ML12174A090
| ML12174A090 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/15/2012 |
| From: | Boles B FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-12-152 | |
| Download: ML12174A090 (191) | |
Text
FENOC FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 N. State Route 2 Oak Harbor, Ohio 43449 May 15, 2012 L-12-152 10 CFR 50.36a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit 1 Docket Number 50-346, License Number NPF-3 Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2011 In accordance with 10 CFR 50.36a(a)(2), this letter transmits the combined 2011 Annual Radiological Environmental Operating Report (AREOR) and Radiological Effluent Release Report (RERR) for the period January 2011 through December 2011. These annual reports are submitted for the Davis-Besse Nuclear Power Station (DBNPS). The AREOR and the RERR must be submitted by May 15 of each year to satisfy the requirements of the DBNPS Technical Specifications 5.6.1 and 5.6.2.
The Attachment provides a listing of the specific requirements detailed in the DBNPS Offsite Dose Calculation Manual (ODCM) and the portion of the AREOR which was prepared to meet each requirement.
The following information is also provided only to the Document Control Desk. This information includes:
2011 RERR Meteorological Data (on Compact Disc)
Environmental, Inc. Midwest Laboratory, Monthly Progress Report for January through December 2011 (which contains the 2011 Radiological Environmental Monitoring Program Sample Analysis Results), dated February 15, 2012 (on Compact Disc)
Davis-Besse ODCM, Revision 25, dated February 23, 2011 Davis-Besse ODCM, Revision 26, dated November 3, 2011 A~6~
Davis-Besse Nuclear Power Station, Unit 1 L-12-152 Page 2 of 2 There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Alvin Dawson, Manager - Site Chemistry (acting), at (419) 321-7374.
Sincerely, Brian D. Boles Director-Site Operations Davis-Besse Nuclear Power Station VAW/AMP
Attachment:
Summary Location(s) of Off-Site Dose Calculation Manual Requirements Contents in the Annual Radiological Environmental Operating Report
Enclosure:
Annual Radiological Environmental Operating Report, including the Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2011 cc:
Regional Administrator, NRC Region III DB-1 NRC Senior Resident Inspector DB-1 NRC/NRR Project Manager Branch Chief, Division of Reactor Safety, Branch 6 Utility Radiological Safety Board
L-12-152 Attachment Page 1 of 1 Summary Location(s) of Off-Site Dose Calculation Manual Requirements Contents in the Annual Radiological Environmental Operating Report Description of Requirement Summaries, interpretations, and analyses of trends of the radiological environmental surveillance activities, and an assessment of the observed impacts of the plant (pages 31 through 80 and Appendix D)
Results of the Land Use Census (pages 111 through 116)
Results of the analysis of radiological environmental samples and of environmental radiation measurements (Environmental, Inc. Midwest Laboratory, Monthly Progress Report for January through December 2011 (pages 26 through 80))
Summary description of the Radiological Environmental Monitoring Program (also pages 26 through 80)
At least two legible maps, covering sampling locations keyed to a table giving distances and directions from the centerline of one reactor (pages 40 through 77)
The results of licensee participation in the Inter-laboratory Comparison Program (Appendix A)
Discussion of cases in which collection of specimens had irregularities due to malfunction of automatic sampling equipment and other legitimate reasons (page 36)
L-12-152 Enclosure Annual Radiological Environmental Operating Report, including the Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2011 (1 Report follows)
Ak 2a4
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Davis-Besse Nuclear Power Station January 1, 2011 through December 31, 2011 Davis-Besse Nuclear Power Station May 2012
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE OF CONTENTS Title Page List of Tables iv List of Figures vi Executive Summary viii INTRODUCTION Fundamentals 1
Radiation and Radioactivity 2
Interaction with Matter 3
Quantities and Units of Measurement 5
Sources of Radiation 7
Health Effects of Radiation 9
Health Risks 10 Benefits of Nuclear Power 11 Nuclear Power Production 11 Station Systems 16 Reactor Safety and Summary 19 Radioactive Waste 19 Description of the Davis-Besse Site 22 References 24 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Introduction 26 Pre-Operational Surveillance Program 26 Operational Surveillance Program Objectives
.27 Quality Assurance 27 Program Description 28 Sample Analysis 32 Sample History Comparison 34 i
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Title Page RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) 2011 Program Anomalies 36 Atmospheric Monitoring 36 Terrestrial Monitoring 43 Aquatic Monitoring 55 Direct Radiation Monitoring 67 Conclusion 78 References 78 RADIOACTIVE EFFLUENT RELEASE REPORT Protection Standards 81 Sources of Radioactivity Released 81 Processing and Monitoring 82 Exposure Pathways 83 Dose Assessment 84 Results 85 Regulatory Limits 86 Effluent Concentration Limits 87 Average Energy 87 Measurements of Total Activity 87 Batch Releases 88 Abnormal Releases 88 Percent of Offsite Dose Calculation Manual (ODCM) Release Limits 88 Sources of Input Data 89 Dose to Public Due to Activities Inside the Site Boundary 89 Inoperable Radioactive Effluent Monitoring Equipment 90 Changes to The ODCM and Process Control Plan (PCP) 90 Borated Water Storage Tank Radionuclide Concentrations 90 Onsite Groundwater Monitoring 106 LAND USE CENSUS Program Design 111 Methodology 111 Results 112 ii
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Title Page NON-RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring 117 On-Site Meteorological Monitoring 118 Land and Wetlands Management 132 Water Treatment Plant Operation 133 Chemical Waste Management 136 Other Environmental Regulating Acts 137 Other Environmental Programs 139 APPENDICES Appendix A: Interlaboratory Comparison Program Results 140 Appendix B: Data Reporting Conventions 159 Appendix C: Maximum Permissible Concentrations of Radioactivity in Air 161 and Water Above Background in Unrestricted Areas Appendix D: REMP Sampling Summary 163 Appendix E: Supplemental Analyses 170 iii
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report List of Tables Title Risk Factors: Estimated Decrease in Average Life Expectancy Sample Codes and Collection Frequencies Sample Collection Summary Radiochemical Analyses Performed on REMP Samples Air Monitoring Stations Milk Monitoring Location Groundwater Monitoring Locations Broadleaf Vegetation and Fruit Locations Animal/Wildlife Feed Locations Wild Meat Locations Soil Locations Treated Surface Water Locations Untreated Surface Water Locations Shoreline Sediment Locations Fish Locations Thermoluminescent Dosimeter Locations Gaseous Effluents - Summation of All Releases Gaseous Effluents - Ground Level Releases - Batch Mode Gaseous Effluents - Ground Level Releases - Continuous Mode Ground Level Releases - LLDs for Continuous and Batch Mode Gaseous Effluents - Mixed Mode Releases -Batch Mode Gaseous Effluents - Mixed Mode Releases - Continuous Mode LLDs for Gaseous Effluents - Mixed Mode Releases Liquid Effluents - Summation of All Releases Liquid Effluents - Nuclides Released in Batch Releases Table Number 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 18 18 19 19 19 20 21 Page Number 10 30 31 33 39 44 46 47 48 49 51 57 60 61 63 69 91 92 93 94 95 96 97 98 99 iv
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table Page Title Number Number Liquid Effluents - Nuclides Released in Continuous Releases 21 101 Liquid Effluents - LLDs for Nuclides Released 21 102 Liquid Effluents - Solid Waste and Irradiated Fuel Shipments 22 103 Groundwater Monitoring Wells Sampled in 2011 23 106 Doses Due to Gaseous Releases for January through December 2011 24 108 Doses Due to Liquid Releases for January through December 2011 25 109 Annual Dose to the Most Exposed (from all pathways) Member 26 110 of the Public 2011 Closest Exposure Pathways Present in 2011 27 114 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) 28 116 and Deposition (D/Q) Parameters Summary of Meteorological Data Recovery for 2011 29 122 Summary of Meteorological Data Measured for 2011 30 123 Joint Frequency Distribution by Stability Class 31 128 v
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report List of Figures Figure Page Description Number Number The Atom 1
1 Principal Decay Scheme of the Uranium Series 2
3 Range and Shielding 3
4 Sources of Exposure to the Public 4
8 Fission Diagram 5
12 Fuel Rod, Fuel Assembly, Reactor Vessel 6
13 Station Systems 7
15 Dry Fuel Storage Module Arrangement 8
21 Map of Area Surrounding Davis-Besse 9
22 2011 Airborne Gross Beta 10 38 Air Sample Site Map 11 40 Air Samples 5-mile Map 12 41 Air Sample 25-mile Map 13 42 Gross Beta Groundwater 1982-2011 14 45 Cs-137 in Soil 1972-2011 15 50 Terrestrial Site Map 16 52 Terrestrial 5-mile Map 17 53 Terrestrial 25-mile Map 18 54 Gross Beta in Treated Surface Water 1972-2011 19 56 Gross Beta Concentration in Untreated Surface Water 1977-2011 20 59 Gross Beta in Fish 1972-2011 21 62 Aquatic Site Map 22 64 Aquatic 5-mile Map 23 65 Aquatic 25-mile Map 24 66 Gamma Dose for Environmental TLDs 1973 - 2011 25 68 TLD Site Map 26 75 TLD 5-mile Map 27 76 TLD 25-mile Map 28 77 Exposure Pathways 29 84 vi
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Figure Page Description Number Number Davis-Besse Onsite Groundwater Monitoring H-3 Trends 30 107 Land Use Census Map 31 113 Wind Rose Annual Average 1 OOM 32 125 Wind Rose Annual Average 75M 33 126 Wind Rose Annual Average 10M 34 127 vii
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Executive Summary The Annual Radiological Environmental Operating Report (AREOR) is a detailed report on the Environmental Monitoring Programs conducted at the Davis-Besse Nuclear Power Station (Davis-Besse)from January 1 through December 31, 2011. This report meets all of the require-ments in NRC Regulatory Guide 4.8, Section 5.6 of Davis-Besse Technical Specifications, and Davis-Besse Offsite Dose Calculation Manual (ODCM) Section 7.1.
Reports included are the Radiological Environmental Monitoring Program, Radiological Effluents Release Report, Land Use Census, Groundwater Monitoring, and the Non-Radiological Environmental Programs, which consist of Meteorological Monitoring, Land and Wetland Management, Water Treatment, Chemical Waste Management, and Waste Minimization and Recycling.
Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is established to monitor the ra-diological condition of the environment around Davis-Besse. The REMP is conducted in accor-dance with NRC Regulatory Guide 4.8, Davis-Besse Technical Specifications, and the Davis-Besse ODCM, Section 6.0. This program includes the sampling and analysis of environmental samples and evaluating the effects of releases of radioactivity on the environment.
Radiation levels and radioactivity have been monitored within a 25-mile radius around Davis-Besse since 1972. The REMP was established at Davis-Besse about five years before the Station became operational. This pre-operational sampling and analysis program provided data on radia-tion and radioactivity normally present in the area as natural background. Davis-Besse has con-tinued to monitor the environment by sampling air, groundwater, milk, wild meat, fruit and vegetables, wild animal feed, drinking water, surface water, fish, shoreline sediment, and by di-rect measurement of radiation.
Samples are collected from Indicator and Control locations. Indicator locations are within 5 miles of the site and are expected to show naturally occurring radioactivity plus any increases of radioactivity that might occur due to the operation of Davis-Besse. Control locations are farther away from the Station and are expected to indicate the presence of only naturally occurring ra-dioactivity. The results obtained from the samples collected from indicator locations are com-pared with the results from those collected from control locations and with the concentrations present in the environment before Davis-Besse became operational. This allows for the assess-ment of any impact the operation of Davis-Besse might have had on the surrounding environ-ment.
Over 2,000 radiological environmental samples were collected and analyzed in 2011.
There were no missed ODCM samples or other ODCM sample anomalies during the year.
The results of the REMP indicate that Davis-Besse continues to be operated safely in accordance with applicable federal regulations. No significant increase above background radiation or radio-activity is attributed to the operation of Davis-Besse.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report The sampling results are divided into four sections: atmospheric monitoring, terrestrial monitor-ing, aquatic monitoring and direct radiation monitoring.
Air samples are continuously monitored at ten locations. Four samples are collected onsite. The other six are located between one-half and twenty-two miles away. Particulate filters and iodine cartridges are collected weekly. The 2011 indicator results were in close agreement with the samples collected at control locations. Iodine-131 was detected in all ten air sample locations over a four-week period between March 22 and April 12 following the fuel damage at the Fuku-shima Daiichi Nuclear Station in Japan due to an earthquake and subsequent tsunami on March 11, 2011. There was virtually no difference in iodine-131 concentration in control and indicator locations during this period.
Terrestrial monitoring includes analysis of milk, groundwater, meat, fruits, vegetables, animal feed, and soil samples. Samples are collected onsite and up to twenty-five miles away, depend-ing on the type of sample. Results of terrestrial sample analyses indicate concentrations of radio-activity similar to previous years and indicate no build-up of radioactivity due to the operation of Davis-Besse.
Aquatic monitoring includes the collection and analysis of drinking water, untreated surface wa-ter, fish and shoreline sediments from onsite and the vicinity of Lake Erie. Tritium was detected on January 31, 2011 in Untreated Surface Water sample T-3 (620 pCi/ liter) and in sample T-22 (351 pCi/liter). This activity is likely due to the operation of Davis-Besse, and is well below the federal EPA limit for drinking water sources of 20,000 pCi/liter. There was no other detectable tritium result in the surface water samples collected during this reporting period.
The 2011 results of analysis for fish, treated surface water and shoreline sediment indicate nor-mal background concentration of radionuclides and show no increase or build-up of radioactivity due to the operation of Davis-Besse.
Direct radiation averaged 16.7 mrem/91 days at indicator locations and 17.9 mrem/91 days at control locations, which is similar to results from previous years and indicates no influence on the surrounding environment from the operation of the plant during 2011.
The operation of Davis-Besse in 2011 caused no significant increase in the concentrations of ra-dionuclides or adverse effects on the quality of the environment surrounding the plant. Radioac-tivity released in the Station's effluents was well below the applicable federal regulatory limits.
The estimated radiation dose to the general public due to the operation of Davis-Besse in 2011 was well below all applicable regulatory limits.
In order to estimate radiation dose to the public, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is per-formed as part of the REMP. During the census, Station personnel travel every public road within a radius of five miles of Davis-Besse to locate radiological exposure pathways (e.g., resi-dences, vegetable gardens, milk cows/goats, etc.). The most important pathway is the one that, for a specific radionuclide, provides the greatest dose to a sector of the population. This is called the critical pathway. The critical pathway for 2011 was a garden in the West sector 1,560 meters from Davis-Besse, and is unchanged from 2010.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Radiological Effluent Release Report The Radiological Effluent Release Report (RERR) is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period January 1 through December 31, 2011. The doses due to radioactivity released during this period were only a fraction of what is-allowed by our operating license.
During 2011, gaseous radioactive effluent samples obtained from Station Vent identified de-tectable iodine-131 concentrations between March 28 and April 19 that could be attributed to operation of Davis-Besse. The concentrations detected were above the non-detectable levels observed during this operating period.
Concentrations of iodine-131 returned to non-detectable after April 19. Given the events of March 2011 at the Fukushima Daiichi Nuclear Station in Japan and the associated airborne releases and subsequent trans-Pacific transporta-tion, the slightly elevated concentrations detected at this release point are reasonably attrib-uted to the Fukushima Daiichi Nuclear Station releases. However, the concentrations at Davis-Besse and projected doses are conservatively included in this report for completeness.
The Total Body doses to an individual and population in an unrestricted area due to direct radiation from Davis-Besse is not distinguishable from background. These doses represent an extremely small fraction of the limits set by the NRC or the limits set in the ODCM.
Unplanned Releases One unplanned gaseous release occurred on December 5, 2011, when 2 Auxiliary Steam valves lifted for approximately three seconds during plant startup. A total of 1.OE-06 curies of tritium was calculated in this release with a whole body dose of 3.OE-11 mrem.
Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP)
There were two revisions of the ODCM in 2011.
There were no revisions of the PCP during 2011.
Groundwater Protection Initiative Davis-Besse began monitoring groundwater wells near the plant in 2007 as part of the FENOC Groundwater Protection Initiative (GPI) in order to determine whether there have been any inad-vertent releases of radioactivity that have impacted groundwater or could potentially affect local water supplies. In addition to several existing pre-construction wells, 16 new GPI monitoring wells were drilled in 2007, which are sampled on a semi-annual basis in spring and fall. None of these wells are drinking water sources. Any well with over 2,000 pCi/liter tritium requires cour-tesy notification of state, county and local officials.
The tritium concentrations found were all below the 30,000 pCi/liter EPA limit for non-drinking water sources. Sampling of these wells is normally performed on a semi-annual basis, or as often as needed.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report GPI samples were collected in spring and fall of 2011.
All tritium results were less than the 2,000 pCi/liter concentration requiring courtesy notifications.
A courtesy notification was made on March 29, 2011 when an unknown amount of water con-taining 7,340 pCi/liter tritium was spilled onto the ground during transfer from the East Con-denser Sump to the North Settling Basin.
A second courtesy notification was made on October 11, 2011 when a temporary hose used dur-ing the 17M midcycle outage to direct Turbine Building sumps to the South Settling Basin be-came disconnected, causing a spill of low-level tritiated water onto the ground.
There is no indication that the spill traveled offsite or affected offsite dose in either event. A new discharge line with welded connections has since been installed in order to prevent future inci-dents during periods when this temporary lineup is in place.
Non-Radiological Environmental Programs Meteorological Monitoring The Meteorological Monitoring Program at Davis-Besse is part of a program for evaluating the radiological effects of the routine operation of Davis-Besse on the surrounding environment.
Meteorological monitoring began in October of 1968.
Meteorological data recorded at Davis-Besse include wind speed, wind direction, sigma theta (standard deviation of wind direction), ambient temperature, differential temperature, dew point and precipitation. Two instrument-equipped meteorological towers are used to collect data. Data recovery for the five instruments that are operationally required by Davis-Besse Technical Re-quirements Manual was 99.45 %.
Marsh Management FirstEnergy owns the Navarre Marsh. It is leased to the U.S. Fish and Wildlife Service, who manage it as part of the Ottawa National Wildlife Refuge.
The Davis-Besse site currently has two active American Bald Eagle nests on the property. A total of twenty-two healthy eaglets have fledged from Davis-Besse nests since 1995.
Water and Wastewater Treatment Davis-Besse withdraws water from Lake Erie and processes it through a vendor-supplied water treatment process to produce the high-purity water used in the Station's cooling systems.
Since December 1, 1998, the Carroll Township Water Treatment Plant has provided for domestic water needs at Davis-Besse.
Sewage is treated at the Davis-Besse Wastewater Treatment Plant (WWTP) and its effluent is pumped to a settling basin. Following a retention period, this water is discharged with other Sta-tion liquid effluents back to Lake Erie. There was one National Pollutant Discharge Elimination System permit violation during 2011.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Chemical Waste Management The Chemical Waste Management Program at Davis-Besse was developed to ensure that the off-site disposal of non-radioactive hazardous and nonhazardous chemical wastes is performed in accordance with all applicable state and federal regulations. Chemical waste disposal vendors contracted by Davis-Besse use advanced technology for offsite disposal, including recycling of chemical wastes, in order to protect human health and the environment. In 2011, the Davis-Besse Nuclear Power Station generated approximately 35,815 pounds of hazardous waste. Non-hazardous wastes generated include 12,700 gallons of used oil, latex paints, caulks and grout. As required by Superfund Amendment and Reauthorization Act (SARA), Davis-Besse reported haz-ardous products and chemicals to local fire departments and local and state planning commis-sions. As part of the program to remove PCB fluid from Davis-Besse, all electrical transformers have been retrofilled and reclassified as non-PCB transformers.
Waste Minimization and Recycling The Waste Minimization and Recycling Program at Davis-Besse began in 1991 with the collec-tion and recycling of paper. This program was expanded and reinforced during 1993 to include the recycling of paper, aluminum cans, cardboard, and metal. Paper and cardboard recycling typically exceeds 50 tons annually. The scrap metal collected onsite is sold to scrap companies.
Appendices Appendix A contains results from the Interlaboratory Comparison Program required by Davis-Besse ODCM. Samples with known concentrations of radioisotopes are prepared by the Envi-ronmental Resources Associates (ERA), and then sent (with information on sample type and date of collection only) to the laboratory contracted by the Davis-Besse Nuclear Power Station to ana-lyze its REMP samples. The Environmental Resources Associates (ERA) compares results to known standards.
Appendix B contains data reporting conversions used in the REMP at Davis-Besse. The appen-dix provides an explanation of the format and computational methods used in reporting REMP data. Information on counting uncertainties and the calculations of averages and standard devia-tions are also provided.
Appendix C lists the effluent concentration limits for alpha and beta-emitting radioisotopes and for certain other radioisotopes in air and water samples. These concentrations are taken directly from the Code of Federal Regulations, and provide comparison values for actual REMP sampling results for 2011.
Appendix D provides a REMP sampling summary from 2011. The appendix provides a listing of the following for each sample type:
" number and type of analysis performed
- lower limit of detection for each analysis
" mean and range of results for control and indicator locations xii
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report
" mean, range, and description of location with highest annual mean
" number of non-routine results For detailed studies, Appendix D provides more specific information than that listed in this re-port. The information presented in Appendices A through D was provided by Environmental, Inc. Midwest Laboratory in their Final Progress Report to Davis-Besse (February, 2012).
Appendix E contains airborne iodine-131 results following the tsunami affecting the Fukushima Daiichi Nuclear Station. Detectable iodine was reported at similar levels in all indicator and con-trol samples between the March 22 and April 5, 2011 air samples. Following this, the concentra-tions of iodine-131 continued to diminish until it was no longer detectable in any samples after May 3, 2011.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Introduction Coal, oil, natural gas and hydropower are used to run this nation's electric generating stations; how-ever, each method has its drawbacks. Coal-fired power can affect the environment through mining, acid rain and air pollution. Oil and natural gas are in limited supply and are, therefore, costly. Hy-dropower is limited due to the environmental impact of damming our waterways and the scarcity of suitable sites.
Nuclear power provides a readily available source of energy. The operation of nuclear power sta-tions has a very small impact on the environment. In fact, the Davis-Besse Nuclear Power Station is surrounded by hundreds of acres of marshland, which make up part of the Ottawa National Wildlife Refuge. In order to provide better understanding of this unique source of energy, background infor-mation on basic radiation characteristics, risk assessment, reactor operation and effluent control is provided in this section.
Fundamentals The Atom All matter consists of atoms. Simply de-scribed, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, respec-tively (Figure 1).
The relatively large pro-tons and neutrons are packed tightly to-gether in a cluster at the center of the atom called the nucleus. Orbiting around the nu-cleus 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. This holds the atom together.
Other attractive forces between the protons and neutrons keep the densely packed protons from repel-ling each other, and prevent the nucleus from breaking apart.
0 fRO-MN ELECTRor Figure 1: An atom consists of two parts: a nucleus containing positively charged protons and electrically neutral neutrons and one or more negatively charged electrons orbiting the nucleus. Protons and neutrons are nearly identical in size and weight, while each is about 2000 times heavier than an electron.
I
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Radiation and Radioactivity Isotopes and Radionuclides A group of identical atoms containing the same number of protons make up an element. In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms with one proton are hydrogen atoms, and all atoms with eight protons are oxygen atoms. How-ever, the number of neutrons in the nucleus of an element may vary. Atoms with the same num-ber of protons but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties, and many are stable or nonradioactive. An un-stable or radioactive isotope of an element is called a radioisotope, a radioactive atom, or a radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess energy is usually due to a surplus or deficit in the number of neutrons in the nucleus. Ra-dionuclides such as Uranium-238, Berylium-7 and Potassium-40 occur naturally. Others are man-made, such as Iodine-131, Cesium-137, and Cobalt-60.
Radiation Radiation is simply the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation is another type of radiation and has similar properties to those of the examples listed above. Ion-izing radiation consists of both electromagnetic radiation and particulate radiation. Electro-magnetic radiation is energy with no measurable mass that travels with a wave-like motion through space. Included in this category are gamma rays and X-rays. Particulate radiation con-sists of tiny, fast moving particles which, if unhindered, travel in a straight line through space.
The three types of particulate radiation of concern to us are alpha particles, which are made up of 2 protons and 2 neutrons; beta particles, which are essentially free electrons; and neutrons.
The properties of these types of radiation will be described more fully in the Range and Shielding section.
Radioactive Decay Radioactive atoms, over time, will reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of energy from an atom through the emis-sion 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 daugh-ter products that eventually result in a stable atom.- The loss of energy and/or matter through radioactive decay may transform the atom into a chemically different element. For example, when Uranium-238 decays, it emits an alpha particle and, as a result, the atom loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom deter-mines 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 succes-sive daughter products of Uranium-238. Radon is another daughter product, and the series ends with stable Lead-206.
2
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report This example is part of a known radioactive decay series, called the Uranium series, which be-gins with Uranium-238 and ends with Lead-206 (Figure 2).
S238 U 4.5 x 109 yr 234 u
,2.5 x 105 Yr "4 Pa T
12 12 min j
234Th 24 d 230°h 8.0 x 104Yr 1
226 Ra 1600 Yr 1
3.82 d I
Beta Decay Alpha Decay 2183P0 3.05 min
~1.6 x104 S 210OPo
- ,138.4 d 214 Bi' 210Bi
__ 19.7 min f _ 5.01d 7
214 Pb 26.8 min-21 pb 23 Yr 2 06Pb stable Figure 2: Principal Decay Scheme of the Uranium Series.
Half-life Most radionuclides vary greatly in the frequency with which their atoms release radiation. Some radioactive materials, in which there are only infrequent emissions, tend to have a very long half-.
lives. Those radioactive materials that are very active, emitting radiation more frequently, tend to
.have comparably shorter half-lives. The length of time an atom remains radioactive is defined in terms of half-lives. Half-life is the amount of time required for a radioactive substance to lose half of its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years.
Interaction with Matter Ionization Through interactions with atoms, alpha, beta, and gamma radiation lose their energy. When these forms of radiation interact with any form of material, the energy they impart may cause 3
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report atoms in that material to become ions, or charged particles. Normally, an atom has the same number of protons as electrons. Thus, the 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 that 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 compara-tively large size, an alpha particle usually does not travel very far before it loses most of its en-ergy through collisions and interactions with other atoms. As a result, a sheet of paper or a few centimeters of air can easily stop alpha particles (Figure 3).
Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed of light (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1.
Because they are so small and have a low charge, they do not collide and interact as often as al-pha particles, so they can travel farther. Beta particles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood.
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rIATERIAL PAPER ALUMINUM LEAD CONCRETE Figure 3: As radiation travels, it collides and interacts with other atoms and loses energy. Alpha particles can be stopped by a sheet of paper, and beta particles by a thin sheet of aluminum. Gamma radiation is shielded by highly dense materials such as lead, while hydrogenous materials (those containing hydrogen atoms), such as water and concrete, are used to stop neutrons.
Gamma rays are pure energy and travel at the speed of light. They have no measurable charge or mass, and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray finally loses all of its energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions.
Very high-energy gamma radiation can travel a considerable distance, whereas low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of Lead or concrete may be needed to effectively shield. gamma rays.
Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within operating nuclear power reactors. However, neu-4
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report trons are not of environmental concern since the neutron source at nuclear power stations is sealed 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. When deflected, the neutron loses some of 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 neu-tron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons.
Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons.
Neutron shielding materials commonly used to slow neutrons down are water or polyethylene. The shield is then completed with a material such as Cadmium, to absorb the now thermal neutrons. At Davis-Besse, concrete is used to form an effective neutron shield because it contains water mole-cules and can be easily molded around odd shapes.
Quantities and Units of Measurement There are several quantities and units of measurement used to describe radioactivity and its ef-fects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent.
Activity: Curie Activity is the number of atoms in a sample that disintegrate (decay) per unit of time. Each time an atom disintegrates, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms of a radioactive substance are decaying.
One curie indicates the disintegration of 37 billion atoms per second.
A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. For example, one gram (1/28th of an ounce) of radium-226 is the equivalent of one curie of activity, but it would take 9,170,000 grams (about 10 tons) of thorium-232 to equal one curie.
Smaller units of the curie are often used, especially when discussing the low concentrations of radioactivity detected in environmental samples. For instance, the microcurie (uCi) is equal to one millionth of a curie, while the picocurie (pCi) represents one trillionth of a curie.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Absorbed Dose: Rad Absorbed dose is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation. The Rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material (1 Rad = 100 erg/gm).
The rate of absorbed dose is usually given in Rad/hr.
If the biological effect of radiation is directly proportional to the energy deposited by radiation in an organism, the Rad would be a suitable measurement of the biological effect. However, bio-logical effects depend not only on the total energy deposited per gram of tissue, but on how this energy is distributed along its path. Experiments have shown that certain types of radiation are more damaging per unit path of travel than are others. Thus, another unit is needed to quantify the biological damage caused by ionizing radiation.
Dose Equivalent: Rem Biological damage due to alpha, beta, gamma and neutron radiation may result from the ioniza-tion caused by this radiation. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or X-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to a particular type of ionizing radia-tion. The dose equivalent is measured in rem (radiation equivalent man).
An example of this conversion from absorbed dose to dose equivalent uses the quality factor for alpha radiation, which is equal to 20. Thus, 1 Rad of alpha radiation is approximately equal to 20 rem. Beta and gamma radiation each have a quality factor of 1, therefore one Rad of either beta or gamma radiation is approximately equal to one rem. Neutrons have a quality factor rang-ing from 2 to 10. One rem produces the same amount of biological damage, regardless of the source. In terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit, the mil-lirem, is often used. One millirem (mrem) is equal to 1/1,000 of a rem.
Deep dose equivalent is the measurement of dose within the body, from sources of radiation that are external to the body. It is what is measured and recorded on thermoluminescent dosimeters (TLDs), film badges or other dosimeters. For example, at Davis-Besse or at any hospital that has x-ray equipment, you will see people wearing these devices. These instruments are worn to measure DDE.
Committed Effective Dose Equivalent (CEDE)
Committed effective dose equivalent is a measure of the dose received from any radioactive ma-terial taken into the body. It is calculated from the sum of the products of the committed dose 6
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report equivalent to the organ or tissue multiplied by the organ or tissue-weighting factor. CEDE ac-counts for all the dose delivered during the entire time the radioactive material is in the body.
Total Effective Dose Equivalent (TEDE)
Total effective dose equivalent is the sum of the deep dose equivalent (for dose from sources ex-ternal to the body) and the committed effective dose equivalent (for internal dose). Since they, are both doses to the body, they are not tracked separately. The NRC limits occupational dose to a radiation worker to five rem (5,000 mrem) TEDE per year.
Sources of Radiation Background Radiation Radiation did not begin with the nuclear power industry, and occurs naturally on earth. It is probably the most "natural" thing in nature. Mankind has always lived with radiation and proba-
,bly always will. In fact, during every second of life, over 7,000 atoms undergo radioactive decay "naturally" in the body of the average adult. In addition, radioactive decay occurs naturally in soil, water, air and space. All these common sources of radiation contribute to the natural back-ground radiation to which we are all exposed.
The earth is being showered by a steady stream of high-energy gamma rays and particulate radia-tion that come from space known as cosmic radiation. The atmosphere shields us from most of this radiation, but everyone still receives about 20 to 50 mrem each year from this source. The thinner air at higher altitudes provides less protection against cosmic radiation. People living at higher altitudes or flying in an airplane are exposed to even higher levels cosmic radiation. Ra-dionuclides commonly found in the atmosphere as a result of cosmic ray interactions include Be-ryllium-7, Carbon-14, tritium (H-3), and Sodium-22.
Another common naturally occurring radionuclide is Potassium-40. About one-third of the ex-ternal and internal dose from naturally occurring background radiation is attributed to this radio-active isotope of potassium.
The major source of background radiation is Radon, a colorless, odorless, radioactive gas that results from the decay of Radium-226, a member of the Uranium-238 decay series. Since Ura-nium occurs naturally in all soils and rocks, everyone is continuously exposed to Radon and its daughter products. Radon is not considered to pose a health hazard unless it is concentrated in a confined area, such as buildings, basements or underground mines. Radon-related health con-cerns stem from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it decays, which can cause damage to internal tissues when inhaled. As a result, exposure to the lungs is a concern, since the only recognized health effect associated with exposure to Ra-don is an increased risk of lung cancer. This effect has been seen when Radon is present at levels common in uranium mines. According to the National Council on Radiation Protection and Measurement (NCRP), more than half of the radiation dose the average American receives is at-tributed to Radon.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report SOURCES OF EXPOSURE TO THE PUBLIC Terrestrial 8%
j Radon 55%
Internal 11%
Manmade 18% (X-Rays 10%, Nuclear Medicine 4%,
Consumer Products 3%,
Nuclear Power <0.2%)
Figure 4: The most significant annual dose received by an individual of the public is that received from naturally occurring radon. A very small annual dose to the public results from producing electricity by nuclear power.
Further information on Radon, its measurement, and actions to reduce the Radon concentration in buildings can be obtained by contacting the state Radon program office at the following ad-dress:
Ohio Department of Health, Bureau of Radiation Protection 246 North High Street Columbus, Ohio 43215 (614) 644-2727 (614) 644-0381 FAX The approximate average background radiation in this area (see Figure 4) is 300 mrem/year.
Man-made Radiation In addition to naturally occurring cosmic radiation and radiation from naturally occurring radio-activity, people are also exposed to man-made radiation. The largest sources of exposure include 8
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include Strontium-90, Cesium-137, and tritium. Less than one percent of the annual dose a member of the public re-ceives is a result of having electricity generated by nuclear power.
Health Effects of Radiation The effects of ionizing radiation on human health have been under study for more than ninety years. Scientists have obtained valuable knowledge through the study of laboratory animals that were exposed to radiation under extremely controlled conditions. However, it has been difficult to relate the biological effects of irradiated laboratory animals to the potential health effects on humans.
The effects of radiation on humans can be divided into two categories, somatic and genetic. So-matic effects are those which develop in the directly exposed individual, including an unborn child. Genetic effects are those which are observed in the offspring of the exposed individual.
Somatic effects can be divided further into acute and chronic effects. Acute effects develop shortly after exposure to large amount of radiation. Much study has been done with human populations that were exposed to ionizing radiation under various circumstances. These groups include the survivors of the atomic bomb, persons undergoing medical radiation treatment, and early radiologists, who accumulated large doses of radiation, unaware of the potential hazards.
Chronic effects are a result of exposure to radiation over an extended period of time. Examples of such groups are clock dial painters, who ingested large amounts of Radium by "tipping" the paint brushes with their lips, and Uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (Uranium ore). The studies performed on these groups have increased our knowledge of the health effects from comparatively very large doses of radiation received over long periods of time.
Continuous exposure to low levels of radiation may produce somatic changes over an extended period of time. For example, someone may develop cancer from man-made radiation, back-ground radiation, or some other source not related to radiation. Because all illnesses caused by low level radiation can also be caused by other factors, it is virtually impossible to determine in-dividual health effects of low level radiation. Even though no effects have been observed at doses less than 50 rem, we assume the health effects resulting from low doses of radiation occur proportionally to those observed following large doses of radiation. Most radiation scientists agree that this assumption over-estimates the risks associated with a low-level radiation expo-sure. The effects predicted in this manner have never been actually observed in any individuals exposed to low level radiation. Therefore, the most likely somatic effect of low level radiation is believed to be a small increased risk of cancer. Genetic effects could occur as a result of ionizing radiation interacting with the genes in the human cells. Radiation (as well as common chemi-cals) can cause physical changes or mutations in the genes. Chromosome fibers can break and rearrange, causing interference with the normal cell division of the chromosome by affecting their number and structure. A cell is able to rejoin the ends of a broken chromosome, but if there are two breaks close enough together in space and time, the broken ends from one break could 9
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report join incorrectly with those from another. This could cause translocations, inversions, rings, and other types of structural rearrangements. When this happens, new mutated genes are created.
