ML16147A006

Transmittal of Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear: Power Station - 2015

ML16147A006
Person / Time
Site:	Davis Besse
Issue date:	05/10/2016
From:	Saltz D C FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML16147A012	List: L-16-134, Offsite Dose Calculation Manual, Revision 31 ML16147A006 ML16147A009
References
L-16-134
Download: ML16147A006 (186)

Text

FE NOCŽ " FirstEnergy Nuclear Operating Company May 10, 2016 L-16-134 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 . Davis-Besse Nuclear Power Station 5501 N. State Route 2 Oak Harbor. Ohio 43449 10 CFR 50.36a Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear: Power Station -201-Q :*; ' .. ' . In accordance 1 O CFR .50.36a(a)(2), this the combined 2015 Annual Radiological Environmental Operating Report (AREOR) and Radiological Effluent Release Report (RERR) for the period January 2015 through December 2015. These annual reports are submitted for the Qavis-Besse Nuclear 'Power Station (DBNPS). The AREOR and the RERR must be s.ubmitted 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 ARE OR which was prepared to meet each requirement.

The following information is also,provided only tb the Pocument Control Desk. This information includes:

• 2015 RERR Meteorological Data (on Co_mpact Disc)

• Environmental, Inc. Midwest Laboratory, Mo1nthly Progress Report for January through December 2015 which contains the 2015 Radiological Environmental Monitoring Program Sample Analysis Results (on Compact Disc) -* Davis-Besse Offsite Dose Calculation Manual, Rev. 30 and 31 (on Compact Disc)

Davis-Besse Nuclear Power Station, Unit 1 L-16-134 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, at (419) 321-7374.

Sincerely, Douglas Director-Site Operations Davis-Besse Nuclear Power Station VAW/LTZ

Attachment:

Summary Location(s) of Off-Site Dose Calculation Manual Requ)rements 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 -2015 cc: Regional Administrator, NRC Region Ill 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-16-134 Attachment Page 1of1 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 78 and Appendix D)

• Results of the Land Use Census (pages 108 through 128)

• Results of the analysis of radiological environmental samples and of environmental radiation measurements (Environmental, Inc. Midwest Laboratory, Monthly Progress Report for January through December 2015 (pages 26 through 78))

• Summary description of the radiological environmental monitoring program (also pages 26 through 78)

• 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 75)

• 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-16-134 Enclosure Annual Radiological Environmental Operating Report, including the Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station -2015 (1 Report follows) 2015 Annual Radiological Environmental Operating Report Radiologi eleas ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Davis-Besse Nuclear Power Station January 1, 2015 through December 31, 2015 Davis-Besse Nuclear Power Station May2016 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE OF CONTENTS List of Tables List of Figures Executive Summary INTRODUCTION Fundamentals Radiation and Radioactivity Interaction with Matter Quantities and Units of Measurement Sources of Radiation Health Effects of Radiation Health Risks Benefits of Nuclear Power Nuclear Power Production Station Systems i Reactor Safety and Summary Radioactive Waste Description of the Davis-Besse Site References RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Introduction Pre-Operational Surveillance Program Operational Surveillance Program Objectives Quality Assurance Program Description Sample Analysis Sample History Comparison iv vi viii 1 2 3 5 7 9 10 11 11 16 19 19 22 24 26 26 27 27 28 32 34 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) 2015 Program Anomalies Atmospheric Monitoring Terrestrial Monitoring Aquatic Monitoring Direct Radiation Monitoring Conclusion References RADIOACTIVE EFFLUENT RELEASE REPORT Protection Stap.dards Sources of Radioactivity Released Processing and Monitoring Exposure Pathways Dose Assessment

• Results Regulatory Limits Effluent Concentration Limits Average Energy Measurements of Total Activity Batch Releases Abnormal Releases Percent of Offsite Dose Calculation Manual (ODCM) Release Limits Sources of Input Data Dose to Public Due to Activities Inside the Site Boundary Inoperable Radioactive Effluent Monitoring Equipment Changes to The ODCM and Process Control Plan (PCP) Borated Water Storage Tank Radionuclide Concentrations Onsite Groundwater Monitoring LAND USE CENSUS Program Design Methodology Results ii 36 36 43 53 66 76 76 79 79 80 81 82 83 84 85 85 85 85 86 86 86 87 87 88 88 103 108 108 109 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Title NON-RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring On-Site Meteorological Monitoring Land and Wetlands Management Water Treatment Plant Operation Chemical Waste Management Other Environmental Regulating Acts Other Environmental Programs APPENDICES Appendix A: Interlaboratory Comparison Program Results Appendix B: Data Reporting Conventions Appendix C: Supplemental Analyses Appendix D: REMP Sampling Summary iii v 114 115 129 130 133 134 136 138 157 159 161 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report List of Tables Table Page. Title Number Number Risk Factors: Estimated Decrease in Average Life Expectancy 1 10 Sample Codes and Collection Frequencies 2 30 Sample Collection Summary 3 31 Radiochemical Analyses Performed on REMP Samples 4 33 Air Monitoring Locations 5 39 Milk Monitoring Location 6 44 Groundwater Monitoring Locations 7 '46 Broadleaf Vegetation and Fruit Locations 8 47 Soil Locations 9 49 Treated Surface Water Locations 10 55 Untreated Surface Water Locations 11 58 Shoreline Sediment Locations 12* 59 Fish Locations 13 61 Thermoluminescent Dosimeter Locations 14 67 Gaseous Effluents

-Summation of All Releases 15 89 Gaseous Effluents

-Ground Level Releases -Batch Mode 16 90 Gaseous Effluents

-Ground Level Releases -Continuous Mode 16 91 Ground Level Releases -LLDs for Coittinuous and Batch Mode 16 92 Gaseous Effluents

-Mixed Mode Releases -Batch Mode 17 93 Gaseous Effluents

-Mixed Mode Releases -Continuous Mode 17 94 LLDs fo:r Gaseous Effluents

-Mixed Mode Releases 17 95 Liquid Effluents

-Summation of All Releases 18 96 '--Liquid Effluents

-Nuclides Released in Batch Releases 19 97 iv Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Liquid Effluents

-Nuclides Released in Continuous Releases Liquid Effluents

-LLDs for Nuclides Released Liquid Effluents

-Solid Waste and Irradiated Fuel Shipments 2015 Groundwater Tritium Results Doses Due to Gaseous Releases for January through December 2015 Doses Due to Liquid Releases for January through December 2015 Annual Dose to the Most Exposed (from all pathways)

Member of the Public 2015 Closest Exposure Pathways Present in 2015 Pathway Locations and Corresponding Atmospheric Dispersion CXJQ) and Deposition (D/Q) Parameters Summary of Meteorological Data Recovery for 2015 Summary of Meteorological Data Measured for 2015 Joint Frequency Distribution by Stability Class v Table Number 19 19 20 21 22 23 24 25 26 27 28 29 Page Number 99 100 101 104 105 107 107 111 113 119 120 125 Davis-Besse Nuclear Power Station 2015 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 2015 Airborne Gross Beta 10 38 Air Sample Site Map 11 40 Air Samples 5-rnile Map 12 41 Air Sample 25-mile Map 13 42 Gross Beta Groundwater 1982-2015 14 45 -Cs-137 in Soil 1972-2015 15 48 Terrestrial Site Map 16 50 Terrestrial 5-mile Map 17 Terrestrial 25-rnile Map 18 52 Gross Beta in Treated Surface Water 1972-2015 19 54 Gross Beta Concentration in Untreated Surface Water 1977-2015 20 57 Gross Beta in Fish 1972-2015 21 60 Aquatic Site Map 22 62 Aquatic 5-rnile Map 23 63 Aquatic 25-rnile Map 24 64 Gamma Dose for Environmental TLDs 1973 2015 25 66 TLD Site Map 26 73 TLD 5-rnile Map 27 74 ,TLD 25-rnile Map 28 75 Exposure Pathways 29 82 vi Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Figure Page Description Number Number Davis-Besse Onsite Groundwater Monitoring H-3 Trends 30 105 Land Use Census Map 31 110 Wind Rose Annual Average 1 OOM 32 122 Wind Rose Annual Average 75M 33 123 Wind Rose Annual Average 1 OM 34 124 vii ( I Davis-Besse Nuclear Power Station 2015 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 vis-Besse) from January 1 through December 31, 2015. This report meets all of the requirements in NRC Regulatory Guide 4.8, Section 5.6 of Davis-Besse Technical Specifications, and Besse Offsite Dose Calculation Manual (ODCM) Section 7.1. Reports included are the logical 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, ical Waste Management, and Waste Minimization and Recycling.

Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is established to monitor the diological condition of the environment around Davis-Besse.

The REMP is conducted in cordance with NRC Regulatory Guide 4.8, Davis-Besse Technical Specifications, and the Besse ODCM, Section 6.0. This program includes the sampling and analysis of environmental samples and evaluation of the effects of releases of radioactivity on the environment.

Radiation levels and radioactivity have been monitored within a 25-mile radius around 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 tion and radioactivity normally present in the area as natural background.

Davis-Besse has tinued to monitor the environment by sampling air, groundwater, milk, fruit and vegetables, drinking water, surface water, fish, shoreline sediment, and by direct 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 further away from the Station and are expected to indicate the presence of only naturally occurring oactivity.

The results obtained from the.samples collected from indicator locations are compared with the results from those collected from control locations and with the concentrations present in the environment before Davis-Besse became operational.

This a119ws for the assessment of any impact the operation of Davis-Besse might have had on the surrounding environment.

Approximately 2,000 radiological environmental samples were collected and analyzed in 2015. 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 activity is attributed to the operation of Davis-Besse.

viii Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report The sampling results are divided into four sections:

atmospheric monitoring, terrestrial ing, aquatic monitoring and direct radiation monitoring.

Air samples are continuously collected 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 2015 indicator results were in close agreement with the samples collected at control locations.

Terrestrial monitoring includes analysis of milk, groundwater, meat, fruits, vegetables, and soil samples. Samples are collected onsite and up to twenty-five miles away, depending on the type of sample. Results of terrestrial sample analyses indicate concentrations of radioactivity 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 (Treated Surface ter), Untreated Surface Water, fish and shoreline sediments collected onsite and in the vicinity of Lake Erie. Tritium was detected at two locations with concentrations slightly over the detection limit of 330 pCi/l, the highest being 721 pCi/L in Untreated Surface Water samples during 2015. The 2015 results of analysis for fish, treated surface water and shoreline sediment indicate mal background concentration of radionuclides and show no increase or build-up of radioactivity due to the operation of Davis-Besse.

Direct radiation averaged 14.5 mrem/91 days at indicator locations and 17.5 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 2015. The operation of Davis-Besse in 2015 caused no significant increase in the concentrations of dionuclides or adverse effects on the quality of the environment surrounding the plant. 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 2015 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 formed as part of the REMP. During the census, Station personnel travel every public road in a radius of five miles of Davis-Besse to locate radiological exposure pathways (e.g., residences, 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 2015 was a garden in the Southwest sector 0.73 miles from Davis-Besse, this is a change from 2014. 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, 2015. The doses due to radioactivity released during this period were only a fraction of allowable per our operating license. 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 setin the ODCM. ix Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Unplanned Releases There were no unplanned releases of liquid or gaseous radioactivity from Davis-Besse during 2015. Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP) There were two revisions of the ODCM in 2015. The changes included the abandonment of RE8433 Station Effluent radiation monitor. Results of the 2014 Land Use Census were also dated. There were no revisions of the PCP during 2015. Groundwater Protection Initiative (NEI 07-07) Davis-Besse began sampling wells near the plant in 2007 as part of an industry-wide Groundwater Protection Initiative (GPI), which was established to ensure that there are no inadvertent releases of radioactivity from the plant which could affect offsite groundwater supplies.

In addition to several existing pre-construction era wells, sixteen new GPI ing 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. In January, seven out of ten wells indicated tritium concentrations of greater than 2000 pCi/L requiring courtesy notifications to local, county, and state officials.

Increased sampling frequency on selected wells was implemented in an attempt to identify the source of the groundwater contamination.

Based on the completion of a systematic evaluation of the identified potential leakage sources, The conclusion of the problem solving team was that the most probable cause was due to construction activities surrounding the removal of the Primary Water Storage Tank. Since the initial identification of elevated concentrations, well sampling results have indicated a decreasing trend over the year, indicating that the cause is intermittent and no longer active. In the area of highest concentrations, the concentration has decreased from 10,527 pCi/L in February to 2,866 pCi/L in December 2015 with the highest concentrations detected in the western wells within the Protected Area. The assumptions regarding groundwater flow and modeling remain valid that the flow does not impact areas outside the Owner Controlled Area and essentially discharges into the Intake Canal. There is no evidence that the tritium traved offsite or contributed to offsite dose. Additionally, the groundwater tritium sample results remain below the 30,000 pCi/L EPA limit described in the Davis-Besse Offsite Dose Calculation Manual for non-drinking water sources. 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 x Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 quirements Manual was 97.69 % in 2015. 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.

More than thirty 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 tion liquid effluents back to Lake Erie. There were two National Pollutant Discharge Elimination System permit violations in 2015. On October 2, 2015 Total Residual Oxidants (TRO) measured 0.19 parts per million (PPM) at Outfall 001. This concentration exceeded the permit limitation of 0.05 PPM. On December 17, 2015 Total Residual Chlorine (TRC) measured 0.29 PPM at Outfall 001. This concentration exceeded the permit limitation of 0.2 ppm. In both instances, the Station Chlorination System was isolated until chlorine concentration was restored to below permit tations. Chemical Waste Management The Chemical Waste Management Program at Davis-Besse was developed to ensure that the offsite disposal of non-radioactive hazardous and nonhazardous chemical wastes is performed in accordance with all applicable state and federal regulations.

Chemical waste disposal vendors contracted by Davis-Besse use advanced technology for offsite disposal, including recycling of chemical wastes, in order to protect human health and the environment.

In 2015, the Besse Nuclear Power Station generated approximately 4,166 pounds of hazardous waste. hazardous wastes generated include 1,329 gallons of used oil and 21,488 pounds of hazardous waste such as oil filters, resins and caulk, latex paints, and grout. As required by perfund Amendment and Reauthorization Act (SARA), Davis-Besse reported hazardous products and chemicals to local fire departments and local and state planning commissions.

As part of the program to remove PCB fluid from Davis-Besse, all electrical transformers have been retro-filled and reclassified as non-PCB transformers.

Waste Minimization and Recycling The Waste Minimization and Recycling Program at Davis-Besse began in 1991 with the 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 ically exceeds 50 tons annually.

The scrap metal collected onsite is sold to scrap companies.

xi Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Appendices Appendix A contains results from the Inter-laboratory Comparison Program required by the vis-Besse ODCM. Samples with known concentrations of radioisotopes are prepared by the vironmental 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 analyze 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 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 tions are also provided.

Appendix C contains supplemental analyses of a Toft' s Dairy milk control sample. Appendix D provides a REMP sampling summary from 2015. 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 (LLD)

• mean and range of results for control and indicator locations

• 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 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 11, 2016). xii Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Introduction Coal, oil, natural gas and hydropower are used to run this nation's electric generating stations; 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. 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 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 bf this unique source of energy, background 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 scribed, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, tively (Figure 1). The relatively large tons and neutrons are packed tightly gether in a cluster at the center of the atom called the nucleus. Orbiting around the 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 ling each other, and prevent the nucleus from breaking apart. 1 , 'I Q P!IOTON 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.

