table B 4. In house " blank" samples. Concentmtion (oCl/LJ Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 c) (4.66 o) SPS 5386 Milk Jan 1988 1-131 <0.1 <1 SPW 5448 " Dead" Water Jan 1988 H3 <177 <300 SPS-5615 Milk Mar 1988 C3-134 < 2.4 <10 Cs-137 <2.5 <10 1-131 <0.3 <1 Sr 89 <0.4 <5 Sr 90 2.410.5a <3 SIS-5650 D.I. Water Mar 1988 Th 228 <0.3 <1 Th 230 <.0.04 d Th 232 <0.05 <1 U-234 <0.03 <1 U 235 <0.03 <1 U-238 <0.03 <1 Am-241 <0.06 <1 Cm-241 <0.01 <1 Pu-238 <0.08 <1 Pu-240 <0.02 <1 SPS-6090 Milk Jul 1988 Sr-89 <0.5 <1 Sr 90 1.810.5 <1 1131 <0.4 <1 Cs 137 c0.4 <10 SPW-6209 Water Jul 1988 Fe-55 <0.8 <1 SPW-6292 Water - Sep 1988 Sr-89 <0.7 <1 Sr-90 <0.7 <1 l SFS-6477 Milk Oct 1988 1-131 <0.2 <1 l Cs-134 < 6.1 <10 1 Cs-137 <5.9 <10 SPW-6478 Water Oct 1988 1131 <0.2 <1 SPW-6479 Water Oct 1988 Co-60 <5.7 <10 Cs-134 <3.7 <10 l Cs-137 < 4.3 <10 L SPW-6480 Water Oct 1988 H-3 <170 <300 B-23
- ----,t e- , , gz e yer W- '--+-4 .y 4 u +y.+-:
I Table B-4. In house " blank" samples (continued)
~
_le,ncentration (rCl/ L) Acceptance - Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 o) (4.66 c) SPW-6625 Water Dec 1988 Gr. alpha <0.7 <1 Cr.hta <1.9 <4 S 5 6723 Milk Jan 1989 St 89 <0.6 <S St-90 1.910.5a <3 1131 (0.2 <1 Cs-134 <4.3 <10 C3-137 < 4.1 <10 SPW-6877 Water Mar 1989 Sr-89 <0.4 <5 St-90 <0.6 <1 SPS-6963 Milk Apr 1989 l131 <0.3 <1 Cs-134 <5.9 <10 Cs-137 <6.2 <10 SPW-7561 Water Apr 1989 11-3 <150 <300 SPW 7207 Water Jun 1989 Ra 226 <0.2 <1
, Ra 228 <0.6 <1 Sl%7208 Milk Jun 1989 Sr-89 <0.6 <5 St 90 2.110.5a <j 1 131 <0.3 <1 Cs-134 <6.4 <10 Cs-137 <7.2 <10 SPW 7588 - Water Jun 1989 Gr. alpha <0.2 <1 Cr. beta <1.0 <4 SPS-7322 Milk Aug 1989 Sr 89 <1,4 <5 Sr-90 4.811.0a <1 1-131 <0.2 <1 Cs-134 <6.9 <10 Cs-137. <8.2 <!O. i SPW 7559 Water Sep 1989 Sr-89 <2.0 <5 Sr.90 <0.7 <1 SPW-7560 Water Oct 1989 l-131 <0.1 <1 SPW 7562 Water Oct 1989 H' <140 <300 B 24 l
- - -. - ~_
Table B-4. In-house " blank" samples (continued) Concentrat'3n (nCi/1.) Acceptance lab Sarnple Date Results Criteria Code Type Collected Analysis (4.66 o) (4.66 c) S 5 7605 Milk Nov 1989 l131 <0.2 <1 l Cs-134 < 8.0 <10 Cs 137 <10 <10 SPW.7971 Water Dec 1989 Cr, alpha <0. 4 <1 Cr. beta <.0.8 <4 SPW-6039 Water Jan 1990 Ra-226 <0.2 <1 S 5 8040 Milk Jan 1990 Sr 89 <0.8 <5 i Sr-90 < 1.0 <1 i SPS-8208 Milk Jan i990 Sr-89 <0.8 <.5 Sr-90 1.610.5a <j Cs-134 <3.5 <10 Cs 137 <4.7 <10 S15-8312 Milk Feb l990 Sr 89 <0.3 <5 Sr 90 1.210.3a <j SPW-8312A Water Feb l990 Sr-89 <0.6 <5 i St 90 <0.7 <5 l SPS-8314 Milk Mar 1990 1-131 <0.3 <1 SPS-8510 Milk May 1990 1131 <0.2 <1 Cs-134 <4.6 <10 C3-137 <4.8 <10 SPW-8511 A Water May 1990 H3 <200 <300 i SPS-8600 Milk Jul1990 Sr-89 <0.8 <5 l- Sr-90 1.7i0.6a <j l l-131 <0.3 <1 l Cs-134 <5.0 <10 Cs-137 <7.0 <10 l l SPM-8877 Milk Aug 1990 1131 <0.2 <1 L SPW-8925 Water Aug 1990 H-3 <200 (300 l l l B 25
i Table E*A. In house " blank" samples (continued)
' Concentration (rCi/D ,
Acceptance lab Sample Date Resuhs Criteria ) Code Type Collected Analysis (4.66 c) (4.66 c) SPW 8926 Water Aug 1990 Gr. alpha <0.3 <1 Cr. beta <0.7 <4 , SPW 8927 Water Aug 1990 U 234 <0.01 <1 U-235 <0.02 <1 U 238 <0.01 <1 SPW 8928 Water Aug 1990 Mn 54 <4.0 <5 C&58 <4.1 <5 C&60 <2. 4 <5 Cs 134 <3.3 <5 Cs 137 <3.7 <5 SPW 8929 Water Aug 1990 Sr-89 <1.4 <5 Sr 90 <0.6 <1 SPW 69 Water .cep 1990 St 89 < 1.8 <5 Sr 90 <0.8 <1 SPW 106 Water Oct 1990 H3 <180 <300 1-131 <0.3 <1 SPM 107 Milk Oct 1990 1-131 <0.4 <1 Cs 134 <3.3 c5 Cs-137 <4.3 <5 SPW 370 Water Oct 1990 Mn 54 < 1.7 (5 Co-58 <2.6 <5 Cod) < 1.6 <5 Cs-134 <1.7 <5 Cs-137 <1.8 <5 SPW-372 ' Water Dec 1990 Cr. alpha <0.3 <1 Gr. beta <0.8 <4 SPS-406 Milk Jan 1991 Sr-89 <0.4 <5 Sr-90 1.810.48 <1 Cs 134 <3.7 <5 C9137 <5.2 <S SPS-421 Milk Feb l991 I131 <0.3 <1 i SPW-451 Water Feb l991 Ra.226 <0.1 <1 Ra-228 <0.9 -
<1
l Table B-4. In. house " blank" samples (continued) Concentration (oCL/1L.,% Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 o) (4.66 o) SPW 514 Water Mar 1991 Sr-89 <1.1 <5 Sr-90 <0.9 <1 SPW 586 Water Apr 1991 1 131 <0.2 <1 Co-60 <2.5 <5 Cs-1M <2.4 (5 Cs-137 <2.2 <5 SPS-587 Milk Apr 1991 1131 <0.2 <1 Cs-134 <1.7 <5 Cs-137 <1.9 <5 SPW 837 Water Jun 1991 Cr. alpha (0. 6 <1 Cr. beta <1.1 <4 SPM 953 Milk Jul 1991 Sr-89 <0.7 <5 Sr-90 0.410.3a <1 1131 <0.2 <1 Cs-137 <4.9 <5 SPM 1236 Milk Oct 1991 1-131 <0.2 <l Cs-134 <3.7 <5 Cs-137 <4.6 <5 SPW 1254 Water Oct 1991 Sr-89 <2. 8 <5 Sr-90 <0.7 <1 SPW-1256 Water Oct 1991 1-131 <0.4 <1 Co-60 <3.6 <5 Cs-1M <4.0 <5 Cs-137 <3.6 <5 SPW 1259 Weter Oct 1991 H-3 <160 <300 SPW-1444 Water Dm 1991 Ci. alpha <0.4 <1 Cr. beta <0.8 <4 i Low level of Sr-90 concentration in milk (1 - 5 pCi/L) is not unusual. B 27
1 TIML-BLIND 41 Revision 0,12 29-86 A*ITACHMENT B ACCEPTANCE CRITERIA FOR " SPIKED
- SAMPLES LADORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa j i
I One Standard Deviation Analysis Level for Single Determination l Gamma Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter
>100 pCl/ liter or kg 5% of known value Strontium 89b 5 to 50 pCl/ liter or kg 5 pCi/ liter
>50 pC1/ liter or kg 10% of known value Strontium 90b 2 to 30 pCi/ liter or kg 3.0 pCi/ liter
>30 pCl/ liter or kg 10% of known value Potassium >0.1 g/ liter or xg 5% of known va'ue Cross alpha <20 pC1/ liter 5 pCi/ liter
>20 pCl/ liter 25% of known value Cross beta <100 pCl/ liter 5 pCi/ liter ,
>100 pCi/ liter 5% of Imown value Tritium <4,000 pCi/ liter is = (pCl/ liter) =
169.85 x (known).0933
>4,000 pCi/ liter 10% of known value ,
Radium 226, 228 <0,1 pC1/19er 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value lodine 131, <55 pCi/ liter 6 pCi/ liter lodine 1 9b >55 pCi/ liter 10% of known value . Uranium-238, <35 pCi/ liter 6 pCi/ liter Nickel-64b, >35 pCi/ liter 15% of known value Technetium.99b Iron-55b 50 to 100 pCl/ liter 10 pCi/ liter
>100 pCl/ liter 10% of known s alue a From EPA publication, " Environmental Radioactivity Laboratory intercomparison Studies Procram, Fiscal Year,1981 1982, EPA-600/4-81-004.
b TIML limit. B 28 y - ,
i ADDENDUM TO APPENDIX 11 r The following is an explanation of the reasons why certain samples were outside the control limit specified : by the Environmental Protection Agency for the Interlaboratory Comparlons Program starting January ' 1988. EPA > TIML Control ' Result 1.imit lab Code Analysis (pCi/L)a (pCi/L)a Explanation STF-524 K 1010.71158.5b 1123.5-1336.5b Error in transference of data. Correct data was 1105133 mg/kg. Results m the past have been within the limits and TIML will monitor the situation in the future. STW-532 1131 9.012.0 6.2-8.8 Sample recounted after 12 days. The average result was 8311.7 pC1/L (within EPA control limits). The sample was recounted in order to check the decay. Results in the pasi have been within the limits and TIML will continue to monitor the situation in the future. STW-534 Co-60 63.311.3- 41.3 58.7 High level of Co 60 was due to contamination of beaker. Beaker was discarded upon discovery of > contamination and sample was recounted. Recount results were 53.213.6 and 50.912.4 pCi/L STM 554 Sr-90 51.012.0 54.8-65.2 The cause of low result was due to very-high fat content of milk. It should be noted that 63'T of all pt *ticipants failed this test. A. a, the average for all participants was 54.0 pCi/L before the Grubb and 55.8 pCi/L after the Crubb. STW-560 Pu-239 5.811.1 3.5-4.9 The cause of high results is not known though it is suspected that the standard was not properly calibrated by supplier and is under investigation. New Pu-236 standard was obtained and will be ustd for the next test. STW 568. Ra-228 2.611.0 2.7-4.5 The cause of low results is not known. Next EPA cross check results were within the control imits. No further action is planned. l B-29 .
)
ADDENDUM TO APPENDIX B (continued) EPA TIML Control Result Limit Lab Code Analysis (pCl/Da (pC1/Da Explanation STM 570 Sr-89 26.0110.0 303-47.7 The cause of low results was falsely high Sr 90 45.714.2 49.8-60.2 recovery due to suspected incomplete calcium removal. Since EPA sample was used up, interral spike was prepared and analyzed. The results were within control limits (See table B 3, sample QC MI 24). 140 further action is planned. STW-589 Sr 90 17.311.2 17.4-22.6 Sample was reanalyzed in triplicate; results of reanalyses were 18.811.5 pCl/L No further action is planned.
- STM-599 K 1300.0169.2c 1414.716853C Sample was reanalyzed in triplicate.
Results of reanalyses were 1421.7i95.3 mg/L. The cause of low results is unknown. STW-601 Cr. alpha 11.012.0 11.6 32.4 Sample was reanalyzed in triplicate. Results of reanalyses were 13.411.0 pCi/L STAF-626 Gr. alpha 38.7i1.2 14.6-35.4 The cause of high results is the difference in geometery between standard used in the TIML lab and EPA filter. STW 632 Ba-133 74.016.9 51.6-72.4 Sample was reanalyzed. Results of the reanalyses were 63.816.9 pCi/L within EPA timit. STW-641 1131 130.7116.8 88.9-127.1 The cause of high result is unkn6wn, in-house spike sample was prepared with activity of I-13168.316.8 pCi/L. Result of the analysis was 69.119.7 pCi/L a Reported in pCi/L unless otherwbe noted, b Concentrations are reported in mgf kg. c Concentrations are reported in mg/t. l B 30 t . , - , - - - - - - . - - -
1 Davis Besse Nuclea Power Stanon 1991 Annual Environmental Operating Report APPENDIX C - Data Reporting l Conventions ! I 4 ! e l L C-1 l 1. i-
Data Reporting Conventions 1.0. All activities. except grus5 alpha and gross beta, are decay correcteo to collection time or the end of the collection period. 2.0. Single Measurements Each single measurement is reported as follows: xts where x = value of the measurement; 5 = 2a counting uncerta4nty (corresponding to the 95% confidence level). In cases where the activity is found to be below the lower limit of detection L it is reported as
<L where L = is the lower limit of detection based on 4.660 uncertainty for a background sample.
3.0. Duplicate Analyses 3.1. Individual results: x1 i 51 x2 2 52 Reported result: xis
~
where x = (1/2) (x1 + x2) 2 s = (1/2) 5 3l 3.2. Individus) results: <t1
<l2 .
Reoorted result: <L where L = lower of L1 and L2 3.3. Individual results: xt5
<L Reported result: x1 5 if x > Li otherwise C -2
4.0. ComDutation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average I and standard deviation (s) of a set of n numbers x1, x2. - In are defined as follows: x = f Ix 3, I(x-Il2 n.1 4.2 Values below the highest lower 1imit of detection are not included in the average. t 4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLO is reported. 4.4 If all but or, of the values are less than the highest LLD, the single value ., and associatea two sigma error is reported. 4.5. In rounding off, the following rules are follored: 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example,11.443 is rounded off to 11.44. 4.5.2 If the figure following those to be retained is greater than 5, the figure is dropped, and the last retained figure is raised by 1. As an example,11.446 is rounded off to 11.45, 4.5.3. If the figure following those to be retained is 5, and if there are no figures other than Zeros beyond the five, the ' figure 5 is dropped, and the last-place figure retained is incre . sed by one if it is an odd r. umber or it is kept unchanged if an even number. As an example, 11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42. C-3 1
_ . - = . . - . .. . I Davis Besse Nuclear Power Station 1991 Annut! Environmental Operating Report l APPENDIX D - Maximum Permissible i Concentrations of Radioactivity in Air i and Water Above Natural Background in Unrestricted Areas i E 4 r D1 _ . . _ . . _ - _ . . _ . _ _ _ , , . .-,_a., . _ . . - - . . ., . _s
Table 0-1 Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.4 Water Air Strontium-89 3,000 pct /1 3 pC1/m3 Gross alpha 300 pC1/1 pCi/m3 Strontium-90 Gross beta 100 Cesium-137 20,000 pCl/l
-0.14 pCl/m3 Iodine-131b 20,000 pC1/1 Barium-140 300 pC1/1 Iodine-131 Potassium-40C 3,000 pC1/1 Gross alpha 30 pCi/1 100 pCi/1 Gross beta 3 x 106 pCi/1 Tritium _-
" Taken from Code of Federal Regulations Title 10. Part 20. Table 11 and Concentrations may be averaged over a period not greater priate f ootnotes.
than one year. b From 10 CFR 20 but adjusted by a f actor of 700 to reduce the dose r from the. air-grass-cow-milk-child pathway, c A natural . radionuclide. D-2
- - - . . - - - . _ . . _ _ _ _ ~~~----,--,n.,_ , _ _ _ _
I DmpBesse Nuclear Power Station 1991 Annual Envirmmental Operating Reton Appendix E - REMP Sampling Summary E1 l
.1
Table E-1 Environmental Radiological Monitoring Program Sirmmary bettet Pts. SU-J46 Name of fac Ul'.y D47ts-Besse Mus tear Pow? $tation krport6ng Perewd January - Dec ewor - t ve l tocation of Iacility Ottoms. Chio (County, State) toptrul Inditatur totation wth Heyhest t oc at t oeis Me r e t tocattens Aanval twen __ Sample Type and Hean (3 P Pe n (I F Ine-rowtone lhecer of Mean (F)( , Eaenjet E d.e9e-( kewi t se lype tg gb ganye c locatson* (Units) Analyses a 0.022 t zbo/ite) o 0.021 (312/JII) 7-12 Teleen teater C.023 (52/52) At rt> erne 68 620 0.005 (0.0014-0.042) (0.001-0.044) 10.006-0.041) Treatment Plant l Particulates 23.5 mi n.w (ptt/m3) .
. qtu O
$r-89 40 0.0013 ettD -
l - <t t U U
$r-90 40 0.0006 <tto -
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o i l l t Table E-1 Envirtmmental Raliological Monitoing Program Summary (continued) Dmitet fau . 50-34t> Mme of f.ctlety Davis-Besse hc lear Power 5tation _ Peporting Perted January - tw eed,e r 19,8 tocation of f actitty Ottawa Ohio (County, State) location with Magt.est (entrul Ind ic ator t o(at nun kwa er et l locations k val Mean hon- ruut ine Sample Type and Hren (T~jr- he.* (F)( { Type hunber of Mean (f)f g,n9,( g m,, ( besults' T Analyses a Ltob Range C te(attend (Units)
- <it u o Ground biater 04 (55) 15 0.8 <tto -
3.1 (4/4) 2.1 (2/l) 0 Ca (DS) 15 2.3 3.0 (a/8) 1-54,far , (2.3 2.3) (2.4-3.3) 4.8 at *A (2.4 3.3) I 2.4 (s/s) o 15 2.3 3.0 (8/8) 1-54,feru 3.1 (4/4) GB (IR) 4.s s.1 su (2.4 3.3) (2.9-2.a) (2.4-3.3)
- *ttb u H-3 15 330 4t0
- .ti o o Sr-89 15 1.5 4tD o.,(g/gj ,, t o o 0.9 0.9 (1/3) 1-y, 5ano seash 5r-se 15 0.9 mi ftJ
[T1 C5 15 d, o
- *ttu C5-137 10.0 410 -
Edth; Meat G5 4 (FCl/9 wet) I-191, Fars 2.11 ( t/I) 1.94 ttft) o E-40 0.1 2.03 (3/3) (1.41-2.71) 1.1 se w
- 'L t u O Cs-131 0.029 rit 0 -
- t.O u 6 0.006 <t LD Frwit5 and Sr-89 l 0.005 (1/3) U.uit (1/ 3) 0 Vegetables 0.004 (1/3) 1-173, I t relands (pCf/g wet) $r-90 6 0.001 wnnery $anceshy 20.0 en LE i qsu ,O 1-131 6 0.033 't tD -
e
'- - . i
Table E-l Environmental Radiological Monisoing Program Summary (continued) hae of Factitty Davis-Besse hv(lear Power station Dottet 20 % 346 Location of f acility ettawa. Ohio Reporting Period January - Unend,er l's91 LL*wnty State) Indit ator Lo(etion with Highest Cont rol Locations Annual sacan to(ations enumtrer of Sample Type and hun-rvutone Type Number of Mean (F)C Mean (FP Mean (F )( Analysesa it Db pg et Locatlend 3.,9,C g, pc 8ewlts' (Dnits) _ _ _ _ _ _ - _ , _. F ruits and G5 6 Wegetables o (pCI/g met) K-40 0.50 2.09 (3/3) f-8. f a m 2.59 (2/2) 1.68 ( 3/3) (continued) (0.91-4.21) 2.7 at u"4 (0.91-4.21) (1.06-2.20) 4LD - "Lt 0 0 h 95 0.022 - 4LD - <t t 0 0 le-95 0.032 - 4tD - "L L D o Cs-131 0.018 - 0.026 4tD - - 'I t u 0 Ce-141 4tD - < t t is u Ce-144 0.11 - 9 A 0.009 4LD - - <t : 0 o Broad Leaf $r-89 16 Vegetation et t u o (pCl/g wet) $r-90 16 0.004 0.005 (5/13) T-8, f em 0.005 (4/1) (0.004-0.005) 2.1 et W5W ( 0.004-U .00*2 ) 4LD -
- t 10 0 I-131 16 0.047 -
G5 16 1-25,fa m o.si (6/6) 1.79 ( 3/3) u t-40 0.1 5.30 (13/13) (3.13-8.91) 3.7 at 5 (4.09-8.91) ( I .51-2.0b)
- 'tt u c te,-95 0.036 *LLO -
<t t D 0 fr-95 0.052 <tLD - -
4LD - <t t o o Cs-131 0.030 -
<t t 0 0 Le-141 0.049 < tid - -
0.14 4t0 - - *tt D 9 Ce-144 , L w
- - - ____m
Table E-1 Envisunments! Radiological Monitoing Program Summary (continued) name of f acility Davis-Besse huclear Power Station L% ket ha. 50-346 to(stion of facility Ott awa. Obie Reporting Perted January - Deceea,er 1991 (County, State)
! Indicator to(st$on with Itighest (ent rol Sample Type and Localicas Annual Mean
- wattons hutaw r of i Type hunter of 64ean(f)C Mean {f p ^ tan (f)( hun-evutsee 4 (Units) Analyset 8 L10 l* Ranget location 8 Ranget konge l Rewlts' t
Ins 65 2 (FCl/g wet) E-40 0.01 1.01 (1/l) T-34, Of f stte 1.33 (1/3) 1.33 (LLD) 0
- rov 6ag locatten -
It>-95 0.G35 <tLD - - *ttD 0 2 r-95 0.047 'LLD - - <tt 0 0 Bu-103 0.023 <t L D - - <tt 0 0 Au-106 0.16 (LLD - - <t t u o i i (s-131 0.014 <t LD - - *tt b u Ce-141 0.039 <LL D - - "tiu o 0.11 (LLD - - *ttu U M Ce-144 i
+
Artaal - G5 10 Wilditie Fred Be- F 0.36 1.02 (2/') 1-198, Toussatut 1.20 (1/l) 0.10 (1/3) e (pct /g met) (0.64-1. 3) Creet , 4.0 e6 W'a - E-40 0.1 5.50 (1/7) t-a, farm 9.08 (3/3) 1.64 (3/3) 0 (2.03-12.70) 2.7 at W'A (2.03-12.10) (2.59-16.40) It>-95 0.050 <t t 0 - - <t t 0 0 Zr-95 0.082 <tLD - - *ttu o Re-103 0.043 *LL D - - "ttD 0 Re-106 0.2b *ttD - - "t L D D (s-137 0.036 <tt D - - attb 0 Ce-141 0.060 <t t 0 - - 'lt b o a Ce-144 0.23 *LL D - - ettD 0 , i e _ _ _ _ _ _ _ __-_M
Table E.1 Environmental Radiological Monitoing Program Summary (continued) P.mme of f acility Davis-Besse hutlear rower Station Docket k . $0-346 l LMatton of f acility Ottawa. Ohio Reporting Ferlud January - DetMer 1991 (County, State) Indic at or Location esith Highest Control Sample Type and l ocat ions Annual Mean tuettons Mer of Type pueber of Mean (F)C Mean (Fj' Mean (1)t sean- rout ine (Unit s ) Analysesa (g gb g,nge t LM ationd ganget p ,9,t Sesults' Soil L5 22 (pCi/g dry) Be-T G.56 0.98 (1/12) T-8, farm 0.98 (1/2) <t t D 0 2.7 mt W3 E-40 1.0 13.79 (12/12) i-8, Farm 22.92 (2/2) !!.33 (10/10) 0 (7.33-23.68) 2.7 at W ,W (22.15-23.68) (9.92-20.ls) 2 N95 0.086 <tL D - -
<l t b 0 tb-95 0.13 4tD - - <lt u o h-103 0.063 't L D - - <t t u u Ru.106 0.98 <l LD - <t t u 0 (T1 Cs-137 0.043 0.23 (9/12) i-9, Oak Harter 0.% (2/2) 0.40 (10/10) 0 b (0.t24-0.36) Substation (0.39-0.73) (0.15-0.73) 6.8 al SW Ce-141 0.12 4t0 - - <tt u u Ce-144 0.41 <tt D - - <tLD 0 I
l Treated Surfa(e (.8 (55) 12 0.9 4tD - - <t t o u kater (pCl/L) GB (05) 12 1.0 2.3 (36/h) T-144,t.reen Cove 2.5 (12/12) 2.2 (%/%) 0 (1.6-3.3) Cond., 0.9 et MW (1.7-3.3) (l.B-2.6) te (in) 12 1.'O 1.6 ( %/% ) T-144. 4.reen Cove 2.5 (12/12) 2.2 (%/%) 0 (1.6-3.3) Cend., 0.9 at nrad (1.7-3.3) (i.e-2.6) 1+-3 24 330 <tLD - - <tlD 0 5r-89 24 1.6 <t L D - - <110 0 5r-99 24 0.6 0.7 (2/12) 1-144 Green Cove 0.5 (t/4) 0.6 0 (0.6-0.8) Cond., 0.9 na MW (0.6-u(2/12)
.6)
G5 24 Cs-137 10.0 41D - - <t t u 0 e
v_ s . . i Table E.1 Environmenta) Radiological Monitoing Program Summary (ctmtinued) Isaket ha. w-346 A me of facility Davis-Besse Nuclear Po=er Station keporting Period Janua ry - Dec reter l991 Luetton of f acility Ottawa. Ohia (CJunty, State) tocation i.ith Highest (metrul ladicator totet nesis Naa.e r of loc at ions Annual Mean Sample Type and Nan (F)4 Nea (f Il km evuttee haber of Mean (f)( g,. g p.,,y e c Fesults' Type itDb p,q ,c taattend (Units) Analyses a ~_ 2.1 ( 2/ IN ) 0 ritD i-12, Toledo Water 2.7 (2/18) 156 0.9 ( 1.2-4 .2 ) Untreated GB (55) treatment Flant (1.2 4.21 Surf ace Water 11.25 mi 84 (pC1/L) U 1-3, site to.,ndary 3.0 (12/12) 2.3 { te/le) GB (05) 156 1.0 2.6 (18/F6) (I.9-3.6) ( 1.6- 4.1 ) (1.5-4.4) 1.4 ml 15E 2.4 (is//s) 0 2.6 (78/18) 1-12. Toledo W.ter 3.1 (12/l2) GB (TR) 156 1.0 ( 2.1 8.3) ( 1.6-U . J ) (1.5-4.4) Treatearnt Plant 11.25 at PW 333 (1/16 ) o 531 (5/J3) 1-130, take I rte 6b4 (1/6) n-3 156 330 - (331-884) 1.1 at E 5E
- 4tb o 108 2.3 < tt D Sr-89 1.1 (1/54) 0 4 1-158. take irte 1.4 (1/6)
Sm90 108 0.9 1.1 (3/54) (0.9-1.4) (0.9-1.2) 10.0 m his G5 156
- *ttD u (s-111 10 <ttD -
2./6 ( 3/ 3) 0 f-35, t ake t rie 2.16 13/3) Le 6 0.1 2.43 (3/3) (2.21-3.31) (2.21-3.31) ftsh (2.20-2.66) 710 at rad 6 us G 6 l 2.12 (3/3) 0 T-33, t ake Erie 2.42 ( 3/3) 8-40 0.1 2.42 (3/3) (1.%- 3.11) ( 1.81-2.% ) (1.90-3.11) 1.5 et NL
-- 'l10 0 0.035 <t t D -
CS-131 O
Table F 1 Environmental Radiological Monitoing Program Summary (continued) Mane of f acil tty Davis-Besse Nuclear Power Station Dmbet No. 50-346 Location cf Fattlfty Ottawa. Ohio Reporting Period January Det enter 1991 (County, State) Indicator LM ation alth Hlyhest Cont rol
$aeple Type and tuations Annect Mean twcatter.s he,e r of Type Mumber of Mean (f)C Mean (F)' Mean (F)' bi- mu t t ne (Units) Analyse $a tg gb RangeC to(ationd RangeC Wesults' Nan 9et Shoreline G5 15 5edteents (pCi/g dry) K-40 0.1 12.91 (9/9) f-138,take Erie 15.46 (2/2) 12.01 (6/6) 0 (9.57-17.80) 11.0 ml * (13.10-17.82) (9.10-11.82)
Cs-131 0.0ti2 0.14 (3/9) T-138, t ake E rie 0.52 (2/2) 0.52 (2/6) 0 (0.11-0.20) 11.0 mi * (0.41-0.51) (0.41-0.51)
* (a a gross beta. G5 = 9amma scan, 55 = suspended sol 6ds b5 = dissolved solids. Ik = total ersidue.
b ttD = nominal lower limit of detection 1:ssed on 4.66 Sigma (ocntin3 errer f or bachgesmnd senple. C Mean based upon dete(table measuresents only. Fra(tton of detectable acaswrements at specif ted locations is inde(ated an parenneses (F). d tocations are specified by station code (Table 4.1) .nd distance (elles) and dire (tlon relative to reactor site.
*I Mon-reuttne results are those which eateed ten times the ce9 trol station value.
f[I One result (<0.1 pct /l) was escluded in the determination of $r-90 in ellk. the elevated LLD resulted fri,ms low c a r r t e r ret uve ry , oo 9 One result (<l.40 pct $r-90/g Ca) was excluded in the determinatica of it0 of $r-90/Ca. the elevated tto resultw f rse h avn Ltc for Sr-90.
- v
- p
- _ _ . _ - _ - -_.)
i;.. ..., I : l l ATTACHMENT 1 l to the ) l ANNUAL ENVIRONMENTAL OPERATING REPORT: l Radiological Environmental Monitoring Program Sample Analys s Results for DAVIS-BESSE NUCLEAR POWER STATION January 1,1991 to December 31,1991 Prepared by: Radiological Environmental Davis-Besse Nuclear Power Station Toledo Edison Company Toledo, Ohio April 1992 i !~ .l 1
Table of. contents Description Page No. List of Tables 11 Introduction 1 Data Tables 2 Appendix A-1 l' i 1 l.
.f
. ~ . -- . . . . - . . - - . . . . . - . . - - .. . .- - .. ..
l l List of Tables i
' Table No.
Description Page No. 1 Airborne parciculates and iodine 2 collected at Location T-1, analyses for gross beta and iodine-131.
- 2. ' Airborne particulates and iodine 3 collected at Location T-2, analyses for gross beta and iodine-131.
3 , borne particulates and . iodine 4
';iected at Location f.3, analyses for gross beta and iodine-131.
4 Airborne particulates and io '..e 5 collected at Location T-4 talyses for gross beta and iodine-131. S- Airborne'particulates aad iodine 6 collected at Location T-7, analyses for gross beta and iodi..-131. 6 Airborne particulates and iodine 7 collected at Location T-8, analyses for gross beta and iodine-131. 7 Airb?tne particulates and iodine 8 coliected at Location T-9. anelyses for gross beta and iodine-131, 8 Airborne particulates and iodine 9 collected at Location T-11, analyses for gross beta and iodine-131, 9 Airborne particulates and iodine 10 collected at-Location =T-12, analyses forEgross beta and iodine-131, 10 Airborne particulates and iodine 11 collected at Location.T-27, analyses for: gross beta and iodine-131. . 11 Airborne particulates,-gross beta 12 analyses, monthly averages, minima, and maxima, 1991. l l-ii - l-l.
l l l List of Tables'(continued)' Table No. Description Page-Xo. I 12 -Airborno particulates, quarterly 18 composites of all indicator and all control. locations, analyses for strontium and gamma-emitting isotopes, 1991. 13 Area monitors (TLD), quarterly, 1991, 22 14 Area monitors (TLD), annually, 1991. 26 15 Milk samples, analyses for Sr-89, 29 - vr-90, I-131, and gamma-emitting isotopes. Collection: Semimenthly, May through October, monthly otherwise. r 16 Milk samples, analyses for calcium, 31 stable potassium, and ratios of pCi St-90/g Ca.and pCi- Cs-137/9 K. Collection: Semimor.thly, May through , October, monthly otherwise. , 17 Groundwater samples, analyses for 33 gross beta, Sr-89, Sr-90 and gamma-emitting isotopes. Collection: Quarterly-11 8 Domestic meat samples, analysis for 36 gamma-emitting isotopes. Collection: Annually E19 Wildlife meat samples, analysis for 37 gamma-emitting isotopes. Collection: Annually 20 Broad leaf vegetation, analyses for 38
-strontium-89, strontium-90, I-131, and other gamma-emitting isotoper.
Collection: Monthly in season. 21 Fruit samples, analyses for strontium-89, 40 , strontium-90, I-131, gamma-emitting isotopes. Collection:-Monthly in
-seasoa.
111 p l-
1 List of Tables'(continued) Table No. Desctiption Page No. 22 Animal-wildlife feed samples, analysis 41 for gamma-emitting isotopes. , Collection: Annually. 23 Soil samples, analysis for gamma- 43 I emitting isotopes. 24 Treated c'irface water' samples,-monthly 45 composites of weekly samples, analysis for. gross beta, 1991. 25 Treated surface water' samples, monthly El composites of weekly samples, analyses Q for gross beta, tritium, gamma-emitting isotopes, strontium-89 and strontium-90, 1991. , 26 Treated surface water samples, ) quarterly composites of weekly samples, analyses for tritium, strontium and gamma-emitting isotopes, 1991...
- 27. Untreated surface water samples, monthly 55 composites of-weekly samples, analysis for. gross beta, tritium, and gamma-emitting isotopes, 1991.
28 Untreated surface water samples, monthly 61 composites of weekly samples, analyses'for gross beta, tritium, strontium, and gamma-emitting isotopes 1991. 29 Untreated surface water samples, 63 quarterly composites of weekly samples, analysis for strontium, 1991. iv
i List of Tables (continued) Table No. Description _ _ _ Page No. 30 Untreated surface lake water samples, 65 monthly composites of weekly grab samples, analysis for gross beta, tritium, strontium-89, strontium-90 and gamma-emitting isotopes, collected June through October, 1991, 31 Fish samples, analyses for gross beta 69 and gamma-emitting isotopes. Collection: Semiannually.
-32 Shoreline sediment samples, analysis 70 for gamma-emitting isotopes.
Collection: Semiannually. 33 Egg samples, analysis for gamma-emitting 72 isotopes. Collection: Annually l l Y I= L !~ l
k Introduction Attachment ~1-to'the Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Report.(AEOR) ir4cludes the results of analysis of all radiological environmental radiation measurements taken es part of the 1991 Radiological Environmental Monitoring Program (REMP),-The summaries provided in Appendix ?. and thoughout the text of the 1991 AEOR are based on the data presented in the following table. Data tabulation and sample analyses results were provided by-Teledyne Isotopes Midwest Laboratory (TIML) in the TIML annual report to Toledo Edison (Part II, Feb 1992). I 1 1
Table 1. Airborne particulates and iodine collected at Location T-1, analyses for gross beta and iodine-131,a Oate Volume Gross "ata Date Volume Gross Beta Collected (m3) (pCi/m)) Coll ected (m3) (pC1/m3) 01-07-91 304 0.02810.003 07-08-91 288 0.01720.003 01-14-91 23 8 0.02520.003 07-15-91 27 4 0.01420.003 01-21-91 297 0.03220.004 07-22-91 30 1 0.03420.004 01-28-91 30 5 0.021 0.003 07-29-91 28 0 0.01420.003 02-04-91 29 8 0.02620.003 08-05-91 28 2 0.01620.003 02-11-91 299 0.02920.004 08-12-91 292 0.01620.003 02-18-91 297 0.01520.003 08-19-91 30 5 0.01320.003 02-25-91 30 9 0.021 0.003 08-26-91 28 5 0.01420.003 03-04-91 299 0.02020.003 09-02-91 284 0.02210.002 03-11-91 281 0.02520.004 09-09-91 28 3 0.020 0.003 03-18-91 27 5 0.015 0.003 09-16-91 279 0.02120.003 03-25-91 28 5 0.01620.004 09-23-91 20 2 0.02720.003 04-01-91 283 0.016 0.003 09-30-91 23 0 0.012!0.002 1st Qtr. mean 2 s.d. 0.02220.006 3rd Qtr. mean s.d. 0.01820.006 04-08-91 285 0.02820.004 10-07-91 255 0.029!0.004 04-15-91 27 7 0.020 0.003 10-14-91 287 0.02020.003 04-22-91 27 8 0.008 20.003 10-21-91 287 0.01920.003 04-29-91 27 6 0.02420.003 10-28-91 284 0.02210.002 05-06-91 204 0.01620.004 11-04-91 31 3 0.025!0.003 05-13-91 28 3 0.01620.003 11-11-91 294 0.02410.003 05-20-91 27 9 0.01410.003 11-18-91 27 0 0.03520.003 05-27-91 285 0.01610.002 11-25-91 281 0.02510.004 06-03-91 282 0.02110.003 12-02-91 28 5 0.03020.004 06-10-91 284 0.00920.003 12-09-91 28 7 0.02210.004 06-17-91 282 0.01820.003 12-16-91 287 0.03020.004 06-24-91 28 5 - 0.02110.003 12-23-91 284 0.02120.004 07-01-91 285 0.02010.003 12-30-91 28 5 0.02410.004 2nd Qtr. mean s.d.- 0.018 0.006 4th Qtr. mean 2 s.d. 0.02520.005 a Iodine-131 concentrations are <0.07 pC1/m3 unless noted otherwise in Appenr.x C. 2 t
.~ . - - Tabl e 2. Af rborne particulates and iodine collected. at Location T-2, analyses for 9ross beta and iodine-131.a D ate Vol ume Gross Beta Date Vol ume Gross Beta Collected (m3) (pC1/m3) Collected (m3) (pCi/m3) 01-07-91 2 90 0.032 0.004 07-08-91 2 99 0.02010.003 01-14-91 289 0.02210.003 07-15-91 30 0 0.01220.003 01-21-91 293 0.03020.004 07-22-91 301 0.03020.004 01-28-91 291 0.022 0.003 07-29-91 29 8 0.01410.003 02-04-91 289 0.02610.003 08-05-91 302 0.018 0.003 02-11-91 28 8 0.032 0.004 08-12-91 29 6 0.01510.003 02-18-91 286 0.018!0.003 08-19-91 29 9 0.025 0.004 02-25-91 288 0.02020.003 08-26-91 30 5 0.02020.003 03-04-91 286 0.01910.003 09-02-91 29 9 0.026:0.003 03-11-91 28 9 0.02210.003 09-09-91 29 8 0.02310.003 03-18-91 28 5 0.01220.003 09-16-91 29 6 0.023:0,003 03-25-91 291 0.02220.004 09-23-91 287 0.016 0.002 04-01-91 291 0.01720.003 09-30-91 289 0.01210.002, 1st Qtr. mean z s.d. 0.023 0.006 3rd Qtr. mean i s.d. 0.02010.006 04-08-91 289 0.02220.004 10-07-91 300 0.02010.003 04-15-91 285 0.021i0.003 10-14-91 30 4 0.02320.003 04-22-91 291 0.01120.003 10-21-91 29 7 0.02120.003 04-29-91 295 0.02220.002 10-28-91 29 1 0.02510.002 05-06-91 297 0.01120.003 11-04-91 29 8 0.027 0.003 05-13-91 297 0.020 0.003 11-11-91 29 0 0.02610.004 05-20-91 298 0.015 0.003 11-18-91 288 0.04020.003 .