Radiation is not the only mechanism by which such changes can occur. Spontaneous mutations and chemically induced mutations also have been observed. These mutated genes may be passed from parent to offspring. Viable mutations due to low level, low dose radiation have not been observed in humans.
Health Risks While people may accept the risks inherent in their personal activities, such as smoking and driv-ing to work each day, they are less inclined to accept the risk inherent in producing electricity.
As with any industrial environment, it is not possible to guarantee a risk free environment. Thus, attention should be focused on taking steps to safeguard the public, on developing a realistic as-sessment of the risks, and on placing these risks in perspective. The perceptions of risk associ-ated with exposure to radiation may have the greatest misunderstanding. Because people do not understand ionizing radiation and its associated risks, many fear it. This fear is compounded by
'the fact that we cannot hear, smell, taste or feel ionizing radiation.
We do not fear other potentially hazardous things for which we have the same lack of sensory perception, such as radio waves, carbon monoxide, and small concentrations of numerous cancer-causing substances. These risks are larger and measurable compared to those presumed to be as-sociated with exposure to low level, low dose radiation. Most of these risks are with us through-out our lives, and can be added up over a lifetime to obtain a total effect. Table 1 shows a number of different factors that decrease the average life expectancy of individuals in the United States.
Table 1: Risk Factors: Estimated Decrease in Average Life Expectancy Overweight by 30%:
3.6 years Cigarette smoking:
1 pack/day 7.0 years 2 packs/day 10.0 years Heart Disease:
5.8 years Cancer:
2.7 years City Living (non-rural):
5.0 years All operating commercial nuclear power plants totaled:
less than 12 minutes 10
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report 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. Today more than twenty per-cent of the electricity produced in the United States is from nuclear powered electrical generating stations.
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 operating, Uranium, the fuel for nuclear power stations, is a relatively inexpensive fuel that is readily available in the United States,
" Nuclear power is the cleanest energy source for power stations that use steam to produce electricity. There are no greenhouse gases or acid gases produced when using nuclear fuel.
The following sections provide information on the fundamentals of how Davis-Besse uses nu-clear fuel and the fission process to produce electricity.
Nuclear Power Production Electricity is produced in a nuclear power station in the same way as in a fossil-fueled station with the exception of the source of heat. Heat changes water to steam that turns a turbine. In a fossil-fueled station, the fuel is burned in a furnace, which is also a boiler. Inside the boiler, wa-ter is turned into steam. In a nuclear station, a reactor that contains a core of nuclear fuel, primar-ily uranium, replaces the furnace. Heat is produced when the atoms of Uranium are split, or fissioned, inside the reactor.
What is Fission?
A special force called the binding force holds the protons and neutrons together in the nucleus of the atom. The strength of this binding force varies from atom to atom. If the bond is weak enough, the nucleus can be split when bombarded by a free neutron (Figure 5). This causes the entire atom to split, producing smaller atoms, more free neutrons, and heat. In a nuclear reactor, a chain reaction of fission events provides the heat necessary to boil the water to produce steam.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Kcat Bombarding Neutron@
Free Atom /~
\\
Neutron Atom Fissio Fragment Figure 5: When a heavy atom, such as uranium-235 is split or fissioned, heat, free neutrons, and fission fragments result. The free neutrons can then strike neighboring atoms causing them to fission also. In the proper environment.
this process can continue indefinitely in a chain reaction.
Nuclear Fuel The fissioning of one Uranium atom releases approximately 50 million times more energy than the combustion of a single Carbon atom common to all fossil fuels. Since a single small reactor fuel pellet contains trillions of atoms, each pellet can release an extremely large amount of en-ergy. The amount of electricity that can be generated from three small fuel pellets would require about 3.5 tons of coal or 12 barrels of oil to generate.
Nuclear fission occurs spontaneously in nature, but these natural occurrences cannot sustain themselves because the freed neutrons either are absorbed by non-fissionable atoms or quickly decay. In contrast, a nuclear reactor minimizes neutron losses, thus sustaining the fission proc-ess by several means:
" using fuel that is free of impurities that might absorb the free neutrons,
- enriching 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 fis-sion easily,
" slowing down neutron by providing a "moderator" such as water to increase the probability of fission.
Natural Uranium contains less than one percent U-235 compared to the more abundant U-238 when it's mined. Before it can be economically used in a reactor, it is enriched to three to five percent U-235, in contrast to nuclear material used in nuclear weapons which is 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.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report After the Uranium ore is separated from the earth and rock, it is concentrated in a milling proc-ess. After milling the ore to a granular form and dissolving out the Uranium with acid, the Ura-nium is converted to Uranium hexafluoride (UF 6). UF6 is a chemical form of Uranium that exists as a gas at temperatures slightly above room temperature. The UF6 is then highly purified and shipped to an enrichment facility where gaseous diffusion converters increase the concen-tration of U-235. The enriched gaseous UF 6 is then converted into powdered Uranium dioxide (U0 2), a highly stable ceramic material. The U0 2 powder is put under high pressure to form fuel pellets, each about 5/8 inch long and 3/8 inch in diameter. Approximately five pounds of these pellets are placed into a 12-foot long metal tube made of Zirconium alloy. The tubes constitute the fuel cladding. The fuel cladding is highly resistant to heat, radiation, and corrosion. When the tubes are filled with fuel pellets, they are called fuel rods.
The Reactor Core Two hundred eight fuel rods comprise a single fuel assembly. The Reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fuel rods, the fuel assembly also contains 16 vacant holes for the inser-tion of control rods, and one vacant hole for an incore-monitoring probe. This probe monitors temperature and neutron levels in the fuel assembly. The Davis-Besse reactor vessel, which con-tains all the fuel assemblies, weighs 838,000 pounds, has a diameter of 14 feet, is 39 feet high, and has steel walls that are 8 V2 inches thick.
F-1M b.,
REACTOR VESSEL Figure 6: The reactor core at Davis-Besse contains 177 fuel assemblies. Each assembly contains 208 fuel rods.
Each fuel rod is filled with approximately five pounds of fuel pellets, each pellet is approximately 3/8 inch diameter and 5/8 inch long.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Fission Control Raising or lowering control rod assemblies into the reactor core controls the fission rate. Each assembly consists 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, high-purity boric acid is con-centrated or diluted in the coolant to achieve the desired level of fission. Boron-10 readily ab-sorbs free neutrons, forming Boron-11, removing the absorbed neutrons from the chain reaction.
Reactor Types Virtually all of the commercial reactors in this country are either boiling water reactors (BWRs) or pressurized water reactors (PWRs). Both types are also called light water reac-
.tors (LWRs) because their coolant, or medium to transfer heat, is ordinary water, which contains
'the light isotope of Hydrogen. Some reactors use the heavy isotope of Hydrogen (deuterium) in the reactor coolant. Such reactors are called heavy water reactors (HWRs).
In BWRs, water passes through the core and boils into steam. The steam passes through separa-tors, which remove water droplets. The steam then travels to dryers before entering the turbine.
After passing though the turbine the steam is condensed back into water and returns to the core to repeat the cycle.
In PWRs, the reactor water or coolant is pressurized to prevent it from boiling. The reactor water is then pumped to a steam generator (heat exchanger) where its heat is transferred to a secon-dary water supply. The secondary water inside the generator boils into steam, which is then used to turn the turbine. This steam is then condensed back into water and returned to the steam gen-erator. Davis-Besse uses a PWR design.
The following paragraphs describe the various systems illustrated in Figure 7. Major systems in the Davis-Besse Station are assigned a different color in the figure.
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CONTAINMENT V1 TURBINE BUILDING-AUXILIARY 0
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Station Systems Containment Building and Fission Product Release Barriers The Containment building houses the reactor vessel, the pressurizer, two steam generators, the Reactor Coolant Pumps and Reactor Coolant System piping. The building is constructed of an inner 1 -1/2 inch thick steel liner or Containment vessel, and the Shield Building with steel-reinforced concrete walls 2 feet thick. The shield building protects the containment vessel from a variety of environmental factors and provides an area for a negative pressure boundary around the steel Containment vessel. In the event that the integrity of the Containment vessel is com-promised (e.g., a crack develops), this negative pressure boundary ensures that any airborne ra-dioactive contamination present in the containment vessel is prevented from leaking out into the environment. This is accomplished by maintaining the pressure inside the Shield Building lower than that outdoors, thus forcing clean outside air to leak in, while making it impossible for the contaminated air between the Containment vessel and the Shield Building to leak out. The Con-tainment vessel is the third in a series of barriers that prevent the release of fission products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel cladding itself. The second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and associated piping.
The Steam Generators The steam generators perform the same function as a boiler at a fossil-fueled power station.
The steam generator uses the heat of the primary coolant inside the steam generator tubes to boil the secondary side feedwater (secondary coolant). Fission heat from the reactor core is trans-ferred to the steam generator in order to provide the steam necessary to drive the turbine. How-ever, heat must also be removed from the core even after reactor shutdown in order to prevent damage to the fuel cladding. Therefore, pumps maintain a continuous flow of coolant through the reactor and steam generator. Primary loop water (green in Figure 7) exits the reactor at ap-proximately 606*F, passes through the steam generator, transferring some of its heat energy to the Secondary loop water (blue in Figure 7) without actually coming in contact with it. Primary coolant water exits the steam generator at approximately 558'F to be circulated back into the re-actor where it is again heated to 606'F as it passes up through the fuel assemblies. Under ordi-nary conditions, water inside the primary system would boil long before it reached such temperatures. However, it is kept under a pressure of approximately 2,200 pounds-per-square-inch (psi) at all times. This prevents the water from boiling and is the reason the reactor at Davis-Besse is called a Pressurized Water Reactor. Secondary loop water enters the base of the steam generator at approximately 450'F and under 1,100 psi pressure. At this pressure, the water can easily boil into steam as it passes over the tubes containing the primary coolant water.
Both the primary and the secondary coolant water are considered closed loop systems. This means that they are designed not to come in physical contact with one another. Rather, the cool-ing water in each loop transfers heat energy by convection. Convection is a method of heat transfer that can occur between two fluid media. It is the same process by which radiators are used to heat homes. The water circulating inside the radiator is separated from the air (a "fluid" medium) by the metal piping.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report The Turbine Generator The turbine, main generator, and the condenser are all housed in what is commonly referred to as the Turbine Building. The purpose of the turbine is to convert the thermal energy of the steam produced in the steam generator (referred to as main steam, red in Figure 7) to rotational energy of the turbine generator shaft. The turbine at Davis-Besse is actually composed of one six-stage high-pressure turbine and two seven-stage low-pressure turbines aligned on a common shaft. A turbine stage refers to a set of blades. Steam enters at the center of each turbine and moves outward along the shaft in opposite directions through each successive stage of blading.
As the steam passes over the turbine blades, it loses pressure. Thus, the blades must be propor-tionally larger in successive stages to extract enough energy from the steam to rotate the shaft at the correct speed.
The purpose of the main generator is to convert the rotational energy of the shaft to electrical energy for commercial usage and support of station systems. The main generator is composed of two parts, a stationary stator that contains coils of copper conductors, and a rotor that supplies a rotating magnetic field within the coils of the stator. Electrical current is generated in the stator portion of the main generator. From this point, the electric current passes through a series of transformers for transmission and use throughout northern Ohio.
The Condenser After the spent steam in the secondary loop (blue in Figure 7) passes through the High and Low Pressure Turbines, it is collected in the condenser, which is several stories tall and contains more than 70,000 small tubes. Circulating Water (yellow in Figure 7) goes to the Cooling Tower after passing through the tubes inside the Condenser. As the steam from the Low Pressure Tur-bines passes over these tubes, it is cooled and condensed. The condensed water is then purified and reheated before being circulated back into the steam generator again in a closed loop system.
Circulating water forms the third (or tertiary) and final loop of cooling water used at the Davis-Besse Station.
Similar to the primary to secondary interface, the secondary-to-tertiary interface is based on a closed-loop design. The Circulating Water, which is pumped through the tubes in the Water Box, is able to cool the water in the Condenser by the processes of conduction and convection.
Even in the event of a primary-to-secondary leak, the water vapor exiting the Davis-Besse Cool-ing Tower would remain non-radioactive. Closed loops are an integral part of the design of any nuclear facility. This feature greatly reduces the chance of environmental impact from Station operation.
The Cooling Tower The Cooling Tower at Davis-Besse is easily the most noticeable feature of the plant. The tower stands 493 feet high and the diameter of the base is 411 feet. Two nine-foot diameter pipes circu-late 480,000 gallons of water per minute to the tower. Its purpose is to recycle water from the Condenser by cooling and returning it.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report After passing through the Condenser, the Circulating Water has warmed to approximately 1 00°F.
In order to cool the water back down to 70'F, the Circulating Water enters the Cooling Tower forty feet above the ground. It is then sprayed evenly over a series of baffles called fill sheets, which are suspended vertically in the base of the tower. A natural draft of air is swept upward through these baffles and cools the water by evaporation. The evaporated water exits the top of the Cooling Tower as water vapor.
As much as 10,000 gallons of water per minute are lost to the atmosphere via the Cooling Tower. Even so, approximately 98 percent of the water drawn from Lake Erie for station opera-tion can be recycled through the Cooling Tower for reuse. A small portion of the Circulating Water is discharged back to Lake Erie at essentially the same temperature it was withdrawn ear-lier. The slightly warmer water has no adverse environmental impact on the area of lake sur-rounding the discharge point.
Miscellaneous Station Safety Systems The orange system in Figure 7 is part of the Emergency Core Cooling System (ECCS) housed in the Auxiliary Building of the station. The ECCS consists of three overlapping means of keeping the reactor core covered with water, in the unlikely event of a Loss-of-Coolant Accident (LOCA), thereby protecting the fuel cladding barrier against high-temperature failure. Depend-ing on the severity of the loss of pressure inside the Primary System, the ECCS will automati-cally channel borated water into the Reactor by using High Pressure Injection Pumps, a Core Flood Tank, or Low Pressure Injection Pumps. Borated water can also be sprayed from the ceiling of the Containment Vessel to cool and condense any steam that escapes the Primary Sys-tem.
The violet system illustrated in Figure 7 is responsible for maintaining the Primary Coolant water in a liquid state. It accomplishes this by adjusting the pressure inside the Primary System. Heat-ers inside the Pressurizer turn water into steam. This steam takes up more space inside the Pres-surizer, thereby increasing the overall pressure inside the Primary System. The Pressurizer is equipped with spray heads that shower cool water over the steam in the unit. In this case, the steam condenses and the overall pressure inside the Primary System drops. The Quench Tank is where excess steam is directed and condensed for storage.
The scarlet system in Figure 7 is part of the Auxiliary Feedwater System, a key safety system in event the main feedwater supply (blue in Figure 7) to the Steam Generator is lost. Following a 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 Turbine Building along with the Turbine, Main Generator, and the Condenser.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Reactor Safety and Summary Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb, because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. Also, many safety features are equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the local environment. Davis-Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features. If one sys-tem should fail, there are still back-up systems to assure the safe operation of the Station. During normal operation, the Reactor Control System regulates the power output by adjusting the posi-tion of the control rods. The Reactor can be automatically shut down by a separate Reactor Pro-tection System, which 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 wa-ter into the reactor automatically if the reactor coolant pressure drops below a predetermined level.
The Davis-Besse Nuclear Power Station was designed, constructed, and operates to produce a reliable, safe, and environmentally sound source of electricity.
Radioactive Waste Many of the activities we depend on in our everyday lives produce radioactive waste by-products.
Nuclear energy, industrial processes, and medical treatments are some of these activities. These by-products are managed and disposed of under strict requirements set by the federal govern-ment. With the exception of used nuclear fuel assemblies, these by-products produced at com-mercial power plants are referred to as low level radioactive waste.
Low Level Radioactive Waste Low level radioactive waste consists mainly of ordinary trash and other items that have become contaminated with radioactive materials. It includes plastic gloves and other protective clothing, machine parts and tools, medical and laboratory equipment, filters, resins, and general scrap.
The radioactive material in low level radioactive waste emits the same types of radiation that naturally occurring radioactive materials tend to emit. Most low level activity in radioactive waste decay to background levels within months or years. Nearly all activity diminishes to stable materials in less than 300 years.
Davis-Besse currently ships low-level radioactive waste to facilities in Tennessee for waste minimization processing prior to disposal. Davis-Besse has the capacity to store low-level waste produced on site for several years in the Low Level Radioactive Waste Storage Facility (LLRWSF), should these facilities close.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report High Level Nuclear Waste Like any industrial or scientific process, nuclear energy does produce waste. The most radioac-tive is defined as "high-level" waste (because it has high levels of radioactivity). Ninety-nine percent of high-level waste from nuclear plants is used nuclear fuel. The fuel undergoes certain changes during fission. Most of the fragments of fission, pieces that are left over after the atom is split, are radioactive. After a period of time, the fission fragments trapped in the fuel assem-blies reduce the efficiency of the chain reaction. The oldest fuel assemblies are removed from the reactor and replaced with fresh fuel at 24 month intervals.
High-level nuclear waste volumes are small. Davis-Besse produces about 30 tons of used fuel every 24 months. All the used fuel produced by all America's nuclear energy plants since the first plant started operating over 30 years ago would cover an area the size of a football field about five yards deep. All of America's nuclear plants combined produce only 3,000 tons of used fuel each year. By contrast, the U.S. produces about 300,000,000 tons of chemical waste annu-ally. Also, nuclear waste slowly loses its radioactivity, but some chemical waste remains hazard-ous indefinitely.
Davis-Besse presently stores most of its used fuel in a steel-lined water-filled concrete vault in-side the plant. The Department of Energy is charged with constructing a permanent high-level waste repository for all of the nation's nuclear plants. By law, the Department of Energy was required to accept fuel from utilities by the end of 1998. Until the permanent DOE site is devel-oped, nuclear plants will be responsible for the continued safe storage of high-level waste. At Davis-Besse, the fuel pool reached its capacity in 1996. At the end of 1996, Davis-Besse began the process of moving the older fuel assemblies that no longer require water cooling to air-cooled concrete shielded canisters. These will remain onsite until the Department of Energy facilities are ready to receive them. Dry fuel storage is already used in many countries, including Canada, and in the U.S. at nuclear plants in Arkansas, Colorado, Maryland, Michigan, Minnesota, Vir-ginia, Wisconsin and South Carolina. Figure 8 below illustrates the Dry Fuel Storage module arrangement at Davis-Besse.
In 2001, work was performed to increase the storage capacity of the Spent Fuel Pool. The pool remains the same size, however, removing old storage racks and replacing them with new ones changed the configuration of storage. This allows the site to safely hold all the fuel used during its 40 years of expected life. This modification was completed in April of 2002.
Davis-Besse added the Old Steam Generator Storage Facility (OSGSF) in 2011 to house the Re-actor Vessel Closure Head, Service Support Structure and Control Rod Drive mechanisms re-moved during the 17M outage. Two Steam Generators and two Reactor Coolant System Hot Leg piping sections, which will be replaced during 18RFO in 2014, will also be stored there. The re-enforced concrete building is comprised of three sections, the largest of which will contain the old steam generators and hot legs. The old reactor vessel head is kept in another bay and is com-pletely enclosed with concrete for shielding. The dose rates outside the walls of this section are at background levels. The third section is the vestibule, which provides access to the other two sec-tions. Both the steam generator and reactor vessel head sections have floor drains that lead to a sump that can be monitored and sampled from the vestibule. Quarterly surveys are performed by Radiation Protection personnel to monitor the dose rates and tritium production.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report zLU wU C
Figure 8: Dry Fuel Storage Module Arrangement 21
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Description of the Davis-Besse Site The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the south-western shore of Lake Erie, just north of the Toussaint River. The site lies north and east of Ohio State Route 2, approximately 10 miles northwest of Port Clinton, 7 miles north of Oak Harbor, and 25 miles east of Toledo, Ohio (Figure 9).
This section of Ohio is flat and marshy, with maximum elevations of only a few feet above the level of Lake Erie. The area originally consisted of swamp forest and marshland, rich in wildlife but unsuitable for settlement and farming. During the nineteenth century, the land was cleared and drained, and has been farmed successfully since. Today, the terrain consists of farmland with marshes extending in some places for up to two miles inland from the Sandusky Lake Shore Ridge.
Lzake EJrie A
Figure 9: Davis-Besse is near Oak Harbor, Port Clinton, and the Ottawa National Wildlife Refuge.
The Davis-Besse site is mainly comprised of marshland, with a small portion consisting of farm-land.
The marshes are part of a valuable ecological resource, providing a breeding ground for a variety of wildlife, and a refuge for migratory birds. The site includes a tract known as Navarre Marsh, which was acquired from the U.S. Bureau of Sport Fisheries and Wildlife, Department of the Interior. In 1971, Toledo Edison purchased the 188-acre Toussaint River Marsh. The Tous-saint River Marsh is contiguous with the 610-acre Navarre Marsh section of the Ottawa National Wildlife Refuge.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report The immediate area near Davis-Besse is sparsely populated. The year 2010 Census listed the population of Ottawa County at 41,428. The incorporated communities nearest to Davis-Besse are:
Port Clinton - 10 miles southeast, population 6,391 Oak Harbor - 7 miles south, population 2,805 Rocky Ridge - 7 miles west southwest, population 386 Toledo (nearest major city) - 25 miles west, population 287,208 There are some residences along the lakeshore used mainly as summer homes. However, the ma-jor resort area of the county is farther east, around Port Clinton, Lakeside, and the Bass Islands.
The majority of non-marsh areas around the Davis-Besse site are used for farming. The major crops include soybeans, corn, wheat, oats, hay, fruits and vegetables. Meat and dairy animals are not major sources of income in the area. The main industries within five miles of the site are lo-cated inErie Industrial Park, about four miles southeast of the station.
Most of the remaining marshes in the area have been maintained by private hunting clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife. The State of Ohio Department of Natural Resources operates many wildlife and recrea-tional areas within 10 miles of the Station. These include Magee Marsh, Turtle Creek and Crane Creek Wildlife Research Station. Magee Marsh and Turtle Creek lie between three and six miles WNW of the Station. Magee Marsh is a wildlife preserve that allows public fishing, nature study, and a controlled hunting season. Turtle Creek, a wooded area at the southern end of Magee Marsh, offers boating and fishing. Crane Creek is adjacent to Magee Marsh, and is a popular birding and hunting area. The Ottawa National Wildlife Refuge, which is operated by the U.S. Fish and Wildlife Service, lies four to nine miles WNW of the Site, immediately west of Magee Marsh.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report References
- 1. "Basic Radiation Protection Criteria," Report No. 39, National Council on Radiation Protec-tion and Measurement, Washington, D.C. (January 1971).
- 2. "Cesium-137 from the Environment to Man: Metabolism and Dose," Report No. 52, National Council on Radiation Protection and Measurements, Washington, D.C. (January 1977).
- 3. Deutch, R., "Nuclear Power, A Rational Approach," Fourth edition, GP Courseware, Inc.,
Columbia, MD. (1987).
- 4. Eisenbud, M., "Environmental Radioactivity," Academic Press, Inc., Orlando, FL. (1987).
- 5. "Environmental Radiation Measurements," Report No. 50, National Council on Radiation Protection and Measurements, Washington, D.C. (December 1976).
- 6. "Exposure of the Population in the United States and Canada from Natural Background Ra-diation," Report No. 94, National Council on Radiation Protection and Measurements, Wash-ington, D.C. (December 1987).
- 7. "Health Effects of Exposure to Low Levels of Ionizing Radiation: BEIR V," Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects Research Commis-sion on Life Sciences, National Research Council, National Academy Press, Washington, D.C. (1990).
- 8. Hendee, William R., and Doege, Theodore C., "Origin and Health Risks of Indoor Radon,"
Seminars in Nuclear Medicine, Vol. XVIII, No. 1, American Medical Association, Chicago, IL. (January 1987).
- 9. Hurley, P., "Living with Nuclear Radiation," University of Michigan Press, Ann Arbor, MI.
(1982).
- 10. "Indoor Air Quality Environmental Information Handbook: Radon," prepared for the United States Department of Energy, Assistant Secretary for Environment, Safety and Health, by Mueller Associated, Inc., Baltimore, MD. (January 1986).
- 11. Introduction to Davis-Besse Nuclear Power Station Plant Technology, July 1992, Rev. 4, Pg.2-9.
- 12. "Ionizing Radiation Exposure of the Population of the United States," Report No. 93, Na-tional Council on Radiation Protection and Measurements, Washington, D.C. (September 1987).
- 13. "Natural Background Radiation in the United States," Report No. 45, National Council on Radiation Protection and Measurements, Washington, D.C. (November 1975).
24
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report
- 14. "Nuclear Energy Emerges from 1980's Poised for New Growth," U.S. Council for Energy Awareness, Washington, D.C. (1989).
- 15. "Nuclear Power: Answers to Your Questions," Edison Electric Institute, Washington, D.C.
(1987).
- 16. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurement, Washington, D.C. (De-cember 1987).
- 17. "Radiation Protection Standards," Department of Environmental Sciences and Physiology and the Office of Continuing Education, Harvard School Of Public Health, Boston, MA.
(July 1989).
- 18. Radiological Environmental Monitoring Report for Three Mile Island Station," GPU Nuclear Corporation, Middletown, PA. (1985).
- 19. "Sources, Effects and Risk of Ionizing Radiation," United Nations Scientific Committee on the Effects of Atomic Radiation, 1988 Report to the General Assembly, United Nations, New York (1988).
- 20. "Standards for Protection Against Radiation," Title 10, Part 20, Code of Federal Regulation, Washington, D.C. (1988).
- 21. "Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50, Code of Federal Regulations, Washington, D.C. (1988).
- 22. "Environmental Radiation Protection Standard for Nuclear Power Operations," Title 40, Part 190, Code of Federal Regulations, Washington, D.C. (1988).
- 23. "Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1979).
- 24. Site Environmental Report, Femald Environmental Management Project, United States De-partment of Energy (June 1993).
77, National Council on Radiation Protection and Measurements, Washington, D.C. (1984).
- 26. "Evaluation of Occupational and Environmental Exposures to Radon and Radon daughter in the United States,"Report No. 78, National Council on Radiation Protection and Measure-ments, Washington, D.C. (1984).
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at Davis-Besse for several reasons: to provide a supplementary check on the adequacy of containment and effluent controls, to assess the radiological impact of the Station's. operation on the surrounding area, and to determine compliance with applicable radiation protection guides and standards. The REMP was established in 1972, five years before the Station became operational. This pre-operational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of Davis-Besse. After Davis-Besse became operational in 1977, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas.
A variety of environmental samples are collected as part of the REMP at Davis-Besse. The se-lection of sample types is based on the established critical pathways for the transfer of radionu-clides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population char-acteristics, and land usage in the area of interest. The selection of sampling frequencies for the various environmental media is based on the radionuclides of interest, their respective half-lives, and their effect in both biological and physical environments.
A description of the REMP at Davis-Besse is provided in the following section. In addition, a brief history of analytical results for each sample type collected since 1972, and a more detailed summary of the analyses performed during this reporting period, is also provided.
Pre-operational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental moni-toring prior to constructing the facility. This pre-operational surveillance program is for the col-lection of data needed to identify critical pathways, including selection of radioisotope and sample media combinations for the surveillance conducted after facility operations begin. Ra-diochemical analyses performed on samples should include nuclides that are expected to be re-leased during normal facility operations, as well as typical fallout radionuclides and natural background radioactivity. All environmental media with a potential to be affected by facility op-eration, as well as those media directly in the critical pathways, should be sampled during the pre-operational phase of the environmental surveillance program.
The pre-operational surveillance design, including nuclide/media combinations, sampling fre-quencies and locations, collection techniques, and radiochemical analyses performed, should be carefully considered and incorporated in the design of the operational surveillance program. In 26
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report 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. Data collection during the pre-operational phase should be planned to provide a com-prehensive database for evaluating any future changes in the environment surrounding the plant.
Davis-Besse began its pre-operational environmental surveillance program five years before the Station began producing power for commercial use in 1977. Data accumulated during that time provides an extensive database from which Station personnel are able to identify trends in the radiological characteristics of the local environment. The environmental surveillance program at Davis-Besse will continue after the Station has reached the end of its economically useful life and decommissioning has begun.
Operational Surveillance Program Objectives The operational phase of the environmental surveillance program at Davis-Besse was designed with the following objectives in mind:
" to fulfill the obligations of the radiological surveillance sections of the Sta-tion's Technical Specifications and Offsite Dose Calculation Manual
- to determine whether any significant increase in the concentration of radionu-clides in critical pathways occurs
" to identify and evaluate the buildup, if any, of radionuclides in the local envi-ronment, or any changes in normal background radiation levels
" to verify the adequacy of Station controls for the release of radioactive mate-rials Quality Assurance An important part of the environmental monitoring program at Davis-Besse is the Quality Assurance (QA) Program, which is conducted in accordance with the guidelines specified in NRC Regulatory Guide 4.15,."Quality Assurance for Radiological Monitoring Programs". The QA Program is designed to identify possible deficiencies in the REMP so that corrective actions can be initiated promptly. Davis-Besse's Quality Assurance program also provides confidence in the results of the REMP through:
- performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keeping
- performing audits of contractor laboratories which analyze the environmental samples
- requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross Check Program
- requiring analytical contractor laboratories to split samples for separate analy-sis followed by a comparison of results
- splitting samples prior to analysis by independent laboratories, and then com-paring the results for agreement 27
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report requiring analytical contractor laboratories to perform in-house spiked sample analyses Quality Assessment audits and inspections of the Davis-Besse REMP are performed by the FirstEnergy Nuclear Operating Company QA Department and the NRC. In addition, the Ohio Department of Health (ODH) also performs independent environmental monitoring in the vicin-ity of Davis-Besse. The types of samples collected and list of sampling locations used by the ODH were incorporated in Davis-Besse's REMP, and the analytical results from their program can be compared to Davis-Besse's. This practice of comparing results from identical samples, which are collected and analyzed by different parties, provides a valuable tool to verify the qual-ity of the laboratories' analytical procedures and data generated.
In 1987, environmental sampling personnel at Davis-Besse incorporated their own QA program into the REMP. Duplicate samples, called quality control samples, were collected at several lo-cations. These duplicate samples were assigned different identification numbers than the num-bers assigned to the routine samples. This ensured that the analytical laboratory would not know the samples were identical. The laboratory results from analysis of the quality control samples and the routine samples could then be compared for agreement. Quality control sampling has been integrated into the program and has become an important part of the REMP since 1987.
Quality control sampling locations are changed frequently in order to duplicate as many sampling locations as possible, and to ensure the contractor laboratory has no way of correctly pairing a quality control sample with its routine sample counterpart.
Program Description The Radiological Environmental Monitoring Program (REMP) at Davis-Besse is conducted in accordance with Title 10, Code of Federal Regulations, Part 50; NRC Regulatory Guide 4.8; the Davis-Besse Nuclear Power Station Operating License, Sections 5.6.1 and 5.6.2 of Davis-Besse Technical Specifications, the Davis-Besse Offsite Dose Calculation Manual (ODCM) and Station Operating Procedures. Samples are collected weekly, monthly, quarterly, semiannually, or annu-ally, depending upon the sample type and nature of the radionuclides of interest. Environmental samples collected by Davis-Besse personnel are divided into four general types:
- atmospheric -- including samples of airborne particulate and airborne radio-iodine
- terrestrial -- including samples of milk, groundwater, broad leaf vegetation, fruits, animal/wildlife feed, soil, and wild and domestic meat 0 aquatic -- including samples of treated and untreated surface water, fish, and shoreline sediments 0 direct radiation -- measured by thermoluminescent dosimeters All environmental samples are labeled using a sampling code. Table 2 provides the sample codes and collection frequency for each sample type.
REMP samples are collected onsite and offsite up to 25 miles away from the Station. Sampling locations may be divided into two general categories: indicator and control. Indicator locations are those which would be most likely to display the effects caused by the operation of Davis-Besse, and are located within five miles of the station. Control locations are those which should 28
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report be unaffected by Station operations, and are more than five miles from the Station. Data from indicator locations are compared with data from the control locations. This comparison allows REMP personnel to take into account naturally-occurring background radiation or fallout from weapons testing in evaluating any radiological impact Davis-Besse has on the surrounding envi-ronment. Data from indicator and control locations are also compared with pre-operational data to determine whether significant variations or trends exist.
Since 1987 the REMP has been reviewed and modified to develop a comprehensive sampling program adjusted to the current needs of the utility. Modifications have included additions of sampling locations above the minimum amount required in the ODCM and increasing the num-ber of analyses performed on each sample. Besides adding new locations, duplicate or Quality Control (QC) sample collection was initiated to verify the accuracy of the lab analyzing the envi-ronmental. samples. These additional samples are referred to as the REMP Enhancement Sam-ples. Approximately 2,000 samples were collected and over 2,300 analyses were performed during 2011. In addition, 15% of the sampling locations were quality control sampling locations.
Table 3 shows the number of the sampling location and number collected for each type.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 2: Sample Codes and Collection Frequencies Sample Type Airborne Particulate Airborne Iodine Thermoluminescent Dosimeter Milk Groundwater Broadleaf Vegetation Surface Water - Treated Surface Water -
Untreated Fish Shoreline Sediment Soil Wildlife Feed Meat-Wild Fruit Sample Code AP Al TLD Collection Frequency Weekly Weekly Quarterly, Annually MIL WW BLV SWT SWU FIS SED Sol WFE WME FRU Monthly (semi-monthly during grazing season)
Quarterly (when available)
Monthly (when available)
Weekly Weekly Annually Semiannually Annually Annually Annually Annually 30
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 3: Sample Collection Summary Sample Type (Remarks)
Collection Type*/
Frequency**
Number of Locations Number of Samples Collected Number of Samples Missed Atmospheric Airborne Particulates Airborne Radioiodine Terrestrial Milk (Jan.-Dec.)
Groundwater Wild Meat Broadleaf Vegetation Fruit Soil Animal/Wildlife Feed Aquatic Treated Surface Water Untreated Surface Water Fish (2 species)
Shoreline Sediments Direct Radiation Thermoluminescent Dosimeters (TLD)
C/W C/W 10 10 529 529 1
1 G/M G/Q**
G/A 1
3 2
12 8
2 G/M G/A G/A G/A Comp/WM G/WM***
G/WM***
Comp/WM G/A G/SA 3
3 10 3
4 1
3 3
2 5
88 88 9
3 10 3
212 53 159 159 6
10 350 86 0
0 0
0 0
0 0
0 0
0 0
0 0
2 2
- Type of Collection: C = Continuous; G = Grab; Comp = Composite
- Frequency of Collection: WM = Weekly composite Monthly; W = Weekly, M = Monthly; Q = Quarterly when available; SA = Semiannually; A = Annually
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Sample Analysis When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Davis-Besse REMP include:
Gross beta analysis measures the total amount of beta emitting radioactive material present in a sample. Beta radiation may be released by many different radionuclides. Since beta decay gives a continuous energy spectrum rather than the discrete lines or "peaks" associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal concentra-tions of beta emitting radionuclides; it does not identify specific radionuclides. Gross beta analy-sis merely acts as a tool to identify samples that may require further analysis.