Davis-Besse NJ,lclear Power Station 2015 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. ever, the number of neutrons in the nucleus of an element may vary. Atoms with the same 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 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. 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 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. izing radiation consists of both electromagnetic radiation and particulate radiation. 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 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 sion of ionizing radiation.

Radioactive atonis may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several 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, 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 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 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 2015 Annual Radiological Environmental Operating Report This example is part of a known radioactive decay series, called the Uranium series, which gins with Uranium-238 and ends with Lead-206 (Figure 2). 238LJ 234LJ 4.5x10 9 Yr 2.5x10 5 Yr i 2a4pa i 1.2 min 234Th 2s0Th 24d 8.0 x 1 b 4 Yr i 22sRa 1600 Yr i 222Rn 3.82d i 21ap 0 3.05 min i 214Bi 19.7 min 214pb 26.8 min Figure 2: Principal Decay Scheme of the Uranium Series. Half-life 214p 0 1.6 x 10 4 s i 210pb 23 Yr Beta Decay Alpha Decay 210Bi 5.01 d 210p 0 138.4 d 206pb stable Most radio-nuclides 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 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 2015 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 om at speeds ranging from 2,000 to 20,000 miles per second. However, due to its comparatively large size, an alpha particle usually does not travel very far before it loses most of its energy through collisions and interactions with other atoms. As a result, a sheet of paper or a few timeters 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 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. o:> ,. f\ADIOACTIVE -MATERIAL 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, 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 interaction!i, 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 ma 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 sity. 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 2015 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 c;_harge, 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 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 vis-Besse, concrete is used to form an effective neutron shield because it contains water 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 fects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent.

Activity:

Curie ! Activity is the numqer of atoms in a sample that disintegrate (decay) per unit of tin;ie. 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 (I/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 samples .. For instance, the microcurie (uCi) is equal to one millionth of a curie, while the picocurie (pCi) represents one trillionth of a curie. 5 Davis-Besse Nuclear Power Station 2015 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, 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 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 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 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 millirem, is often used. One millirem (mrem) is equal to 1/1,000 of a rem. Deep Dose Equivalent (DDE) 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 terial taken into the body. It is calculated from the sum of the products of the committed dose 6 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report equivalent to the organ or tissue multiplied by the organ or tissue-weighting factor. CEDE counts for all the dose delivered during the entire time the radioactive m.aterial 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 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 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 ground radiation to which we are all exposed. The earth is being showered by a steady stream of high-energy gamma rays and particulate 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. dionuclides commonly found in the atmosphere as a result of cosmic ray interactions include ryllium-7, Carbon-14, tritium (H-3), and Sodium-22.

Another common naturally occurring raqionuclide is Potassium-40.

About one-third of the 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 um 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 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 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 Health Physics Society, University of Michigan, more than half of the radiation dose the average American receives is attributed to Radon. 7 Davi s-Besse Nuclear Power Station 2015 Annual Radiolo g ical Environmental Operating Report Sources of Radiation Exposure to the US Population Nuclear Medicine 4/. Medi c al X-rays 11 /. Intern a l 11 /. Cosmic 8/. Con s umer Products 3/. Other < 1 /. Radon 54/. Figure 4: The mo st 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 (taken from the Health Physics Society , University of Michigan , 2013). Further information on Radon , its measurement, and actions to reduce the Radon concentration in building s can be obtained by contacting the state Radon program office at the following dre ss: Ohio Department of Health, Bureau of Environmental Health 246 North High Street Columbus, Ohio 43215 (614) 644-272 7 (614) 466-0381 FAX The approximate average background radiation in this area i s 620 mrem/year (Princeton sity, 2013). Man-made Radiation In addition to naturally occurring cosmic radiation and radiation from naturally occurring radioactivity, people are also exposed to man-made radiation.

The largest sources of exposure include medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer product s suc h as televisions , smok e detector s, and fertilizers.

Fallout from nuclear weapons tests is a nother so urce of man-made exposure.

Fallout radionuclides include Strontium-90, 8 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Cesium-137, and tritium. Less than one percent of the annual dose a member of the public 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. 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, 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 dividual health effects of low level radiation.

Even though no effects have been observed at es 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 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 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 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 oc,cur. Spontaneous mutations and chemically induced mutations also have been observed.

These mutated genes may be passed 9 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 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 sessment of the risks, and on placing these risks in perspective.

The perceptions of risk associat-,ed 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 causing substances.

These risks are larger and measurable compared to those presumed to be sociated with exposure to low level, low dose radiation.

Most of these risks are with us 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%: Cigarette smoking: Heart Disease: Cancer: City living (non-rural):

All operating commercial nuclear power plants totaled: 1 pack/day 2 packs/day

3.6 years

7.0 years 10.0 years 5.8 years 2.7 years 5.0 years less than 12 minutes IO Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Benefits of Nuclear Power Nuclear power plays an important part in today's electricity needs, and will continue to serve as an important source of electric energy well into the future. Today more than twenty 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 1958, 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 ar 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, ter is turned into steam. In a nuclear station, a reactor that contains a core of nuclear fuel, ily uranium, replaces the furnace. Heat is produced when the atoms of Uranium are split inside the reactor. The process of splitting atoms is called fission. 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. 11 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 cpmmon to all fossil fuels. Since a single small reactor fuel pellet contains trillions of atoms, each pellet can release an extremely large amount of gy. 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 occurrence's 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 cess by severaf 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 sion easily,

• slowing down neutrons 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. 12 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report After the Uranium ore is separated from the earth and rock, it is concentrated in a milling cess. After milling the ore to a granular form and dissolving out the Uranium with acid, the nium is converted to Uranium hexafluoride (UF6). UF6 is a chemical form of Uranium that exists as a gas at tel,llperatures slightly above room temperature.

The UF6 is then highly purified and shipped to an enrichment facility where gaseous diffusiOn converters increase the . tration of U-235. The enriched gaseous UF6 is then converted into powdered Uranium dioxide (U02), a highly stable ceramic material.

The U02 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 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 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 Yz inches thick. Futtl Rod ..... ...... REAClOR VESSEi.. Figure 6: The at Besse contains 177 fuel assemblies.

Each 208 . Each fuel rod rs filled with approximately five pounds of fuel pellets. Each pellet rs approximately 3/8 mch diameter and 5/8 inch long. 13 /

Davis-Besse Nuclear Power Station 2015 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, fudium, and Cadmium metals that absorb-free neutrons, thus disrupting the fission chain reaction.

When control rod assemblies are slowly withdrawn from the core, The fission process begins and heat is produced.

If the control rod semblies are inserted rapidly into the -reactor core, as occurs during a plant "trip", the chain tion ceases. A slower acting (but more evenly distributed)'

method of fission control is achieved by the addition of a neutron poison to the reactor coolant water. At Davis-Besse, high-purity boric acid is concentrated or diluted in the coolant to achieve the desired level of fission. Boron-10 readily absorbs free neutrons, forming Boron-11, removing the absorbed neutrons from the chain reaction.

Reactor Types Virtually all of the commercial reactors in this country are either boiling water reactors (BWRs) or pressurized water reactors (PWRs). Both types are also called light water 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 tors, which remove water droplets.

The steam then travels to dryers before-entering the turbfoe. 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 ary water supply. The water inside the steam generator boils into steam, which is then used to tum the turbine. This steam is then condensed back into water and returned to the steam generator.

Davis-Besse uses a PWR design. The following paragraphs describe the various systems illustrated in Figure 7. Major systems in the Davis-Besse Station are assigned a different color in the figure. 14

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CONTAINMENT COOLING TOWER TURBINE BUILDING 0

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Davis-Besse Nuclear Power Station 2015 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 reinforced concrete walls 30 inches 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 radi-oactive 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 ferred to the steam generator in order to provide the steam necessary to drive the turbine. 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 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 actor where it is again heated to 606°F as it passes up through the fuel assemblies.

Under 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 inch (psi) at all times. This prevents the water from boiling and is the reason the reactor at vis-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 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. 16 Davis-Besse Nuclear Power Station 2015 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 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 ll;Se 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 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 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 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 late 480,000 gallons of water per minute to the tower. purpose is to recycle water from the Condenser by cooling and returning it. 17 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report

• After passing through the Condenser, the Circulating Water has warmed to approximately 100°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 through evaporation via the Cooling Tower. Even so, approximately 98 percent of the water drawn from Lake Erie for station operation can be recycled through the Cooling Tower for reuse. A small portion of the Circulating Water is discharged back to Lake Erie at essentially the same temperature it was withdrawn earlier. The slightly warmer water has no measureable adverse environmental impact on the area of lake surrounding 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. ing on the severity of the loss of pressure inside the Primary System, the ECCS will ly 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 tem. The violet system illustrated in Figure 7 is r,esponsible for maintaining the Primary Coolant water in a liquid state. It accomplishes this by adjusting the pressure inside the Primary System. ers inside the Pressurizer tum water into steam. This steam takes up more space inside the 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.

18 Davis-Besse Nuclear Power Station 2015 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. Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features.

If one 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 tion of the control rods. The Reactor can be automatically shut down by a separate Reactor 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 ter into reactor automatically if the reactor coolant pressure drops below a predetermined el. The Davis-Besse Nuclear Power Station was designed, constructed, and is operated to produce a reliable, safe, and environmentally sound source of electricity.

Radioactive Waste Many of the 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 ment. With the exception of used nuclear fuel assemblies, these by-products produced at mercial power plants are referred to as low level radioactive waste. Low Level Radioactive Waste Low level radioactive waste consists of ordinary trash and other items that have become inated with radioactive and can include 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 as rally-occurring radioactive materials.

Most low level activity in radioactive waste decay to ground 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 Barnwell, South Carolina for cessing, after which it is shipped to Utah for disposal.

Davis-Besse has the capacity to store level waste produced on site for several years in the Low Level Radioactive Waste Storage ity, should this facility close. Davis-Besse added the Old Steam Generator Storage Facility (OSGSF) in 2011 to house the actor Vessel _Closure Head, Service Support Structure and Control Rod Drive mechanisms moved during the 17M outage. Two Steam Generators and two Reactor Coolant System Hot Leg 19 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report piping sections were replaced during 18th Refueling Outage (18RFO) in 2014, and are also stored there. The reinforced concrete building is comprised of three sections, the largest of which contains the old steam generators and hot legs. The old reactor vessel head is kept in other bay. The sections of the building are completely enclosed with concrete for shielding.

The dose rates outside the walls of this section are at background levels. The third section is the tibule, which provides access to the other two sections.

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. High Level Nuclear Waste Like any industrial or scientific process, nuclear energy does produce waste. The most 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 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 ly. Also, nuclear waste slowly loses its radioactivity, but some chemical waste remains ous indefinitely.

Davis-Besse presently stores most of its used fuel in a steel-lined water-filled concrete vault 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 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, ia, Wisconsin and South Carolina, to name a few. Figure 8 below illustrates the Dry Fuel age 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 dqring the initial 40 years of expected life. This modification was completed in April of 2002. 20 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Figure 8: Dry Fuel Storage Module Arrangement 21 Davis-Besse Nuclear Power Station 2015 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 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. \ Lake .Erie Figure 9: Davis-Besse is near Oak Harbor, Port Clinton, and the Ottawa National Wildlife Refuge. The Davis-Besse site is mainly comprised of freshwater marsh land, with a small portion ing of farmland.

The marshes are part of a valuable ecological resource, providing a breeding ground for a variety of wildlife and a refuge for migratory birds. The site includes a tract known as Navarre Marsh, which was acquired from the U.S. Bureau of Sport Fisheries and Wildlife, Department of the Interior.

In 1971, Toledo Edison purchased the 188 acre Toussaint River Marsh. The Toussaint River Marsh is contiguous with the 610 acre Navarre Marsh section of the Ottawa National Wildlife Refuge. 22 I Davis-Besse Nuclear Power Station 2015 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 6,056

• Oak Harbor -7 miles south, population 2,759

• Rocky Ridge -7 miles west southwest, population 417

• Toledo (nearest major city) -25 miles west, population 287,208 There are some residences along the lakeshore used mainly as summer homes. However, the 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, com, 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 cated in Erie Industrial Park, about four miles southeast of the station. Most of the remaining marshes in the area have been maintained by private hunting clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife.

The State of Ohio Department of Natural Resources operates many wildlife and 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 is a wooded area at the southern end of Magee Marsh, which offers boating and fishing. Crane Creek is adjacent to Magee Marsh, and is a popular bird watching and hunting area. The Ottawa National Wildlife Refuge, which is ated by the U.S. Fish and Wildlife Service, lies four to nine miles WNW of the Site, immediately west of Magee Marsh. 23 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report References

1. "Basic Radiation Protection Criteria," Report No. 39, National Council on Radiation 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 diation," Report No. 94, National Council on Radiation Protection and Measurements, 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 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. XVID, 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, 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 2015 Annual Radiological Environmental Operating Report \ 14. "Nuclear Energy Emerges from 1980s 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. 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. ly 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, Fernald Environmental Management Project, United States partment of Energy (June 1993). 25. "Exposure from the Uranium Series with Emphasis on Radon and its Daughters" Report No. 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 ments, Washington, D.C. (1984). 25 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at 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 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. lection of sample types is based on the established critical pathways for the transfer of clides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population 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 Program The federal government requires nuclear facilities to conduct radiological environmental toring prior to constructing the facility.

This pre-operational surveillance program is for the lection of data needed to identify critical pathways, including selection of radioisotope and sample media combinations for the surveillance conducted after facility operations begin. ochemical analyses performed on samples should include nuclides that are expected to be 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 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 quencies and locations, collection techniques and radiochemical analyses performed, should be 26 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report carefully considered and incorporated in the design of the operational surveillance program. In this manner, data can be compared in a variety of ways (for example: from year to year, location to location, etc.) in order to detect any radiological impact the facility has on the surrounding vironment.

Data collection during the pre-operational phase should be planned to provide a comprehensive 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 u§e 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 economic viability and commissioning 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 tion's Technical Specifications and Offsite Dose Calculation Manual

• to determine whether any significant increase in the concentration of clides in critical pathways occurs

• to identify and evaluate the buildup, if any, of radionuclides in the local ronment, or any changes in normal background radiation levels

• to verify adequacy of Station controls for the release of radioactive 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 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 sis followed by a comparison of results 27 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report

• splitting samples prior to analysis by independent laboratories, and then paring the results for agreement

• 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 ty 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 ty of the laboratories' analytical procedures and data generated.

In 1987, environmental sampling personnyl at Davis-Besse incorporated their own QA 'program into the REMP. Duplicate samples, called quality control samples, were collected at several cations. These duplicate samples were assigned different identification numbers than the 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 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 and soil

• aquatic --including samples of treated and untreated surface water, fish, and shoreline sediments

• direct radiation

--measured by thermoluminescent dosimeters All environmental samples are labeled using a sampling code. Table 2 provides the sample codes and collection frequency for each sample type. . REMP samples are collected onsite and offsite up to 25 miles away from the Station. Sampling locations may be divided into two general categories:

indicator and control. Indicator locations 28 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report are those which would be most likely to display the effects caused by the operation of Besse, and are located within five miles of the station. Control locations are those which should 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 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 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 ronmental samples. These additional samples are referred to as the REMP Enhancement ples. Approximately 2,000 samples were collected and over 2,300 analyses were performed during 2015. 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. 29 Davis"Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report -', Table 2: Sample Codes *and Collection Frequencies Sample Collection Sample Type Code Frequency Airborne Particulate AP Weekly Ail-borne Iodine AI Weekly Thennoluminescent TLD Quarterly, Annually Dosimeter Milk MIL Monthly (semi-monthly during grazing season) Groundwater WW Quarterly (when available)

Broadleaf Vegetation BLV Monthly (when Surface Water -Treated SWT Weekly Surface Water -swu Weekly Untreated Fish FIS Annually Shoreline Sediment SED Semiannually Soil SOI Annually Fruit FRU Annually 30 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 3: Sample Collection Summary Sample Collection Number of Number of Number of Type Type*/ Locations Samples Samples (Remarks)

Frequency**

Collected Missed Atmospheric Airborne Particulates C/W 10 520 0 Airborne Radioiodine C/W 10 520 0 Terrestrial Milk (Jan.-Dec.)