05-27-91 30 3 0.01620.002 11-25-91 29 3 0.028 0.004 06-03-91 266 0.00710.003 12-02-91 28 9 0.03120.004 06-10-91 299 0.010 0.003 12-09-91 283 0.022:0.004
^ 06-17-91 29 6 0.01610.003 12-16-91 29 3 0.031 0.004 06-24-91 291 0.018 0.003 12-23-91 28 5 0.01610.003 07-01-91 296 0.02120.003 12-30-91 28 9 0.02620.004 2nd Qtr. mean 2 s.d. 0.01620.005 4th Qtr. mean s.d. 0.02610.006 a Iodine-131 concentrations are <0.07 pCi/m3 unless noted otherwise in Appendix C.
3
u ., - - _ __ _ . _ _ . _ _._._ - . - _ __ _ _ _ _ _ _ . Table 3. Airborne particulates and iodire collected at . Location T-3, analyses for gross beta and iodine-131.a 1 Date Volume Gross Beta Date -Volume Gross Beta i Collected (m3) (pCi/m3) Collected - (m3) (pCi/m3)- 01-07-911 287- 0.03220.004 07-08-91 2 85 0.023 0.004
~
01-14-91 2 84 0.02410.003 07-15-91 27 8 0.01410.003 01-21-91 293 0.03220.004 07-22-91 28 5 0.03220.004 01-28-91 282 .0.02220.003- 07-29 28 3 0.01610.003-02-04 298 0.02820.003 08-05-91 28 5 0.01720.003 02-11-91 28 8 0.03220.004 '08-12-91 29 2 - 0.01720.003 02-18-91 274 0.01820.003 08-19-91 29 2 0.02310.003 ' 02-25-91 279 0.02420.003 08-26-91 29 0 0.018 0.003 03-04-91 274 0.024 0.003 09-02-91 291 0.025 0.003 03-11-91 27 9 '0.025 0.004 09-09-91 284 0.01910.003 18-91 27 1 0.01310.003 09-16-91 293 0.025 0.004' 25-91 282 -0.01910.004 '09-23 29 2 0.01920.002 04-01-91L 26 5 0.018 0.004 30-91 293 0.01010.002 1st 'Qtr . mean' 2 s.d. -0.02420.006 3rd Qtr. mean i s.d. 0.02010;006 i 04-08-91 282 0.02520.004 10-07-91 '293 0.02320.003. 04-15 27 8 - -0.01820.003 10-14-91 287 0.02410.004 04-22-91 .273 '0.01010.003- 10-21 293- 0.01910.003 04-29-91 275 0.019 0.002' 10-28-91 28 0 0.01620.002 05-06-91 284 .0.01010.003 11-04-91 - 30 5 0.02410.003-05-13-91 -2841 0.019 0.003- 11-11-91 29 2- 0.02220.003
;05-20-91 271 0.01520.003 11-18-91 29 6 0.03720.003 05-27-91-. 30 7 : 0.01420.002 _11-25 297 0.026 0.003
'06-03-91 27 4 - '0.00610.002' 12-02-91 294 0.02620.003 06-10-91; 27 7 ' i0.00920.003 12-09-91 29 4 0.02010.003-06-17 278 0.01120.003 12-16-91 29 5_ 0.02810;004 06-24-91 280: 0.02010.003- 12-23-91 29 7 . 0.016 0.003 07-01 307- 0.02120.003 12-30-91 29 6 0.02110.003
. 2nd ;Qtr. mean s .d .; 0.01510.006- 4th Qtr. mean i s.d.- 0.02310.006 a : Iodine-131 concentrations are <0.07 pC1/m3 unless noted otherwise in Appendix C.-
4
Table 4. Airborne particulates and iodine collected at Location T-4, analyses for gross beta and iodine-131.a Date Vol ume Gross Beta Date Volume Gross Beta Collected (m3) (pCi/m3) Collected (m3) (pC1/m3) 01-07-91 2 94 0.03120.004 07-08-91 267 0.02220.004 01-14-91 28 5 0.025 0.003 07-15-91 273 0.01420.003 01-21-91 298 0.03620.004 07-22-91 272 0.03420.004 01-28-91 284 0.024 0.004 07-29-91 26 9 0.014 0.003 02-04-91 292 0.02920.004 08-05-91 277 0.01620.003 02-11-91 27 7 0.02920.004 08-12-91 26 5 0.01620.003 02-18-91 270 0.01620.003 08-19-91 272 0.03120.004 02-25-91 292 0.02010.003 08-26-91 26 6 0.01820.003 03-04-91 282 0.021 0.003 09-02-91 26 9 0. 026 0.003 03-11-91 2 83 0.024 0.004 09-09-91 274 0.02620.004 03-18-9) 278 0.017 0.003 09-16-91 268 0.024 0.004 03-25-91 291 0.02120.004 09-23-91 27 0 0.01720.002 04-01-91 288 0.018 0.003 09-30-91 226 0.008:0.002 1st Qtr. mean 2 s.d.. 0.02420.006 3rd Qtr. mean 2 s.d. 0.0202r 007 04-08-91 27 9 0.02320.004 10-07-91 24 3 0.02220.004 04-15-91 27 7 0.02120.003 10-14-91 29 3 0.02120.003 04-22-91 - 28 6 0.006 0.003 10-21-91 243 0.01820.004 04-29-91 282 0.02120.002 10-28-91 29 3 0.025 0.002 05-06-91 236 0.01820.004 11-04-91 29 8 0.026 0.003 05-13 269- 0.020 0.003. 11-11 293 0.02620.003 05-20-91 270 0.019 0.003 11-18-91 288 0.038 0.003 05-27-91 27 8 0.01420.002 11-25-91 2 99 0.02820.004 06-03-91 272 0.01220.003 12-02-91 288 0.026 0.004 06-10-91 279 0.01220.002 12-09-91 28 5 0.02220.004 06-17-91 270' O.01620.003 12-16-91 29 6 0.03120.004 06-24-91 271 0.02020.003 12-23-91 2 86 0.02120.004 07-01-91 275 0.02020.003 12-30-91 292 0.02120.003 L 2nd Qtr. mean 2 s.d. 0.01720.005 4th Qtr. mean 2 s.d. 0.02520.005 l l - a Iodine-131 concentrations are <0.u/ pCi/m3 unless noted otherwise in ~ Appendix C. l l I l l 5 1
Table 5. Airborne particulates and iodine collected at Location T-7, analyses for 9ross beta and iodine-131.8 Date Vol ume Gross Beta Date Vr ume Grcss Beta Collected (m3) (pC1/m3) Collected (m3) (pCi/m3) 01-07-91 264 0.02720.004 07-08-91 308 0.02020.003 - 01-14-91 271 0.02510.004 07-15-91 29 6 0.01620.003 01-21-91 275 0.03120.004 07-22-91 29 8 0.03320.004 01-28-91 274 0.02410.004 07-29-91 29 8 0.01620.003 02-04-91 295 0.02520.003 08-05-91 29 8 0.019 0.003 02-11-91 275 0.02620.004 08-12-91 29 9 0.01620.003 02-18-91 268 0.01420.003 08-19-91 29 7 0.027 0.004 02-25-91 27 3 0.0211 J.003 08-26-91 30 8 0.018 0.003 03-04-91 274 0.02120.003 09-02-91 29 8 0.02520.002 03-11-91 273 0.02020.003 09-09-91 30 0 0.02720.004 03-18-91 270 0.019 0.003 09-16-91 29 7 0.03120.004 03-25-91 282 0.01920.004 09-23-91 29 0 0.01820.002 04-01-91 27 0 0.01820.004 09-30-91 29 8 0.012 0.002 1st Qtr. mean i s.d. 0.022 0.004 3rd Qtr. mean 2 s.d. 0.02120.006 04-08-91 269 0.02120.004 10-07-91 2 99 0.03020.004 04-15-91 260 0. 020 c0.004 10-14-91 29 8 0.02320.003 04-22-91 25 6 0.008 0.003- 10-21-91 29 8 0.01920.003 04-29-91 283 0.02020.002 10-28-91 29 9 0.030!0.003
~ .05-06-91 276 0.00820.003 11-04-91 29 8 0.029 0.004 13-91 272 0.01820.003 11-11-91 297 0.02320.003 05-20-91 277 0.01720.003 11-18-91 298 0.04120.003 05-27-91 277 0.016 0.002 11-25-91 298 0.03210.004 06-03-91 26 9 0.01520.003 12-02-91 300 0.02820.004 06-10-91 278 0.00920.003 12-09-91 29 6 0.02410.004 06-17-91 270 0.01820.003 12-16-91 Z85 0.032 0.004 06-24-91 27 4 0.01710.003 12-23-91 2 83 0.02220.004 07-01-91 278 0.020 0.003 12-30-91 28 5 0.02420.004 2nd Qtr. mean 2 s.d. 0.01610.005 4th Qtr. mean s.d. 0.02720.006 a lodine-131 concentrations are <0.07 pCi/m3 unless noted otherwise in Appendix C.
6-
i i 1 Table 6. Airborne particulates and-iodine collected at Location T-8, analyses for gross beta and iodine-131.a D ate - Volume Gross Beta Date Volume Gross Beta Collected (m3) (pCi/m3) Collected (m3) (pCi/m3) 01-07-91 286 0.03320.004 07-08-91 279 0.02020.003 01-14-91 276 0.02220.003 07-15-91 287 0.01020.003 01-21-91 291 0.03420.004 07-22-91 284 0.03020.004 01-28-91 2S4 0.02720.004 07-29-91 28 9 0.015 0.003 02-04-91 30 5 0.02720.003 08-05-91 286 0.01620.003 : 02-11-91 311 0.028!0.003 08-12-91 28 5 0.01420.003 1 02-18-91 26 0 0.01820.003 08-19-91 283 0.022 0.004 02-25-91 286 0.02220.003 08-26-91 29 8 0.02120.003 03-04-91 251 0.023 0.004 09-02-91 29 2 0.02420.002 03-11-91 277 0.026 0.004 09-09-91 287 0.024 20.004 03-18-91 273 0.01210.003 09-16-91 291 0.02420.003 03-25-91 2/0 0.018 0.004 09-23-91 288 0.01920.002 04-01-91 261 0.020 0.003 09-30-91 296 0.013 0.002 1st Qtr. mean 2 s.d. 0.024 0.006 3rd Qtr. mean i s.d. 0.01920.006 04-08-91 27 2 0.034 0.004 10-07-91 29 2 0.013 0.003 04-15-91 256 0.01920.004 10-14-91 29 5 0.025 0.003 04-22-91 282 0.00520.003 10-21-91 297 0.02020.003 . 04-29-91 28 9 0.02420.002 10-28-91 296 0.024 0.002 00-06-91 27 2 0.01120.003 11-04-91 30 0 0.023 0.003 05-13-91 28 8 0.020 0.003 11-11-91 2 92 0.02220.003 E0-91 27 0 0.017 0.003 11-18-91 2 94 0.040 0.003 05-27-91 26 6 0.016 0.002 11-25-91 2 98 0.025!0.003 06-03-91 289 0.015 0.003 12-02-91 300 0.02620.003 06-10-91 284 0.01020.003 12-09-91 29 2 0.02220.004 06-17-91 28 5 0.018 0.003 12-16-91 302 0.02720.004 06-24-91 283 0.01820.003 12-23-91 29 3 0.01620.003 07-01-91 281 0.01720.003 12-30-91 289 0.02120.003 2nd Qtr. mean s.d. 0.01720.007 4th Qtr. mean 2 s.d. 0.023 0.006 a Iodine-131 concentrations are <0.07 pCi/m3 unless noted otherwise in Appendix C. 7
Table 7. Airborne particulates and iodine collected at Location T-9, analyses for gross beta and iodine-131.a Date Volume Gross 8cta Date Volume Gross Beta Collected (m3) (pCi/m3) Coll ect ed (m3) (pCi/m3) 01-07-91 292 0.028 0.004 07-08-91 294 0.02420.003 01-14-91 29 4 0.02420.003 07-15-91 297 0.01720.003 01-21-91 292 0.03420.004 07-22-91 234 0.02320.004 01-28-91 295 0.02210.003 07-29-91 29 4 0.01520.003 02-04 01 28 9 0.02620.003 08-05-91 29 9 0.01920.003 02-11-91 2 99 0.03120.004 08-12-91 29 6 0.019 0.003 02-18-91 292 0.01410.003 08-19-91 29 0 0.025!0.004 02-25-91 294 0.019 0.003 08-26-91 29 5 0.02020.003 03-04-91 28 8 0.02220.003 09-02-91 29 5 0.025 0.003 03-11-91 29 1 0.023 0.003 09-09-91 29 2 0.02820.004 03-18-91 - 28 7 0.015 0.003 09-16-91 29 2 0.02720.004 03-25-91 29 9 0.01820.004 09-23-91 29 4 0.02110.002 04-01-91 286 0.02020.003 09-30-91 29 9 0.01220.002 1st Qtr. mean 2 s.d. 0.02320.006 3rd Qtr. mean 2 s.d. 0.02120.005 04-08-91 294 0.02420.004 10-07-91 301 0.02620.003 04-15-91 275 0.02010.003 10-14-91 29 9 0.02320.003 04-22-91 28 6 0.004 0.003 10-21-91 28 0 0.02120.003 04-29-91 290 0.02010.002 10-28-91 276b 0.02820.003 05-06-91 290 0.011 0.003 11-04-91 285 0.02720.004 05-13-91 295 0. 017 t0.003 11-11-91 284 0.02320.003 05-20-91 323 0,92020.003 11-18-91 289 0.039 0.003 05-27-91 29 7 0.01720.002 11-25-91 28? 0.03020.004 06-03-91 297 0.01720.003 12-02-91 27 1 0.03320.004 06-10-91 30 4 0.01120.003 12-09-91 275 0.02420.004 06-17-91 29 6 0.019 0.003 12-16-91 2 85 0.036 0.004 06-24-91 301 0.018 0.003 12-23-91 28 8 0.02110.004 07-01-91 29 5 0.022 0.003 12-30-91 2B4 0.027 0.004 2nd Qtr. mean s.d. 0.01720.005 4th Qtr. mean 2 s.d. 0.02320.006 I-a Iodine-131 concentrations are <0.07 pCi/m3 unless noted otherwise in Appendix C. b Corrected calibration curve. l l 8.
Table 8. Airborne particulates and iodine collected at location T-11, analyses for gross beta and iodine-131.a Date Vol ume Gross Beta Date Volume Gross Beta Collected (m3) (pCi/m3) Collected (m3) {pci/m3) 01-07-91 372 0.023 0.003 07-08-91 283 0.023:0.004 01-14-91 34 6 0.01820.003 07-15-91 282 0.01520.003 01-21-91 30 4 0.030 0.004 07-22-91 277 0.03020.004 01-28-91 295 0.02120.003 07-29-91 26 5 0.01410.003 02-04-91 30 0 0.03120.004 08-05-91 282 0.01720.003 02-11-9?. 30 5 0.03220.004 08-12-91 28 0 0.01510.003 02-?8-91 273 0.014. 0.003 08-19-91 272 0.02610.004 02-25-91 28 3 0.018 0.003 08-26-91 305 0. 019 t0.003 03-04-91 278 0.018 0.003 09-02-91 273 0.02320.003 03-11-91 285 0.02520.004 09-09-91 294 0.025t0.004 03-18-91 279 0.01320.003 09-16-91 271 0.02620.004 03-25-91 287 0.018 0.004 09-23-91 276 0.02620.003 04-01-91 282 0.018 0.003 09-30-91 278 0.012!0.002 1st Qtr. mean t s.d. 0.021:0.006 3rd Qtr. mean t s.d. 0.02120.006 04-08-91 285 0.022 0.004 10-07-91 28 5 0.02620.004 04-15 28 5 0.019 0.003 10-14-91 2/2 0.024 0.004 04-22-91 277- 0.010 0.003 10-21-91 277 0.020 0.003 04-29-91 28 0 0.02120.002 10-28-91 275 0.02810.003 05-06 283 0.00910.003 11-04-91 269 0.027 0.004 05-13-91 283 0.018t0.003 11-11-91 294 0.026 0.003 05-20-91 27 9 0.016 0.003 11-18-91 273 0.04410.003 05-27-91 283 0.01720.002 11-25-91 316 0.01820.003 06-03-91 285 0.017t0.003 12-03-91 304 0.024 0.003 06-10-91 28 7 0.01020.003 12-09-91 237 0.026 0.004 06-17-91 280 0.01820.003 12-16-91 279 0.03720.004 06-24-91 27 7 ' O.02320.004 12-23-91 27 3 0.021 0.004 07-01-91. 27 - 0.019 0.003 12-30-91 -278 C.026 0.004 2nd ' Qtr. mean 2 s.d. 0.01720.005 4th Qtr. mean i s.d. 0.02720.007 a lodine-131 concentrations are <0.07 pCi/m3 unless noted otherwise in Appendix C. 9
Table 9. Airborne particulates and iodine collected at Location T-12, analyses for gross beta and iodine-131.a C at e Volume Gross Beta Date Volume Gross Beta Collected (m3) (pCi/m3) Coll ected (m3) (pCi/m3) 01-37-91 2 96 0.03120.004 07-08-9) 280 0.02210.004 01-14 28 9 0.a?S 20.003 07-15-91 283 0.01610.003 01-21-91 295 0.03410.004 07-22-91 27 5 0.032 0.004 01-28-91 30 9 0.02220.003 07-29-91 288 0.01820.003 02-04-91 29 5 0.030 x0.004 08-05-91 284 0.01620.003 02-11-91 303 0.028 0.003 08-12-91 281 0.01820.003 02-18-91 30 0 0.017 0.003 08-19-19 278 0.02420.004 02-25-91 313 0.022 0.003 08-26-91 27 6 0.022:0.003 03-04-91 322 0.02120.003 09-02-91 282 0.02520.003 03-11-91 311 0.02640.003 09-09-91 280 0.028 0.004 03-18-91 31 2 0.013 0.003 09-16-91 278 0.026 0.004 03-25-91 312 0.02010.004 09-23-91 278 0.021 0.h 2 04-01-91 29 4 0.017 0.003 09-30-91 282 0.01210 ^U2 1st Qtr. mean 2 s.d. 0.024 0.006 3rd Qtr. mean t s.d. 0.02220.006 04-08-91 30 6 0.02520.004 10-07-91 273 0.02710.004 04-15-91 30 2 0.02120.003 10-14-91 27 3 0.03420.004 04-22-91 300 0.00920.003 10-21-91 267 0.02220.004 04-29-91 299 0.02020.002 10-28-91 285 0.02310.002 05-06-91 302 0.011 0.003 11 -0 ^-91 282 0.02810.'04 05-13-91 29 5 0.017 0.003 11-11-91 276 0.02410.004 5-20-91 29 5 0.016 0.003 11 18-91 283 0.04210.003 d5-27-91 28 2 0.01710.002 11-25-91 2 86 0.027 0.004 06-03-91 28 4 0.023i0.003 12-02-91 28 0 0.02210.003 06-10-91 286 0.01320.003 12-09-91 27 4 0.02120.004 06-17-91 28 2 0.01820.003 12-16-91 279 0.03410.004 06-24-91 27 9 0.01910.003 12-23-91 27 9 0.021 0.004 07-01-91 28 0 0.02010.003 12-30-91 28 0 0.023!0.004 2nd Qtr. mean t s.d. 0.01810.005 4th Qtr mean s.d. 0.02720.006 a Iodine-131 concentrations are (0.07 pCi/m3 unless noted otherwise in Appendix C. 1 10 l
l Table 10. Airborne particulates and iodine collected at location T-27, analyses for gross beta and iodine-131.a Date Volume G.oss Beta 04te Volume Gross Beta Collected (m3) (pCi/m3) Collected (m3) (pCi/m3) 01-07-91 299 0.03210.004 07-08-91 287 0.020 0.003 01-14-91 29 1 0.025:0.003 07-15-91 28 8 0.016 t0.003 01-21-91 293 0.03310.004 07-22-91 99 4 0.032 0.004 01-28-91 29 6 0.024 0.003 07-29-91 ca7 0.016 0.003 02-04-91 29 4 0.02810.00/ 08-05-91 28 9 0.01610.003 02-11-91 28 3 0.030 0.004 08-12-91 28 6 0.01510.003 02-18-91 289 0.016 0.003 08-19-91 289 0.02220.003 02-25-91 296 0.01920.003 08-26-91 27 8 0.0?010.003 03-04-91 285 0.022i0.003 09-02-91 29 2 0.02f.20.003 03-11-91 2 90 0.02520.004 09-09-91 291 0.03020.004 03-18-91 277 0.01120.003 (9-16-91 28 8 0.02620.004 03-25-91 29 4 0.01810.004 ,8-23-91 29 0 0.01620.002 04-01-91 28 6 0.018 0.003 09-30-91 289 0.01520.002 1st Qtr. mean i s.d. 0.02310.007 3rd Qtr. mean t s.d. 0.02120.006 04-08-91 285 0.016 0.003 10-07-91 293 0.02520.003 04-15-91 289 0.019!0.003 10-14-91 289 0.02220.003 04-22-91 28 5 0.00720.003 10-21-91 289 0.02010.003 1 04-29-91 289 0.021 0.002 10-28-91 29 0 0.026 0.002 05-06-91 291 0.01220.003 11-04-91 29 1 0.03010.004 05-13-91 286 0.019 0.003 11-11-91 286 0.02420.063 05-20-91 28 8 0.01920.003 11-18-91 287 0.04120.003 05-27-91 28 8 0.015 0.002 11-25-91 291 0.03020.004 06-03-91 28 8 0.01410.003 12-03-91 326 0.02210.003 06-10-91 28 8 0.010 0.003 12-09-91 25 4 0.02920.004 06-17-91 28 6 0.019 0.003 12-16-91 292 0.037 +0.004 06-24-91 287 0.01810.003 12-23-91 28 8 0.02310.004 07-01-91 287 0.01920.003 12-30-91 28 7 0.025 0.004 2nd Qtr. mean 2 s.d. 0.01620.004 4th Qtr. mean s.d. 0.027!0.006 a Iodine-131 concentraticns are <0.07 pCi/m3 unless noted otherwise in Appendix C. , 11 l
w Table 11. Airborne particulates , gross beta analyses, monthly averages, minima, and maxima, 1991.a Number of Gross Beta Activity (pCi/m3) Location Sampl es3 Average Minimum IMximum Month January T-1 4 0.026 0.021 0.032 T-2 4 0.026 0.022 0.032 T-3 4 0.028 0.022 0.032 T-4 4 0.029 0.024 0.036 T-7 4 0.027 0.024 0.031 T -8 0.029 0.022 0.034 _4 All Indicators 24 0.028 0.021 0.036 T-9 4 0.027 0.022 0.034 T-11 4 0.023 0.018 0.030 T-12 9 0.028 0.022 0.034 _4; 0.028 0.024 0.033 T-27 All Controls 16 0.026 0.018 0.034
^
4 0.023 0.015 0.029 February T-1 0.032 T-2 4 0.024 0.018 T-3 4 0.026 0,018 0.032 T-4 4 0.024 0.016 0.029 4 0.022 0.014 0.026 T-7 T-8 0.024 0.018 0.028 _4 4 0.032 9 All Indicators 24 0.024 0.014 4 0.022 0.014 0.031 T-9 4 0.024 0.014 0.032 T-11 4 0.024 0.017 0.030 T-12 0.023 0.016 0.030 T-27 _4 0.023 0.014 0.032 All Controls 16 8 Unless specified otherwise, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. 12
~- .. . .. -
Table 11. Airborne particulates, gross beta analyses, monthly averages, minima, and maxima,1991a (continued) Number Gross beta activity (pC1/m3) of Samplesa Average Minimum Maximun Month- Location T-1 5 0.018 0.015 0.025 March T-2 5 0.018 0.012 0.022 T-3. 5 0.020 0.013 0.025 T-4 5 0.020 0.017 0.024 T-7 5 0.019 0.018 0.021 T-8 5 0.020_ 0.012 0.026 All Indicators 30 0.019 0.012 0.026 T-9 5 0.020 0.015 0.023 T-11 5 0.018 0.013 0.025 T-12 5 0.019 0. 013 0.026 i 0.019,_ 0.011 0.025
-T-?7- 5 All Contrels 20 0.019 0.011 0.026 0.020 0.008 0.028
! April T-1 4 0.022 T-2 4 0.019 0. 011 [ 0.010 0.025 T-3 4 0.018 L 0.006 0.023 l T-4 4 0.018 0.017 0.008 0.021 L T 4 4 0.020 0.005 0.034 l T-8 l - 0.019 0.005 0.034 j- All. Indicators 24 0.017 0.004 0.024 T-9 4 4 0.018 0.010 0.022 f T-11 0.019 0.009 0.025 T-12 4 ( 4 0.016 0.007 0.021 l: T-27 I 0.018 0.004' O.025 All Controls 16 a Unless specified otherwise, data for samples- collected on the first, second,
~
! -or third day of a month are grouped with data of the previous month. Numbers _in _ parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. 13
Table 11. Airborne particulates, gross beta analyses, monthly averages, minima, and maxima,19913 ( continued ) Number Gross beta activity (pCi/m3) Month Location of Sanplesa Average Minimwn Maximum May T-1 5 0.017 0.014 0.021 T-2 5 0.014 0. 007 0.020 T-3 5 0.013 0.006 0.019 T-4 5 0.017 0.01 2 0.020 T-7 5 0.015 0.008 0.018 T-8 5 0.016 0.011 0.020 All Indicators 30 0.015 0. 006 0.021 T-9 5 0. 01 6 0.011 0.020 T-11 5 0.017 0.009 0. 01 8 T-12 5 0.017 0.011 0.023 T-27 5 0.016 0.012 0.019 All Controls 20 0.016 0. 009 0.023 June T-1 4 0.017 0.009 0.021 T-2 4 0.016 0.010 0.021 T-3 4 0.015 0.009 0.021 T-4 4 0.017 0.012 0.020 T-7 4 0.016 0.009 0.020 T-8 4 0.016 0.010 0.018 All Indicators 24 0.016 0.009 0.021 T-9 4 0.018 0.011 0.022 T-11 4 0.018 0.010 0.023 T-12 4 0.018 0.013 0.020 T-27 4 0.016 0.010 ___ 0.019 All Contro'Is 16 0.018 0.010 0.023 8 Unless specified otherwise, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. 14
Table 11. Airborne particulates, gross beta analyses, monthly averages, minima, and maxima,1991a (continued) Nurber Gross beta activity (pCi/m3) Honth Location of Samplesa Average Minimum Maximum July T-1 4 0.020 0.014 0.034 T-2 4 0.019 0.012 0.030 T-3 4 0.021 0.014 0.032 T-4 4 0.021 0.014 0.034 T-7 4 0.020 0.016 0.033 T8 4 0.019 0.010 0.030 All Indicators 24 0.020 0.010 0.034 T-9 4 0.020 0.015 0.024 T-11 4 0.020 0.014 0.030 T-12 4 0.022 0.016 0.032 T-27 4 0.021 0.016 0.032 All Controls 16 0.021 0.014 0.032 August T-1 5 0.016 0.013 0.022 T-2 5 0.021 0.015 -0.026 T-3 5 0.020 0.017 0.025 T-4 5 0.01 8 0.016 0.031 T-7 5 0,021 0.016 0.027 T-8 5 0.019 0.014 0.024 All Indicators 30 0.019 0.013 0.031 T-9 5 0.022 0.019 0.026 T-11 5 0.020 0.01 5 0.020 T-12 5 0.021 0.016 -0.0' T-27 5 0.020 0.016 0.0 - All Controls 20 0.021 0.015 C.026 a Unless specified otherwise, data for samples collected on the first, second, or third day of a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. 15' I U"" _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
Table 11. Airborne particulates, gross beta analyses, monthly averages, minima, and maxima,1991a (continued)
+
Number Gross beta activity (pC1/m3)_ Month Location of Samplesa Average Minimum Pb41 mum September T-1 4 0.020 0.012 0.027 T-2 4 0.018 0.012 0.023 T-3 4 0.018 0.010 0.025 T-4 4 0.01 9 0.008 0.026 T-7 4 0.022 0.012 0.031 T-8 4 0.020 0.013 0.024 All Indicators 24 0.020 0. 008 0.031 T-9 4 0.022 0.012 0.028 T-11 4 0.022 0.012 0.026 T-12 4 0.022 0.012 0.028 T-2 7 4 0.022 0.015 0.030 All Controls 16 0.022 0.012 0.030 October T-1 4 0.022 0.01 9 0.029 T-2 4 0.022 0.020 0.025 T-3 4 0.020 0.016 0.024 T-4 4 0.022 0.018 0.025 T 4 0.026 0.019 0.030 T 4 0.020 0 013 0.025 All Indicators 24 0.022 0.013 0.030 . T-9 4 0.024 0.021 0.028 k T-11 4 0,024 0.020 0.028 T-12 4 0.026 0.022 0.034 l T-27 4 0.023 0.020 0.026 L All Controls 16 0.024- 0.020 0.034 i a Unless specified otherw se, data for sampies collected en the first, second, i or- third day of. a month are . grouped with data of the previous month. l Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. [ 16
Table 11. Airborne particulates, 9ross beta analyses, monthly averages, minima , and ' maxima , 19918 (continued' Number Gross beta activity (pCi/m3)
~
Month Location of Samplesa Average Minimum Maximum November T-1 5 0.028 0.024 0.035 T-2 5 0.030 0.026 0.040 T-3 5 0.027 0.022 0.037 T-4 0.029 0.026 0.038 5 T-7 5 0.031 0.023 0.041 T-8 5 0.027 0.022 0.040 All Indicators 30 0.029 0.022 0.041 T-9 5 0.030 0.023 0.039 T-11 5 0.028 0.018 0.044 T-12 5 0.029 0.022 0.042 T-27 5, _ 0.029 0.022 0.041 All -Control s 20 0.029 0.018 0.044 December T-1 4 0 . 024 0.021 0.030
-T-2 4 0.024 0.016 0.031 T-3 4 0.021 0.016 0.028 T-4 4 0.024 0.021 0.031 1 -7 4 0.026 0.022 0.032 T-8 4 0.022 0.016 0.027 All Indicators 24 0.024 0.016 0.032 T-9 4 0.027 0.021 0.036 T-11 4 0.028 0.021 0.037 T-12 4 0.025 0.021 0.034 T-27 4 0.028 0.023 0.037 All Controls 16 0.027 0.021 0.037 8
Unless specified otherwise, data for.amples collected on the first, second, or- third - day of. a month are grouped with data of the previous month. Numbers in parentheses indicate the number of samples with unreliable and less than value results which are excluded from the average. J 17
Table 12. Airborne particulates,- quarterly composites of all indicator and all control locations, analyses for strontium and gamma-emitting isotopes , 1991.
. m _. ,_
Sample Description and Actiyity (pCi/m3) January - Mare? Lab Code TAP-2525 TAP-2526 TAP-2528 TA P-2530 TAP-2532 Location T-1 T-2 T-3 T-4 T-7 3830 3756 3656 3714 3564 Volume (m3) Sr-89 <0.0004 <0.0005 <0.0004 <0.0004 <0.0004 Sr-90 <0.0004 <0. 0004 <0.0004 <0.0004 <0.0003 Be-7 0.058!0.013 0.066 0.011 0.04620.011 0.05820.012 0.05020.015 K-40 <0.026 <0.021 <0.019 <0.021 <0.0024 Nb-95 <0.0015 <0.0012 <0.0014 <0.0015 <0.0012 Zr-95 <0.0023 <0.0026 <0.0025 <0.0025 <0. 0028 Ru-103 < 0.0009 <0.0009 <0.0013 <0.0010 <0.0010 Ru-106 <0.010 <0.0056 <0.0096 <0.0091 <0.011 Cs-134 <0.0010 <0.0008 <0.0010 <0.0009 <0.0009 Cs-137 <0.0012 <0.0010 <0.0011 <0.0010 <0.0012 Ce-141 <0.0016 <0.0013 <0.0016 <0.0014 <0.0018 Ce-144 <0.0061 <0. 0055 <0.0066 <0.0055 (0.0052 Lab Code TAP-2533 TAP-2534 TAP-2535 TAP-2536 TAP-2537 Location T-8 T-9 (C) T-11 (C) T-12 (C) T-27 (C) 3651 3798 3889 3951 -3773 Volume (m3) Sr-89 <0.0003 <0.0003 <0.0003 <0.0004 <0.0003 Sr-90 <0.0003 <0.0003 <0.0003 <0.0003 <0.0003 Be-7 0.06310.010 0.05920.012 0.060 0.010 0.05410.013 0.06620.011 K-4 0 - < 0. 020 <0.023 <0. 01.7 <0.022 <0.019 Hb-95 <0.0010 <0.0014 <0. 0010 <0.0012 <0.0008
<0.0025 <0.0017 <0. 0026 - <0. 0014 Zr-95 <0.0022 Ru-103 <0.0009 <0.0008 <0. 0007 - <0.0008 (0.0008 Ru-106 <0.0052 <0.008 <0.0049 <0.0076 <0.0060 Cs-134 <0. 0008 <0. 0009 <0.0006 <0.0010 <0.0008
<0.0012 <0. 0007 <0.0012 <0.0008 Cs-137 <0.0008
<0.0008 <0.0016 <0.0007 <0.0014 <0.0009 Ce-141
<0.0026 <0.0054 <0.0024 <0.0058 <0.0025
-Ce-144 p
i 18 f
Table 12. Airborne particulates, quarterly composites of all inoicator and ali control locations, analyses for strontium and gamma-enitting isotopes,1991 (continued) Sample Description and Activity (DC1/m3) April - June Lab Code TAP 4645 TAP-2646 TAP-2647 TAP-2648 TAP-2649 Location T-1 T-2 T-3 T-4 T -7
-3585 3803 3670 3544 3539 Volume (m3)
Sr-89 <0.0004 <0.0004 <0.0003 <0.0005 <0.0005 S r-90 <0.0003 <0.0003 <0. 0002 <0.0004 <0.0004 Be-7 0.05620.016 0.05620.013 0.05420.014 0.05910.010 0.061 t0.011 X-40 <0.029 <0. 019 <0.022 <0.017 <0.022 Nb -95 <0.0017 <0.0013 <0.0017 <0.0016 <0.0022 Zr-95 <0.0029 <0. 0022 <0.0021 <0. 0018 <0.0028
<0.0007 <0.0013 <0.0007 <0,0013 Ru-103 <0.0013 Ru-106 <0.011 <0.0079 <0.0071 <0.0075 <0.0080 Cs-134 <0.0010 <0.0004 <0.0010 <0.0006 <0.0009 Cs-137 <0.0012 <0.0007 <0.0009 <0.0007 <0.0011 Ce-141 <0.0023 <0.0011 <0.0017 <0.0008 <0.001 L
<0. 0067 <0.0022 <0.0061- <0.0024 <0.00E Ce-144 Lab Code TAP-2650 TAP-2651 TAP-2652 TAP-2653 TAP-2654 Location T-6 T-9 (C ) T-11 (C) T-12 (C) T-27 (C) 3617 3617 3661 3792 3737 Vol ume -(m3)
<0.0004 <0.0004 <0.0003 <0.0004 <0.0004 Sr-89
<0.0003 <0.0003 <0.0002 <0.0003 <0.0003 Sr-90 Be-7 0.06120.011 0.061 0.008 0.05520.009 0.066 0.016 0.060 0.019
<0.019 <0. 012 <0.011 <0.027 <0.027 K -40
<0.0012 <0.0016 <0.0012 <0.0018 <0.0033 Hb -95
<0.0015 <0.0023 <0.0016 <0.0031 <0.0027 Zr-95 <0.0015 Ru-103 <0.0008 <0.0014 <0.0009 <0.0014
<0.0069 <0.010 <0.0066 <0.0095 <0.0096 Ru-106
<0.0006 <0.0009 <0.0008 <0.0008 <0.0010 Cs-134
<0.0011 <0.0009- <0.0013 <0.0011 Cs-137. <0.0009
<0.0024 <0.0011 <0.0022 <0.0027 Ce-141 <0.0010
<0.0065 <0.0032 <0.0065 <0.0066 Ce-144 <0.0023 19
- . . - - ~ . - - - - . - ~~ ..~ . , - . . - - - . . .. - ..
' Table 12. - Airborne particulates, quarterly composites of all indicator and-
.all control locations, analyses for strontium and gamma-emittin9 isotopes,1991 (continued) .