Gamma spectral analysis provides more specific information than does gross beta analysis.
Gamma spectral analysis identifies each gamma emitting radionuclide present in the sample, and the amount of each nuclide present. Each radionuclide has a very specific "fingerprint" that al-lows for swift and accurate identification. For example, gamma spectral analysis can be used to identify the presence and amount of Iodine-131 in a sample. Iodine-131 is a man-made radioac-tive isotope of Iodine that may be present in the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power stations.
Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the amount present. As discussed in the Introduction section, tritium is an isotope of Hydrogen that emits low energy beta particles.
Strontium analysis identifies the presence and amount of Strontium-89 and Strontium-90 in a sample. These man-made radionuclides are found in the environment as a result of fallout from nuclear weapons testing. Strontium is usually incorporated into the pool of the biosphere. In other words, it accumulates in living organisms, where it is stored in the bone tissue. The princi-pal Strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from airborne releases.
Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure. Table 4 provides a list of the analyses performed on environ-mental samples collected for the Davis-Besse REMP.
Often samples will contain little radioactivity, and may be below the lower limit of detection for the particular type of analysis used. The lower limit of detection (LLD) is the smallest amount of sample activity that can be detected with a reasonable degree of confidence at a predetermined level. When a measurement of radioactivity is reported as less than LLD (<LLD), it means that the radioactivity is so low that it cannot be accurately measured with any degree of confidence by a particular method for an individual analysis.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples Sample Type Atmospheric Monitoring Airborne Particulate Airborne Radioiodine Terrestrial Monitoring Analyses Performed Gross Beta Gamma Spectroscopy Strontium-89 Strontium-90 Iodine-131 Milk Groundwater Broadleaf Vegetation and Fruits Wildlife Feed Soil Wild Animal Meat Gamma Spectroscopy Iodine-131 Strontium-89 Strontium-90 Stable Calcium Stable Potassium Gross Beta Gamma Spectroscopy Tritium Strontium-89 Strontium-90 Gamma Spectroscopy Iodine-131 Strontium-89 Strontium-90 Gamma Spectroscopy Gamma Spectroscopy Gamma Spectroscopy 33
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples (continued)
Sample Type Aquatic monitoring Analyses Performed Untreated Surface Water Treated Surface Water Fish Gross Beta Gamma Spectroscopy Tritium Strontium-89 Strontium-90 Gross Beta Gamma Spectroscopy Tritium Strontium-89 Strontium-90 Iodine-131 Gross Beta Gamma Spectroscopy Gamma Spectroscopy Shoreline Sediment Direct Radiation Monitoring Thermoluminescent Dosimeters Gamma Dose Sample History Comparison The measurement of radioactive materials present in the environment will depend on factors such as weather or variations in sample collection techniques or sample analysis. This is one reason why the results of sample analyses are compared with results from other locations and from ear-lier years. Generally, the results of sample analyses are compared with pre-operational and op-erational data. Additionally, the results of indicator and control locations are also compared.
This allows REMP personnel to track and trend the radionuclides present in the environment, to assess whether a buildup of radionuclides is occurring and to determine the effects, if any, the operation of Davis-Besse is having on the environment. If any unusual activity is detected, it is investigated to determine whether it is attributable to the operation of Davis-Besse, or to some other source such as nuclear weapons testing.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Atmospheric Monitoring
- Airborne Particulates: No radioactive particulates have been detected as a result of Davis-Besse's operation. Only natural and fallout radioactivity from nuclear weapons test-ing and the 1986 nuclear accident at Chernobyl have been detected.
- Airborne Radioiodine: Radioactive Iodine-131 fallout was detected in 1976, 1977, and 1978 from nuclear weapons testing, and in 1986 (0.12 to 1.2 picocuries per cubic meter) from the nuclear accident at Chernobyl. Iodine-131 was detected in all ten air sample locations over a four-week period between March 22 and April 12, 2011 following the Fukushima, Japan disaster. There was virtually no difference in iodine-131 concentration in control and indicator locations during this period.
Terrestrial Monitoring:
- Groundwater: Tritium was not detected above the lower limit of detection during 2011 in any REMP groundwater samples.
- Milk: Iodine-131 from nuclear weapons testing fallout was detected in 1976 and 1977 at concentrations of 1.36 and 23.9 picocuries/liter respectively. In 1986, concentrations of 8.5 picocuries/liter were detected from the nuclear accident at Chernobyl. No Iodine-131 detected has been attributable to the operation of Davis-Besse. There was no iodine detected in milk samples following the Fuku-shima Daiichi Nuclear Station disaster.
" Wild Meat: Only naturally-occurring Potassium-40 and very low Cesium-137 from fallout activity has been detected in meat samples. Potassium-40 has ranged from 1.1 to 4.6 picocuries/gram weight (wet). Cesium-137 was detected in 1974, 1975, and 1981 due to fallout from nuclear weapons testing.
- Broadleaf Vegetation and Fruits: Only naturally-occurring radioactive material and material from nuclear weapons testing have been detected.
" Soil: Only natural background and material from nuclear weapons testing and the 1986 nuclear accident at Chemobyl have been detected.
" Animal/Wildlife Feed: Only natural background and material from weapons test-ing have been detected.
Aquatic Monitoring
- Surface Water (Treated and Untreated): Historically, tritium has been detected sporadically at low levels in treated and untreated surface water at both Control and Indicator locations. During 2011 there were two samples of Untreated Water that showed detectable tritium which were likely due to operation of Davis-Besse Nuclear Power Station.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Fish: Only natural background radioactive material and material from nuclear testing have been detected.
- Shoreline Sediments: Only natural background radiation, material from nuclear testing and the 1986 nuclear accident at Chernobyl have been detected.
Direct Radiation Monitoring Thermoluminescent Dosimeters (TLDs): The annual gamma dose rates for the current reporting period recorded by TLDs averaged 68.7 millirem/year at Control locations, and 61.7 millirem/year at Indicator locations. No increase above natural background radiation attributable to the operation of Davis-Besse has been ob-served.
2011 Program Anomalies On 9/6/11 ODCM-required Air/Particulate sampler at control location T-11 was found shut down with only 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on the timer. A blown fuse was replaced and the sampler was restarted. En-hancement control sample T-9 was substituted in its place to satisfy ODCM requirements.
Abnormal Releases There was one abnormal gaseous release during 2011, when two Auxiliary Steam valves lifted unexpectedly for 3 seconds during plant startup on December 5. A calculated release of 1.OE-06 curies of tritium occurred with an associated total body dose of 3.OE-1 1 mrem.
Atmospheric Monitoring Air Samples Environmental air sampling is conducted to detect any increase in the concentration of airborne radionuclides that may be inhaled by humans or serve as an external radiation source. Inhaled radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air sam-ples collected by the Davis-Besse REMP include airborne particulate and airborne radioio-dine.
Samples are collected weekly with low volume vacuum pumps, which draw a continuous sample through a glass fiber filter and charcoal cartridge at a rate of approximately one cubic foot per minute. Airborne particulate samples are collected on 47 mm diameter filters. Charcoal car-tridges are installed downstream of the particulate filters to sample for the airborne radioiodine.
The airborne samples are sent to'an offsite contract laboratory for analysis. At the laboratory, the airborne particulate filters are stored for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before they are analyzed to allow for the decay of naturally-occurring short-lived radionuclides. However, due to the short half-life of iodine 131 (approximately eight days), the airborne radioiodine cartridges are analyzed upon receipt by the contract laboratory.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Airborne Particulate Davis-Besse has ten continuous air samplers that monitor for air particulate and iodine. There are six indicator locations including four around the site boundary (T-1, T-2, T-3, and T-4), one at Sand Beach (T-7), and another at a local farm (T-8). There are four control locations, Oak Harbor (T-9), Port Clinton (T-11), Toledo (T-12) and Crane Creek (T-27). Gross beta analysis is performed on each of the weekly samples.
Each quarter, the filters from each location are combined (composite) and analyzed for gamma-emitting radionuclides, Strontium-89 and Strontium-90. Beta-emitting radionuclides were de-tected at an average concentration of 0.026 pCi/m3 at indicator locations and 0.027 pCi/m3 at control locations.
Beryllium-7 was the only gamma-emitting radionuclide detected by the gamma spectroscopic analysis of the quarterly composites.
Beryllium-7 is a naturally-occurring radionuclide produced in the upper atmosphere by cosmic radiation. No other gamma-emitting radionuclides were detected above their respective LLDs.
Strontium-89 and Strontium-90 were not detected above their LLDs. These results show no ad-verse change in radioactivity in air samples attributable to the operation of the Davis-Besse Nu-clear Power Station in 2011.
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Airborne Iodine-131 Airborne iodine-131 samples are collected at the same ten locations as the airborne particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly, sealed in separate collection bags and sent to the laboratory for gamma analysis. Following the Fukushima Daiichi Nuclear Station disaster in March, iodine-131 was detected in all air samples for a four-week period between March 22 and April 19, 2011. The concentrations of Iodine-131 were nearly identical at both control and indicator locations and the highest concentration was 0.166 pCi/meter3 at control location T-12.
2011 Ai rborne Gross Beta Q04 Q(Q5 Q03 C25 Qcp-Q015 0-Figure 10. Concentrations of beta-emitting radionuclides in airborne particulate samples were nearly identical at indicator and control locations during 2011.
38
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 5: Air Monitoring Locations Sample Location Number T-l*
T-2*
T-3*
T-4 T-7*
Type of Location I
I I
I I
Location Description Site boundary, 0.6 miles ENE of Station Site boundary, 0.9 miles E of Station Site boundary, 1.4 miles ESE of Station Site boundary, 0.8 miles S of Station Sand Beach, main entrance, 0.9 miles NW of Station Earl Moore Farm, 2.7 miles WSW of Station Oak Harbor Substation, 6.8 miles SW of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 20.7 miles WNW of Station Crane Creek, 5.3 miles WNW of Station T-8 T-9 T-11*
T-12 T-27 I
C C
C C
I = Indicator C = Control
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Terrestrial Monitoring The collection and analysis of groundwater, milk, meat, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. Animal and wildlife feed samples provide additional information on radionuclides that may be present in the food chain. The data from soil sampling provides information on the deposition of radionuclides from the atmosphere.
Many radionuclides are present in the enviromnment due to sources such as cosmic radiation and fallout from nuclear weapons testing. Some of the radionuclides present are:
" Tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere and as a result of routine release from nuclear facilities
" Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere
" Cesium-137, a manmade radionuclide which has been deposited in the environment, (for example, in surface soils) as a result of fallout from nu-clear weapons testing and routine releases from nuclear facilities
" Potassium-40, a naturally occurring radionuclide normally found through-out the environment (including in the human body)
- Fallout radionuclides from nuclear weapons testing, including Strontium-89, Strontium-90, Cesium-137, Cerium-141, Cerium-144, and Ruthenium-106. These radionuclides may also be released in minute amounts from nuclear facilities The radionuclides listed above are expected to be present in many of the environmental samples collected in the vicinity of the Davis-Besse Station. The contribution of radionuclides from the operation of Davis-Besse is assessed by comparing sample results with pre-operational data, op-erational data from previous years, control location data, and the types and amounts of radioac-tivity normally released from the Station in liquid and gaseous effluents.
Milk Samples Milk sampling is a valuable tool in environmental surveillance because it provides a direct basis for assessing the buildup of radionuclides in the environment that may be ingested by humans.
Milk is collected and analyzed because it is one of the few foods commonly consumed soon after production. The milk pathway involves the deposition of radionuclides from atmospheric re-leases onto forage consumed by cows. The radionuclides present in the forage-eating cow are incorporated into the milk, which is then consumed by humans.
When available, milk samples are collected at indicator and control locations once a month from November through April, and twice a month between May and October. Sampling is increased in the summer when the herds are normally outside on pasture and not consuming stored feed. In December of 1993, indicator location T-8 was eliminated from the sampling program, and no other indicator milk site has existed since that time. The control location will continue to be 43
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report sampled monthly in order to gather additional baseline data. If dairy animals are discovered within five miles of the station, efforts will be made to include them in the milk sampling pro-gram as indicator sites.
The 2011 milk samples were analyzed for Strontium-89, Strontium-90, Iodine-131, other gamma-emitting radionuclides, stable Calcium and Potassium. A total of 12 milk samples were collected in 2011. Strontium-89 was not detected above its LLD of 0.7 pCi/l. The annual aver-age concentration of Strontium-90 was 0.6 pCi/l. The annual average concentration was similar to those measured in previous years.
Iodine-i 31 was not detected in any of the milk samples above the LLD of 0.5 pCi/l. The concen-trations of Barium-140 and Cesium-137 were below their respective LLDs in all samples col-lected.
Since the chemistries of Calcium and Strontium are similar, as are Potassium and Cesium, organ-isms tend to deposit Cesium radioisotopes in muscle tissue and Strontium radioisotopes in bones.
In order to detect the potential environmental accumulation of these radionuclides, the ratios of the Strontium radioactivity (pCi/1) to the concentration of Calcium (g/l), and the Cesium radioac-tivity (pCi/1) compared to the concentration of Potassium (g/l) were monitored in milk. These ratios are compared to standard values to determine if buildup is occurring. No statistically sig-nificant variations in the ratios were observed.
Table 6: Milk Monitoring Location Sample Location Type of Number Location Location Description T-24 C
Toft Dairy, Sandusky, 21.0 miles SE of Station C = Control Groundwater Samples Soil acts as a filter and an ion exchange medium for most radionuclides. However, tritium and other radionuclides such as Ruthenium-106 have a potential to seep through the soil and could reach groundwater. Davis-Besse does not discharge its liquid effluents directly to the ground. In the past, REMP personnel sampled local wells on a quarterly basis to ensure early detection of any adverse impact on the local groundwater supplies due to Station operation. In addition, a quality control sample was collected at one of the wells each quarter. The groundwater samples were analyzed for beta-emitting radionuclides, tritium, Strontium-89, Strontium-90 and gamma-emitting radionuclides.
During the fall of 1998, the Carroll Township Water Plant began operation and offered residents a reliable source of high-quality, inexpensive drinking water. This facility has replaced all of the 44
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report drinking water wells near Davis-Besse, as verified by the Ottawa County Health Department, and the indicator groundwater sampling was discontinued for a year. Since that time, two beach wells were located within five miles of the Station. Although the residents are seasonal and only use the township system for their drinking water needs, these wells were added to our sampling program as Indicator locations. The gross beta averaged 1.7 pCi/1 at Indicator sites and 2.5 pCi/l at the Control site, T-27A. REMP Groundwater samples were not affected by the operation of the Davis-Besse Nuclear Power Station.
Gross Beta Ground Water 1982-211 8
7 6
3 2
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45
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 7: Groundwater Monitoring Locations Sample Location Type of Number Location Location Description T-225 I
Long Beach and Park, 1.5 mi NW of Station T-226 I
Allen residence, 1.6 miles NW of Station C = control I = indicator Broadleaf Vegetation and Fruit Samples Fruits and broadleaf vegetation also represent a direct pathway to humans. Fruits and broadleaf vegetation may become contaminated by deposition of airborne radioactivity (nuclear weapons fallout or airborne releases from nuclear facilities), or from irrigation water drawn from lake wa-ter which receives liquid effluents (hospitals, nuclear facilities, etc.). Radionuclides from the soil may be absorbed by the roots of the plants and become incorporated into the edible portions.
During the growing season, edible broadleaf vegetation samples, such as kale and cabbage, are collected from gardens and farms in the vicinity of the Station. Fruit, typically apples, is col-lected from orchards in the vicinity of Davis-Besse, and a control sample is collected, as well.
In 2011, broadleaf vegetation samples were collected at two indicator locations (T-227 and T-19) and one control location (T-37). Fruit samples were collected at two indicator locations (T-8 and T-25) and one control location (T-209). Broadleaf vegetation was collected once per month dur-ing the growing season and consisted of cabbage. The fruit that was collected was apples. All samples were analyzed for gamma-emitting radionuclides, Strontium-89, Strontium-90, and Io-dine-131.
Iodine-13 1 was not detected above the LLD of 0.0 14 pCi/g (wet) in any broadleaf vegetation nor above the LLD of 0.010 pCi/g (wet) in fruit samples. The only gamma-emitting radionuclide de-tected in the fruit and broadleaf vegetation samples was Potassium-40, which is naturally occur-ring.
Results of broadleaf vegetation and fruit samples were similar to results observed in previous years. Strontium 89 and Strontium 90 were not detected in any sample above their re-spective LLDs (0.004 and 0.002 pCi/l wet) in broadleaf vegetation samples at control and indica-tor locations. Operation of Davis-Besse had no observable adverse radiological effect on the surrounding environment in 2011.
46
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 8: Broadleaf Vegetation and Fruit Locations Sample Location Type of Number Location Location Description T-8 I
Moore Farm, 2.7 miles WSW of Station T-19*
I L. Bowyer Jr., 1.0 mile W of Station T-25 I
Witt Farm, 1.6 miles S of Station T-37*
C Bench Farm, 13.0 miles SW of Station T-209 C
Roving Control Fruit location T-227*
I Roving BLV location I = indicator, C = control
- denotes ODCM-required sample Animal/Wildlife Feed Samples Vegetation consumed by wildlife can provide an indication of airbOrne radionuclides deposited in the vicinity of the Station. Analyses of wildlife feed samples can also provide data for deter-mining radionuclide concentration in the food chain. Wildlife feed samples are collected from the Navarre Marsh 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 Beryl-lium-7, and fallout radionuclides such as Strontium-89 and Strontium-90 from nuclear weapons testing may be present in the feed samples.
Wildlife feed was collected at three locations (T-3 1, T-32 and T-198), and consisted of the edible portions of cattails. Samples were analyzed for gamma-emitting radionuclides. Naturally occur-ring Potassium-40 was detected in all samples. Beryllium-7 was detected at indicator location T-31 at 1.09 pCi/g (wet), 0.66 pCi/g (wet) at indicator location T-32. and 0.96 pCi/g (wet) at con-trol location T-198. All other radionuclides were below their respective LLDs. These samples indicate that the operation of Davis-Besse had no observable adverse effects on the surrounding environment.
47
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 9: Animal/Wildlife Feed Locations Sample Location Type of Number Location Location Description T-31 I
Davis-Besse Navarre Marsh T-32 C
Roving offsite location, 7.0 miles W of station in 2010 T-198 I
Toussaint Creek Wildlife Area, 4.0 miles WSW of the Station I = indicator C = control Wild Meat Samples Sampling of wild meat provides information on environmental radionuclide concentrations that humans may be exposed to through an ingestion pathway. The principle pathways for radionu-clide contamination of meat animals include deposition of airborne radioactivity in their food and drinking water and contamination of their drinking water from radionuclides released in liquid effluents.
The REMP generally collects wild meat on an annual basis. Wild animals commonly consumed by residents in the vicinity of Davis-Besse include waterfowl, deer, rabbits and muskrats. Analy-ses from these animals provide general information on radionuclide concentration in the food chain. When evaluating the results from analyses performed on meat animals, it is important to consider the age, diet and mobility of the animal before drawing conclusions from radionuclide concentrations in the local environment or in a species as a whole.
Wild Meat samples were taken in 2011 as follows:
Muskrat samples were collected on Station property in Navarre Marsh and at a control location west of Crane Creek. The samples showed only naturally-occurring activity and showed no affects of the operation of the plant on the surrounding environment.
48
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 10: Wild Meat Locations Sample Location Type of Number Location Location Description T-31 I
Onsite roving location T-210 C
Roving offsite location (7.0 mi. W of the Station in 2010)
I = indicator C = control Soil Samples Soil samples are generally collected once a year adjacent to our ten continuous air samplers.
Only the top layer of soil is sampled in an effort to identify possible trends in the local environ-mental nuclide concentration caused by atmospheric deposition of fallout and station-released radionuclides. Generally, the sites are relatively undisturbed, so that the sample will be represen-tative of the actual deposition in the area. Ideally, there should be little or no vegetation present, because the vegetation could affect the results of analyses. Approximately five pounds of soil are taken from the top two inches at each site. Many naturally occurring radionuclides such as Be-ryllium-7 (Be-7), Potassium-40 (K-40) and fallout radionuclides from nuclear weapons testing are detected. Fallout radionuclides that are often detected include Strontium-90 (Sr-90) and Ce-sium-137 (Cs-137).
Soil was collected at ten sites in 2011. The indicator locations included T-1, T-2, T-3, T-4, T-7, and T-8. The control locations were T-9, T-1 1, T-12, and T-27. All soil samples were analyzed for gamma-emitting radionuclides. The only gamma emitter detected (in addition to naturally occurring Be-7 and K-40) was Cs-137. Cs-137 was found in Indicator and Control locations at average concentrations of 0.15 pCi/g (dry) and 0.11 pCi/g (dry), respectively. The concentrations were similar to that observed in previous years (Figure 15).
49
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report 1.1-137 in Si 1972-2511 1.15 1.1 1,5 095 0.9 085 0.8 Q75 0.7 EQ65 E 0.6 0550.5 /,/
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Contrl Figure 15: The concentration of Cesium-137 in soil has steadily declined in recent years. The peak seen in 1978 was due to fallout from nuclear weapons testing.
50
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 11: Soil Locations Sample Location Number T-1 T-2 T-3 T-4 T-7 Type of Location I
I I
I I
Location Description Site boundary, 0.6 miles ENE of Station Site boundary, 0.9 miles E of Station Site boundary 1.4 miles ESE of Station Site boundary 0.8 miles S of Station Sand Beach, main entrance, 0.9 miles NW of Station Moore Farm, 2.7 miles WSW of Station Oak Harbor Substation, 6.8 miles SW of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 20.7 miles WNW of Station Crane Creek, 5.3 miles WNW of Station T-8 T-9 T-11 T-12 I
C C
C C
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Aquatic Monitori Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-off/soil erosion, and releases of radioactive material in liquid effluents from hospitals or nu-clear facilities. These sources provide two forms of potential exposure to radiation, external and internal. External exposure can occur from the surface of the water, shoreline sediments and from immersion (swimming) in the water. Internal exposure can occur from ingestion of ra-dionuclides, either directly from drinking water, or as a result of the transfer of radionuclides through the aquatic food chain with eventual consumption of aquatic organisms, such as fish. To monitor these pathways, Davis-Besse samples treated surface water (drinking water), untreated surface water (lake or river water), fish, and shoreline sediments.
Treated Surface Water Treated surface water is water from Lake Erie, which has been processed for human consump-tion. Radiochemical analysis of this processed water provides a direct basis for assessing the dose to humans from ingestion of drinking water.
Samples of treated surface water were collected from two indicators (T-22B and T-50) and two control locations (T-11 and T-12). These locations include the water treatment facilities for Car-roll Township, Erie Industrial Park, Port Clinton and Toledo. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta-emitting radionu-clides. The samples were also composited in a quarterly sample and analyzed for Strontium-89, Strontium-90, gamma-emitting radionuclides, and tritium. One QC sample was collected from a routine location, which was changed each month.
The annual average of beta-emitting radionuclides for indicator and control locations was 2.2 and 2.0 pCi/l, respectively. These results are similar to previous years shown in Figure 19. Tritium 55
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report was not detected above the LLD of 330 pCi/1 during 2011. Strontium-89 was not detected above the LLD of 1.0 pCi/1. Strontium-90 activity was not detected above its LLD of 0.7 pCi/1. These results are similar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse during 2011.
Each month, weekly quality control samples were collected at different locations. The results of the analyses from the quality control samples were in agreement with the routine samples. The average concentration of beta-emitting radionuclides detected at the QC locations was 1.7 pCi/1.
Gross Beta in Treated Surface Water 1972-2011 4,5 4
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2.5 2
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Figure 19: Since 1974, the annual concentrations of beta emitting radionuclides in treated surface water samples col-lected from indicator locations have been consistent with those from control locations. Davis-Besse has had no measurable radiological impact on surface water used to make drinking water.
56
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 12: Treated Surface Water Locations Sample Location Number Type of Location Location Description T-11*
T-12 C
C Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 20.7 miles WNW of Station Carroll Township Water Treatment Plant, sampled at Davis-Besse REMP lab T-22B*
I T-143 QC Quality Control Site I = indicator C = control QC = quality control
- denotes ODCM-required sample 57
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to hu-mans from external exposure from the lake surface as well as from immersion in the water. It also provides information on the radionuclides present, which may affect drinking water, fish, and irrigated crops.
Routine Program The routine program is the basic sampling program that is performed year round. Untreated wa-ter samples are collected from water intakes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo, Carroll Township and Erie Industrial Park. A sample is also collected from Lake Erie at the mouth of the Toussaint River. These samples are collected weekly and composited monthly. The monthly composite is analyzed for beta-emitting radionuclides, tritium, and gamma-emitting radionuclides.
The samples are also composited quarterly and analyzed for Strontium-89 and Strontium-90.
A QC sample is also collected weekly, with the location changing each month.
58
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Sample Results For the routine untreated surface water samples that are composited weekly, the beta emitting radionuclides had an average concentration of 2.5 pCi/L at indicator locations during 2011. Con-trol locations averaged 2.1 pCi/L during this period.
Tritium was detected in 2011 at 351 and 620 pCi/liter in Untreated Surface Water samples T-3 and T-22, respectively. These activites are likely due to the operation of Davis-Besse, and are well below the federal EPA limit for drinking water sources of 20,000 pCi/liter. There were no other detectable tritium results in surface water samples collected during this period.
Each month, weekly composited quality control samples of untreated water were analyzed from different locations. The results of the analyses from the quality control samples were consistent with the routine samples, and averaged 2.7 pCi/L of beta emitting radionuclides.
Gross Beta Concentration in Untreated Surface Water 1977-2011 7
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59
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 13: Untreated Surface Water Locations Sample Location Type of Number Location Location Description T-3 Site boundary, 1.4 miles ESE of Station T-11*
C Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 C
Toledo Water Treatment Plant, sample taken from intake crib, 12.6 miles NW of Station T-22A*
Carroll Township Water Plant, State Route 2, 2.1 miles NW of Station T-145 QC Roving Quality Control Site I = indicator, C = control
- denotes ODCM-required sample 60
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Shoreline Sediment The sampling of shoreline sediments can provide an indication of the accumulation of insoluble radionuclides which could lead to internal exposure to humans through the ingestion of fish, through re-suspension into drinking water supplies, or as an external radiation source from shore-line exposure to fishermen and swimmers.
Samples of deposited sediments in water along the shore were collected at various times from three indicator sites (T-3, T-4, and T-132) and one control location (T-27). Samples were ana-lyzed for gamma-emitting radionuclides. Naturally occurring Potassium-40 was detected at both control and indicator locations. These results are similar to previous years.
Table 14: Shoreline Sediment Locations Sample Location Number Type of Location Location Description T-3 T-4 I
I Site boundary, 1.4 miles ESE of Station Site boundary, 0.8 miles S of Station Crane Creek, 5.3 miles WNW of Station Lake Erie, 1.0 miles E of Station T-27*
T-132 C
I I = indicator C = control Denotes ODCM-required sample 61
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Fish Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondar-ily to serve as indicators of radioactivity in the aquatic ecosystem. The principal nuclides that may be detected in fish include naturally-occurring Potassium-40, as well as Cesium-137, and Strontium-90.
Depending upon the feeding habit of the species (e.g., bottom-feeder versus predator), results from sample analyses may vary.
Davis-Besse routinely collects three species of fish once per year from sampling locations near the Station's liquid discharge point and more than ten miles away from the Station where fish populations would not be expected to be impacted by the Station operation. Walleye are col-lected because of being a popular recreational fish and white perch and white bass are collected because their importance as a commercial fish. Carp are collected because they feed on the bot-tom where contaminants may settle.
The average concentration of beta-emitting radionuclides in fish was similar for indicator and control locations (3.4 pCi/g and 3.7 pCi/g wet weight, respectively). No gamma emitters were detected above their respective LLDs.
Gross Beta in Fish 1972-2011 Ywr I---- Indcaor ControlI Figure 21: Average concentrations of beta-emitting radionuclides in fish samples were similar at indicator and con-trol locations, and were comparable to results of previous years.
62
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 15: Fish Locations Sample Location Type of Number Location Location Description T-33*
Lake Erie, within 5 miles radius of Station T-35*
C Lake Erie, greater than 10 mile radius of Station I = indicator C= control
- Denotes ODCM-required sample 63
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Thermoluminescent Dosimeters Radionuclides present in the air and deposited on the ground may directly irradiate individuals.
Direct radiation levels at and around Davis-Besse are constantly monitored by thermo-luminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information.
The TLDs used at Davis-Besse contain a Sulfate:Dysprosium (CaSO4:Dy) card with four main readout areas. Multiple readout areas are used to ensure the precision of the measurements.
Thermoluminescence is a process in which ionizing radiation interacts with phosphor, which is the sensitive material in the TLD. Energy is trapped in the TLD material and can be stored for several months or years. This provides an excellent method to measure the dose received over long periods of time. The energy that was stored in the TLD as a result of interaction with radia-tion is released and measured by a controlled heating process in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy in the form of light. The amount of light detected is directly proportional to the amount of radiation to which the TLD was exposed.
The reading process re-zeroes the TLD and prepares it for reuse.
TLD Collection Davis-Besse has 88 TLD locations (77 indicator and 11 control locations). TLDs are collected and replaced on a quarterly and annual basis. Nineteen QC TLDs are also collected on this schedule. There are a total of 214 TLDs in the environment surrounding Davis-Besse. By col-lecting them on a quarterly and annual basis from a single site, each measurement serves as a quality control check on the other. All ODCM quarterly and annual TLDs placed in the field were retrieved and evaluated during the current reporting period.
In 2011, the average dose equivalent for quarterly TLDs at indicator locations was 16.7 mremr91 days, and for control locations was 17.9 mrem/91 days. The average dose equiva-lent for annual TLDs in 2011 was 61.7 mrem/365 days at indicator locations and 68.7 mrem/365 days for control locations.
Quality Control TLDs Duplicate TLDs have been placed at 18 sites. These TLDs are placed in the field at the same time and location as some of the routine TLDs, but are assigned quality control site numbers.
This allows us to take several measurements at the location without the laboratory being aware that they are the same. A comparison of the quality control and routine results provides a method to check the accuracy of the measurements. The average dose equivalent of indicator quality control TLDs averaged 14.3 mrem/91 days while the quality control TLDs at control locations yielded an average dose equivalent of 17.8 mrem/91 days.
67
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Gamma Dose for Environmental TLDs 1973-2011 24 z18 16 inldicato controlI Figure 25: The similarity between indicator and control results demonstrates that the operation of Davis-Besse has not caused any abnormal gamma dose.
68
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table Sample Location Number T-l*
T-2*
T-3*
T-4*
T-5*
T-6
- T-7*
T-8*
T-9 T-10*
16: Thermoluminescent Dosimeter Locations Type of Location Location Description I
Site boundary, 0.6 miles ENE of Stati I
Site boundary, 0.9 miles E of Station I
Site boundary, 1.4 miles ESE of Statio I
Site boundary, 0.8 miles S of Station I
Site boundary, 0.5 miles W of Station I
Site boundary, 0.5 miles NNE of Stati4 I
Sand Beach entrance, 0.9 miles NW oJ I
Earl Moore Farm, 2.7 miles WSW of C
Oak Harbor Substation, 6.8 miles SW
)n Dn on f Statiom Station of Station T-11*
T-12*
T-24 T-27 T-38 T-39 T-40*
I C
C C
C I
Site boundary, 0.5 miles SSW of Station near warehouse Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 20.7 miles WNW of Station Sandusky, 21.0 miles SE of Station Crane Creek, 5.3 miles WNW of Station Site boundary, 0.6 miles ENE of Station Site boundary 1.2 miles ENE of Station Site boundary, 0.7 miles SE of Station Site boundary, 0.6 miles SSE of Station Site boundary, 0.8 miles SW of Station I
I I
T-42*
69
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)
Sample Location Number T-43 T-44 T-45 T-46*
T-47*
T-48*
T-49 T-50*
Type of Location I
I I
I I
I I
I T-51 T-52*
T-53 T-54*
T-55*
T-60 T-62 T-65 T-66 T-67*
T-68*
T-69 Location Description Site boundary, 0.5 miles SW of Station Site boundary, 0.5 miles WSW of Station Site boundary, 0.5 miles WNW of Station Site boundary, 0.5 miles NW of Station Site boundary, 0.5 miles N of Station Site boundary, 0.5 miles NE of Station Site boundary, 0.5 miles NE of Station Erie Industrial Park, Port Clinton, 4.5 miles SE of Station on Siren Pole, 5.5 miles SSE of Station Miller Farm, 3.7 miles S of Station Nixon Farm, 4.5 miles S of Station McNutt residence, 4.8 miles SW of Station King Farm, 4.5 miles W of Station Site boundary, 0.3 miles S of Station Site boundary, 1.0 mile SE of Station Site boundary, 0.3 miles E of Station Site boundary, 0.3 miles ENE of Station Site boundary, 0.3 miles NNW of Station Site boundary, 0.5 miles WNW of Station Site boundary, 0.4 miles W of Station 70
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)
Sample Location Type of Number Location T-71 T-73 T-74 T-75 T-76 T-80 T-81 T-82 T-83 T-84 T-85 T-86 T-88 T-87 T-89 T-90 T-91*
T-92 T-93 I
I I
I I
QC QC QC QC QC QC QC QC QC QC I
Location Description Site boundary, 0.1 mile NNW of Station Site boundary, 0.1 mile WSW of Station Site boundary, 0.1 mile SSW of Station Site boundary, 0.2 mile SSE of Station Site boundary, 0.1 mile SE of Station Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site I
I I
Quality Control in lead pig DBAB Annex Quality Control Site Site Personnel Processing Facility State Route 2 and Rankie Road, 2.5 miles SSE Locust Point Road, 2.7 miles WNW of Station Twelfth Street, Sand Beach, 0.6 miles NNE of Station State Route 2, 1.8 miles WNW of Station State Route 579, 9.3 miles W of Station T-94 T-95 I
C 71
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)
Sample Location Number T-100 Type of Location C
T-111 T-112*
T-113 T-114 T-115 T-116 T-117 T-118 T-1 19 T-120 T-121 T-122 T-123 T-124 T-125 T-126 C
I Location Description Ottawa County Highway Garage, Oak Harbor, 6.0 miles S of Station Toussaint North Road, 8.3 miles WSW of Station Thompson Road, 1.5 miles SSW of Station Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site State Route 19, 2.0 miles W of Station Duff Washa and Humphrey Road, 1.7 miles W of Station Zetzer Road, 1.6 miles WSW of Station Church and Walnut Street, Oak Harbor, 6.5 miles SSW of Station Behlman and Bier Roads, 4.4 miles SSW of Station Camp Perry Western and Toussaint South Road, 3.7 miles S of Station Camp Perry Western and Rymers Road, 4.0 miles SSE of Station I
C I
I T-127 72
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)
Sample Location Type of Number Location T-128 I
T-142 T-150 T-151*
T-153 T-154 T-155 T-200 T-201 T-202 T-203 T-204 T-205 T-206 T-207 T-208 I
I I
I C
Location Description Erie Industrial Park, Port Clinton Road, 4.0 miles SE of Station Site Boundary, 0.8 miles SSE of Station Humphrey and Hollywood Roads, 2.1 miles NW of Station State Route 2 and Humphrey Road, 1.8 miles WNW of Station Leutz Road, 1.4 miles SSW of Station State Route 2, 0.7 miles SW of Station Fourth and Madison Streets, Port Clinton, 9.5 miles SE of Station Quality Control Site Sand Beach, 1.1 miles NNW of Station Sand Beach, 0.8 miles NNW of Station Sand Beach, 0.7 miles N of Station Sand Beach, 0.7 miles N of Station Sand Beach, 0.5 miles NNE of Station Site Boundary, 0.6 miles NW of Station Site Boundary, 0.5 miles N of Station Site Boundary, 0.5 miles NNE of Station.