G/M 1 12 0 Groundwater GIQ** 3 8 0 Broadleaf Vegetation G/M 3 8 0 Fruit GIA 3 3 0 Soil GIA 10 10 0 Aquatic Treated Comp/WM 3 156 0 Surface Water G/WM*** 1 51 1 Untreated G/WM*** 2 104 0 Surface Water Comp/WM 3 156 0 Fish (3 species) GIA 2 6 0 Shoreline Sediments GISA 5 8 0 Direct Radiation Thermoluminescent CIQ 88 350 2 Dosimeters (TLD) CIA 88 86 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 ***Includes quality control location.

SWU and SWT QC included in weekly grab sample/composited monthly Number of samples is the product oflocations times frequency.

Except for groundwater, broadleaf vegetation, fish. These are the number of samples available.

31 Davis-Besse Nuclear Power Station 2015 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 decay gives a continuous energy spectrum rather than the discrete lines or "peaks" associated with gamma radiation, identification 1 of specific beta emitting nuclides is much more difficult.

Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal tions of beta emitting radionuclides; it.does not identify specific radionuclides.

Gross beta sis merely acts as a tool to identify samples that may require further analysis .. Gamma spectral analysis provides more specific information than gross beta analysi$.

Gamma spectral analysis identifies each gamma emitting radionuclide present in the sample, and the amount of each nuclide present. Each radionuclide has a very specific "fingerprint" that allows for swift and accurate identification.

For example, gamma spectral analysis can be used to tify the presence and amount of lodine-131 in a sample. Iodine-131 is a man-made radioactive isotope of Iodine that may be present in the environment as a result of fallout from nuclear ons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power tions. 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 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 environmen-. tal 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 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.

/ 32 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples Sample Type Atmospheric Monitoring Airborne Particulate Airborne Radioiodine Terrestrial Monitoring Milk Groundwater Broadleaf Vegetation and Fruits Soil Analyses Performed Gross Beta Gamma Spectroscopy Strontium-89 Strontium-90 Iodine-131 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 33 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples (continued)

Sample Type Aquatic monitoring Untreated Surface Water Treated Surface Water Fish Shoreline Sediment Direct Radiation Monitoring Thermoluminescent Dosimeters Sample History Comparison Analyses Performed 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 Gamma Dose 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 er years. Generally, the results of sample analyses are compared with pre-operational and tional 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 ed to determine whether it is attributable to the operation of Davis-Besse, or to some other source such as nuclear weapons testing. 34 Davis-Besse Nuclear Power Station 2015 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 'Yeapons testing 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 at all ten air sample locations over a four-week period between March 22 and April 12, 2011 following the Fukushima Daiichi Nuclear Station disaster in Japan. There was virtually no difference in Iodine-131 concentration at control and tor locations during this period. Terrestrial Monitoring:

• Groundwater:

Tritium was not detected above the lower limit of detection during 2015 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.

Iodine was not detected in REMP milk samples following the shima Daiichi Nuclear Station disaster in 2011. No lodine-131 detected in any REMP samples was attributable to the operation of Davis-Besse.

'

• 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 Chernobyl 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.

Tritium was detected at two locations with concentrations slightly over the detection limit of 330 pCi/L, the hightest being 721 pCi/L in Untreated Surface Water samples during 2015.

• Fish: Only natural background radioactive material was detected.

• Shoreline Sediments:

Only natural background radiation, material from nuclear testing and the 1986 nuclear accident at Chernobyl have been detected.

35 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Direct Radiation Monitoring

• Thermoluminescent Dosimeters (TLDs): The annual gamma TLD dose rates for the current reporting period averaged 56.2 millirem/year at Indicator locations, and 63.8 millirem/year at Control locations.

No increase above natural background radiation tributable to the operation of Davis-Besse has been observed.

2015 Program Anomalies There has been elevated Gross Beta results at the T-i 1 Ottawa County Regional Water Intake Facility.

This is not attributed to normal power plant operations as indicated by T-3 Site ry, near mouth of Toussaint River sample point indicating normal gross beta results. The elevated results at T-11 were verified to be potassium by ICP analysis.

This potassium may be attributed to fertilizer runoff into the mouth of the Portage River which is located near the T-11 sample point. Gross Beta is not a reportable radioactivity concentration per the ODCM. The Site Boundary, ESE of the station did not indicate any anomalous Gross Beta results. This would. indicate that the DBNPS is not the source of the elevated Gross Beta results at the Ottawa, County facility.

All REMP samples were collected.

Abnormal Releases There were no abnormal liquid or gaseous releases occurring during 2015. 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 sorirce. Inhaled radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air ples collected by the Davis-Besse REMP include airborne particulate and airborne 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 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.

/ 36 D avis-B esse ucl ea r P ower St a tion 2015 Annual R adiologica l Environmental Op erati ng Rep o rt 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 i s performed on each of the weekly sa mple s. Each quarter , the filters from each location are combined (composite) and analyzed for gammaemitting radionuclides, Strontium-89 and Strontium-90.

Beta-emitting radionuclides were tected at an average concentration of 0.028 pCi/m 3 at both indicator and control location s. lium-7 was the only gamma-emitting radionuclide detected by the gamma s pectro s copic analysis of the quarterly compo s ite s. 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 verse change in radioactivity in air samples attributable to the operation of the Davi s-Bes se clear Power Station in 2015. 37

... 0 Q. Davi s-Be s se Nuclear Power Station 2015 Annual Radiol og ical Environmental Operating R e port Airborne Iodine-131 Airborne Iodine-131 samples are collected at the same ten location s a s the airborne particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly , sealed in s eparate collection bags and sent to the laboratory for gamma analy s is. 2015 Ai r borne Gross Beta 0.045 0.04 0.035 0.03 0.025 0.02 Ja n. Feb. M a r. Apri l May Ju ne Ju ly Aug. Sep t. Oct. av. Mom h I --+-Cootrol -+-Ind i cator I Figure 10. Concentration s of beta-emitting radionuclide s in airborne particulate s amples were nearly identical a t indicator and control location s during 2015. 38 De c_

Davi s-B esse Nuclear Power Station 2015 Annual Radiolo g ical Environmental Operating R e port Table 5: Air Monitoring Locations Sample Location Type of Number Location T-1

• I T-2* I T-3* I T-4 I T-7* I T-8 I T-9 c T-11

• c T-12 c T-27 c I= Indicator C = Control *denote s ODCM-required sam ple Location Description Site boundary, 0.6 miles ENE of Station Site boundary , 0.9 mile s E of Station Site boundary , 1.4 miles ESE of Station Site boundary, 0.8 mile s S of Station Sand Beach , main entrance, 0.9 miles NW of St a tion Earl Moore Farm, 2.7 miles WSW o f Station Oak Harbor Substation , 6.8 mile s SW of Station Port Clinton Water Treatment Plant , 9 .5 miles SE of Station Toledo Water Tr eatme nt Pl ant, 20.7 miles WNW of Station Crane Creek , 5.3 miles WNW of Station 39 DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AIR SAMPLES: SITE ' NW ' NNW N ' ' I ' I ' I I ' I I ' 0 0 ' I , < I , (/J I , I CD I # CD (/J (/J CD I I z I I c 0 , iD , , , 0 , , I , , , , -u I , 0 ---CD ---, ------V> -., .+ 0 ID w c 0 ' E :::J CD N 0 ---U1 ------l> l> ---:::J ---:::J ' ---c -"' ... 0 ... ---0 V> ---... ---:0 ... ---... 0 "O ' ... Q_ CD ' ... ... 0 ' ... I (/l I 0 ID -+ ESE I 0 CD I 0 :;:::: INDICATOR STATIONS I 0 I , '4J rri "O -.J :::J I ... < ... ' ... , A IR S A t.f>LE ... I.., 0 ... :::J ... I ... , 3 ... CD ... :::J ... , .+ ... 0 I ... , , I ... SW , 0 "O CD , , , , ' 0 , ' SE , .+ , ... I ' , ... , l :::J ' ID I ' , , :0 ' , CD , "O ' , 0 , , .+ DB' 04-02-16 DFN*F*/SCHEO/SK2817.0GN WNW ... . .. w .,, -'° c ' (1) N l> =i" .bo (/) u (1) en U1 ' 3 -(1) :;::: WSW 0 u D A V IS-BES S E NUCLEAR POWER STATION RADIOLOGICAL ENV I RONMENTAL MON IT ORING PROGRAM *****: .... . ci ci : er er ::r: .u .111 . er * <[ :o .. *. C r eek ...J ...J 0 er $*. er * .. j .. w er <[ .f * .... SW er 0 a.. B I ER *.RD( CARROLL z <[ ::::;; ...J INDICATOR STATIONS I w ID ' A I R SA lif>L E ci *****: w '-' z ::; a.. <[

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Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Terrestrial Monitoring The collection and analysis of groundwater, milk, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. The data from soil pling provides information on the deposition of radionuclides from the atmosphere.

Many radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. Some of the radionuclides present are:

• Tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere and as a result of routine release from nuclear facilities

• B eryllium-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 clear weapons testing and routine releases from nuclear facilities

• Potassium-40, a naturally occurring radionuclide normally found out the environment (including in the human body)

• Fallout ra di on u clides 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, erational data from previous years, control location data, and the types and amounts of 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 es onto forage consumed by cows. The radionuclides present in the forage-eating cow are porated 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 sampled monthly in order to gather additional baseline data. If dairy animals are discovered 43 Davi s-Be sse Nuclear Power Station 2015 Annual R a diological Environmental Operatin g Report within five miles of the station, efforts will be made to include them in the milk sampling gram as indicator sites. The 2015 milk samples were analyzed for Strontium-89, Strontium-90, Iodine-131, other ma-emitting radionuclides , stable Calcium and Potassium.

A total of 12 milk samples were lected in 2015. Strontium-89 was not detected above its LLD of 0.6 pCi/l. The annual average concentration of Strontium-90 was 0.7 pCi/l. The annual average concentration was similar to those measured in previou s years. Iodine-131 was not detected in any of the milk sa mple above the LLD of 0.5 pCi/l. The trations of Barium-140 and Cesium-137 were below their respective LLDs in all samples collected. Since the chemistries of Calcium and Strontium are similar, as are Potassium and Cesium, 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/l) to the concentration of Calcium (g/l), and the Cesium tivity (pCi/l) compared to the concentration of Pota ss ium (g/l) were monitored in milk. These ratios are compared to standard values to determine if buildup is occurring.

No statistically nificant variations in the ratios were observed. Table 6: Milk Monitoring Location Sample Location Number T-24 C =Control Type of Location c Groundwater Samples Location Description Toft Dairy , Sandusky, 21.0 miles SE of Station Soil acts as a filter and an ion exchange medium for most radionuclides.

However , tritium and other radionuclides s uch as Ruthenium-I 06 ha ve a potential to seep through the soil and could reach groundwater.

Davis-Besse does not di sc harge its liquid effluents directly to the ground. REMP personnel sample local wells on a quarterly ba sis to ensure early detection of any adverse impact on the local groundwater supplies due to Station operation.

In addition , a quality control sample is collected when the wells are sampled. The groundwater samples are analyzed for emitting radionuclides, tritium, Strontium-89, Strontium-90 and gamma-emitting radionuclides.

During the fall of 1998, the Carroll Town s hip Water Plant began operation a nd offered residents a reliable, inexpensive source of high-qu ality drinking water. This facility ha s replaced all of the drinking water wells near Davi s-Be sse, as verified by the Ottawa County Health Department , and 44 Davis-Be sse Nuclear Power Station 2015 Annual Radiolo g ical Environmental Operating Report 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 3.5 pCi/l at Indicator sites and 1.8 pCi/l at the Control site, T-27 A. REMP Groundwater samples were not affected by the operation of the Davis-Besse Nuclear Power Station. Gross Beta Gro u nd Water 1 982-2015 u Q. 0 l8 al SJ gi 8 8 8 a N v <D (I) (I) (I) (I) (I) a a 0 0 0 0 0 0 0 N N N N N N N N N Year --I ndi cat or -tt-Contro l Figure 14: Shown above are the annual averages for gross beta in groundwater from 1982-2015. There were no cator sa mple s available in 2000 and no control sa mple s available in 2009. 45 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 7: Groundwater Monitoring Locations Sample Location Number T-27A T-225 T-226 C = control I = indicator Type of Location c I I Broadleaf Vegetation and Fruit Samples Location Description Crane Creek Long Beach and Park, 1.5 mi NW of Station Allen residence, 1.6 miles NW of Station 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 ter which receives liquid effluents (hospitals, nuclear facilities, etc.). Radionuclide s 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 ed from orchards in the vicinity of Da vis-Besse, and a control sample is collected, as well. In 2015, broadleaf vegetation samples were collected at two indicator locations (T-227 and T-19) and one control location (T-37). Fruit samp le s were collected at two indicator locations (T-8 and T-25) and one control location (T-209). Bro adleaf vegetation was collected once per month ing the growing season and consisted of cabbage. The fruit that was collected was apples. All samp le s were analyzed for gamma-emitting radionuclides, Strontium-89, Strontium-90, and dine-131.

Iodine-131 was not detected above the LLD of 0.022 pCi/g (wet) in any broadleaf vegetation nor above the LLD of 0.020 pCi/g (wet) in fruit samples. The only gamma-emitting radionuclide detected in the fruit and broadleaf vegetation samples was Pota ssi um-40 , which is naturally ring. Re sults 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 respective LLDs (0.004 and 0.001 pCi/l wet) in broadleaf vegetation samples at control and indicator locations.

Op erat ion of Davis-Besse had no observable adverse radiological effect on the surrounding environment in 2015. 46 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 8: Broadleaf Vegetation and Fruit Locations Sample Location Type of Number Location T-8 I T-19* I T-25 I T-37* c T-209 c I= indicator, C = control *denotes ODCM-required sample Soil Samples Location Description Moore Farm, 2.7 miles WSW of Station (F RU) L. Bowyer Jr., 1.0 mile W of Station (BLV) Witt Farm , 1.6 miles S of Station (FRU) Bench Farm, 13.0 miles SW of Station (BLV) Roving Control Fruit location (FRU) Soil samples are generally collected once a year adjacent to our ten continuous air samplers. ly the top layer of soil is sampled in an effort to identify possible trends in the local environmental nuclide concentration caused by atmospheric deposition of fallout and station-released radionuclides.

Generally, the sites are relatively undisturbed, so that the sample will be sentative of the actual deposition in the area. Ideally, there should be little or no vegetation sent, because the vegetation could affect the results of analyses.

Approximately five pounds of soil are taken from the top two inches at each site. Many naturally occurring radionuclides such as Beryllium-7 (Be-7), Potassium-40 (K-40) and fallout radionuclides from nuclear weapons ing are detected.

Fallout radionuclides that are often detected include Strontium-90 (Sr-90) and Cesium-137 (Cs-137).

Soil was collected at the ten sites in 2015. The indicator locations included T-1, T-2, T-3, T-4, T-7, and T-8. The control locations were T-9, T-11 , T-12 , and T-27. All soil samples were lyzed for gamma-emitting radionuclides.