Senple Description and- Activity (pCi/m3) July - September Lab Code TAP-2763 TAP-2764 TAP-2765 TAP-2766 TAP-2767
~ Location. T T-2 T-3 T-4 T-7 >
Volume (m3) 3635 3869 3743 3468 3885 : Sr-89. <0.0006 <0.0006 <0.0005 (0.0006 <0.0009
'Sr-90. <0.0002 <0.0003 <0.0002 <0.0003 <0. 0004 Be-7 0.05720.013 0.06010.010 0.05110.014 9.05510.010 0.05010.012 K-40 <0.024 <0.016 <0.024 <0.016 <0.022 Nb-95: <0.0015. <0.0013 <0.0017 <0.0013 <0.0016 Zr-95 - <0.0023 - <0.0022 <0.0032 <0.0020 <0.0021 Ru-103 <0.0012 <0.0007 <0.0011 <0.0008 <0.0011
. Ru-106 <0.0097 <0.0066 <0.010 v .0072 (0.0093 LCs-134 <0.0008 <0.0008 <0.0011 <0.0006 <0.0009 Cs-137 <0.0013' <0.0008 <0.0012 <0.0008 <0. 0010 Ce-141- -<0.0016 <0.0008 <0.0014 <0.0009 <0.0014 Ce-144 <0.0060 <0.0027 <0.0052 <0.0031 <0.0048, Lab Code - TAP-2768 TAP-2769 ' TAP-2770 TAP-2771 TAP-2772-Location T-8 T-9 (C) T-11 (C) T-12 (C) .T-27(C) 3745 3771 3658- 3645 3748 Volume .(m3) Sr <0.0010 <0.0008 <0.0009 <0.0008 <0.0013 Sr ' <0.0004 <0. 0004 <0.0004 <0.0004 <0.0006 Be-7 0.05710.010 0.06110.012 .0.05610.011 0.05620.014 0.05410.012 K-40 -<0.015 <0.023- <0.015 <0.018 <0.021 Nb-95. '0.0012
< <0.0015 - <0.0013 - <0.0017 <0.0015 Zr-95: <0. 0016 . <0.0025 . <0.0023 <0.0026 <0.0022 Ru-103~ <0. 0008 . <0.0012 <0 . 0009 . <0.0010 <0.0009 Ru-106 <0.0063- <0.011 <0.0095 - <0.012 <0. 0064 -
-Cs-134_ <0.0005 <0.0011 <0. 0007 (0.0009 <0.0008 Cs-137 <0.0006 <0.0010 <0.0009 - <0 . 0014 - <0.0009 Ce-141 <0.0008 <0.0017. <0.0010 <0.0017 <0.0015 Ce-144 <0.0023 <0.0053 <0.0028 <0.0048 <0. 0050 I
i: 20
Table 12. Airborne particulates, quarterly composites of all indicator and all control locations, analyses for strontium and 9amma-emitting isotopes,1991 (continued) Sanple Description and Activity (pC1/m3) October - December Lab Code TAP-2890 TAP-2891 TAP-2892 TAP-2893 TAP-2894 Location T-1 T-2 T-3 T-4 T-7 3699 3800 3819 3693 3834 Volume (m3) Sr-89 <0.0004 <0.0004 <0.0005 <0.0004 <0.0004 Sr-90 (0.0004 <0.0004 <0.0005 <0.0003 <0.0004 Be-7 0.04710.008 0.050 0.012 0.04120.008 0.047 0.015 0.05420.015 K-40 <0.015 <0.029 <0.024 <0.028 <0.029 Nb-95 <0.0013 <0.0021 <0.0018 <0.0017 <0.0017 Zr-95 <0.0017 <0.0032 <0.0029 <0.0023 <0.0019 Ru-103 <0.0007 <0.0015 <0.0014 <0.0012 <0. 0012 Ru-106 <0.0060 <0.013 <0.013 <0.0099 <0.011 Cs-134 <0.0006 <0.0013 <0.0010 <0.0011 <0.0011 Cs-137 <0.0007 <0.0013 <0.0014 <0.0011 <0.0014 Ce-141 (0.0008 <0.0022 <0.0024 (0.0025 <0.0027 Ce-144 <0.0023 <0.0087 <0.0082 <0.0085 <0.0079 Lab Code TAP-2895 TAP-2896 TAP-2897 TAP-2898 TAP-2899 Location T-8 T-9 (C) T-11 (C) T-12 (C) T-27 (C) 3840 3701 3632 3617 3763 Volume (m3) Sr-89 <0.0004 <0.0004 <0.0005 <0.0004 <0.0004 Sr-90 <0.0004 <0.0003 <0.0004 <0.0004 <0.0004 Be-7 0.050 0.015 0.05110.016 0.04410.009 0.04820.008 0.04310.008 K-40 <0.027 <0.029 <0.011 <0.011 <0.013 Nb-95 <0.0020 <0.0016 <0.0014 <0.0012 <0.0012 Zr-95 <0.0026 <0. 0030 <0.0021 <0.0018 <0.0019 Ru-103 <0.0016 <0.0013 <0.0011 <0.0009 <0.0010 Ru-106 <0.014 <0.013 <0.0083 <0.0067 <0.0069 Cs-134 <0.0012 <0.0011 <0.0009 <0.0007 <0.0008 Cs-137 <0.0016 <0. 0014 <0.0010 <0.0009 <0.0008 Ce-141 <0.0026 <0.0024 <0.0020 <0.0012 <0.0015 Ce-144 <0.0081 <0.0080 <0.0058 <0.0034 <0.0046 21
Tabl e 13 . Area monitors (TLD), quarterly,1991. mR/91 days Location 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Indicator T-1 10.510.3 -11.120.4 11 .220.7 11.920.6 T-2 11 .920.4 10.920.2 12 .320.6 11.920.5 T-3 11 .9 0 .5 11.420.8 12.720.6 12.220.9 T-4 15.0 0.6 12.620.4 15.020.7 13.920.4 T-5 13.120.8 11.520.3 12.720.7 12 .2 0 .3
'T 10.420.6 11.020.5 11 .6 0 .6 11 .6 0.7 T-7 16.410.8. 16.120.7 15.920.7 16.820.6 T-8 21.010.8 17 .7 0.9 21.411.1 18.1 0.5 T-10 13 .8 0.6 13.120.5 13.9 0.8 13 .4 0 .7 T-38 11.8 0.3 13 .120.5 11.7t0.5 13.320.7 T-39 14.0 0.7 13.820.3 13.410.7 13.720.6 T-40 12.620.7 13 .220.6 13.710.6 14 .2:0.6 T-41 10.120.6 12.320.4 10.9 0.8 13.120.7 T-42 9.920.6 10.4:0.6- 9.910.5 11.320.4 T-43 14 .2 0.9 16 . 0 t0.7 16.220.8 16.6 0.7 .T-44 14.510.7 15.221.0 16.120.9 16.820.6 T-45 18.920.9 17.5 0.6 20.710.8 18.110.9 T 12 .3 0 . 5 12 .1 0.5 13.310.5 12.620.9 T-47 8.2 0.5 9.320.4 9.220.5 10.220.7 T-48 14.9!0.8 15 . 7 t0. 5 17 .2 0.5 16,820.8 T-49 11 .8 0.6 11 .520.4 12.020.5 10 .820..
T-50 17.410.4 21.220.7 20.010.6 20.9 0.4 T-51 14.420.7 15.020.5 16 .7 0.8 16 . 3t0.9 T-52 118.2 0.4 21.020.5 21.520.5 20.220.5 T-53 16.6 0.6 22.7 1.1 19.410.5 22 .5 0.5 T-54 16.310.4 19.820.8 19.410.6 21.620.3 T-55 14.520 5 14.6:0.6 17.0i0.5 15.6 0.6 Mean i s.d. 13.923.0 14.4 3.6 15.023.6 15.113.5 Control T-9 11.720.4 12.120.5- 12.120.5 11.521.1 T-11 13.410.4 12 .820.6 14 .9 0 .6 12 .7 1 .0 T-12 19.4 1.1 17.620.9 19 .7 0.5 17.5 0.8 L T-23 13.310.4 14 .0 0 .7 13.620.6 11 .9 1 .0 - T-24 17.420.6 15.8 0.5 18.220.5 16.820.5 T-27 15.7 0.4 16.8 0.7 17.220.7 17.821.0 l: Mean 2 s.d. 15.2 2.9 14.822.2 16.012.9 14.723.0 l 22-
Table 13 Area monitors (TLD), quarterly,1991 (continued) mR/91 days Location 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr _ Indicator T-60 12.020.6 10.910.6 11.120.7 12.010.4 T-61 11.820.5 10.520.7 10.910.6 10 .910.7 T-62 11.320.5 10.710.4 11.310.3 11 .420.6 . T-63 14.020.7 12.220.5 13 .1 0.3 13 .0 0.6 T-64 9.5 0.8 9.3 0.7 8.510.3 10.620.4 T-65 '16.510.8 15.220.7 16.020.6 15.920.9 7-66 22.120.8 21 .820.7 22.020.9 20 .2i0 .7 T-67 20 .821.0 18.911.3 21 .5 0.5 19 .2 1.2 T-68 16 .3 0.8 17.521.3 18 .6 0.8 18.6 1.0 T-69 19.6 1.6 14.320.6 20 .3 0.7 13.3 0.7 T-70 11 .9 0 .8 9.720.6 11.210.6 11.020.6 T 17 .9 0.7 18.310.6 15.1 0.4 16 .8 0.9 T 14.4tl.0 12.520.6 13.710.4 13.320.4 T-74 13 .7 0.9 11.3 0.5 12.420.6 11 .3 0.5 T-75 16 .3 0 .9 14.810.8 16.520.7 15.220.7 T-76 12.510.7 11.010.8 12 .2 0 .6 11 .2 0.6 T 11 .5 0 .5 9.510.4 10 .6 0.6 10 .7 0.5 T-90 17.510.7 17.610.8 18.120.4 18 .1 1.2 T-91 . NDa 16.210.9 17 .7 0 .7 17 .520.4 T-92 12.2 0.5 9.9 0.7 13.220.3 9.6 0.9 , T-93 12 .4 0 .6 15.110.2b NDa 11 .720.9 T-94 17.110.6 11. 5 + 0. 4 18.020.4 12.320.6 T-97 18.220.5 17 .5 0 .9 20.5 0.4 17.0 0.5 T-99 18.8 0.7 18 .9 0.6 20 .0 0.6 19.5 0.5 T-112 15.321.0 15.4 0.6 15 .3 0 .3 15 .0 0.5 T-121 17.8 0.7 19 .5 0 .9 19.310.8 19 .5 0 .5 T-122 15.0 0.9 13.4 0.4 16.9 0.8 14.7 0.3 T-123 14.521.0- 15 .7 0.9 16.610.8 16.020.4 T-125 16.110.7 17.320.5 18 .2 0.6 18.510.9 T-126 15.910.7 16 .7 1 .0 18.410.6 17.010.6 T-127' 20 .2: 0 .9 20.510.8 22.520.5 20.420.7 T-128 18.020.5 '19.020.9 19.610.6 18.920.8 T-150 12.520.8 9.2!0.6 12.810.2 9.8 0.3 T-151 18.1 0.5 19 .0 1 .2- 20.0 0.4 19.0 1.0 T-153 19.521.1 21.921.6 21.820.9 21.020.8 T-154 16.220.7 16 .6 1 .1 18.020.6 15.9 0.6 T-201 14.110.3 15.6 0.8 14.1 0.4 13.220.6 T-202 14.020.8 17.320.5b 13.9 0.3 N)a T-203 - toa 15.320.6 NDa 13.720.5 T-204' NDa 16.1 0.8 NDa- 13 .7 0 .4 T-205 16.3 0.6 18.921.0 15 .5 0.3 16 .4 0 .9 T-206 11 9 0.4 11.920.5 12 .6 1.1 10.720.7-T-207 11.4 0.4 11.220.5 11 . 2 i 0 .7 10 .0 0 .6 T-208 12.120.3 10.8 0.8 11.720.4 10.0 0.6 Mean s.d. 15.323.1 14 .9 3 .7 15 .9 3.8 14.7 3.5 a to = No data; TLD missing, b Placed 04-11-91; removed 10-09-91. 23
_ _ _ _ ._ .s. ___ . _. _ _ _ _ _ _ . _ . Table 13. : Area monitors (TLD), quarterly,1991;(continued) mR/91 days _ Location : 1st - Qtr 2nd Qtr 3rd Qtr - 4th-Qtr
-Control-
- T-78 . NDb NDb NDb Nob T-95 19.221.0 18.921.4 20.211.0 18.620.9 s T -10 .0 0.5- 10.820.7 10 .1 0 .3 - 11 .121.0
,T 19.521.0 19.0t0.3 19.320.7 0
-19.210.8 '
T-100- 17.3 0.8 16.521.2 19 . 11 ).5 17 .0 0 .8 ' T-101- -16.3 0.7 16.221.0 17 .01.0 .7 16 .420.7
'T-102: 13.510.9 12.120.6 13 .8: 0.5 8.210.9 T-103 -17.4 0.6 16.720.7 18.210.8 16.520.9 T-104 15.221.0- 15.8:0.8 16.110.9 15.320.9 T-105 -18.711.4 18 .521 .2 19 .8 !1 .2 17.020 9 T-106 14.2 0.6 16.1 0.7 14 .7 0 .6 15.010.8
. T-107 - 15.2 1.1 18.221.4 16.521.0 16.020.6-
-T-108 17.3 0.7 19.920.5. 19 .1 0.5 18.820.4 l T-109 20 .6 0 .5 20.320.5 18.820.6 18,710.5 !
T-110- 17.210.9 17,920.9 18.010.6 16.6 0.9 !
'T-111 16.610.6 19 .9 1 .2- 17 .3 0.7 17.210.9 T-124 13.8 1.0- 13.721.0 15.020.8 14 .5 0.4 T-155- 16.020.6- -14.020.7 17.6i0.6 15.3 0.6
. Mean1s.d. 16.J 2.6 16.822.8 17 .1 2 .6 16.022.8 _QC L
' T-7 9 ' - ND b' NDb NDb NDb ,
T-80 13 .610.8 11 .9 : 0 .7 13 .120.8 12.810.8 ' JT-81~ 13.010.7 11.420.6 12.710.9 12 .1 0.6
;T-82 9.220.9 9.120.6 8.820.3 9.610.5 T 110.520.6 9.1:0.5 10 .7 0.41 9.8 0.4 T-64 114.520.6- 13 .1 0.7 13 .9 0 .3 13 .4 0 .6 T-85 c 14 .210.5 12.920.7 13 .2 0 . 5 . 13.110.7
- T-86 :10.520.93 9.9 0,5 '10.120.6- 10 .9 0.8-T-88' 20 .7 0 .6- 18.320.9 21.910.7 18.320.6
- f-89 15.520.8. 13.920.6 '14.720.4 14.520.3 T-113: 113.710.8 '15.3 0.8 14.520.4 14 .5 0 .4 T-114 -NDa 17,2 0.5c 12.920.6 11.410.3 T-115 20.221.11 21 .8 :0 .8 - 21'.5 t1.3 18.621.0 T-116 ' 19.811. L NDa 21 .4 0 .8 16.520.6 T-117 16.710.8~ 18.920.8 18 .5 0.9 17.710.6 DT-118- 13.8 0.8. 17.021.1 15 ;6 0 .8- 15.420.6 LT-119~ 19 .3 1 .0 -21.3 0.8- 22 .7 0 .6- 22.010.9 T-120 15.7 0.7- :18.821.1 17 .8 0 . 5 19.420.5
? -T-200 !15.2 1.1 18.7 0.8 15.820.9 17.010.8 Hean2 s .d . L15.1 3.4- 15.224.2 15 .5 4.2 14.823.5 L: a ND = No data. TLD missing . L _ b ND = No data; site deleted frsa ' project. c Placed; 04-11-91; removed 10-03-91. s
Table 13 Area monitors (TLD), quarterly,1991 (continued)
. Location mR/91 dcys Ist Qtr 2nd Qt' 3rd Qtr 4tn'Qtr Shield T-87 5.000.6 4.3:0.5 5.620.3 4.820.3 25
Table 14 Area monitors (TLD), annually,1991. Location rR/365 days Indicator
~
T-1 50 .012.2 T-2 51 .211.2 T3 48 ,811.1 r4 58.011.1 T-5 52 .711.8 T-6 tea T-7 61.310.7 T-8 82 .311.2 T-10 62 .012.5 T-38 45.611.0 T-39 51.0il .2 T-40 57 .511.2 T-41 48.711.1 T-42 42 .921.9 T-43 69.510.9 T.44 72 .111.1 T-45 71.810.8 T-46 51 .011.0 T 47 35.620.7 T-48 65.611.1 T-49 47 .810.9 T-50 78.310.7 T-51 59.3t0.8 T-52 80.721.9 T-53 74.711.7 T-54 70.721.7 T-55 58.2tl.0 Mean i s.d. 59 .5212.5 Control T.-9 52.812.4 T-11 63.110.8 T-12 80.711.7
. T-23 57 .711.2 T-24 74 .011.4 T-27 74.011.2 Mean i s.d. 67.0110.8 a to = no data; TLD missing.
26
Table 14 Area monitors (TLD), annually,1991 (continued) Location rR/365 days j,ndicator T-60 48.711.6 T-61 47.111.6 T-62 46.410.6 T-63 52.910.7 T-64 39.210.6 T-65 65 .821.4 T-66 83.412.4 T-67 79.011.7 T-68 72.211.6 T-69 77.011.9 T-70 43.511.1 T-71 fB.8tl.0 T-73 55.711.1 T-74 54.021.7 T-75 61 .111.4 T-76 17.112.3 T-77 44.710.8 T-90 79.712.1 T-91 tea T-92 53.712.0 T-93 toa T-94 72.211.7 T-97 77.611.8 T-99 78.811.0 T-112 61 ,011.3 T-121 76.412.4 T-122 63.611.6 T-123 65 .211.1 T-125 72.311.4 T-125 62.612.0 T-127 73.410.7 T-128 76.112.0 T-150 56.211.1 T-151 73.711.4
-T-153 81.512.0 T-154 66.511.1 T-201 53.811.5 T-202 roa T-203 NDa T-204 NDa T-205 56.811.7 T-206 20.211.5b T-207 37.721.5 T-208 41.912.0 Mean i s.d. C1.2114.9 0
ND = No data; TLO missing, b llD wet; may account for low reading. 27
Table 14 Area monitors (TLD), annually,1991 (continued) l Location mR/365 days Control T-78 toa
!T-95 77.611.8 T-96 50 .921.3 i T-98 75.410.8 l T-100 69.110.9 T-101 72.310.6 T-102 56.511.5 T-103 73.6t0.6 .
T-104 66.711.2 T-105 80.421.1 T-106 61.0 1.1 ' T-107 70.920.8 T-108 78.411.1 T-109 76 .5 2.6 T-110 68.421.9 T-111 70.211.7 T-124 59.422.0 T-155 67.9il.3 Mean a s.d. 69.118.2 T-79 f0a T 48.221.6 T-81 46 .010.5 T-82 36.910.7 T-83 38.520.5 T-84 53.620.7 T-85 50.510.8 T-86 42.821.3 T-88 80.911.1 T-89 57 .511.3 . T-113 55.021.0 T-114 T0b T-115 77.820.9 T-116 80.621.9 T-117 70.712.8 T-118 59.321.8 , o T-119 85.411.0-T-120 69.720.6 L , ET-200 65.7 2.3
-Mean i s.d. 59.9215.5 Shield .
T 87 24 .921.5-a
.f0 = No data; site deleted f rom project.
b l t0 = No data; TLO missing. 28
Table 15 Mil k samples, anal yses for Sr-89, Sr-90,1-131, and gamma-enitting isotopes. Collection: Scaimonthly May through October , monthly other wi se . Date Activity (pCi/L) Collected Lab Code Sr-89 Sr-90 1-131 Ba-La-140 Cs-137 K-40 T-8 Farm. 2.7 mi WSV of Station 01-14-91 iMI-5811,2 (0.4 1.110.2 (0 . 4 <10 <10 1220i100 02-11-91 5892 <0.6 1.110.4 (0.3 <10 <10 11702110 03-11-91 5970 <0.4 0.810.3 <0.2 <10 <10 11501150 04-08-91 6034 <0.5 0.520.3 <0.2 (10 <10 11802150 05-13-91 6163 <0.8 0.7 t0.4 (0.4 <10 <10 1240 100 05-27-91 6241 <0.9 1.410.6 <0.3 <10 <10 12601150 06-10-91 6324 <0.7 0.710.3 <0.4 <10 <10 1230 90 06-24-91 6406 <0,5 0.710.3 (0.3 <10 <10 12002150 07-08-91 6486 <0.6 0.720.3 <0.3 (10 <10 13701140 07-22-91 6576 <0.9 1.010.5 <0.1 <10 <10 1280 100 08-12-91 6725 <0.6 0.810.3 (0.3 <10 (10 1100 130 08-26-91 6781 <0.5 0.8 0.3 <0.3 (10 <10 12501120 09-09-91 6848 <0.9 1.9:0.7 <0.2 <10 <10 11701150 ~ 09-23-91 6949 <0.6 1.110.4 <0.3 (10 <10 15001170 10-15-91 7066 <1.1 <0.7 <0.3 <10 <10 12801140 10-28-91 7136 <0.5 0.920.4 <0.2 <10 <10 12901140 11-12-91 7206 <0.7 0.820.4 <0.2 <10 (10 11301110 12-09-91 7274 <0.7 1.810.6 <0.2 <10 <10 lI301130 T-199 (C) Farm, 8.5 mi SW of Station 01-14-91 E l-5815 (0.4 2.420.5 <0.3 (10 (10 12402150 02-12-91 N5a .. .. a NS = No sample; location dropped f rom program.
- 29. l l
Table 15 Mil k samples, anal yses for Sr-89, S r-90,1-131, and gamma-emitting isotopes (continued) Date tctivity (pCi/L) Collected Lab Code Sr-89 Sr-90 1-131 Ba-La-140 Cs-13/ K-40 T-24 (C) Sandusty, 21.0 mi,SE of Station 01-15-91 Dil-5813 <0.4 0.9:0.3 <0.2 <10 <10 1410:160 02-22-91 5693 <0.7 1.2:0.5 <0.3 (10 <10 1230t150 03-12-91 5971 <0.4 1.4:0.4 <0.2 <10 (10 12001100 04-09-91 6035 <0.5 1.2:D.: <0.2 <10 (10 12602140 05-14-91 6164 <0.7 1.8:0.5 <0.3 <10 <10 13101110 05 ^.8-91 6242 <0.7 2.1 3.5 <0.3 <10 <10 12001130 06- 11-9 1 6325,6 <0.7 1.4:0.3 <0.4 <10 (10 12F0160 06-25-91 6407 <0.5 1.4:0.0 <0.2
<10 <10 l' 150
<0.5 2.1:3.5 <0.3 (10 <10 1-, e 2140 07-09-91 6487 07-23-91 6577 (1.1 1.7:3.4 <0.3 (10 (10 12301110 '
08-13-91 6726 (0.5 1.3:0.4 <0.3 (10 <10 11101110 08-27-91 6782 <0.6 0.9:0.4 <0.2 (10 <10 1200:130 09-10-91 6849 (0.7 1.5:0.5 <0.2 <10 <10 13302140 09-24-91 6950 <0 . 6 1.1:0.4 <0.4 <10 <10 11601130 10-15-91 7067 <0.7 1.4:0.4 <0.3 (10 <10 11802160 10-29-91 7137 <0.5 1.5:E.4 (0.4 (10 (10 12901140 11-12-91 7206,7 <0.9 1.1::.3 <0.2 <10 <10 1320290 , 12-10-91 7275 <0.6 1.2:1.4 <0.3 <10 (10 1270280 T-57 (C) Farm, 22 miles SSE of Station . 01-15-91 TM1-5814 <0.4 0.S:).3 (0.2 <10 <10 1200:120 _ 02-12-91 5894 <0.5 0.9:0.3 <0.2 <10 <10 1340:120 03-12-91 5972 <0.4 0.9:3.4 <0.2 <10 <10 1170:120 04-09-91 6036 (0.4 0.5:0.3 <0.2 (10 (10 13101130 05-14-91 6165 <0.6 0.B:0.3 <0.2 <10 (10 1220 t110 05-28-91 6243 <0.6 1.3:0.4 (0.3 <10 <10 10502130 I 06-11-91 6327 <0.6 1.1:0.4 (0.3 <10 <10 11702120 06-25-91 6408 <0.5 0.S:0.3 <0.3 <10 <10 12902150 07-09-91 6488 <0.6 1.2:0,4 <0.3 <10 <10 12902150 07-23-91 6578 <0.7 1.3:0.4 <0.2 (10 <10 14602100 08-13-91 6727 <0.6 1.B:0.4 <0.3 <10 (10 12502140 08-27-91 6783 <0.7 2.1:0.7 <0.3 <10 <10 11602120 09-10-91 6850 <0.6 0.6:0.3 (0.2 (10 (10 12902140 09-24-91 6951 <0.6 1.0:0.4 <0.3 <10 (10 13002120 10-15-91 7068 <0.7 0.6 0.4 (0.4 <10 <10 1340:130 10-29-91 7138 (0.6 0.6:0,3 (0.3 <10 <10 12801170 11-12-91 7208 <0.7 1.2:0,4 <0.2 <10 <10 13102140 12-10-91 7276 <0.6 0.S:0.4 <0.3 <10 <10 1300:90 30
1 Table 16 Milk samples, analyses for calcium, stable potassium, and ratios of Sr-90 (pC1) per gram of calcium and -Cs-137 (pC1) per gram of potassium. Collection : Semimonthly May th cugh October; monthly otherwise. Sr-90 (pci) Cs-137 (pC1) , Date Calcium Potassium per gram per gram Collected Lab Code (9/L) (9/L) of Calcium of Potassium T-8 Farm. 2.7 mi WSW of Station Cl-14-91 TMI-5811,2 0.92- 1.4120.12 1.20 <7.09 - 02-12-91 5892 s.70 1,3510.13 1.57 <7.41
.-03-12-91 5970 0.85 1.3310.17 0.94 <7 . 52 04-08-91 . 6034 = 0.85 1.36 10.17 0.59 < 7 . 35 05-13-91 6163 0.E6 1.44 0.12 0.81 (6.94 05-27-91 6241 0.85 1.4620.17 1.65 (6.85 06-10-91 '6324 0.87 1.42 :0.10 0.80 <7 . 04 06-24-91 6406 0.78 1.3920.17 0.90. <7 .19 -
_07-08-91 6486 0.79 1.58 0.16 0.89. (6.33 07-22-91 6576 0.84 1.4820.17 1.19- <6.76 08-12 6725 0.65 1.2720.15 0.94 (7 .87
^
08-26-91 6781 1.01 1.4410.14- 0.79 <6.94 09-09-91 6848 0.84 1.3510.17 2.26 <7.41 09-23-91 6949 0.97 1.7310.20 1.13 (5.78 10-15-91 7066 0.50b 1,48 0.16 <1.40 (6.76 10-28-91 7136 0.95 1.4910.16 0.95 <6.71 11-12-91 7205 0.92 1.31:0,13 0.87 <7.63 12-09-91 7274 0.85 1.4210.15 2.12 <7.03 _
~
'T-199 (C) varm 8.5 mi SW of Station 01-14-91 TMla5815 0.96 1.4320.17 2.50 <6.99 02-12-91 f6 a . -- --
. a tis = No sample;. location croppeo f rom program, b Analysis was repeated; result of reanaljsis 0.50 9/L.
31 4 i ii .____..___.______._m__ ____.m.,-_.m____ __ _ _ _ _ _ _ _ _ _ __ __ . _ . ___._.._._.
\
l i Table 16. Milk sample:, analyses for calcium, stable potassium, and ratios of Sr-90 (oCi) per gram of calcium and Cs-137 (pCi) per 9 ram of potassium (continued) 1 Sr-90 (pC1) Cs-137 (pCi) l Date Calcium Potassium per gram per gram ) Collected Lab Code (9/L) (9/L) of Calciu.m of Potassium ; i T-24 (C) Sandusky. 21.0 mi SE of ' tat,,1,on 01-15-91 TM1-5813 0.90 1.6310.18 1.00 <6.13 1 02-12-91 5893 0.93 1.4210.17 1.P.9 <7 .04 03-12-91 5971 0.81 1.39:0.12 1.73 (7.19 04-09-91 6035 1.18 1.4610.16 1.02 (6.85 05-13-91 6164 0.82 1. 5110.13 2.20 <6.62 05-27-91 6242 0.93 1.3920.15 2.26 <7 .19 06-10-91 6325,6 0.82 1.'510.09 1.71 (6.85 06-24-91 6407 1.06 1. 310.17 1.32 (7.19 , 07-09-91 6487 0.81 1.4720.16 2.59 <6.80 07-23-91 6577 0.9< 1.4210.13 1,77 <7 . 04 , 08-13-91 6726- 0.89 1.2010.13 1.46 < 7 . 81 08-27-91 6782 0.87 1.39i0.15 1.03 <7 .19 09-10-9) 6849 0.84 1.5410.16 1,79 (6.49 ' 09-24-91 6950 0.93 1.3410.15 1.18 <7.46 10-15-91 7067 0.88 1.06 0.18 1.59 <7.35 ' 10-29-91 7137 0.88 1.4910.16 1.70 <6 . 71 11-12-91 7206,7 0.88 1.53 0.10 1.25 <6.54 ! 12 10-91 7275 0.61 1.4710.09 1.97 (6.80 r T-57 (C) Farm. 22 miles SSE of Station 01-15-91 THI-5314 0.89 1.3910.14 0.90 <7.19 02-12-91 5894 0.87 1.5510.14 1.03 <6.45 03-12-91 5972 0.88 1.3510.14 1.02 <7.41 , 04-09-91 6036 1.01 1.5110.15 0.59 <6.62 05-13-91 6165 0.83 1.4110.13 0.96 < 7 . 09 - 05-27-91 6243 0.84 1.2110.15 1.55 <8. 26 . 06-10-91 6327 0.92 1.3510.14 1.20 <7.41 06-24-91 6408 0.88 1.4910.17 0.91 <6.71 07-09-91 6488 0.91 1.4910.17 1.32 <6.71 07-23-91 6578 0.97 1.6910.12 1.34 <5.92 08-13-91 6727 0.97 1.4410.16 1.86 <6.94 08-27-91 6783 0.94 1.34 0.14 2.23 <7.46 H 09-10-91 6850 0.92 1.4910.16 0.65 <6 . 71 09-24-91 6951 ~0.98 1.5010.14 1.02 -<6.67 ; 15-91 7068 0.94' 1.5510.15 0.64 <6.45 , 10-29-91. 7138 1.03 1.48 t0.20 C 58 <6.76 , 11-12-91 7208 0.87 1.5110.16 1.38 <6.62 12-10-91 7276 0.90 1.5010.10 0.89 <6.67 _ L 32 L
s Table 17. Ground water samples, analyses for gross beta , Sr-89, Sr-90, and 9mma-enitting isotopes. Collection: Quarterly. , Annual Mean Seple Description and Activity (pCi/L) 2 s.d. , _T-7 , Lab Code TWW-9260 TWW-321 TWW-1523 TWW-2839 Coll ection- Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. _ Gross Beta Suspended Solids <0.4 <0.2 <0.2 <0.8 <0.8 Dissolved Solids 2.920.5 2.920.4 3.020.7 3.020.3 3.020.1 Totai Residue 2.920.5 2.9 0.4 3.020.7 3.010.3 3.0 0.1 H-3 <330 <330 <330 <330 <330 Sr-89 <0.9 <0.6 <0.8 <0.8 <0.9 Sr-90 <0.9 <0.5 0.610.3 0.9 0.3 0.810.2 , Cs-137 <10 <10 <10 <10 <10 T-54 Lab Code TWW-9262 TWW-323,4 TWW-1525 TWW-2841 Collection Period 1st. Qtr . 2nd Qtr. 3rd Qtr. 4th Qtr. Gross Beta Suspended Solids <0.4 <0.3 <0.2 <0.8 <0.8 Dissolved Solids 2.421.1 3.320.9 3.3t?.3 3.320.4 3.120.4 Total Residue 2.4tl.1 3.320.9 3.322.3 3.320.4 3.120.4 H-3 <330 <330 <330 <330 <330
-89 <0.5- <0.5 <0.8 <1.2 <1.2 - 'Sr-90 <0.4 <0.4 <.0 . 4 <0.5 <0.5 ,
Cs-137 <10 <10 <10 <10 <10 . o m 33 -
. . ~, . - . . - . . . . - . - . - . - - . . . . . - - . - - . . - - . - . - . . - ..
Table 17 Ground water samples, analyses for gross beta, Sr-89, Sr-90, and gamma-omitting isotopes (continuea) Annual Mean Sample Description and Activity (pCi/L) i s.d. T-23 (C) Lab Code NDa TWW-1408 TWW-3464 TWW-3716 Collection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. _ Gross Beta, Suspended Solids -- <0.2 <0.2 <0.7 <0.7 Dissolved Solids -- 2.3:1.7 (2.3 <1.9 2.311.7 Total Residue -- 2.3:1.7 <2.3 <1.9 2.311.7 H-3 -- <330 (330 (330 (330 Sr-89 -- <0.7 <1.3 <1.1 <1.3 Sr-90 -- <0.4 (0.5 <0.4 <0.5 Cs-137 -- <10 <10 <10 <10 T-27 (C) Lab Code TWW-9261 TWW-322 TWW-1524 TWW-2840 Collection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Gross Beta Suspended Solids <0.4 <0.2 <0.2 <0.8 <0.8 Dissolved Solids 1.810.8 2.3:1.3 1.811.3 1.6 1.2 1.910.3 Total Residue 1.810.8 2.3:1.3 1.811.3 1.611.2 1.910.3 H-3 <330 <330 <330 <300 <330 Sr-89 <0.9 <0.7 <1.1 <1.5 <1.5 Sr-90 <0.6 <0.6 <0.5 <0.7 <0.7 Cs-137 <10 <10 (10 <10 <10 a ND = No data; samples not available. 34
Table 17. Ground water samples, analyses for_ gross beta, Sr-89, Sr-90, and gamma-emitting isotopes (continued) Annual !!ean Sample Description and Activity (pC1/L) i s.d. T-141 (QC) Lab Code TWW-9263 TWW-325 NSa Egy.2842 Collection Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Gross Beta Suspended Solids <0.3 <0.2 -- <0.8 <0.8 Dissolved Solids <1.0 3.320.1 -- 3.310.4 3.310.0 Total Residue <1.0 3.320.7 -- 3.310.4 3.310.0 H3 <330 <330 -- <330 <330 Sr-89 <0.8 <0.5 -- <1.1 <1.1 Sr-90 (0.6 <0.5 -- <0.4 <0.6 Cs-137 <10 <10 -- <10 <10 a RS = no sample; sample not received. S U 35
i Table 18. Damestic meat samples, analysis for gamma-enitting isotopes. Date Sampl e Activity (pCi/g wet) Lo:ation Collected Lab Code Type K-40 Cs-137 T-197 07-29-91 TME -149 Chicken 2.7120.48 <0.029 T-34 09-13-91 TME-156 Chicken 1.9420.40 <0.017 , en 36 m m __m__.__._.__m___________._._-____.__._____..__.-__-.--.___._-_.________.___m._._______._.__m___ _ _ - _ _ _ . _ _ _ . _ . -
Table 19 Wildlife meat samples, analysis for gamma-enitting isotopes. Collection Lab Sample Activity (pci/g wet) location Date Code Type K-40 Cs-137 T-31 09-10-91 EE-155 Goose 1.9010.46 <0.020 12-24-91 -157 Muskrat 1.4710.32 <0.021 4 6 4 w , \ J 37
L ! !I irl ' . j
- l[ ;i itl! i !
81 a 9 19h 04 65469 516a 1 - c 10 4 0 00 0 000000 111022 2 - 1 n 1 E - i 00 0 100000 g TV7 p << T0S 0.< n 8 i t t i . m t e n
- e a 1 m m 91i 0 1 31 8 e a
m g 79l 1 - o G 81 1 c 00 0 000000 1 40 4 2 5231 18802 28 89e 71 - g 00 311 a 21 00 7 1 0 2.11027 07996 000000 r u s
- - 2c - 2b 1 a r TE - o 03 0 400000 T E b 00 0 600000 e 0.< < < < <
h e V8r T0B
<0 0
- 6. < < <<< V8a T0C m
t 3 2 f o 0 o d e n m a i t 1 3 81 2 91 e d 1 t . 1 79e 0 9 19g 11 5 175472 a
- 1 - g 70 0 243366 71 - a 00 0 11023 -
1 811 a 0 2 121 16 316b 00 0 000000 O
- - 2b 00 01 000000 - - 1b 1 L
, ) TE - b 1 TE - a 00 0 400000 L V8a 05 0 500000 V7C << < < < < <
0 9 t e T0C <0 < < <<< T0 7. < s
- w 0 5. < 1 i m 2 u g 0 l
t i / t i u n C r s o p h e e r ( 71 s 21 w 2 r t 79i 3 89o 0 2 y 51 60 0501 d s
, i t
1 - d 611 a 00
- - 2r 00 0 0000011 32 7 4
6108 6.35334 11f 2- - 2i l 0 00 0 5 3 634334 000001 t e 9 v TE e TE - l 1 r 8 i " 8s 00 << 0 100000 V8u 04 0 500000 < < < < o t T0r < < <<< T0a <0 < p m c o 9. < C 0 4. < e u A H 4 4 R i 0 t d . n . n g on a n ro t s n i t sa o 11 0 n e i 71 2 89 u rs t 19b 0 8 51 - 42 6 6060 524233 o o p r 70 17049 211 e 00 3 f n i i r 81
- 16a T - 1b 0
2 2 00 0 000000 TE - a 4.11101 - 2l 00 0 000001 1 c V8K n s ey c s e E - u V7h 1 03 0 300000 1 1 < < < < < T0 00 0
< < ( 90<0000 0 < ( < < i sl T0R <0 4 y yh D 0 .
l t 3 a an e 0 l e no l p d aM m o S a t s: 2 en h 0 a 7 01 8 89y 74 8861 e l o bi 61 s 90 1 9i d 0 00 01 000000 9 0 132897 22045 51 - e 00 211l 00 0 9 3 624232 000001 d u at 81 1 - - 2s 1 t c - 16a TE r 00 0 900000 d ee T - 1 r 04 0 100000< < < < < V8a < < < < < < < e gl E - e <0 9. < T0P 6. < h el V7 s 0 7 c vo T0r o 6 a C 0 y H e r f a . t es o l e n p no e 1 et e 3 eo t t a . . rs a D 1 Gi D 1 n n r
. o o o 0 nei nei f 2 odt odt -
_ ioc 714 i tC e oc 90 1 55344 714 O _ e tC e 90 1 55344 a l e 89 3 099111 L l a l e 89 3 099111 cbl p - - 1 4 - - - - - L
- - 4 - - - - -
T b a cbl p oaoy rr LLCT SS I 1
- - b rsee KHZCCC oaoy rr LLCT SS 1
- - brsee KNZCCC *-
a wc ( , ii i: ; ; iL 1I j ; ; ;1 .
Table 20. Green leafy vegetables, analyses for strontium-89, strontium-90, I-131 and other gamma-amitting isotopes (continued)' Sample Description and Activity (pCi/g wet) T -37 T-25 T-25 T-8 T-8 Location T-8 T VE-1243 TVE -1245 TVE-1250 TVE-1247 TVE-1248 09-17-91 Lab Code TVE-1246 09-17-91 09-17-91 09-17-91 99-17-91 Parsley Collection Date 09-17-91 Cabbage Pepper Leaves Broccoli Tomatoes Horseradish Type <0.006
<0.006 <0.002 <0.004
<0.007 (0.006 <0.001 0.00320.0C2 S r-89 0.00510.002 <0.001 0.00510.002 0.00410.002 Sr-90 <0.029
<0.030 <0.014 <0.033
<0.04 7 <0.033 1-131 8.9120.66 4.4310.47 1.5710.21 5.8910.52 4.2510.58 4.2710.46 <0,014 < 0.020 <0.025 f K-40 <0.022 <0.024
<0.035 <0.022 <0.031 <0.042 !
Hb-95 <0. 042
<0.052 <0.032 <0.020 <0.022 l Zr-95 <0.018 <0.024 <0.012
<0.028 l Cs-137 <0.029 <0.014 <6.026 (0.026 <0.028 <0.12 l Ce-141 <0.038 (0.057 (0 .10
<0.11 <0.11 Ce-144 <0.14 i i
L _ _ _ _ _ _
i Table 21. Fruit Sacples, analyses for strontium-89, strontium-90, I-131 and other gar.na-ar tting isotopes.