QC I
I I
I I
I I
I 73
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 16: Thermoluminescent Dosimeter Locations (continued)
Sample Location Type of Number Location Location Description T-21 1 I
Site boundary, 0.79 miles E of Station T-212 I
Site boundary, 1.2 miles ESE of Station T-213 I
Site boundary, 0.6 miles SSW of Station T-214 I
Site boundary, 0.7 miles SW of Station T-215 I
Site boundary, 0.5 miles W of Station T-216 I
Site boundary, 0.7 miles NW of station T-217 I
Salem-Carroll Rd., 4.7 miles SSW of Station T-218 I
Toussaint East Rd., 4.0 miles WSW of Station T-219 I
Toussaint Portage Rd., 4.8 miles WSW of Station T-220 I
Duff-Washa Rd., 4.8 miles W of Station T-221 C
Magee Marsh, 5.1 miles WNW of Station T-222 I
Turtle Creek Access, 3.7 miles WNW of Station T-223 I
Lawrence Rd., 5.0 miles SE of Station T-224 I
Erie Industrial Park, 4.4 miles SE of Station I = Indicator C = Control QC = Quality Control
- denotes ODCM-required TLD 74
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Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Conclusion The Radiological Environmental Monitoring Program at Davis-Besse is conducted to determine the radiological impact, if any, of the Station's operation on the environment. Radionuclide con-centrations measured at indicator locations were compared with concentrations measured at con-trol locations in previous operational studies and in the pre-operational surveillance program.
These comparisons indicate normal concentrations of radioactivity in nearly all environmental samples collected in 2011. Davis-Besse's operation in 2011 indicated no adverse radiological impact on the residents and environment surrounding the station. The results of the sample analyses performed during the period of January through December 2011 are summarized in Ap-pendix D of this report.
References
- 1. "Cesium-137 from the Environment to Man: Metabolism and Dose," Report No. 52, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1977).
- 2. "Environmental Radiation Measurements," Report No. 50, National Council on Radiation Protection and Measurement, Washington, D.C. (December 1976).
- 3. "Exposure of the Population in the United States and Canada from Natural Background Ra-diation," Report No. 94, National Council on Radiation Protection and Measurement, Wash-ington, D.C. (December 1987).
- 4. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy Instal-lations," DOE/EP-0023, Department of Energy, Washington, D.C. (July 1981).
- 5. "Ionizing Radiation Exposure of the Population of the United States," Report No. 93, Na-tional Council on Radiation Protection and Measurement, Washington, D.C. (September 1987).
- 6. "Natural Background Radiation in the United States," Report No. 45, National Council on Radiation Protection and Measurement, Washington, D.C. (November 1975).
- 7. "Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion 'As Low As Reasonably Achievable' for Radioactive 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," Appendix 1 (1988).
- 8. "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry,"
American National Standards Institute, Inc., ANSI-N45-1975, New York, New York (1975).
- 9. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurement, Washington, D.C. (De-cember 1987).
78
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report
- 10. "Radiological Assessment: Predicting the Transport, Bioaccumulation and Uptake by Man of Radionuclides Released to the Environment," Report No. 76, National Council on Radiation Protection and Measurement, Washington, D.C. (March 1984).
- 11. Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," US NRC (April 1975).
- 12. Regulatory Guide 4.13, "Performance, Testing, and Procedural Specifications for Thermolu-minescent Dosimetry: Environmental Applications," US NRC (July 1977).
- 13. Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment," US NRC (February 1979).
- 14. Regulatory Guide 0475, "Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities," US NRC (September 1978).
- 15. "Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, Part 20 (1993).
- 16. 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).
- 17. Teledyne Isotopes Midwest Laboratory, "Final Monthly Progress Report to Toledo Edison Company", (1991-1999).
- 18. Environmental, Inc. Midwest Laboratory, "Final Report to FirstEnergy Corporation", (2000-2011)
- 19. Teledyne Isotopes Midwest Laboratory, "Pre-operational Environmental Radiological Moni-toring for the Davis-Besse Power Station Unit No. 1", Oak Harbor, OH (1972-1977).
- 20. Toledo Edison Company, "Davis-Besse: Nuclear Energy for Northern Ohio."
- 21. Toledo Edison Company, Davis-Besse Nuclear Power Station, Unit No. 1, Radiological Ef-fluent Technical Specifications", Volume 1, Appendix A to License No. NPF-3.
- 22. Toledo Edison Company, "Final Environmental Statement -Related to the Construction of Davis-Besse Nuclear Power Station," Docket #50-346 (1987).
- 23. Toledo Edison Company, "Performance Specifications for Radiological Environmental Monitoring Program," S-72N.
- 24. Davis-Besse Nuclear Power Station, "Radiological Environmental Monitoring Program,"
DB-CN-00015.
79
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report
- 25. Davis-Besse Nuclear Power Station, "Radiological Environmental Monitoring Quarterly, Semiannual, and Annual Sampling", DB-CN-03004.
- 26. Davis-Besse Nuclear Power Station, "Radiological Monitoring Weekly, Semimonthly, and Monthly Sampling," DB-CN-03005.
- 27. Davis-Besse Nuclear Power Station, "REMP Enhancement Sampling", DB-CN-10101.
- 28. Toledo Edison Company, "Updated Safety Analysis for the Offsite Radiological Monitoring Program", USAR 11.6, Revision 14, (1992).
- 29. Davis-Besse Nuclear Power Station, "Annual Radiological Environmental Operating Report Preparation and Submittal", DB-CN-00014.
- 30. Davis-Besse Nuclear Power Station, "Preparation of Radioactive Effluent Release Report",
DB-CN-00012.
- 31. Davis-Besse Nuclear Power Station, "Offsite Dose Calculation Manual".
- 32. "Tritium in the Environment", Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979).
- 33. NEI 07-07, "Industry Ground Water Protection Initiative - Final Guidance Document",
August, 2007.
- 34. "Groundwater Monitoring Well Installation & Monitoring Report Davis-Besse Nuclear Power Station Oak Harbor, Ohio", Environmental Resources Management, March 18, 2008.
80
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2011 Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ioniz-ing radiation were recognized and efforts were made to establish radiation protection standards.
The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recommendations have been given legislative authority by being published in the Code of Federal Regulations by.the Nuclear Regulatory Commission.
The main objective in the control of radiation is to ensure that any dose is kept not only within regulatory limits, but kept as low as reasonably achievable (ALARA). The ALARA principle applies to reducing radiation dose both to the individual working at Davis-Besse and to the gen-eral public. "Reasonably achievable" means that exposure reduction is based on sound economic decisions and operating practices. By practicing ALARA, Davis-Besse minimizes health risk and environmental detriment and ensures that doses are maintained well below regulatory limits.
Sources of Radioactivity Released During the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces, which have been activated, are present in the primary coolant water. The three types of radioactive material released are noble gases, Io-dine and particulates, and tritium.
The noble gas fission products in the primary coolant are given off as a gas when the coolant is depressurized. These gases are then collected by a system designed for gas collection and stored for radioactive decay prior to release.
Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primary coolant system. These liquids are collected through a series of floor and equipment drains and sumps. All liquids of this nature are monitored and processed, if neces-sary, prior to release.
During 2011, gaseous radioactive effluent samples obtained from Station Vent identified detect-able iodine-131 concentrations between March 28 and April 19, 2011 that could be attributed to operation of Davis-Besse. The concentrations detected were above the non-detectable levels ob-served during this operating period. Concentrations of iodine-131 returned to non-detectable af-ter April 19, 2011. Given the events.of March 2011 at the Fukushima Daiichi Nuclear Station in Japan and the associated airborne releases and subsequent trans-Pacific transportation, the slightly elevated concentrations detected at this release point are reasonably attributed to the Dai-Ichi releases. However, the concentrations at Davis-Besse and projected doses are conservatively included in this report for completeness.
81
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as Xenon (Xe) and Krypton (Kr). Noble gases are biologically and chemically inert.
They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an external source of radiation exposure to the body. Xe-133 and Xe-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive noble gases released. They are readily dispersed in the atmosphere.
Iodine and Particulates Annual releases of radioisotopes of Iodine, and those particulates with half-lives greater than 8 days, in gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing sys-tems, minimize their discharge. The predominant radioiodine released is Iodine-131 with a half-life of approximately eight days. The main contribution of radioactive Iodine to human dose is to the thyroid gland, where the body concentrates Iodine.
The principal radioactive particulates released are fission products (e.g., Cesium-134 and Ce-sium-137) and activation products (e.g., Cobalt-58 and Cobalt-60). Radioactive Cesium and Co-balt contribute to internal radiation exposure of tissues such as muscle, liver, and the intestines.
These particulates are also a source of external radiation exposure if deposited on the ground.
Tritium Tritium, a radioactive isotope of Hydrogen, is the predominant radionuclide in liquid effluents. It is also present in gaseous effluents. Tritium is produced in the reactor coolant as a result of neu-tron interaction with deuterium (also a Hydrogen isotope) present in the water and with the Bo-ron in the primary coolant. When tritium, in the form of water or water vapor, is ingested or in-haled it is dispersed throughout the body until eliminated.
Carbon-14 Carbon-14 (C-14) is a naturally occurring isotope of carbon produced in the atmosphere by cos-mic rays. Its concentration in the environment was significantly increased by nuclear weapons testing in the 1950s and 1960s. It is also produced in nuclear power production in much lesser amounts.
C-14 is a pure beta emitter and generates no dose from direct radiation. Its predominant expo-sure pathway is through ingestion of produce which has incorporated C-14 into plant matter in the chemical form of CO2 via photosynthesis.
Processing and Monitoring Effluents are strictly controlled to ensure radioactivity released to the environment is minimal and does not exceed regulatory limits. Effluent control includes the operation of monitoring sys-82
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report tems, in-plant and environmental sampling and analysis programs, quality assurance programs for effluent and environmental programs, and procedures covering all aspects of effluent and en-vironmental monitoring.
The radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gaseous wastes that contain radioactivity. For example, the Waste Gas Decay Tanks allow radioactivity in gases to decay prior to release via the Station Vent.
Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits.
These instruments provide a continuous indication of the radioactivity present. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure the limits will not be exceeded. If a monitor alarms, a release from a tank is automati-cally stopped.
All wastes are sampled prior to release and analyzed to identify the specific concentrations of ra-dionuclides. Sampling and analysis provides a more sensitive and precise method of determining effluent composition than can be accomplished with monitoring instruments.
A meteorological tower is located in the southwest sector of the Station which is linked to com-puters that record its data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public. Beyond the plant, devices maintained in conjunction with the Radiological Environmental Monitoring Program continuously sample the air in the sur-rounding environment. Frequent samples of other environmental media, such as water and vege-tation, are taken to determine if buildup of deposited radioactive material has occurred in the area.
Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to ra-dioactive material. The major pathways of concern are those which could cause the highest cal-culated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the envi-ronment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An an-nual average of the water flow, wind speed, and wind direction are used to evaluate how the ra-dionuclides will be distributed in an area for gaseous or liquid releases. An important factor in evaluating the exposure pathways is the use of the environment. Many factors are considered such as dietary intake of residents, recreational use of the area, and the locations of homes and farms in the area.
The external and internal exposure pathways considered are shown in Figure 29. The release of radioactive gaseous effluents involves pathways such as external whole body exposure, deposi-tion of radioactive material on plants, deposition on soil, inhalation by animals destined for hu-man consumption, and inhalation by humans. The release of radioactive material in liquid efflu-ents involves pathways such as drinking water, fish, and direct exposure from the lake at the shoreline while swimming.
83
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Figure 29: The exposure pathways shown here are monitored through the Radiological Environmental Monitoring Program (REMP) and are considered when calculating doses to the public.
Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure route that will provide, for a specific radionu-clide, 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 fraction of the dose is called the critical organ.
Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body exposure to ra-diation involves the exposure of all organs. Most background exposures are of this form. Both radioactive and non-radioactive elements can enter the body through inhalation or ingestion.
When they do, they are usually not evenly distributed. For example, Iodine concentrates in the thyroid gland, Cesium collects in muscle and liver tissue, and Strontium collects in the bone.
The total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the length of time that the radionuclide remains there. Some radionu-clides remain for short times due to their rapid radioactive decay and/or elimination rate from the body. Other radionuclides may remain in the body for longer periods of time.
84
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report The dose to the general public in the area surrounding Davis-Besse is calculated for each liquid or gaseous release. The dose due to radioactive material released in gaseous effluents is calcu-lated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the average weather conditions at the time of the release, the locations of expo-sure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inha-lation, food consumption). The dose due to radioactive material released in liquid effluents is calculated by using factors such as the total volume of the liquid released, the total volume of di-lution water (near field dilution), and usage factors, such as water and fish consumption, and shoreline and swimming factors. These calculations produce a conservative estimation of the dose.
Results The Radioactive Effluent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period from January 1 through December 31, 2011.
" Summation of the quantities of radioactive material released in gaseous and liquid efflu-ents (Tables 17-23)
" Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites (Table 24)
- A listing of all radioactive effluent monitoring instrumentation required by the Offsite Dose Calculation Manual, but which were inoperable for more than 30 days During this reporting period, the estimated maximum individual offsite dose due to radioactivity released in effluents was:
Liquid Effluents:
- 3.76E-02 mrem, maximum individual whole body dose
" 5.03E-02 mrem, maximum individual significant organ dose (liver)
Gaseous Effluents:
Noble Gas:
" 1.82E-04 mrem, whole body
" 3.05E-04 mrem, skin Iodine - 131, Tritium, and Particulates with Half-lives greater than 8 Days
- 2.43E-03 mrem, whole body dose
- 2.44E-03 mrem, significant organ dose (thyroid)
Carbon-14 1.46E-01 mrem, whole body
" 7.29E-01 mrem, significant organ dose (bone)
These doses are a small fraction of the limits set by the NRC in the Davis-Besse ODCM.
85
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Additional normal release pathways from the secondary system exist. For gaseous effluents, these pathways include the Auxiliary Feed Pump Turbines exhaust, the main steam safety valve system and the atmospheric vent valve system, steam packing exhaust and main feed water. For liquid effluents, the additional pathways include the Turbine Building drains via the settling ba-sins. Releases via these pathways are included in the normal release tables in this report.
Regulatory Limits Gaseous Effluents In accordance with Offsite Dose Calculation Manual, dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
Noble gases:
" Released at a rate equal to or less than 500 mrem TEDE per year.
- Released at a rate such that the total dose to the skin will be less than or equal to 3000 mrem in a year.
Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
- Released at a rate such that the total dose to any organ will be less than or equal to 1500 mrem in a year.
In accordance with 1 OCFR50, Appendix I, Sec. JIB. 1, air dose due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
- Less than or equal to 10 mrad total for gamma radiation and less than or equal to 20 mrad total for beta radiation in any calendar year.
In accordance with 1 OCFR50, Appendix I, Sec. IIC, dose to a member of the public from Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gase-ous effluents released to areas at and beyond the site boundary shall be limited to the following:
- Less than or equal to 15 total mrem to any organ in any calendar year.
Carbon-14 Carbon-14 (C-14) is calculated based on plant power production. The C-14 doses are based on a calculated value of 8.76 Ci of C-14 released from Davis-Besse through the Station Vent during 2011.
86
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Liquid Effluents In accordance with 10CFR50, Appendix I, Sec IIA, the dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to accumulated doses of:
- Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ in any calendar year.
Effluent Concentration Limits The Effluent Concentration Limits (ECs) for gaseous and liquid effluents at and beyond the site boundary are listed in 10CFR20, Appendix B, Table II, Columns 1 and 2, with the most restric-tive EC being used in all cases. For dissolved and entrained gases in liquids, the EC of 2.0E-04 uCi/ml is applied. This EC is based on the Xe-135 DAC of IE-05 uCi/ml of air (submersion dose) converted to an equivalent concentration in water as discussed in the International Com-mission on Radiological Protection (ICRP), Publication 2.
Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and activa-tion products to less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radio-activity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable.
Measurements of Total Activity Fission and Activation Gases:
These gases, excluding tritium, are collected in Marinelli beakers specially modified for gas sampling, in steel flasks, or in glass vials, and are counted on a Germanium detector for principal gamma emitters. Radionuclides detected are quantified via gamma spectroscopy.
Tritium gas is collected using a bubbler apparatus and counted by liquid scintillation.
Iodine Iodine is collected on a charcoal cartridge filter and counted on a germanium detector. Specific quantification of each iodine radionuclide is performed using gamma spectroscopy.
Particulates Particulates are collected on filter paper and counted on a Germanium detector. Specific quanti-fication of each radionuclide present on the filter paper is performed by using gamma spectros-copy.
Liquid Effluents Liquid effluents are collected in a Marinelli beaker and counted on a germanium detector. Quan-tification of each gamma-emitting radionuclide present in liquid samples is via gamma spectros-copy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system.
87
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Batch Releases Liquid from 1 / 1 / 11 through 12/31 /11
- 1. Number of batch releases:
- 2. Total time period for the batch releases:
- 3. Maximum time period for a batch release:
- 4. Minimum time period for a batch release:
- 5. Average time period for a batch release:
Gaseous from 1 / 1 / 11 through 12/31 /11
- 1. Number of batch releases:
- 2. Total time period for the batch releases:
- 3. Maximum time period for a batch release:
- 4. Minimum time period for a batch release:
60 99.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 238 minutes 96 minutes 100 minutes 15 521 hours0.00603 days <br />0.145 hours <br />8.614418e-4 weeks <br />1.982405e-4 months <br /> 336 hours 205 minutes Abnormal Releases There was one abnormal gaseous release of radioactivity from the station on December 5, 2011 when two Auxiliary Steam valves unexpectedly lifted for three seconds during plant startup.
This resulted in a release of 1.OE-06 curies of tritium with a total body dose of 3.OE-1 1 mrem.
There were no abnormal liquid releases of radioactivity from the station during 2011.
Percent of ODCM Release Limits The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent of limits, for January 1, 2011 through December 3 1, 2011.
PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1, 2011-December 31, 2011 (gaseous)
Noble gases (gamma) 1.65E-04 mrad 10 mrad 1.65E-03 Noble gases (beta) 2.77E-04 mrad 20 mrad 1.39E-03 1-131, tritium and particulates 2.43E-03 mrem 15 mrem 1.62E-02 C-14 6.63E-01 mrad 20 mrad 3.31E+0o Report Period: January 1, 2011 - December 31, 2011 (liquid)
Total body 3.76E-02 mrem 3 mrem 1.25E+00 Organ (liver) 5.03E-02 mrem 10 mrem 5.03E-01 88
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Sources of Input Data
" Water Usage: Survey of Water Treatment Plants (DSR-95-00347)
" 0-50 mile meat, milk, vegetable production, and population data was taken from 1982 Annual Environmental Operating Report entitled, "Evaluation of Compliance with Appendix I to 10CFR50: Updated Population, Agricultural, Meat - Animal, and Milk Production Data Tables for 1982". This evaluation was based on the 1980 Census, the Agricultural Ministry of Ontario 1980 report entitled "Agricul-tural Statistics and Livestock Marketing Account", the Agricultural Ministry of Ontario report entitled "Agricultural Statistics for Ontario, Publication 21, 1980",
the Michigan Department of Agriculture report entitled "Michigan Agricultural Statistics, 1981", and the Ohio Crop Reporting Service report entitled "Ohio Agri-cultural Statistics, 1981".
- Gaseous and liquid source terms: Tables 17 through 21 of this report.
- Location of the nearest individuals and pathways by sector within 5 miles, see Land Use Census Section of the report.
- Population of the 50-mile Radius of Davis-Besse (DSR-95-00398).
Dose to Public Due to Activities Inside the Site Boundary In accordance with ODCM Section 7.2, the Radioactive Effluent Release Report includes an as-sessment of radiation doses from radioactivity released in liquid and gaseous effluents to mem-bers of the public from activities inside the site boundary.
The Wellness Center, Pavilion, Training Center pond are accessible to employees and their fami-lies. The Pavilion may be accessible to the public for certain social activities. The Training Cen-ter pond allows employees and their families to fish on site under a "catch-and-release" program; therefore the fish pathway is not considered applicable. Considering the frequency and duration of the visits, the resultant dose would be a small fraction of the calculated maximum site bound-ary dose. For purposes of assessing the dose to members of the public in accordance with ODCM Section 7.2, the following exposure assumptions are used:
- Exposure time for maximally-exposed visitors is 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> (1 hr/day, 5 day/ week, 50 wk/yr)
- Annual average meteorological dispersion (conservative, default use of maximum site boundary dispersion).
- For direct "shine" from the Independent Spent Fuel Storage Installation (ISFSI), de-fault use of the maximum dose rate for a completed (full) ISFSI, at a distance of 950 feet. ODCM equations may be used for calculating the dose to a member of the pub-lic for activities inside the site boundary. This dose would be at least a factor of 35 less than the maximum site boundary air dose, as calculated in the ODCM. Nowhere onsite are areas accessible to the public where exposure to liquid effluents could oc-cur. Therefore, the modeling of the ODCM conservatively estimates the maximum potential dose to members of the public.
89
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report 0
The Old Steam Generator Storage Facility (OSGSF) will provide long term storage for two (2) Once Through Steam Generators (OTSGs), two (2) Reactor Coolant System (RCS) Hot Leg Piping sections, one (1) Reactor Vessel Closure Head (RVCH) (with Control Rod Drive Mechanisms and Service Support Structure).
The OSGSF has been designed such that the dose rates at the exterior of the facility are within station designated dose rate limits which are more restrictive than the dose rate limits of 1 OCFR20 (refer to page 20).
Inoperable Radioactive Effluent Monitoring Equipment There were two required radioactive effluent monitors that were inoperable for more than 30 days during the reporting period. REl 878B was declared inoperable on January 3, 2011 and re-mained inoperable throughout the year for insulating rail replacement. RE1 822B remained out of service since November 16, 2011 awaiting a cabinet modification. ODCM requirements for these monitors have been fulfilled by backup monitors.
Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Procedure (PCP)
There were two changes to the OCDM during 2011, and included updating information from the 2011 Land Use Census, an addition of a nuclide to Table 2-5, and a description of the Old Steam Generator Storage Building (OSGSF). Several small editorial changes were made, as well.
There were no changes to the PCP during this reporting period.
Borated Water Storage Tank Radionuclide Concentrations During the reporting period of 2011, the Borated Water Storage Tank's sum of limiting fractions of radionuclides concentration, a unitless number, did not exceed the ODCM Section 2.2.4 limit of 1.
90
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 17 Gaseous Effluents - Summation of All Releases I st Qtr 2011 2nd Qtr 3rd Qtr 2011 2011 Est.
4th Qtr Total %
2011 Error Nuclide Unit Fission and Activation Gases Total Release Average Release Rate for Period Percent of ODCM Limits lodines Total lodines (1-13 1)
Average Release Rate for Period Percent of ODCM Limits Ci 5.54E-02 1.62E-01 7.45E-01 4.02E-01 uCi/sec 6.99E-03 2.02E-02 8.28E-02 4.85E-02 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination 2.5 E+0 I Ci 2.79E-06 4.22E-06 0.OOE+00 0.OOE+00 2.5E+01 uCi/sec 3.51E-07 5.24E-07 N/A N/A See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Particulates Particulates with half-lives greater than 8 days Average Release Rate for Period Percent of ODCM Limits Ci 0.OOE+/-00 0.OOE-'-0 0.OOE+00 0.OOE+00 2.5E+01 uCi/sec N/A N/A N/A N/A See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Gross Alpha Activity Ci 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 2.5E+01 Tritium Total Release Average Release Rate for Period Percent of ODCM Limits Ci 2.62E+01 1.85E+01 1.12E+01 2.74E+01 2.5E+01 uCi/sec 3.31E+00 2.30E+00 1.24E+00 3.31E+00 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Note: The average release rate is taken over the entire quarter, not over the time the time period of the re-leases.
91
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 18 Gaseous Effluents - Ground Level Releases - Batch Modea 1st Qtr 2011 2nd Qtr 2011 3rd Qtr 2011 4th Qtr 2011 Nuclide Unit Fission Gases Ci Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD N/A
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD N/A
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD N/A
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD N/A Total for Period:
lodines Ci 1-131 1-133 1-135
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Total for Period:
Particulates and Tritium H-3 Sr-89 Sr-90 Cs-134 Cs-137 Ba-La-140 Total for Period:
N/A N/A N/A N/A Ci 9.28E-03
<LLD
<LLD
<LLD
<LLD
<LLD 9.28E-03 9.58E-03
<LLD
<LLD
<LLD
<LLD
<LLD 9.58E-03 1.37E-02
<LLD
<LLD
<LLD
<LLD
<LLD 1.37E-02 1.32E-03
<LLD
<LLD
<LLD
<LLD
<LLD 1.32E-03 92
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 18 (Continued)
Gaseous Effluents - Ground Level Releases Continuous Modeb 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2011 2011 2011 2011 Fission Gases Ci Kr-85
<LLD
<LLD
<LLD
<LLD Kr-85m
<LLD
<LLD
<LLD
<LLD Kr-87
<LLD
<LLD
<LLD
<LLD Kr-88
<LLD
<LLD
<LLD
<LLD Xe-133
<LLD
<LLD
<LLD
<LLD Xe-135
<LLD
<LLD
<LLD
<LLD Xe-135m
<LLD
<LLD
<LLD
<LLD Xe-138
<LLD
<LLD
<LLD
<LLD Total for Period:
N/A N/A N/A N/A lodines Ci 1-131
<LLD
<LLD
<LLD
<LLD 1-133
<LLD
<LLD
<LLD
<LLD 1-135
<LLD
<LLD
<LLD
<LLD Total for Period:
N/A N/A N/A N/A Particulates and Tritium Ci H-3 2.96E-02 3.28E-02 3.49E-02 1.74E-02 Sr-89
<LLD
<LLD
<LLD
<LLD Sr-90
<LLD
<LLD
<LLD
<LLD Cs-134
<LLD
<LLD
<LLD
<LLD Cs-137
<LLD
<LLD
<LLD
<LLD Ba-La-140
<LLD
<LLD
<LLD
<LLD Total for Period:
2.96E-02 3.28E-02 3.49E-02 1.74E-02 93
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 18 (Continued)
Gaseous Effluents - Ground Level Releases LLDs for Continuousb and Batch' Mode Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 1-131 1-133 1-135 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Ce-141
<1.7E-08
<1.3E-06
<4.6E-09
<2.5E-08
<1.9E-08
<1.IE-08
<4.OE-08
<3.5E-09
<2.5E-07
<4.9E-07
<1.5E-14
<1.6E-14
<7.9E-14
<1.2E-14
<1.4E-14
<3.7E-14
<1.9E-14
<8.0E-16
<2.4E-16
<2.4E-14
<2.2E-14
<1.4E-14
<2.2E-14
<2.4E-14
<l.OE-13
<9.4E-14 piCi/ml
ýtCi/ml liCi/ml pCi/ml l.tCi/ml ptCi/ml liCi/ml iiCi/ml 1tCi/ml piCi/ml ptCi/ml piCi/ml itCi/ml itCi/ml tCi/ml aCi/ml pCi/ml pCi/ml tCi/ml pCi/ml pCi/ml pCi/ml lCi/ml pCi/ml RCi/ml RCi/ml a
Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, and Auxiliary Boiler Outage Release are listed as batch releases.
b Atmospheric Vent Valve weepage and Steam Packing Exhaust are continuous releases.
94
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 19 Gaseous Effluents - Mixed Mode Releases Batch Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Unit 2011 2011 2011 2011 Nuclide Fission Gases Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Total for Period:
- Iodines 1-131 1-133 1-135 Total for Period:
Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.81 E-02
<LLD
<LLD
<LLD
<LLD
<LLD 2.62E-02
<LLD 1.16E-03
<LLD
<LLD
<LLD 1.62E-01
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 2.42E-0 I 1.74E-01
<LLD
<LLD
<LLD
<LLD 3.14E-01
<LLD 1.60E-03
<LLD
<LLD 5.72E-02 2.12E-02
<LLD
<LLD
<LLD 1.29E-03 3.16E-01 1.40E-03 4.60E-03
<LLD
<LLD 5.54E-02 1.62E-0 I 7.45E-01 4.02E-01 Ci Ci Ci Ci
<LLD
<LLD
<LLD 0.OOE+00
<LLD
<LLD
<LLD 0.OOE+00
<LLD
<LLD
<LLD 0.OOE+00
<LLD
<LLD
<LLD 0.00E+00
- Release of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Sta-tion Vent)
Ci Ci Ci Ci Ci Ci Ci 4.54E-02
<LLD
<LLD
<LLD
<LLD
<LLD 4.54E-02 2.24E-03
<LLD
<LLD
<LLD
<LLD
<LLD 2.24E-03 1.21 E+00
<LLD
<LLD
<LLD
<LLD
<LLD 1.2 1E+00 5.19E-01
<LLD
<LLD
<LLD
<LLD
<LLD 5.19E-01 95
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 19 (Continued)
Gaseous Effluents - Mixed Mode Releases Continuous Mode Nuclide Fission Gases Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci 1st Qtr 2011
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 2nd Qtr 2011
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 3rd Qtr 2011
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 4th Qtr 2011 Total for Period:
0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 lodines 1-131 1-132 1-133 1-135 Total for Period:
Ci Ci Ci Ci 2.79E-06
<LLD
<LLD
<LLD 2.79E-06 4.22E-06
<LLD
<LLD
<LLD 4.22E-06
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Particulates, Tritium and Carbon-14 Co-58 Sr-'89 Sr-90 Cs-134 Cs-137 Ba-La-140 C-14 H-3 Total for Period:
Ci Ci Ci Ci Ci Ci Ci Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 2.65E+00 2.62E+0 I 2.88E+01
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 2.65E+00 1.85E+01 2.11E+01
<LLD
<LLD
<LLD
.<LLD
<LLD
<LLD 2.65E+00 9.95E+00 1.26E+01
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 8.15E-01 2.69E+0 1 2.77E+01 96
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 19 (Continued)
LLDs for Gaseous Effluents - Mixed Mode Releases Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 1-131 1-133 1-135 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Ce-141 Continuous Modea
<2.3E-06 pCi/ml
<7.2E-09 vCi/ml
<2.3E-08 tCi/ml
<2.3E-08 aCi/ml
<1.3E-08 aCi/ml
<4.3E-08 pCi/ml
<5.1E-09 RCi/ml
<2.2E-07 pCi/ml
<7.3E-07 pCi/ml
<1.5E-14 PCi/ml
<1.5E-14 pCi/ml
<6.9E-14 pCi/ml
<1.2E-14 pCi/ml
<5.6E-14 pCi/ml
<5.6E-14 VCi/ml
<1.9E-14 pCi/ml
<8.OE-16 ACi/ml
<2.4E-16 pCi/ml
<2.3E-14 pCi/ml
<2.3E-14 pCi/ml
<1.6E-14 pCi/ml
<1.5E-14 pCi/ml
<3.6E-14 pCi/ml
<1.2E-13 XCi/ml
<2.5E-14 PCi/mI Ar-41 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 1-131 1-133 1-135 Sr-89 Sr-90 Cs-134 Cs-137 Ba-140 La-140 Batch Modea
<2.OE-06
[tCi/ml
<7.2E-07
[tCi/ml
<3.OE-06 pCi/ml
<2.2E-06 pCi/ml
<1.2E-06 uCi/ml
<6.OE-06 pCi/ml
<7.9E-07 pCi/ml
<1.8E-05 pCi/ml
<3.4E-05 pCi/ml
<8.8E-07 pCi/ml
<1.1E-06 pCi/ml
<4.8E-06 pCi/ml
<8.OE-16 pCi/ml
<2.4E-16 vCi/ml
<1.IE-06 pCi/ml
<9.7E-07 pCi/ml
<3.4E-06 pCi/ml
<1.1E-06 uCi/ml a
These radionuclides were not identified in every quarter in concentrations above the lower limit of detection (LLD).
97
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 20 Liquid Effluents - Summation of All Releases Type Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total 2011 2011 2011 2011
% Error Fission and Activation Products Total Release (without Tritium, Gases, Alpha)
Average Diluted Concentration During Perioda Percent of ODCM Limits Percent of 1 OCFR20 Limit Tritium Total Release Average Diluted Concentration During Perioda Percent of 1 OCFR20 Limit Dissolved and Entrained Gases Total Release Average Diluted Concentration During Perioda Percent of 10CFR20 Limit Gross Alpha Total Release Volume of Waste Released (prior to dilution)
Batch Continuous Volume of Dilution Water Batch Continuous Total Volume of Water Released Ci 3.46E-03 4.95E-03 1.31E-03 1.69E-03 2.OE-'0l 1.80E-10
.tCi/ml 3.19E-10 4.27E-10 9.42E-1 I See Supplemental information in ODCM Section 2.3, Release Limits 9.25E-03 2.84E-02 1.50E-03 1.55E-03 Ci 1.84E+02 1.76E+02 1.84E+02 9.63E+01 2.OE+01
ýtCi/ml 1.69E-05 1.52E-05 1.32E-05 1.02E-05 1.69E+00 1.52E+00 1.32E+00 1.02E+00 Ci 0.OOE+00 0.00E+00 0.OOE+00 5.3 1E-04 2.OE+01 lpCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 5.62E-I1 6.09E-03 1.73E-05 7.01E-08 2.81E-05 Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.OE+01 liter 3.95E+05 3.62E+05 3.96E+05 5.89E+05 2.OE+01 liter 5.59E+07 4.13E+07 5.51E+07 4.83E+07 2.OE+01 liter
- 1. 14E+08 1.22E+08 1.40E+08 1.63E+08 2.OE+01 liter 1.07E+10 1.14E+10 1.37E+10 9.23E+09 2.OE+01 liter 1.09E+I0 1.16E+I0 1.39E+10 9.44E+09 a Tritium and alpha may be found in both continuous and batch releases. Average diluted concentrations are based on total volume of water released during the quarter. Fission and Activation products and Dissolved and Entrained Gases are normally only detected in batch releases.