The only gamma emitter detected (in addition to rally occurring Be-7 and K-40) was Cs-137. Cs-137 was found in Indicator and Control locations at average concentrations of 0.12 pCi/g (dry) and 0.09 pCi/g (dry), respectively.

The concentrations were similar to that observed in previous years. 47 E I! IOI ::. (.) Q, Da v i s-B esse ucl ear Po w er St a tion 2015 Annu al R a di o l og i ca l En v ironm e ntal Ope ra tin g Report Cs-137 i n Soil 1972-2015 1.2 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.0 N v <D CXl 0 N v <D CXl 0 N v <D CXl 0 N v <D CXl 0 N ..... ..... ..... ..... CXl CXl CXl CXl CXl O> O> Cl O> O> 0 0 0 0 0 --Year --I nd i cat o r --c on tro l Figure 15: The concentration of Cesium-137 in s oil has s teadily declined in recent years. The pe a k s een in 1978 wa s due to fallout from nuclear weapon s te s ting. 48 v CXl --

Davis-Be sse Nuclear Pow e r Station 2015 Annual Radiolo gica l Environmental Operating Report Sample Location Type of Number Location T-1 I T-2 I T-3 I T-4 I T-7 I T-8 I T-9 c T-11 c T-12 c T-27 c I = indicator C = control Table 9: Soil Locations 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 Sub statio n, 6.8 miles SW of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 20.7 mile s WNW of Station Crane Creek, 5.3 miles WNW of Station 49 NW ... ---,, '° w c ., ct> en -I ct> ., Ul ., 0 ct> (/) -+ ., 0 WSW (/l -+ ct> ; :;:: ; 0 ; "O ; SW I DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I ' I I ' ' ' ' I I ' ' ' ' ' NNW ' I I I I I I I I N I I I I I I I I I I I I I I I I I I I I TERRESTRIAL SAMPLES: SITE I # ---------------------... ... ------... ... ... ... ... ... ... ... ... INDICATOR STATIONS ... ... ... ... ... ... a SOIL ... I I ' ' ' ' ' SE ' ' ' E ------ESE ... ... ... ... I I ... I I I I ---I I ---I I I I 1 1-J -./ , ... DB* 04-02-1 6 DFN*F*/SCHED/SKZ817.0GN 0 0 < (/) 0 :J "' 0 ll1 )> :J :J c 0 ;o 0 0. 0 0 '° 0 0 rri :J < , 0 :J 3 ct> :J ..+ 0 0 "O ct> , 0 :J '° ;o ct> "O 0 , ..+

"Tl <D c ' (1) -..J -I (1) ' ' U1 (1) en -+ ' -0 U1 ' 3 -(1) :;:: 0 u DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM WNW w WSW . ci : o:: : I .u . Vl *O:: * <{ : a TERRESTRIAL SAMPLES: 5 MILE RADIUS ci 0:: ci 0:: RustXJ .

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• SOIL TERRESTRIAL SAMPLES: 5-25 MILE RADIUS .**¢ . .**"{> SE SSW DB: 04-0 2-16 DFN*F:/SCHED/SKZ815.DGN CJ 0 < (/) I Cll ro (/) (/) ro z c () (D 0 , "lJ 0 "' ro , Vl rl-0 rl-0 :::J N 0 Ul l> :::J :::J c 0 ::0 0 0. 0 0 '° () 0 rn :::J < , 0 :::J 3 ro :::J rl-0 0 "O ro , 0 rl--* :::J '° ::0 ro "O 0 , rl-Davi s-Be sse Nuclear Power Station 2015 Annual Radiological Environmental Operatin g Report -.. *"' 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 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, s horeline sediments and from immersion (swimming) in the water. Internal exposure can occur from ingestion of nuclides, 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 collects samples of 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 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 one indicator (T-22B) and two control tions (T-11 and T-12). These locations include the water treatment facilities for Carroll ship, Port Clinton and Toledo. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta-emitting radionuclides.

The sa mples were also posited in a quarterly sample and analyzed for Strontium-89 , Strontium-90, gamma-emitting dionuclides, and tritium. One QC sample was collected from a routine location , which changed each month. 53 5 4_5 4 3_5 3 5 2.5 0 a. 2 1.5 0 N ..... en -Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report The annual average of beta-emitting radionuclides for indicator and control location s was 2.3 and 2.6 pCi/l, respectively.

The se results are similar to previous years. Tritium was not detected above the LLD of 330 pCi/l during 2015. Strontium-89 was not detected above the LLD of 0.8 pCi/1. Strontium-90 activity was not detected above its LLD of 0.8 pCi/1. The se results are lar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse during 2015. 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. Gross Beta in Treated Surface Water 1972-2015

! CC> co 0 N

B :B N -a; co 8 N s 8 co S! N ..... ..... co co en (]) 0 0 -en en en en en (]) en en (]) 0 0 0 0 0 0 0 ---------N N N N N N N Year --I ndicator --control I Figure 19: Since 1974, the ann ual concentrations of beta emitting radionuclides in treated surface water samples collected from indicator locations have been consistent with those from control locations.

Da vis-Besse has had no measurable radiological impact on treated surface water used to make drinking water. 54 0 0 N N Davis-Be sse Nuclear Power Station 2015 Annual R a diological Environmental Operating Report Table 10: Treated Surface Water Locations Sample Location Number T-11

• T-12 T-22B* T-143 I = indicator C =control QC = qu a lit y control Type of Location c c I QC

• denotes ODCM-r eq uired sam ple Location Description 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, sa mpled at Davis-Besse REMP lab Quality Control Site 55 Davi s-Be sse Nuclear Power Station 2015 Annual Radiological Environmental Operatin g Report Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to humans from external exposure from the lake surface as well as 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 ter samples are collected from water intakes used by nearby water treatment plant s. Routine samples are collected at Port Clinton, Toledo and Carroll Township.

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. 56

.. D av i s-B esse N ucl ear P owe r S ta ti o n 2015 A nnu al R a di o l ogica l E n v i ro nm e nt a l Op era tin g R e p o rt Sample Results For the routine untreated s urface water s amples that a re composited weekly, the beta emitting radionuclides had an average concentration of 2.6 pCi/L at indicator locations during 2015. trol locations averaged 10.3 pCi/L during thi s period. Each month , weekl y compo s ited qualit y control s ample s of untreated w a ter were analyzed from different location s. The re s ult s of the T-11 control sa mple point located at the Ottawa County Regional Water Int a ke F a cility s tarted s ho wi ng ele va t e d Gro ss Bet a re s ul ts in Augu s t and ued through December.

Gro ss Beta in Untr e at e d Sur fa ce Water i s not a report a ble radioacti v it y concentration per the Off s ite Do s e Calculation M a nu a l. The ele v ated Gro ss Beta s ample result s were verified to be pota ss ium by ICP analy s i s. The pota ss ium ma y be attributed to fertilizer runoff into the Portage Ri v er which is near the T-11 sample point. The Site Boundary , ESE of the s tation did not indicate any anomalou s Gro ss Beta re s ult s. This would indicate that the DBNPS i s not the s ource o f the ele v ated Gro ss Beta re s ult s at the Ottawa County facility.

Gross Beta Concentration i n Untreated S u rface Water 1977-2015 0.0 ..... O> ;;; :a :;; a; l7l :;; 0 a t; -<") "' ..... ..... 0 0 0 0 0 0 0 0 N N N N N N N N Year I -+-Indicator

--contro l I Fi g ure 20: The ave rage concentration o f bet a-emittin g radionuclide s in Untr ea ted Surf a ce Water. 57 Davi s-Be sse Nuclear Power Station 2015 Annual Radiolo g ic a l Environmental Operating Report Table 11: Untreated Surface Water Locations Sample Location Number T-3 T-11

• T-12 T-22A* T-145 Type of Location I c c I QC I = indicator , C = co ntrol *denotes ODCM-requir e d sa mpl e Location Description Site boundary, 1.4 mile s ESE of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant , sample taken from intake crib, 12.6 miles NW of Station Carroll Town s hip Water Plant , State Route 2, 2.1 mile s NW of Station Roving Quality Control Site 58 Davi s-Be ss e Nuclear Power Station 2015 Annual Radiolo g ical Environmental Operating Report Shoreline Sediment The sampling of shoreline sediments can provide an indication of the accumulation of insoluble radionuclide s 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 line exposure to fi s hermen 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). Sample s were lyzed for gamma-emitting radionuclides.

Naturally occurring Potassium-40 was detected at both control and indicator locations. These re s ults are s imilar to previous years. Table 12: Shoreline Sediment Locations Sample Location Type of Number Location T-3 I T-4 I T-27* c T-132 I I = indicator C = control *Denotes ODCM-required sample Location Description Site boundary, 1.4 miles ESE of Station Site boundary, 0.8 mile s S of Station Crane Creek , 5 .3 miles WNW of Station Lake Erie , 1.0 miles E of Station 59 0 Da vis-B esse Nuclear Power Station 2015 Annual Radiolo gica l Environmental Operating Report Fish Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondarily to serve as indicators of radioactivity in the aquatic ecosystem.

The principal nuclides 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 s pecies (e.g., bottom-feeder versus ator), results from sa mple analyses may vary. Da v i s-Besse routinely collects three s pecies of fish once per year from sa mpling 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 ed because of being a popular recreational fish and white perch and white bass are collected cause their importance as a commercial fish. Carp are not ODCM-required samples, but are collected as enhancement sa mple s becau se they feed on the bottom where contaminants may tle. The average concentration of bet a-emitting radionuclides in ODCM-required fish was similar for indicator and control locations (3.55 pCi/g and 3.83 pCi/g wet weight, respectively).

No gamma emitters were detected above their respective LLDs. Gross Beta in F i s h 1972-2015

"' .... "' .., 0 "' :8 "' a: N ;l :g "' 8 N <!; 8 "' :t co Ii; Si S; .... "' .., "' CJ> CJ> 0 0 ;; 0 0 0 0 0 0 0 0 "' N "' "' "' "' "' "' "' Y ear 1--l ndicalllr

---Ccntrnl I Fi g ure 21: Average conce nt rations of beta-emittin g radionuclides (pCi/gram) in fish sa mple s were s imilar at i nditor and control locations , and were comparable to results of previous years. 60 Davi s-Be ss e ucl e ar Power St a tion 2015 Annu a l R a diolo g i ca l En v ironm e nt a l Oper a tin g R e port Table 13: Fish Locations Sample Location Number T-33* T-35* Type of Location I c I = indicator C= control *Denote s ODCM-required sample Location Description Lake Erie, within 5 mile s radius of Station Lake Erie , greater than 10 mile radius of Station 61 DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AQUATIC SA MPL ES: S I TE ' I NW ' NNW I N ' ' ' ' ' ' CJ 0 < I I (/) I I I CD I (!) I (/) (/) (!) I z I c I 0 I , (!) , 0 , I , , " I , 0 " , ---(!) ------, ---Vl rl-0 ,, w 0 '° c E :J -, (1) "' 0 "' N ---U1 ---------)> ---:J )> ---:J c "' D ---"' c ' ---0 0 -------+ ' :u ' ' 0 n ' 0. ' ' Vl ' ' 0 ' -+ I 0 (!) IO ES E I 0 3:: INDICATOR STATIONS 0 0 I "O 1 t..J fTl ...., :J I i SHORELINE SEO I MENTS ' < I ' ' , I ii SURFACE ' I.._ 0 WAT E R TREATED ' :J , I ' I 3 'ft SURFACE ' (!) WATER UNTREATED

' :J ' rl-' , 0 I ' , , I ' SW , 0 , "O ' (!) , , , ' , ' 0 ' , ' SE , ' rl-, ' , ' ' :J ' , '° ; :T-4 ' :u ' (!) ' "O ' 0 , rl-DB* 0*-02-16 DFN*F */SCHEO/SK ZB 11.DGN WNW ... . .. DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . ....... . z .. ::i: _J I w ro . *. RD. AQUATIC SAMPLES: 5 MILE RADIUS ci c:) 0:: 0:: C AMP PERRY-\I I I-::i 0 V> *,,CN g] t-t-** *fr. . .... ::i ... w *3: _J .,.... .... V> ::i 0 I-c:) 0:: w .. "" 0 0:: ro ****** SE OB* 0<-02-1 6 OFN*F*/SCHEO/SK2816

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,, '° c , CD N .b l> £J "' c .b 0 .+ 0 N U1 I 3 ro 3: 0 "O DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM M IC H Oreoon .... ... .. FISH : 111 *lo/ : ,:: *en .... .*** ... ... ... SHORELINE SEDIMENTS ii SURFACE WATER TREATED W SURF ACE WATER UNTREATED AQUATIC SAMPLES: 5-2 5 MILE RADIUS :.,, *w : .... :; /<..,'-' .* *"{> SE SSW DB: 04-02-1 6 D F N*F:/SC HED/SK Z8 1 5.DGN 0 0 < CJ> I c:n CD CJ> CJ> CD z c 0 CD 0 , -u 0 "" CD , Vl .+ 0 .+ -* 0 ::J N 0 U1 l> ::J ::J c 0 :0 0 0. 0 0 '° 0 0 rn ::J < , 0 ::J 3 CD ::J .+ 0 0 "O CD , 0 rl-::J '° :0 CD "O 0 , .+

Davis-Besse Nuclear Powe r Station 2015 Annual Radiologic al 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 luminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information.

The TLDs used at Davis-Besse contain a Sulfate:Dysprosium (CaS0 4: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 mea s ure the dose received over long periods of time. The energy that was stored in the TLD as a result of interaction with 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 proce ss re-zeroes the TLD and prepares it for reuse. TLD Collection Davis-Bes s e 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 381 TLDs in the environment surrounding Davi s-Be ss e. By lecting them on a quarterly and annual ba sis from a si ngle site, each measurement serv es 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 2015 , the average dose equivalent for quarterly TLDs at indicator locations was 14.5 rnrem/91 day s, and for control locations was 17.5 rnrem/91 days. The average dose lent for annual TLDs in 2015 was 56.2 rnrem/365 day s at indicator locations and 63.8 rnrem/365 days for control locations.