' Coll ect .sn : Monthly in season, f Sample Description and Activity (pCi/g wet) f T-173 T-23 T -37 T-2S Location T-8 TVE-1240 TVE-1280 T'E-1241,2 TVE-1244 Lab Code TVE-1249 09-17-91 09-09-91 09-17-91 10-11-91 0?-17-91 Collection Date Apples Apples Grapes Appies Grapes Type
<0.001a <0.002 <0.005
<0.001 <0.003 0.00510.002 Sr-89 <0.001a <0.001
<0.001 <0.001 Sr-90
<0.019 <0.020 <0.041
<0.015 <0.01 I-131 1.0610.13 1.10 0 .18 1.7710.26 K-40 0.9110.17 2.2010.18 <0.016 l
(0.010 <0.012
<0.013 <0.007 <0.026 Nb-95 <0.018 <0.018
<0.018 <0.012 <0.012 Zr-95 <0.006 <0.011 <0.009 Cs-137 <0.009 <0.016 <0.020
<0.010 <0.016 Ce-141 <9.016 <0.061 <0.072
<0.040 <0.062 Cc-144 <0.064 Locatien l Lab Code Collection Date Type
-Sr-89 4
S r-90 I-131 i K-40 Nb-95 Zr-95 Cs-137 Cc-141 Ce-144 d Result Of single analysis; not enough sample to duplicate, l l l --
Table 22 Animal - wildlife feed samples, analysis for gama-mitting isotopes. Collection: Annually. Sample Description and Activity (pCi/g wet) location T-8 T-57 T-U.J Collection Date 01-14-91 01-15-91 07-29-91 Lab Code TCF-447 TCF-448 TCF-450 Type Mixed Feed Mixed Feed Mixed Feed Be-7 <0.18 <0.098 <0.076 K-40 12.50i0.62 2.5920.30 3.8110.31 Nb-95 <0.020 <0.014 <0.014 Z r-95 <0.034 <0.023 <0.025 Ru-103 (0.020 <0.012 <0.010 Ru-106 <0.17 (0.11 <0.088 Cs-137 <0.022 <0.011 <0.010 -' Ce-141 (0.047 <0.020 <0.006 Ce-144 <0.23 <0.090 <0.022 . Location 1-8 T-8 T-57 Collection Date 08-13-91 08-13-91 08-13-91 Lab Code TCF-452 TCF-453 TCF-454 Type Haylage Corn Hay B e-7 <0.14 <0.14 0.7020.14 K-40 12.70 0.37 2.03:0.20 16.4010.70 Nb-95 <0.020 <0.020 <0.029 Z r-95 <0.030 <0.029 <0.042 Ru-103 <0.018 <0.020 <0.024 Ru-106 <0.12 <0.12 <0.19 Cs-137 <0.014 <0.013 (0.023 Ce-141 <0.040 <0.041 <0.037 C e-144 <0.11 <0.11 <0.13 41
Table 22. Animal - wildlife feed samples, analysis for gamma-emitting isotopes. Collection : Annually. Sample Description and Activity (pC1/g wet) location T-31 T-31 T-34 Collection Date 09-11-91 09-11-91 09-13-91 Lab Code TCF-463 TCF-464 TCF-462 Type Smartweed Cattail Chicken feed Be-7 0.8420.05 <0.36 (0.089 K-40 3.0610.12 2.3510.52 3.9310.30 Nb-95 <0.007 <0.050 <0.016 Zr-95 <0.011 <0.082 <0.024 Ru-103 <0.006 <0.043 <0.012 Ru-106 <0.043 <0.26 <0.087 Cs-137 <0.005 <0.036 <0.010 Ce-141 <0.014 <0.060 (0.020 Ce-144 <0.037 <0.18 <0.059 Location T-198 Collection Date 09-11-91 Lab Code TCF-465 Type Smartweed Be-7 1.2010.23 K-40 2.0520.38 Nb-95 <0.032 Zi-95 <0.048 Ru-103 <0.025 Ru-106 <0.17 Cs-137 <0.020 Ce-141 <0.039 Ce-144 <0.13 42
1 N Table 23 Soil samples, analysis for ganma-anittin9 isotopes. Sample Description and Activity (pCi/9 dry) Location T-1 T-2 T-3 T-4 Date 04-15-91 04-15-91 04-15-91 04-15-91 Lab Code TS0-522 TS0-523 TS0-524 TS0-525 Be-7 (0.33 <0.23 (0.48 <0.48 K-40 11.9610.90 8.76 0.55 15.2011.14 18.8011.00 Nb-95 <0.046 <0.028 <0.063 <0.077 Zr <0.073 <0.043 <0.096 <0.13 Ru-103 <0.034 <0.029 <0.050 <0.060 Ru-106 <0.35 <0.20 <0.40 <0.98 Cs-137 0.2310.063 0.3620.033 0.08410.055 0.2410.045 Ce-141 <0.067 <0.078 <0.081 <0.12 Ce-144 <0.20 <0.30 <0.28 <0.41 Location T-7 T-8 T-9 (C) T-11 (C) Date 04-15-91 04-15-91 04-15-91 04-15-91 Lab Code TSO-526 TSO-527,8 TS0-529 TS0-530 - Be-7 <0.26 <0.30 <0.46 <0.31 K-40 8.5610.50 22.15 0.79 14.1010.85 12.4010.63
-Nb-95 <0.045 <0.054 <0.070 <0.048 Zr-95 <0.072 <0. 084 <0.12 <0.080 Ru-103 <0.032 <0.037 <0.058 <0.038 Ru-106 <0.58 <0.34 <0.85 <0.58 Cs-137 0.03020.021 0.15 0.024 0. 39t0.048 0.1210.027 Ce-141 <0.069 <0.054 <0.11 <0.076 Ce-144 <0.25 <0.20 <0.37 (0.26 Location T-12 (C) T-23 (C) T-27 (C)
Date 04-15-91 05-29-91 04-15-91 Lab Code T50-531 TS0-557 iso.532 . Be-7 <0.54 <0.43 <0.45 K-40 -20.18tl.38 15.4010.81 18.0010.94 Nb <0.070 <0.G8 <0.075 Zr-95 <0.11 <0.11 <0.12 Ru-103 <0.059 <0.055 <0.058 Ru-106 <0.49 <0.82 <0.88 Cs-137 0.5310.089 0.4810.050 0.34 0.046 Ce-141 <0.096 <0.10 <0.11 Ce-144 <0.33 <0.35 <0.38 43
. _ . .._ ._ =. _-. _ - -- .- __- - . .. . - .
Table 23 Soil samples, analysis for gamma-emittin9 isotopes (continued) Sample Description and Activity (pC1/g dry) , 1 Location T-1 T-2 T-3 T-4 Date 10-14-91 10-14-91 10-14-91 10-14-91 Lab Code T50-588 T50-569 TS0-590 T50-591 Be-7 <G.24 <0.56 0.4710.36 <0.40 K-40 9.1410.55 9.4121.06 7.3310.75 18.3011.00 Nb-95 <0.036 <0.073 <0.080 <0.066 Zr-95 <0.054 <0.11 (0.085 <0 .11 Ru-103 <0.031 <0.059 <0.054 <0.053 Ru-106 <0.29 <0.45 <0.29 <0.58 Cs-137 0.2120.027 0.26 0.070 <0.041 0.23 0.040 Ce-141 <0.064 <0.10 <0.11 <0.12 Ce-144 <0.21 <0.29 <0.21 <0.38 Location T-7 T-6 T-9(C) T-11(C) Date 10-14-91 10-14-91 10-14-91 10-14-91 Lab Code TS0-592 T50-593.4 TS0-595 TS0-596 Be-7 <0.35 0.9820.33 0.5510.28 <0.32 K-40 12 .1320.81 23.6810.83 16.04 0.87 11 .2010.61 Nb-95 <0.054 <0.086 <0.069 <0.066 Zr-95 <0.072 <0.10 <0.071 <0.074 Ru-103 <0.038 <0.063 <0.051 <0.048 Ru-106 <0.32 <0.39 <0.32 <0.24 i Cs-137 <0.043 0.29 20.037 0.7310.064 0.2210.027 Ce-141 <0.070 <0.12 <0.062- <0.10 Ce-144 <0.19 < 0. 27 <0.16 <0.18 Location T-12(C) T-23 (C) 7-27(C) Date 10-14-91 10-11-91 10-14-91 i Lab Code TS0-597 TSO-587 TS0-598 Be-7 <0.38 0.2410.10 <0.41 K-40 18.1520.89 9.9220.28 17 .8710.93 Nb-95 <0.065 <0.019 <0.086 Zr-95 <0.092 <0.024 <0.11 Ru-103 <0.051 <0.014 -<0.055 Ru-106 <0.48 < 0 .11 <0.32 Cs-137 0.4610.041 0.5910.022 0.1520.045 Ce-141 <0.11 <0.017 <0.11 Ce-144 <0.32 <0.058 <0.22 44
- ,we-e, p -r - - e yv
1 Table 24 Treated surface water samples, monthly composites of weekly grab samples, analysis for gross beta,1991. Gross Beta Activity (pCi/L) Collection Su spenced Dissolved Total Period Lab Code Sol id s Solids Residue T-11 (C) January TSWT-9394,5 <0.4 3.210.4 3.210.4 February 9694 <0.2 2.010.4 2.010.4 March 31 <0.2 2.520.3 2.520.3 1st Qtr. meant s.d. <0.4 2.610.6 2.610.6 April TSWT-515 <0.2 2.710.3 2.720.3 May 833 <0.2 2.2t0.6 2.210.6 June 1238 <0.2 2.6t0.4 2.620.6 2nd Qtr. meanis.d. <0.2 2.610.3 2.520.3 July TSWT-1787 <0.2 2.410.6 2.420.6 August 2162,3 <0.8 2.410.4 2.410.4 September 2662 <0.9 1.8t0.5 1.8 0.5 3rd Qtr. meanis.d. so .9 2.210.3 2.210.3 October TSWT-3105 <0.5 2.8 0.7 2.820.7
. November 3496 <0.2 2.220.5 2.210.5 December 4042 ,< 0. 2 2.210.6 2.2 0.6 4th Qtr. mean2s.d. <0,5 2.420.3 2.410.3 L
l 45
l l T abl e 2 4. Treated surface water samples, monthly composites of weekly grab samples, analysis for gross beta,1991 (continued) Gross Beta Activity (pCi/L) Collection Suspended Dist.ol ved Total Period Lab Code Solids Solids Residue T-12 (C) January TSWT-9396 <0.4 2.910.5 2.910.5 Februa ry 9695 <0.2 1.610.4 1.610.4 March 32 <0.2 1.710.3 1.710.3 1st Qtr. meants.d. <0.4 2.110.7 2.110.7 April TSWT-516 <0.2 2.410.3 2.410.3 May 834 (0.2 1.610.5 1.610.5 June 1239 <0.2 1.810.4 1.810.4 2nd Qtr. meants.d. <0.2 1.910.4 1.910.4 July TSWT-1788 <0.2 1.810.6 1.810.6 August 2164 <0.4 1.510.4 1.510.4 September 2663 302 2 2.010.5 2.010.5 3rd Qtr. mean s.d. <0.4 1.810.2 1.810.2 October TSWT-3106 <0.3 2.010.6 2.010.6 November 3497,8 <0.2 1.910.3 1.910.3 December 4043 <0.2 1.610.5 1.620.5 4th Qtr. meants.d. <0.3 1.810.2 1.810.2 46
'T Table 24 Treated surface water samples, monthly composites of wekly grab samples, analysis for 9ross beta,1991 (continued)
Gross Beta Activity (pC1/L) Collection Easpended Dissolved Total Period t.ab Code Solids Solids Residue
.T-23 (C)
January TSWT-9525,6 <0.2 2.010.2 2.010.2 February 9815 <0.4 2.2 0.5 2.210.5 March 192 ,3 <0.4 2.110.4 2.110.4 1st Qtr. meants.d. <0.4 2.110.1 2.110.1 April TSWT-600 <0.3 2.210.3 2.210.3 May 985 <0.2 2.110.6 2.110.6 June 1410 <0.2 1.910.5 1.912.5 2nd Qtr. meants.d. <0.3 2.110.2 2.120.2 - July TSWT-1822,3 <0.4 1.710.5 1.710.5 Au9ust 2342 <0.4 2.110.5 2.110.5 September 2723 <0.2 2.120.5 2.110.5 3rd Qtr. meants.d. <0.4 2.010.2 2.010.2 October TSWT-3229 <0.4 2.310.5 2.320.5 November 3715 <0.4 2.010.5 2.020.5 December 4206 <0.3 3.020d 3.012.5 4th Qtr meants.d. <0.4 2.410.5 2.4 0.5 47
Table 24. Treated 'urface water samples, monthly composites of weekly grab sam pl e, wlysis for gross beta,1991 (continued) Gross Beta Activity (pCi/L) Collection Suspended Dissolved Total Perico Lab Code Solids Solids Residue T-28 January TSWT-9397 <0.4 3.210.5 3.210.5 February 9696,7 <0.4 2.310.3 2.310.3 March 33 <0.2 1.910.3 1.910.3 1st Qtr.- meant s.d. <0.4 2.520.7 2.520.7
-April TSWT-517,8 <0.7 1.810.2 1.810.2 May 835 <0.2 2.210.6 2.210.6 June 1240 <0.2 1.610.4 1.610.4 2nd Qtr. meants.d. <0.7 1.910.3 1.910.3 July TSWT-1789,90 <0 . 2 1.4 0.4 1.410.4 August 2165 <0.4 1.6 0.4 1.610.4 September 2664 <0.2 1.720.E 1.7 0.5 3ro Qtr. meants.d. <0.4 1.620.2 1.610.2 October TSWT-3107 <0.4 1.610.6 1.610.6 November 3499 <0.4 1.420.4 '1.420.4 December 4044 <0.2 2.010.5 2.020.5 4th Qtr. meants.d. (0.4 1.720.3 1.720.3 48
Table 2 4 Treated surface water samples, monthly composites of weekly grab samples, analysis for gross beta,1991 (continued) Gross Beta Activity (pCi/L) Collection suspenced Oissolved Total Period Lab Code Solids Solids Residue T-50 January TSWT-9398 <0.4 3.110.5 3.110.5 Februa ry 9698 <0.4 2.220.5 2.210.5 March 34 <0.2 2.310.3 2.310.3 1st Qtr. mean1s.d. 'O.4 2.510.5 2.510.5 April T SWT-519 <0.4 2.610.3 2.610.3 May 836 <0 . 2 2.320.6 2.3 0.6 June 1241 <0.2 2.0 0.4 2.010.4 2nd Qtr. meants.d. <0.4 2.310.3 2.310.3 July TSWT-1791 <0 . 2 2.420.6 2.420.6 August 2166 <0.4 2.210.5 2.210.5 September 2665,6 <0.2 2.310.4 2.320.4 3rd Qtr. meants.d. <0.4 2.320.1 2.320.1 October TSWT-3108 <0.4 2.410.7 2.410.7 November 3500 <0.3 2.620.5 2.610.5 December <s45 <0.2 2.110.6 2.1!0.6 4th Qtr. meants.d. <0.4 2.420.2 2.410.2 49
Table 24 Treated surface water samples, monthly composites of weekly 9rab samples, analysis for gross beta,1991 (continued) Gross Beta Activity (pci/L) Collection Suspended 01ssolved Total Period Lab Code Solids Solids Residue _T_-144 January TSWT-9400 <0.4 2.810.5 2.810.5 February 9700 <0.2 3.710.6 3.710.6 March 37 <0.2 3.410.3 3.410.3 1st Qtr. meants.d. <0.4 3.310.5 3.310.5 April TSWT-521 <0.7 2.010.5 2.010.5 May 8 38 <0.2 3.420.6 3.410.6 J une 1243 <0.2 2.010.5 2.0 0.5 2nd Qtr. meants.d. <0.7 2.510.8 2.5 0.8 July TSWT-1793 <0.2 1.820.6 1.810.6 August 2168 <0.4 2.110.5 2.110.5 September 2668 <0.3 1.310.4 1.310.4 3rd Qtr. meant s.d. <0.4 1.710.4 1.710.4 October TSWT-3110 <0 .8 2.610.5 2.610.5 November 3502 <0.2 2.710.5 2.710.5 December 4047 <0.2 2.410.6 2.410.6 4th Qtr. meanis.d. <0.8 2.610.2 2.610.2 50
Table 2 5. Treated surface water samples, monthly composite of weekly samples, analysis for gross beta, tritium, gamma-emitting isotopes, Sr-89, and Sr-90,1991. Quarterly Sample Description and Activity (pC1/L) Meants.d. T-143 (QC) Lab Code 13WT-9399 TSWT-9699 TSWT-35.6 Collection Period January February March 1st Qtr. Gross Beta Suspended Solids <0.3 <0.4 <0.9 <0.9 Dissolved Solids 2.810.3 2.010.5 2.510.4 2.410.4 Total Residue 2.810.3 2.010.5 2.510.4 2.410.4 H-3 <330 <330 <330 <330 Sr-89 <0.9 <1.2 <0.4 <1.2 Sr-90 <0.8 <1.1 <0.4 <1.1 ~ Cs-137 <10 <10 <10 <10 Lab Code TSWT-520 TSWT-837 TSWT-1242 Collection Period April May June 2nd Qtr. _ Gross Beta Suspended Solids <0 . 4 <0.2 <0.4 <0.4 Dissolved Solids 3.010.5 2.4 0.6 1.710.6 2.410.6 Total Residue 3.010.5 2.410.6 1.720.6 2.410.6 H-3 <330 <330 <330 <330 Sr-89 <0.6 <0.8 <0.6 <0.8 Sr-90 <0.4 <0.5 0.610.3 0.620.3 Cs-137 <10 <10 <10 <10 51 }
l Table 25. Treated surface water samples, monthly composite of weekly samples, analysis for gross Deta , tritium, gamma-emitting isotopes, Sr-89 and Sr 90,1991 (continued) Quarterly Sample Description and Activity (pci/L) Meants.d. _T-143 (QC) l Lab Code TSWT-1792 TSWT-2167 TSWT-2667 Collection Period July August Sept ember 3rd Qtr. _ Gross Beta Suspended Solids <0.2 <0.6 <0.4 <0.6 Dissolved Solids 2.220.5 2.520.6 1.810.4 2.2 0.4 Total Residue 2.210.5 2.5 0.6 1.8 0.4 2.220.4 H-3 <330 3932108a <330 3932108 Sr-89 <0.7 <0.8 <1.4 <1.4 Sr-90 <0.4 0.8!0.4 <0.6 0.8!0.4 Cs-137 <10 <10 <10 <10 Lab Code TSWT-3109 TSWT-3501 TSWT-4046 Collection Period October November December 4th Qtr. Gross Beta Suepended Solids <0.3 <0.2 <0.3 <0.3 Dissolved Solids 1.420.4 2.810.5 1.810.4 2.010.7 Total Residue 1.420.4 2.820.5 1.8 0.4 2.910.7 , H-3 <330 <330 <330 <330 Sr-89 <1.2 <0.8 <0.8 <1.2 Sr <0.6 0.620.3 <0.7 0.620.3 Cs-137 <10 <10 <10 <10 a Analysis was repeated, result of reanaiysis 335194 pCi/L. l l 52
l Table 26. Treated surface water samples, quarterly composites of weekly grab samples, analysis for tritium, strontium and gamma-mitting isotopes. 1991 Collection ~ Activity (pC1/L1~~~ Location Period Lab Coue H-3 $r-89 Sr-90 Cs-137 Control T-11 1st Quarter TSWT-360 (330 <0.7 <0.6 <10 2nd Quarter 1549 (330 <1.2 <0.6 <10 3rd Quarter 3115 <330 <1.2 0.620.3 <10 4th Quarter 4133 <330 <0.6 0.610.3 <10 Annual nean s.d. <330 <1.2 0.610.0 <10 T-12 1st Quarter TSWT-361 <330 <0.8 <0.6 <10 2nd Quarter 1550 <330 <1.0 <0.5 <10 3rd Quarter 3116 <330 si.6 <0.6 <10 4th Quarter 4134 <330 <0.8 (0.6 <10 Annual mean s.d. <330 <1.6 <0.6 <10 TSWT-362 <330 <0.8 <0,5 <10 T-23 1st Quarter 2nd Quarter 1702 <330 <0.9 <0.5 <10 3rd Q"arter 3120 <330 (0.8 <0.4 <10 4207 <330 <0.6 <0.5 <10 4th Qarter Annual mean s.d. <330 <0.9 <0.5 <10 j 53 i J -- _ _ - - - - -- - - - - _ _ - _ - - _ _ - - - - -- - _ _ _ _ _ _ _ _ _ _
Table 26 Treated surface water samples, quarterly composites of weekly grab samples, analysis for tritium, strontium and gamma-enitting isotopes, 1991 (continued) Collected Activity (~otf/L) Location Oate Lab Code th3 Sr-89 3r-90 Cs-137 Jnd,1cator _T-28 1st Quarter TSWT-36? <330 (0.8 <0.6 <10 2nd Quarter F 01.' <330 <1.0 40.5 <10 3rd Quarter
<330 <1.1 <0.5 <10 4th Quarte. 4135 <330 <0.8 <0.6 <10 Annual mean 2 s.d. <330 <1.1 <0.6 <10 T-50 1st Quarter TSPT-364 <330 <0.7 <0.5 <10 2nd Quarter 1553 <330 <0.8 0.510.3 <10 ,
3rd Quarter 3118 <330 <1.2 0.610.3 <10 4th Quarter 4136 <330 <0.7 <0.5 <10 Annual mean ! s.d. <330 <1.2 0.6 0.1 <10 T-144 1st Quarter TSWT-365 <330 <0.7 <0.5 <10 2nd Quarter 1554 <330 <0.9 <0.5 <10 3rd Quarter 3119 <330 <1.5 <0.6 <10 4th Quarter 4137 <330 <0.6 0.810.3 <10 Annual nean i c.d. <330 <1.5 -0.810.3 <10 54
Table 27 Untreated surface water samples, monthly composites of weekly samples, analysis' for gross beta, tritium, and gamma-emitting isotopes , 1991. Gross Beta Activity (pCi/L) Collection Suspended Dissolved Total Activity (pCi/L)_ Period Lab Code Solids Solids Residue H-3 Cs-137 _ Cont rol ,T-11 (C) January TSWU-9388 <0.3 2.820.3 2.810.3 <330 <10 February 9685,o <0.4 2.710.4 2.710.4 <330 <10 March 24 ,5 <0.9 2.710.3 2.7 0.3 <330 <10 1st Qtr mean s.d. <0.9 2.710.1 2.7 0.1 <330 <1C April TSWU-509 <0.2 2.510.5 2.5 0.5 <330 <10 May 826 <0.2 2.510.3 2.510.3 <330 <10 ' June 1231 <0.5 2.210.5 2.2 0.5 <330 <10 -2nd Qtr mean s.d. <0.5 2.4 0.2 2.4 0.2 <330 <10 July TSWU-1781 <0.2 2.810.4 2.8r0.4 <330 <10 August 2196,7 <0.3 2.0 0.3 2.0 0.3 <330 <10 September 2657 <0.2 .2.010.5 2.010.5 <330 <10 3rd. Qtr. mean i s.d. <0.3 2.319.5 2.320.5 <330 <10 October -TSW U-3098 <0.4 2.510.3 2.510.3 <330 <10 November 3490 <0.2 2.020.5 2.0 0.5 <330 <10 December 4036 <0.2 2.1!0.5 2.110.5 <330 <10 4th Qtr. mean -s.d. <0.4 2.2 0.3 2.210.3 <330 <10 m 55
Table 27. Untreated surface water semples, monthly composites of weekly nmples, analysis for gross beta, tritium, and 9ammt-enitting isotopes,1991 (continued) Gross Beta Activity (pCi/L) Collection Suspended Dissolved Total Activity (pCi/L) Period Lab Code Solids. Solids Residue H-3 Cs-137 Control T-12 (C) January TSWU-9389 4.220.5a 4.120.3 8.310.6 <330 <10 February % 87 <0.2 2.420.3 2.410.3 <330 <10 March 26 <0.5 2.4!0.4 2.420.4 <330 <10 1st Qtr. mean i s.d. 4.2 0.5 3.021.C 4.413.4 <330 <10 April TSWU-510 <0.2 2.2 0.5 2.2i0.5 <330 <10 May 827 1.2 0.2 3.020.3 4.2 0.4 <330 <10 June 1232 <0.4 2.4 0.3 2.420.3 <330 <10 2nd Qtr.'mean i s.d.- 1.210.2 2.520.4 2.911.1 <330 <10 July TSWU-1782 <0.4 2.820.3 2.820.5 <330 <10 August 2157 <0.2 2.620.3 2.610.3 <330 <10 September 2658 <0.2 2.9:0.5 2.9 0.5- <330 <10 3rd Qtr. mean t s.d. <0.4 2.8 0.2 2.810.2 <330 <10 l October 'TSW U-3099 <0.4 2.120.2 2.110.2 <330 <10 November -3491 <0.2. 2.320.5 2.3 0.5 <330 <10 December 4037 <0.2 2.3 0.5 2.310.5- <330 <10 4th Qtr. mean s.d. <0.4 2.2 0.1 2.220.1 <330 <10 l a Analysis was repeated; result of reanalysis, 6.8 0.4 pCi/L; sample very L cloudy and very high in sediment content. 56
Table 27 Untreated surface water samples, monthly composites of weekly samples, analysis for 9ross beta, tritium, and 9amma-emitting isotopes,1991 (continued) Gross Beta Activity (pCi/L). Collection Suspended Dissolved Total Activity (pCi/L) Pericd Lab Code Solids Solids Residue H-3 Cs-137 Control T-23 (C) J.inuary TSWU-9527 <0.2 2.320.3 2.310.3 <330 <10 February 9814 <0.5 2.720.5 2.710.5 <330 <10 March 194 0.520.1 2.7 0.3 3.2 0.3 <330 <10 1st Qtr. mean s.d. 0.520.1' 2.610.2 2.710.4 <330 <10 April TSWU-601 <0.2 1.920.5 1.910.5 <350 <10 May 986 <0.2 2.210.3 2.210.3 <330 <10 June 1409 <0.4 2.810.5 2.810.5 <330 <10, 'S 2nd Qtr. mean s.d. <0.4 2.310.5 2.310.5 <330 <10 July TSWU-1821 <0.2 1.9:0.3 1.920.3 <330 <10 August 2341 <0.3 1.6 0.4 1.6t0.4 <330 <10 September 2722 <0.2 2.420.5 2_.4 0.5 <330- <10 3rd Qtr. mean s.d. <0.3 2.010.4 2.020.4 <330 <10 October TSWU 3228 <0.4 2.120.5 2.120.5 <330 <10 November 3714 <0.2 3.021.0 3.011.0 <330 <10 December 4205 <0.2 1.920.5 1.9 0.5 <330 <10 4th Qtr. mean s.d. <0.4 2.3 0.6 2.310.6 <330 <10 G I 57
Table 27 Untreated surface water samples, monthly composites of weekly samples, analysis for 9ross beta , tritium, and gamma-emitting isotopes,1991 (continued) Gross Beta Activity (pCi/L) Collection suspended Dissol ved Total Activity (pCi/L) Period Lab Code Solids Solids Residue H-3 Cs-137 Indicator T-3 January TSWU-9387 (0.3 3.3 0.3 3.320.3 <330 <10 Februa ry 9684 <0.2 3.710.3 3.720.3 <330 <10 March 22 <0,5 2.920.5 2.910.5 <330 <10 1st Qtr. mean s.d. <0.5 3.3 0.4 3.3 0.4 <330 <10 April TSWU-506,7 <0.2 3.620.2 3.6 0.2 <330 <10 May 824 <0.3 3.3 0.4 3.320.4 <330 <10 June 1229 <0.2 3.020.3 3.010.3 <330 <10 2nd Qtr. mean i s.d. <0.3 3.320.3 3.310.3 <330 <10 g July TSW U-1778,9 <0.2 2.8 0.2 2.810.2 <330 <10 August 2155 0.320.1 1.920.5 2.210.5 424x107 a <10 September 2654,5 <0.3 3.020.4 3.0 0.4 <330 <10 3rd Qtr. mean 2 s.d. 0.310.1 2.610.6 2.7t0.4 4242107 <10 Oct ober . T5W U-3096 <0.4 3.220.3 3.210.3 <330 <10 November 3488 <0.2 2.720.5 2.7 0.5 <330 <10 December 4034 0.620.1 2.2 0.6 2.820.6 (330 <10 4th Qtr. mean s.d. 0.610.1 2.710.5 2.910 <330 <10 a Analysis was repeated; result of reanalysis 458199 pCi/L. 9 58 !
L Table 27. Untreated surface water samples, monthly composites of weekly samples, analysis for 9ross beta, tritium, and gamma-enittin9 isotopes,1991 (continued) Gross Beta Activity (pCi/l.) ~ Collection Suspended Diss'clved Total Activity (pCi/M Lab Code Solids Solids Residue H-3 Cs-137 Period Indicator T-28 January TSWU-9391 <0 . 4 3.410.3 3.420.3 <330 <10 Februa ry % 89 <0.2 3.210.5 3.210.5 <330 <10 March 28 <0.5 2.420.6 2.410.6 <330 < 10_ 1st Qtr. mean s.d. <0.5 3.010.5 3.0 0.5 <330 <10 April TSWU-512 <0.2 3.0 0.5 3.010.5 <330 <10 May 829 <0.2 3.210.3 3.210.3 <330 <10 ' 1234 <0.2- 2.320.3 2.310.3 <330 <10 June 2nd Qtr. mean : s.d. <0.2 2.520.5 2.8 0.5 <330 <10 July TSW U-1784 <0.2 2.3 0.3 2.320.3 3531100 <10
<0.3 2.020.5 2.020.5 <330 <10 August 2159
<0.2 2.610.5 2.610.5 <330 <10 September 2659
<0.3 2.310.3 2.310.3 3532100 <10 3rd Qtr. mean i s.d.
<0.4 3.010.8 3.020.8 <330 <10 October TSWU-3100
<10 November 3493 <0.2 2.710.5 2.710.5 <330
<0.2 2.510.5 2.510.5 <330 <10 December 4338 4th Qtr. mean i s,d. <0.4 2.710.2 2.7 0.2 <330 <10 59 .
I
\
Table 27 Ontreated surf ace water samples, monthly composites of we .or samples, analysis for gross beta , tritium, and gsnma-enitting isotopes,1991 (continued) Gross Beta Activity (pCi/L', Suspenaec Dissolved Total Activity (pCi/L) Coll ection Period Lab Code Solids Solids Residue H-3 Cs-137 Indicator T-50 ilanua ry TSWU-9392 <0.3 3.2:0.3 3.210.3 <330 (10 February 9590 <0.2 2.8:0.5 2.820.5 <330 <10 March 29 <0.5 2.110.6 2.1 0.6 <330 <10 , 1st Qtr. mean 1 s.d. (0.5 2.720.6 2.7:0.6 <330 <10 April TSWU-513 <0.2 3.2 0.5 3.2 0.5 <330 <10 May 830 <0.2 4.4 0.4 4.4 0.4 <330 <10 June 1235 <0.3 2.1:0.3 2.1 0.3 <330 <10
<0.3 3.2 1.2 3.221.2 <330 <10 2nc Qtr. mean 2 s.d.
July TSWU-1785 <0.2 2.0 0.3 2.020.3 <330 <10 August 2160 <0.2 2.3:0.6 2.310.6 6572115 a <10 _ September 2660 <0.2 2.5:0.5 2.5 0.5 <330 <10 3rd Qtr. mean 2 s.d. <0.2 2.3:0.2 2.310.2 6571115 <10 October TSWU-3101 <0.3 2.410.5 2.410.5 337 96 <10 November 3494 <0.2 2.9!0.5 2.9 0.5 <330 <10 4039,40 <0.2 2.6:0.4 2.610.4 <330 <10 December 4th Qtr. mean s.d. <0,3 2.6t0.2 2.610.2 337296 <1C , a Analysis was repeated; result of reanalysis 578 103 pCi/L. 60
T abl e 2 8. Untreated surf ace water samples, monthly composite of weekly > samples, analysis for gross beta, tritium, strontium, and gamma-anitting isotopes,1991. . Quarterly
$6mple Description and Activity (pCi/L) Meants.d.
T-145 (QC) Lab Code TSWU-9393 TSW U-9691 TSW U-30 Collection Period January February March 1st Qtr. Gross Beta Suspended Solids <0. 3 - <0.2 <0.5 <0.5 Dissolved Solids 4.920.4 3.420.5 3.010.6 3.821.0 Total Residue 4.9 0.4 3.420.5 3.020.6 3.8 1.0 H-3 <330 <330 <330 <330 Sr-89 <0.8 < .4 (0.6 <0.8 Sr-90 <0.6 <0.4 <0.6 <0.6 - Cs-137 <10 <10 <10 <10 Lab Code' TSWU-514 TSWU-831,2 TSWU-1236,7 Collection Period April May June 2nd Qtr. Gross Beta Suspended Solids <0.4 0.810.2 <0.4 0.810.2 Dissolved Solids 2.810.5 3.020.2 2.2!0.2 2.7 0.4 Total Residue 2.8 0.5 3.820.3 2.220.2 2.910.8 H-3 <330 <.330 <330 <330 Sr-89' <0.6 <0.4 <0.5 <0.6 Sr-90 <0.5 <0.5 <0.7 <0.7 Cs-137 <10 <10 <10 <10 61 -
. _- . . - ~
l
- Table 28 Untreated surface water samples, monthly composite of weekly samples, enalysis for gross beta, tritium, strontium, and gamma-emitting isotopes,1991 (continued).