98
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 21 Liquid Effluents - Nuclides Released in Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2011 2011 2011 2011 Nuclide Fission and Activation Products Cr-51 Mn-54 Fe-55b Co-57 Co-58 Fe-59 Co-60 Ni-63 Zn-65 Se75 Sr-89b Sr-90b Sr-92 Nb-95 Zr-95 Zr-97 Mo-99 Tc-99m Ru-103 Ru-106 Ag-110m Sb-122 Sb-124 Sb-125 1-131 1-132 Te-132 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.63E-05
<LLD
<LLD
<LLD 9.39E-05
<LLD 4.84E-05 6.3 1E-04
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1.78E-03
<LLD
<LLD
<LLD 3.55E-04 5.24E-04
<LLD
<LLD
<LLD
<LLD 1.99E-05 3.23E-04
<LLD 3.89E-05
<LLD 4.96E-05 7.6 1E-04
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 6.50E-04
<LLD
<LLD
<LLD 1.22E-03 1.88E-03
<LLD
<LLD
<LLD
<LLD
<LLD 4.75E-04
<LLD 3.76E-06
<LLD 1.18E-05 1.86E-04
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1.17E-06
<LLD
<LLD 4.58E-04
<LLD
<LLD
<LLD 6.44E-05 1.11 E-04
<LLD
<LLD
<LLD
<LLD 1.14E-05
<LLD 2.95E-07 3.30E-04
<LLD 1.23E-05 3.53E-04
<LLD
<LLD
<LLD
<LLD
<LLD 1.11 E-05 6.92E-06
<LLD
<LLD
<LLD
<LLD
<LLD 1.99E-05
<LLD 3.16E-04 5.77E-04
<LLD 3.67E-06 1.87E-06 1.30E-05 3.86E-05
<LLD
<LLD
<LLD Total for Period:
Ci 3.46E-03 4.95E-03 1.31E-03 1.69E-03 99
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 21 (continued)
Liquid Effluents - Nuclides Released In Batch Releases Nuclide H-3 Unit Ci Dissolved and Entrained Gases Kr-85 Xe-131m Xe-133 Xe-133m Xe-135 Total for Period:
Ci Ci Ci Ci Ci Ci 1st Qtr 2011 1.84E+02
<LLD
<LLD
<LLD
<LLD
<LLD O.00E+00 2nd Qtr 2011 1.75E+02
<LLD
<LLD
<LLD
<LLD
<LLD O.00E+00 3rd Qtr 2011 1.84E+02
<LLD
<LLD
<LLD
<LLD
<LLD 0.OOE+00 4th Qtr 2011 9.6E+0 1 4.55E-04
<LLD 7.42E-05
<LLD 1.68E-06 5.3 1E-04 100
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 21 (continued)
Liquid Effluents - Nuclidesa Released In Continuous Releases 1st Qtr 2011 2nd Qtr 2011 3rd Qtr 2011 4th Qtr 2011 Nuclide Unit Fission and Activation Products Cr-51 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr-89b Sr-90b Nb-95 Zr-95 Mo-99 Tc-99m 1-131 Cs-134 Cs-137 Ba/La-140 Ce-141 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 4.79E-07
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Total for Period:
4.79E-07 0.OOE+00 0.OOE+00 0.OOE+00 1.15E-01 1.88E-01 1.66E-01 2.45E-01 Tritium Ci Dissolved and Entrained Gases Xe-133 Xe-135 Ci Ci Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Total for Period:
0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 101
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 21 (continued)
Liquid Effluents - LLDs for Nuclides Releaseda Cr-51 Mn-54 Fe-55' Co-57 Co-58 Fe-59 Co-60 Zn-65 Kr-85 Sr-89b Sr-90b Sr-92 Zr-95 Zr-97 Nb-95 Tc-99m Mo-99 Ru-103 Ru-106 Ag-110m Sb-124 Sb-125
<7.1E-08
<1.OE-08
<8.9E-07
<6.3E-09
<1.4E-08
<2.4E-08
<1.4E-08
<2.7E-08
<3.4E-06
<2.2E-08
<9.8E-09
<2.1E-08
<1.2E-08
<1.3E-08
<1.5E-08
<l.1E-08
<9.1 E-08
<i.lE-08
<i.iE-07
<i.iE-08
<1.3E-08
<3.5E-08
[tCi/ml
[tCi/ml LtCi/ml ptCi/ml
ýtCi/ml jiCi/ml PiCi/ml PCi/ml P.Ci/ml PtCi/ml PCi/ml
.tCi/ml PCi/ml p.Ci/ml P.Ci/ml
[tCi/ml PiCi/ml PCi/ml PCi/ml PCi/ml jiCi/ml ACi/ml Ar-41 1-131 Xe-131m Xe-133 Xe-133m Cs-134 Xe-135 Cs-137 Ba-140 La-140 Ce-141 Ce-144
<2.OE-08
<1.OE-08
<4.5E-07
<3.2E-08
<9.5E-08
<1.5E-08
<1.OE-08
<1.3E-08
<3.2E-08
<2.OE-08
<1.7E-08
<9.OE-08 pLCi/ml
[tCi/ml LICi/ml jtCi/ml
[Ci/ml
[tCi/ml ItCi/ml
[tCi/ml
[LCi/ml PCi/ml PtCi/ml PCi/ml a These radionuclides were not identified every quarter in concentrations above the lower limit of detection (LLD). LLDs are applicable to both batch and continuous modes due to identical sample and analysis methods.
b Quarterly composite sample 102
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 22 Solid Waste and Irradiated Fuel Shipments A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 12-month Est. Total
- 1. Type of Waste Unit Period Error, %
- a.
Spent resins, filter sludges, m 3 6.34E+00 2.5E+O1 evaporator bottoms, etc.
Ci 8.09E+O1 2.5E+01
- b.
Dry compressible waste, m3 6.83E+02 2.5E+01 contaminated equip., etc.
Ci 1.95E-01 2.5E+01
- c.
Irradiated components, m3 control rods, etc.
Ci N/A N/A
- d.
Filters m3 2.5E+01 Ci N/A 2.5E+01
- e.
Others: Spent Resin Storage m3 1.14E+O1 2.5E+01 Tank Liquor Ci 6.31E+00 2.5E+01
- 2. Estimate of major nuclide composition (by type of waste)
Type
- a.
Spent Resins
- b.
Dry compressible waste, contaminated equipment, etc.
Ni 63 Cs1 3 7 Cs' 34 Co 6 0 Fe'5 H
3 Ni59 Co 60 Cs' 3 7 Ni 63 Fe55 Nb 95 Zr 95 Co 58 Mn 54 Cs1 3 4 Sb1 25 Pu 241 Sr 90 Percent (%)
6.2 1E+01 1.77E+01 6.59E+00 6.49E+00 6.19E+00 3.59E-01 3.25E-01 3.22E+0 1 3.1OE+01 9.11E+00 7.56E+00 6.97E+00 4.73E+00 3.44E+00 2.89E+00 5.59E-01 5.30E-01 5.02E-01 2.89E-01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+0I Est. Error, %
103
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report
- c.
none
- d. none
- e.
Others: Spent Resin Storage Tank Liquor H3 7.41E+01 2.50E+01 Ni 63 1.84E+01 2.50E+01 Fe55 3.95E+00 2.50E+01 Co 60 1.55E+00 2.50E+01 Co58 1.1OE+00 2.50E+01 AgI 1 Im 3.68E-01 2.50E+01 c14 2.1OE-01 2.50E+O1 Nb95 1.37E-01 2.50E+01 104
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 22 (Continued)
Solid Waste and Irradiated Fuel Shipments
- 3. Solid Waste Disposition Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing 14 Truck Energy Solutions - Clive, UT for disposal at Energy Solutions Clive, UT Metal boxes (assorted sizes, 20-70.8 mi3) 193 m3 13 Truck Energy Solutions - Oak Ridge, TN for processing and disposal at Energy Solutions, Clive, Utah Metal boxes (assorted sizes, 6.1-35.4 m 3) 501.3 m3 1
Truck Entergy Solutions, Kingston, TN for processing and disposal at Energy Solutions of Utah Metal liners (6.1 m 3) 3.964 mi 3
1 Truck Studsvik - Erwin, TN for processing and disposal at Waste Control Specialists; Andrews, TX Metal liners (6.1 mi3 )
2.379 m3 B. IRRADIATED FUEL SHIPMENTS There were no shipments of irradiated fuel.
105
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Onsite Groundwater Monitoring
.Davis-Besse began sampling wells near the plant in 2007 as part of an industry-wide Groundwater Protection Initiative, which was put in place to ensure that there are no inadvertent releases of radioactivity from the plant which could affect offsite groundwater supplies. Sixteen new wells were installed in 2007 to accomplish the monitoring required. These wells are not used for drinking water purposes, and are typically sampled in spring and fall of each year.
The tritium concentrations found in 2011 were all below the 2,000 pCi/liter requiring courtesy notification and the 30,000 pCi/liter EPA limit for non-drinking water sources. Tritium results in site groundwater wells sampled during 2011 continued to trend downward and are listed in Table 23 below:
Table 23. 2011 Groundwater Tritium Results Year 2011 Spring Fall Well No.
[H-3], pCi/I
[H-3], pCiII MW-100A 358 188 MW-100B 358 158 MW-100C
<156
<150 MW-1O1A 296
<144 MW-101B 199 232 MW-101C
<141
<144 MW-102A 565 486 MW-102B 612 397 MW-102C
<156
<150 MW- 03A 539 389 MW- 03B 661 557 MW-103C
<164
<144 MW-104A 419 250 MW-104B 220 280 MW-104C
<164
<150 MW-105A 1021 785 MW-1 8S 275 MW-20S 333 MW-30S 727 MW-31S 1077 MW-32S 606 MW-34S 752 723 MW-37S 1051 794 Figure 30. Davis-Besse Groundwater Monitoring through 2011 106
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Summary of Onsite Spills (>100 gallons) and Notifications On March 29, 2011 an unknown amount of water was spilled while pumping the East Condenser sump to the North Settling Basin during a temporary maintenance lineup. The water contained 7,340 pCi/liter tritium, and required nofication of State, local and county officials.
A spill of unknown volume occurred during the mid-cycle outage on October 11, 2011 when a temporary line being used to direct Turbine Building sumps to the South Settling Basin became disconnected.
The water contained 3,640 pCi/l of tritium and soaked into the surrounding soil.
Notification was made to state, county and local officials following this event. There is no indication that the water in either of the above incidents traveled offsite or affected offsite dose.
The line used in both of these events has been replaced with a more robust, welded plastic pipe to
-prevent future malfunctions during use of this temporary lineup.
Summary of Items Added to Decommissioning Files per 10CFR50.75(g)
The spills listed above were added to the Davis-Besse 1 OCFR50.75(g) decommissioning file and are described in Condition Reports 2011-91925 and 2011-03404.
107
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 24 Doses Due to Gaseous Releases for January through December 2011 Maximum Individual Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.
Whole Body Dose 2.43E-03 mrem Significant Organ Dose (thyroid) 2.44E-03 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 1.82E-04 mrem Skin Dose 3.05E-04 mrem Maximum Individual Dose Due to C-14 Whole Body Dose 1.46E-01 mrem Significant Organ Dose (bone) 7.29E-01 mrem Population Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.
Total Integrated Population Dose 2.16E-02 person-rem Average Dose to Individual in Population 9.89E-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 1.07E-04 person-rem Average Dose to Individual in Population 4.89E-08 mrem Population Dose Due to C-14 Total Integrated Population Dose 1.74E-01 person-rem Average Dose to Individual in Population 7.97E-05 mrem.
108
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 25 Doses Due to Liquid Releases for January through December 2011 Maximum Individual Whole Body Dose Maximum Individual Significant Organ Dose (LIVER)
Population Dose Total Integrated Population Dose Average Dose to Individual 3.76E-02 mrem 5.03E-02 mrem I.36E+00 person-rem 6.24E-04 mrem 109
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 26 Annual Dose to The Most Exposed (from all pathways) Member of the Public 2011 ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem)
(mrem)
LIMIT Whole Body Dose*
Noble Gas 1.82E-04 Iodine, Tritium, Particulates 2.43E-03 C-14 1.46E-01 Liquid 3.76E-02 Total Whole Body Dose 1.86E-01 25 7.44E-01 Thyroid Dose Iodine, Tritium, Particulates 5.70E-03 75 7.60E-03 Skin Dose Noble Gas 3.05E-04 25 1.22E-03 Significant Organ Dose (liver) 5.27E-02 25 2.1OE-01 Significant Organ Dose (C-14) 7.29E-01 25 2.92E+00 (bone)
Meteorological Data Meteorological data, stored on a compact disk for January 1 through December 31, 2011, has been submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555.
- Direct radiation from the facility is not distinguishable from natural background and is, therefore, not included in this compilation.
110
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Land Use Census Program Design Each year a Land Use Census is conducted by Davis-Besse in order to update information neces-sary to estimate radiation dose to the general public and to determine if any modifications are necessary to the Radiological Environmental Monitoring Program (REMP). The Land Use Cen-sus is required by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis-Besse Nuclear Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use Census Data. The Land Use Census identifies gaseous pathways by which radioactive mate-rial may reach the general population around Davis-Besse. The information gathered during'the Land Use Census for dose assessment and input into the REMP ensure these programs are as cur-rent as possible. The pathways of concern are listed below:
" Inhalation Pathway - Internal exposure as a result of breathing radionuclides car-ried in the air.
" Ground Exposure Pathway - External exposure from radionuclides deposited on the ground
" Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.
" Vegetation Pathway - Internal exposure as a result of eating vegetables, fruit, etc.
which have a build up of deposited radioactive material or which have absorbed ra-dionuclides through the soil.
- Milk Pathway - Internal exposure as a result of drinking milk, which may contain radioactive material as a result of a cow or goat grazing on a pasture contaminated by radionuclides.
Methodology The Land Use Census consists of recording and mapping the locations of the closest residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) in each me-teorological sector within a five mile radius of Davis-Besse.
The surveillance portion of the 2011 Land Use Census was performed during the month of Au-gust. In order to gather as much information as possible, the locations of residences, dairy cows, dairy goats, and vegetable gardens were recorded. The residences, vegetable gardens, and milk animals are used in the dose assessment program. The gardens should be at least 500 square feet in size, with at least 20% of the vegetables being broadleaf plants (such as lettuce and cabbage).
Each residence is tabulated as being an inhalation pathway, as well as ground and plume expo-sure pathways. Each garden is tabulated as a vegetation pathway:
III
Davis-Besse. Nuclear Power Station 2011 Annual Radiological Environmental Operating Report All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 mi-nute series of the relevant quadrangles) which has been divided into 16 equal sectors correspond-ing to the 16 cardinal compass points (Figure 30). If available, the closest residence, milk ani-mal, and vegetable garden in each sector are determined by measuring the distance from each to the Station Vent at Davis-Besse.
Results The following changes in the pathways were recorded in the 2011 census:
SSW sector: A garden at 5,630 meters replaced the one at 4,280 meters.
SSE sector: A garden at 2,890 meters replaced the garden at 2,930 meters.
The critical receptor is a garden in the W sector at 1,560 meters from Davis-Besse, and is unchanged from 2010.
The detailed list in Table 27 was used to update the database of the effluent dispersion model used in dose calculations. Table 27 is divided by sectors and lists the distance (in meters) of the closest pathway in each.
Table 28 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and deposition (D/Q) parameters for each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and in cal-culating liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints.
112
DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PRIMARY PATHWAYS WITHIN A 5 MILE RADIUS WNW I-CL CD 3
CLOSEST SITES Within Sector RES I DENCE a
DB: 04-19-12 DFN-Fý
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 27 Closest Exposure Pathways Present in 2011 Sector Distance from Station (meters)
Closest Pathways N
880 Inhalation Ground Exposure Plume Exposure NNE 880 Inhalation Ground Exposure Plume Exposure NE 900 Inhalation Ground Exposure Plume Exposure ENE, E, ESE N/A Located over Lake Erie SE 8,000 Inhalation Ground Exposure Plume Exposure
- SSE 2,890 Vegetation SSE 1,500 Inhalation Ground Exposure Plume Exposure S
6,040 Vegetation S
1,090 Inhalation Ground Exposure Plume Exposure
- SSW 5,630 Vegetation SSW 980 Inhalation Ground Exposure Plume Exposure SW 1,070 Inhalation Ground Exposure Plume Exposure
- Changed from the 2010 Land Use Census 114
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 27 Closest Exposure Pathways Present in 2011 Sector Distance from Station (meters)
Closest Pathways SW 5,600 Vegetation WSW 1,540 Inhalation Ground Exposure Plume Exposure WSW 6,450 Vegetation W
980 Inhalation Ground Exposure Plume Exposure W
1,560 Vegetation WNW 1,520 Inhalation Ground Exposure Plume Exposure NW 2,250 Vegetation NW 1,490 Inhalation Ground Exposure Plume Exposure NNW 1,290 Inhalation Ground Exposure Plume Exposure 115
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 28 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q)
Parameters SECTOR METERS CRITICAL AGE X/Q D/Q PATHWAY GROUP (SEC/M3)
(M-2)
N 880 Inhalation Child 9.15E-07 8.40E-09 NNE 880 Inhalation Child 1.24E-06 1.44E-08 NE 900 Inhalation Child 1.26E-06 1.58E-08 E N E
- E
- E S E
- SE 8,000 Inhalation Child 3.43E-08 1.45E-10 SSE**
2,890 Vegetation Child 6.83E-08 7.96E-10 S
6,040 Vegetation Child 2.82E-08 1.56E-10 SSW**
5,630 Vegetation Child 2.60E-08 2.04E-10 SW 5,600 Vegetation Child 3.58E-08 2.94E-10 WSW 6,450 Vegetation Child 3.89E-08 2.39E-10 W
1,560 Vegetation Child 2.94E-07 4.67E-09 WNW 1,520 Inhalation Child 1.89E-07 2.27E-09 NW 2,250 Vegetation Child 7.19E-08 6.04E-10 NNW 1,290 Inhalation Child 2.31E-07 1.67E-09
- Since these sectors are located over marsh areas and Lake Erie, no ingestion pathways are present.
- Changed from 2010 Land Use Census 116
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Non-Radiological Environmental Programs Meteorological Monitoring The Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nu-clear power stations on the surrounding environment. Both NRC regulations and the Davis-Besse Technical Requirements Manual provide guidelines for the Meteorological Monitoring Program. These guidelines ensure that Davis-Besse has the proper equipment, in good working order, to support the many programs utilizing meteorological data.
Meteorological observations at Davis-Besse began in October 1968. The Meteorological Moni-toring Program at Davis-Besse has an extensive record of data with which to perform climate studies which are used to determine whether Davis-Besse has had any impact upon the local cli-mate. After extensive statistical comparative research the meteorological personnel have found
.no impact upon local climate or short-term weather patterns.
.-,The Meteorological Monitoring Program also provides data that can be used by many other groups and programs such as the Radiological Environmental Monitoring Program, the Emer-gency Preparedness Program, Site Chemistry, Plant Operations, Nuclear Security, Materials Management and Industrial Safety, as well as other plant personnel and members of the sur-rounding community.
The Radiological Environmental Monitoring Program uses meteorological data to aid in evaluat-ing the radiological impact, if any, of radioactivity released in Station effluents. The meteoro-logical data is used to evaluate radiological environmental monitoring sites to assure the program is as current as possible. The Emergency Preparedness Program uses meteorological data to cal-culate emergency dose scenarios for emergency drills and exercises and uses weather data to plan evacuations or station isolation during adverse weather. The Chemistry Unit uses meteorological data for chemical spill response activities, marsh management studies, and wastewater discharge flow calculations. Plant Operations uses meteorological data for cooling tower efficiency calcu-lations, Forebay water level availability and plant work which needs certain environmental condi-tions to be met before work begins. Plant Security utilizes weather data in their routine planning and activities. Materials Management plans certain Plant shipments around adverse weather conditions to avoid high winds and precipitation, which would cause delays in material deliveries and safety concerns. Industrial Safety uses weather and climate data to advise personnel of un-safe working conditions due to environmental conditions, providing a safer place to work.
Regulatory Affairs uses climate data for their investigation into adverse weather accidents in rela-tion to the Plant and personnel.
- i. More detailed weather information is available upon request.
117
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report On-site Meteorological Monitoring
System Description
At Davis-Besse there are two meteorological systems, a primary and a backup. Both are housed in separate environmentally controlled buildings with independent power supplies. Both primary and backup systems have been analyzed to be statistically identical, so that if a redundant system in one unit fails, the other system can take its place. The instrumentation of each system follows:
PRIMARY BACKUP 100 Meter Wind Speed 100 Meter Wind Speed 75 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 100 Meter Wind Direction 75 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 100 Meter Delta Temperature 75 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Ambient Temperature 10 Meter Dew Point 10 Meter Solar Incidence Precipitation Meteorological Instrumentation The meteorological system consists of one monitoring site located at an elevation of 577 feet above mean sea level (IGLD 1955)*. It contains a 100m free-standing tower located about 3,000 feet SSW of the Cooling Tower and a 10m auxiliary tower located 100 feet west of the 100 m tower. Both are used to gather the meteorological data. The 1 00m tower has primary and backup instruments for wind speed and wind direction at 100m and 75m. The 100m tower also measures differential temperature (delta Ts): 100-10m and 75-10m. The 10m tower has instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the 1 Om tower.
According to the Davis-Besse Nuclear Power Station Technical Requirements Manual, a mini-mum of five instruments are required to be operable at the two lower levels (75m and 10m) to measure temperature, wind speed, and wind direction. During 2011, average annual data recov-eries for all required instruments were 99.45 percent. Minor losses of data occurred during rou-tine instrument maintenance, calibration, and data validation.
Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly. Data is reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required. Tower instrumentation maintenance and semiannual calibrations are performed by in-house facilities and by an outside consulting firm. These instruments are wind tunnel tested to assure compliance with applicable regulations and plant specifications.
- International Great Lakes Data - 1955 118
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Meteorological Data Handling and Reduction Each meteorological system, primary and backup, have two Campbell Scientific Data-loggers (model 21XL) assigned to them. The primary system has a first data logger to communicate 900 second averages to the control room via a Digital Alpha computer system. This is a dedicated line. If a failure occurs at any point between the primary meteorological system and the control room the control room can utilize the second data logger in the primary shelter. Each data logger has its own dedicated communication link with battery backup. The backup meteorological sys-tem is designed the same as the primary; so to lose all meteorological data the primary and backup meteorological systems would have to lose all four data loggers. However, this would be difficult since each is powered by a different power supply and equipped with lightning and surge protection, plus four independent communication lines and data logger battery backup.
The data from the primary and backup meteorological systems are stored in a 30-day circular storage module with permanent storage held by the Digital Alpha computer. Data goes back to 1988 in this format and to 1968 in both digital and hardcopy formats. All data points are scruti-nized every 900 seconds by meteorological statistics programs running continuously. These are then reviewed by meteorological personnel daily for validity based on actual weather conditions.
A monthly review is performed using 21 NRC computer codes, which statistically analyze all data points for their availability and validity. If questionable data on the primary system can not be corroborated by the backup system, the data in question is eliminated and not incorporated into the final database. All validated data is then documented and stored on hard copy and in digital format for a permanent record of meteorological conditions.
Meteorological Data Summaries This section contains Tables 29-31, which summarize meteorological data collected from the on-site monitoring program in 2011.
Wind Speed and Wind Direction Wind sector graphics represent the frequency of wind direction by sector and the wind speed in mph by sector. This data is used by the NRC to better understand local wind patterns as they re-late to defined past climatological wind patterns reported in Davis-Besse's Updated Safety Analysis Report. The maximum measured sustained wind speed for 2011 occurred on November 29, when they were measured at 50.08 mph at the 100m level, 44.11 mph on February 2 at the 75m level, and 33.16 mph on November 29 at the 10m level.
Figures 32-34 give an annual sector graphic of average wind speed and percent frequency by, di-rection measured at the three monitoring levels. Each wind sector graphic has two radial bars.
The darker bar represents the percent of time the wind blew from that direction. The hatched bar represents the average wind speed from that direction. Wind direction sectors are classified us-ing Pasquill Stabilities. Percent calms (less than or equal to 1.0 mph) are shown in the middle of the wind sector graphic.
119
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2011 are given in Table 30.
These data are measured at the 10m level; with differential temperatures taken from 100 meter and 75 meter levels. The yearly average ambient temperature was 51.32°F.
The maximum temperature was 97.28'F on July 21, 2011 with a minimum temperature of -5.3 1°F on February 10, 2011. Yearly average differential temperatures were -0.867°F (100 meter), and -0.289°F (75 meter). Maximum differential temperatures for 100 meter and 75 meter levels were 7.94°F on December 13, 2011 (100 meter), and 2.87°F (75 meter) on December 12, 2011. Minimum dif-ferential temperatures for 100m and 75m levels were -3.73°F on December 05, 2011 (100 meter) and -1.45°F on December 15, 2011 (75 meter). Differential temperatures are a measurement of atmospheric stability and used to calculate radioactive plume dispersions based on Gaussian Plume Models of continuous effluent releases.
Dew Point Temperatures and Relative Humidity Monthly average and extreme dew point temperatures for 2011 are provided in Table 30. These data are measured at the 10m level. The average dew point temperature was 1.103°F with a maximum dew point temperature of 21.44°F on December 21, 2011. Please note that dew point temperatures above 75°F are highly suspect and are possibly due to calm winds and high solar heating allowing the aspirated dew point processor to retain heat. The minimum dew point (dew point under 32°F is frost point) temperature was -13.620'F on December 11, 2011. It is possible to have relative humidity above 100 percent, which is known as supersatura-tion. Conditions for supersaturation have been met a few times at Davis-Besse due to its close proximity to Lake Erie, and the evaporative pool of moisture available from such a large body of water.
Precipitation Monthly totals and extremes of precipitation at Davis-Besse for 2011 are given in Table 30. To-tal precipitation for the year was 39.90 inches. The maximum daily precipitation total was 2.90 inches on August 14, 20i1. There were many days on which no precipitation was recorded. It is likely that precipitation totals recorded in colder months are somewhat less than actual due to snow/sleet blowing across the collection unit rather than accumulating in the gauge.
Lake Breeze and Lake Level Monitoring Lake Breeze is monitored at Davis-Besse because of its potential to cause major atmospheric/
dispersion problems during an unlikely radioactive release. A lake breeze event occurs during the daytime, usually during the summer, where the land surface heats up faster than the water, and therefore reaches higher temperatures than the water. The warmer air above the land rises faster because it is less dense than the cooler air over the lake. This leads to rising air currents over the land with descending denser air over the lake. This starts a wind circulation, which draws air from the water to the land during the daytime, creating a "Lake Breeze" effect. This event could be problematic if a release were to occur because diffusion would be slow thus creat-120
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Davis-Besse to observe, evaluate, predict and disseminate high or low lake level information.
This data is critical in the running of the plant due to the large amounts of water needed to cool plant components. If water levels get too low the plant operators can take measures for the safe shutdown of the plant. Since Lake Erie is the shallowest of the Great Lakes, it is not uncommon for five feet lake level fluctuation to occur within an eight to ten hour period (plus or minus).
High water levels also affect the plant due to emergency transportation and evacuation pathways.
121
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 29 Summary of Meteorological Data Recovery For The Davis-Besse Nuclear Power Station January 1, 2011 through December 31, 2011 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2010 100m Wind Speed 100 100 99.87 94.17 100 100 100 100 100 100 99.72 100 99.49 100M Wind Direction 100 100 100 87.92 100 100 100 96.10 100 43.82 91.94 100 93.24 75M Wind Speed 100 100 99.87 99.72 100 100 100 100 100 100.
99.72 100 99.94 75M Wind Direction 100 100 100 79.17 100 100 100 100 100 100 100 100 98.29 1OM Wind Speed 100 100 99.87 100 100 100 100 100 100 100 99.72 100 99.97 1OM Wind Direction 100 100 100 100 100 100 100 100 100 93.95 100 1.00 99.49 1OM Ambient Air Temp 100 100 99.87 100 100 100 100 100 100 100 99.72 100 99.97 10M Dew Point Temp 100 100 99.87 100 100 100 100 100 100 100 99.72 100 99.97 Delta T (IOOM-IOM) 100 100 99.87 100 100 100 100 100 100 100 99.72 100 99.97 Delta T (75M-IOM) 100 100 99.87 100 100 100 100 100 100 100 99.72 100 99.97 Joint lOOM Winds and Delta T (IOOM-1OM) 100 100 99.87 87.92 100 100 100 96.10 100 43.82 91.67 100 93.21 Joint 75M Winds and Delta T (IOOM-IOM) 100 100 99.87 78.89 100 100 100 100 100 100 99.72 100 98.23 Joint 1OM Winds and Delta T (75M-IOM) 100 100 99.87 100 100 100 100 100 100 93.95 99.72 100 99.45
- all data for individual months expressed as percent of time instrument was operable during the month, divided by the maximum number of hours in that month that the instru-ment could be operable. Values for annual data recoveries equals the percent of time instrument was operable during the year, divided by the number of hours in the year that the instrument Was operable.
122
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 30 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1, 2011 through December 31, 2011 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV 100M WIND Max Speed (mph)
Date of Max Speed Min Speed (mph)
Date of Min Speed Ave Wind Speed 75M WIND Max Speed (mph)
Date of Max Speed Min Speed (mph)
Date of Min Speed Ave Wind Speed IOM WIND Max Speed (mph)
Date of Max Speed Min Speed (mph)
Date of Min Speed Ave Wind Speed 29.54 48.79 35.93 47.29 34.14 33.46 24.95 39.41 01/15 02/02 03/05 04/28 05/15 06/01 07/22 08/24 1.89 0.15 1.50 1.17 2.31 1.93 1.01 1.83 01/20 02/26 03/25 04/01 05/20 06/11 07/09 08/21 14.90 17.45 16.56 19.71 14.92 14.31 12.21 12.30 26.94 44.11 31.48 37.38 29.36 31.24 23.28 35.06 01/15 02/02 03/05 04/15 05/23 06/01 07/02 08/24 1.90 0.42 1.38 1.67 2.36 2.16 1.68 1.58 01/20 02/23 03/28 04/13 05/20 06/20 07/09 08/31 13.35 15.11 14.67 17.76 12.97 13.04 10.99 11.08 20.79 29.17 21.94 31.917 24.19 22.71 18.49 24.17 01/15 02/14 03/12 04/28 05/15 06/01 07/13 08/24 1.72 1.05 1.11 1.47 1.49 1.23 0.96 1.29 01/20 02/23 03/25 04/13 05/04 06/20 07/08 08/20 8.64 10.27 9.97 12.14 8.76 8.09 6.55 6.78 37.05 09/07 1.72 09/09 14.92 32.53 09/30 1.65 09/09 12.96 37.63 50.08 10/15 11/29 1.24 1.98 10/07 11/14 15.85 20.90 35.19 39.20 10/15 11/09 1.63 2.11 10/07 11/14 13.79 18.30 DEC 2011.
36.15 50.08 12/15 11/29 1.97 0.15 12/23 02/26 16.85 15.86 32.90 44.11 12/28 02/02 1.66 0.42 12/23 02/23 14.82 14.04 23.73 33.16 12/15 11/29 1.46 0.88 12/23 09/11 9.10 8.97 25.65 26.10 33.16 09/07
.10/15 11/29 0.88 1.23 1.36 09/11 10/05 11/03 8.33 8.05 11.26 123
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 30 (continued)
Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1, 2011 through December 3 1, 2011 JAN FEB MAR APR MAY JUN JUL AUG IOM AMBIENT TEMP Max (F) 56.63 56.43 67.96 82.27 89.73 94.23 97.28 87.85 Date of Max 01/01 02/18 03/17 04/10 05/31 06/08 07/21 08/24 Min (F)
-0.02
-5.31 19.84 31.94 41.89 57.35 66.79 55.81 Date of Min 01/22 02/10 03/07 04/03 05/05 06/03 07/05 08/22 Ave Temp 22.63 27.43 35.82 47.76 59.49 70.46 77.82 72.42 IOM DEW POINT TEMP Mean (F)
-6.90
-3.96 2.24 11.15 20.69 27.51 33.31 29.11 Max (F) 20.00 19.63 23.29 33.23 38.53 42.08 43.54 40.01 Date of Max 01/01 02/18 03/17 04/10 05/30 06/07 07/21 08/24 Min (F) -24.42
-28.52
-10.16
-0.73 5.57 15.65 22.62 17.73 Date of Min 01/22 02/10 03/03 04/06 05/05 06/03 07/01 08/30 PRECIPITATION Total (inches) 0.96 2.30 2.61 3.92 5.16 1.37 2.42 4.33 Max. in One Day 0.30 0.61 0.76 0.74 1.75 0.40 1.01 2.90 Date 01/01 02/28 03/05 04/25 05/25 06/21 07/23 08/14 SEP OCT 91.85 75.15 09/02 10/08 43.40 32.15 09/30 10/30 63.83 53.25 23.33 14.28 40.97 28.18 09/02 10/08 7.47 1.12 09/30 10/30 6.63 0.85*
1.90 0.29*
09/08 10/01*
NOV DEC 2010 68.74 58.75 97.28 11/08 12/21 07/21 26.26 19.05
-5.31 11/18 12/11 02/10 46.99 36.34 51.32 8.57 1.10 13.47 23.53 21.44 43.54 11/14 12/21 07/21
-7.68
-13.62
-28.52 11/18 12/11 02/10 5.82 3.53 39.90*
1.74 1.04 2.90 11/22 12/05 08/14 Note: 1.84 inches was recorded by Toledo Weather Bureau on Oct 1 9th, 2011 which was not recorded by Davis-Besse due to an electrical fault at the rain gauge.
Reference CR 2011-04034.
124
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Figure 32 Wind Rose Annual Average 1 OOM Wi
ý-PEED (11!-, CT[OG F, ~i it)
DAVIS-BESSE ANNUAL 2011 1OOM LEVEL 125
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average 75M E
111 0crio PFOUI'M NCY C.X DAVIS-BESSE ANNUAL 2011 75M LEVEL 126
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Figure 34 Wind Rose Annual Average 1 M W
WIND SPEEO (MPH)
OMFEGIJON FREQUENCYM DAVIS-HBESSE ANNUAL 2011 IOM LEVEL 127
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 31 Joint Frequency Distribution by Stability Class DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT PROGRAM:
JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP DATA PERIOD EXAMINED: 01/01/Il - 12/3 1/11 15-Mar-12 PAGE 91 TIME OF DAY:
14:10:40 SITE IDENTIFIER: I I
- ANNUAL
- STABILITY CLASS A STABILITY BASED ON:
DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:
35.0 FEET WIND THRESHOLD AT:
1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)'
N NNE NE ENE E
WNW NW NNW TOTAL CALM 0
1.01-3.49 0
0 0
I 2
0 1
0 0
2 3
4 3
I 2
0 19 3.50-7.49 14 3
14 24 34 9
4 2
0 8
10 11 5
15 25 17 195 7.50-12.49 20 7
22 53 27 5
0 1
3 6
14 16 16 31 72 31 324 12.50-18.49 7
4 12 4
0 0
0 1
1 4
4 8
10 18 21 II 105 18.50- 24.49 4
1 5
4 4
1 0
0 0
0 1
3 0
0 0
2 25 5
0 0
0 0
14
>24.49 0
2 2
4 0
0 0
0 0
0 1
TOTAL 45 17 55 90 67 15 5
4 4
20 33 47 34 65 120 61 682 STABILITY CLASS B STABILITY BASED ON:
DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:
35.0 FEET WIND THRESHOLD AT:
1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)
N NNE NE ENE E
WNW NW NNW TOTAL CALM 1.01-3.49 0
0 0
0 I
1
.1 0
3 0
0 3.50-7.49 2
6 9
7 10 7
6 2
1 10 13 7.50-12.49 8
3 7
21 8
3 0
1.,
2 12 25 0
0 5
3 9
9 0
0 3
I 8
8 2
2 I
7 4
89 8
132 6
66 12.50 -18.49 2
4 6
8 0
0 0
1 4
7 8
10 6
18.50- 24.49 1
3 0
- 2.