Quality Control TLDs Duplicate TLDs have been placed at 18 sites. The se TLD s 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 measurement s at the location without the laboratory being aware that they are the same. A compari so n 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 13.4 rnrem/91 days while the quality control TLD s at control location s yielded an average dose equivalent of 16.5 rnrem/91 days. 65 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Gamma Dose for E n vironmental TLOs 1973-2015

• ii' 1:1 e E f E 8 Ol ;! ie 00 l!j Cb l8 8 Sl 8 ;!; :g 0 t--Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 0 0 0 N N N N N N N Year --I n d i cator --c o n tr o l Figure 25: The similarity between indicator and control results demonstrates that the operation of Davi s-Be sse ha s not caused any abnormal gamma dose. 66 .,,. 0 0 N N Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations Sample Location Type of Number Location T-1 * *1 T-2* I T-3* I T-4* I T-5* I T-6

• I .T-7* I T-8* I T-9 c T-10* I T-11

• c T-12* c T-24 c T-27 c T-38 I T-39 I T-40* I T-41* I T-42* 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 Site boundary, 0.5 miles W of Station Site boundary, 0.5 miles NNE of Station Sand Beach entrance, 0.9 miles NW of Statiom Moore Farm, 2.7 miles WSW of Station Oak Harbor Substation, 6.8 miles SW of Station 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 67 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location T-43 I T-44 I T-45 I T-46* I T-47* I T-48* I T-49 I T-50* I T-51 c T-52* I T-53 I T-54* I T-55* I T-60 I T-62 I T-65 I T-66 I T-67* I T-68* I T-69 I Location Description Site boundary, 0.5 miles SW of Station Site boundary, 0.5 miles WSW of Station Site boundary, 0.5 miles W"NW 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 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) miles ENE of Station Site boundary, 0.3 miles N"NW of Station Site boundary, 0.5 miles W"NW of Station Site boundary, 0.4 miles W of Station 68 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number* Location Location Description T-71 I Site boundary, 0.1 mile NNW of Station T-73 I Site boundary, 0.1 mile WSW of Station T-74 I Site boundary, 0.1 mile SSW of Station T-75 I Site boundary, 0.2 mile SSE of Station T-76 I Site boundary, 0.1 mile SE of Station T-80 QC Quality Control Site T-81 QC Quality Control Site T-82 QC Quality Control Site T-83 QC Quality Control Site T-84 QC Quality Control Site T-85 QC Quality Control Site T-86 QC Quality Control Site T-88 QC Qualicy Control Site T-87 QC Quality Control in lead pig DBAB Annex T-89 QC Quality Control Site T-90 I Site Personnel Processing Facility T-91

• I State Route 2 and Rankie Road, 2.5 miles SSE T-92 I Locust Point Road, 2.7 miles WNW of Station T-93 I Twelfth Street, Sand Beach, 0.6 miles NNE of Station T-94 I State Route 2, 1.8 miles WNW of Station T-95 c State Route 579, 9.3 miles W of Station 69 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location T-100 -c T-111 c T-112* I T-113 QC T-114 QC T-115 QC T-116 QC T-117 QC T-118 QC T-119 QC T-120 QC T-121 I T-122 I T-123 I T-124 c T-125 I T-126 I T-127 I Location Description 9ttawa 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 t 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 Lake Street, Ottawa Co. Agricultural Complex 5.5 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 r -Camp Perry Western and Rymers Road, 4.0 miles SSE of Station 70 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations Sample Location Number T-128 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 Type of Location I I I I I I c I I I I I I I I 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. 71 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Number T-211 T-212 T-213 T-214 T-215 T-216 T-217 T-218 T-219 T-220 T-221 T-222 T-223 T-224

• I = Indicator C =Control QC = Quality Control Type of Location I I I I I I I I I I c I I I *denotes ODCM-required TLD Location Description Site boundary, 0.79 miles E of Station Site boundary, 1.2 miles ESE of Station Site boundary, 0.6 miles SSW of Station Site boundary, 0.7 miles SW of Station Site boundary, 0.5 miles W of Station Site boundary, 0.7 miles NW of station Salem-Carroll Rd., 4.7 miles SSW of Station Toussaint East Rd., 4.0 miles WSW of Station Toussaint Portage Rd., 4.8 miles WSW of Station Duff-Washa Rd., 4.8 miles W of Station Magee Marsh, 5 .1 miles WNW of Station Turtle Creek Access, 3.7 miles WNW of Station Lawrence Rd., 5.0 miles SE of Station Erie Industrial Park, 4.4 miles SE of Station 72 NW ..,, '° c ' Cl> N en -...) (JJ ---< ,---0 Ul -+ Cl> :,;: 0 u SW , DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM \ \ \ \ \ \ \ T-206 (!)' NNW \ I I I I I I I I N I T-207 1 1 T-208 (!) (!) I I I I I I , , , SERVICE ;' ; ; , B LOC. , T-66 T L D S AM P L ES: S IT E ; ; ;;; (!) ---------' ' ' ---' ' ' ' ---------INDICATOR STATIONS I I 1 T-'11 I CD I I I I 'i" THERMOLUMINESCENT DOSIMETER

< TLD I \ \ \ \ \ E ---------' ' ' ' ' ' SE ---ESE ' ' ' ' T-'10 (!) ' ' ' , , , , ------, , , I I I 1 '41 ...., I.._ I D B* 0 4-0 2-1 6 D F N*F*/S CHEO/SKZ811.DGN 0 0 < (/I ' CD Cl> (/I (/I Cl> z c 0 Cl> 0 , -u 0 , Ul .+ 0 0 ::J N 0 lJ1 )> ::J ::J c 0 :u 0 0. 0 0 '° 0 0 [Tl ::J < , 0 ::J 3 Cl> ::J .+ 0 0 u Cl> , 0 .+ ::J '° :u Cl> u 0 , .+

,., -* '° c -, CD N ..... ..... --< .b r Cl U1 3 -CD 3:: 0 "O WNW ... ... w WSW DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . ......... . -' -' 0 *o :o:: *:r: :u

• Vl *O:: * <[ :o Rusho .* j .. 0 0:: SW .s'. TLD SAMPLES: 5 MILE RADI U S 0 0:: 0 0:: CAM P PERRY-T -53.CD CD T *52 'f-126 BIER * ** Ro ,* a .. er vi CAR.ROLL . * ** RD. T *21 7 SALEM-0 >-INDICATOR STATIONS <D THERMOLUMIMESCEMT DOS I METER <TLD l z <[ :::? -' I w al *** ct: . .. .<[ w .;.: -' *>-: <[ z ..... Vl 0 >-D 0:: w <[ "" 0 0:: al SE DB* D .. 02-16 DFN*F*I SCHED/SKZ816.DG N -u 0 , l/l ..... 0 0 ::J N D U1 l> ::J ::J c 0 ;o 0 0. 0 0 '° () 0 fTl ::J < , 0 ::J 3 CD ::J ..... 0 0 "O CD , 0 ..... ::J '° ;o CD "O 0 , .....

M I C H .,, -'° c , <D N a:> -..J __, r "' 0 N "' .. ' 3 -<D :;:: 0 "O DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Or-e oon ... ."!J .*** SW CONTROL STATIONS THERMOLUMINES C ENT "-!...'DOSIMETER

<TLD I TLD SAMPLES: 5-25 MILE RAD I US .**°¢ .. **{> SE SSW 08: 04-02-16 D FN*F:/SCHED/SKZ815.D GN 0 0 < (/I I CD <D (/I (/I <D z c 0 <D 0 , Cl 0 "' <D , Vl ..+ 0 ..+ 0 :::J N 0 -"' )> :::J :::J c 0 ::0 0 0. 0 0 '° 0 0 ,,., :::J < , 0 :::J 3 <D :::J ..+ 0 0 "O <D , 0 ..+ -* :::J '° ::0 <D "O 0 , ..+

Davis-Besse Nuclear Power Station 2015 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 cort-) centrations measured at indicator locations were compared with concentrations measured at trol locations in previous operational studies and in the pre-operational surveillance program. These comparisons indicate normal concentrations of radioactivity in all environmental samples collected in 2015. Davis-Besse's operation in 2015 indicated no adverse radiological impact on the residents and environment surrounding the station. The results of the sample' analyses formed during the period. of January through December 2015 are summarized in Appendix 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 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 diation," Report No. 94, National Council on Radiation Protection and Measurement, ington, D.C. (December 1987). 4. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy 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, 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 I (1988). 8. "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," American National Standards Institute, Inc., ANSI-N45-1975, New York, New York (1975). 9. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurement, Washington, D.C. cember 1987). 76 Davis-Besse Nuclear Power Station 2015 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 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 Besse Nuclear Power Station Unit No.l, 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", (2000-2014) 19. Teledyne Isotopes Midwest Laboratory, "Pre-operational Environmental Radiological 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 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 itoring Program," S-72N. 24. Davis-Besse Nuclear Power Station, "Radiological Environmental Monitoring Program," DB-CN-00015.

77 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 25. Davis-Besse Nuclear Power Station, "Radiological Environmental Monit,oring 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 Op(frating 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 er Station Oak Harbor, Ohio", Environmental Resources Management, March 18, 2008. 78 , /

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2015 Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ionizing radiation were recognized and efforts were made to establish radiation protection standards.

The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recom-. mendations have been given legislative authority by being published in the Code of Federal ulations 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 general public. "Reasonably achievable" means that exposure.reduction is based on sound economic cisions 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 amoµnts of radioactive fission products and trace amounts of the component and structure surfaces, which have been activated, are present in the primary coolant water. The three types of radioactive material released are noble gases, Iodine and particulates, and tritium.

• The noble gas fission products in the primary coolant are given off as a gas *when the coolant is depressurized.

These gases are then collected by a system designed for gas collection and stored for radioactive decay prior t<? 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 ment drains and sumps. All liquids of this nature are mqnitored and processed, if necessary, prior to release. 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 ofradiation exposure to the body. Xe-133 andXe-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive noble gases leased. They are readily dispersed in the atmosphere.

79 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 tems, minimize their discharge.

The predominant radioiodine released is Iodine-131 with a 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 Cesium-137) and activation products (e.g., Cobalt-58 and Cobalt-60).

Radioactive Cesium and Cobalt 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 neutron interaction with deuterium (also a Hydrogen isotope) present in the water and with the Boron in the primary coolant. When tritium, in the form of water or water vapor, is ingested or inhaled 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 cosmic 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 exposure pathway is through ingestion of produce which has incorporated C-14 into plant matter via the chemical form of C02 during 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 systems, in-plant and environmental sampling and analysis programs, quality assurance programs for ent and environmental programs, and procedures covering all aspects of effluent and tal 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 80 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure the limits will not be exceeded.

If a monitor alarms, a release from a tank is automatically stopped. All wastes are sampled prior to release and analyzed to identify the specific concentrations of radionuclides.

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 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 rounding environment.

Frequent samples of other environmental media, such as water and tation, are taken to determine if buildup of dep'Osited radioactive material has occurred in the area. Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to radioactive materiaL The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the ment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An annual age of the water flow, wind speed, and wind direction are used to evaluate how the radionuclides will be distributed in an area for gaseous or liquid releases.

An important factor in evaluating the exposure pathways is the use of the environment.

Many factors are considered such as dietary intake of 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, deposition of radioactive material on plants, deposition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents involves pathways such as drinking water, fish, and direct exposure from the lake at the shoreline while swimming.

81 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report

• • • -..... ,..*.. . ..

Diluted By Atmosphere Ail'llorne Releases 'Consumed By Consumed By Animals II "_,;v By Man -By Man MAN R l.J"'-."-. Drillldng Sllareline0 ExiillSUre f.Al(E 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 by many different pathways, some result in more dose than others. The critical pathway is the exposure _route that will provide, for a specific clide, the greatest dose to a population, or to a specific group of the population called the critical gtoup. 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 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 radionuclides 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. 82 Davis-Besse Nuclear Power Station 2015 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 calculated 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 exposure ways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation, food I 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 dilution 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, 2015.

• Summation of the quantities of radioactive material released in gaseous and liquid ents (Tables 15-19)

• Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites (Table 20) During this reporting period, the estimated maximum individual offsite dose due to radioactivity released in effluents was: Liquid Effluents:

• 4.86E-03 mrem, maximum individual whole body

• 5.41E-03 mrem, maximum individual significant organ dose (liver) Gaseous Effluents:

Noble Gas:

• 5.04E-04 mrem, whole body

• 7.40E-04 mrad, skin Iodine -131, Tritium, and Particulates with Half-lives greater than 8 Days:

• 3.lSE-02 mrem, whole body dose _

• 3.lSE-02 mrem, significant organ dose (liver) Carbon-14:

• 2.60E-01 mrem, whole body

• 0.127E+Ol mrem, significant organ dose (bone) These doses are a small fraction of the limits set by the NRC in the Davis-Besse ODCM. tional 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 83' Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report effluents, the additional pathways include the Turbine Building drains via the settling basins. leases 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. I

• Released at a rate such that the total dose to the skin will be less than or equal to 300Q 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 10CFR50, Appendix I, Sec. IIB. 1, air dose due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

• Less than or equal to 10 mrad total for gamma radiation and less than or equal to 20 mrad total for beta radiation in any calendar year. ' In accordance with 10CFR50, Appendix I, Sec. IIC, dose to a member of the public from Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be 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 3.19 Ci of C-14 in the form of C02 released from Davis-Besse through the Station Vent during 2015. 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. 84 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 2, Columns 1 and 2, with the most restrictive 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 lE-05 uCi/ml of air (submersion dose) verted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication

2. Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release-of fission and activation products to less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the.skin.

Therefore, the average beta and gamina energies (E) for gaseous ents as described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable.

Measurements ofTotal Activity Fission and Activation Gases: These gases, excluding tritium, are collected in: Marinelli beakers specially modified for gas sam'." piing, 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 cation of each radionuclide present on the filter paper is performed by using gamma spectroscopy.

Liquid Effluents Liquid effluents are collected in a Marinelli beaker and counted on a germanium detector. _tification of each gamma-emitting radionuclide present in liquid samples is via gamma copy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system. Batch Releases Liquid from 1/1/15 through 12/31/15 1. Number of batch releases:

62 2. Total time period for the batch releases:

164.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 3. Maximum time period for a batch release: 243 minutes 4. Minimum time period for a batch release: 81 minutes 5. Average time period for a batch release: 160 minutes 85 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Gaseous from 1/1/15 through 12/31/15 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: ,,. Abnormal Releases 5 481.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 447.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 213 minutes There were no abnormal gaseous releases of radioactivity from the station during 2015. There were no abnormal liquid releases of radioactivity from the station during 2015. Percent of ODCM Release Limits The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent oflimits, for January 1, 2015 through December 31, 2015. PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1, 2015-December 31, 2015 (gaseous)

Noble gases (gamma) 3 .46E-05 mrad 10 mrad 3.46E-04 Noble gases (beta) 6.12E-05 mrad 20mrad 3.06E-04 I-131, tritium and particulates 2.24E-03 mrem 15 mrerri 1.49E-02 C-14 5 .35E-02 mrem 20mrem 2.68E-03 Report Period: January 1, 2015 -December 31, 2015 (liquid) Total body 4.42E-03 mrem 3mrem 1.47E-01 Organ (GILLI) 3.48E-03 mrem 10 mrem 3.48E-02 Sources of Input Data

• Water Usage: Survey of Water Treatment Plants (DSR-95-0034

7)

• 0-50 mile meat, milk, vegetable production, and population data was taken from 1982 Annual Environmental Operating R,eport entitled, "Evaluation of Compliance with Appendix I to 10CFR50: Updated Population, Agricultural, Meat -Animal, and Milk Production Data Tables for 1982". This evaluation was based on the 1980 Census, the Agricultural Ministry of Ontario 1980 report entitled "Agricultural tistics and Livestock Marketing Account", the Agricultural Ministry of Ontario port entitled "Agricultural Statistics for Ontario, Publication 21, 1980", the gan Department of Agriculture report entitled "Michigan Agricultural Statistics, 1981 ", and the Ohio Crop Reporting Service report entitled "Ohio Agricultural tistics, 1981 ".

• Gaseous and liquid source terms: Tables 16 through 19 of this report. 86 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating 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 sessment of radiation doses from radioactivity released in liquid and gaseous effluents to members of the public from activities inside the site boundary.

The Pavilion and Training Center pond are accessible to employees and their families.

The ion may be accessible to the public for certain social activities.

The Training Center 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 boundary dose. For poses 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), default 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 public for activities inside the site boundary.

This dose would be at least a factor of 35 times 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 occur. fore, the _modeling of the ODCM conservatively estimates the maximum potential dose to members of the public.

• The Old Steam Generator Storage Facility (OSGSF) provides long-term storage for two Once Through Steam Generators, two Reactor Coolant System Hot Leg Piping sections, one Reactor Vessel Closure Head (with Control Rod Drive Mechanisms and Service Support Structure).