Quarterly Sample Description and Activity (pCi/L) Meants.d. T-145 (QC) Lab Code TSWU-1786 TSWU-2161 TSWU-2661 Collection Period July August September 3rd Qtr , Gross Beta Suspended Solids <0.3 <0.2 <0.4 <0.4 Dissolved Solids 2.420.3 1.910.5 2.020.5 2.120.3 Total Residue 2.4 0.3 1.910.5 -2.0*0.5 2.120.3 H-3 <330 <330 <330 <330 Sr <0.7 <0 . 7 <1.0 .<1.0 Sr-90 0.810.3 <0.4 <0.5 0.810.3 Cs-137 <10 <10 <10 <10 Lab Code TSW U-3104 TSWU-3495 TSWU-4041 Collection Period October November December 4th Qtr. Gross Beta
. Suspended Solids <0.4 <0.2 (0.2 <0.4 Dissolved Solids 3.1!0.3 2.920.5 2.020.5 2.710.6 Total Residue 3.110.3 2.910.5 2.010.5- 2.710.6 H-3 <330 <330 <330 <330 Sr-89 <1.0 <0.7 <0.7 <1.0 Sr-90 <0.6 0.5 0.3 <0.6 0.520.3 i' Cs-137 <10 < 10 <10 <10 62
s. Table 29 Untreated surface water samples, quarteriy composites of weekly grab samples, analysis for strontium,1991. Collection Activity (pCi/L) Location Date Lab Code S r-89 Sr-90 Control T-11 1st Quarter TSW U-31'2 ,3 <0.7 <0.6 2nd Quarter 1696 <0.8 0.6 0.3 3rd Quarter 3085 <1.3 <0.5 4th Quarter 4176 <0.6 0.6t0.3 Annual meant s.d. <1.3 0.610.0 T-12, 1st Quarter TSWU-314 <0.8 <0.7 2nd Quarter 1697 <0.7 <0 . 4 3rd Quarter 3086 <1.5 <0.6 4th Quarter 4177 <0.6 0.9 0.5 ' Annual meants.d. <1.5 0.9 0.5 T-23 1st Quarter TSWU-366 <0.9 <0.7 2nd Quarter 1756 <1.3 <0.7 3rd Quarter 3121 <1.9 <0.8 4th Quarter 4268 <0.6 0.710.3 Annual mean s.d. <1.9 0.720.3 63
Table 29 Untreated surface water samples, quarterly composites of weekly , grab samples, analysis for strontium,1991 (continuca) l Collection Activity (pCi/L) Location Date Lab Code Sr-89 Sr-90 ; Indicator T-3 1st Quarter TSWU-311 <0.8 <0.6 2nd Quarter 1694 <0 .9 0.6 0.3 3rd Quarter 30C4 <1.2 0.6 0.3 4th Quarter 4175 <0,7 <0.6 Annual meanis.d. <1.2 0.610.0 T-28 1st Quarter TSWU-316 <0.7 <0.8 2nd Quarter 1699 <1.1 <0.6 3rd Quarter 3087 <1.2 <0.5 4th Quarter 4178 <0.6 <0.5 Annual meanis.d. <1.2 <0.8 T-50 1st Quarter TSWU-317 <0.7 <0.7 2nd Quarter 1700,1 <1.2 <0.7 3rd Quarter 3088 <1.6 1.2 0.5 4th Quarter 4179,80 ,0.8
< <0.7 Annual mean s.d. <1.6 1.2 0.5 64
Table 30. Untreated ' surface lake water samples, monthly composites of. weekly grab samples,. analysis-for gross. beta, tritium, strontium-89,' strontium-90 and gamma-emitting isotopes, collected Hay through October, .1991. Gross Beta' Activity-(pCi/L) -Activity (pCi/L) Suspended Dissolved- Total Location period Lab Code ' Solids - Solids Residue H-3 Sr-89 Sr-90 Cs-137 (MAY; TSWU-855 <0.4 2.4 0.6 2.4 0.6 <330 <0.5 <0.4 <10 T-130 1310 0.510.2 2.510.5 3.020.5- d330 <0.7 <0.5 <10
~(JUN) 1884 <0.2 2.410.4 2.d+n.a < 330 <0.9 <0.4 <10 (JUL) <0.5 2198 <0.2 2.010.6 2.010.6 8841113a <0.7 <10 (AUG) <0.6 <10 2669- 0.410.2 2.110.5' '2.Si0.5 <330 <1.1 (SEP) 3138 <0.8 2.510.3 2.5 0.3 <330 <1.4 <0.6 -<10 (OCT)
T-131 TSWU-856 <0.4 1.6 0.9 1.6i0.9 <330 <0.9 1.210.5 <10 (MAY) <0.7 <10 (dun) 1311 <0.4 2.Si0.3 2.520.3 <330 <1. 2 1885 <0.4 2.210.5 2.210.5 <330 <1.1 <0.5 <10 (JUL) <0.6 <10'
$ ~(AUG) 2199 <0.2 2.310.3 2.3io.3 <330 <1.0 2670 <0.4 2.610.6 2.6i0.6 <330 <1.6 <0.8 <10 (SEP) <0.6 3139 :<0.3 2.710.5 2.710.5 <330 <1.6 < 10 (OCT)
TSWU-857 <0.4 2.Sio.6 2.5 0.6 <330 <0.7 <0.4 <10 T-132 (MAY) 1312 <0.2 2.110.5 2.110.5 <330 <0.6 <0.4 <10 (JUN) 0.6 0.3 <10-1886 <0.3 1.710.4 1.710.4 <330 <0 .9 (JUL) <0.7 <0.4 <10-(AUG) 2200 <0.2 2.610.6 2.610.6 <330 2671 <0.4 1.710.5 1.710.5 <330 <0.9 0.910.3 <10-(SEP) 0.610.3 <10 3140 <0.4 2.210.5 2.210.5 <330 <1.3 (OCT)
<0.3 2.0 1.0 2.011.0 <330 <0.8 0.610.4 <10 ;
T-133 (MAY) TSWU-858 1313,4. <0.7 2.410.2 2.410.2 <330 <1.0 (0.6 <10 (JUN) 0.710.3 <10 1887 <0.2 2.0 0.5 2.010.5 <330 <1.0 '
.(JUL) <1.0 <0.7 <10 (AUG) 2201 <0.2 2.210.3 2.210.3 <330 2672 <0.3 2.010.5 2.020.5 <330 <1.1 0.810.4 <10 (SEP) <1.2 0.620.4 <10 (OC1) 3141 0.710.2 2.410.3 3.110.4 <330 a Analysis was repeated; result of reanalysis 8861112 pCi/L. ,
f ausu . . -
Table 30.' Untreated surf ace lake water samples,. monthly composites of s sekly grab samples, analysis for gross beta, tritium, strontium-89, strontium-90 and gamma-ernitting isotopes, collected May.through October,1991 (continued). Gross ' Beta Activity (pCi/L) Activity (pCi/L) Suspended Dissolved Total Location ~ Period Lab Code Solids Sol?.ts Residue 11- 3 Sr-89 Sr-90 Cs-137 T-134 TSWU-859 <0.4 2.510.8 2.520.8 <330 <0.8 0.810.4 <10 (MAY) 1315 <0.2 2.310.5 2.310.5 <330 <0.6 <0.4 <10 (JUN) (JUL) 1888 <0.2 2.210.4 2.210.4 <330 <1.0 0.610.3 <10 2202 <0.2 1.510.5 1.510.5 <330 <0.8 <0.5 <10 (AUG). (SEP) 2673 <0.4 2.610.6 2.610.6 <330 <1.1 0.6 0.3- <10 3142 0.6 0.2 2.910.5 3.520.5 <330 <1.5 <0.6 <10 (OCT) T-135 TSWU-860 <0.4 2.311.0 2.311.0 <330 <0.7 0.620.3 <10 (MAY) 1316 <0.2 2.010.5 2.010.5 <330 <0.5 <0.4 <10
-(JUN)
(JUL) 1889,90 <0.7 2.310.2 2.310.2 <330 <0.8 0.610.? <10 2203 <0.2 2.210.3 2.210.3 <330 <1.0 <0 6 <10
$ (AUG)
<0.4 2.210.5 2.210.5 <330 <1.4 <0.5 <10 (SEP) 2674 3143 <0.7 2.610.5 2.610.5 <330 <1.6 <0.7 <10 (OCT)
TSWU-861 ' <0.2 2.610.7 2.610.7 <330 <0.9 0.610.3 <10 T-137 (C) (MAY)
<0.5 0.510.3 <10 (JUN) 1317 <0.2 2.210.5 2.210.5 <330 1891 <0.2 2.510.4 2.510.4 <330 <0.9 0.810.3 <10 (JUL) 0.610.4 <10 2204 <0.2 1.810.5 1.810.5 <330 <0.8 (AUG) 2675 0.410.2 2.610.5 3.010.5 <330 <1.2 0.610.4 <10 (SEP) <0.6 <10 3144 <0.7 2.310.5 2.310.5 <330 <2.3 (OCT)
TSWu-862 <0.5 1.7 0.7 1.710.7 <330 <0.6 1.010.4 <10 T-138 (C) (MAY) 1.810.5 <330 <1.3 1.210.6 <10 (JUN) 1318 <0.2 1.810.5 1892 <0.3 2.110.5 2.110.5 <330 <0.8 0.710.3 <10 (JUL) <0.6 0.810.4 <10 (AUG) 2205- <0.2 2.010.5 2.010.5 <330 2676,7 <0.4 2.410.3 2.410.3 <330 <1.1 0.620.3 <10 (SEP) 3145 <0.7 2.010.5 2.010.5 <330 <1.3 1.010.4 <10 (0CT) m
Table 3 0. Untreated surf ace lake water t.amples, monthly composites of weekl .. May through October,1991 (continued) } Gross Beta Activity (pCi/L) Activity (pCi/L) Suspended Dissolved Total Cs-137 Residue Sr-89 Sr-90 Lab Code Solids Solids 11- 3 Location Period
<330 <0.8 <0.4 <10
<0.5 3.310.7 3.310.7 <10 ;
T-152 (MAY) TSWU-863 3.810.5 <330 <1.0 <0.6 1319 0.310.1 3.510.5 <0. 5 <10 (JUN) 3.310.4 3.310.4 <330 <1.0 (JUL) 1893 <0.2 <0.8 0.610.3 <10 l 2.310.6 2.310.6 <330 ' 2206 <0.2 <330 <1. 2 <0.6 <10 (AUG) 2678 <0.3 7.510.7 2.510.7 (SEP) 3.410.4 <330 <1. 2 0.710.4 <10 3146,7 <0.4 3.420.4 (OCT)
'330
< <0 .9 <0.9 <10 ISWU-864,5 <0.3 2.110.7 2.110.7 <10 T-158 (C) (MAY) 2.310.3 <330 <1.4 <0.8 1320 <0.3 2.310.3 <0.4 <10 (JUN) 2.610.5 <330 <0 .9 1894 <0.4 2.610.5 <0.5 <10 (JUL) 2.410.6 <330 <0.7 2207 <0.2 2.410.6 <0 .6 <10
$ (AUG) 2.110.5 <330 <1. 3 2679 <0.3 2.110.5 <1.4 1.410.5 <10 (SEP) 2.710.5 2.710.5 <330 3148 <0.8 (0CT)
<0.9 <0.6 <10 2.411.0 2.411.0 <330 TSWU-866 <0.4 <1.0 <0.6 <10 T-162 (C) (MAY)
<0.4 2.110.3 2.110.3 <330 1321 <0.8 <0.4 <10 (JUN) 2.220.4 2.210.4 <336 1895 <0.2 <0.7 1.010.3 <10 (JUL) 2.210.4 2.210.4 s330 2206,9 <0.4 <1.3 <0.7 <10 (AUG) 2.110.5 2.110.5 <330 2680 <0.4 <330 <1.4 <0.6 <10 (SEP) 2.020.5 2.010.5 3149 <0.7 (OCT) 1.610.9 <330 <0.8 0.720.4 <10
<0.3 1.610.9 <0.9 <10 T-164 (C) (HAY) TSWU-867 2.6i0.5 2.610.5 <330 <l.5 1322 <0.4 <1.9 <0.9 <10 (JUN) 2.010.3 2.010.3 <330 1896 <0.4 <330 < 0 .9 <0.5 <10 (JUL) <0.3 1.820.5 1.820.5 2210 <1.2 <0.5 <10 (AUG) 2681 <0.4 2.210.5 2.2 0.5 <330
<0.5 <10 (SEP) 2.210.7 333291 <1.2 3150 <0.7 2.2 6.7 (OCT) _
)
L Table 30. Untreated surface lake water samples, monthly composites of weekly grab samples, analysis for gross beta, tritium, strontium-89, strontium-90 and gamma-enitting isotopes, collected
' May through October,1991 (continued) f Gross Beta ActP.ity (pCi/L) /*.civity (pCi/L)
Suspended Dissolved Total Residue H-3 Sr-89 Sr-90 Cs-137-Locat' ion Period Lab Code Solids Solids 2.510.7 2.510.7 <330 <0.8 <0.5 <10 T-167 (C) (MAY) TSWU-868 - <0.4 0.710.4 <10 2.510.5 2.510.5 <330 <0.9 (JUN) 1323 <0.3 0.710.3 <10
<0.3 2.0c0.8 2.010.8 <330 <0.9 (JUL) 1897 <1.7 0.710.4 <10
<0.3 : 110.5 2.120.5 <330 (AUG) 2211 <1.2 0.610.4 <19 z.410.5 2.420.5 <330 (SEP) 2682 <0.3 0.810.4 <.19 2.210.5 2.210.5 <330 <1.1 (OCT) 3151 <0.8
<330 <1.2 <0.8 <10 TSWU-869 <0.5 1.7 0.6 1.710.6 T-168 (C) (MAY ) - 2.2 0.2 <330 <0.7 <0.5 <10 1324 ,5 <0.7 2.210.2 (JUN) 2.3 0.3 2.310.3 <330 <0.9 0.610.3 <10 (JUL) 1898 <0.4 1.010.4 <10 1.710.5 1./10.5 <330 <0.9 2212 <0.2 l g (AUG) 2683 <0.4 2.310.5 2.310.5 <330 <l.2 <0 6 <10 (SEP) < 1. 2 <0.6 <10 3152 <0.7 2.010.4 2.010.4 <330 (OCT) i NOTE: Pages 72 through 74 are intentionally left out.
l \ F- ______
I Table 31. Fish samples, analyses for grass beta and gamma-onitting isotopes. Co11ection: Soniannually. Sample Description and Activity (pCi/g wet) Indicator Control l T-35 l Location T-33 (Lake Frie 1.5 mi HE of Station) 05-23-91 05-23-91 05-23-91 05-23-91 Collection Date 05-23-91 05-23-91 TF-1468,9 TF-1463,4 TF-1465 TF-1466 TF-1467 Lab Code TF-1462 Wall eye White Bass Carp Walleye White Bass Carp Sample Type 2.2010.07 2.4310.06 2.6610.08 3.3110.10 2.2710.08 2.6910.05 g Gross Beta 3.1710.41 1.9310.64 1.8710.34 2.5610.26 K -40 1.9010.37 2.1810.22
<0.013 '0.035 <0.020 <0.019a Cs-137 <0.023 0.02610.018 T-35 Location T-33 (Lake Erie 1.5 mi NE of Station)
Collection Date Lab Code Sample Type Gross Beta K-40 Cs-137 , ~ . , _ a Corrected result.
. _ _ _ - M
I l Table 32 Shoreline sediment samples, analyses for guana-emitting isotopes. Coll ection : Semiannually. Sample Description and Activity (pCi/g dry) location T-3 T-4 T-4 T-27 (C) Date 05-02-91 05-02-91 05-29-91 05-02-91 !! TBS-938 TBS-939 TBS-961 TBS-941 1-Lab Code b, K-40 14.5410.89 16.77 1.02 17.80 0.98 11.78t0.9/s . 2 Mn-54 <0.038 <0. 047 <0.061 <0.029 - Co-58 <0.035 <0.035 <0.075 <0 /. . Co-60 <0.052 <0.056 <0.079 <0.f~ : C
<0.031 <0.035 <0. 080 <0.026 ' )/
Cs-134 Cs-137 0.1110.038 <0.046 <0.062 <0.037 Loc ation T-132 T-138(C) T-164 (C) Date 05-29-91 05-29-91 05-29-91 Lab Code TBS-962 TBS-963 TBS-664 K-40 10.5010.58 17.8211.14 9.9210.54 Ma-54 <0.035 <0.050 <0.P16 Co-58 <0.036 <0.053 <0.039 Co-60 <0.043 <0.061 <0.045 Cs-134 <0.034 <0.039 <0.042 Cs-137 <0.030 0.57 0.063 <0.035 _ Location Date. Lab Code K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 70
I Table 32. Shoreline sediment samples (continued)- Sample Description and Activity (pCi/g dry) location T-3 T-4 T-4 T-23 T-27 (C) Date 10-31-91 10-03-91 10-31-91 10-11-91 10-31-91 Lab Code TBS-1054 TBS-1014 TBS-1055 TBS-1022 TBS-1057 K-40 10 .73 :0.37 13.7520.70 11.8010.66 11 .3010.51 9.7020.53 Mn-54 <0.014 <0.034 <0.038 <0.025 <0.028 Co-58 <0.016 <0. 042 <0.046 <0.025 <0.035 Co-60 <0.017 <0.039 <0. 048 <0.030 <0.037 Cs-134 <0.012 <0.024 <0.047 <0.030- <0.034 Cs-137 <0.016 0.1210.028 <0.035 0.20 0.020 <0.026 Location T-132 T-138 (C) T 164(C) Date 10-03-91 10-03-91 09-27-91
- Lab Code TBS-1018 TBS-1015 TBS-1002 K-40 9.07 0.50 13 .1010.94 10 .1010.45 Mn-54 <0.027 <0.046 <0.013 Co-58 <0.039 <0.050 <0.016 Co-60 <0.034 <0.055 <0.017 Cs-134 <0.029 <0.057 <0.020 Cs-137 <0.022 0.4710.049 <0.013 Location Date Lab Code K-40 Mn-54 Co-58 'Co-60 Cs-134 Cs-137 i
71
l Table 33. Egg samples, analysis for ganma-enitting isotopes. Collection : Annually. Saaple Description and Activity (pCi/9 wet) location T-34 T-197 Date 09-13-91 07-29-91 Lab Code TE-60 TE-59 -- K-40 1.3320.411 1.0110.17 Nb-95 <0.035 <0.014 Zr-95 <0.047 <0.020 Ru-103 <0.0'3 <0.012 Ru-106 <0.]6 <0.091 Cs-137 <0.018 <0.011 Ce-141 <0.039 <0.016 Ce 144 <0.11 <0.055 72
y ANNUAL ENVIRONMENTAL OPERATING REPORT: for Davis-Besse Nuclear Power Station January 1,1991 to December 31,1991 i Prepared by: Radiological Environmental Davis-Besse Nuclear Power Station Toledo Edison Company l Toledo, Ohio l April 1992
.z 7 ,
i > i x u TABLE OF CONTENTS Title Page
- List of Tables - vil-
- = List of Figures lx Summary xil Introduction 1-1
- Fundamentals 1-1 ;
Th'e Atom 1 - Isotopes . 1-2
- Radiation and Radioactivity 1-3 ,
4- Radionuclides ' 1-3 . l Radiation . 1 Radioactive Decay .1-4 - Half-life - 1 - Interaction with Matter--- 1-5 Ionization .- 1 Range and Shielding 5
- Quantities and' Units of Measurement- 1 Activity: Curie 1 -Exposure: Roentgen 1-7 Absorbed Dose: Rad ' 1-8 Dose Equivalent: Rem 1-8 i
.{
Sources of Radiation 19 Background Radiation 1-9 Man-made Radiation 1-13 Health Effects of Radiation - 1-13
\
Studies 1-13 Health Risks 1-14 Benefits of Nuclear Power - 1-16 Nuclear Power Production 1-17 What is Fission? 1-17 Nuclear Fuel 1-18 The Reactor Core - 1-19 1- Fission Control 20
- f. ReactorTypes 1-21
.s
. ' Future Reactor Types 1-21 Advanced Pressurized Water Reactor 1-21 Advanced Boiling Water Reactor 1-22 Simplified Boiling Water Reactor 1-23
- Liquid Metal Reactor 1-24 Modular High Temperature Gas-Cooled Reactor 1-24
_ Station Systems :1-26 Containment Building and Fission-Product Release Barriers 1-28 The Steam Generators 1-28
- The Turbine-Generator- 1 The Condenser - 1-29 The Cooling Tower. 1-30 Miscellaneous Station Safety Systems 1-31
- Reactor Safety and Summary 1-32 Description of the Davis Besse Site 1-33 11
.. _ . -. ~ _ . ._ _ _ _ - _.
a The 1991 Radioactive Liquid and Gaseous . Emuents Summary 1-36 Protection Standards 1-36 Limits 1 - Sources of Radioactivity Released 1-37
- Noble Gas- 1-38
+ Iodine and Particulates 1-38
- Tritium - 1-39
~ Processing and Monitoring 1-39 Exposure Pathways 1-40 Dose Assessment . 1-42 Results' 1-43
- References 1 Radiological Environmental Monitoring Program -. 2-1
- Introduction 2-1
- - Preoperational Surveillece Program ~2-2
. Operational Surveillance Program -
- Objectives 2 t
' l0uality Assurance - 2-3
- Program Description 2-4 Overview 2 Sample Analysis- 2-6
~ Sample History Comparison 2-7 Atmospheric Monitoring 2-9 Terrestrial Monitoring 2-10 Aquatic Monitoring - 2-10 4 i- Direct Radiation Monitoring 11-iii
- - - . ~, - - - . .. -.
J
.' f 1991 Sampling Program .2-11
- 1.
- 1991 Program Deviations 2-13 Sampling Imations - 2-14
- ; Atmospheric Monitoring 2-14 Lair Samples 2 r . Airborne Particulates 2-15 '
Airborne Iodine-131 2-16
-- . Terrestrial Monitoring 2-20 Milk - 2-21 Groundwater 2-23
- Broadleaf Vegetation and Fruit Samples . .
2 24 - Animal / Wildlife Feed S2mples 2-25
' DomesticiWild Meat Samples- 2 26 Soil Samples . 2-27 -
-- Aquatic Monitoring - 2-33 -
~ Treated Sarface Water 2-33 Untreated Surface Water 2-35 Shoreline Sediment 39
' Fish 2-40
- --- Direct Radiation Monitoring 2 45 Thermoluminescent Dosimeters - 2-45 ,
TLD Collection - 45 Quality Control TLDs - 2 NRC TLD Monitoring; 2-47
-. Conclusion - 2-58
- -: - References 2 - Lan'd Use Census ~ 3 1.
Program Design 3-1 Methodology 3-2
- ; Rhsults _ 3-2 iv w e - y p e -r -y 5 - i.,wy
Meteorolcgical Monitoring 4-1
- Introduction 4-1
- Onsite Meteorological Monitoring 4-2 System Description 4-2 MeteorologicalInstrumentation 4-2 Meteorological System Maintenance and Calibration 4-3 Meteorological Data Handling and Reduction 4-3 Meteorological Data Recovery 4-4 Marsh Management 5-1
- Navarre Marsh 51 Special Projects in 1991 5-3 References 5-5 Zebra Mussel Control 6-1
- Introduction 6-1
- Monitoring 6-1 Research- 6-2 Water Treatment 7-1
- Water Treatment Plant Operation 7-1 Description 7-1 Clarifier Operation 7-2
- New Drinking Water Rules 7-2
- Wastewater Plant Operation 7-3 Summary of 1991 Wastewater Treatment Plant Operations 7-3
- National P . utant Discharge Elimination Systems (NPDES) Reporting 7-5
- 1991 NPDES Summary 7-6 Outfall 001 7-6 Outfall 002 7-6 v
P I y
-?
Outfall 003 - 7-6 Ou$1601 - 7-6 Outfall 602 - 7-7 7-7
. Sampling Point 801 -
- _ Storm Water Monitoring - 7-7 Chemical Waste Management Program 81 Introduction 8-1
>- -Waste Management 81 Resource Conservation and Recovery
' Act(RCRA) 8-1 Hazardous and Solid Waste L Amendment (HSWA) 8-2 Emergency Response Planning 8-3 Comprehensive Environmental
- Response, Compensation, and Liability Act(CERCLA) 8-3 Superfund Amendment and -
Reauthorization Act (SARA) . 8-4 Other Regulating Acts 8-5 I- Clean Air Act - 8-6 Transportation Safety Act 8-6 Other Programs 8-7 Underground Storage Tanks 8-7 1 . Bum Permits - 8 - Summary - 7
' Appendix A: Glossary A Appendix B: Interlaboratory Comparison :-
. Program B1
. Appendix C: Data Reporting Conventions . C Appendix D: Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas D 1.
Appendix E: REMP Sampling Summary E-1 vi
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l LIST OF TABLES Table No. Page No. Title 1-1 1-3 1sotopes of Uranium 1-2 1-15 Risk Factors 1-3 1-37 Dose Limits to a Member of the Public 1-4 1-43 Annual Doses to the Public Due to Radioactivity Released in Gaseous and Liquid Effluents 2-1 2-5 Sample Codes & Collection Frequencies 2-2 2-8 Rs.diochemical Ar.nlysis Per-formed on REMS Samples 2-3 2-12 Samp!c Collect'.on Summary 2-4 2-16 Air Monitoring Locations 2-5 2-22 Milk Monitoring Imcations 2-6 2-23 Groundwater Monitoring Locations 2-7 2-25 Broadleaf Vegetation and Fruit Locations 2-8 2-26 Animal / Wildlife Feed Locations 2-9 2-27 Wild / Domestic Meat Locations 2-10 2-29 Soil Locations 2-11 2-35 Treated Surface Water Locations 2-12 2-38 Untreated Surface Water Locations le Shoreline Sediment Locations 2-13 2-40 2-14 2-41 Fish Locations 2-15 2-48 Thermoluminescent Dosimeter Locations 3-1 3-5 Closest Exposure Pathways Present in 1991 3-2 3-8 Pathway Locations and Corresponding Atmospheric l Dispersion (X/Q) and Deposition (D/0) Parameters vii l
.i l
1 i t Table No. Page No. Title ! 41 48 Summary of Meteorological Pata i Recovery for DBNPS 1991 42 49 Summary of Meteorological Data j Measured at DBNPS for 1991 42- 4 10- ' Summary of Meteorological Data ! Measured at DBNPS for 1991 (Con't) ,
?
5 F i
)
T t h 1 1 6 1 viii
^.
s _ , . . . . . ._ , , , , . . . . . . . . . _ . . , , . , . - - , . . _
A List of Figures Figure No. Page No. Title
~
1-1 12 The Atom 1-2 1-6 Range and Shielding of Radiation 1-3 1 10 Sources of Radiation 1-4 1 17 Comparison of Nuclear with Other Energy Sources 1980 and 1991 1-5 1-1P Fission Diagram 1-6 1 20 Fuel Rod, Fuel Assembly, Reactor Vessel 1-7 1-22 Advanced Pressurized Water Reactor 1-8 1 23 Simplified Boll!ng Water Reat: tor-1 19 1-25 High Temperature Gas Cooled Reactor 1-10 1 27 Schematic of the Davis Besse 1 11 1-33 Map of the Area Surrounding Davis-Besse 1-12 1 41 External Exposuie Pathway 1-13 1-42 Internal Exposure Pathway 2-1 2-15 Air Samples: Gross Beta
.2-2 2 17 Sampling Locations on the Davis-Besse Site ix
. . . . . . - - - - . .- - .- - _.. _ -. - - ..- - .-. - ~.- - .-. -
5 Figure No. Page No. Title , 23 2 18 Sampling location within a Five Mile Radius 24 2 19 Sampling Locations within a Twenty. ! five Mile Radius 25 2 22 Milk Samples: Strontium 90 26 2 28 Soll: Cesium 137 27 2-30 Sampling locations on the Dcvis Txsse Site
- 28 2 31 Sampling Locations within a Five Mlle Radius
-2 9 2 32 Sampling Locations within a Twenty-Five Mile Radius 2 10 2 34 Treated Water: Gross Beta -
2 11 2 37 Untreated Water: Gross Beta r-2-12 2-41 Fish: Gross Beta 2 13 2-42 Sampling Locations on the Davis Besse Site l l 2-14 2-43 Sampling Locations within a Five Mile j2 Radius 2-15 2-44 Sampling Locations within a Twenty-L Five mile Radius 2-16 2-46 TLD Samples: Comparison of Doses i Measured Since 1987 2-17 2-47 Comparison of NRC vs Davis Besse TLDs Since 1987 2-18 2 55 Sampling Locations on the Davis-Besse Site l~ x w.
, u - _. _
, -, , . . _ . . - . , . . . , . , - . . , , . . _ . . , . . . . , ~ -
Vigure No. Page No. Title 2-19 2 56 Sampling locations within a Five Mile Radius 2-20 2 57 Samp!ing Locations within a Twenty-Five Mile Radius 31 34 Land Use Census Map 41 4-3 Transmission of Meteorological Data from Towers 4-2 45 10 Meter Wind Rose 4-3 4-6 75 Meter Wind Rose 4-4 4-7 100 Meter Wind Rose 6-1 62 Zebra Mussel Graph 62 6-3 Mussel Study Device 7-1 74 Floor Plan Waste Water Treatment Plant l l l l l l x1 1- i
Davis Besse Nuclear Power Station 1941 Annual Dwironmental Operating Reprt Summary The Annual Environmental Operating Report is a detailed report of the Envi-ronmental Monitoring Programs conducted at the Davis Besse Nuclear Pow-er Station from January 1 through December 31,1991. Reports included are the Radiological Environmental Monitoring, Land Use Census, Meteorologi-cal Monitoring, Marsh Management, Zebra Mussel Control, Water Treat. ment, and Chemica! Waste Management Programs. Radiological Environmental Monitoring Program The operation of a nuclear power station results in the release of small amounts of radioactivity to the surroundmg environment. These releases must comply with stringent regulations imposed by the Nuclear Regulatory Commission (NRC). The Radiological Environmental Monitoring Program (REMP) has been established to monitor the radiological condition of the en. vironment around Davis Besse. This program includes the sampling and analysis of environmental samples, and the evaluation of the effects of re-leases of radioactivity on the environment. Radiation levels and radioactivity are monitored within a 25 mile radius around Davis Besse.The environment around Davis-Besse has been moni-tored for approximately 20 years. The REMP was established about five years before Davis Besse became operational. This program pmvided data on background radiation und radioactivity which is normally present in the area. Davis Besse has continued to monitor the environment 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 measuring radiation directly, Samples are collected from both indicator and controllocations. Indicator locations are within approximately five miles of Davis-Besse and are ex-pected to show naturally occuring radioactivity plus any increases of radioac-tivity that might occur due to the operation of Davis-Besse. Control location are greater than five miles away from Davis Hesse, and are expected to indi-cate the presence of only naturally occurring radioactivity. The results ob-tained at the samples collected from indicator locations are compared with xii
l Davis-Besse Nuclear Power Station 1991 Annual Environtnental Optating Repet l I the results from those collected at control locations ar.d with the concentra-tions present in the environment before Davis Besse became operational. This allows for the assessment of any impact the operation of Davis-Besse might have had on the surrounding environment. In 1991, over 2600 radiological environmental samples were collected, and over 3600 analyses for radioactivity were performed. Radionuclide con-centrations measured at indicator locations were compared with cone-ntra-tions 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 11 esse complies with all applicable federal regulations. Rese results are divided into four e. ctions: atmospheric monitoring, terrestrial monitoring, aquatic monitoring and direct radiation nonitoring.
- Atmospheric Monitoring Samples of air are collected to monitor the atmosphere. The 1991 results are similar to those observed in preoperational and previous operational programs. Only background radioactivity normally present in the environ-ment was detected.
- Terrestrial monitoring This includes analysis of milk, groundwater, meat, fruits, vegetables, animal feed and soll samples. The results of the sample analyses compare favorably with those of previous years. For example, cesium-137 radioactivity in soil was at an average concen, ration of 0.30 picoeurie per gram dry weight (pCi/g)in 1991, 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 f.o buildup of radioactiv-ity attributable to the operation of Davis-Besse.
- Aquatic monitoring This includes the collection and analysis of drinking water, untreated surface water, fish and shoreline sediments. The 1991 results of analyses for fish, drinking water, and shoreline sediment indicate normal background con-centrations of radionuclides and show no increase or buildup of radioactivity due to station operation, in untreated water, a trace amount of tritium (884 pCi/l) that cculd be attributed to station operation was detected in only one xiii
i j I l Davis-lkue Nuclear Ibwer Station 1991 Annual Envirtrunental Operating Report sample. This had no impact on the nearby residents or the surrounding envi-ronment.
- Direct Radiation Direct radiation measurements averaged 15.0 mrem /91 days at indicator loca-tiens ar.:116.2 mrem /91 days at con +rol locations, showing that, in 1991, radi-ation in the area of Davis Besse wa similer to radiation at locations greater than 5 miles away from the Station The 1991 operation of Davis Besse caused no significant increase in the con-centrations of radionuclides in the environment and no significant change in the quality of the environment. All radioactivity released in the Sution's effluents was well below the applicable federal regulatory limits. The esti-mated radiation dose to the general public due to the operation of Davis.
Besse in 1991 was also well below all applicable regulatory limits. In order to estimate this radiation dose, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the RUMP. During the cen-sus, Davis-Besse personnel travel every public road within a five mile radius of the Station vent to locate the radiological exposure pathways. The one pathway of particular concern is the pathway that, for a specific radionuclide, provides the greatest dose to a sector of the population, and is called the criti-cal pathway. The critical pathway for 1991 remained unchanged from the 1990 Land Use Census, which is an infant / milk pathway at 4270 meters in the west southwest sector. Meteorological Monitoring s The Meteorologice Monitoring Program at Davis Besse !s part of a program for evaluating the effects of the routine opetution of the station on the sur-rounding environment. Met-orological Monitoring began in october 1968. Meteorological instruments measure continuously and are monitored daily by meteorological monitoring personnel. Meteorological data recorded at Davis-Besse include wind speed, wind direc-tion, sigma theta (standard deviation of wind direction), ambient temperature, differential temperature, dew point and precipitation. Two instrument equipped meteorological towers are used to collect data. Data recovery for 1991 was 90% or greater ter all measured pararneters. In 1991, the data xiv
DavMlet.se Nuclear Power Station 1991 Annual Environmental Operating Rc; ort recovery for the six instruments required to be operational by Davis Besse Technical Specifications was greater than 901 Marsh Management Toledo Edison and the Cleveland Electric Illuminating Company co-own the Navarre Marsh which they lease to the U.S. Fish and Wildlife Service, who manage it as part of the Ottawa National Wildlife Refuge. Davis Besse Envi-ronmental Compliance personnel are responsible for inspecting the marsh , and reporting its status monthly. Special projects conducted in 1991 includcd song bird and Canada goose banding. In 1991,6432 birds were banded, in addition, unwanted and dis-ruptive plant species, such as purple loosestrife (Lythrum saliceria) and the giant reed (Phragmitics australlsi), 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 mussel infestation at Davis Besse. Routine sampling and analyses of water from various locations at the station provide estimates of the number of zebra mussels which might enter the plant. In addition to the sampling, Davis-Besse and the Electric Power Research in-stitute are conducting experiments to determine alternate methods for con-trolling the zebra mussel. Water Treatment Davis Besse uses Lake Erie as a source of water for the site Water Treatment Plant. The water is treated onsite to provide domestic water and to produce high purity water for use in the $tation's cooling systems. Principal activities in 1991 included the removal of precipitator number one from service for cleaning and maintenance and the implementation of the new Ohio Environ-mental Protection Agency' Drinking Water Standards which placed more stringant restrictions on turbity and additional bacteriological requirernent. xv
Davis Hease Nuclear Power Station 1991 Annual Environmental Operating Rc;w. Wastewater generated onsite is treated at the Davis Besee Wastewater Treat-ment Plant. Tne wastewater is processed and then p. imped to nolding basins where further reduction in solid content takes place. Following many days in the basin, the wastewa:er is discharged, along with other Station waste wa-ters, back into Lake Erie. During 1991, Waste Water Treatment Plant Num-ber 1 was out of service due to damage to an interior tank. The installation of supports has corrected the prob'em and the plant should be back in opera-tion early in 1992. Current plans are to remove Wastewater Treatment Plant Number 2 from service for cleaning and maintenance in 1992. Chemical Waste Management The Chemical Waste Management Program at Davis Besse was developed to ensure that the offsite disposal of nonradioactive hazardous and non-hazardous chemical wastes is performed in accordance with all applicable state and federal regulations. Davis Besse uses the best available technology, such as incineration or treatment to reduce toxicity, for offrite disposal of its chemical wastes in order to protect human health and the environment. In 1991, as a result of waste rninimization efforts,648 pounds of hazardous waste (used solvents),7,355 gallons of waste oil and 24 nickel cadmium battery cells were sent to recycling firms or a fuel blenders for thermal ener-gy purposes. As required by Superfund / .mendment and Reauthorization Act (SARA), Davis B:sse reponed eight hazardous products and chemicals to local and state agencies. Two of the chemicals, hydrazine and sulfuric acid, are classi-fled as " extremely hazardous" substances. As part of the program to remove polychorinated biphenyls (PCB) fluid from navis Besse, ten previously filled PCB transformers were retrofilled for the final time in 1990. These were sampled and analyzed in 1991 and re-clas.;ified to non PCB. The last identified PCB transformer at Daws Besse received the final retrofill in 1991. This transformer will be analyzed in 1992 and is expected to be re-clacsified as non-PCB . Appendices Appendix A contains a Glossary cf terms used throughout this report. It is not meant to be a comprehensive reference source for interpreting any docu-ments other than this 1992 Annual Entronmental Operating Report. xvi
)
1 Davis Msc Nuclear Power Station 1991 Annual Envirternental Operating Repvt Appendix B contains results from the. Interlaboratory Comparison Program required by DavM'3 esse Technical Specifications. Samples with known con-centrations of radioisotopes are prepared by the Environmental Prc,tection Agency (EPA), and then sent (with information on sample type and date of collection only) to the laboratory contracted by the Centerior Energy Corpo-ration to analyze the REMP samples. He results are then checked by the j EPA to ensure consistency with the know values. The results from both the , contracted laboratory and the EPA are provided in Appendix B. Appendix C contains data reporting conventions itsed in the REMP at Davis. Desse. The appendix provides an expl. nation of the format and computation. al methods used in reporting REMP data. Information on counting uncer-tainties, and computation of averages and standard deviations is also provided. Appendix D lists the maximum permissible concentrations of alpha and beta emitting radioisotopes and of certain other radioisotopes in air and water samples. These concentrations are taken directly from the Code of Federal Regulations, and provide compariron values for actual REMP sampimg re. sults for 1991. Appendix E provides a REMP sampling summary from 1991. He appendix provides a listing of the following for each sample type:
- the number and types of analyses performed
- the Icwer limit of detection for each analysis
- the mean and range of results for control and indicator locations a the w. tan, range, and locatinn description for the location with the highest annual mean
- the number of non-routine 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 Annual Environmental Monitoring Report Attach-ment 1. This document is not distributed with the rest of the Annual Envi-ronmental Operating Report due to its large size and techn;si nature. The information presented in Appendices B through E were provided lav Tele-dyne Isotopes Midwest Laboratories in their Annual Report to Toledo Edison (Part 1, Feb.1992).
xvil
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Annual Environmental Operating Repon 1991 Davis Besse Nuclear l'ower Statk>n Introduction Coal, oil, natural gas, and hydropower have been used to run this natior6 s electric generating stations; however, each method has its drawbacks. Coal fired power can affect the environment through mining, acid rain, and airborne discharges. Oil and natural gas are in limited supply and are therefore costly, and hydropower is limited due to the environmental impact of damming our waterways and the scercity of suitable sites in our country. Nuclear energy provides an alternate source of energy which is readily available. The operation of nuclear power stations has a very small impact on the environment in fact, the Davis Besse Nuclear Power Station is surrounded by hundreds of acres of marshland which makes up part of the Ottawa National Wildlife Refuge, the only national refuge in Ohio. In order to more fully understand this unique source of energy, background information on basic radiation characteristics, risk assessment, rear tor operation, and effluent control, is provided in this chapter. Fundamentals The Atom All matter consist of atoms. Simply described, atoms are made up of positivHv and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, respectively (Figure 1 1). The relatively large protons and neutrons are packed tightly together in a cluster at the center of the atom, called the nucleus. Orbiting around this nucleus are one or more smaller electrons. In an electrically neutral atom, the negative charges of the electrons are balanced by the positive charges of the protons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other, which helps hold the atom together. Other attractive forc:s between the protons and neu;nas keep the densely pachd protons from rep:lling each other, preventing the nucleus from breaking apart. 1-1
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- - -.-- . _ _ ~ ____ _
W EnvironmentalOperating Report 1991 Davis-Desse Nuclear Power Station . 1 O racrrDN O e nanson 8 n.m raoN I J } L ; pe%
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1 omarr I Figure 1 1t An atom conshts of two parts: a nucleus containing positively darged prutons and electrically neutral neutrorr and orw or more negatively charged electmns orbiting the nucleus. Protons and ocutrons are nea:1y identical in size and weight, while cach is about 2000 times heavier than an ejecuen. Isotopes A group of identical atoms, containing the same number of protons, make up an element. In fact, the number of protons an atoms contains detennines its chemical identity. For instance, all atous with one proton are hydrogen atoms and all the atoms with eight protons are oxygen atoms. However, the number of neutrons in the nucleus of an element may vary. Atoms with the same number of protons, but different number of neutrons, are called L isotopes.' As an example., Table 1 1 list some of the isotopes of uranium. Different isotopes of the same element have the same chemical properties, l- and many are stable, or nonradioactive. An unstable or radioactive isotope of l an eleuent is called a radioisotope. 1-2 ! =,
Annual Environmental Operating Repon 1991 Davis.Besse Nuclear Power Statk>n Radiation and Radioactivity Radionuclides The parts of an atom are normally in a balanced, stable state. If the nucleus of an atom contains an excess of energy, it is called a radioisotope, radioactiva atom, or radionuclide. The excess energy is usually due to excess number of neutrons in the nucleus of the atom. Radionuclides can be naturally occurring such as uranium-238, beryllium 7 and potassium-40, or man.made, such as lodine 131, cesium-137, and cobalt-60. Table 1-1: Isotopes of Uranium Isotope Symbol # of Protons # of Neutrons U ran i um-23 5.... ......... U-23 5...................... 92................... . . ... 14 3 Uran i u m 23 6. ..... ....... .. ~ 3 6.... ...... ........... . 92.. . .. ............ .. . .. .. . . 14 4 Uran lum -23 7.... .........U 23 7.............. ...... 92.......................... 145 Ur an l um -23 8........ .... ... U-23 8. ... ... .... . .......... 92..... .. . ..... ....... . .. .. . 146 Ura n i u m -23 9............. .. U-23 9. .. .. ...... ........... 92... .......... . ... .... .. ... 1 A7 Urs nium 24 0..............U-240............ .. ...... 92.................... ...... 148 Radiation Radiation is simply the conveyance of energy through space. For instance, he it emanating from a steve is a form of radiation, as are light rays, microwaves, and radia waves. lonizing radiation is another type of rad'ation and has similar properties to those of the examples listed above. L Ionizing radiation consists of both electromagnetle radiation and L L padiculate radiation. Electromagnetic radiation consists of rays of energy with no measurable mass that travel with a wave-like motion through space. Included in this category are gamma rays and X-rays. Particulate radiation l l- 1-3 L
Anaual Environmental Operating Report 1991 Davis-Bene Nuctear Pcmer Station 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 tc an atom); and neutrons. The properties of these types of radiation will be described more fully in the Range and Shielding section on page 1-5. Radioactive Decay Radicactive atoms attempt to reach a stable, non radioactive state through a process known as radioactive decay. Radioactive decay is the release of ! energy from an atom through the emission of ionizing radiation. Radioactia atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several , daughter products which eventually result in a stable atom. The loss of l energy and/or matter through radioactive decay may transform the atom into a chemically different element. For example, when uranium-238 decays, it emits an alpha particle and, as a result, the atom loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom dc. ermines its chemical identity. Therefore, when the uranium-238 atom loas the 2 protons and 2 neutrons, it is transformed into an atom of thorium-234. Thorium-234 is one of the 14 successive daughter products of uranium-238. Radon is another daughter product, and the series ends with stable lead 206. This example is part of a known radioactive decay series, called the uranium series, which begins with uranium 238 and ends with lead 206. Half-life Most radionuclides vary greatly in the frequency with which their atoms release radiation. Some radioactive materials, in which there are only idrequent emissions, end to have a very long half lives. Those radioactive materials that are very active, emitting radiation more frequently, tend to have a comparably short half-lives. The length of time an atoms remains radioactive is def'med in terms of half-lives. Half-life is the amount of time required for a radioactive substance to lose half its activity through the process of radioactive decay. Half lives vary from millionths of a second to millions of years. l 1-4 i l
i r- - l Annual Environmental Operating Repon 1991 Davis.Besse Nuclear Power Station Interaction With Matter Ionization Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When these forms of radiation interact widi any form of material, the energy they impart may cause atoms in that material to become ions, or charged particles. Normally, an atom has the same number of protons as electrons. Thus, the number of positive and negative charges cancel, and the atom is electrically neutral. When one or more electrons are removed an ion is forrned. Ionization is one of the processes which may result in damage to biological systems. Range and Shiciding Particulate and electromagnetic radiation each travel throup matter differently because of their different properties. Alpha particles contain 2 protons and 2 neutrons, are relatively large, and carry an electrical charge of
+2. Alpha } rticles are ejected from the nucleus of a radioactive atom at speeds rrnging 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 centirreters of air (Figure 12).
Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed oflight (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1. Because they are so small and have a low charge, they do not collide and interact as often as alpha particles, so they can travel farther. Beta particles can usually travel through several n'eus cf air, but may be stopped by a thin piece of metal or wood. Gamma rays are pure energy that travel at the speed oflight. They have no , measurable charge or mass, and generally travel much farther than alpha or l beta particles before being absorbed. After repeated interactions, the gamma l ray finally loses all ofits energy it and vanishes. The range of a gamma ray in air varies,' depending on the ray's energy and interactions. Very high energy gamma radiation can travel a con 31derale distance, whereas low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of lead or concrete may be needed to effectively shield gamma rays. 1-5
-*e
1 l l Annua! Environmental Operating Report 1991 Davis Besse Nuclear Power Stat *on. l sa
.d: 'j Y
~ ~-
IPf,* _-- ~ _ g ___-- Gemma - .~ Neutron. -- f .-,., ' RadioscJve Paper aluminum Lead Concrete Waterial Figure 12:As radiation travels, it collides and interacts with other stoms 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 demie materials such as lead, while hydrogenous matedals (those containing hyd ogen atoms), such as water and concnte, are used tu ste.p neutrons. Neutrons come from several sources, including tne interactions of cosmic t radiation with the earth's atmosphere and nuclear reactions within nuclear { power reactors. However, neutrons are generally not of environmental ~ concern since nuclear power stations are designed to keep neutrons within the containment building. Because neutrons have no charge, they are able to pass very close to the nuclei of the material 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 ball is deflected when it strikes another. When deflected, the neutron loses some if its energy. After a series of these deflections, the neutron has lost most ofits energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal neutron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can
%ve from 200 thousand to 200 million times the energy of thermal neutrons.
1-6
F 1 l l t Annual Environmental Operating Report 1991 Davis Beene Nucicar Power Station Neutron shielding is designed to slow down fast neutrons and absorb thermal I neutrons. Often neutron shieldicg material consists of several components, including a highly dense 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 thennal neutrons. At Davis Besse, concrete is used to form an effective neutran shla!d. C =ete is used because it contains water molecules and can be easily molded around odd shapes. , Quantities and Units Of Measurement P There are several quantitles and units of measurement used to describe radioactivity and its effects. Four terms of particular usefulness are activity, exposure, absorbed dose, and dose equivalent. Activity: Curie Activity is the number of nuclei in a sample that disintegrate (decay) ner unit of t.ne. Each time a nucleus disintegrates, radiation is emitted. The curie _(Ci) 3 the unit used to describe the activity of a material and indicates the
. rate at which the atoms of a radioactive substance are decaying. One curie indicates the disintegration of 37 billion atoms per second.
A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. For example, one gram of ,
- radium 226 is the equivalent of one curic of activity, but it would take 9,170,000 grams (about 10 tons) of thorium 232 to equal one curie.
Smaller units of the curie are often used, especially when discussing the low concentrations of radioacilvity detected in environmental samples. For
~
instance, the microcurie (uCi) is equal to one millionth of a curie, while the picocurie (pCi) represents one trillionth of a cude.
- Exposure: Roentgen .
Exposure is a term used to describe the ability of ionizing radiat5n 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 roentgen is the quantity of exposure that causes approximately two billion ionizing events (i.e., creation of Ion pairs) per cubic centimeter of air.
1-7 q ' y ei=W use W ie*=y-p-1mi g w gm.-4 gsog ,tw,a
l l Annual Environmental Operating Repon 1991 Davis Besse Nuclear Power Station A common way to describe the rate of exposure to gamma radiation is in i roentgens per hour (Whr). Often a smaller unit used is milliroentgens per I hour (mWhr), 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. m , addition, the roentgen applies only to the energy of the radiation in air, and l does not eccount for the fact that differen; substances absorb different l amounts of energy. Thus, another unit is n:cessary to describe the amount of energy absorbed by any material. Absorbed Dose: Rad Absorbed dose is a tenu used to describe the radiation energy absorbed by any <naterial 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 defm' ed as the energy ofionizing radiation deposited per gram of absorbing material (1 rad
= 100 erg /gm). The rate of absorbed dose is usually given in rad /hr.
If the biological effect of radiation was directly proportional to the er.ergy deposited by radiation in an organism, the rad would be a suitable measurement of the biological effect. However, biological effects depend not only on the total energy deposited per gram of tissue, but on how this energy is distributed along its path. Experiments have shown that some types of radiation are rnore damaging per unit path of travel than others. Thus, another unit is needed to quantify the biological damage caused by lonizing radiation. Dose Equivalent: Rem Biological damage due to alpha, beta, gamma and neutron radiation may result from the ionization caused by these radiations. Some types of rrdiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or X rays. Therefore, a qual!!y factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to a particular type of ionizing radiation. The dnse equivalent is measured in rem (radiation equivalent man). 1-8
l Annual Environmen;al Operating Reprt 199t Davis Desse Nucicar Power Station As an example of this conversion from absorbed dox to dose equivalent, the quality factor for alpha radiation is 20. Ilence, I rad of alpha radir. tion is approximately equal to 20 rem. Beta and gamma rr.aintion 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 environmental radiation, the tem is a large unit. 'Iherefore, a smaller unit, the millirem,is often used. One millirem (mrem)ir 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 occurrence 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 bodies, it also occurs naturally in the soil, water, air, and space. All these common sources of radiation contribute to the natural background radiatio.1 to which everyone is exposed (Figure 13). The earth is constantly showered by a s:cady stream of high energy gamma rays and particulate radiation that come from space, known as costnic 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 provides 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 cosmic radiation is approximately 26 mrem per year. Radionuclide; commonly found in the atmosphere as a result of cosmic ray interaction > :nclude beryllium 7, carbon-14, tritium, and sodium 22. 19 l
Annual Environmental Operating Report 1991 Davis-Deue Nuclear Power Station Sources of Exposure to the Public Natural Background Nuclear Industry Radon 0.C51 55% [ Others less than LOX Cansuser Products 3.01 Nucles We dieme Rocks and loil Wedical I-rays 8.0 % R a dio a c tivit y Inside the Body 80 it!
, If ot o: Shaded portion indicates senmade radiation.
Source: National Council on Radiation Protection and Weasurements. NCRP Report No.93. Figure 1-3: A very small annual dose to the public results from the nuclear pcmer industry. Actually, the most significant annual dose the average individual receives is that from naturally occurring radon. 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 exists 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, archaeologists can estimate the point at which it no longer assimilated radioactive carbon in its tissues (i.e., the point of death). Another common naturally occurring 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 radiation-radon. According to the National Council on Radiation Protection (NCRP), over half of the radiation dose the average American receives is i 1-10
Annual Environmenta! Operating Repon 1991 Davis lbse Nuclear Power Station attributed to radon. Redon 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 I the soil to rerb the atmosphere. Radon occurs in all soils, but because it is a 1 daughter proCoc of uranium, it occurs in higher concentrations in rocks (and soils derived from rocks) with high concentrations of uranium, such as black shale >, granites, phosphate roch and carbonate rocks. Radon occurs indoors as a result of 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 trugrate through uncracked slabs, slabs with cracks or 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 of uranium content of the soil:
- weather conditions constructions methods
- presence / absence of any cracks or openings in the foundations Some weather conditions, such as low pressure systems or increased rain fall, act to force radon out of the soil at an increased rate. In addition, construction methods affect indoor radon concentrations. Buildings built on a slab with no crawl space, sealed to prevent energy loss, those with bisements, and those without fully ventilated crawl spaces tend to be linked to higher radon concentrations.
Because uranium naturally occurs in all soils and rxks, 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. 1-11
._. .- . -_ _. -- .- . . _ = - -. _ . . - - _ _ . _
I Annual Environmental Operating Repon 1991 Davis flesse Nucicar Power Station Radon.related health concerns stem frcm the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it decays. Alpha radiation can easily be stopped by a person's dead skin layer. However, alpha radiation can cause darnage to internal tissues when ingested or inhaled. As a result, exposure to the lungs is of greatest concern, especially as 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. hree common methods used presently to detect radon in homes and other buildings are as follows:
- Charcoal canister method:
Charcoal canisters, which absorb 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 analyzed. From this information, the laboratory can determine the approximate concentration of radon gas required to produce the decay prod. ucts measured. 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 laboratory for analysis. At the laboratory the number of tracks on the film are counted. His information is used to estimate the average concentration of radon in the building dur-ing the period that the film was exposed. l l l
- Electronic monitoring method:
- Electronic monitors are available which continuously detect the number of negative ions produced by decaying radon and pro-l vide 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
- l. recommendations for concentrations at which to take corrective actions.
l Further information on radon, its detection , and actions to reduce the radon l concentration in buildings can be obtained by contacting the state radon l program office at the following address: 1-12 0 . ~
Annual Environmental Operating Iteport 1991 Davis lhe Nuclear Power Station Ohio Department of Health P.O. BOX 118 Columbus, Ohio 43266-0118 l (614) 481-5800 (800) 523-4439 (in Ohio Only) Man-Made Radiation In addition to naturally occurring radiation and radioactivity, people are also exposed to man made radiation. The largest sources of exposure include medical x rays and radioactive. pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium 90, cesium-137, carbon-14, and tritium. As shown in Figure 1-3, 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 1991 were only 0.07 and 0.04 mrem, respectively. Each of these doses is less than the dose an individual would receive from one coast to-coast jet flight (3 mrem). Health Effects Of Radiation Studies The effects ofiocizing radiation on human health have been under study for more than eighty years. Scientists have obtained valuable knowledge through the study oflaboratory animals that were exposed to radiation under extremely controlled conditions. However, it has proven difficult to relate the biological effects of irradiated laboratory animals to the potential health effects on humans. Hence, much study has been done with human populations that were radiated 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.
1 13
r Annual Environmental Operating Repon 1991 Davis.Besse Nuclear Power Station 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 effects 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 a low level radiation exposure. The effects predicted in this manner have never been actually observed in individuals exposed to low level radiation. However, this assumption provides a highly conservative model of radiation induced health effects, because it most probably overestimates the risks associated with receiving low doses of radiation. Health Risks Since the actual effects of exposure to low radiation are difficult to assess, scientists often refer to the risk involved. The problem is one of evaluating attematives, of comparing risks and weighing them against benefits. People make decisions involving risks every day, such as whether to(.not to) wear seat belts; or_whether to (not to) 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 automobile accidents. By building safer cars or wearing seat belts, this risk can be reduced, however, even a parked car is not risk free. You could choose not to drive, but even as a pedestrian or a bicyclist you may be injured by cars.' Reducing the risk of injury from automobiles io zero requires moving to a place where there are no automobiles. While most people accept the risks inherent in such activities as smoking and driving to work each day, some people seem to feel that their energy needs should be r"t on a risk-free basis. However, this is impossible , no matter what the energy source. The buming of fossil fuels can have a negative impact on the environment, and even the use of hydropower entails risks, including that of a ruptured dam and habitat destruction that can result from damming waterways. Tht.s, attentic,n should be focused on taking steps to safeguard the p4' c, 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.
- l. 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 feel ionizing radiation. Sometimes, if we have another source of information, we may believe the widespread myths about ionizing 1-14
,. . - .- . _ _ _ _ _ _ = - __ . . .. .-_ Annual Environmental Operating Report 1991 Davis Besse Nuclear Pmver Station 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. Although these risks are just as real as the risks concerning in radiation. Most risks are with us throughout our lives, and their effects can be added up over a lifetime to obtain a total effect on our lives. Table 1-2 shows a number of different factors that decrea:- the average life expectancy ofindividuals in the United States. Table 1-2t Risk Factors Factors Estimated Decrease in Average Life Enpectancy* Male rather than female 5.0 years Overweight by 30% 3.6 years Cigarette smoking: 1 pack / day 7.0 years 2 packs / day 10.0 years Heart diseases 5.8 years Cancer 2.7 years City Living (not rural) 5.0 years 125 operating nuclear power stations less than 12 minutes
- The typical life span in the United States is now 76 years for women and 71 years for men.
The American Cancer Society estimates that about 30 percent of all Americans will develop cancer at sorne 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 millitem in addition 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 person from tha' group may develop cancer during his/her lifetime. 'Ihis increases the risk from 30 percent to 30 01 percent. For comparison, the average offsib dose to individuals in the population due to the operation of the Davis Besse Nuclear Power Station is significantly less than one millirem (0.001 millitem in 1991). Ifit is 1-15
, --- . - -- - .-.-. . . .- . ~-.
Annual Environmental Operating Report 1991 Davis.Besse Nuc1 car Power Station considered that the Davis.Besse Nuclear Power Station will operate for the remainder of its license at this rate, the probability of even one person in the population developing a cancer due to the presence of the Davis Besse Nuclear Power Station is ~t-mely small. The preceding table shot vide you with an idea of the risks associated with nuclear power with respect to other, more significant risks that we accept as a pa;t ;f our daily lives. Only wl.en one is presented with a basis l for comparison, can he or she make the decisions that he benefits derived from a particular activity (e.g., driving an automobile) outweigh the costs associated with that activity (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 associated with nuclear power in perspective. Benefits of Nuclear Power l Nuclear power plays an important part in meeting today's electricity needs, l and will continue to serve as an important source of electric energy well into i the future. In 1980, nuclear power accounted for only eleven percent of the l electricity produced in the United States (Figure 1-4). By the end of 1991, however, this number was greater than twenty percent. At the same time, dependence on oil as an energy source decreased by more than half. By
- decreasing the nations' dependence on oil, dependence on foreign oil supplies
- also decreases, thereby ensuring the nation can continue to be self-sufficient in meeting 'he energy needs of it's private and business sectors.
Nuclear power offers several advantages over alternative sources of electric l energy: nuclear power has an excellent safety record dating back to 1957 when the first commercial nuclear power station began operat-log, uranium, the fuel for nuclear power stations, is a relatively inex-pensive fuel that is readily available in the United States, l 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 and how Davis-Besse uses nuclear fuel and the fission process to produce electricity. 1-16
Annual Environmental Operating Report 1991 Davis Desse Nuclear Power Station NUCLEAR POWER'S CONTRIBUTION IN MEETING THE NATION'S ELECTRICITY OFMANDS (1980) NUOLEAR COAL NATUnAL oAS OR 65.5 '- -
'O' O -'
15.1 avono oTHER I to g NATURAL oAS 4.2 coal NUCLEAR 20.c 1980 19 91 SOURCW 'f5 COUNCTL POR ENf TOY AE ALENEM Figure 1-4 : Since 1980, the nation's dependcoce on nuclear power for supplying electricity has almost doubled. This has led to the decreased dependena on the amount of oil and natural gas needed to omduce electricity. "Ihe advantage to this is less emission to the atmosphere which may cause acid rain. Nuclear Power Production Electricity is produced in a inclear 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, which is also a boiler. Inside the boiler, water is turned into steam. In a nuclear station, the furnace is replaced by a reactor containing a core of nuclear fuel, primarily uranium. Heat is produced when the atoms of uranium are split, or fissioned, inside the reactor.
- What is Fission?
A special 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 the bond is weak enough, the nucleus can be split when bombarded by a free neutron (Figure 1-5). This causes the entire atom to split, producing smaller atoms, more free neutrons, and heat. In a nuclear reactor, a chain reaction of fission events provides the heat , necessary to boil the water to produce steam. 1-17 i
\
Annual Environmental Operating Report 1991 Davis-Besse Nuclear Power Station
.\ / ,/ O
>O i
>O ass No 7
O aturnon S PROTUN w HEAT Figure 15: When a heavy atom, such as uranium 235 is split, or fissioned, beat, free neutrons, and fission fragments result. 'Ihe free neutrons can then strike neighboring atoms causing them to fission also. In the proper environment, this process can continue indefinitely in a chain reaction. Nuclear Fuel The fissioning of one uranium atom releases approximately 50 million times more energy that the combustion of a single carbon atom common to all fossil fuels. Since a singte small reactor fuel pellet contains trillions of atoms, each pellet can release an extremely large amount of energy. The amount of electricity that can be generated from three small fuel pellets would require about 3.5 tons of coal or 12 barrels of oil to generate. Nuclear fission occurs spontaneously in nature, but these natural occurrences cannot sustain themselves because the freed nuetrons either are absorbed by non-fissionable atoms or quickly decay. In contrast, a nuclear reactor minimized neutron losses, thus sustaining the fission process by several means: using fuel that is free of impurities that might absorb the freed neutrons; I l-18
, =
Anmial Environmental Operating Report 1991 Davis-Besse Nuc1 car Power Station l
; + 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; g ' - and slowing neutrons down to increase the probability of fission by providing a " moderator" such as water.
; 1 o Natural uranium con'ains less than one percent U-10 compared to the more o abundant U-238 when it is mined. Before it can be economically used in a g
nuclear reactor, it is enriched to approximately three percent U-235 to [ U-238. In contrast, the nucleer material used in nuclear weapons has been enriched m over 97 pe.rcent. Because of the low levels of U-235 in nuclear fuel, a nuclear power station cannot explode like a bomb. After the uranium is separated from the earth and rock in the ore, it is t concentrated by a milling process. After milling the ore to a granular form an(! 4 solving out the uranium with acid, the uranium is converted to uranium hexafluoride (UF6). A chemical form ot uranium that exists as a gas at temperatures slightly above room temperatute. The uranium is then highly purified and shipped to un enrichment facility where gaseous diffusion converters increase the concentration of U-235 in the fuel. The enriched gaseous UF6 is then converted into powdered uranium dioxide WG) a highly stable ceramic material. The UO 2pewder is put under high p cssere to form fuel pd'Its, each about 5/8 inch long and 3/8 inch in diameter (refer to Figurr.1-6). Approximately five pounds of these pellet 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 ofiieat, i radiation and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods. The Reactor Ce.e Two hundred eight fuel rods comprise a single fuel assembly. The reactor core at Davis-Besse contains 177 cf these fuel assemblies, ech approximately 14 feet tall and 2,000 pounds in weight. In r,ddition to the fuel r'xis, the fuel assembly also contains 16 vacant holes for the insertion of control rods, r.nd one vacant hole for an incore monitoring probe. This probe monitors temperature and neutron levels in oc fuel assembly. The Davis-Besse reacto vessel weighs 838,000 pounds, has a diameter of 14 feet, is 39 feet high, and has 81/2 inch thick steel walls. 1-19
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l l Annual Environmental Operating Report 1991 Davis.Besse Nuclear Powcr Statk>n Fuei Pellet 0 bl i
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" fingers" containing silver, indium, and cadmium metals that absorb free neutrons, thus disrupting the fission chain reaction. When control rod assemblies are slowly withdrawn from the core, fissioning begins and heat is produced. If the control rod assemblies are inserted rapidly intn the reactor core, as during a plant " trip," the chain reaction ceases. A slower acting (but
- more evenly distributed) method of fission control is achieved by the addition of a neutron polson to the reactor coolant water. At Davis-Besse, beric acid can be concentrated or diluted as necessary, in the coolant to achieve the desired level of fission. After boric acid is added to the coolant water, the acid turns into borore 10. Boron-10 radily absorbs free neutrons, hence the term " neutron poison," forming boron-11. The baron-11 in turn decays to r.on-radioactive lithium by the emission of an alpha particle. 'j Reactor Types Virtually all of the co r mercial reactors in this country are either boiling water reactors (BWks) or pressurized water reactors (PWRs). Both 1-20
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Aanual Environantal Operating Repon 1991 Davis Besse Nuclear Power SWon l l types are also called light water reactors (LWRs) because their coolant, or L medium to transfer heat, is ordinary water, containing the light isotope of I hydrogen. Some reactors use the heavy isotope of hydrogen (deut 'am) in l the reactor coolant. Such reactions are called heavy water reactors, or HWRs. l
- In BWRs, water passes through the core and boils 3 steam. The steam passes through separators which removes water dro, ts. The steam then f travels to dryers before entering the turbine. After passing though the turbine l the water returns to the core to repeat the cycle.
! 1 In PWRs, the reactor water or coolant is precsurized to prevent it from l boiling. The hot water is pumped to a steam generator (heat exchanger) where its heat is transferred to a separate water supply. The water int.ide the l generator bails into steam which is used to turn the turbine. 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 tcactors in the State of Ohio. 1 l Future heactor Types ! l In the future, the BWks and PWRs may not be the only types of commercial reactors in operation in the United States. Presently, several reactor typer are being designed or developed which would be licensed by design or class. l The new reactors will be smaller and more modular units, approximately 80-6lL Megawatis electric (MWe) in size. These proposed reactors would have more passive sysems relying on gravity, natural air flow (convection) and evaporation cooling systems in the event of a loss of coolant situation. Also, these reactors could be fabricated at the manufacturers and shipped to a l plant for installation. This would save money and time during construction. l The following paragraphs discuss five reactors that ma y be licensed in this l country. l ! Advanced Pressurized Water Reactors ; The Advanced Pressurized Water Reactor (APWR) or passive water-cooled l L reactor by Westinghouse Electric Corporation is a 600 MWe reactor which ; L replaces many active systems with more passive ones. The AP-600, Westinghouse's version, is t.imilar to current PWRs with the following exceptions. The containment building is larger than usual. Safety features 1-21
Annual Environmen:al Operating Report 1991 Davis-Desse Nuc1 car Power Station that aid in the maintenance of the building pressure and the prevention of a reactor vessel ruptune include cooling sprinklers located above the reactor vessel and air baffles that allow natural convection cooling. Gravity-Feed Emergency Flood Tanks located above the core allow water to free-flow down in case of a loss of coolant situation. The reactor uses a uranium dioxide pellet as fuel and operates at 60(PF. Construction of the AP-600 is estimated to take five years. Since prefabricated modules (reactors) can be purchased and installed, construction time and cost would be considerably less than building a reactor at a site. Figure 1-7:'Ihc AP600, shown bere,is fabricated at. the manufacturers' and shipped to a site ~ '" for installation. 'Ihis reduces both " construction time and cost without nU - f compromising plant safety. " ""', / x =e a
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in the reactor vessel. This reduces the amount of shielding required and the number of welds in the system. Also, the control systems are driven electromechanically rather than hydraulically, thereby reducing maintenance. Safety systems are more redundant, requiring less operator intervention. The ABWR would be capable of producing 1350 MWe and would use uranium dioxide as a fuel. Tokyo Electric Power Company in Japan has plans to build the firs
- AWR once pre approved certification is completed.
The plant constructio.. ..me is estimated to take five to six years. 1-22
.f Annual Environmental Operating Report 1991 Davis-Desse Nuclear Power Station
- Simplified Boiling Water Reactor (SBWR)L The General Electric Company is also developing a secend type of BWR
- called the Simplified Boilin3 Water Reactor. This design focuses on safety and simplicity. relying on gravity and natural circulation for cooling during a
- loss of coolant situation. The reactor core is at th: bottom of the containment - !
building. A Gravity-Feed Cooling Tank, located above the core, is used to flood the core during a loss of coolant situation. This reactor is considered
.an inherently safe design which means reactor operator would have 72 hours
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to respond to a loss of coolant situation instead of 20 minutes like current reac m. Also, this response time can be lengthened by adding more water to the core.; The SBWR would produce 600 MWe and use a uranium dioxide j fuel. Pre-approval certification is targeted for 1995, with construction time ' being 30 months.
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i w , Annual Environmental Operating Report 199t Davis-Desse Nuc1 car Power Station Liquid Metal Reactor Presently, General Electric Company is designing their version of a Liquid Metal Reactor (LMR) called PRISM (Power Reactor Inherently Safe Module). The PRISM is considered walk away safe because the reactor coolant surround the core is liquid (mohen) sodium. Theoretically, the sodium would never reach its boiling point where it would boil into vapor and uncover the reactor core. The PRISM uses a three loop system to produce steara for the tur'a ine. The first loop has liquid sodium passing through the core to be heated. The sodium from the first loop goes to a heat exchanger and heats the liquid sodium in the second loop. This sodium then travels to a second heat exchanger where it converts water to steam, for mnning the turbine. By using sodium as the coolant the primary system can operate at higher temperrtures without being pressurized. Since the reactor operates at a higher temperature (11564), a thermal efficiency of 40% is achievable compared to 33% for current BWRs e.nd PWRs. A group of nice LMRs with a capacity of 155 MWe each, would form a 1345 MWe plant. The reactors are fueled with uranium-plutonium-zirconium alloy. The PRISM is a breeder reactor, which mesns it converts uranium-238 to plutonium-239. He Pu-239 would later be usd to fuel another nuclear plant. One major draw back of the PRISM is that sodium is highly reactive with air and water, but design features eliminate most of the problems. Modular High Temperature Gas-Cooled Reactor The last reactor being considered in the United States is the Moo alar High Temperature Gas-Cooled Reactor (HTGR) which uses helium as the reactor coolant. It is being designed under the cooperation of General Atomics, Gas Cooled Reactor Associates, and Electric Power Research Institute (EPRI). In the HTOR, helium heated in the reactor core passes to a heat exchanger, then back to the reactor again. In the heat exchanger, water is converted to steam to run the turbine,just as in PWRs. Since there is no possibility of phase change of reactor coolant, the system can operate at a high temperature (12684) without pressurization, allowing thermal efficiency of 40E The core of the HTGR is made of graphite blocks with vertical and horizontal holes drilled through the blocks, in the vertical holes fuel rods, containing carbon and silicon carbide coated uranium pellets and control rods are inserted. The horizontal holes allow helium to pass through and be heated before going to the heat exchangers. His design is considered walk 1-24 l
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-: away sa' fe because the fuel can withstand temperatures higher than that
- produced during a loss of coolant situation. This design calls for four 135-MWe reactors to be grouped together to from a 540 MWe plant.-
These designs are based on forty years of progressing technology and -
, operating experience. : The safety systems _are less dependent on operator
= assista'nce and outside power supplies. The sma!!er size allows them to be.
more modular and facilitate construction.- Utilities looking to increase their . power production 'oy a small amount niay find that these newer designs will allow for this. Less time invested in the licensing and construction phases
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I Annual Environmental Operating Report 1931 Davis-Besse Nuclear Power Station . Station Systems The following paragraphs describe the various systems illustrated in Figure 1-10. Major systems in the Davis-Besse Station are assigned a different color in the figure, FIGUR!' 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 (Tert iary Coolant Water) GOLD - Emergency Core Cooling System i SCARLET - Auxillary Feeriwater System GREY - Pressurizer and Associated Structures n ' ~ 1-26 I
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Annual Environmental Operating Report 1991 Davis-Iksse Nuclear Power Station Containment Building and Fission Product Release Barriers The containment building at Davis-Besse houses the reactor vessel, the pressurizer and two steam generators. The building is .:onstructed of an inner 1 inch thick steel liner or containment vessel, ar.d the shleid building with steel reinforced concrete walls 2 feet thick. He shield building protects the contair. ment vessel from a variety of environmental factors, and provides an area for a negative pressure boundary around the steel containment vessel. In the event that the integrity of the shield building is compromisert (e.g., a crack develops), this negative pressure boundary ensures that any airborne radioactive contamination present in the containment vessel is prevented from leaking out into the environment. 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 ti ie contaminated air inside the containment vessel to leak out. He free-standing containment vessel is the third in a series of barriers that prevent the release of fission products in the unlikely event of an accident. ne first barrier to the relea:,e l of fission products is the fuel cladding itself. De second barrier is the walls of the primary system, i.e. the reactor vessel, steam genecator and associated piping. The Stearn Generators The steam generators at Davis-Besse perform the same function as a boiler at a fossil-fueled power station. He steam generator uses the heat of the primary coolant inside the steam generator tubes to boil the secondary side feedwater(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, heat must also be removed from the core even after reactor shutdown in order to prevent damage to the fuel cladding. Herefore, pumps maintain a continuous flow of coolant through the reactor nd steam generator. Primary loop water (green in Figure 1-10) exits the reactor at approximately 606cF, passes ! through the steam generator, transferring some of its heat energy to the secundary loop water (blue in Figure 1-10) without ever actually coming in contact with ;t. Primary coolant water exits the steam generator at appr'..timately 5580F to be circulated back into the reactor where it is again hweu to 6060F as it passes up through the fuel assemblies. Under ordinary conuitions, water inside the primary system would boil long before it reached L such temperatures. However, it is kept under a pressure of cpproximately l 2,200 pounds-per-square-inch (psi) at all times. His preveats the water from 1 l- 1-28 l l l
Annual Environmc.ntal Operating Report 1991 Davis-Besse Nu: lear Power Station boiling and is the ruson the reactor at Davis-Besse is called a Pressurized Water Reactor. Set ndary loop water enters the base of the swam generator at approximately 4JF amt under 1100 psi pressure. At this pressure, the water can casily boil into steam as it passes over the tubes containing the primarv coolam water. Both the piimary and the secondary coolant water are considered closed loop systems. Thit means they are designed not to come in physical contact with one another. Rather, the coolant (i.e., wate;) contained in each loop transfers heat energy by the process of convection. Convection is a method of heat transfer that can occur between two fluid media. It is the same process by which radiators are used to heat homes. The water circulating inside the radiator is separated from the air (a " fluid" mulium) by the metal piping. The Turbine . Generator l The turbine, main generator, and the condenser are all housed in what is commonly referred to as the Turbine Building. The purpose of the turbine is to convert the thermal energy of the steam produced in the steam generator (referred to as main steam, red in Figure 1-10) to rotational energy of the turbine -generator shaft. The turbine at Davis-Besse is actually composed of one six- stage high pressure turbine and two seven-s.tage low pressure turbines aligned on a common shaft. A turbine stage refers to a set of blades. - Steam enters at the center of each turbine and flows outward along
- the shaft in opposite directions through each successive stage of blading. As the steam passes over the turbine blades, it loses pressure. Thus, the blades must be proportionally larger in successive stages to extract enough energy
'from the steam to rotate the shcft at the correct speed.
el - The purpose of the main generator is to convert the rotational energy of the shaft to electrical energy fc: .:ommercial usage and support of station systems. The main gencwor is composed of two parts, a stationary stator that contains coils of copper conductors, and a rotor that supplies a rotating magnetic field within the coils of the stator. Electrical current is generated in the stator portion of the main generator. From this point, the electric current passes through a series of transformers for transmission and use throughout northern Ohio. The Condenser After the spent steam in the secondary loop (blue in Figure 1-10) passes through the high and low pressure turbines, it is collected in a cavernous 1-29
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Annual Environmental Operating Report 1991 Davis.Besse Nuc1 car Power Station i l condenser several stories tall and containing more than 70,000 smail tubes. Circulating (cire) water (yellow in Figure 1-10) goes to the coming tower after passing through the tubes inside the condenser. As the steam from the low pressure turbines passes over these tubes, it is cooled and condensed. The condensed water is then purified and reheated before being citculated back into the steam generator agsin in a closed loop system. Circ water forms the third (or tertiary) and final loop of coollag water used at the Davis-Besse Station. As the primary to secondary interface, the secondary to tertiary interface is based on a closed loop design. In other words, the circulating water is able to cool the steam in the conderer, without ever actually coming in contact with it, by the process of convection. Even in t! e event of a primary to secondary leak, the water vapor exiting the Davis-Besse cooling tower would remain non-radioactive. Closed loops are an integral part of the design of any nuclear facility. This design feature greatly reduce the chance of environmental impact from station operation. The Cooling Tower The cocling tower at Davis Bes,e is easily the most noticeable and the most misunderstood, feature of the plant. The tower stands 493 feet high and the diameter of the ban is 411 feet. The two pipes circulating 480,000 gallons of water per minute to the towe are 9 feet in diameter. This is enough water to fill a swimming pool the sin of a football field 32 feet deep. The purpose of the tower h to recycle wate 1 rom the condenser by cooling it. 1 After passing through the condenser, the circulating water has warmed to approximately 1009. In order to cool the water back down ja around 700 F, the circulating water enters the cooling tower about 40 feet above the ground. Tne water is sprayed evenly over a series of baffles called f111 sheets which are suspended vertically in th'so. of the tower. A natural draft of air i, blowing up through these baffles cools the water through the process of I evaporation. The evaporated water exits the top of the cooling tower in the form of water vapor. I< As much as 10,000 gallons of water per minute are lost to the atmosphere y via the cooling tower. Even so, approximately 98 percent of the water drawn
# rom Lake Erie for station operation can be recycled through the cooling l tower for reuse. A small portion of the circulating water is discharged back l ,
to Lake Erie at essentially the same temperature it was withdrawn earlier. In ! 1991, the average difference between the intake and discharge water temperatums was only 6.27. The *!y warrner discharge water had no 1-30 l l f
Annual Environmental Operating Report 199t Davis-Besse h.br Power Station adverse environmental impact on the area of lake surrounding :he discharge point. Many power stations, both nuclear and fossil-fueled, utilize cooling towers to cool station discharge water. Federal regulations goveming the water temperature of rive s, lakes, and brys aquire that power station cperation introduce relatively small changes in water temperature. An increase in water temperature is not necessarily detrimentel to aquatic life. Fishermen usually find that the best fishing areas are in the vicinity of warm water effluents from power stations. Wum 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 aquanc organisms such as the zebra mussel. In addition, an increase in water temperature during the summer months could decrease the water's oxygen content and could therefore precipitate a fish kill. Miscellaneous Station Safety Systerns The gold system in Figure 1-10 is part of the Emergency Core Cooling dystem (ECCS) housed in the Aux 1111ary 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 fuei el: ' ding 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 Idection pumps, a core flord tank, or low pressure idection pumps. Borated water can also be sprayed from the ceiling of the containment vessel to ecol and condense any steam that may escape fiom the primar) ..ystem. The grey system illustrated in Figure 1-10 is responsible for maintaining the primary coolant water in a liquid state. It accomplishes this by adjusting the pressure inside the primary system. Heaters inside the pressurizer turn water into steam. This steam takes up more space inside the pressurizer, therefore increasing the overall pressure inside the primary system. The pressurizer is also equipped with spray heads that shovier cool water over the steam in the pressurizer. In this casa, the steam condenses and the overall pressure inside the primary system drops. The quench tank pictured in Figure 1-10 is simply where excess steam is directed and condensed for storage. The scarlet system in Figure 1-10 is part of the Auxilliary Feedwater System, a key safety system in event the main feedwater supply (blue in 1-31
i l Annual Environmental Operating Report 1991 Davis-Bewe Nuclear Power Station 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 Condensate storage Tanks. The Auxiliary Feedwater System is housed in the l'urbine Building along with the turbine, main generator, and the t.ondensu. Reactor Safety and Summary Nuclear power plants are inherently safe, not only by the laws of physicc, but by design. Nuclear power plants cannot explode like a bomb because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. Just as the battery of a flashli5ht provides enough energy to produce light, the amount of energy produced by the battery is not enough to cause an electrical shock to a person handling the flashlight. Many safety features are also equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the local environment. Javis Besse, 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 operat!on of the Station. During normal operation, the Reactor Control System regulates the power output by adjusting the position of the control rods The reactor can be automatically shut down by a separate Reactor Protectioa System that causes all the control rod assemblies to be quickly and completely inserted into the reactor core, < stopping the chain reaction. To guard agrMst the possibility of a Loss Of
- Coolant Accident, the Emergency Core Cooling System is designed to pump reserve water into the reactor automatically if the reactor coolant pressure drops below a predetermined level.
The Davis-Besse Nuclear Power Station was designee ,nstructed and operates to produce a reliable, safe, and em . onmentr '.. sound source of electricity. ) 1-32
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Davi:.-Besse Nucicar Power Station 1991 Annual Environmental Operating Report 1 Description of the Davis-Besse Site The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. . It is on the southwestern shore of Lake Erie, just north of the mouth of the Toussaint River. The site lies north and east of Ohio State Route 2, approxi. mately 10 miles northwest of Port Clin:on,7 miles north of Oak Harbor, and 25 miles east of Toledo, Ohio (Figure 1-11). Tw 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 marshlend, rich in wildlife but unsuitable for settlement and farming. During the nineteenth century, the land was cleared and drained, and has been farmed successfully since. Today, the terrain consists of farmland with marshes extending in some placer for up to two miles in-land from the Sandusky Lake Shore Ridge,
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> More than half of the Davis-Bes e site area is marshland. A small portion of the site was farmland. The marshes are part of a valuable ecological re-source, providing a breeding ground for a variety of wildlife, and a refuge for migratory birds. Majcr specien of birds using this portion of the Lake Erie marshes include mal' iros, black ducks, widgeon, egrets, grea' blue herons, blue-winged teal, and Canada geese. In fact, there are hundreds of geese liv-ing right on site. Bald eagles, osprey, swans, great horned owls, and a large number of hawks ara also seen in the area. The site includes a tract known as Navarre Marsh, which was acquired for the U.S. Bureau of Sport Fisheries and Wildlife, Department of the Interior. In 1971, Toledo Edison purchased the 188 acre Toussaint River Marsh. 'Ihe Toussaint River Marsh is contigu-ous with the 610 acre Navarre Marsh section of the Ottawa National Wildlife Refuge.
Most of the remaining marshes in the. area have been maintained by private huntir.g clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife. There are some residences along the lake shore used mainly as summer homes. However, the major resort area of the county is farther east, around Port Clinton, Lakeside, and the Bass Islands.
- j. The immediate area near Davis-Besse is sparsely populated; Ottawa County l had a populatior. of only 40,029 in the 1990 census. The nearest incorpo-rated communities are:
- Port Clinton - 10 miles southeast, populatiort 7,106
- Oak Haibor - 7 miles south, population 2,637
+ Rocky Ridge - 7 miles west southwest, population 425
- Toledo (the nearest major city)- 25 miles west, population 322,943 l
l The non-marsh areas around the Davis Besse site are used primarily for l farming. The major crops include soybeans, corn, wheat, oats, nay, fruits and vegetables. Meat and dairy animals are not major sources of income in the area. The main industries within five miles of the site are located in Erie In-dustrial Park, about four miles southeast of the Station. l The State of Ohio Department of Natural Resources operates many wildlife and recreational areas within 10 miles of the Station. These include Magee Marsh, Turtle Creek, Crane Creek State Park, and " : Ottawa National i Wildlife Refuge. Magee Marsh and Turtle Creek lie between three and six i 1-34 [.