0 0
0 0
0 0
0
>24.49 0
1 I
0 0
0 0
0 0
0 4
2 1
0 0
0 0
0 0
I 0
9 7
TOTAL
' 13 17 23 38 19 11 7
4 10 29 50 26 19 13 12 19 310 128
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 15-Mar-12 PAGE 92 TIME OF DAY:
14:10:40 PROGRAM:
JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP DATA PERIOD EXAMINED: 01/01/Il - 12/3 1/Il1
- ANNUAL
- STABILITY CLASS C SITE IDENTIFIER: I I STABILITY BASED ON:
DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:
35.0 FEET WIND THRESHOLD AT:
1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)
N NNE NE ENE E
WNW NW NNW TOTAL CALM 1.01 - 3.49 0
0 0
0 0
0 0
3.50-7.49 3
7 7
9 11 6
9 7.50- 12.49 7
8 12 13 9
1 1
12.50-18.49 1
7 3
6 3
0 0
18.50 -24.49 1
10 1
2 0
0 0
>24.49 0
2 1
0 0
0 0
0 3
1 0
0 0
0 1
1 4
13 10 2
15 17 3
8 20 1
2 3
0 1
0 0
4 13 16 4
0 7
8 4
0 0
4 5
6 0
0 0
5 8
4 0
0 0
0 3
3 99 9
128 4
89 0
28 0
4 TOTAL 12 34 24 30 23 7
10 4
10 40 51 37 21 15 17 16 351 STABILITY CLASS D STABILITY BASED ON:
DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:
35.0 FEET WIND THRESHOLD AT:
1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)
CALM N
NNE NE ENE E
WNW NW NNW TOTAL 0
1.01-3.49 6
5 1
4 11 7
10 11 12 14 4
3 3
I 6
3 101 3.50-7.49 48 58 78 91 85 47 31 41 106 113 72 57 45 19
- 20.
26 937 7.50-12.49 50 85 113 145 94 26 27 23 53 166 172 135 93 49 47 69 1347 12.50- 18.49 53 135 128 67 20 5
2 I
22 56 133 100 57 39 20 53 891 18.50 -24.49 10 63 29 23 1
0 0
2 3
7 31 34 10 5
24 9
251
>24.49 10 5
3 3
0 0
0 0
1 1
9 1
I 0
0 1
35 TOTAL 177 351 352 333 211 85 70 78 197 357 421 330 209 113 117 161 3562 129
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT PROGRAM: JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP DATA PERIOD EXAMINED: 01/01/11 - 12/31/11 15-Mar-12 PAGE 93 TIME OF DAY:
14:10:40 SITE IDENTIFIER: II
- ANNUAL ***
STABILITY CLASS E STABILITY BASED ON:
DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:
35.0 FEET WIND THRESHOLD AT:
1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)
N NNE NE ENE E
WNW NW NNW TOTAL CALM 1.01-3.49 7
9 4
7 24 25 27 50 68 25 28 3.50-7.49 18 20 41 54 117 114 82 102 161 243 128 7.50-12.49 23 16 25 44 43 14 16 18 81 179 129 12.50 -18.49 7
11 9
7 2
4 5
3 14 74 51 18.50-24.49 1
1 3
0 0
0 0
1 0
7 12
>24.49 0
0 0
0 0
0 0
0 0
0 4
10 9
6 3
6 308 65 56 30 19 23 1273 92 55 32 49 29 845 34 19 9
19 8
276 10 0
0 0
I 36 0
0 0
0 0
4 TOTAL 56 57 82 112 186 157 130 174 324 528 352 211 139 STABILITY CLASS F STABILITY BASED ON:
DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:
35.0 FEET WIND THRESHOLD AT:
1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET 77 90 67 2743 SPEED (MPH)
CALM N
NNE NE ENE E
WNW NW NNW TOTAL 2
1.01 -3.49 0
1 3.50-7.49 2
0 7.50- 12.49 0
4 12.50- 18.49 0
1 18.50 - 24.49 0
0
>24.49 0
0 2
1 7
0 0
0 4
8 17 21 43 46 41 25 13 8
5 29 27 16 17 54 142 61 46 30 3
5 1
1 2
5 4
13 8
6 0
0 0
0
- 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 2
17 5
1 "5
0 0
0 0
0 0
2 234 1
453 3
68 0
1 0
0 0
0 TOTAL 2
6 10 12 42 45 38 62 105 187 99 67 44 19 12 6
758 130
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 15-Mar-12 PAGE 94 TIME OF DAY:
14:10:40 PROGRAM: JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP DATA PERIOD EXAMINED: 01/01/11 - 12/31/11
- ANNUAL ***
STABILITY CLASS G SITE IDENTIFIER: I I STABILITY BASED ON:
DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:
35.0 FEET WIND THRESHOLD AT:
1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)
N NNE NE ENE E
WNW NW NNW TOTAL CALM 1.01 -3.49 0
0 3.50-7.49 0
0 7.50-12.49 0
0 12.50-18.49 0
0 18.50 - 24.49 0
0
>24.49 0
0 0
0 1
0 0
0 1
5 9
12 20 35 44 10 0
9 4
4 5
16 69 21 1
1 1
0 0
0 0
0 0
0 0
0 0
0
.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
11 5
11 8
0 I
0 0
0 0
0 0
1 0
I 0
0 0
0 0
0 0
0
.0 0
0 153 0
148 0
5 0
0 0
0 0
0 TOTAL 0
0 1
2 15 14 16 25 51 113 31 22 14 0
0 306 STABILITY CLASS ALL STABILITY BASED ON:
DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:
35.0 FEET WIND THRESHOLD AT:
1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)
CALM N
NNE NE ENE E
WNW NW NNW TOTAL 3
1.01 -3.49 13 15 7
17 51 59 72 124 164 127 71 41 29 10 13 12 825 3.50-7.49 87 94 150 190 295 214 152 172 342 598.
315 199 148 89 75 74 3194 7.50-12.49 108 123 187 280 187 51 45 46 146 382 370 273 187 126 189 149 2849 12.50 -18.49 70 162 158 92 25 9
7 6
44 149 216 168 100 74 66 82 1428 18.50 -24.49 17 78 38 31 5
1 0
3 4
16 47 53 15 5
24 12 349
>24.49 10 10 7
7 0
0 0
0 1
2 18 6
I 0
1 I
64 TOTAL 305 482 547 617 563 334 276 351 701 1274 1037 740 480 304 368 330 8712 131
Land and Wetlands Management The Navarre Marsh, which is part of the Ottawa National Wildlife Refuge, makes up 733 acres of wetlands on the southwestern shore of Lake Erie and surrounds the Davis-Besse Nuclear Power Station. The marsh is owned by FirstEnergy and jointly managed by the U.S. Fish and Wildlife Service and FirstEnergy. Navarre Marsh is divided into three pools. The pools are separated from Lake Erie and each other by a series of dikes and revetments. Davis-Besse is responsible for the maintenance and repair of the dikes and controlling the water levels in each of the pools.
A revetment is a retaining structure designed to hold water back for the purposes of erosion con-trol and beach formation. Revetments are built with a gradual slope, which causes waves to dis-sipate their energy when they strike their large surface area. Beach formation is encouraged through the passive deposition of sediment. A dike is a retaining structure designed to hold wa-ter for the purpose of flood control and to aid in the management of wetland habitat. When used as a marsh management tool, dikes help in controlling water levels in order to maintain desired vegetation and animal species. Manipulating water levels is one of the most important marsh management techniques used in the Navarre Marsh. Three major types of wetland communities exist in Navarre Marsh, the freshwater marsh, the swamp forest, and the wet meadow. Also, there exists a narrow dry beach ridge along the lakefront, with a sandbar extending out into Lake Erie. All these areas provide essential food, shelter and nesting habitat, as well as a resting area for migratory birds.
Davis-Besse personnel combine their efforts with a number of conservation agencies and organi-zations. The Ottawa National Wildlife Refuge, the Ohio Department of Natural Resources (ODNR), and the Black Swamp Bird Observatory work to preserve and enhance existing habitat.
Knowledge is gained through research and is used to help educate the public about the impor-tance of preserving wetlands.
With its location along two major migratory flyways, the Navarre Marsh serves as a refuge for a variety of birds in the spring and fall, giving them an area to rest and restore energy reserves be-fore continuing their migration. The Black Swamp Bird Observatory, a volunteer research group, captures, bands, catalogues, and releases songbirds in the marsh during these periods.
Navarre Marsh is also home to wildlife that is typical of much of the marshland in this area, in-cluding deer, fox, coyote, beavers, muskrats, mink, rabbits, groundhogs, hawks, owls, ducks, geese, herons, snakes and turtles. American Bald Eagles chose the Navarre Marsh as a nesting site in late 1994, and fledged a healthy eaglet in July 1995. A second pair built a nest in 1999-2000, and the total number of eagles fledged from these two nests since 1995 is twenty-two.
Ohio has gone from a low of 4 nesting eagle pairs statewide in 1978 to setting new hatch records every year for nearly three decades.
132
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Water Treatment Plant Operation Description The Davis-Besse Nuclear Power Station draws water from Lake Erie for its water treatment plant. The lake water is treated with sodium hypochlorite and/or sodium bromide, coagulant aid, filtration, electrolysis and demineralization to produce high-purity water used in many of the Sta-tion's cooling systems.
Water from the Carroll Township Water Treatment Plant is used in Davis-Besse's Fire Protection System.
Water Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which remove debris greater than one-half inch in size. The water is then pumped to chlorine detention tanks. Next, the water is sent to the pre-treatment system, which is comprised of coagulation and filtration to remove sediment, organic debris, and certain dissolved compounds from the raw wa-ter. The next step of the process is reverse osmosis, where pressure is used to remove certain im-purities by passing the water through a selectively-permeable membrane.
The water is then stripped of dissolved gases, softened, electrolytically deionized and finally, is routed through a polishing demineralization process before being sent to storage.
Domestic Water When Davis-Besse began operation over 30 years ago, all site domestic water was produced in the Water Treatment Facility. Operation of the domestic water treatment and distribution system, including the collection and analysis of daily samples, was reportable to the Ohio Environmental Protection Agency.
Since December of 1998, the Carroll Township Water Treatment Plant has supplied domestic water to Davis-Besse. Carroll Township Water and Wastewater District follow all applicable regulatory requirements for the sampling and analysis of Station drinking water.
Zebra Mussel Control With the exception Of its domestic water, the Plant withdraws all of its water through an intake system from Lake Erie. Zebra mussels have, in the past, had the potential to severely impact the availability of water for Plant processes. Dreissena polymorpha, commonly known as the zebra mussel, is a native European bivalve that was introduced into the Great Lakes in 1986 and was discovered in Lake Erie in 1989. Zebra mussels are prolific breeders that rapidly colonize an area by forming byssal threads, which enable them to attach to solid surfaces and to each other.
Because of their ability to attach in this manner, they may form layers several inches deep. This has posed problems to facilities in the past for water intakes on Lake Erie because mussels attach to the intake structures and restrict water flow.
133
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Zebra mussels have not caused any significant problems at Davis-Besse due to effective biocide control. At present, the mussel populations are declining.
Lake Erie continues to exhibit changes, and strand-forming blue-green algae has become more prolific during the last few years. Blue-green algae has the potential to cause problems with Ciculating Water screen plugging and system fouling. Increased addition of oxidants has kept the algae in check thus far, but changes in lake conditions requires constant vigilance to prevent operational challenges.
Wastewater Treatment Plant (WWTP) Operation The WWTP operation is supervised by an Ohio licensed Wastewater Operator. Wastewater gen-erated by site personnel is treated in an onsite extended aeration package treatment facility de-signed to accommodate up to 38,000 gallons per day. In the treatment process, wastewater from the various collection points around the site enters the facility through a grinder, from where it is distributed to the surge tanks of one or both of the treatment plants.
The wastewater is then pumped into aeration tanks, where it is digested by microorganisms.
Oxygen is necessary for good sewage treatment, and is provided to the microbes by blowers and diffusers. The mixture of organics, microorganisms, and decomposed wastes is called activated sludge. The treated wastewater settles in a clarifier, and the clear liquid leaves the clarifier under a weir and exits the plant through an effluent trough. The activated sludge contains the organ-isms necessary for continued treatment, and is pumped back to the aeration tank to digest incom-ing wastewater. The effluent leaving the plant is drained to the wastewater basin (NPDES Out-fall 601) where further treatment takes place.
Summary of 2011 Wastewater Treatment Plant Operations National Pollutant Discharge Elemination System (NPDES) Reporting The Ohio Environmental Protection Agency (OEPA) has established limits on the amount of pol-lutants that Davis-Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 21B000 11.
Parameters such as chlorine, suspended solids and pH are monitored under the NPDES permit. Davis-Besse personnel prepare the NPDES Reports and submit them to the OEPA each month.
Davis-Besse has eight sampling points described in the NPDES permit. Seven of these locations are discharge points, or outfalls, and one is a temperature monitoring location. Descriptions of these sampling points follow:
Outfall 001 Collection Box: a point representative of discharge to Lake Erie Source of Wastes: Low volume wastes (Outfalls 601 and 602), Circulating Water system blow-down and Service Water 134
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Outfall 002 Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water runoff, Circulating Water pump house sumps Outfall 003 Screenwash Catch Basin: Outfall to Navarre Marsh Source of Wastes: Backwash water and debris from water intake screens Outfall 004 Cooling Tower Basin Ponds: Outfall to State Route 2 Ditch Source of Wastes: Circulating Water System drain (only during system outages)
Outfall 588 Sludge Monitoring Source of Wastes: Wastewater Plant sludge shipped for offsite processing Outfall 601 Wastewater Plant Tertiary Treatment Basin: Discharge from Wastewater Treatment Plant Sources of Wastes: Wastewater Treatment Plant Outfall 602 Low volume wastes: Discharge from settling basins Sources of wastes: Water treatment residues, Condensate Polishing Holdup Tank decants and Condensate Pit sumps Sampling Point 801 Intake Temperature: Intake water prior to cooling operation 2011 NPDES Summary There was one National Pollutant Discharge Elimination System (NPDES) violation on Oc-tober 4, 2011, when the Total Residual Oxidant limit was exceeded at Outfall 001 when a loss of power occurred to at the dechlorination system pump. The power was restored shortly after the problem was discovered. No other violations occurred in 2011.
135
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Chemical Waste Management The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes generated at the Davis-Besse Nuclear Power Station was developed to ensure wastes are man-aged and disposed of in accordance with all applicable state and federal regulations.
Resource Conservation and Recovery Act The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid haz-ardous waste. Solid waste is defined as a solid, liquid, semi-solid, or contained gaseous material.
The major goals of RCRA are to establish a hazardous waste regulatory program to protect hu-man health and the environment and to encourage the establishment of solid waste management, resource recovery, and resource conservation systems. The intent of the hazardous waste man-agement program is to control hazardous wastes from the time they are generated until they are properly disposed of, commonly referred to as "cradle to grave" management. Anyone who gen-erates, transports, stores, treats, or disposes of hazardous waste are subject to regulation under RCRA.
Under RCRA, there are essentially three categories of waste generators:
" Large quantity Generators - A facility which generates 1,000 kilograms/month!
(2,200 lbs./month) or more.
- Small quantity Generators - A facility which generates less than 1,000 kilograms/
month (2,200 lbs./month).
- Conditionally Exempt Small Quantity Generators - A facility which generates 100 kilo-grams/month (220 lbs./month).
In 2011, the Davis-Besse Nuclear Power Station generated approximately 38,815 pounds of haz-ardous waste.
Non-hazardous waste generated in 2011 included 12,700 gallons of used oil and other nonhaz-ardous wastes such as oil filters, latex paints and caulks.
RCRA mandates other requirements such as the use of proper storage and shipping containers, labels, manifests, reports, personnel training, a spill control plan and an accident contingency plan. These are part of the Chemical Management Program at Davis-Besse. The following are completed as part of the hazardous waste management program and RCRA regulations:
- Weekly Inspections of the Chemical Waste Accumulation Areas are designated through-out the site to ensure proper handling and disposal of chemical waste. These, along with the Chemical Waste Storage Area, are routinely patrolled by security personnel and in-spected weekly by Environmental and Chemistry personnel. All areas used for storage or accumulation of hazardous waste are posted with warning signs and drums are color-coded for easy identification of waste categories.
" Waste Inventory Forms are placed on waste accumulation drums or provided in the ac-cumulation area for employees to record the waste type and amount when chemicals are added to the drum. This ensures that incompatible wastes are not mixed and also identi-136
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report fies the drum contents for proper disposal.
Other Environmental Regulating Acts Comprehensive Environmental Response, Compensation and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, or Superfund) established a federal authority and source of funding for responding to spills and other releases of hazardous materials, pollutants and contaminants into the environment. Super-fund establishes "reportable quantities" for several hundred hazardous materials and regulates the cleanup of abandoned hazardous waste disposal sites.
Superfund Amendment and Reauthorization Act (SARA)
Superfund was amended in October 1986 to establish new reporting programs dealing with emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enhanced by ensuring that the potential for release of hazardous substances is minimized, and that adequate and timely responses are made to protect surrounding populations.
Davis-Besse conducts site-wide inspections to identify and record all hazardous products and chemicals onsite as required by SARA. Determinations are made as to which products and chemicals are present in reportable quantities.
Annual SARA reports are submitted to local fire departments and state and local planning com-missions by March 1 for the preceding calendar year.
Toxic Substances Control Act (TSCA)
The Toxic Substance Control Act (TSCA) was enacted to provide the USEPA with the authority to require testing of new chemical substances for potential health effects before they are intro-duced into the environment, and to regulate them where necessary. This law would have little impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management sys-tem, very similar to the hazardous waste management system established under RCRA.
In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers onsite.
PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with non-PCB liquid.
Retro-filling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with PCB-leaching solvents and allowing the solvent to circulate in the transformer during operation. The entire retro-fill process takes several years and will extract almost all of the PCB.
In all, Davis-Besse performed retro-fill activities on eleven PCB transformers between 1987 and 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors.
These capacitors are being replaced and disposed of during scheduled maintenance activities.
137
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Clean Air Act The Clean Air Act identifies substances that are considered air pollutants. Davis-Besse holds an OEPA permit to operate an Air Contaminant Source for the station Auxiliary Boiler. This boiler is used to heat the station and provide steam to plant systems when the reactor is not operating.
A report detailing the Auxiliary Boiler operation is submitted annually.
The Ohio EPA has granted an exemption from permitting our six emergency diesel engines, in-cluding the Station Blackout Diesel Generator, the 2 Emergency Diesel Generators, the Emer-gency Response Facility Diesel Generator, the Miscellaneous Diesel, and the Fire Pump Diesel.
These sources are operated infrequently to verify their reliability, and would only be used in the event of an emergency.
In response to recent "Clean Air Act Title VW legislation, an independent study identifying and quantifying all of the air pollution sources onsite was performed. Of particular significance is asbestos removal from renovation and demolition projects for which USEPA has outlined spe-cific regulations concerning handling, removal, environmental protection, and disposal. Also, the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concern for worker protection. Removal teams must meet medical surveillance, respirator fit tests, and training requirements prior to removing asbestos-containing material. Asbestos is not considered a hazardous waste by RCRA, but the EPA does require special handling and 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 Trans-portation Safety Act of 1976. These regulations are enforced by the United States Department of Transportation (DOT) and cover all aspects of transporting hazardous materials, including pack-ing, handling, labeling, marking, and placarding. Before any wastes are transported off site, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations, including verification that the vehicle has appropriate placards and it is in good oper-ating condition.
138
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Other Environmental 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. Additional standards require leak detection sys-tems and performance standards for new tanks. At Davis-Besse two 40,000 gallon and one 8,000 gallon diesel fuel storage tanks are registered USTs.
Spill Kits Spill control equipment is maintained throughout the Station at chemical storage areas and haz-ardous chemical and oil use areas. Equipment in the kits may include chemical-resistant cover-alls, gloves, boots, decontamination agents, absorbent cloth, goggles and warning signs.
Waste Minimization and Recycling Municipal Solid Waste (MSW) is normal trash produced by individuals at home and by indus-tries. In some communities, MSW is burned in specially designed incinerators to produce power or is separated into waste types (such as aluminum, glass, and paper) and recycled. The vast ma-jority of MSW is sent to landfills for disposal. As the population increases and older landfills reach their capacity, MSW disposal becomes an important economic, health, and resource issue.
The State of Ohio has addressed the issue with the State Solid Waste Management Plan, other-wise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing land-fills by reducing the amount of MSW produced, by reusing certain waste material, and by recy-cling other wastes. This is frequently referred to as "Reduce, Reuse, and Recycle."
Davis-Besse has implemented and participated in company wide programs that emphasize the reduction, reuse, recycle approach to MSW management. An active Investment Recovery Pro-gram has greatly contributed to the reduction of both hazardous and municipal waste generated by evaluating options for uses of surplus materials prior to the materials entering Davis-Besse's waste streams. Such programs include paper, cardboard, aluminum cans, used tires, and metals recycling or recovery. Paper and cardboard recycling is typically in excess of 50 tons annually.
This represents a large volume of recyclable resources, which would have otherwise been placed in a landfill. Aluminum soft drink cans are collected for the Boy Scouts of America to recycle.
Additionally, lead-acid batteries are recycled and tires are returned to the seller for proper dis-posal.
Although scrap metal is not usually considered part of the MSW stream, Davis-Besse collects and recycles scrap metals, which are sold at market price to a scrap dealer for resource recovery.
139
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report E nvironmental, Inc.
Midwest Laboratory S700 Landwhr Road Northbrook, IL 60062-2310 phone (847) 564-0700
- fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:
Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January through December, 2011 140
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples 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 a laboratory's analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report themrto the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Table A-2 lists results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.
Out-of-limit results are explained directly below the result.
141
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptan STW-1243 STW-1243 STW-1244 STW-1 244 STW-1244 STW-1244 STW-1244 STW-1245 STW-1245 STW-1246 STW-1247 STW-1247 STW-1247 STW-1248 STW-1256 STW-1256 STW-1257 STW-1257 STW-1257' STW-1257 STW-1257 STW-1258 STW-1258 STW-1259 STW-1260 STW-1260 STW-1260 STW-1261 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 04/04/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 10/07/11 Sr-89 Sr-90 68.2
+/-5.8 44.3
+/-2.4 69.8
+/-3.9 87.9
+/- 3.8 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 69.5 77.9 105.2
+/- 3.7
+/- 5.3
+/- 8.4 63.2 42.5 75.3 88.8 72.9 77.0 98.9 50.1 49.8 27.5 12.1 11.6 39.8 51.1
-71.2 31.3
-48.8 63.0
- 82.8 79.9
- 100.0 59.5
- 80.2 69.3
- 87.4 89.0
-118.0 26.1
-62.9 33.8
- 56.9 22.9
- 32.3 9.0
-14.0 7.6
-14.3 32.2
- 44.4 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium 41.5
+/-2.3 48.9
+/-1.8 26.6
+/-1.7 13.2
+/-0.6 11.2
+/-0.6 36.4
+/-0.6 10322
+/- 285 68.7
+/- 6.0 36.9
+/- 2.4 H-3 10200.0 8870
-11200 Pass Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 88.2 116.5 38.8 45.6 84.9 35.7 36.1 25.0 12.2 11.5 46.6 17435
+/- 7.8
+/- 7.1
+/-8.0
+/- 7.3
+/- 15.4
+/- 3.8
+/- 3.3
+/-1.1
+/- 0.6
+/- 1.7
+/-0.5
+/- 382 69.7 41.1 96.9 119.0 33.4 44.3 76.8 53.2 45.9 27.5 11.6 10.3 48.6 17400 81.8 107.0 26.3 39.4 68.9 27.8 30.9 22.9 8.7 6.7 39.4 15200
- 106.0
- 133.0
- 36.7
-51.7
- 92.5
- 66.6
-53.1
- 32.3
- 13.4
- 12.8
- 54.0
- 19100 56.9
- 77.9 30.2
- 47.2 Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d The sample was reanalyzed. Result of reanalysis was acceptable, 32.9 +/- 7.4 pCi/L.
142
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value t 2 sigma Limits Acceptance Environmental, Inc.
2010-2 12/1 2010-2 12/1 2010-2 12/1 2010-2 12/1 2010-2 12/1
'2010-2 12/1 2010-2 12/1 2010-2 12/1 2010-2 12/1 2010-2 12/1 2010-2 12/1 Environmental, Inc.
2011-1 7/E 2011-1 7/E 2011-1 7/W 2011-1 7/E 2011-1 7/E 2011-1 7/E 2011-1 7/W 2011-1 7/f 2011-1 7/E 2011-1 7/E 2011-1 7/E 2011-1 7/E 3/2010 3/2010 3/2010 3/2010 3/2010 3/2010 13/2010 13/2010 13/2010 13/2010 13/2010 100 cm.
110 cm.
120 cm.
150 cm.
180 cm.
40 cm.
50 cm.
60 cm.
60 cm.
80 cm.
90 cm.
4.94 4.09 3.43 2.2 1.53 30.89 19.77 13.73 13.73 7.72 6.1 4.65 3.50 2.68 1.75 1.32 38.56 23.35 14.53 15.84 8.33 5.93
+/- 0.57
+/- 0.74
+/- 0.36
+/- 0.42
+/- 0.52
+/- 2.11
+/- 1.82
+/- 1.24
+/- 1.53
+/- 0.74
+/- 0.73 3.46 2.86 2.40 1.54 1.07 21.62 13.84 9.61 9.61 5.40 4.27
- 6.42
- 5.32
-4.46
- 2.86
-1.99
-40.16
- 25.70
- 17.85
- 17.85
- 10.04
- 7.93 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 3/2011 3/2011 3/2011 3/2011 5/2011 3/2011 3/2011 3/2011 3/2011 3/2011 3/2011 3/2011 100 cm.
110 cm.
120 cm.
150 cm.
180 cm.
40 cm.
45 cm.
50 cm.
60 cm.
70 cm.
80 cm.
90 cm.
6.71 5.54 4.66 2.98 2.07 41.92 33.12 26.83 18.63 13.69 10.48 8.28 5.64 4.60 4.68 2.93 2.05 52.36 41.83 28.61 21.00 13.24 12.18 7.95
+/- 0.30
+/- 0.46
+/- 0.29
+/- 0.66
+/- 0.18
+/- 3.08
+/- 3.46
+/- 2.63
+/- 1.15
+/- 1.76
+/- 0.65
+/- 0.82 4.70 3.88 3.26 2.09 1.45 29.34 23.18 18.78 13.04 9.58 7.34 5.80
-8.72
- 7.20
- 6.06
- 3.87
- 2.69.
- 54.50
- 43.06
- 34.88
- 24.22
- 17.80
- 13.62
- 10.76 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 143
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-3.
Samples In-House "Spike" Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 C Activity Limits d Acceptance SPW-202 W-20111 W-20711 W-2071 1 XWW-331 XWW-331 XWW-331 XWW-331 SPAP-567 SPAP-569 SPAP-569 SPAP-571 SPW-581 SPW-581 SPW-581 SPW-581 SPMI-583 SPMI-583 SPW-602 SPW-686 SPF-1113 XWW-1602 XWW-1602 XWW-1602 XWW-1602 XWW-2537 XWW-2537 XWW72537 XWW-2537 SPW-2877 SPMI-3167 SPMI-3167 SPMI-3167 SPMI-3167 W-52411 W-60711 W-60711 SPAP-4167 SPAP-4167 SPW-4169 SPW-4169 1/17/2011 2/1/2011 2/7/2011 2/7/2011 2/11/2011 2/11/2011 2/11/2011 2/11/2011 2/14/2011 2/14/2011 2/14/2011 2/14/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/15/2011 2/17/2011 2/25/2011 3/17/2011 3/21/2011 3/21/2011 3/21/2011 3/21/2011 4/4/2011 4/4/2011 4/4/2011 4/4/2011 5/3/2011 5/24/2011 5/24/2011 5/24/2011 5/24/2011 5/24/2011 6/7/2011 6/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 U-238 Ra-226 Gr. Alpha Gr. Beta Ba-133 Cs-134 Cs-137 H-3 Gr. Beta Cs-134 Cs-137 H-3 Cs-134 Cs-137 Sr-89 Sr-90 Cs-137 Sr-90 U-238 Ni-63 Cs-137 Ba-133 Cs-1 34 Cs-137 H-3 Ba-133 Cs-134 Cs-1 37 H-3 Ra-228 Cs-134 Cs-137 Sr-89 Sr-90 Ra-226 Gr. Alpha Gr. Beta Cs-134 Cs-1 37 Cs-134 Cs-137 4.19 16.32 23.02 46.59 144.30 22.20 64.70 13399 46.90 7.70 102.47 75815 39.91 56.28 112.92 47.80 57.04 36.27 3.98 167.41 2369 26.83 18.90 33.98 7348 43.40 13.50 68.30 7134 25.23 33.04 51.53 90.89 41.17 17.90 23.00 43.27 6.92 108.02 34.52 58.29
+/- 0.19
+/- 0.47
+/- 0.45
+/- 0.41
+/- 8.50
+/-3.70
+/- 7.40
+/- 334
+0.11
+ 1.70
+ 3.20
+ 542
+ 1.38
+/- 2.28
+/- 5.61
+ 2.02
+ 2.76
+/- 1.47
+0.19
+/- 3.05
+ 22
+/-6.35
+/- 4.06
+/- 5.88
+ 248
+/- 4.26
+/- 2.40
+/- 5.90
+/- 257
+/- 2.48
+/- 8.25
+/- 8.63
+/- 4.30
+/- 1.53
+/- 0.42
+/- 0.49
+/- 0.42
+/- 1.45
+/- 2.84
+/- 4.79
+/- 6.19 4.17 16.77 20.00 45.20 144.40 21.50 61.00 12538 48.10 7.49 106.79 73230 37.45 53.39 121.42 42.07 53.39 42.07 4.17 208.11 2170 28.58 16.30 30.50 7617 42.70 11.90 60.70 7234 31.62 34.19 53.06 93.47 41.80 16.80 20.00 45.20 6.57 105.80 32.84 52.92 0.00 11.74 10.00 35.20 129.96 11.50 51.00 10030 28.86 0.00 96.11 58584 27.45 43.39 97.14 33.66 43.39 33.66 0.00 145.68 1953 18.58 6.30 20.50 6094 32.70 1.90 50.70 5787 22.13 24.19 43.06 74.78 33.44 11.76 10.00 35.20 0.00 95.22 22.84 42.92
-16.17
-21.80
- 30.00
- 55.20
- 158.84
-31.50
-71.00
- 15046
- 67.34
- 17.49
-117.47
- 87876
- 47.45
- 63.39
- 145.70
- 50.48
- 63.39
- 50.48
-16.17
- 270.54
- 2387
- 38.58
- 26.30
- 40.50
-9140
- 52.70
-21.90
- 70.70
- 8681
-41.11
-44.19
-63.06
-112.16
- 50.16
-21.84
- 30.00
- 55.20
- 16.57
-116.38
- 42.84
- 62.92 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 144
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-4169 7/7/2011 Sr-89 66.12
+/-4.18 69.64 55.71
-83.57 Pass SPW-4169 7/7/2011 Sr-90 41.72
+/- 1.79 41.68 33.34
-50.02 Pass SPW-4171 7/7/2011 H-3 70582
+/- 767 71646 57317
-85975 Pass SPW-4180 7/7/2011 Tc-99 95.69
+/- 1.65 97.02 67.91
- 126.13 Pass SPW-41821 7/7/2011 Ra-228 32.57
+/- 2.63 30.63 21.44
-39.82 Pass SPW-4241 7/7/2011 Ni-63 403.01
+/- 4.66 415.20 290.64
- 539.76 Pass SPW-4180 7/8/2011 Tc-99 100.30
+/- 1.75 97.02 67.91
- 126.13 Pass SPW-5029 7/29/2011 C-14 3991
+/- 17 4739 2843
- 6634 Pass SPW-5031 7/29/2011 Fe-55 13801
+/- 331 14895 11916
-17874 Pass W-91411 9/14/2011 Gr. Alpha 21.58
+/- 0.44 20.00 10.00
-30.00 Pass W-91411 9/14/2011 Gr. Beta 43.02
+/- 0.40 45.20 35.20
-55.20 Pass SPW-91511 9/15/2011 Tc-99 29.92
+/- 1.07 32.34 20.34
-44.34 Pass W-91911 9/19/2011 Ra-226 17.06
+/- 0.42 16.80 11.76
-21.84 Pass W-100711 10/7/2011 Gr. Alpha 22.05
+/- 0.45 20.00 10.00
- 30.00 Pass W-100711 10/7/2011 Gr. Beta 45.51
+/- 0.41 45.20 35.20
-55.20 Pass W:101111 10/11/2011 Ra-226 16.02
+/- 0.40 16.80 11.76
-21.84 Pass XWW-7220 11/17/2011 Ba-133 25.11
+/- 4.36 27.47 17.47
-37.47 Pass XWW-7220 11/17/2011 Cs-134 14.09
+/- 3.11 16.60 6.60
-26.60 Pass XWW-7220 11/17/2011 Cs-137 35.59
+/- 4.28 29.98 19.98
-39.98 Pass W-113011 11/30/2011 Ra-226 16.12
+/- 0.39 16.80 11.76
-21.84 Pass W-120111 12/1/2011 Gr. Alpha 21.34
+/- 0.43 20.00 10.00
-30.00 Pass W-120111 12/1/2011 Gr. Beta 45.55
+/- 0.41 45.20 35.20
-55.20 Pass SPW-41823 12/9/2011 Ra-228 26.98
+/- 2.38 29.40 20.58
- 3822 Pass SPMI-8906 12/22/2011 Cs-134 29.11
+/-3.52 28.14 18.14
-38.14 Pass SPMI-8906 12/22/2011 Cs-137 58.27
+/- 7.62 52.36 42.36
-62.36 Pass SPW-8916 12/22/2011 Cs-134 31.74
+/- 3.63 28.14 18.14
-38.14 Pass SPW-8916 12/22/2011 Cs-137 56.48
+/- 6.12 52.36 42.36
-62.36 Pass SPAP-8902 12/23/2011 Gr. Beta 45.72
+/- 0.11 47.11 28.27
- 65.95 Pass SPAP-8904 12/23/2011 Cs-134 5.19
+/- 0.63 5.63 0.00
-15.63 Pass SPAP-8904 12/23/2011 Cs-137 101.21
+/- 2.55 104.71 94.24
-115.18 Pass SPW-8918 12/23/2011 H-3 136759
+/- 1056 137638 110110
-165166 Pass SPW-8922 12/23/2011 Ni-63 202.21
+/- 3.75 206.88 144.82
-268.94 Pass SPW-8924 12/23/2011 Tc-99 126.10
+/- 1.86 129.36 90.55
-168.17 Pass SPF-8926 12/23/2011 Cs-1 34 0.34
+/- 0.01.
0.33 0.20
- 0.47 Pass SPF-8926 12/23/2011 Cs-137 2.34
+/- 0.02 2.09 1.25
-2.93 Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m), and solid samples (pCi/g).
Laboratory codes as follows: W (water), MI (milk), AP (air filter), SO (soil), VE (vegetation),
CH (charcoal canister), F (fish), U (urine).
c Results are based on single determinations.
d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2a.
NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.