The OSGSF is designed so that 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 10CFR20 (See page 19). Inoperable Radioactive Effluent Monitoring Equipment All required radioactive effluent monitoring equipment was in service during 2015. There was no radioactive effluent equipment out of service for more than 30 days. 87 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Procedure (PCP) There were two revisions to the ODCM during 2015. The first change was to update the ODCM with the latest Land Use Census information.The second change was related to the abandonment of RE8433 Collection Box Outlet to the Lake Radiation Monitor. RE8433 was a Non-Required Radiation Monitor. There were no changes to the Process Control Procedure Manual during 2015. Borated Water Storage Tank Radionuclide Concentrations During the reporting period of 2015, 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. 88 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Nuclide Table 15 Gaseous Effluents

-Summation of All Releases Unit 1st Qtr 2015 2nd Qtr 2015 3rdQtr 2015 4th Qtr 2015 Est. Total% Error Fission and Activation Gases Total Release Ci 0.00E+OO 0.00E+OO 3.46E-01 7.48E-05 2.5E+Ol Average Release Rate for Period Percent of ODCM Limits Iodines Total Iodines (I-131) Average Release Rate for Period Percent of ODCM Limits Particulates Particulates with half-lives greater than 8 days Average Release Rate for Period Percent of ODCM Limits uCilsec NIA NIA 3.66E-02 9.48E-06 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Ci uCi/sec O.OOE+OO NIA O.OOE+OO NIA O.OOE+OO NIA 0.00E+OO NIA See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Ci 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO uCilsec NIA NIA NIA NIA See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination 2.5E+Ol 2.5E+Ol Gross Alpha Activity Ci O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 2.5E+Ol Tritium Total Release Average Release Rate for Period Percent of ODCM Limits Carbon-14 Total Release Ci uCi/sec 2.04E+Ol 2.56E+OO 1.44E+Ol l.83E+OO l.23E+Ol l.30E+OO l.17E+Ol 1.48E+OO See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Ci 2.65E+OO 2.65E+OO 2.65E+OO 2.65E+OO Note: The average release rate is taken over the entire quarter, not over the time the time period of the leases. 89 2.5E+Ol Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 16 Gaseous Effluents

-Ground Level Releases -Batch Mode 1st Qtr 2nd Qtr 3rdQtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 Fission Gases Kr-85 Ci <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD

<LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD

<LLD Xe-135 Ci <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD Xe-138 , Ci <LLD <LLD <LLD <LLD Total for Period: NIA NIA NIA NIA

\ Iodines I-131 Ci <LLD <LLD <LLD <LLD I-133 Ci <LLD <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD <LLD Total for Period: NIA NIA NIA NIA Particulates and Tritium H-3 Ci <LLD <LLD <LLD

<LLD Sr-89 Ci <LLD <LLD <LLD

<LLD Sr-90 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD

<LLD Cs-137 Ci <LLD <LLD <LLD <LLD Ba-La-140 Ci <LLD <LLD <LLD <LLD Total for Period: O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 90 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 16 (Continued)

Gaseous Effluents

-Ground Level Releases Continuous Mode 1st Qtr 2nd Qtr 3rdQtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 Fission Gases Kr-85 Ci <LLD <LLD <LLD

<LLD Kr-85m Ci <LLD <LLD <LLD

<LLD -Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD

<LLD Xe-133 Ci <LLD <LLD <LLD

<LLD Xe-135 Ci <LLD <LLD <LLD

<LLD Xe-135m Ci <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD Total for Period: NIA NIA NIA NIA Iodines I-131 Ci <LLD <LLD <LLD

<LLD I-133 Ci <LLD <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD

<LLD Total for Period: NIA NIA NIA NIA Particulates and Tritium H-3 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD

<LLD Cs-134 Ci <LLD <LLD <LLD

<LLD Cs-137 Ci <LLD <LLD <LLD <LLD Ba-La-140 Ci <LLD <LLD <LLD <LLD Total for Period: NIA NIA NIA NIA 91 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 16 (Continued)

Gaseous Effluents

-Ground Level Releases LLDs for Continuousb and Batcha Mode Ar-41 <5.lOE-09

µCi/ml Kr-85 <l.63E-06

µCi/ml Kr-85m <6.74E-09

µCi/ml Kr-87 <2.48E-08

µCi/ml Kr-88 <2.66E-08

µCi/ml Xe-133 <l.51E-08

µCi/ml

• Xe-133m <4.52E-08

µCi/ml Xe-135 <6.65E-09

µCi/ml Xe-135m <2.13E-07

µCi/ml Xe-138 <6.59E-07

µCi/ml I-131 <7.20E-15

µCi/ml I-133 <9.56E-15

µCi/ml I-135 <6.25E-14

µCi/ml Cs-134 <8.32E-15

µCi/ml Cs-137 <9.92E-15

µCi/ml Ba-140 <2.48E-14.

µCi/ml La-140 <7.lOE-15

µCi/ml Sr-89 <l.40E-15

µCi/ml Sr-90 <4.90E-16

µCi/ml Mn-54 <l.32E-14

µCi/ml Fe-59 <2.16E-14

µCi/ml Co-58 <l.69E-14

µCi/ml Co-60 <l.69E-14

µCi/ml Zn-65 <2.44E-14

µCi/ml Mo-99 <l.OOE-13

µCi/ml Ce-141 <1.17E-14

µCi/ml a Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, and Auxiliary Boiler Outage Release are listed as batch release. b Atmospheric Vent Valve weepage and Steam Packing Exhauster are continuous releases.

92 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 17 Gaseous Effluents

-Mixed Mode Releases Batch Mode Nuclide Unit Fission Gases Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Total for*Period:

• Iodines I-131 Ci I-133 Ci I-135 Ci Total for Period: Ci *Particulates

& Tritium H-3 Ci Sr-89 Ci Sr-90 Ci Cs-134 Ci Cs-137 Ci Ba-La-140 Ci Total for Period: Ci

• Release of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Station Vent) 93 1st Qtr 2nd Qtr 2015 2015 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD O.OOE+OO O.OOE+OO <LLD <LLD <LLD <LLD

<LLD <LLD O.OOE+OO O.OOE+OO <LLD 4.45E-04 <LLD <LLD <LLD <LLD

<LLD <LLD <LLD <LLD

<LLD <LLD <LLD 4.45E-04 3rdQtr 2015 3.03E-01 <LLD <LLD <LLD <LLD <LLD 4.02E-02 <LLD 2.63E-03 <LLD <LLD 3.46E-01 <LLD <LLD <LLD O.OOE+OO l.37E+OO <LLD <LLD <LLD <LLD

<LLD l.37E+OO 4th Qtr 2015 <LLD <LLD <LLD <LLD <LLD <LLD 7.48E-05 <LLD

<LLD <LLD <LLD 7.48E-05 <LLD <LLD <LLD 0.00E+OO 5.98E-04 <LLD <LLD <LLD <LLD <LLD 5.98E-04 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 17 (Continued)

Gaseous Effluents

-Mixed Mode Releases -Continuous Mode 1st Qtr 2ndQtr 3rdQtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 Fission Gases Kr-85 Ci <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD

<LLD Xe-133m Ci <LLD <LLD <LLD

<LLD Xe-135 Ci <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD

<LLD Xe-138 Ci <LLD <LLD

<LLD <LLD Total for Period: 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO Iodines I-131 Ci <LLD <LLD <LLD

<LLD I-132 Ci <LLD <LLD <LLD <LLD I-133 Ci <LLD <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD

<LLD Total for Period:* O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO Particulates, Tritium Co-58 Ci <LLD <LLD <LLD

<LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD

<LLD <LLD Ba-La-140 Ci <LLD <LLD <LLD <LLD H-3 Ci 2.04E+Ol 1.44E+Ol l.09E+Ol l.17E+Ol Total for Period 2.04E+Ol 1.44E+Ol l.09E+Ol l.17E+Ol Carbon-14 Ci 2.65E+OO 2.65E+OO 2.65E+OO 2.65E+OO 94 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 17 (Continued)

LLDs for Gaseous Effluents

-Mixed Mode Releases Continuous Mode 3 BatchModea Kr-85 <l.63E-06

µCi/ml Ar-41 <1.38E-06 Kr-85m <6.74E-09

µCi/ml Kr-85m <9.40E-07 Kr-87 <2.48E-08

µCi/ml Kr-87 <2.lOE-06 Kr-88 <2.66E-08

µCi/ml Kr-88 <3.35E-06 Xe-133 <l.51E-08

µCi/ml Xe-133 <1.52E-06 Xe-133m <4.52E-08

µCi/ml Xe-133m <6.85E-06 Xe-135 <6.65E-09

µCi/ml Xe-135 <7.76E-07 Xe-135m <2.13E-07

µCi/ml Xe-135m <l.29E-05 Xe-138 <6.59E-07

µCi/ml Xe-138 <3.98E-05 I-131 <7.20E-15

µCi/ml I-131 <7.18E-07 I-133 <9.57E-15

µCi/ml I-133 <8.44E-07 I-135 <6.25E-14

µCi/ml I-135 <3.40E-06 Cs-134 <8.32E-15

µCi/ml Sr-89 <1.40E-15 Cs-137 <9.92E-15

µCi/ml Sr-90 <4.90E-16 Ba-140 <2.48E-14

µCi/ml Cs-134 <9.71E-07 La-140 <7.lOE-15

µCi/ml Cs-137 <8.60E-07 Sr-89 <1.40E-15

µCi/ml Ba-140 <2.85E-06 Sr-90 <4.90B-16 uCi/ml La-140 <L87E-06 Mn-54 <l.32E-14

µCi/ml Fe-59 <2.16E-14

µCi/ml Co-58 <l.69E-14

µCi/ml Co-60 <l.69E-14

µCi/ml Zn-65 <2.44E-14

µCi/ml Mo-99 <l.OOE-13

µCi/ml Ce-141 <1.17E-14

µCi/ml a These radionuclides were not identified in every quarter in concentrations above the lower limit of detection (LLD). 95 µCi/ml µCi/ml µCi/ml µCi/ml uCi/ml µCi/ml µCi/ml , µCi/ml µCi/ml µCi/ml µCi/ml µCi/ml . µCi/ml µCi/ml µCi/ml µCi/ml µCi/ml uCi/ml Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 18 Liquid Effluents

-Summation of All Releases Type Unit Fission and Activation Products Total Release (without Tritium, Ci Gases, Alpha) Average Diluted Concentration

µCi/ml During Period" 1st Qtr 2015 6.71E-05 5.63E-12 2nd Qtr 3rd Qtr 2015 2015 6.64E-04 4.42E-03 5.63E-11 3.74E-10 4th Qtr 2015 6.59E-04 9.69E-11 Est. Total % Error 2.0E+Ol Percent of ODCM Limits % See Supplemental information in ODCM Section 2.3, Re-lease Limits Percent of 1 Limit % 3.70E-05 7.69E-04 l.95E-03 9.20E-04 Tritium Total Release Ci 7.63E+Ol 2.51E+02 l.82E+02 3.10E+02 2.0E+Ol Average Diluted Concentration

µCi/ml 6.40E-06 2.13E-05 l.54E-05 2.58E-05 During Period" Percent of 10CFR20 Limit % 6.40E-01 2.13E+OO l.54E+OO 2.58E+OO Dissolved and Entrained Gases Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.61E-05 2.0E+Ol Average Diluted Concentration

µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO 7.17E-12 During Period" Percent of 1 OCFR20 Limit % O.OOE+OO O.OOE+OO O.OOE+OO 3.59E-06 Gross Alpha Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.0E+Ol Volume of Waste Released (prior to dilution)

Batch liter l.80E+05 4.69E+05 4.11E+05 6.30E+05 2.0E+Ol Continuous liter 5.62E+07 l.44E+08 8.16E+07 l.33E+08 2.0E+Ol Volume of Dilution Water Batch liter 1.07E+08 3.00E+08 2.15E+08 3.63E+08 2.0E+Ol Continuous liter l.18E+10 l.13E+10 l.15E+10 l.15E+10 2.0E+Ol Total Volume of Water Released liter l.19E+10 l.18E+10 l.18E+10 l.20E+10 *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 quartec Fission and Activation products and Dissolved and Entrained Gases are mally only detected in batch releases.

96 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 19 Liquid Effluents

-Nuclides Released in Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 Fission and Activation Products Na-24 Ci <LLD <LLD l.06E-06 <LLD Mn-54 Ci <LLD <LLD l.18E-04 6.41E-06 Fe-55b Ci <LLD <LLD l.73E-03 <LLD Co-57 Ci <LLD <LLD 7.59E-06 9.66E-07 Co-58 Ci 4.70E-06 4.64E-05 2.08E-04 4.62E-04 Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci l.71E-06 4.05E-05 2.63E-04 7.99E-05 Ni-63 Ci 4J4E-05 3.19E-04 l.93E-03 <LLD Zn-65 Ci <LLD <LLD <LLD <LLD Se-75 Ci <LLD <LLD <LLD , <LLD Br-82 Ci <LLD <LLD <LLD <LLD Sr-89b Ci <LLD <LLD <LLD <LLD Sr-90b Ci <LLD <LLD <LLD <LLD Sr-92 Ci <LLD <LLD <LLD <LLD* Nb-95 Ci <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD l.06E-06 Zr-97 Ci <LLD <LLD <LLD <LLD Mo-99 , Ci <LLD <LLD <LLD

<LLD Tc-99m Ci <LLD <LLD <LLD <LLD Ru-103 Ci <LLD <LLD <LLD <LLD Ru-105 Ci <LLD <LLD <LLD <LLD Ru-106 Ci <LLD <LLD <LLD <LLD Ag-llOm Ci l.61E-05 l.94E-04 7.36E-05 2.64E-05 Sb-122 Ci <LLD <LLD <LLD <LLD Sb-124 Ci <LLD 2.25E-05 7.37E-06 3.67E-05 Sb-125 Ci 2.69E-06 6.22E-06 2.82E-06 <LLD 1-131 Ci <LLD <LLD <LLD <LLD 1-132 Ci <LLD <LLD <LLD <LLD Te-132 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD l.71E-06 4.48E-06 3.09E-06 Cs-137 Ci 4.26E-07 3.41E-05 7.38E-05 4.23E-05 Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD Total for Period: Ci 6.71E-05 6.64E-04 4.42E-03 6.59E-04 97 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 19 (continued)

Liquid Effluents

-Nuclides Released In Batch Releases lstQtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 H-3 Ci 7.62E+Ol 2.51E+02 l.82E+02 3.10E+02 Dissolved and Entrained Gases Kr-85 Ci <LLD <LLD <LLD

<LLD Xe-131m Ci <LLD <LLD <LLD-<LLD Xe-133 Ci <LLD <LLD <LLD 8.61E-05 Xe-133m Ci <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD Total for Period: Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.61E-05 98 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 19 (continued)

Liquid Effluents

-Nuclidesa Released Nuclide Fission and Activation Products Cr-51 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr-89b S'r-90b Nb-95 Zr-95 Mo-99 Tc-99m 1-131 Cs-134 Cs-137 Ba/La-140 Ce-141 Total for Period: Tritium Dissolved and Entrained Gases Xe-133 Xe-135 Total for Period: In Continuous Relec;ises Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 99 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2015 2015 2015 2015 <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 <LLD <LLD <LLD <LLD <LLD <LLD

<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO l.65E-01 2.86E-01 3.63E-02 6.00E-02 <LLD <LLD <LLD

<LLD <LLD <LLD <LLD

<LLD O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 19 (continued)