Davis-Besse Nuclear Power Station 1W1 Annual Environmental Operating Repcrt miles WNW of the Station. Magee Marsh is a wildlife preserve allowing public fishing, natur: study, and controlled hunting in season. Turtle Creek, a wooded area at the southern end of Magee Marsh, offers boating and fish-ing. Crane Creek State Park is adjacent to Magee Marsh and is a popular pic-nicking, swimming, and fishing area. The Ottawa National Wildlife Refuge lies four to nine miles WNW of the site, immediately west of Magee Marsh. 1 35
Davis Besse Nucicar Power Sta:lon 1991 Annual Envirointental Operating Report The 1991 Summary of Radicactivity Released in Liquid and Gaseous Effluents Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the poten-tial hazards of ionizing radiation were recognized and efforts were made to establish radiation protection standards. The primary source of recommendations for radiation protection standard, within the United States is the National Council on Radiation Protection and Mer.surements (NCRP). Many of these recommendations have been given legislative authority through publication in the Code of Federal Regulations (CFR) by the Nuclear Regulatory Commission (NRQ. The main objective i a m control of radiation exposurc is to ensure that any necessary exposures are kept as low as is reasonably achievable (ALARA). ! The ALARA orinciple applies to reducing radiation exposure both to the in- j dividual working at Davis Besse and the general public. " Reasonably achie- i vable" means that exposure reduction is based on sound economic decisions and operating practices. By practicing ALARA, Davis-Besse and Centerior Energy minimize health risk and environmental detriment and ensure that doses do not exceed certain specified limits. Limits To protect the general public, guidelines and limits have been established governing the release of radioactivity in liquid and gaseous Station effluents. The Code of Federal Regulations, Title 10, Part 50, Appendix I(10CFR50, App.I) provides guidelines for the Technical Specifications which are part of the license authorizing nuclear reactor operation. Davis-Besse's Technical Specifications restrict the release of radioactivity to the environment and the resulting dose to the public. Table 1-3 presents these limits. i l-36
Davis-Besse Nuc1 car Power Station 199t Annual Environmental Operating Report Table 1-3: Dose Limits to a Member of the Public Source NRC Limits for Davis-Besse Liquid Efiluents Whole body less than or equal to 3 intem/ year Organ less than or equal to 10 mrem / year Gaseous Emuents Noble Gases gamma air dose less than or equal to 10 mrad / year beta air dose less than or equal to 20 mradiyear Iodine-131, tritium and particulates with half-lives greater than 8 days less than or equal to 15 mrem /yr The Davis-Besse limits are only a small fraction of the dose limits estab-lished by tne Environmental Protectioc Agency (EPA). In its environmental dose standard,40 CFR 190, the EPA established environmental radiation protection standards for nuclear power operations. These standards for nor-mal operation provide that the dose from all discharges of radioactivity should r 't exceed:
. 25 mrem / year to the whole body,
. 75 mrem / year to the thyroid, and
. 25 mrem / year to any other organ.
Sources of Radioactivity Released Through the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace stroats of the component and structure surfaces which have been activated are present in the primary coolant water. The three types of radioactive material released are noble gases, iodine and particulates, and tritium. The noble gas fission products in the primary coolant are giv a off as a gas when the coolant is depressurized. These gases are then collected by a sys-1-37
..__ _ __ _ __ . _ _ ._-. _ . . _ . . . . __ _ _ __. _ m_.,
- Davis-Besse Nuclear Power Station 199 Annual Environr.nental Operating Report
, tem designed for gas collection and storage for radicactive decay prior to re- -
lease. Small releases of radioactivity in liquids may occur from valves, piping or -! equipment associated with the primary coolant system. These liquids are cal-lected through a series of floor and equipment drains and sumps. All liquids of this ' nature are processed and carefully monitored prior to release. Noble gas Some of the fission products leased in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are inologi-cally and chemically nonreactive. They do not concentrate in humans or oth-er 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 radicactive noble gases released. They are readily dispersed in the at-
, mosphere.
In 1991, approximately 1160 curies of noble gases were released in gaseous effluents.' The calculated offsite gamma and beta air doses due to the release of this activity were 0.01.i mrad and 0.047 mrad, respectively, and are less
' than 0.25% of their respective Technical Specification limits. Additional dose information is provided in Table 1-4 and page 1-43.
Iodine and-ParticulateS J Annual releases of radioisotopes of iodine and particulates (with half lives greater than eight days) in gaseous and liquid effluents are small. Factors . . E- such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing systems, minimize their discharge. The predominant radioiodine released is iodine-131 with a half-
- life of approximately eight days. The main contribution of radioactive iodine L to human exposure is internal exposure of th'e thyroid gland, whue the body concentrates iodine-l' L The principal radioactive particula _tes released are fission products L (cesium-134 and cesium-137) and' activation products (cobalt-58 and cobalt 60). Radioactive cesiums and cobalts contribute to internal radiation exposure of tissues'such as the muscle, liver, and intestines. These particu.
lates are also a source of external exposure if deposited on the ground. 1-38 s M & a _'._ 'm... __~m _.1 _ . . _a', . . _ . - - 3, _,,- 7 .c ,3,_. y,_, , y
l i Davis-Ik : ) Nucicar Power Station - 1991 Annual Environmental Operating Report During 1991, the amount of radioactive iodine und particulates (excluding tritium) released was approximately 0.01 curie in gaseous effluents and 0.17 curie in liquid effluents. These releases were well below all applicable regu-latory limits.' Additional dose information is provided in T:bie 1-4 on page 1-43. Tritium
- Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in 1.iquid effluents. It is also present in gaseous effluents. Tritium is produced
- in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) present in the water aad with the boron in the primary coolant used for reactivity control of the uactor. When tritium is ingested or Inhaled it disperses throughout the body and exposes all tissues until it is eliminated.
The amount of tritium released in 1991 was approximately 64.6 curies in gas-cous effluents and 325.6 curies in liquid effluents. The associated doses were .
.well below all regulatory limits, and additional dose information is provided in Table 1-4.
Processing and. Monitoring
- Effluents are strictly controlled to ensure idioactivity released to the envi-ronment is minimal and does not exceed release limits. Effluent control in-cludes the operation of monitoring syster.ls, in-plant and environmental sampling and analysis programs, quality assurance programs for effluent and environmental programs, and procedures covering all aspects of effluent and
- environmental monitoring.
The radioactive waste treatment systems at Davis-Besse are designed to col-ilect and process the liquid and gaseous wastes which contain radioactivity.
-For example, the Waste Gas Decay Tanks are holding tanks which allow ra-dioactivity in gases to decay prior to release via the station vent.
Radioactivity monitoring systems are used to ensure that all releases are be-low regulatory limits. These instruments provide a continuous indication of the radioactivity 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 contrrst room. The alarm setpoints are low to ensure , the limits will not be exceeded. If a monitor alarms, a release from a tank is automatical', stopped. 1-39
Davis Desse Nuclear Power Station 1991- Annual Environmental Operating Report All wastes are sampled prior to release and analyzed in a laboratory to identi-fy the specific concentrations of radionuclides being released. Sampling and analysf 3 provide a more sensitive and precise mv.aod of determining effluent composition than with monitoring instruments alone. A meteorological tower is located in the southwest sector of the Station. It is linked to computers which record the meteorological data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public. - Beyond the plant, devices mait.ained in conjuction with the Radiological En-vironmental Monitoring Program constantly sample the air in the surround-ing environment. Frequent samples of other environmental media, such es water and vegetation, are also taken to determine if buildup of deposited ra-dioactivity has occurred in the area. Exposure Pathways
- Radiological exposure pathways define the methods by which people may become exposed to radioactivity. The major pathways of concern are those which could cause the highest calculated radiation dose. These pathways are determined from the type and amount of radioactivity released, the environ-
- mental transport mechanism, and the use of the environment. The environ-mental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area.- Information on the water flow, wind speed and wind direction at the time of a gaseous or liquid release is used to evaluate how the radionu-clides will be distributed in the area. An important factor in evaluating the
- exposure pathways is the use of the environment. Many factors are consid-cred 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 Figures 1-12 and 1-13. The release of radioactive gaseous effluents involves path-
- ways such as external whole body exposure, deposition of radioactive materi-al on plants, deposition on soil, inhalation by animals destined for human
' consumption, and inhalation by humans. The release of radioactive in liquid I
v t-4- -w-= w-v'-- - = 3 g
l Davis-P<sse Nuclear Power Station 199t Annual Envuonmental Operating Report effluents involves pathways such as drinking water, fish consumption, and direct exposure from .he lake at the shoreline and while swimming. l l Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure path-way which will provide, for a specific rad!onuclide, the greatest dose to a population, or to a specific group of the population, called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, or other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest frac-tion of the dose is called the eritical organ. N n.tntD DY ATMOSMER ,t.
- /i . Jy v.
nive US cumune % I" , a is / 5 Sy{gu
} A&r n
=- x j' i T f ang l
{ [ l Figure 1-12 'Ihc external exposure pathways shown here, are monitoried through the Radi-ological Environmental Monitoring Program (REMP), and are considered when calculating doses to the public. 1-41
Davis-Iksse Nuclear Power Station 1991 Annual Envuonmental Operating Report k*y a.11NNU oNSTEm o CO{AMTEM E
\
f _m_ 3 g
^
1Na._ m h r .j
' un. d $ y aN l m,wm Mu n
-mm
*N &
t av == q rua, E sw]
*TviE ,
Figure 1-13: Internal exposure pathways include tbc methods by whids radioactivity could reach people around the Station viathte foods they eat, the milk they drink, and the air they breathe. Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body radiation exposure involves the exposure of all organs. Most back-ground exposures are of this form. Both non-radioactive and radioactive ele-ments can enter the body through inhalation or ingestion. When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium col-lects in bone tissue. , The total dose to organs from a given radionuclide depends on the amount of radioactivity present in the organ and the amount of time that the radionu-clide remains in the organ. some radionuclides remain for very short times due to their rapid radioactive decay and/or elimination rate from the body, while other radionuclides may remain in the body for longer periods of time. 1-42
Dtvis-Besse Nuclear Power Station 1991 Annual Environmental Operating Report The dose to people in the area surrounding Davis-Besse is calculated for each
-liquid or gaseous release. The dose due to radioactivity released in gaseous effluents is calculated using factors such as the amount of radioactivity re-leased, the concentration of radioactivity beyond the site boundary, the weather conditions at the time of the release, the locations of exposure path-ways (cow milk, goat milk, vegetable gardens, and residences), and usage factors (inhalation, food consumption). The dose due to radioactivity re-leased in liquid effluents is calculated using factors such as the tota volume
. of radioactive liquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption, shoreline and swimming fac-tors). These calculations produce a conservative estimstion of the dose.
ReSuitS The results of the effluent monitoring program are reported to the Nuclear Regulatory Commission in the Semiannual Radioactive Effluent and Waste Disposal Report. For 1991, the doses from radioactivity released in gaseous and liquid eftluents were a small fraction of the Davis-Besse Technical Specifications limits. The offsite whole body d( te due to radioactivity re-leased in liquid effluents was approximately 2.3% of the annual Technical Specifications limits. The offsite gr.mma and beta air doses due to radioac-tivity released in gaseous effluents were smaller; each was less than 0.39% of the annual Technical Specifications limits. Table 1-4 suinmarizes the dose due to radioactivity released in efDuents in 1991. Table 1-4 Annual Doses to the Public Due to Radioactivity Released in Gaseous and Liquid Eftuents - 1991 Annual- Percent Dese Limit of Limit Liquid Effluents Whole Body 0.07 mrem 3 mrem 2.3% Organ (GI-LLI) 0.11 mrem 10 mrem 1.1% Gaseous Effluents Gamma air dose 0.015 mrad 10 mrad 0.15 % Beta air dose 0.047 mrad . 20 mrad 0.24 % Iodinee131, tritium and particulates with half-lives greater than 8 days - 0.06 mrem - 15 mrem 0.40 % r:- 1-43
- +
- , .r- - - , w ,# , - - . 7 - m
a. Davis-B%se Nuclear 6 cr Station 1991 Annual Environmental Operating Report References
- 1. "A Citizen's Guide to Pedon: What It is and What to da About It", United States Environmental Protection Agency, United States Department of Health Services, Centers for Disease Control (August 1986).
- 2. " Basic Radiation Protection Criteria", Report No. 39, National Council on Radiation Protection and Measurement, Wasnington, D.C. (January 1971).
- 3. "Cesit.m-137 from the Environment to Man: Metabolism and Dose", Re-port No. 52, National Council on Radiation Protection and Measerements, Washingto. , D.C. (January 1977).
- 4. Deutch, R., " Nuclear Power, A Rational Approach", fourth edition. GP Courseware, Inc., Columble, MD. (1987).
- 3. Eisenbud, M., " Environmental Radioactivity", Academic Press, Inc., Or-lando, FL (1987).
- 6. " Environmental Radiation Measurements", Repoit No. 50, National Coun-cil on Radiation Protection and Measurements, Washington, D.C. (December 1976).
- 7. " Exposure of the Population in the United States and Canada from Natural Background Radiation", Report No. 94, National Council on Radiation Protection and Measurements, Washington, D.C. (Decembcr 1987).
- 8. Fisher. Arthur, "New Generation Nuclear Reactors; Dare We Puild Them?," Popular Science, (April 1990) pp. 68-77,112-114.
- 9. Gola: ",icheal W., and Todreas, Neil E., " .dvanced Light-Water Reac-tors," s Gatific American,(April 1990) pp. 82-89.
- 10. " Health Effects of Exposure to 1.ow Levels of Ionizing Radiation: BEIR V", Committee on the Biological Effects ofIonizing Radiations, Board on Radiation Effects Research Commission on Life Sciences, National Research Council. National Academy Preza, Washington, D.C. (1990).
1-44
1 1 , 4 Davis.Bea Nuc! car Power Station 1991 Annual Environmental Opernung Report
- 11. Hendee, William R., and Doege, Theodore C, " Origin and Health Risks l of Indoor Radon", Seminars in Nuclear Medicine, Vol. XVIII, No.1, Ameri- !
canMedical Association, Chicago,IL (January 1987). ; 1
- 12. Hurley, P., "Living with Nuclear Radiation", University of Michigan Press, Ann Arbor, MI. (1982).
- 13. " Indoor Air Quality Environmental Information Handbook: Radon", pre-pared for the United States Department of Energy, Assistant Secretar ; for Environment, Safety and Health, by Mueller Associates, Inc., Baltimore, MD. (January 1986).
- 14. " Ionizing Radiation Exposure of the Population of the United States", Re-port No. 93, National Council on Radiation Protection and Measurements,
' Washington, D.C (September 1987).
- 15. Miller, Peter. "Our Electric Future," Naticanal Geographic, Vol.180 (August 1991) pp. 60-89.
- 16. " Natural Background Radiation in the United States", Report No. 45, Na-tional Council on Radiation Protection end Measurements, Washington, D.C (November 1975).
.17. " Nuclear Energy Emerges from 1980's Poised for New Growth", U.S.
' Council for Energy Awareness, Washington, D.C. (1989).
- 18. " Nuclear Power: Answers to Your Questions", Edison Electric Institute, Washington, D.C (1981).
- 19. " Nuclear Power: Answers to Your Question; " Edison Electric Institute, .
Washington, D.C (1987).
- 20. "Public Radiation Exposure from Nuclear Power Generation in the United States", Report No. 92, National Council on Radiation Protection and Measurements, Washington, D.C (December 1987).
- 21. "Rediation Protection Standards", Department of Environmental Science and Physiology and the Of5ce of Continuing Education, Harvard School of Public Hecith, Boston, MA. (July 1989).
- 22. _" Radon in Buildings: Sources, Biological Effects, Monitoring and Con-trol", caurse notes form the Advanced Wmkshop on Occupational and Envi-1 45
I Davis-Besse Nuclear Power Station 199t Annual Emimnrnental Operating Rc;xvt 1 l ronmental Radiation Protection, Office of Continuing Education, Harvard l School of Public Health, Boston, MA. (July 1989).
- 23. " Removal of Radon from Household Water", United S;ates Environmen-tal Pratection Agency, Washington, D.C (September 1987).
- 24. "1985 Radiological Environmental Monitoring Report for Three Mile Is-land Station", GPU Nuclear Corporation, Middletown, PA (1985).
- 25. " Sources, Effects and Risks of lonizing Radiation", United Nations Scientific Committee on the Effects of Atomic Radiation,1988 Report to the General Assembly, United Nations, New York (1988).
- 26. " Standards for Protection Against Radiation", Title 10, Pa t 20, Code of Federal Regulation, Wachington, D.C (1988).
- 27. " Domestic Licensing of Production and Utilization Facilities", Title 10 Part 50, Code of Federal Regulations, Washington, D.C. (1988)
- 28. " Environmental Radiation Protection Standard for Nuclear Power Opera-tions", Title 40, Part 190, Code of Federal Regulations, Washington, D.C.
(1988).
- 29. " Tritium in the Enviranment", Report No. 62, National Council on Radi.
ation Protection and Measurement, Washington, D.C. (Maich 1979). l f l i 1-46
i Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Report Radiological Emironmental Monitoring Program . ._ Introduction The Radiological Environmentzt Mo titoring Program (REMP) was established at Davis-Besse for several reasons: to provide a supplementary check on the adequacy of containment and effluent controls, to assess the radi-ological impact, if any, that Station operation has on the surrounding area, and to determine compliance with applicable radiation protection guides and stan-dards. Environmental surveillance has been a part of the radiological pro-grams for approximately 20 years. The Radiological Environmental Monitoring Program was established in 1972, five years before the Stat!on be-came operational. This preoperational surveillance program was estab-lished to describe and quantify the radioactivity, and its variability, in the area prior to commerical operation. When Davis-Besse became operational in 1977, the REMP continued to measure radiation and radioactivity in the sur-rounding areas. The operational surveillance program has been collecting environmental data for over 14 years. A wide variety of environmenal samples are collected as p.ttt of the REMP. " The selection of sample types is based on the established critical pathways for the transfer of radionuclides through the environment to humans. The selec-tion of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population characteristics, and land usage in the area of interest. The selection of sampling frequencies for the various environmental media i based on the radionuclides of interest, their re-spective balf-lives, and their neaavior in both the biological and physical envi-ronments. A description of the Radiological Environmental Monitoring Program is pro-vided in the following section. In addition, a brief history of analytical results fo. each sample type collected since 1972, and a more detailed summary of the analyses performed in 1991, are also provided. 2-1
Davis-Besse Nuclear Power Station 199t Annual Environmental Operating Report Preoperational Surveillance Program All nuclear facilities are required by the federal govemment to conduct radi-ological environmental monitoring prior to constructing the facility. This pre-operational surveillance program should be aimed at collecting the data needed to identify critical pathways, including selection of the radioisotope and sam-ple media combinations to be included in the surveillar.cc program conducted : after facility operation begins. Radiochemical analyses performed on the envi-ronmental samples should include not only those nuclides expected to be re. leased during facility operation, but should also include typical fallout radionuclides and natural background radioactivity. All environmental media with a potential to be affected by facility operation, as well as those media di-rectly in the critical pathways, should be sampled on at least an annual basis during the preoperational phase of the environmental surveillance program. The preoperational surveillance design, including nuclide/ media combinations, sampling frequencies an;l locations, collection techniques, and radioanalyses performed, should be carefully considered and incorponited in the design of the operational surveillance program. In this manner, data can be compared in a variety of ways (for example: from year to year, location to location, etc.), in order to detect any radiological impact the facility has on the surrounding en-vironment. Total 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 charac-teristics of the local environment. The environmental surveillance program at Davis-Besse will continue well after the Station has reached the end of its eco-nomically useful life and decommissioning has begun. Such a rigorous, long term environmental surveillance program provides a measure ofinsurance that any radiological impact the operation of Davis-Besse has had on the surround ~ ing environment, is detected to preserve the integrity of the local environment. Operational Surveillance Program Objectives The operational phase of the environmental surveillance program at Davis-Besse. was designed with the following objectives in mind: 2-2
1 l Davis Besse Lclear Power Station 1991 Annual Environtantal Operming Rep >rt i to fulfill the obligations of the radiological surveillance sections of the ! Stations Technical Specifications. l to determine whether any significant increase occurs in the concentration of radionuclides in critical pathways, to identify and evaluate the buildup, if any, of radioactivity in the local environment, or any changes in normal background radioactivity, and to verify the adequacy of Station controls for the release of radioactivity. Quality Assurance An important part of the environmental monitoring program at Davis Besse is the Quality Assurance (OA) Program. OA consists of all the planned and systematic actions that are necessary to provide adequate confidence in the re-sults of an activity such as the REMP. OA is a rmgram which checks the ade-quacy and validity of the monitoring program through routine audits, strict adherence to written policies and procedures, and attention to good record-keeping practices. The OA program at Davis-Besse is conducted in accordance with the guide-lines specified in NRC Regulatory Guide 4.15. " Quality Assurance for Radi-ological Monitoring Programs." The OA program is designed to identify pos-sible deficiencies in the REMP so that corrective actions can be initiated promptly. Davis-Besse's Quality Assurance program also provides confidence in the results of the REMP through: performing regular audits (investigations) of the REMP, including a care-fut examination of sample collection techniques and record keeping, 1 performing audits of contractor laboratories which analyze the environ-mental samples, requiring analytical contractor laboratories to participate in the United States Eevironmental Protection Agency Cross-Check Program, requiring analytical contractor laboratories to split samples for separate l analysis dollowed by a comparison of results, splitting samples prior to analysis by independent laboratories, and then l comparing the results for agreement, and finally, 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 l 2-3
- -. - -. - . - - . . . _ . . - ~ - . . - .
I Davis.Besse Nuclear Power Station tWl Annual Environmental Operating Report addition, the NRC and the Ohio Department of Health (ODii) also perform independent environmental monitoring in the vicinity of Davis-Besse. The types of samples collected and the sampling locations used by the NRC and ODH were incorporated ir Davis-Besse's REMP Hence, the analytical results from the different programs can be compared. This practice of comparing re-suits from identical samples, collected and analyzed by different parties, pro-vides a valuable QA 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 quality control samples, were collected at several locations. These duplicate e samples were assigned different identification numbers than the numbers as. signed to the routine samples. This ensured the analyticallaWry would not know the samples were identical. The laboratory results e analyses of the quality control samples and the routine samples could then ve compared for agreement- Quality control sampling has become an important part of the REMP since 1987, providing 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 possi-ble, and to ensure the contractor laboratory has no way of correctly pairing a quality control sample with its routine sample counterpart. Program Description Overview The Radiological Environmental Monitoring Program at Davis-Besse consists of the collection and analysis of a wide variety of environmental samples. . Samples are collected on a routine basis either weekly, monthly, quarterly, semiannually, or annually, depending upon the sample type and nature of the radionuclides of interest. Environmental samples collected by Davis-Besse personnel are divided into four general categories: stmospheric -- including samples of airborne particulates and airborne radiciodine, terrestrial -- including samples of milk, groundwater, broad leaf vegeta-tion, fruit, animal / wildlife feed, soil, and wild and domestic meat, aquatic - . including samples of treated and untreated surface water, fish, and suoreline sediments, 2-4
Davis Bese Nuclear Power Station 1991 Annual Environmental Operating Rep >n direct radiation - measured by thermoluminescent dosimeters. All envi-ronmental samples are labeled using a sampling code. Table 21 provides the sample codes and collection frequency for each sample type. Table 2-1: Sample Codes and Collection Frequencies Sample Type Sample Collection Code Frequency Airborne Particulate AP Weekly Airborne lodine Al Weekly inermoluminescent TLD Quarterly, Annually Dosimeter Milk MIL Monthly (semi-monthly during grazing season) Groundwater GW Quanerly Broad Leaf Vegetation BLV/ Monthly (July-September) and Fruits FRU Surface Water - Treated SWT Weekly Surface Water - Untreated SWU Weekly Fish FIS Semiannually
- Shoreline Sediments SED Semiannually Soil SOI Semiannually Animal / Wildlife Feed AF Semiannur'ly Meat-Domestic Me(D) Annually Meat-Wild Me(W) Annually
- 2-5 l
Devts-Desse Nuclear Power Stauon 1o91 Annual Environmental Operating Report Sample Analysis When environmental samples are analyzed for radioactivity, several types of measurements may be performed to provide information about the types of radiation and radionuclides present. De major analyses that are perfomied on environmental samples collected for the Davis-Besse REMP include: Gross beta analysis Gamma spectral analysis Tritium analysis Strontium analysis 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 radio- , nuclides. Since beta decay gives a continuous energy spectrum rather than the discrete lines or " peaks" associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal con-centrations of beta emitting radioactivity; it does not identify specific radionu- ! clides. Gross beta analysis merely acts as a tool to identify samples that may require further analysis. Gamma spectral analysis provides more spec'fic information than does gross beta analysis. Gamma spectral analysis identifies each radionuclide present in the sample that emits gamma radiation and the amount of radiccctivity emitted by each. Each radionuclide has a very specific *fingerpri'it" that allows for swift and accurate identification. For example, gamma spectral analysis can
- be used to identify the presence and amount of iodine-131 in a sample.
L Iodine-131 is a man made radioactive isotope ofiodine that may be present in j the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power sta-tions. Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the amount of radioactivity present as a result. As discussed in Chapter One, tritium is an isotope of hydrogen that emits low energy beta par-ticles. Strontium analysis identifies the presence and amount of strontium-89 and strontium-90 in a sample. These man-made radionuclides are found in the en-l 2-6
Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Report vironment 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 incorpo-rated in bone tissue. The principal strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from gaseous re-leases. Gamma Doses received by thermoluminescent dosimeters while in the field are read by a special laboratory procedure that is more thoroughly discussed on page 2-11. Table 2-2 provides a listing of the types of analyses performed on environmen-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 sample activity which can be detected with a reasonable degree of confi-dence at a predetermined level. When a measurement of radioactivity is re-ported as less than LLD (<LLD), it means that the radioactivity is so low that it cannot be accurately measured by that particular method for an individual 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 analysis are compared with results from other locations and from earlier years. Generally, the results of sample analyses are compared with preoperational and operational data. Additionally, the results of indicator and control locations are also compared. This allows REMP personnel to track and trend the radioactivity present in the environment, to assess whether a buildup of radionuclides is occurring and to determine the effects, if any, the operation of Davis-Besse is having on the en-vironment. If any unusual radioactivity is detected, it is investigated to deter. mine whether it is attributable to the operation of Davis-Bev.e, or to some other source such as nuclear weapons testing. A summary of the REMP sam-I pie analyses performed from 1972 to 1991 is provided in the following sec-l tion. l 27 l
Davis-Besse Nuclear Power Station 19)! Annual Environmental Operating Re;urt Table 2-2: Radiochemical Analyses Performed on REMP Samples Sample Type - Analyses Performed ATMOSPHERIC MONITORING Airborne Paniculates Gross Beta Gamma Spectral Strontium 49 Strontium-90 Airborne Radiciodine Iodine-131 TERRESTRIAL MONITORING Milk Gamma Spectral Iodine-131 Strontium 89 Strontium-90 Stable Calcium Stable Potassium Groundwater Gross Beta Gamma Spectral Tritium Strontium-89 Strontium 90
) '
Broad Leaf Vegetation and Fruits Gamma Spectral Iodine-131 Strontium-89 Strontium-90 Animal / Wildlife Feed Gamma Spectral Soil Gamma Spectral Wild and Domestic Meat Gamma Spectral t 2-8 l
Davis-Besse Nuc! car Power Station 1991 Annual Environmental Operating Regurt Table 2-2: Radiochemical Analyses Performed On REMP Samples Sample Type Analyses Performed AQUATIC MONITORING Untreated Surface Water Gross Beta Gamma Spectral Tritium Strontium-89 Strontium 90 Treated Surface Water Gross Beta Comma Spectral Tritium Strontium-89 Strontium-90 lodine-131 Fish Gross Beta Gamma Spectral I Shoreline Sediments Gamma Spectral DIRECT RADIATION MONITORING Thermoluminescent Dosimeters Gamma Dose l I Atmospheric Monitoring
- Airborne Particulates: N - radioactive particulates have been detected as a result of Davis-Besse's operation. Only natural and fallout radioactivity from nuclear weapons testing and the 1986 nuclear accident at Chernobyl have been detected.
Airborne Radiolodine: Radioactive iodine-131 fallout was detected la 1976,1977, and 1978 from nuclear weapons testing, and in 1986 (0.12 to 1.2 picoeuries per cubic meter) from the nuclear accident at Chemobyl. 2-9
I I Davis Besse Nuclear Power Station 1991 Annual Environmental Operating Repin l l Terrestrial Monitoring: Groundw ater: Only naturally occurring background radioactivity has been detected in groundwater. Mllk: Iodine-131 from nuclear weapons testing fallout was detected in 1976 and 1977 at concentrations of 1.36 and 23.9 picoeuries/ liter respec- , tively. In 1986. concentrations of 8.5 picocuries/ liter were detected from the nuclear accident at Chemobyl. No iodine 131 detected has been at. tributable to the operation of Davis Besse. Domestic and Wild Meat: Only naturally occurring potassium-40 and very low cesium-137 activity have 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 nu. clear weapons testing. Broad Leaf Vegetation and Fruits: Only natural background radioactiv-ity and radioactivity from nuclear weapons testing have been detected. Soll: Only natural background radioactivity and radioactivity from nu-clear weapons testing and the 1986 nuclear accident at Chernobyl have been detected. Animal / Wildlife Feed: Only ' ural background radioactivity and radio-activity from weapons testing h ve been detected. Aquatic Monitoring
. Surface Water (Trsated and Untreated): In 1979 and 1980, the tritium concentrations at location T-7 were above normal background. Location T-7 is a beach well fed directly by Lake Erie. The fourth quarter sample in 1979 read 590 picocuries per liter, and the first quarter sample in 1980 had a concentration of 510 picocuries per liter compared with the normal background concentration of 450 picocuria per liter. A follow up sam-ple 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 attribu;ed to the op-eration of Davis-Besse. Even so, the results at T-7 were more than 39 times lower that 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 of 3,000,000 picocuries per liter) for tritium in unrestricted areas. The follow-up sample was less than 0.1% of the MPC. None of the subse-2 10
Davis-Besse Nuclear Power Station t991 Annual En ironmental Operating Rcport quent samples indicate any significant difference between the background tritium concentration and the concentration at T-7. Fish: Only natural background radioactivity and radioactivity from nu-clear testing have been detected. Shoreline Sediments: Only natural background radioactivity and radio-activity from nuclear testing and the 1986 nuclear accident at Chernobyl have been detected. Di!ect Radiatica Monitoring: Thermoluminescent Dosimeters (FLDs): ne annual average gamma dose rates recorded by TLDs have ranged from 42 to 87 millirems _ per year at control locations and between 36.8 and 86.1 millirems per year at indicator locations. No increase above natural background radiation at-tributable to the operation of Davis Besse has been observed. 1991 Sampling Program The Radiological Environmental Monitoring Program (REMP)is conducted in accordance with the Davis-Besse Nuclear Power Station Operatmg License, Appendix A. Technical Specifications. The program includes the collection and analysis of airbome particulates, airbome radiciodine, groundwater, milk, eggs, domestic and wild meat, fruits and broad leaf vegetation, soil, treated and untreated surface water, fish, shoreline sediments, and measurements of direct radiation (refer to Table 2 3). 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 implement a more comprehensive REMP, the number of samples collected and analyzed was selectively increased. 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 efforts, over 2600 samples were col-lected during 1991. Of these samples collected, only 337o were required to satisfy regulatory requirements or Technical Specification. In addition, of the 143 sampling locations utilized in 1991,14c7c were quality control locations. j 2-11 i l l
s Davis-Desse Nuclear Power Station 1991 Annual Environmental Operating Reprt Table 2-3: Sample Collection Summary Sample Collection Number Number of Number of Type Type'/ of Samples Samples (Remarks) Frequency"Imations Collected Missed ATMOSPilERIC Autrrne Particulates C/W 10 520 0 Airtiorne Radiciodine C/W 10 520 0 TERRL5 TRIAL Milk (May-Oct.) G/GM 4 36 0 (Nov..Apr.) G/M 4 19 0 Groundwater G/O 5 19 1 Edrole Meat wild G/A 1 0 domestic G/A 2 2 0 Broad I.caf Vegetation / Fruit G!M 5 22 0 Soil G/S 11 22 0 Animal / Wildlife Feed G/A 6 10 0 AQUATIC Treated Surface - Water G/WM 7 362 2 Untreated Surface Water G/Wm 16 Comp /WM 5 260 0 Fish (3 species) G/SA 2 6 6 Shoreline Sediments G/SA 7 15 0 i DIRECT RADIA'llON Thermoluminescent Dosimeters C/O 111 435 9 C/A 111 105 6 l.
- Type of Collection:
l l C/ = Continuous; G/ = Grab; Comp / = Composite.
" Frequency of Collection:
/WM = Weekly composited Monthly; /W = Weekly
[ /SM = Semimonthly; /M = Monthly;
/Q = Quanerly; /SA = Semiannually; /A = Annually l
2-12
Davis-Besse Nuclear Power Station -1991 Annual Environrnental Operating Repon 1991 Program Deviations Provided below is a description and explanation of 1991 environmental sample collection deviations.
- A composite sample of T 12 untreated surface water could not be col-lected on 1-14 91 because lines leading to compositor were frozen. A grab sample was substituted in place of the composite sample.
Treated surface water samples at T-144 were unavailable on January 28, and March 14,1091 because the waterline to tnat faucet was frozen.
- There were no data for TLD locations T 91, T-114, T-203 and T 204 for first quarter 1991. TLDs were lost due to vandalism.
TLD locations, T-78 and T-79 were eliminated from the sampling pro-gram. The T-23 groundwater sample for first Quarter 1991 was unavailable from the Put In-Bay Water Treatment Plant because their well is sealed up during the winter months. Precipitation / snow samples were eliminated from the 1991 sampling program.
- The treated surface water sample at T 28 for week of March 19,1991 was inadvertently discarded. A grab sample was collected as a substitute for the lost sample.
There was tio TLD for location T-116 second quarter 1991. The TLD was lost due to vandalism. T 12 composite of untreated surface water for week of May 20,1991 was not collected. The water sample container was damaged after collection of composite, the sample leaked out of the container while in transit from the intake crib back to the Toledo Water Treatment Plant Lab. A grab sample was collected as a substitute.
- There were no data for TLD locations T-93,T-203, and T-204 for third quarter 1991. TLDs lost due to vandalism.
Ne fish samples were collected during october 1991 because desired fish species were unavailable.
- There were no data for TLD locations T-202 and T-204 for fourth quarter 1991. TLDs lost due to vandalism.
The annual 1991 TLD for T-108 was lost in transit from field to laboratory. 2 13
I l i l Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Report The annual 1991 TLD for T-108 was lost in transit from field to laboratory. 1
- There were no data for Annual TLDs at T-6, T 91, T 97, T-Il4, T 202, l and T-203, these being TLDs lost due to vandalism.
Sampling 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 w hich would be most likely to display the effects caused by the operation of Davis- 1 Besse. Generally, they are located within five miles of the station. Control j locations are those which should be unaffected by Station operations and are l typically, more than five miles away. Data obtained from the indicator loca- 1 tions are compared with data from the control locations. This comparison al- 1 lows REMP personnel to take into account naturally occurring background radiation, or fallout from weapons testing in evaluating any radiological im-pact Davis-Besse has cn the surrounding environment. Data from indicator and control locations are also compared with preoperational data to determine whether significant variations or trends exist. Atmospheric Monitoring Air Samples Environmental air sampling is conducted to detect any increase in the con-centration of airborne radionuclides that may be inhaled by humans, or serve as an external radiation source. Inhled radionuclides may be absorbed from the lung, gastrointestinal tract, ot from the skin. Air samples collected by the REMP include both airborne particulates and airborne radiolodine. Air sampling pumps are used to draw continuous samples through particulate membrane filters and charcoal cartridges at a rate of approximately one cubic foot per minute. De samples are collected on a weekly basis. Airborne particulate samples are collected on 47 mm diameter membrane fil-ters. Charcoal cartridges are installed downstream of the particulate '"Mrs to sample for the presence of airborne radiciodine. The airbome samples are sent to a contractor laboratory for analysis. At the laboratory, the airborne par-ticulate filters are stored for 72 hours before they are analyzed to allow for the decay of naturally occurring short lived radionuclides. However, due to the short half-life of iodine-131 (approximately eight days), the airborne radicio-dine cartridges are analyzed upon receipt by the contractor laboratory. 2-14
. _._ m . -- ,_.
Davis Besse Nuclear Power Station _ 1901 Annual Environmental Operating Report Airborne Particulates Davis-Besse samples air for airbome radioactivity continuously at ten loca-tions. There are six indicator locations including four around the site bound-ary, one at Sand Beach, and another at a local faim. There are four control , locations, Oak Harbor, Port Clinton, Toledo and Magee Marsh. Gross beta analysis is performed on each of the weekly samples. Each quarter, the filters from each location are combined (composited) and analyzed for gamma emitting radionuclides. The gross beta analyses yield an annual aver-age of .021 pCi/miat indicator locations and .022 pCi/m2 at control locations for 1991. Evidence of the similarity of results of control .nd indicator loca-tions may be seen in the average monthly results shown in Fig 2-1. The n!sh-est annual average (.023 pCi/m)) was detected at the Toledo location. The 1991 annual average was .021 pCi/m2 which is similar to previous years. Beryllium-7 was the only gamma emitting radionuclide detected by the gamma spectroscopic analyses of the quarterly composites. Beryllium 7 is a naturally occurring radionuclide produced in the upper atmosphere by cov ic radiation. No other radionuclides were detected above their respective Lt.lr 1991 Air Particulates Gross Beta pCl/m3 0.04 0.03 - - - - - - - - - -- cf 0.02 - -- \ q -- 041 - - - - ~ - - - - - - - - ' - - -- - ' ~ ' ' ' 't ' ' ' '- ' 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec
+ Indicator --*- C on t rol Figure 2-1: Concentration of Beta emitting radionuclaies in aistome particulate samples were essentially identical at indicator and courol kw;ations.