145
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Analysis Lab Code Sample Date b
Laboratory results (4.66a)
Acceptance Criteria Type LLD Activityc (4.66 a)
SPW-202 W-20111 W-20711 W-20711 SPAP-566 SPAP-568 SPAP-568 SPAP-570 SPW-580 SPW-580 SPW-580 SPW-580 SPMI-582 SPMI-582 SPMI-582 SPMI-582 SPMI-582 SPW-601 SPW-685 SPF-1112 SPF-1112 BKW-40111 BKW-40111 BKW-40111 BKW-401 11 SPW-2887 W-52411 W-60711 W-60711 SPAP-4164 SPW-4168 SPW-4168 SPW-4168 SPW-4168 SPW-4171 SPW-41811 Water Water Water Water Air Filter Air Filter Air Filter Air Filter Water Water Water Water Milk Milk Milk Milk Milk Water Water Fish Fish 1/17/2011 U-238 2/1/2011 Ra-226 Gr.
2/7/2011 Alpha 2/7/2011 Gr. Beta 2/14/2011 Gr. Beta 2/14/2011 Cs-134 2/14/2011 Cs-137 2/14/2011 H-3 2/15/2011 Cs-134 2/15/2011 Cs-137 2/15/2011 Sr-89 2/15/2011 Sr-90 2/15/2011 Cs-134 2/15/2011 Cs-137 2/15/2011 1-131 (G) 2/15/2011 Sr-89 2/15/2011 Sr-90 2/17/2011 U-238 2/25/2011 Ni-63 3/17/2011 Cs-134 3/17/2011 Cs-137 0.10 0.04 0.44 0.75 0.64 2.34 1.56 103.20 2.68 2.84 0.73 0.57 3.49 3.54 4.14 0.71 0.55 0.20 1.61 6.74 5.45 4.16 3.11 4.73 5.04 0.72 0.04 0.51 1.58 0.72 3.41 2.45 0.72 0.51 152.00 0.77 0.12
+/- 0.12 0.05
+/- 0.03 1
1
-0.02
-0.03 2.24
+/- 0.29
+/- 0.53
+/- 0.61
-49.40
+/- 52.50 0.24
+/- 0.57 0.02
+/- 0.27 1
3.2 3.2 100 100 200 10 10 5
1 10 10 20 5
1 1
20 100 100 0.16 0.59 0.09 0.05
+/- 0.67
+/- 0.32
+/- 0.17
+/- 0.98 Water 4/1/2011 1-131 Water 4/1/2011 Co-60 Water 4/1/2011 Cs-134 Water 4/11/2011 Cs-137 Water 5/3/2011 Ra-228 Water 5/24/2011 Ra-226 Gr.
Water 6/7/2011 Alpha Water 6/7/2011 Gr. Beta 10 1.0 10 10 2
1 0.46
+/- 0.39 0.05
+/- 0.03 0.00
+/- 0.36 0.38
+/- 1.12 1.04
+/- 0.48 Air Filter Water Water Water Water Water Water 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 7/7/2011 Gr. Beta Cs-134 Cs-137 Sr-89 Sr-90 H-3 Ra-228 1
3.2 3.2 10 10 5
1 200 2
0.40
-0.19 37.10 0.51
+/- 0.50
+/- 0.21
+/- 81.80
+/- 0.42 146
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Samrple Date Analysisb Laboratory results (4.66a)
Acceptance Criteria (4.66 Type LLD Activityc a)
SPW-4241 Water 7/7/2011 Ni-63 1.70 0.09
+/- 1.03 20 SPW-4179 Water 7/8/2011 Tc-99 1.20
-0.96
+/- 0.71 10 SPW-5028 Water 7/29/2011 C-14 109.80 61.90
+/- 59.20 200 SPW-5031 Water 7/29/2011 Fe-55 140.60 0.00
+/- 85.30 1000 W-91411 Water 9/14/2011 Gr. Alpha 0.48
-0.06
+/- 0.33 1
W-9141 1 Water 9/14/2011 Gr. Beta 0.78
-0.43
+/- 0.53 3.2 SPW-91511 Water 9/15/2011 Tc-99 1.11
-0.62
+/- 0.66 10 W-91911 Water 9/19/2011 Ra-226 0.03 0.04
+/- 0.02 1
W-100711 Water 10/7/2011 Gr. Alpha 0.44
-0.26
+/- 0.28 1
W-100711 Water 10/7/2011 Gr. Beta 0.76
-0.43
+/- 0.52 3.2 W-101111 Water 10/11/2011 Ra-226 0.04 0.05
+/- 0.03 1
W-113011 Water 11/30/2011 Ra-226 0.03 0.04
+/- 0.02 1
W-120111 Water 12/1/2011 Gr. Alpha 0.41
-0.20
+/- 0.27 1
W-120111 Water 12/1/2011 Gr. Beta 0.75
-0.10
+/- 0.53 3.2 SPW-41813 Water 12/9/2011 Ra-228 0.71 0.17
+/- 0.35 2
SPMI-8905 Milk 12/22/2011 Cs-134 3.27 10 SPMI-8905 Milk 12/22/2011 Cs-137 3.38 10 SPMI-8905 Milk 12/22/2011 1-131(G) 2.17 20 SPW-8915 Water 12/22/2011 Cs-134 3.37 10 SPW-8915 Water 12/22/2011 Cs-137 3.45 10 SPW-8915 Water 12/22/2011 1-131 (G) 3.38 20 SPAP-8901 Air Filter 12/23/2011 Gr. Beta 0.78 0.50
+/- 0.46 3.2 SPAP-8903 Air Filter 12/23/2011 Cs-134 1.65 100 SPAP-8903 Air Filter 12/23/2011 Cs-137 2.41 100 SPW-8917 Water 12/23/2011 H-3 150.20
-3.04
+/- 78.80 200 SPW-8921 Water 12/23/2011 Ni-63 16.92
-4.60
+/- 10.16 20 SPW-8923 Water 12/23/2011 Tc-99 5.66
-5.45
+/- 3.34 10 SPF-8925 Fish 12/23/2011 Cs-134 7.15 100 SPF-8925 Fish 12/23/2011 Cs-137 9.73 100 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b 1-131(G); iodine-131 as analyzed by gamma spectroscopy.
c Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.
147
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLEA-5. In-House "Duplicate" Samples Concentration (pC j/L)a Averaged Result Lab Code CF-20, 21 CF-20, 21 CF-20, 21 WW-65, 66 BS-165, 166 BS-165, 166 BS-165, 166 BS-176, 177 BS-176, 177 BS-197, 198 BS-197, 198 BS-1 97, 198
,WW-358, 359 DW-20009, 20010 DW-20009, 20010 WW-337, 338 W-491, 492 W-491, 492 DW-20014, 20015 SWU-447, 448 W-694,695 DW-20022, 20023 SW-626, 627 LW-825, 826 SWT-845, 846 MI-998, 999 W-1024, 1025 WW-1156, 1157 P-1198, 1199 SW-1434, 1435 WW-1588, 1589 SG-1714, 1715 SG-1714, 1715 AP-1862, 1863 W-2143, 2.144 AP-2269, 2270 DW-20061, 20062 SWU-1455, 1456 SWU-1522, 1523 PM-1543, 1544 PM-1543, 1544 Date 1/3/2011 1/3/2011 1/3/2011 1/6/2011 1/11/2011 1/11/2011 1/11/2011 1/11/2011 1/11/2011 1/11/2011 1/11/2011 1/11/2011 1/17/2011 1/19/2011 1/19/2011 1/25/2011 1/27/2011 1/27/2011 1/28/2011 1/31/2011 Analysis Be-7 K-40 Sr-90 H-3 Cs-137 H-3 K-40 H-3 K-40 Cs-137 H-3 K-40 H-3 Ra-226 Ra-228 H-3 Ra-226 Ra-228 Gr. Alpha Gr. Beta First Result Second Result Acceptance 2/7/2011 H-3 2/9/2011 Ra-228 2/16/2011 H-3.
2/24/2011 Gr. Beta 3/1/2011 Gr. Beta 3/7/2011 K-40 3/712011 H-3 3/16/2011 Gr. Beta 0.24
+/-0.14 0.34
+/-0.17 10.37
+/-0.43 9.76
+/-0.68 0.01
+/- 0.01 0.01
+/- 0.01 321.91
+/-97.19 345.76
+/-98.16 0.13
+/-0.02 0.15
+/-0.02 286.00
+/- 80.00 284.00
+/- 80.00 14.11
+/-0.52 13.79
+/-0.60 391.00
+/- 92.00 332.00
+/- 89.00 9.06
+/- 0.44 8.28
+/- 0.81 0.14
+/- 0.03 0.15
+/- 0.04 459.00
+/- 103.00 283.00
+/- 95.00 14.40
+/-0.77 14.16
+/- 1.23 331.44
+/- 93.05 407.65
+/- 95.91 3.66
+/- 0.57 2.74
+/- 0.43 1.51
+/-0.64 1.36
+/-0.60 21986
+/-402 21896
+/-401 6.70
+/-0.50 6.10
+/-0.50 6.60
+/- 1.30 8.40
+/- 1.40 1.91
+/- 0.71 2.34
+/- 0.80 7.42
+/-1.17 6.85
+/-1.11
+/-
628.26
+/- 104.30 692.37 106.89 0.71
+/-0.47 1.13
+/-0.54 1268.1
+/-
7
+/- 129.52 1144.65 125.39 2.65
+/- 0.82 2.45
+/- 0.74 1.11
+/-0.39 0.80
+/-0.37 1760.1
+/-
0
+/- 127.50 1708.50 131.60
+/-
489.83
+/- 101.09 581.39 105.06 1.79
+/-0.78 0.47
+/-0.66
+/-
504.00
+/- 133.00 597.00 136.00 15523
+/-359 15968
+/-364 1.81
+/- 1.23 2.81
+/- 1.38 8.82
+/- 0.81 8.58
+/- 0.74 13.78
+/-0.65 12.76
+/-0.58 0.09
+/- 0.02 0.08
+/- 0.02 536.40
+/- 99.37 466.79
+/- 96.46 0.07
+/- 0.01 0.08
+/- 0.01 2.82
+/- 1.33 3.89
+/- 1.26 2.50
+/- 0.75 2.75
+/- 0.83 1.36
+/-0.87 2.14
+/-0.96 13.81
+/-0.26 13.67
+/- 0.27 8.12
+/- 3.20 7.71
+/- 3.25 0.29 10.07 0.01 333.83 0.14 285.00 13.95 361.50 8.67 0.15
- 371.00 14.28 369.55 3.20 1.44 21941 6.40 7.50 2.13 7.14
+/- 0.11
+/- 0.40
+/- 0.00
+/- 69.06
+/- 0.01
+/- 56.57
+/- 0.40
+/- 64.00
+/- 0.46
+/- 0.03
+/- 70.06
+/- 0.73
+/- 66.81
+/-0.36
+/- 0.44
+/- 284
+/- 0.35
+/- 0.96
+/- 0.53
+/- 0.81 660.32
+/- 74.67 0.92
+/- 0.36 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 1206.41 2.55 0.96
+/- 90.14
+/- 0.55
+/- 0.27 1734.30
+/- 91.62 535.61
+/- 72.90 1.13
+/- 0.51 3/17/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/28/2011 3/29/2011 3/29/2011 3/29/2011 3/29/2011 H-3 H-3 Gr. Beta Gr. Alpha Gr. Beta Be-7 H-3 Be-7 Gr. Alpha Gr. Beta Gr. Beta Gr. Beta Sr-90 550.50 15746 2.31 8.70 13.27 0.08 501.59 0.07 3.36 2.62 1.75 13.74 7.91
+/- 95.11
+/- 256
+/- 0.92
+/- 0.55
+/- 0.44
+/- 0.01
+/- 69.25
+/- 0.01
+/- 0.92
+/- 0.56
+/- 0.65
+/- 0.19
+/- 2.28 148
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Lab Code Date Analysis Firsi Result Averaged Result Second Result Acceptance SWT-5885, 5886 AP-1883,1884 AP-2248, 2249 DW-20066, 20067 DW-20066, 20067 P-1 567, 1568 M1-1609, 1610 MI-1609, 1610 MI-1609, 1610 S-1651, 1652 S-1651, 1652 AP-1841, 1842 AP-1841, 1842 AP-1 841, 1842 S-1990, 1991 S-1990, 1991 WW-2552,2553 PM-1904, 1905 PM-1904,1905 P-2011, 2012 WW-2053, 2054 BS-2095, 2096 DW-20099, 20100 DW-20099, 20100 WW-2416,2417 P-2185, 2186 WW-2353,2354 DW-20115, 20116 DW-20115, 20116 SO-2960, 2961 MI-2657, 2658 DW-20130, 20131 DW-20130, 20131 DW-20148, 20149 DW-20148, 20149 PM-2810,2811 PM-2810, 2811 PM-2810,2811 WW-3065, 3066 WW-3086, 3087 3/29/2011 3/30/2011 3/30/2011 3/30/2011 3/30/2011 Gr. Beta Be-7 Be-7 Ra-226 Ra-228 4/1/2011 H-3 4/4/2011 1-131 4/4/2011 4/4/2011 4/4/2011 4/4/2011 4/7/2011 4/7/2011 4/7/2011 4/7/2011 4/7/2011 4/7/2011 4/11/2011 4/11/2011 4/11/2011 4/13/2011 4/13/2011 4/13/2011 4/13/2011 4/19/2011 4/20/2011 4/20/2011 4/26/2011 4/26/2011 4/27/2011 5/2/2011 5/2/2011 5/2/2011 5/3/2011 5/3/2011 5/4/2011 5/4/2011 5/4/2011 5/16/2011 5/16/2011 K-40 Sr-90 Ac-228 Pb-214 Be-7 Cs-137 1-131(G)
Ac-228 Pb-2114 H-3 K-40 Sr-90 H-3 H-3 K-40 U-233/4 U-238 H-3 H-3 H-3 U-233/4 U-238 K-40 K-40 U-233/4 U-238 U-233/4 U-238 Cs-134 Cs-137 K-40 H-3 H-3 1
1.21
+/- 0.54 0.07
+/- 0.01 0.06
+/- 0.01 2.14
+/- 0.16 2.55
+/- 0.65
+
289.00 103.00 0.85
+ 0.17
+/-
1323.80 112.00 0.85
+/- 0.33 0.88
+/- 0.08 1.09
+/- 0.12 0.12
+/- 0.02 0.00
+/- 0.00 0.02
+/- 0.00 15.83
+/- 0.39 11.21
+/-0.23
+/-
761.09 116.48 13585
+/-611 9.94
+/- 3.05
+/-
670.00 108.00 220.20
+/- 86.50 12.88
+/- 0.72 1.64
+/- 0.40 1.49
+/- 0.39 217.10
+/- 97.00 405.00
+/- 93.00
+/-
525.54 119.74 11.94
+/-2.34 2.70
+/- 1.15 22.63
+/- 1.36
+/-
1319.30 101.30 7.59
+/- 0.90 4.67
+/- 0.72 6.64
+/- 0.83 6.11
+/-0.83 18.64
+/- 12.16 28.99
+/- 14.92 14368
+/- 720 280.51
+/- 86.98 341.14
+/-85.94 1323.20 0.97 1.03 0.84 0.12 0.00 0.03 16.12 11.81 759.04 14278 5.62 619.00 246.80 13.56 1.31 1.28 184.90 504.00 399.41 10.71 3.89 22.90 1403.20 7.62 4.84 6.35 5.18 33.33 21.17 14309 179.46 377.97 0.77
+/- 0.54 0.09
+/- 0.02 0.06
+/- 0.01 2.10
+/- 0.16 1.78
+/- 0.62
+/-
296.00 103.00 0.91
+/- 0.18
+/- 96.22
+/- 0.34
+/- 0.22
+/- 0.16
+/- 0.01
+/- 0.00
+/- 0.00
+/- 0.64
+/- 1.22
+/-
116.41
+/- 648
+/- 2.52
+/-
106.00
+/- 87.80
+/- 1.08
+/- 0.34
+/- 0.33
+/- 95.60
+/- 98.00
+/-
115.99
+/- 1.19
+/- 0.72
+/- 0.03
+/-
131.60
+/- 0.83
+/- 0.66
+/- 0.81
+/- 0.73
+/- 11.86
+/- 12.16
+/- 638
+/- 82.83
+/- 87.43 292.50
+/- 72.83 0.88
+/- 0.13 1323.50
+/- 73.83 0.91
+/- 0.24 0.96
+/- 0.12 0.97
+/- 0.10 0.12
+/- 0.01 0.00
+/- 0.00 0.03
+/- 0.00 15.98
+/-0.37 11.51
+/-0.62 0.99 0.08 0.06 2.12 2.17
+/- 0.38
+/- 0.01
+/- 0.01
+/- 0.11
+/- 0.45 760.07 13932 7.78 644.50 233.50 13.22 1.48 1.39 201.00 454.50 462.48 11.33 3.30 22.77 1361.25 7.61 4.76 6.50 5.65 25.99 25.08 14339 229.98 359.56
+/- 82.34
+/- 445
+/- 1.98
+/- 75.66
+/- 61.63
+/- 0.65
+/- 0.26
+/- 0.26
+/- 68.10
+/- 67.55
+/- 83.35
+/- 1.31
+/- 0.68
+/- 0.68
+/- 83.04
+/- 0.61
+/- 0.49
+/- 0.58
+/- 0.55
+/- 8.49
+/- 9.62
+/- 481
+/- 60.05
+/- 61.30 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 149
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration (pG /L)a Averaged Result Lab Code Date Analysis First Result Second Result Acceptance SG-3134, 3135 SG-3134, 3135 F-3221, 3222 SS-3434, 3435 AP-3329, 3330 WW-3350, 3351 G-3413,3414 G-3413,3414 G-3413,3414 AP-3602, 3603 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 SO-3797, 3798 MI-3935, 3936 BS-4172, 4173 BS-4172, 4173 DW-20183, 20184 DW-20183, 20184 WW-401914020 PM-4193, 4194 LW-4235,4236 AP-4367, 4368 MI-4416,4417 W-4914,4915 MI-4438, 4439 VE-4481, 4482 AP-4677, 4678 W-5537,5538 P-4764, 4765 WW-5211, 5212 5/16/2011 5/16/2011 5/23/2011 5/25/2011 5/26/2011 6/1/2011 6/1/2011 6/1/2011 6/1/2011 6/3/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 6/8/2011 Ac-228 Pb-214 K-40 K-40 Be-7 H-3 Be-7 Gr. Beta K-40 Be-7 Ac-228 Bi-212 Bi-214 Cs-137 K-40 Pb-212 Pb-214 Th-232 U-233/4 U-238 11.19 9.12 2.73 11533.0 0
0.24 235.37 0.28 11.04 6.80 0.20 0.99 1.10 0.87 0.41 16.08 0.98 0.95 0.47 0.16 0.16
+/- 0.82
+/- 0.17
+/- 0.39
+/-
563.70
+/- 0.11
+/- 83.98
+/- 0.10
+/- 0.31
+/- 0.33
+/- 0.08
+/- 0.05
+/- 0.12
+/- 0.02
+/- 0.01
+/- 0.26
+/- 0.10
+/- 0.02
+/-0.05
+/- 0.02
+/- 0.02
+/-
119.40
+/- 23.78
+/-
679.60
+/- 1.00
+/- 0.80
+/- 1.20
+/-
759.00
+/- 0.72
+/- 0.10 12.50
+/- 0.84 9.37
+/- 0.42 2.81
+/- 0.42 11236.0
+/-
0 566.10 0.23
+/- 0.13 173.12
+/-81.05 0.25
+/- 0.09 10.85
+/- 0.31 6.71
+/- 0.38 0.25
+/- 0.10 1.00
+/- 0.06 1.08
+/- 0.17 0.86
+/- 0.02 0.39
+/- 0.01 16.27
+/- 0.29 0.93
+/- 0.02 0.91
+/- 0.02 0.49
+/- 0.04 0.15
+/- 0.02 0.13
+/- 0.02
+/-
1843.10 136.50 48.57
+/- 17.06 11120.0
+/-
0 512.30 8.40
+/- 0.90 6.10
+/- 0.80 3.16
+/- 1.21 14660.0
+/-
0 750.00 2.11
+/-0.78 0.19
+/-0.11
+/-
1447.00 114.80
+/-
584.67 110.67
+/-
1381.20 112.70
+/-
4767.90 349.70 0.23
+/- 0.09
+/-
695.39 106.94 138.72
+/- 82.79 136.22
+/- 82.76 11.85 9.25 2.77 11384.5 0
0.24 204.25 0.27 10.95 6.76 0.22 1.00 1.09 0.87 0.40 16.18 0.96 0.93 0.48 0.16 0.15 1803.85 50.04 11425.0 0
9.20 6.40 3.36 14727.5 0
2.41 0.18
+/- 0.59
+/- 0.23
+/- 0.29
+/- 399.45
+/- 0.08
+/- 58.36
+/- 0.07
+/- 0.22
+/- 0.25
+/- 0.07
+/- 0.04
+/- 0.10
+/- 0.01
+/- 0.01
+/- 0.19
+/- 0.05
+/- 0.01
+/- 0.03
+/- 0.01
+/- 0.01
+/- 90.68
+/- 14.63
+/- 425.53
+/- 0.67
+/- 0.57
+/- 0.85
+/- 533.52
+/- 0.53
+/- 0.07 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 6/20/2011 K-40 1764.60 6/21/2011 Cs-137 51.50 11730.0 6/21/2011 K-40 0
6/21/2011 U-233/4 10.00 6/21/2011 U-238 6.70 6/24/2011 Gr. Beta 3.56 14795.0 6/30/2011 K-40 0
6/30/2011 Gr. Beta 2.70 7/7/2011 Be-7 0.17 7/11/2011 K-40 7/11/2011 H-3 7/12/2011 K-40 7/13/2011 K-40 7/15/2011 Be-7 1342.40
+/- 91.49
+/-
576.36 110.35
+/-
1280.60 107.50
+/-
4452.60 332.40 0.18
+/- 0.08
+/-
650.13 105.19 179.82
+/- 84.81 191.94
+/- 85.50 1394.70
+/- 73.40 580.52
+/- 78.14 1330.90
+/- 77.87 4610.25
+/- 241.24 0.20
+/- 0.06 7/18/2011 7/19/2011 7/24/2011 H-3 H-3 H-3 672.76 159.27 164.08
+/- 75.00
+/- 59.26
+/- 59.50 150
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4998, 4999 7/25/2011 Be-7 543.90
+/- 158.20 488.30
+/- 163.80 516.10
+/- 113.86 Pass VE-4998, 4999 7/25/2011 K-40 2562.20
+/- 319.80 2414.00
+/- 350.00 2488.10
+/- 237.05 Pass DW-20258, 20259 7/25/2011 U-233/4 21.34
+/- 1.52 24.93
+/- 2.93 23.14
+/- 1.65 Pass DW-20258, 20259 7/25/2011 U-235 0.57
+/- 0.26 0.69
+/- 0.26 0.63
+/- 0.18 Pass DW-20258, 20259 7/25/2011 U-238 14.11
+/- 1.24 15.81
+/- 1.23 14.96
+/- 0.87 Pass DW-20269, 20270 7/25/2011 U-233/4 4.93
+/- 0.73 4.65
+/- 0.68 4.79
+/- 0.50 Pass DW-20269, 20270 7/25/2011 U-238 3.26
+/- 0.60 2.53
+/- 0.50 2.90
+/- 0.39 Pass DW-20280, 20281 7/25/2011 U-233/4 3.58
+/- 0.58 3.33
+/- 0.56 3.46
+/- 0.40 Pass DW-20280, 20281 7/25/2011 U-238 1.64
+/- 0.40 2.11
+/- 0.45 1.88
+/- 0.30 Pass MI-5019, 5020 7/26/2011 K-40 1348.50
+/- 101.00 1347.40
+/- 109.70 1347.95
+/- 74.56 Pass W-5447, 5448 7/26/2011 H-3 246.31
+/- 99.19 241.99
+/- 99.02 244.15
+/- 70.08 Pass G-5124, 5125 7/28/2011 Gr. Beta 7.48
+/- 0.20 7.17
+/- 0.19 7.33
+/- 0.14 Pass AP-5232, 5233 7/28/2011 Be-7 0.15
+/- 0.08 0.22
+/- 0.13 0.19
+/- 0.08 Pass SL-5169, 5170 8/1/2011 Be-7 2.37
+/- 0.16 2.17
+/- 0.17 2.27
+/- 0.12 Pass SL-5169, 5170 8/1/2011 Gr. Beta 4.74
+/- 0.45 3.94
+/- 0.39 4.34
+/- 0.30 Pass SL-5169, 5170 8/1/2011 K-40 3.12
+/- 0.16 2.96
+/- 0.21 3.04
+/- 0.13 Pass G-5190, 5191 8/1/2011 Be-7 3.14
+/- 0.30 3.44
+/- 0.27 3.29
+/- 0.20 Pass G-5190, 5191 8/1/2011 Gr. Beta 8.07
+/- 0.28 7.86
+/- 0.27 7.97
+/- 0.19 Pass G-5190, 5191 8/1/2011 K-40 5.51
+/- 0.46 5.57
+/- 0.44 5.54
+/- 0.32 Pass DW-20291, 20292 8/2/2011 U-233/4 3.24
+/- 0.54 2.60
+/- 0.50 2.92
+/- 0.37 Pass DW-20291, 20292 8/2/2011 U-238 1.59
+/- 0.38 2.00
+/- 0.43 1.80
+/- 0.29 Pass SG-5342, 5343 8/5/2011 Ac-228 14.41
+/- 0.36 14.13
+/-0.48 14.27
+/- 0.30 Pass SG-5342, 5343 8/5/2011 Bi-212 4.14
+/- 0.65 4.73
+/- 1.21 4.44
+/- 0.69 Pass SG-5342, 5343 8/5/2011 K-40 7.67
+/- 0.92 7.95
+/- 1.21 7.81
+/- 0.76 Pass SG-5342, 5343 8/5/2011 Pb-214 10.72
+/- 0.21 10.67
+/- 0.28 10.70
+/- 0.18 Pass SG-5342, 5343 8/5/2011 TI-208 0.96
+/- 0.06 1.00
+/- 0.06 0:98
+/- 0.04 Pass MI-5405, 5406 8/8/2011 K-40 1545.30
+/- 116.00 1388.00
+/- 98.20 1466.65
+/- 75.99 Pass DW-20301, 20302 8/9/2011 Gr. Alpha 6.36
+/- 1.09 5.30
+/- 1.08 5.83
+/- 0.77 Pass DW-20301, 20302 8/9/2011 Gr. Beta 14.36
+/- 0.92 13.51
+/- 0.89 13.94
+/- 0.64 Pass DW-5603, 5604 8/16/2011 Ra-228 1.68
+/- 0.88 2.26
+/- 0.91 1.97
+/- 0.63 Pass VE-5753, 5754 8/22/2011 Be-7 0.78
+/- 0.20 0.75
+/- 0.23 0.77
+/- 0.15 Pass VE-5753, 5754 8/22/2011 K-40 6.16
+/- 0.51 6.63
+/- 0.57 6.40
+/- 0.38 Pass S-5801, 5802 8/29/2011 Ac-228 0.43
+/- 0.09 0.38
+/- 0.07 0.41
+/- 0.06 Pass S-5801, 5802 8/29/20.11 K-40 6.54
+/- 0.51 5.96
+/- 0.49 6.25
+/- 0.35 Pass S-5801, 5802 8/29/2011 Pb-212 0.31
+/- 0.03 0.36
+/- 0.03 0.34
+/- 0.02 Pass S-5801, 5802 8/29/2011 Pb-214 0.28
+/- 0.04 0.25
+/- 0.04 0.27
+/- 0.03 Pass S-5801, 5802 8/29/2011 TI-208 0.14
+/- 0.02 0.12
+/- 0.02 0.13
+/- 0.01 Pass S-5801, 5802 8/29/2011 U-235 0.05
+/- 0.02 0.04
+/- 0.01 0.05
+/- 0.01 Pass ME-5996, 5997 9/1/2011 Gr. Alpha 0.03
+/- 0.02 0.03
+/- 0.02 0.03
+/- 0.01 Pass ME-5996, 5997 9/1/2011 Gr. Beta 2.55
+/- 0.07 2.62
+/- 0.07 2.58
+/- 0.05 Pass ME-5996, 5997 9/1/2011 K-40 2.66
+/- 0.35 2.24
+/- 0.58 2.45
+/- 0.34 Pass 151
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Lab Code Date Analysis First Result Second Result Result Acceptance SL-6017, 6018 SL-6017, 6018 SL-6017, 6018 VE-6038, 6039 SW-6059,6060 VE-6302, 6303 VE-6302, 6303 VE-6302, 6303 VE-6302, 6303 W-7098,7099 W-6407,6408 MI-6479, 6480 W-6579,6580 AP-7015, 7016 AP-6105, 6106 LW-6603, 6604 AP-7056, 7057 G-6730,6731 G-6730,6731 G-6730,6731 AP-7077, 7078 AP-7077, 7078 VE-6798, 6799 AP-6820, 6821 W-7755,7756 BS-7944,7945 BS-7944, 7945 BS-7140, 7141 AP-7168, 7169 DW-20349, 20350 DW-20349, 20350 WW-7667, 7668 WW-7381, 7382 SS-7495, 7496 W-7516,7517 VE-7537, 7538 MI-7622, 7623 DW-20399, 20400 DW-20399, 20400 BS-7600, 7601 9/6/2011 9/6/2011 9/6/2011 9/7/2011 9/8/2011 9/13/2011 9/13/2011 9/13/2011 9/13/2011 9/19/2011 9/20/2011 9/27/2011 9/27/2011 9/27/2011 9/28/2011 9/28/2011 9/29/2011 10/3/2011 10/3/2011 10/3/2011 10/3/2011 10/3/2011 10/4/2011 10/6/2011 10/9/2011 10/10/2011 10/10/2011 10/13/2011 10/13/2011 10/13/2011 10/13/2011 10/19/2011 10/21/2011 10/26/2011 10/27/2011 10/28/2011 10/31/2011 10/31/2011 10/31/2011 11/1/2011 Be-7 Gr. Beta K-40 Sr-90 H-3 Be-7 Gr. Beta H-3 K-40 H-3 Ra-228 K-40 H-3 Be-7 Be-7 Gr. Beta Be-7 Be-7 Gr. Beta K-40 Be-7 Be-7 K-40 Be-7 H-3 Cs-137 K-40 K-40 Be-7 U-233/4 U-238 H-3 H-3 K-40 H-3 K-40 K-40 U-233/4 U-238 Gr. Beta 0.47 4.23 4.43 1.86 219.75 0.76 27.00 6966.00 20.62 586.61 1.61 1384.10 287.97 0.08 0.11 2.15 0.08 4.24 8.27 6.46 0.08 0.08 11.76 0.22 261.92 291.17 14237.0 2.59 0.25 1.77 0.28 1049.11 1904.40 10.16 191.46 2.08 1386.20 5.70 3.10
+/- 0.17
+/- 0.16
+/- 0.55
+/- 0.98
+/- 97.52
+/- 0.24
+/- 1.02
+/- 249.00
+/- 0.68
+/- 103.06
+/- 0.94
+/- 111.10
+/- 99.68
+/- 0.02
+/- 0.02
+/- 1.04
+/- 0.02
+/- 0.36
+/- 0.33
+/- 0.56
+/- 0.01
+/- 0.01
+/- 0.65
+/- 0.08
+/- 96.52
+/- 34.00
+/- 686.40
+/- 0.35
+/- 0.09
+/- 0.41
+/- 0.19
+/- 116.32
+/- 145.45
+/- 0.55
+/- 84.47
+/- 0.23
+/- 116.80
+/- 0.70
+/- 0.50 0.51 3.94 4.24 2.30 177.41 0.85 25.50 6947.00 20.63 525.71 0.79 1411.40 285.95 0.09 0.09 1.65 0.06 4.47 7.93 5.41 0.07 0.07 11.91 0.18 221.92 330.68 15359.0 2.58 0.25 2.25 0.31 1071.39 1813.62 9.56 224.05 2.41 1407.90 5.70 3.70 5.31
+/- 0.19
+/- 0.15
+/- 0.53
+/- 0.92
+/- 95.76
+/- 0.20
+/- 0.95
+/- 249.00
+/- 0.64
+/- 100.63
+/- 0.81
+/- 105.00
+/- 99.60
+/- 0.02
+/- 0.02
+/- 0.90
+/- 0.01
+/- 0.37
+/- 0.31
+/- 0.50
+/- 0.01
+/- 0.01
+/- 0.62
+/- 0.10
+/- 94.80
+/- 36.40
+/- 703.80
+/- 0.52
+/-0.11
+/- 0.77
+/- 0.33
+/- 117.10
+ 142.91
+/- 0.49
+/- 86.03
+/-0.21
+/- 116.50
+/- 0.70
+ 0.70
+/- 1.35 0.49 4.09 4.34 2.08 198.58 0.81 26.25 6956.50 20.63 556.16 1.20 1397.75 286.96 0.08 0.10 1.90 0.07 4.36 8.10 5.94 0.07 0.07 11.84 0.20 241.92 310.93 14798.0 2.59 0.25 2.01 0.30 1060.25 1859.01 9.86 207.76 2.24 1397.05 5.70 3.40 6.07
+/- 0.13
+/- 0.11
+/- 0.38
+/- 0.67
+/- 68.34
+/- 0.16
+/- 0.70
+/- 176.07
+/- 0.47
+/- 72.02
+/- 0.62
+/- 76.43
+/- 70.45
+/- 0.01
+/- 0.01
+/- 0.69
+/- 0.01
+/- 0.26
+/- 0.23
+/- 0.38
+/- 0.01
+/- 0.01
+/- 0.45
+/- 0.06
+/- 67.65
+/- 24.90
+/- 491.55
+/- 0.31
+/- 0.07
+/- 0.44
+/- 0.19
+/- 82.53
+/- 101.95
+/- 0.37
+/- 60.28
+/- 0.16
+/- 82.48
+/- 0.49
+/- 0.43
+/- 0.98 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 6.83
+/- 1.44 152
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Second Result Lab Code SG-8471, 8472 SG-8471, 8472 DW-20424, 20425 DW-20424, 20425 DW-20424, 20425 DW-20424, 20425 DW-20435, 20436 DW-20435, 20436 SG-7902, 7903 SG-7902, 7903 SG-7902, 7903 SG-7902, 7903 BS-8033, 8034 LW-8075, 8076 AP-8193, 8194 F-8663, 8664 F-8663, 8664 F-8663, 8664 DW-20449, 20450 DW-20449, 20450 SWU-8388, 8389 AP-8841, 8842 W-8886, 8887 W-8886, 8887 W-8886, 8887 SO-8958, 8959 AP-8907, 8908 AP-9196, 9197 LW-9091, 9092 Date 11/1/2011 11/1/2011 11/7/2011 11/7/2011 11/7/2011 11/7/2011 11/8/2011 11/8/2011 11/10/2011 11/10/2011 11/10/2011 11/10/2011 11/11/2011 11/16/2011 11/17/2011 11/19/2011 11/19/2011 11/19/2011 11/28/2011 11/28/2011 11/29/2011 12/15/2011 12/15/2011 12/15/2011 12/1512011 12/21/2011 12/22/2011 12/28/2011 12/29/2011 Analysis Gr. Alpha Gr. Beta U-233/4 U-235 U-238 U-238 U-233/4 U-238 Ac-228 K.40 Pb-212 Pb-214 Cs-137 Gr. Beta Be-7 Cs-137 Gr. Beta K-40 U-233/4 U-238 Gr. Beta Be-7 Gr. Alpha Gr. Beta Ra-226 K-40 Be-7 Be-7 Gr. Beta First Result 13.63
+/-2.32 20.30
+/- 1.43 5.90
+/- 0.80 0.10
+/- 0.10 4.30
+/- 0.70 10.30
+/- 1.00 11.00
+/- 1.10 5.90
+/- 0.80 21.38
+/- 0.47 9.72
+/- 1.04 3.99
+/- 0.10 9.15
+/- 0.23 0.03
+/- 0.02 1.93
+/- 0.62 0:21
+/-0.11 0.03
+/- 0.02 3.55
+/- 0.10 3.04
+/- 0.42 0.70
+/- 0.20 0.60
+/- 0.20 1.66
+/- 0.57 0.23
+/- 0.12 0.83
+/- 0.81 6.80
+/- 1.25 0.23
+/- 0.15 14.58
+/-0.86 0.15
+/- 0.06 0.06
+/- 0.01 1.97
+/- 0.63 11.13 17.65 6.10 0.30 3.70 10.10 10.60 4.90 20.48 9.53 3.99 9.14 0.03 2.55 0.26 0.03 3.71 3.05 0.80 0.60 1.65 0.19 1.58 5.94 0.41 15.07 0.11 0.07 1.74
+/- 2.00
+/- 1.42
+/- 0.80
+/- 0.20
+/- 0.60
+/- 1.00
+/- 0.80
+/- 0.60
+/- 0.52
+/- 0.92
+/- 0.10
+/- 0.21
+/- 0.02
+/- 0.64
+/- 0.13
+/- 0.02
+/- 0.10
+/- 0.35
+/- 0.20
+/- 0.20
+/- 0.59
+/- 0.09
+/- 0.99
+/- 1.22
+/- 0.16
+/- 0.87
+/- 0.07
+/- 0.01
+/- 0.60 Result 12.38
+/- 1.53 18.98
+/- 1.01 6.00
+/- 0.57 0.20
+/-0.11 4.00
+/- 0.46 10.20
+/- 0.71 10.80
+/- 0.68 5.40
+/- 0.50 20.93
+/- 0.35 9.63
+/- 0.69 3.99
+/- 0.07 9.15
+/- 0.16 0.03
+/- 0.01 2.24
+/- 0.44 0.24
+/- 0.08 0.03
+/- 0'01 3.63
+/- 0.07 3.05
+/- 0.27 0.75
+/- 0.14 0.60
+/- 0.14 1.66
+/- 0.41 0.21
+/- 0.07 1.21
+/- 0.64 6.37
+/- 0.87 0.32
+/- 0.11 14.83
+/- 0.61 0.13
+/- 0.05 0.06
+/- 0.01 1.86
+/- 0.44 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, Vegetation, Soil, sediment (pCi/g).