Liquid Effluents

-LLDs for Nuclides Released a Cr-51 <9.00E-08

µCi/ml Ar-41 <4.27E-09

µCi/ml Mn-54 <5.95E-09

µCi/ml I-131 <8.67E-09

µCi/ml Fe-55b <7.lOE-07

µCi/ml Xe-131m <4.27E-07

µCi/ml Co-57 <8.99E-09

µCi/ml Xe-133 <2.53E-08

µCi/ml Co-58 <7.06E-09

µCi/ml Xe-133m <8.30E-08

µCi/ml Fe-59 <2.22E-08

µCi/ml Cs-134 <8.27E-09

µCi/ml Co-60 <9.13E-09

µCi/ml Xe-135 <9.00E-09

µCi/ml Zn-65 <2.50E-08

µCi/ml Cs-137 <9.76E-09

µCi/ml Kr-85 <2.24E-06

µCi/ml Ba-140 <3.24E-08

µCi/ml Sr-89b <2.40E-08

µCi/ml La-140 <1.13E-08

µCi/ml Sr-90b <7.40E-09

µCi/ml Ce-141 <1.67E-08

µCi/ml Sr-92 <1.58E-08

µCi/ml Ce-144 <7.30E-08

µCi/ml Zr-95 <9.83E-09

µCi/ml Zr-97 <8.67E-09

µCi/ml Tc-99m <9.25E-09

µCi/ml Mo-99 <7.51E-08

µCi/ml Ru-103 <9.35E-09

µCi/ml Ru-106 <1.02E-07

µCi/ml Ag-llOm <1.03E-08

µCi/ml Sb-124 <7.97E-09

µCi/ml Sb-125 <3.32E-08

µCi/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 dueto identical sample and analysis methods. b Quarterly composite sample 100 \

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 20 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, m3 2.05E+Ol 2.5E+Ol evaporator bottoms, etc. Ci 5.15E+02 2.5E+Ol b. Dry compressible waste, m3 2.93E+02 2.5E+Ol contaminated equip., etc. Ci 2.96E+OO 2.5E+Ol c. Irradiated components, m3 NIA NIA control rods, etc. Ci d. Filters m3 4.56E-01 2.5E+Ol Ci 1.48E+OO 2.5E+Ol e. Others: Spent Resin Storage m3 2.29E+Ol 2.5E+Ol Tanlc Liquor Ci 8.94E+OO 2.5E+Ol 2. Estimate of major nuclide composition (by type of waste) Percent(%}

Est. Error, % a. Spent Resins Cs 137 3.98E+Ol 2.50E+Ol Ni63 3.59E+Ol 2.50E+Ol cs134 9.22E+OO 2.50E+Ol Co6o 6.75E+OO 2.50E+Ol Fess 4.28E+OO 2.50E+Ol Coss l.92E+OO 2.50E+Ol c14 l.56E+OO 2.50E+Ol Nis9 2.33E-01 2.50E+Ol H3 2.27E-01 2.50E+Ol b. Dry compressible waste, contaminated Cs 137 2.72E+Ol 2.50E+Ol equipment, etc. Ni63 2.25E+Ol 2.50E+Ol Fess l.25E+Ol 2.50E+Ol Ag11om l.04E+Ol 2.50E+Ol Co6o 8.20E+OO 2.50E+Ol Cs134 7.92E+OO 2.50E+Ol Coss 5.37E+OO 2.50E+Ol H3 2.89E+OO 2.50E+Ol c14 2.04E+OO 2.50E+Ol Mns4 3.34E-01 2.50E+Ol ce144 2.72E-01 2.50E+Ol Tc99 l.07E-01 2.50E+Ol c. None 101 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report d. Filters e. Others: Spent Resin Storage Tank Liquor 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 Coss Co6o Ni63 Fess c14 Aguom zr95 Cs 137 H3 Ni63 Coss cs131 Co6o Ag110m Fess Cl4 Nis9 16 Truck 6.46E+Ol l.35E+Ol 8.25E+OO 7.07E+OO 3.88E+OO l.35E+OO l.14E+OO l.20E-01 5.66E+Ol l.58E+Ol 1.47E+Ol 5.15E+OO 3.0lE+OO 2.18E+OO l.73E+OO 7.31E-01 l.OlE-01 Energy Solutions, Oak Ridge, TN 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol for processing and disposal at Energy Solutions, Clive UT Metal boxes (assorted sizes, 1.4-35.4 m 3) 320m 3 7 Truck Energy Solutions, Oak Ridge, TN for processing and disposal at WCS, Andrew TX Poly HIC 3.40 m 3 16.8 m 3

• 1 Truck Energy Solutions, Barnwell, SC for processing and disposal at WCS, Andrew TX Poly HIC 1.16 m 3 0.21 m 3 102 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report B. IRRADIATED FUEL SHIPMENTS There were no shipments of irradiated fuel. Onsite Groundwater Monitoring Davis-Besse began sampling wells near the plant in 2007 as part of an industry-wide Groundwater Protection Initiative (GPI), which was established to ensure that there are no inadvertent releases of radioactivity from the plant which could affect offsite groundwater supplies.

In addition to several existing pre-construction era wells, sixteen new GPI monitoring 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. In January, seven out of ten wells indicated tritium concentrations of greater than 2,000 pCi/L requiring courtesy notifications to local, county, and state officials.

Increased sampling frequency on selected wells was implemented in an attempt to identify the source of the groundwater contamination.

A Problem Solving and Decision Making Team (PSDM) was also formed. Based on the completion of detailed Failure Mode Analyses, the potential pathways have been evaluated and refuted through inspection.

The conclusion of the PSDM Team was that the most probable cause was due to construction activities surrounding the removal of the Primary Water Storage Tank. Since the initial identification of elevated concentrations, well sampling results have indicated an overall decreasing trend over the year, indicating that the cause is intermittent and no longer active. The area of highest concentrations, the concentration has decreased from 10,527 pCi/L in February to 2866 pCi/L in December 2015, with the highest concentration detected in the western wells within the Protected Area. The assumptions regarding groundwater flow and modeling remain valid that the flow does not impact areas outside the Owner Controlled Area and essentially discharges into the Intake Canal. There is no evidence that the tritium traveled offsite or contributed to offsite dose. Additionally, the groundwater tritium sample results remain below the 30,000 pCi/l EPA limit described in the Besse Offsite Dose Calculation Manual for non-drinking water sources. Table 21 contains the Davis-Besse GPI monitoring well sample results for tritium for 2015. 103 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 21. 2015 Groundwater Tritium Results Year 2015 January February March April May June August September October December Well No. [H*3], [H*3], [H*3], [H-3], [H*3], [H*3], [H*3], [H-3], pCi/I [H-3], [H-3], pCi/I . pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I MW-100A 192 <185 850 1742 1146 MW-1008 <185 405 MW-100C <185 <150 MW-101A 302 <150 MW-1018 <183 296 281 MW-101C <147 <150 MW-102A <185 <150 MW-1028 417 2114 1411 1080 MW-102C <185 <150 MW-103A 538 283 MW-1038 311 229 287 MW-103C <185 <150 MW-104A <147 <150 MW-1048 <185 531 MW-104C <185 <150 MW-105A 2578 2648 3085 2798 2876 2588 2625 2566 2026 MW-128 5202 8899 8388 7695 7410 4793 4122

' 3989 MW-148 4736 5485 5850 5825 6166 5952 MW-158 997 1372 1756 1973 2298 2377 MW-188 356 258 386 474 MW-198 953 708 2533 1340 5608 3670 MW-208 7492 8688 7658 6584 6981 6488 6246 3429 3836 3736 MW-218 7938 8608 6141 5739 5332 4773 2509 2856 2866 MW-228 10527 9552 * * * * * *

• MW-238 2563 3792 3225 5259 4642 3726 MW-308 3248 2406 3237 2508 5109 4533 3847 3411 3450 MW-318 6726 6186 7394 6013 6464 4524 MW-328 4512 3777 7124 6617 6427 4222 MW-338 1961 4993 891 4803 5556 5535 MW-348 2379 2917 4716 4621 4951 5106 4651 4591 4462 MW-378 3597 4052 4408 3909 4011 3713 3448 3083 2904 MW-398 2563 552 4808 483 842 999 April and September are the Spring and Fall campaigns; all other results are trending data. Seven *wells remained >2000 pCi/L in 2015. *MW-22S was removed for construction.

MW-20S,MW-21S, and MW23S are in the vicinity and provide adequate groundwater monitoring information.

104 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report ;J 10000 *5 <.J 0 -a. 1000 F i g u re 30 -Onsite Groundwater Monitoring Davis Besse O nsit e Grou n d wat er M on it or i ng P r o gram H-3 Tr e nd s <200 p C i/L"' T ypica l L L D 348 pCi/L = Pre-O perationa l Mean 2 , 000 pC i/L = NR C Req uired L L D Pre Uperat o ral Mean H 2 (HW p<..: 1.L) 2 , 000 p C i/L = FEN O C/NEI C om m u n ication La v el 20,00 0 pCi/L = E PA Reporting Leve l ____ __..._..._

___ .....;._-"-------'

--Nl<C Hequ u ed LLUH 3

>U I LJ Summary of Onsite Spills(> 100 gallons) and Notifications There were no identified onsite spills during 2015. Throughout 2015 , the State , County , and local officals were kept updated on the groundwater monitoring sample results >2 , 000 pCi/L and the Besse problem solving plans/progress.There were s e v en remaining groundwater well s with elevated tritium results where notifications

/updates to State , County and local officials were being made at the end of 2015. Summary of Items Added to Decommissioning Files per 10 CFR 50.75(g) The elevated tritium level described above wa s added to Decommi ss ioning File s per 10 CPR 50.75(g). 105 Davis-Besse Nuclear Power Station 2015 Annual RadiologiCal Environmental Operating Report Table 22 Doses Due to Gaseous Releases for January through December 2015 Maximum Individual Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days. Whole Body Dose 3 .15E-02 mrem Significant Organ Dose (liver) 3.15E-02 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 5.04E-04 mrem Skin Dose 7.40E-04 mrad Maximum Individual Dose Due to C-14 Whole Body Dose 5.35E-02 mrem Significant Organ Dose (bone) 2.68E-01 mrem Population Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days. Total Integrated Population Dose l .53E-02 person-rem Average Dose to Individual in Population 7.0lE-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 7.69E-05 person-rem Average Dose to Individual in Population 3.52E-08 mrem Population Dose Due to C-14 Total Integrated Population Dose 8.09E-02 person-rem Average Dose to Individual in Population 3.70E-05 mrem 106 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 23 Doses Due to Liquid Releases for January through December 2015 Maximum Individual Whole Body Dose Maximum Individual Significant Organ Dose (LIVER) Population Dose Total Integrated Population Dose Average Dose to Individual 5.08E-04 mrem 6.23E-04 mrem 7.31E-01 person-rem 3.35E-04 mrem Table 24 Annual Dose to The Most Exposed (from all pathways)

Member of the Public 2015 ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem) (mrem) LIMIT Whole Body Dose* Noble Gas 5.04E-04 Iodine, Tritium, Particulates 3.15E-02 C-14 2.61E-01 Liquid 4.86E-03 Total Whole Body Dose 3.68E-02 25 l.47E-01 Thyroid Dose Iodine, Tritium, Particulates 3.53E-02 75 4.71E-02 Skin Dose Noble Gas 7.40E-04 25 2.96E-03 Significant Organ Dose 3.69E-02 25 1.48E-Ol (LIVER) Significant Organ Dose (C-14) 1.263 25 5.05E+OO (bone) Meteorological Data Meteorological data, stored on a compact disk for January 1 through December 31, 2015, 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.

107 Davis-Besse Nuclear Power Station 2015 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 sary to estimate radiation dose to the. general public and to determine if ar;tY modifications are necessary to the Radiological Environmental Monitoring Program (REMP). The Land Use Census is required by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis-Besse Nuclear Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use sus Data. The Land Use Census identifies gaseous pathways by which radioactive material may reach the general population around Davis-Besse.

The information gathered during the Land Use Census for dose assessment and input into the REMP ensure these programs are as current as possible.

The pathways of concern are listed below:

• Inhalation Pathway -Internal exposure as a result of breathing radionuclides carried in the air.

• Ground Exposure Pathway -External exp,osure 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 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 meteorological sector within a five mile radius of Davis-Besse.

The surveillance portion of the 2015 Land Use Census was performed during the months of July and August. 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 bage). Each residence is tabulated as being an inhalation pathway, as well as ground and plume exposure pathways.

Each garden is tabulated as a vegetation pathway. All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7 .5 nute series of the relevant quadrangles) which has been divided into 16 equal sectors corresponding 108 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report to the 16 cardinal compass points (Figure 31 ). If available, the closest residence, milk animal, and vegetable garden in each sector are determined by measuring the distance from each to the Station Vent at Davis-Besse.

Results l The following changes in the pathways were recorded in the 2015 census: S sector: A new garden was located at 3 .10 miles distance from the plant. SW sector: A new garden was located at 0.70 miles distance from the plant. WNW sector: A new garden was located at 2.32 miles distance from the plant. The critical receptor is a garden in the SW sector at 0.70 miles from Davis-Besse, which is a change from 2014. The detailed list in Table 25 was used to update the database of the effluent dispersion model used '\ in dose Table 25 is divided by sectors and lists the distance (in miles) of the closest pathway in each. Table 26 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and _deposition (D/Q) parameters for *?ach 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 lating liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints.

109

.,, <Cl c -, CD "" r 0 :J 0. 0 c (/) CD (") CD :J (/) c (/) 3: 0 " DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM WNW ... . .. **:* ... c:i Cl: w ... WSW SW s*. BIE R -..RD,: CLOSEST SITES To Da v Is-Be ss e With in Se ctor" 1111 RESIDENCE 1111 VEGETABLE GARDEN PRI MARY PATHWA YS WITHI N A 5 MIL E RADI US RD. c:i .. ******: w c:i c:i c:i Cl: Cl: Cl: C AMP PE R R Y-D w". ::i: a:. c:i I-w*. Cl: ii ::::i 0 * ** RD. "' z Cl: I-<( .. 'j'; z c:i ::::i .<( Cl: ******* ...J w .31: w ::i: "' w ...J .,_ ::::i I-CD : <( 0 <( I-"' 0 Cl: CD SSW SE OB: 0'-02-1 6 O F N*F:/SCH EO/SKZ 816.0 GN 0 :J N 0 U1 )> :J :J c 0 ::0 0 0. 0 0 '° 0 0 fT'I :J < -, 0 :J :J ... 0 0 " CD -, 0 ... :J '° ::0 CD " 0 -, ...

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report N NNE NE ENE,E,ESE SE SSE SSE *S s SSW SSW SW *changed from 2014 Table 25 Closest Exposure Pathways Present in 2015 Distance from Station (miles) 0.55 0.55 0.56 NIA 4.94 1.82 0.93 3.10 0.68 3.5 0.61 0.67 111 Closest Pathways Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Located over Lake Erie Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure *Plume Exposure ./

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report *SW WSW WSW w w WNW *WNW NW NW NNW

• changed from 2014 Table 25 (Continued)

Closest Exposure Pathways Present in 2015 Distance from Station (miles) 0.70 0.96 4.0 0.61 0.97 0.94 .\ 2.32 1.94 0.93 0.80 112 ClOsest Pathways Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Vegetation Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 26 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters SECTOR MILES CRITICAL AGE X/Q D/Q PATHWAY GROUP (SEC/M 3) (M-2) N 0.55 Inhalation Child 3.23E-06 l.21E-08 NNE 0.55 Inhalation Child 4.06E-06 2.12E-08 . NE 0.56 Inhalation Child 3.13E-06 . 2.27E-08 *ENE *E .._ __ *ESE SE 4.94 Inhalation Child l.90E-08 l.83E-10 SSE 1.82 Vegetation Child 7.52E-08 8.30E-10 **S 3.10 Vegetation Child 2.84E-08 2.55E-10 SSW 3.5 Vegetation Child 2.74E-08 2.35E-10 **SW 0.7 Vegetation Child 4.56E-07 1.57E-08 WSW 4.0 Vegetation Child. 4.33E.;08 3.47E-10 w 0.97 Vegetation Child 6.05E-07 5.13E-09 **WNW 2.32 Vegetation Child 1.40E-07 6.56E-10 NW 1.94 Vegetation Child l.84E-07 6.74E-10 NNW 0.80 Inhalation Child 9.54E-07 3.51E-09 *Since these sectors are located over marsh areas and Lake Erie, no ingestion pathways are present. **Changed from 2014 Land Use Census. 113 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Non-Radiological Environmental Programs Meteorological Monitoring 1 The Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nuclear power stations on the surrounding environment.