2-15
. - - .. .-. . ~.- . . Davis Besse Nuclear Power Station 1991 Annual Environmental Operating Rep >rt Airborne lodine-131 Airborne iodine-131 samples are collected at the same ten locations and with the same samplers as the airborne particulate filters to sample fc,r the presence of airborne radiciodine. These cartridges are collected weekly, sealed in separate collection bags and sent to the laboratory for gamma spectral analysis. In all of the samples collected in 1991, there was no detectable iodine-131 above the LLD of 0.07 pCi/m2 Table 2-4: Air Monitoring Locations Sample Location Type of Location Description Number Location T-1 I Site boundary,0.6 mile ENE of Station T-2 I Site boundary,0.9 mile E of Station T-3 I Site boundary,1.4 miles ESE of Station T-4 I Site boundary,0.8 mile S of Station T-7 I Sand Beach, main entrance,0.9 mile NW of Station T-8 1 Earl Moore Farm,2.7 miles WSW of Station Ta C Oak Harbor Substation,6.8 miles SW of Station T-11 C Port Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station
-T-27. C Crane Creek State Park,5.3 miles WNW of Station. 'I = Indicator C = Control 2 16
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Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Repon TERRESTRIAL MONITORING The collection and analyses of groundwater, milk, meat, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be in-gested by humans. Animal and wildlife feed samples provide additional in-formation on radionuclides that may be present in the food chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere. Many radionuclides are present in the environment due to sources such as cos-mic radiation and fallout from nuclear weapons testing. Some of the radionu-clides present are: tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere and as a result of routine releases from nuclear facili-ties. beryllium 7, present as a result of the interaction of cosmic radiation with the upper atmosphere. cesium-137, a man-made radionuclide which has been deposited in the environment, (fer example, in surface soils), as a result of fallout from nuclear weapons testing and routine releases from nuclear facilities potassium 40, a naturally occurring radionuclide normally found in hu-mans and throughout the environment.. fallout radionuclides which come from nuclear weapons testing, including strontium-89, strontium 90, cesium 134, cerium-141, cerium-144, ruthenium-103. These radionuclides may also be released in minute amounts from nuclear facilities. The radionuclides listed above are expected to be present in many of he envi-L ronmental samples collected in the vicinity of Davis Besse. The contribution i of radionuclides from the plant operation is assessed by comparing sample re-sults with preoperational data, operational data from previous years, control location data, and the types and amounts of radioactivity normally released from the Station in liquid and gaseous effluents. l l 2-20
Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Repon Milk sampling is very important in environmental surveillance because it pro-vides a direct basis for assessing the build up of radionuclides in the environ-ment that may be ingested by human. Milk is particularly important because it is one of the few foods commonly consumed soon after production. The milk pathway involves the deposition of radionuclides from atmospheric releases onto forage consumed by cows. The radionuclides present in the forage eating cow become incorporated into the milk which is then consumed by humans. Samples of milk are collected at three farms i.nd a commercial dairy store once a month from November through April, and twice a month from May through October. Sampling is increased in the summer when the herds are usually out-side on pasture and not on stored feed. The sample locations consist of one indicator and three control locations. The milk samples are analyzed for strontium-89, strontium-90, iodine-131 and other gamma emitting radionuclides. stable calcium and potassium. A total of 55 milk samples were collected in 1991. Strontium-89 was not detected above the LLD of 1.1 pCi/l in any of the sam-ples. Strontium-90 activity was detected in 54 of the 55 samples collected and , ranget from 0.5 to 2.1 pC/1. The annual average concentration of strontium-90 was 0.99 pCi/l at the indicator locations and 1.21 pCi/l at the control locations. For all sample sites, the annual average concentration were simiNr to those i measured in the previous years (Fig 2 5). A total of 55 analyses for iodine-131 in milk were perfomied during 1991. Iodine 131 was not detected in milk samples above the LLD of 0.4 pCi/L The concentrations of barium-140 and cesium-137 were below their respective LLDs in all samples collectea. The results for potassium-40, a naturally oc-curring radionuclide, were similar at indicator and control locations, as is to be expected. Since the chemistries of calcium and strontium, and potassium and cesiums are similar, organisms tend to deposit strontium radioisotopes in bones, and ce-sium radioisotopes in muscle tissue. In order to detect the potential environ-mental accumulation of these radionuclides, the ratios of the strontium radioisotopes radioactivity (pCi/l) to the concentration of calcium (g/l), and cesium radioisotopes radioactivity (pCi/l) to the concentration of potassium (g/l) were monitored in milk. These ratios are compared to standard values to determine if build up is occurring. No statistically significant variations in the ratios were observed. The results of the analyses performed on he milk sam-pies collected in 1991 indicate no effect due to the operation of Davis-Besse. 2-21
Davis-Besw Nuclear Power Station 1991 Annual Environmental Operating Repon ratios were observed. The results of the analyses performed on he milk sam-pies collected in 1991 indicate no effect due to the operation of Davis Besse. MILK CONCENTRATION OF SR-90 0C1/1
$2---7h-------b-77 78 79 80 81 82 83 84 8'a 86 87 88 89 90 91 YEAR E Indicator E control l Figure 2 5:The 1991 average concentration of strontium W detected, in milk sunples, I were similar at indicator and cnn*rol locations; a trend exhibited in previous years.
Table 2-5: Milk Monitoring Locations Sample Location Type of Location Description Number Location T-8 I Moore Farm,2.7 miles WSW of Station l T-24 C Toft Dairy, Sandusky,21.0 miles SE of Station T-57 C Meek Farm,22.0 miles SSE of Station l-T-199 C Ewing Farm 6.5 miles SW of Station
- I = indicator C = control 2 22
Davis-Bev.c Nuclear Pow er Station 1991 Annual Fnvtronrnental Op rating Reput Groundwater Samples It is unlikely that groundwater will accumulate radioactivity from nuclear faci-lities, except for those facilities which discharge liquid effluents to the ground via cribs, pits, or trenches. This is because the soil acts as a filter and an ion exchange medium for most radionuclides, flowever, tritium and other radio-nuclides such as ruthenium 106 have a potential to seep through the soil into the groundwater. A;though Davis-Besse does not discharge its liquid effluents directly to the ground, samples from local wells are collected on a quarterly basis to ensure the detection of any adverse impact on the local groundwater supplies due to Station operation. The four wells sampled include two indica-tor locations, and two control locations. In addition, a quality control sample-is collected at one of the four wells each quarter. T. e groundwater samples are analyzed for beta emitting radioactivity in dis-solved and suspended solids, tritium, strontium-89, strontium 90 and gamma emitting radionuclides. Beta emitting radionuclides concentration in suspended solids were not de-tected above LLD of 0.b pCill. In dissolved solids, the concentration averaged 3.0 pCill at indicator locations and 2.0 pCi/l at control locations. Tritium was not detected in any sample above the LLD of 330 pCi/1. Also, strontium-89 was not detected above the LLD of 1.5 pri/1. Strontium-90 was detected in two indicator samples at an average of 0.8 pCill. There were no gamma emitting radionuclides detected in any of the samples collected. All sample analyses were within normal ranges and were similar to results of pre-vious years. Tabic 2-6: Groundwater Monitoring Locations - Sample Location Type of Location Description Number Location T-7 I Sand Beach,0.9 mile NW of Station T-23 C Put-in-Bay Waterworks,14.3 miles ENE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station l 2s23
Davis-Dest.c ! /uclear Power Station 1991 Annual Environmental Operating Report Tablei-6: Groundwater Monitodng Locations can't Sample Location Type of Location Description NumNr Location
'I M4 I Weis Farm,4.8 miles SW of Station l T-141 OC Roving Site l
- I = indiuwr C = control QC = quality control Broad Leaf Vegetation and Fruit Samples 1 l
Fruits and broad leaf vegetation also represent a direct pathway to humans from ingestion. Fruits and broad leaf vegetation may become contaminated from atmospheric deposition from airborne sources (nuclear weapons fallout or gaseous releases form nuclear facilities) or form irrigation water drawn from lake water receiving liquid effluents (from hospitals, nuclear facilities, etc.). Also, radionuclides from the soil may be absorbed by the roots of the plants and become incorporated into the edible portions. During the growing season (July through September) edible broad leaf vegetation and fruits are collected from farms in the vicinity of Davis-Besse. In 1991, broad leaf vegetation samples were col 4 . 't two indicator loca. tions and one control location. Fruit samples were . - ned at two indicator locations and three control locations. Broad leaf vegeuttion was collected once a month during the growing season and consisted of lettuce, cabbage, spinach, kale, parsley, pepper leafs, broccoli and horse radish leaves. The fruits col-
.lected were apples, and grapes. All samples were analyzed for gamma emit-ting radionuclides, strontium-89, strontium-90, and iodine-131.
Iodine-131 was not detected above the LLD of 0.047 pCi/g wet in any broad leaf vegetation samples. The LLD for iodine 131 could not be reached in two samples collected (T-25 and T-37) on 07-16 91 because of a delay in counting. Iodine-131lwas not detected above the LLD of 0.041 pCi/g wet in fruit.
- The only gamma emitting radionuclide detected in the fruit and broad leaf ve-getation samples was potassium-40 which is naturally occurring. In both fruit
- and broad leaf vegetation, stronthun 89 was not detected above LLD of 0.010 pCi/g wet. Strontium-90 was detected at a concentration of 0.005 pCi/g wet at control location T-173 for fruit samples. In broad leaf vegetation, strontium-90 averaged 0.004 pCi/g wet for indicator locations. All results of analyses were similar to results observed in previous years.
I 2-24
Davis-Besse Nuclear Power Station 1991 Annual Envirorunental Operating Report Table 2-7: Broad Leaf Vegetation and fruit Locations Sample Number Type of Location Description Location Location T-8 1 Moore Farm,2.7 miles WSW of Station T-23 C Heineman Winery, Put IN. Bay,14.3 miles ENE of Station. T I Miller Farm,3.7 miles S of Station T-37 C Bench Fann,13.0 miles SW of Station T-173 C Firelands Winery, Sandusky,20.0 miles SE of station. il = indicator C = control Animal / Wildlife Feed Samples As with broad leaf vegetation and fruit samples, samples of domestic animal feed, as well as vegetation consumed by wildlife, provide and indication of air-borne radionuclides deposited in the vicinity of the Station. Analyses from animal / wildlife feed samples also provide data for determining radionuclide concentration in the food chain. Domestic animal feed samples are collected both at the milk arid 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 fal-lout radionuclides from nuclear weapons testing may be present in the feed samples. 5 - Damestic Animal Feed - Domestic animr.1 feed was collected semi-
- annually at dairy farms and annually at chicken sampling locations.
There are two indica y 'a ations and two control locations. The feed col-lected consisted of ha*, S:clage, mixed feed, chicken feed and corn. All l- samples were analyze r F. gamma emitting radionuclides.
- Wildlife Feed - Wildlife feed was collected annually at two indicator locations. The samples consisted of edible portions of cattails and smartweed. Samples were analyzed for gamma emitting radionuclides.
2-2 >
l Davis lkw.c Nuclear lher Strion IW1 annual Ervnnrnental Operating Repin in both the animal and wildlife leed only naturally xcurring Be 7 and K 40 were detected. All other rsdionuclides were below the respective LLDs. Table 2-8: Animal / Wildlife Feed Leations Sample location Type of location Description Number location T-8 I Moore farn.,2.7 miles WSW of Station T 31 1 Davis Desw, onsite roving location T 34 C Bertsch farm, Ssndusky,20.0 miles SE of L 'an T 57 C Meek Farm,22.0 miles SSE of Station T 197 1 Feisman Farm 1.7 miles W of Station T 198 I Toussaint Creek Wildlife Area 4.0 miles WSW of Station
- 1 = indicator C e control Wild and Domestic Meat Samples Sampling of domestic and wild meat provides infomiation on environmental radionuclide ccncentration that hiimans may '.e exposed to through an in-gestion pathway. The principle pathways for radionuclide contaniination of meat animals include atmospheric deposition from airborne releases on their food, contamination of their drinking water through atmospheric deposition or contamination of their ddning water from radionuclides released in liquid e ffluents.
The REMP generally collects m'd meat domestic meat,(chickens) and eggs on an annual basis. Wild anima's cccme ily consumed by residents in the vi-cinity of Davis-Besse include water fowl, deer, and muskrats. Analyses from anL nis whose meat is eaten by humans provides general information nn ra. dHr uclide concentration in the food chain. When evaluating the results from an%ies performed on incat animals, it is important to consider the age, diet and mobility of the animal before diawing conclusions on radionuclide con-cer.tration in th,: local environment or in a species as a whole. 2 26 L __. - - _- _ ____ _ ___.__ _ _ _ . _. .
Davis Bew: Nuclear Power Station 1W1 Anneal Environmental Opereing Repc n 1 Both wild and domestic meat samples and eggs were sampled in 1991 ac fol-lows: Domestic Meat: Oiickens
- vere collected at one indicator location and one control location.
Wild Meat: One Canada goose was collected from onsite. Four mustrats were collected from the marsh on site. All meat samples were a.nalyzed for gamma emitting radionuclides. Eggs: Eggs were collected from one indicator k> cation and one contiot location. The samples were analyzed for gamma emitting radionuclides. The only radionuclide detected in both the meat and eggs sample , was K 40 which is naturstly occurring and not produced by nuclear power plants. Cs 137 was not detected above LLD of 0 029 pCi/g wet. These results are similar to previous years. Table 2 9: Wild and Domestic Meat Locations Sample Location Type of Locatica Description humber Location T 31 1 Onsite roving location T 34 C Bertsch Egg Farm, Sandusty. 20.0 miles SE of Station T-197 I Priesman Farm,1.7 miles W of Station.
- I = indicatnr C = control Soll Samples During June and October of 1991, soil samples were collected at all sites which are equipped with air samplers and Put in Bay, the top layer of soil is sampled in an effort to identify possible trends in the local environmental nu.
clide concentiation caused by atmospheric deposition of fallout and station re. l leased radionuclides. Generally, the sites are relatively undisturbed, so that the j sample will be representative of the actual deposition in the area. Ideally, 2 27 4
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Davis Dene Nuclear Power Station 1991 Annual Environmental Operating Repon there should be little or no vegetation present, because the vegetation could af-feet the results of analyses. Approximately five pounds of scil are taken from tiie top two inches at each site. Many naturally occurring radionuclides (e.g. beryllium 7 and potassium-40) and fallout rmlionuclides from nuclear weap-ons testing are detected. Fallout radionuclides which are often detected in-clude strontium 90, ceslura 137, cerium 141 and ruthenium 106. All soil samples were analyzed for gamma emitting radionuclides. The results show that the only gamma emitter detected in addition to naturally occurring Be-7 and K-40, was Cs 137. Cs 137 was found in both indicator and control location at a concentration of 0.21 and 0.40 pC!/g dry, respectively. The con. centrations were similar to that observed in previous year (Figure 2-6). SOIL Cs-137 Concentration DCl/g dry 1.5 - -- b $ b _ 77 78 79 80 81 82 83 84 85 80 87 88 89 90 91 YEAR E Indicator E Control Figure 2-6: Ac concentration of cesium-137 in soil has remained fairly mnstant over the years the REMP has been conduced. De peak seen in 1978 was die to fallout form nuclear weapons testing. 2 28 r-m--
i Davis-Desse Nuclear Ibwer Station 1991 Annual Environmental Operating Report ; Table 2-10: Soll Locations Sample Location Type of Location Description Number Location T-1 I Site boundary,0.6 miles ENE of Station ' T-2 I Site boundary,0.9 miles E of Station ; T-3 I Site boundary 1.4 miles ESE of Station T-4 I Site boundary 0.8 miles S of Station T-7 I Sand Beach, main entrance,0.9 miles NW of Station T-8 I Moore Farm. 2.7 miles WSW of Station i T9 C Oak liarbor substation,6.8 miles SW of Station T 11 C Port Clinton Water Treatment Plant,9,5 miles SE of Station . Toledo Water Treatment Plant,23.5 miles T 12 C WNW of Station T-23 C South Bass Island,14.3 miles ENE of Station j T-27 C Crane Creek State Park,5.3 miles WNW of Station
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I = indicator C = controi 2-29 4
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( ' ENVIRONMENTAL MONITORING 8 I' inure 2-9
i Davis-Desse Nuclear hwcr Station 1991 Annual Er.vironmental Operating Report AQUATIC MONITORING l l Radionuclides may be present in 12ke Erie from many sources including at-mospheric deposition, run off/soll erosion, and releases of radioactivity in liquid effluents from hospitals or nuclear facilities. These sources provide two forms of potential radiation exposure, external and internal. External ex-posure can occur from the surface of the water, shore!ine sediments, and the immersion (swimming) in the water. Internal exposure can occur from in-gestion of radionuclides, either directly from drinking wate', or as a result of the transfer of radionuclides through the aquatic food chain with eventual consumption of an aquatic organism, soch as fish. To monitor these path-ways, treated surface water (drinking water), untreated surface water (lake or river water), fish, and shoreline sediments are sampled and analyzed. Treated Surface Water Treated surface water is water from Lake Erie which has been processed for human consumption. Radiochemical analysis of this processed water provides a direct basis for assessing the dose to humans from ingestion of drinking wa. ter. Samples of treated surface water wue collected form three indicator and three control locations. These locations include the water treatment facilities for Davis Besse, Eric Industrial Park, Port Clinton, Toledo and Put In Bay. Sam-pies were collected weekly and composited monthly. The monthly composites were analyzed for beta emitting radioactivity. The samples were also compos-ited in a quarterly sample and analyzed for strontium-89, strontium 90, gamma emitting radionuc!! des and tritium. One Quality Control (OC) sample was col-lected from a routine k> cation which was changed each month. In treated water samples, beta emitting radionuclides were not detected above the LLD of 0.9 pCi/l for suspended solids. The average concentration was similar in dissolved solids for indicator and control locations (2.3 and 2.2 pCi/1, respectively). The annual average for beta emitting radionuclides for all locations was similar to previous years as shown on the following page: 2-33
l Davis Besse Nuclear Ibwer Station 1991 Annual Environmental Operating Report 1972 3.4 pCi/l 1982 2.5 pCi/l 1973 2.9 pCi/l 1983 3.1 pCi/l 1974 2.3 pCi/l 1984 2.4 pCi/l 1975 2.3 pCill 1985 2.2 pCi/l 1976 2.3 pCi/l 1986 2.2 pC1/1 1977 2.8 pCi/l 1987 1.9 pCill 1978 3.1 pCi/l 1988 2.7 pCi/l 1979 2.6 pCi/l 1989 2.5 pCi/l 1980 2.5 pCi/l 1990 2.2 pCi/l 19812.9 pCi/l 1991 2.2 pCi/l All quarterly tritium analyses results were less than the LLD of 330 pCi/l for all routine sites. One monthly tritium analysis on a OC sample showed some detectable concentration of tritium (393+108 pCi/l). The OC sample was col. lected from T-11 Port Clinton water treatment plant (a controllocation) and is attributed to a natural source because tritium concentrations of this level were detected during the preoperational monitoring period. TREATED SURFACE WATER Gross Beta Analyses pCl/l 4 I L
-f.
g&a I.l.M--l.l.H.' 77 78 79 80 81 82 83 84 85 88 87 88 89 90 91 l Year
" indleator Mean M control Mean Figure 210: Over the past 15 years. the annual concentrations of beta emitting radionuclides in treated surface water samplcs mliccted from indicator locations have been mnsistant with those from control locations. This shows that Davis iksse has had no measurable radiologi-cal impact on surfact water used to make dnnking water.
2-34
Davis-11csse Nuclear Pow er Station 1991 Annual Environmental Operating Report 1 All cesium 137 results were less than the LLD of 10.0 pCid. Strontium-89 was not detected above 1.6 pCi/l in any samples. Strontium 90 was detected at i an average concentration of 0.6 at both indicator and control location. These l results are similar to those of previous years and indicate no sigtnficant impact on the environment resulting from the operation of Davis Besse. Table 211 Treated Surface Water Locations Sample Location Type of Location Description Number Location T-11 C Port Clinton Water Treatment Plant 9.5 miles SE of Station T-12 C Toledo Water Treatment Plant 23.5 miles WNW of Station T-23 C Put in Bay water Treatment Plant 14.3 miles ENE of Station. T 28 I Treated water supply from Davis-Besse site T 50 I Erie Industrial Park Port Clinton,4.5 miles SE of Station T-143 OC Ouality Control Site T-144 I Green Cove Condominiums,0.9 miles NNW of Station
- 1 -indicator C= control OC = quality control Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assess.
ing the dose to humans from external exposure from the lake surface as well as immersion in the water. It also provides information on the radioncclides present which may affect drirking water, fish, and irrigated crops. 2 35
Das is.tkue Nuc1 car Pow er Station 1W1 Annual Environmental Operating Re;urt Routine Program: The routine program is the basic sampling program which is performed year round. Untreated water sa:nples are colketed in the areas of the station intake and discharge and at the water intakes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo, Davis Besse, Erie In-dustrial 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 ana-lyzed for beta emitting radionuclides, tritium, and gamma emitting radionu. clides. The samples are further composited quarterly and analyzed for strontium 89 and stiontium 90. A OC sample was collected weekly at a dif-ferent location each month. Sumrner 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 swim. ming. These samples are obtained in areas along ?ie shoreline of Lake Erie and around the islands. The samples are collected weekly and composited monthly. The monthly composites are analyzed for beta emitting radioactivity, tritium, strontium 89, strontium 90 and gamma emitting radionuclides. In untreated water samples, beta emitting radionuclides in suspended solids ranged from 0.3 to 6.8 pCi/1, with and average concentration of 0.5 and 2.8 pCi/l at indicator and control locations, respectively. In dissolved solids, the average concentration was 2.5 pCi/l at indicator and 2.4 pCi/l at control loca-tions. Of the 182 tritium analyses performed on the untreated water,176 were less than the LLD of 330 pCi/1. The concentration of tritium detected in samples ranged form 333 to 884 pCill with an average concentration 531 and 333 pCi/l at ir.dicator and control locations, respectively. Only the August composite for tritium at T-130 (mouth Toussaint Rives) could be attributed to the routine operation of the station. The tritium concentration for that composite was 884 pCi/l. This is only .03% of the maximum permis-sible concentretion of 3,000,000 pCill for tritium in an unrestricted area, as stated in 10 CFR 20, Appendi:e B, Part 20, Table 2. Subsequent samples 2-36
Davis.llesse Nuclear Power Station 1991 Annual Environmental Operating Report Subsequent samples collected during September and October showed that the tritium concentration has retumed to below LLD of 330 pCi/1. Cesium 137 and strontium-89 were not detectable in samples of untreated wa-ter above their LLDs of 10 pCIA and 1.9 pCiA, respectively. Strontium 90 was detected at both indicator and control locations and had an average concentra-tion of 0.7 pCia and 0.9 pCiA, respectively. %c analysis results from un-treated water samples show that the operation of Davis-Besse has not had significant impact on nearby residents or on the environment. Each month, weekly quality control samples were collected at different loca-tion. The results of the analyu:s from the quality control samples were consis-tent with those from the ioutine samples. Some of the samples collected during the summer months in Lake Eric were close to the collection points of some of the routine 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 control samples to check the accuracy of analyses performed by the laboratory. he average concentrations of beta emitting radionuclides for these samples were 2.6 pCia for routine sites and 2.2 pCia for Lake Erie sample. Untreated Surface Water Control vs. Indicator pct /L 3 - U -{ .; g . - - - . . . - .
; hY 1 Jan Feb Mar Apr May Jun Jul Aug Sept Oct Nov oso 1
1991 M Control C indicator Figure 211: The average concentration of beta emitting radionucides in untreated water was similiar between control and indicator locadons. This demonstrates its.t Davis Bcue had no impact on the surrounding environment. 2 37
i Davis Besse Nuclear Power Statkm 1991 Annual Envirmmental Operating R. port Table 212: Untreated Surface Water leentions Sample location Type of Location Description Numbet Location i T-3 I Site boundary,1.4 miles ESE of Station T-11 C. Port Clit. ton Water Treatment Plant 9.5 miles SE of Station - T-12 C Toledo Water Treatment Plant, sample taken form in take crib 11.25 miles NW of Station T-23 C Put-In Bay Treatment Plant,14.3 miles ENE of Station T 28 I Davis Besse Water Treatment Plant T-50 I Eric Industrial Park, Port Clinton,4.5 miles SE of Station - T-130 1 Lake Erie,1.7 miles ESE of Station T-131. I Lake Erie,0.8 mile NE of Station T-132 I Lake Erie,1.0 mile E of Station T-133 I Lake Erie,0.8 mile N of Station T-134 I Lake Erie,1.4 miles NW of Station T-135 I . Lake Erie,2.5 miles WNW of Station T-137 C- Lake Erie,5.8 miles WNW of Station T-138 C Lake Erie,11.0 miles NW of Station T-145 OC Roving Quality Control Site T-152 C Lake Erie,15.6 miles WNW of Station T-158 ' C Lt.ke Erie,10.0 miles WNW of Station 2-38
. -__._________..__.._-_.__._._-___m_ -
Davis 4.'cw.c Nuclear Power Station 1991 Annual Environmental Operating Report TaWe 2-12: Untreated Surface Water Location continued Sample Location- Type of Location Description Number Location T-162 C Lake Erie 5.4 miles SE of Station T.164 C Lake Erie,9.5 miles ESE of Station T.167 C Lake Bie,11.5 miles E of Station T-168 -C Lake Erie,15.5 miles ENE of Station
- 1 = indicator C = control :
Shoreline Sediment The sampling of shoreline sediments can provide an indication of the accumulation of undissolved radionuclides which may lead to internal dose to humans through the ingestion of fish, through resuspension into drinking i water supplies, or as an extemal radiation source from shoreline dose to fishermen and swimmers. Samples of deposited sediments in water were collected in May and October from four indicator locations and four control locations. All samples were : analyzed for gamma emitting radionuclid% i Naturally occurring potassium-40 was detected at both controls and indicator locations. Cesium-137 was detected at a concentration of 0.12 pCi/g at indicator locations and 0.41 pCi/g at control locations. Atmospheric testing of nuclear weapons has been the principal source of cesium-137 in the environment to date. Although no atmospheric nuclear weapons tests have been reported since 1980, cesium 137 is still present in shoreline sediment samples because of its long half life (ag proximately 30 . years).- No other gamma emitting radionuclides were detected in any of the samples, and the concentrations of those detected were consistent with normal l concentrations for this area. 2-39 b ++ , , . - -.-w--.. ,,,m%, , , , , _ , , , , , , , . , y, , -, , - - - y. , , . . .- - - - - , - - . . . . , ,,p.ns.,,yum... , ,, , , ., 9 , ,
Davis Besse Nudcar Power Station - 1991 Annual Environmental Operating Rc;mrt Table 213: Shoreline Sediment lacation Sample location Type of location Description Number location T3 I Site boundary,1.4 miles ESE of Station ' T-4 I Site boundary,0.8 mile S of Station T-23 C South Bass Island,14.3 miles ENE of Station l T-27 C Crane Creek State Park,5.3 miles WNW of Station
- T-130 I Lake Erie,1,7 miles ESE of Station ,
T-132 - I ~ Lake Erie,1.0 mile E of Station T-138 C Iake Erie,11.0 miles NW of Station T-164 C Lake Erie, 9.5 miles ESE of Station
- I = indicator C = control Fish Samples Fish are analyzed primarily to quantify the dietary radionuclide intake by hu-mans, and secondary to serve as indicators of radioactivity in the aquatic eco.
- system. The principle nuclides which may be detected in fish include naturally occurring potassium-40, as well as cesium-137, and strontium 90. Depending '
upon the feeding habit of the species (e.g., bottom feeder versus predator), re-sults from sample analyses may vary. With the aid of local commercial fishermen, Davis Besse rounnely collects three species of fish (walleye, white bass and carp) twice a year from sampling locations near the Station's liquid discharge point and more than ten miles away from the Station where fish populations would not be expected to be im-pacted by the Station operation. Walleye are collected because they are a pop-ular sport fish, white bass because they are an iraportant commercial fish. Carp are' collected because they are bottom feeders and thus would be more likely to be affected by radionuclides deposited in lake sediments. Due to sea-p sonal unavailability no fish samples were obtained for the second half of 1991.The edible portion of fish were analyzed for beta and gamma emitting j . radionuclides. l 2-40 [ . u l
l l l Davis-Bev.c Nuclear Power Station 1W1 Annual Environmental Operating Report i Fish Samples indicator vs. Control Mean Gross Beta yo;g w 4 - - _ _ e
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0- - 77 78 79 80 81 02 83 84 85 80 87 88 09 90 91 bet E Indttel0f M cent,of Figure 212: Average concentrations of beta emitting radionuclides in fLe samples were similar at indicator and controllocatiorn and were within the range of results of previous yean. The average concentration of beta emitting radionuclides in fish muscle was similar for indicator and control location (2.46 and 2.76 pCiig wet weight, re-spectively). Cesium 137 was detected in one indicator location (T 33, white bass sample) at a concentration of 0.026 pCi/g wet weight. All sample analy-sis results were within normal ranges compared to previous years. Table 2 14. Fish IAcations Sample Location Type of Location Description Number Location T-33 I Lake Erie, within 5 miles radius of Station T-35 C Lake Erie, greater than 10 mile radius of Station Y= indicator C= control 2-41
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l l Davis.Ikwse Nyclear Power Station 1991 Annual Envinvunental Operating Report DIRECT RADIATION MONITORING Populations mVy be exposed to extremely small amounts of extemal radiation from nucicar facilities by several pathways, including airborne radioactivity or
;adionuclide deposition in soil, vegetation, or lake bottom sediments. Some radiation will always be preseta from background sources, both man.made and natural. The amuum of ncrmal background radiation can be determined by uemining preoperatt inal measurements ar data collected at control locations. ,
Thern oltteinescent Dosimeters Radiation at and around Davis Besse is constantly monitored oy a network of thermoluminescent dosimeters (l'LDs). TLDs are small devices which store radiation dose information. The TLDs used at Davis.Besse contain a calcium sulfate: dysprosium (CaSO.: Dy) card with four main readout areas. Multiple tradout areas are used to ensure the precision of the measurements. Thermoluminescence is a process by which ionizing radiation interacts with the sensitive materialin the TLD, the phosphor. Energy is trapped in the TLD rnaterial and can be stored for several months or years. This provides an ex-cellent 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 removed and measured by a controlled heating process in a cali. brated reading system. As the TLD is heated, the phosphor releases the stored energy as light. The amount of light detected is directly proportional to the amount of radiat'on !o which the TLD was exposed. The reading process re-zeros the TLD and prepares it for reuse. TLD Collection Davis Besse has 94 TLD locations (71 indicator and 23 control) which are col-lected and replaced on a quarterly and annual basis. An additional seventeen OC TLDs are also collected on a quarterly and annual basis or at any given time. There are a total of 222 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 tach other. In 1991, the annual average dose for all indicator locations was 15.0 mR/91 days, and for all control locations was 16.2 mR/91 days. The annual average dose equivalent for all TLDs in 1991 was 15.3 mrem days. These averages are similar to those observed in previous years as shown on the next page: 2-45
q I Davis-Besse Nuclear Power Station 1991 Annual Environmental Operating Report 1 1972 - 22.4 mremS1 days 1982 - 14.5 mremS1 days i 1973 - 14.3 mremS1 days 1983 - 13.2 mrem /91 days 1974 11.7 mremSt days 1984 - 13.2 mremS1 days 1 1975 - 12.8 mremS1 days 1985 - 14.4 mremS1 days l 1976 - 15.6 mremS1 days 1986 - 14.8 mremB1 days l 1977 - 16.5 mremS1 days 1987 - 14.5 mremS1 days l 1978 - 16.7 mremS1 days 1988 14.5 mremS1 days l 1979 - 13.4 mremS1 days 1989 15.9 mremS1 days I 1980 - 14.5 mremS1 days 1990 - 15.4 mremS1 days 1981 14.8 mrem /91 days 1991 - 15.3 mrem /91 days ! I COMPARISON OF TLD DOSES CONTROL vs INDICATOR mrem /91 days 15- ' I1 ! ' 8 i J ^
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0 -- 'i i i i i i i i i ~i i i ~i , i i "i ~i i~ 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 1987 l 1988 l 1989 l 1990 l 1991 I YEAR G INDICATOR E CONTROL Figure 2-16: similarity between indicator and control results from the last five years demon-strated that the operation of Davis-Desse has not caused any abnormal gamma da.c. Quality Control TLDs Duplicate TLDs have been established at 17 sites. These ~LDs were placed in the field at the same time and at the same location as some of the routine TLDs, but were assigned quality control site numbers. This allows us to take several measurements at the location without the laborstory being aw re that they are the same. A comparison of the quality control and routine results pro-vides a method to check the accuracy of the measurements. The average dose equivalent at the routine TLDs averaged 14.4 mrem /91 days while the quality l control TLDs yielded an average dose equivalent of 15.2 mrem /91 days. All 2-46
Davis Desse Nuclear Power Station 1991 Annual Environmental Operating Report the quality control and routine sample results were similar demonstrating the accuracy of both the TLD: and the laboratory's meas,urements. NRC TLD Monitoring The NRC has 22 TLDs located around Davis-Besse as part of their Direct Monitoring Network Program. Davis-Besse maintains TLDs at all the NRC TLD monitoring sites. The NRC collects their TLDs on a quarterly basis, whereas Davis Besse collects TLDs quarterly and annually at these locations. The NRC TLDs are collected and read independently of Davis-Besse's TLDs, thus providing a quality control check on both laboratories. The NRC uses Panasonic Model UD801 TLDs, which have two elements of lithium borate: copper (Li 2B 0,: Cu) and two elements of calcium sulfate: thu-l'um (CaSO,: Tm). The difference in TLD material used by the NRC and Davis-Besse causes some variation in results. 9 The results of TLD monitoring at these 22 locations show good consistency for the NRC TLDs ud the Davis Besse TLDs. The average of the quarterly results are 16.2 mrem /91 days for the Davis Besse TLDs and 16.3 mrem /91 days for the NRC TLDs (data from first, second, and third quarter). De vari-ance in these measurements is most likely due to the differences in the TLD materials. 1 TLD COMPARISON NRC vs Davls-Besse miem/91 days is q t g i; { p, h p [f ua f4 d 1> k h (( t , . p ', m G - E, L fW Q (4 Fl,%
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l 1987 1988 1989 1090 1991 Year M De O NRc Figure 2 t7: Cornpares NRC and Davis Besse 'll's for tast five years. 2-47
Davis Besse Nuclear Rwer Station 199t Annual Envimnmental Operating Report Table 2-15: Thermoluminescent Dosimeters Locations Sample I.ocation Type of Location Description Number Location T-1 I Site boundary,0.6 mile ENE of Station T-2 1 Site boundary,0.9 mile E of Station T3 1 Site boundary,1.4 miles ESE of Station T-4 1 Site boundary,0.8 mile S of Station T-5 I Site boundary 0.5 mile W of Statio1 T-6 1 Site boundary,0.5 mile NNE of Station T7 1 Sand Beach, main entrance,0.9 mile NW of Station T-8 I Earl Moore Farm,2.7 miles WSW of Station T9 C Oak liarbor Substation,6.8 miles SW of Station T-10 1 Site boundary,0.5 mile SSW of Station near warehouse T-11 C Pon Clinton Water Treatment Plant,9.5 miles SE of Station T-12 C Toledo Water Treatment Plant,23.5 miles WNW of Station T-23 C South Bass Island,14.3 miles ENE of Station, near lighthouse T 24 C Sandusky,21.0 miles SE of Station T-27 C Crane Creek State Park,5.3 miles WNW of Station T-38 i Site boundary,0.6 mile ENE of Station 2-48
Davis Bewe Nwlear Powcr Station 1W1 Annual Em tronmental Operating Repin Table 215: Thermoluminescent Dosimeters IAcations continued Sample location Type of Location Description Number Location T 39 1 Site boundary 1.2 miles ENE of Station T-40 1 Site boundary. 0.7 mile SE of Station T-41 1 Site boundary. 0.6 mile SSE of Station T-42 1 Sit e boundary 0.8 mile SW of Station T-43 1 Site boundary,0.5 mile SW of Station T-44 1 Site boundary,0.5 mile WSW of Station T-45 1 Sie: boundary,0.5 mile WNW of Station T 46 i Site boundary,0.5 mile NW of Station T-47 i Site boundary,0.5 mile N of Station 5 T-43 1 Site boundary,0.5 mile NE of Station T-49 1 Site boundary,0.5 mile NE of Station T-50 1 Erie Industrial Park, Port Clinton,4.5 miles SE of Station T-51 C Daup Farm,5.5 miles SSE of Station T-52 1 Miller Farm,3.7 miles S of Station T-53 i Nixon Farm,4.5 miles 5 of Station T-54 I Weis Farm,4.8 miles SW of Station T-55 I King Fann,4.5 miles W of Station T-60 1 Site boundary,0.3 mile S of Station T-61 1 Site boundary,0.6 mile SE of Station 2-49 m_._._________________.____________.____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
-l Davis Iksse Nuclear Power station 1991 Annual Environmental Opcrating Report Table 215: Thermoluminescent Dosimeters Locations continued Sample location Type of Imcation Description Number Location T-62 1 Site boundary,1.0 mile SE of Station T 63 i Site boundary,1.1 miles ESE of Station T 6J l Site boundary,0.9 mile E of Station !
T-65 i Site boundary,0.3 mile E of Station T-66 i Site boundary,0.3 mile ENE of Station T-67 I Site boundary,0.3 mile NNW of Station T-68 I Site boundary,0.5 mile WNW of Station T-69 i Site boundary,0.4 mile W of Station , T-70 -I Site boundary. 0.3 mile WNW of Station : T-71 I 5.0 boundary,0.1 mile NNW of Station T-73 I Site boundary,0.1 mile WSW of Station T 74 I Site boundary,0.1 mile SSW of Station 1 T-75 1 Site boundary,0.2 mile SSE of Station T-76 I' Site boundary,0.1 mile SE of Station T 77 I . Site boundary,0.1 mile ENE of Station . T-80 OC Ouality control Site T-82 OC Ouality Control Site
;T-83 OC Ouality Control Site
.T-84 OC Ouality Control Site -
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i i Davis Ikue Nuclear Power Station 1991 Annual Environmental Opertaing Repon Table 215: Thermoluminescent Dosimeters location continued Sample location Type of Location Number Number Location T 85 OC Ouality Control Site ; t T 86 OC Ouality control Site T-88 OC Quality Control Site T-89 QC Quality Control Site T 90 I Toussaint East and trutz Roads,2.0 miles SSW of Station I T-91 1 State Route 2 and Rankie Road,2.5 miles SSE of Station s T-92 i Locust Point Road,2.7 miles WNW of Station { T-93 I Twelfth Street, Sand Beach,0.6 mile NNE of Station T-94 1 State Route 2,1.8 miles WNW of Station T 95 C State Route 579,9 3 miles W of Station T-96 C State Route 2 and lloward Road,10.5 miles WNW of Station T 97 1 Duff Washa and Zetzer Road,1.5 miles W of Station T-98 C Toussaint Portage and Bier Road,6,0 miles SW of Station 4 T-99 I - Bentman Road,4.7 miles SSW of Station n .T-100 C Ottawa County Highway Garage, Oak Harbor, m.. 6.0 miles S of Station 2 51
. . _ _ . - . - _ = . _ . _ _ . . . . _ _ _ _ _ _ . _ _ _ _ . . . . .. _ _ .- ._ _ . _ -.
Davis.Besse Nucicar Power Station 1991 Annual Environmental Operating Report i Table 215:Thermoluminescent Dosimeters Locations cont.nued Sample Location Type of Location Description > Number - Location j T 101 C Finke Street, Oak Harbor,64.niles SSW of 1 Station ; T-102 C Oak Street, Oak Harbor,6.5 miles SSW of Station i T-103 C Licker Harder Road,8.5 miles SW of Station T 104 C Salem Carroll Road,7.3 miles SW of Station , T 105 C Lake Shore Drive Port Clinton,6.0 miles SE of Station
- T 106 C Third Street, Port Clinton,8.9 miles SE of Station i T 107- C Little Ponage East Road,8.5 miles SSE of Station T-108 C Boysen Road,9.0 miles S of Station
.T-109 C Stange Road,8.0 miles W of Station !
T 110 C Toussaint North and Graytown Road,10.0 ; miles WSW of Station
~T-111 C Toussaint North Road,8.3 miles WSW of Station
.T 112 I Thompson Road,1.5 miles SSW of Station T-113 OC Ouality Control Site T-114 OC - Quality control Site T 115 QC Ouality Control Site 2 52
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Davis 4 hse Nuclear Power Station 1991 Annual Em irmmental Ograting Rep >rt Table 215: Thermoluminescent Dosimeters locations continued Sample Locatioa Type of Location "escription Number Location T-116 OC Ouality Control Site}}