153
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Code '
Date Analysis Laboratory result Activity Limits d Acceptance STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 STW-1237 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 Am-241 Co-57 Co-60 Cs-134 Cs-137 H-3 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 Zn-65 0.35
+/- 0.10
< 0.2 24.10
+/- 0.40 19.80
+/- 0.40 29.40
+/- 0.50 238.90
+/- 8.80 95.40
+/- 3.10 32.50
+/- 0.60 16.30
+/- 0.60 1.11
+/-0.12 0.88
+/- 0.12 8.70
+/- 0.70 7.60
+/- 0.60
< 0.5 0.53 0.00 24.60 21.50 29.40 243.00 91.00 31.60 18.60 1.06 0.81 8.72 8.99 0.00 0.37
-0.69 17.20 15.10 20.60 170.00 64.00 22.10 13.00 0.75 0.57 6.10 6.29
-32.00
-28.00
-38.20
-316.00
- 118.00
-41.10
-24.20
-1.38
-1.05
-11.34
-11.69 STW-1238 02/01/11 Gr. Alpha STW-1238 02/01/11 Gr. Beta 0.82
+/- 0.07 1.14 2.82
+/- 0.07 2.96 STVE-1239 STVE-1239 STVE-1239 STVE-1239 STVE-1239 STVE-1239 STSO-1240 STSO-1240 STSO-1240 STSO-1240 STSO-1240 STSO-1 240 STSO-1240' STSO-1240 STSO-1240 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Ni-63 U-233/4 U-238 11.27
+/-0.21 4.95
+/- 0.16 5.18
+/- 0.19
< 0.09 6.91
+/- 0.25 3.10
+/- 0.32 9.94 4.91 5.50 0.00 6.40 2.99 0.34
-1.93 1.48
-4.44 6.96
-12.92 3.44
-6.38 3.85
-7.15 4.48
-8.32 2.09
-3.89 Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass 984.10 540.70 726.70 883.10 622.70
-0.30
+/- 4.10
+/- 3.00
+/- 5.92
+/- 4.70
+/- 16.70
+/- 1.00 927.00 482.00 680.00 758.00 540.00 0.00 649.00 337.00 476.00 531.00 378.00 1205.00
-627.00
-884.00
-985.00
-702.00 384.00
+/- 16.90 582.00 407.00
-.757.00 166.60
+/- 7.30 176.00 123.00
-229.00 172.00
+/- 7.40 184.00 129.00
-239.00 1671.00
+/- 13.10 1359.00 951.00 1767.00 STSO-1240 02/01/11 Zn-65 STAP-1 241 STAP-1241 STAP-1 241 STAP-1241 STAP-1241 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 Am-241 Co-57 Co-60 Cs-134 Cs-137 0.00 3.48 0.00 3.44 2.46
+/- 0.01
+/-.0.06
+/- 0.02
+/- 0.27
+/- 0.27 0.00 3.33 0.00 3.49 2.28
-0.10 2.33
-0.10 2.44 1.60
-0.10
- 4.33
-0.10
- 4.54
- 2.96 154
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STAP-1241 STAP-1241 STAP-1241 STAP-1241 STAP-1241 STAP-1241 g STAP-1241 STAP-1241 STAP-1241 STW-1249 STVE-1250 STVE-1250 STVE-1250 STVE-1250 STVE-1250 STVE-1250 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STSO-1251 STAP-1252 STAP-1252 STAP-1252 STAP-1252 STAP-1252 STAP-1252 STAP-1 252 STAP-1 252 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 02/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 Gr. Alpha Gr. Beta Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 1-129 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 0.39 1.54 2.90 0.07 0.06 1.89 0.13 0.14 3.80 7.32 0.01 3.57
-0.02 5.28 6.48 7.35 h
i 1333.90 701.30 0.71 1106.00 749.20 984.30 0.11 97.90 78.80 219.40 110.00 267.00 280.30 1639.90 5.06 3.13 0.01 2.61 0.01 0.13 0.15 1.65
+/- 0.05
+/- 0.07
+/- 0.10
+/- 0.02
+/- 0.02
+/- 0.15
+/- 0.02
+/- 0.02
+/- 0.18
+/- 0.30
+/- 0.02
+/- 0.13
+/- 0.04
+/- 0.20
+/- 0.22
+/- 0.34
+/- 4.20
+/- 3.40
+/- 1.05
+/- 5.60
+/- 19.00
+/- 5.40
+/- 1.21
+/- 7.40
+/- 6.40
+/- 16.70
+/- 8.00
+/- 10.20
+/- 10.40
+/- 11.40
+/- 0.08
+/- 0.09
+/- 0.03
+/- 0.09
+/- 0.03
+/- 0.02
+/- 0.02
+/- 0.16 0.66 1.32 2.64 0.10 0.08 1.36 0.18 0.19 3.18 9.50 0.00 3.38 0.00 4.71 5.71 6.39 1180.00 644.00 0.00 979.00 625.00 848.00 0.00 93.60 77.40 320.00 182.00 263.00 274.00 1560.00 5.09 3.20 0.00 2.60 0.00 0.12 0.14 1.67 0.20 0.66 1.85 0.07 0.05 0.95 0.13 0.13 2.23 6.70 2.37
-0.10 3.30 4.00 4.47
- 4.39
-0.10
-6.12
- 7.42
- 8.31 826.00
- 1534.00 451.00
-837.00
-1.12
-1.99
-3.43
-0.13
-0.10
-1.77
-0.23
-0.24
-4.13
-12.40 685.00 438.00 594.00 65.50 54.20 224.00 127.00 184.00 192.00 1092.00 3.56 2.24
-0.10 1.82
-0.10 0.08 0.10 o1.17
-1273.00
-813.00
-1102.00
-121.70
-100.60
-416.00
-237.00
-342.00
-356.00
-2028.00
-6.62
-4.16
-0.10
-3.38
-0.10
-0.15
-0.18
-2.17 Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 155
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Lab Code c STAP-1252 STAP-1252 STAP-1252 STW-1 254 STW-1 254 STW-1254 STW-1254 Date 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 08/01/11 Analysis U-233/4 U-238 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Laboratory result 0.17
+/- 0.02 0.17
+/- 0.02 4.46
+/- 0.23 Known Activity 0.16 0.17 4.11 36.60 29.30 19.10 0.00 Control Limits d AcceDtance 0.11
-0.21 0.12
-0.22 2.88
- 5.34 37.20 28.80 18.00 0.06
+/- 0.50
+/- 0.40
+/- 0.60
+/- 0.13 25.60 20.50 13.40 STW-1254 08/01/11 H-3 710.0 1039.90
+/- 17.90 1014.00 0
109.0
- 47.60
-38.10
- 24.80
- 1318.00
- 203.00
- 32.50 STW-1254 08/01/11 K-40 161.40
+/- 4.10 156.00 STW-1254 08/01/11 Mn-54 25.70
+/- 0.50 25.00 STW-1254 08/01/11 Ni-63 0.60
+/- 2.00 0.00 STW-1254 08/01/11 Pu-238 0.04
+/- 0.02 0.02 STW-1254 08/01/11 Pu-239/40 2.27
+/- 0.14 2.40 STW-1254 08/01/11 Sr-90 15.60
+/- 1.80 14.20 STW-1254 08/01/11 Tc-99
-0.30
+/- 0.50 0.00 STW-1254 08/01/11 U-233/4 2.78
+/- 0.20 2.78 STW-1254 08/01/11 U-238 2.86
+/- 0.21 2.89 STW-1254 08/01/11 Zn-65 30.20
+/- 0.90 28.50 STW-1255 08/01/11 Gr. Alpha 0.72
+/- 0.12 0.87 STW-1255 08/01/11 Gr. Beta 4.71
+/- 0.15 4.81 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE
ývegetation).
MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and 0
17.50 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 0.00
-1.00 1.68
-3.12 9.90
-18.50 1.95 2.02 20.00 0.26 2.41
- 3.61
- 3.76
-37.10
-1.47
- 7.22 control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
e Result of a repeat analysis was still unacceptable. ERA crosschecks for Am-241 were acceptable, but biased low.
Matrix spikes were prepared, ( 5.17 and 51.7 pCi/L), to verify method; results were acceptable, 4.4 and 47.5 pCi/L.
Am-241 has been added to the internal spike and blank program for 2012.
f An error in percent recovery was found, result of recalculation, 427.3 +/- 18.8 Bq/kg dry.
9 No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.
h The analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.
The lab does not currently analyze soil for Tc-99, but is evaluating the procedure. After consultation with Eichrom, the analysis was repeated using a matrix spike correction. Mean result of triplicate reanalyses; 183.3 Bq/kg.
156
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance STAP-1230 03/21/11 Am-241 46.0
+/- 1.8 62.5 36.6
-85.7 Pass STAP-1230 03/21/11 Co-60 401.2
+/- 12.1 390.0 302.0
-487.0 Pass STAP-1230 03/21/11 Cs-134 268.2
+/- 24.8 279.0 182.0
-345.0 Pass STAP-1230 03/21/11 Cs-137 345.3
+/- 24.9 312.0 234.0
-410.0 Pass STAP-1230 03/21/11 Mn-54
< 1.9 0.0 Pass STAP-1230 03/21/11 Pu-238 76.1
+/- 3.2 69.0 47.4
- 90.7 Pass STAP-1230 03/21/11 Pu-239/40 70.50
+/- 3.10 65.5 47.5
-85 Pass STAP-1230 03/21/11 Sr-90 208.40
+/- 18.70 185.0 81.4
-288 Pass STAP-1230 03/21/11 U-233/4 56.10
+/- 2.10 61.5 38.7
-91 Pass STAP-1230 03/21/11 U-238 58.90
+/- 2.60 61.0 39.0
-87 Pass STAP-1230 03/21/11 Uranium 118.50
+/- 5.52 125.0 63.9
-199 Pass STAP-1230 03/21/11 Zn-65 312.60
+/- 23.40 279.0 193.0
-386 Pass STAP-1231 03/21/11 Gr. Alpha 88.40
+/- 3.70 74.3 38.5
-112 Pass STAP-1231 03/21/11 Gr. Beta 85.10
+/- 2.80 69.5 42.8
-102 Pass STSO-1232 03/21/11 Ac-228 1327.8
+/- 97.5 1490.0 958.0
-2100.0 Pass STSO-1232 03/21/11 Am-241 662.8
+/- 88.1 914.0 546.0
- 1170.0 Pass STSO-1232 03/21/11 Bi-212 1396.2
+/- 185.3 1400.0 368.0
-2090.0 Pass STSO-1232 03/21/11 Bi-214 841.1
+/- 33.2 725.0 445.0
-1040.0 Pass STSO-1232 03/21/11 Co-60 2423.7
+/- 27.1 2220.0 1620.0
- 2980.0 Pass STSO-1232 03/21/11 Cs-134 2481.3
+/- 42.2 2450.0 1580.0
-2950.0 Pass STSO-1232 03/21/11 Cs-137 2108.2
+/- 30.2 1920.0 1470.0
-2490.0 Pass STSO-1232 03/21/11 K-40 11497.3
+/- 276.6 11500.0 8320.0
-15600.0 Pass STSO-1232 03/21/11 Mn-54
< 17.4 0.0 Pass STSO-1232 03/21/11 Pb-212 994.7
+/- 30.0 1440.0 931.0
-2030.0 Pass STSO-1232 03/21/11 Pb-214 918.3
+/- 42.6 805.0 482.0
-1200.0 Pass STSO-1232 03/21/11 Pu-238 1593.6
+/- 156.7 1420.0 813.0
- 2000.0 Pass STSO-1232 03/21/11 Pu-239/40 1428.9
+/- 143.4 1400.0 956.0
-1860.0 Pass STSO-1232 03/21/11 Sr-90 8638.0
+/- 442.8 7590.0 2740.0
- 12400.0 Pass STSO-1232 03/21/11 Th-234 1350.1
+/- 180.0 962.0 305.0
- 1830.0 Pass STSO-1232 03/21/11 U-233/4 748.0
+/- 94.4 972.0 616.0
- 1210.0 Pass STSO-1232 03/21/11 U-238 909.0
+/- 104.9 962.0 588.0
- 1220.0 Pass STSO-1232 03/21/11 Uranium 1690.8
+/- 104.9 1980.0 1130.0
-2670.0 Pass STSO-1232 03/21/11 Zn-65 2356.2
+/- 57.1 1990.0 1580.0
-2670.0 Pass 157
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance STVE-1233 03/21/11 Am-241 2377.5
+/- 83.2 3200.0 1820.0
- 4400.0 Pass STVE-1233 03/21/11 Cm-244 602.9
+/- 38.4 812.0 400.0
-1260.0 Pass STVE-1233 03/21/11 Co-60 810.2
+/- 32.4 733.0 496.0
-1050.0 Pass STVE-1233 03/21/11 Cs-134 849.4
+/- 54.5 770.0 441.0
-1070.0 Pass STVE-1233 03/21/11 Cs-137 889.9
+/- 36.3 829.0 608.0
-1150.0 Pass STVE-1233 03/21/11 K-40 28146.70
+/- 698.80 25800.0 18500.0
-36500 Pass STVE-1233 03/21/11 Mn-54
< 19.3 0.0 Pass STVE-1233 03/21/11 Pu-238 3068.10
+/- 170.70 2990.0 1610.0
-4380 Pass STVE-1233 03/21/11 Pu-239/40 3180.00
+/- 88.90 3100.0 1920.0
-4230 Pass STVE-1233 03/21/11 Sr-90 8549.20
+/- 675.00 7890.0 4410.0
-10500 Pass STVE-1233 03/21/11 U-233/4 2418.60
+/- 142.50 2610.0 1790.0
-3460 Pass STVE-1233 03/21/11 U-238 2417.00
+/- 142.50 2590.0 1820.0
-3270 Pass STVE-1233 03/21/11 Uranium 4929.80
+/- 142.50 5320.0 3660.0
-6860 Pass STVE-1233 03/21/11 Zn-65 962.40
+/- 62.50 799.0 577.0
-1090 Pass STW-1234 03/21/11 Am-241 100.0
+/- 6.4 135.0 92.5
-182.0 Pass STW-1234 03/21/11 Co-60 401.6
+/- 7.2 411.0 358.0
-486.0 Pass STW-1234 03/21/11 Cs-134 222.7
+/- 12.3 231.0 171.0
-265.0 Pass STW-1234 03/21/11 Cs-137 410.3
+/- 9.5 417.0 354.0
-500.0 Pass STW-1234 03/21/11 Mn-54
< 3.0 0.0 Pass STW-1234 03/21/11 Pu-238 130.9
+/- 5.5 131.0 99.1
-162.0 Pass STW-1234 03/21/11 Pu-239/40 113.0
+/- 5.0 119.0 92.1
-147.0 Pass STW-1234 03/21/11 Sr-90 739.6
+/- 13.0 773.0 491.0
- 1030.0 Pass STW-1234 03/21/11 U-233/4 83.4
+/-3.8 94.3 71.1
-122.0 Pass STW-1234 03/21/11 U-238 85.5
+/- 3.9 93.5 71.4
-116.0 Pass STW-1234 03/21/11 Uranium 172.0
+/- 8.5 192.0 138.0
-256.0 Pass STW-1234 03/21/11 Zn-65 114.5
+/- 10.8 111.0 94.1
- 138.0 Pass STW-1235 03/21/11 Gr. Alpha 97.6
+/- 2.9 112.0 49.7
-166.0 Pass STW-1235 03/21/11 Gr. Beta 99.6
+/- 2.0 99.8 58.4
-146.0 Pass STW-1236 03/21/11 H-3 16307.0
+/- 377.0 15200.0 9900.0
-22500.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).
c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.
158
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report APPENDIX B DATA REPORTING CONVENTIONS 159
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Data Reporting Conventions 1.0.
All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x +/- s where:
x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xi +/- sl and x2 +/- S2 Reported result:
x +/- s; where x = (1/2) (x1 + x2) and s = (1/2)
+S2 3.2.
Individual results:
<Li, <L2 Reported result: <L, where L = lower of Li and L2 3.3.
Individual results:
x +/- s, <L Reported result:
x +/- s if x > L; <L otherwise.
4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2... xn are defined as follows:
n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1.
If the number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.
160
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas 161
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.
Air (pCi/m 3)
Water (pCi/L)
Gross alpha Gross beta Iodine-1 3 1b 1 x 10- 3 1
2.8 x 10-1 Strontium-89 Strontium-90 Cesium-1 37 Barium-140 Iodine-131 Potassium-40c Gross alpha Gross beta Tritium 8,000 500 1,000 8,000 1,000 4,000 2
10 1 x 106 a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
c A natural radionuclide.
162
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report APPENDIX D REMP SAMPLING
SUMMARY
163
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No.
Reporting Period 50-346 January-December, 2011 Location of Facility Ottawa, Ohio County. State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Number Type of LLDb Mean (F)c Mean (F)c Mean (F)c Routine Results (Units)
Analysesa Range' Locationd Range' Rangec e
0.026 T-12, Water 0.027 Airborne GB 529 0.003 (318/318)
Treatment 0.028 (53/53)
(211/211) 0 Plant, 23.5 mi.
(0.012-Particulates (0.011-0.050)
WNW (0.013-0.050) 0.051)
(pCi/m 3)
Sr-89 0.0011
< LLD
< LLD 0
Sr-90 0.0008
< LLD
< LLD 0
GS 40 T-27, Crane 0.079 Be-7 0.015 0.075 (24/24)
Creek S.P.
0.086 (4/4)
(16/16) 0 (0.062-(0.059-0.090) 5.3 mi. SW (0.079-0.094) 0.094)
K-40 0.027
< LLD
< LLD 0
Nb-95 0.0021
< LLD
< LLD 0
Zr-95 0.0022
< LLD
< LLD 0
Ru-103 0.0014
< LLD
< LLD 0
Ru-106 0.0089
< LLD
< LLD 0
Cs-1 34 0.0011
< LLD
< LLD 0
Cs-137 f
0.0013 0.0015 (1/24)
T-8, Farm 0.0015 (1/4)
< LLD 0
2.7 mi. WSW Ce-141 0.0020
< LLD
< LLD 0
Ce-144 0.0060
< LLD
< LLD 0
T-12, Water 0.089 Airborne Iodine 1-131 529 0.033 0.081 (22/318)
Treatment 0.091 (4/53)
(13/211) 0 Plant, 23.5 mi.
(pCi/m 3)
(0.033-0.160)
WNW (0.060-0.166)
(0.044-0.166)
TLD (Quarterly)
(mR/91 days)
TLD (Quarterly)
(mR/91 days)
(Shield)
TLD (Annual)
(mR/365 days)
TLD (Annual)
(mR/365 days)
(Shield)
Gamma Gamma 351 4
1.0 1.0 1.0 1.0 16.7 (308/308)
(3.8-27.2)
T-45, Site Boundary 0.5 mi. WNW 25.2 (4/4)
(23.4-27.2) 17.9 (43/43)
(13.3-24.7) 0 0
8.4 (4/4)
(7.9-9.4)
None Gamma Gamma 87 61.7 (77/77)
(38.6-104.6)
T-8, Farm 2.7 mi. WSW 104.6 (1/1) 68.7 (10/10)
(48.8-101.6) 0 0
1 26.8 (1/1)
None 164
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Docket No.
Reporting Period 50-346 January-December, 2011 Ottawa. Ohio
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Mean Type Number of LLDb (F)c Mean (F)c Mean (F)c Routine Results (Units)
Analyses' Rangec Locationd Rangec Rangec e
Milk (pCi/L) 1-131 12 0.5 none
< LLD 0
Sr-89 12 0.7 none
< LLD 0
Sr-90 12 0.6 none T-24, Sandusky 0.7 (8/12) 0.7 (8/12) 0 21.0 mi. SE (0.6-0.9)
(0.6-0.9)
GS 12 1355 K-40 100 none T-24, Sandusky 1355 (12/12)
(12/12) 0 21.0 mi. SE (1286-1410)
(1286-1410)
Cs-134 3.8 none
< LLD 0
Cs-137 4.5 none
< LLD 0
Ba-La-140 3.3 none
< LLD 0
(g/L)
Ca 12 0.50 none T-24, Sandusky 1.14 (12/12) 1.14 (12/12) 0 21.0 mi. SE (0.93-1.29)
(0.93-1.29)
(g/L)
K (stable) 12 none T-24, Sandusky 1.65 (12/12) 1.65 (12/12) 0 21.0 mi. SE (1.57-1.72)
(1.57-1.72)
(pCi/g)
Sr-90/Ca 12 none T-24, Sandusky 0.56 (12/12) 0.56 (12/12) 0 21.0 mi. SE (0.49-0.70)
(0.49-0.70)
(pCi/g)
Cs-137/K 12 none
< LLD 0
Ground Water (pCi/L)
GB (TR)
H-3 8
8 8
8 1.6 330 1.6 0.5 1.7 (2/5)
(1.6-1.7)
T-27A, Crane Creek S.P 5.3 mi. WNW 2.5 (2/3)
(1.7-3.2) 2.5 (2/3)
(1.7-3.2)
Sr-89 Sr-90 GS Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 Ba-La-140 15 30 15 15 30 15 10 10 15
< LLD
< LLD
" LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
" LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 0
0 0
0 0
0 0
0 0
0 0
0 165
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa, Ohio
( County, State)
Docket No.
50-346 Reporting Period January-December, 2011 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units)
Analyses' Rangec Locationd Rangec Rangec Resultse Edible Meat GS 1
(pCi/g wet)
K-40 0.10 2.72 (1/1)
T-31, Onsite 2.72 (1/1) 0 Roving location Nb-95 0.007
< LLD
< LLD 0
Zr-95 0.010
< LLD
< LLD 0
Ru-103 0.005
< LLD
< LLD 0
Ru-1 06 0.044
< LLD
< LLD 0
Cs-134 0.004
< LLD
< LLD 0
Cs-137 0.006
< LLD
< LLD 0
Ce-141 0.018
< LLD
< LLD 0
Ce-144 0.028
< LLD
< LLD 0
Fruits and Sr-89 3
0.003
< LLD
< LLD 0
Vegetables Sr-90 3
0.002
< LLD
< LLD 0
(pCi/g wet) 1-131 3
0.010
< LLD
< LLD 0
GS 3
K-40 0.50 1.32 (2/2)
T-25, Oak Harbor 1.60 (1/1) 1.28 (1/1) 0 (1.03-1.60) 1.6 mi. S Nb-95 0.006
< LLD
< LLD 0
Zr-95 0.010
< LLD LLD 0
Cs-134 0.005
< LLD
< LLD 0
Cs-137 0.008
< LLD
< LLD 0
Ce-141 0.013
< LLD
< LLD 0
Ce-144 0.044
< LLD
< LLD 0
Broad Leaf Vegetation (pCi/g wet)
Sr-89 Sr-90 1-131 9
9 9
9 0.004 0.002 0.014
< LLD
< LLD
" LLD
< LLD
< LLD
< LLD GS K-40 0.50 Nb-95 Zr-95 Cs-134 Cs-137 Ce-141 Ce-144 0.009 0.012 0.007 0.008 0.016 0.059 2.16 (6/6)
(1.71-2.95)
< LLD
< LLD
< LLD
" LLD
" LLD
< LLD T-37, Farm Mkt.
13.0 mi. SW 2.41 (3/3)
(2.02-3.10) 2.41 (3/3)
(2.02-3.10)
< LLD
< LLD
< LLD
< LLD
" LLD
< LLD 0
0 0
0 0
0 0
0 0
0 166
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Summary Table 4.5 Name of Facility Location of Facility Davis-Besse Nuclear Power Station Docket No.
Reporting Period 50-346 January-December, 2011 Ottawa, Ohio
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)0 Mean (F)c Mean (F)c Routine Results (Units)
Analyses' Range' Locationd Range' Range' 0
Animal/
GS 3
Wildlife Feed Be-7 0.10 1.03 (2/2)
T-31, On-site 1.09 (1/1) 0.66 (1/1) 0 (pCi/g wet)
(0.96-1.09)
Roving location K-40 0.10 2.23 (2/2)
T-31, On-site 2.45 (1/1) 0.91 (1/1) 0 (2.00-2.45)
Roving location Nb-95 0.020
< LLD
< LLD 0
Zr-95 0.052
< LLD
< LLD 0
Ru-103 0.025
< LLD
< LLD 0
Ru-106 0.17
< LLD
< LLD 0
Cs-134 0.020
< LLD
< LLD 0
Cs-137 0.028
< LLD
< LLD 0
Ce-141 0.047
< LLD
< LLD 0
Ce-144 0.21
< LLD
< LLD 0
Soil (pCi/g dry)
GS 10 Be-7 K-40 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 0.36 0.1i0 0.053 0.048 0.030 0.18 0.023 0.029 0.076 0.1i4 0.69 (4/6)
(0.37-0.95) 13.79 (6/6)
(7.74-23.52)
< LLD
" LLD
< LLD
< LLD
< LLD 0.15 (4/6)
(0.059-0.24)
< LLD
< LLD T-i, Site Boundary 0.6 mi. ENE T-27, Crane Creek S.P.
5.3 mi. SW T-2, Site Boundary 0.9 mi. E 0.95 (1/1) 23.98 (1/1) 0.55 (1/4) 18.61 (4/4)
(12.84-23.98)
< LLD
< LLD
< LLD
< LLD
< LLD 0.11 (3/4)
(0.048-0.17) 0 0
0 0
0 0
0 0
0 0
0.24 (1/1)
" LLD
< LLD 167
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa, Ohio Docket No.
Reporting Period 50-346 January-December, 2011
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)0 Mean (F)c Routine Results (Units)
Analysesa Range' Locationd Range' Rangec e
2.2 2.0 Treated GB (TR) 36 0.9 (11/12)
T-22, Carroll Twp.
2.2 (11/12)
(23/24) 0 Surface Water (1.1-3.1)
WTP, 3.0 mi. NW (1.1-3.1)
(0.9-3.4)
(pCi/L)
H-3 12 330
< LLD
< LLD 0
Sr-89 12 1.0
< LLD
< LLD 0
Sr-90 12 0.7
< LLD
< LLD 0
GS 12 Mn-54 15
< LLD
< LLD 0
Fe-59 30
< LLD
< LLD 0
Co-58 15
< LLD
< LLD 0
Co-60 15
< LLD
< LLD 0
Zn-65 30
< LLD
< LLD 0
Zr-Nb-95 15
< LLD
< LLD 0
Cs-134 10
< LLD
< LLD 0
Cs-137 10
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
2.5 T-3, Site 2.1 Untreated GB (TR) 48 0.9 (23/24)
Boundary 2.8 (12/12)
(23/24) 0 Surface Water (1.3-4.8) 1.4 mi. ESE (1.3-4.8)
(1.0-3.5)
(pCi/L)
H-3 48 330 486 (2/24)
T-3, Site Boundary 620 (1/12)
< LLD 0
(351-620) 1.4 mi. ESE Sr-89 0
1.1
< LLD
< LLD 0
Sr-90 0
0.7
< LLD
< LLD 0
GS 48 Mn-54 15
< LLD
< LLD 0
Fe-59 30
< LLD
< LLD 0
Co-58 15
< LLD
< LLD 0
Co-60 15
< LLD
< LLD 0
Zn-65 30
< LLD
< LLD 0
Zr-Nb-95 15
< LLD
< LLD 0
Cs-134 10
< LLD
< LLD 0
Cs-137 10
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
168
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa, Ohio
( County, State)
Docket No.
50-346 Reporting Period January-December, 2011 Indicator Location with Highest Control Number Location Sample Type and s
Annual Mean Locations Non-Mean Type Number of LLDb (F)c Mean (F)0 Mean (F)c Routine Results (Units)
Analysesa Rangec Locationd Rangec Rangec 3.40 Fish GB 6
0.10 (3/3)
T-35, Lake Erie 3.70 (3/3) 3.70 (3/3) 0 (2.90-(3.00-(pCi/g wet) 4.40)
> 10 mi.
(3.00-4.60) 4.60)
GS 6
2.67 K-40 0.10 (3/3)
T-35, Lake Erie 2.88 (3/3) 2.88 (3/3) 0 (1.47-(2.54-3.30)
> 10 mi.
(2.54-3.26) 3.26)
Mn-54 0.016
< LLD
< LLD 0
Fe-59 0.213
< LLD
< LLD 0
Co-58 0.034
< LLD
< LLD 0
Co-60 0.012
< LLD
< LLD 0
Zn-65 0.039
< LLD
< LLD 0
Cs-134 0.016
< LLD
< LLD 0
Cs-137 0.017
< LLD
< LLD 0
Shoreline GS 8
11.16 10.13 Sediments K-40 0.10 (6/6)
T-4, Site Boundary 14.35 (2/2)
(2/2) 0 (7.67-(12.00-(9.57-(pCi/g dry) 16.69) 0.8 mi. S 16.69) 10.69)
Mn-54 0.034
< LLD
< LLD 0
Co-58 0.038
< LLD
< LLD 0
Co-60 0.036
< LLD
< LLD 0
Cs-134 0.026
< LLD
< LLD 0
Cs-137 0.034
< LLD
< LLD 0
a GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..
e Non-routine results are those which exceed ten times the control station value.
'Activity observed in the March and April air samples attributable to Fukushima Daiichi accident.
169
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report APPENDIX E SUPPLEMENTAL ANALYSES 170
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report C-1. Airborne iodine-131, as measured in activated charcoal canisters.
Units: pCi/m 3 Required 0.070 LLD:
Collection: Continuous, weekly exchange.
Date Volume Concentration Location Collected (M3) 1-131 (pCi/m3)
T-1 03-22-11 304 0.043
+/-
0.022 T-2 03-22-11 286 0.047
+/-
0.023 T-3 03-22-11 288 0.046
+/-
0.020 T-4 03-22-11 289 0.040
+/-
0.018 T-7 03-22-11 286 0.033
+/-
0.015 T-8 03-22-11 289 0.034
+/-
0.020 T-9 03-22-11 289 0.056
+/-
0.024 T-11 03-22-11 284 0.044
+/-
0.015 T-12 03-22-11 297 0.060
+/-
0.022 T-27 03-22-11 286 0.049
+/-
0.022 T-1 03-29-11 302 0.080
+/-
0.020 T-2 03-29-11 275 0.076
+/-
0.020 T-3 03-29-11 285 0.070
+/-
0.016 T-4 03-29-11 284 0.065
+/-
0.023 T-7 03-29-11 285 0.081
+/-
0.021 T-8 03-29-11 288 0.061
+/-
0.027 T-9 03-29-11 289 0.074
+/-
0.025 T-11 03-29-11 283 0.083
+/-
0.021 T-12 03-29-11 293 0.075
+/-
0.025 T-27 03-29-11 285 0.057
+/-
0.025 T-1 04-05-11 305 0.134
+/-
0.023 T-2 04-05-11 287 0.139
+/-
0.025 T-3 04-05-11 287 0.132
+/-
0.020 T-4 04-05-11 292 0.160
+/-
0.033 T-7 04-05-11 287 0.140
+/-
0.022 T-8 04-05-11 289 0.148
+/-
0.029 T-9 04-05-11 279 0.140
+/-
0.020 T-1 1 04-05-11 285 0.140
+/-
0.022 T-12 04-05-11 301 0.166
+/-
0.031 T-27 04-05-11 292 0.155
+/-
0.026 T-1 04-12-11 302 0.066
+/-
0.024 T-2 04-12-11 285 0.031 T-3 04-12-11 285 0.026 T-4 04-12-11 289 0.032 T-7 04-12-11 286 0.053
+/-
0.026 T-8 04-12-11 289 0.056
+/-
0.032 T-9 04-12-11 294 0.030 T-11 04-12-11 284 0.033 T-12 04-12-11 292 0.064
+/-
0.031 T-27 04-12-11 280 0.026 171
Davis-Besse Nuclear Power Station 2011 Annual Radiological Environmental Operating Report C-1. Airborne iodine-131, as measured in activated charcoal canisters.
Units: pCi/m 3 Required LLD:
0.070 Collection: Continuous, weekly exchange.
Date Volume Concentration Location Collected (M3) 1-131 (pCi/m3)
T-1 T-2 T-3 T-4 T-7 T-8 T-9 T-1 1 T-12 T-27 T-1 T-2 T-3 T-4 T-7 T-8 T-9 T-1 1 T-12 T-27 04-19-11 04-19-11 04-19-11 04-19-11 04-19-11 04-19-11 04-19-11 04-19-11 04-19-11 04-19-11 04-26-11 04-26-11 04-26-11 04-26-11 04-26-11 04-26-11 04-26-11 04-26-11 04-26-11 04-26-11 304 286 286 291 286 288 284 284 297 291 304 287 281 292 286 291 278 284 286 287 0.015 0.017 0.018 0.020 0.015 0.022 0.018 0.017 0.018 0.017 0.017 0.016 0.017 0.015 0.014 0.019 0.024 0.019 0.016 0.016 0.034
+
172