Both NRC regulations and the Davis-Besse nical 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 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 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 Emergency paredness Program, Site Chemistry, Plant Operations, Nuclear Security, Materials Management and Industrial Safety, as well as other plant personnel and members of the surrounding community.

The Radiological Environmental Monitoring Program uses meteorological data to aid in ing the radiological impact, if any, of radioactivity released in Station effluents.

The ical 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 late 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 lations, Forebay water level availability and plant work which needs certain environmental 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 ditions 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 unsafe 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 relation to the Plant and personnel.

1. More detailed weather information is available upon request. 114 Davis-Besse N1,1clear Power Station 2015 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 100 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Dew Point Precipitation Meteorological Instrumentation BACKUP 100 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Solar Incidence The meteorological system consists of one monitoring site located at an elevation of 577 feet above mean sea level (IGLD 1955)*. It contains a 100 meter (m) free-standing tower located about 3,000 feet SSW of the Cooling Tower and a lOm auxiliary tower located 100 feet west of the 100 m tower. Both are used to gather the meteorological data. The lOOm tower has primary and backup instruments for wind speed and wind direction at lOOm and 75m. The lOOm tower also measures differential temperature (delta Ts): 100-lOm and 75-lOm. The lOm tower has instruments for wind speed and wind direction.

Precipitation is measured by a tipping bucket rain gauge located near the base of the lOm tower. According to the Davis-Besse Nuclear Power Station Technical Requirements Manual, a minimum . of five instruments are required to be operable at the two lower levels (75m and lOm) to measure temperature, wind speed, and wind direction.

During 2015, average annual data recoveries for all required instruments were greater than 97 .69 percent. Minor losses of data occurred during routine instrument maintenance, calibration, and data validation.

Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly.

Data is reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required.

Tower instrumentation maintenance and semiannual calibrations are formed 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 115 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Meteorological Data Handling and Reduc.tion 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 system is designed the same as the primary; so to lose all meteorological data the primary and backup teorological 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 tion, 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 age 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 scrutinized 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 27-30, which summarize meteorological data collected from the site monitoring program in 2015. 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 relate to defined past climatological wind patterns reported in Davis-Besse's Updated Safety Analysis Report. The maximum measured sustained wind speed for 2015 occurred on June 27, when they were measured at 50.29 mph at the lOOm level, 47.83 mph on June 27 at the 75m level, and 32.59 mph on June 27 at the lOm level. Figures 32-34 give an annual sector graphic of average wind speed and percent frequency by 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 resents the average wind speed from that direction.

Wind direction sectors are classified using Pasquill Stabilities.

Percent calms (less than or equal to 1.0 mph) are shown in the middle of the wind sector graphic. 116 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2015 are given in Table 29. These data are measured at the 1 Om level; with differential temperatures taken from 1 OOm and 75m levels. The yearly average ambient temperature was 48.74°F. The maximum temperature was 89.07°F on September 07, 2015 with a minimum temperature of-8.57°F on ruary 20, 2015. Yearly average differential temperatures were -0.009°F (lOOm), and -0.272°F (75m). Maximum differential temperatures for 100 meter and 75m levels were 10.97°F on June 27, 2015. Minimum differential temperatures for lOOm and 75m levels were -21.94 °F on October 22, 2015 (lOOm) and-4.000 on May 31, 2015 (75m). 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 2015 are provided in Table 29. These data are measured at the 1 Om level. The average dew point temperature was

• 5.90°F with a maximum dew point temperature of 45.47°F on May 11, 2015. 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 -36.07°F on February 20, 2015. It is sible to have relative humidity above 100 percent, which is known as supersaturation.

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 2015 are given in Table 28. Total precipitation for the year was 30.89 inches. The maximum daily precipitation total was 2.91 inches on June 27, 2015. 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 the unlikely event of an unplanned 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 reaches higher temperatures than the temperature of 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 denser cold air descending over the lake. This starts a wind circulation which draws air from the water to the land during the daytime, creating a "Lake Breeze" effect. This event could be problematic if a release were to occur, because diffusion would be slow, thus creating an adverse atmosphere to the area surrounding the site. 117 Davis-Besse Nuclear Power Station 2015 Annual Radlological Environmental Operating Report Lake and Forebay levels are monitored at Davis-Besse to observe, evaluate, predict and nate high or low lake level information.

This data is critical to the operation 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 of 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 routes. 118 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 27 Summary of Meteorological Data Recovery For The Davis-Besse Nuclear Power Station January 1, 2015 through December 31, 2015 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2015 lOOm Wind Speed 96.37 95.98 100 96.11 100 100 100 100 99.72 96.91 100 100 98.55 1 OQM Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100 75M Wind Speed 96.37 95.98 100 96.11 97.31 100 100 100 99.72 100 100 100 98.81 75M Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100 1 OM Wind Speed 96.37 95.98 100 96.11 97.31 100 100 100 99.72 100 100 100 98.81 1 OM Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100 lOM Ambient Air Temp 96.37 95.98 100 96.11 97.31 100 99.87 100 99.72 100 100 100 98.80 lOM Dew Point Temp 96.37 95.98 100 96.11 97.31 99.58 99.87 100 99.72 100 100 100 98.77 Delta T (lOOM-lOM) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 100 100 100 97.69 Delta T (75M-10M) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 100 100 100 97.69 Joint lOOM Winds and Delta T (lOOM-lOM) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 96.91 100 100 97.43 Joint 75M Winds and Delta T (lOOM-lOM) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 100 100 100 97.69 Joint lOM Winds and Delta T (75M-10M) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 100 100 100 97.69 *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 ment could be operable.

V aloes 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.

119 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 28 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1, 2015 through December 31, 2015 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2015 lOOMWIND Max Speed (mph) 35.66 38.74 33.65 41.57 39.17 50.29 26.85 32.50 35.74 41.37 44.28 47.98 50.29 Date of Max Speed 01/01 02/01 03/29 04/21 05/31 06/27 07/14 08/03 09/29 10/03 11112 12/28 06/27 Min Speed (mph) 2.37 1.86 2.37 1.97 2.63 1.99 2.14 1.82 3.02 2.05 1.66 2.00 1.66 Date of Min Speed 01130 02/16 03/20 . 04/29 05/10 06/20 07/27 08/09 09106 10/06 11108 12/12 11/08 Ave Wind Speed 17.64 16.21 15.70 17.08 15.50 15.54 12.04 12.63 14.70 18.57 18.48 18.05 16.13 75MWIND Max Speed (mph) 34.59 35.92 32.10 38.97 37.60 47.83 24.06 29.81 29.22 40.47 42.56 46.86 47.83 Date of Max Speed 01/01 02/01 03/25 04/21 05/31 06/27 07/14 08/03 09/29 10/03 11/12 12/28 06/27 Min Speed (mph) 2.28 1.57 2.39 1.56 2.21 2.17 2.09 2.23 3.01 2.00 2.16 2.00 1.56 Date of Min Speed 01/25 02/16 03/20 04/03 05/10 06/20 07/27 08/21 09/29 10/06 11/08 12115 04/03 Ave Wind Speed 16.20 14.90 14.29 15.64 14.01 14.45 11.13 11.67 13.08 17.10 16.89 16.35 14.75 lOMWIND Max Speed (mph) 26.97 24.56 23.68 29.68 25.65 32.59 19.73 22.51 24.68 25.05 31.61 26.87 32.59 Date of Max Speed 01101 02/02 03/25 04/21 05/31 06/27 07115 08/03 09/29 10/29 11/12 12/28 06/27 Min Speed (mph) 1.27 1.43 0.92 0.81 0.96 1.04 .1.07 1.01 0.77 1.21 1.24 1.09 0.77 Date of Min Speed 01/26 02/16 03/23 04/29 05/14 06/03 07/26 08/31 09/24 10/25 11104 12/22 09/24 Ave Wind Speed 10.79 9.17 8.59 9.86 8.26 9.05 ,' 6.68 6.75 7.37 10.03 9.70 9.57 8.95 120 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 28 (continued)

Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station

• January 1, 2015 through December 31, 2015 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2015 lOM AMBIENT TEMP Max (F) 43.72 43.98 60.24 74.47 87.43 85.85 88.30 88.20 89.07 79.03 73.90 66.48 89.07 --Date of Max 01/17 02/08 03/16 04/13 05/08 06/10 07/29 08/02 09/07 10/12 11104 12/12 09/07 Min (F) -3.84 -8.57 4.16 29.96 42.94 49.53 59.76 56.56 49.36 33.37 21.91 23.32 DateofMin 01108 02/20 03/06 04/04 05/20 06/01 07/16 08/28 09/13 10/17 11/23 12/20 02120 Ave Temp 21.94 14.77 33.02 47.95 63.46 68.36 72.13 71.10 69.15 55.55 47.71 42.04 48.74 lOM DEW POINT TEMP *Mean (F) -13.34 -18.44

-5.35 8.70 16.50 21.76 23.89 23.44 22.13 11.45 5.77 3.06 6.88 Max (F) 4.64 2.97 12.81 16.62 45.47 32.01 34.41 33.17 35.45 26.31 24.92 20.38 45.47 DateofMax 01/04 02/08 03/16 04/22 05/11 06/15 07/29 08/16 09/07 10/12 11/04 12112 05/11 Min (F) -37.66 -36.07 -26.42 -10.03 -10.99 8.51 15.03 14.12 7.96 -4.91 -11.88 -12.18 -36.07 Date of Min 01/08 02/20 03/06 04/04 05/12 06/01 07/04 08/26 09/13 10/17 11/23 12120 02/20 PRECIPITATION Total (inches) 2.04 1.17 0.93 2.53 2.04 6.56* 3.19 2.90 3.61 1.91 1.59 2.42 30.89* Max in One Day 1.05 0.37 0.34 1.17 1.05 2.91 1.86 0.88 1.21 1.04 0.54 0.92 2.91 Date 01103 02/04 03/26 04/09 05/03 06/27 07/09 08/03 09/03 10/28 11118 12128 06/27 *Note: Rain Data missing for period of 6-11-15 thru 6-17-15 due to clogged Rain Gauge (CR 2015-08348).

NOAA data showed 0.17" on 6-12-15, 0.23" on 6-13-15, 1.01" on 6-15-15 and 0.30" on 6-16-15. 121 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Ope rating Rep ort Figure 32 Wind Rose Annual Average lOOM txX>OQOOOj W I ND s::iEED ( PH) DIRECT ON ft) DAVIS-BESS ANNUAL 2015 100M LEVEL 122 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average 75M t2229@000!

WI r: SPE E.O (MPH: ---e DIRECTJO N FR EOu-CY '"' DAVIS-BESSE ANNUA L 2015 75M LEVEL 123 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Figure 34 Wind Rose Annual Average 1 OM IX)OOOOOOOOl w:NO SPEED (MPH) ---*DIRECTION rRCClUC"4CY (X) DAVIS-BESSE ANNUAL *2015 10M LEVEL 124 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 29 Joint Frequency Distribution by Stability Class STABILITY BASED ON: DELTA T WIND MEASURED AT: 35;0 FEET WIND THRESHOLD AT: 1.00 MPH * *** ANNUAL *** ST ABILITY CLASS A BETWEEN 250.0 AND 35.0 FEET JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 0 3.50 -7.49 24 7.50 -12.49 13 12.50 -18.49 0 18.50 -24.49 0 >24.49 2 TOTAL 39 0 11 1 3 4 0 19 0 5 0 7 4 17 0 2 27 10 5 3 47 STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH 4 10 2 0 0 17 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 2 12 5 0 0 0 18 STABILITY CLASS B BETWEEN 250.0 AND 35.0 FEET 0 18 7 4 0 0 29 0 14 30 11 1 0 56 0 6 20 13 0 0 39 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET 0 5 10 11 4 0 30 1 11 7 6 0 0 25 1 10 14 14 0 0 39 0 5 7 6 0 0 18 0 4 127 153 87 18 6 395 SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 0 3.50-7.49 4 7.50 -12.49 10 12.50 -18.49 6 18.50 -24.49 0 >24.49 0 TOTAL 20 17 4 0 0 0 22 0 5 5 0 12 0 6 52 9 3 0 70 0 14 2 0 0 17 0 0 0 0 2 DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 0 2 0 0 0 0 2 125 0 0 4 8 1 0 1 0 0 0 0 5 10 0 19 12 2 0 0 33 17 24 16 3 0 61 1 6 14 8 5 4 38 0 3 8 1 0 0 12 3 10 0 0 15 5 19 3 0 0 28 0 7 11 2 0 0 20 0 5 108 186 52 12 4 367 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH * *** ANNUAL***

• • • ANNUAL *** STABILITY CLASS C BETWEEN 250.0 AND 35.0 FEET JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50-7.49 7.50 -12.49 12.50 -18.49 18.50 -24.49 >24.49 TOTAL 0 4 5 0 0 IO 0 IO 4 7 0 0 21 0 8 19 1 0 0 28 16 52 8 0 0 77 STABILITY BASED ON: DELTA T WIND MEASURED AT: WIND THRESHOLD AT: 35.0FEET 1.00MPH 1 9 23 3 0 0 36 0 8 2 0 0 0 IO 3 2 0 0 0 6 0 1 0 0 0 0 4 11 2 2 0 0 19 ST ABILITY CLASS D BETWEEN 250.0 AND 35.0 FEET 21 24 8 0 0 19 53 43 IO 2 54 128 0 7 28 20 12 8 75 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET 0 4 13 5 2 0 24 0 6 IO 6 0 0 22 0 8 13 12 0 0 33 0 6 17 6 0 0 29 0 9 141 267 121 24 11 573 SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 4 4 6 5 IO 3.50-7.49 33 51 67 112 151 7.50-12.49 54 81 148 193 161 12.50 -18.49 47 112 83 44 18 18.50 -24.49 11 25 31 32 4 >24.49 5 3 6 IO TOTAL 154 276 341' 396 345 5 86 28 0 0 0 119 9 40 14 5 0 0 68 126 11 46 26 9 0 0 92 20 8 16 75 98 101 67 158 221 10 62 225 0 1 57 0 0 13 172 327 633 6 11 67 35 203 IOO 194 67 80 19 11 0 561 232 6 20 50 34 6 0 116 3 31 57 81 21 0 193 8 31 60 42 7 0 148 0 132 I044 1621 1033 294 49 4173 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH *** ANNUAL *** STABILITY CLASS E BETWEEN 250.0 AND 35.0 FEET JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50-7.49 7.50 -12.49 12.50 -18.49 18.50 -24.49 >24.49 TOTAL 7 6 7 12 1 34 5 16 15 3 0 40 3 14 18 6 0 0 41 2 56 32 4 1 0 95 STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH 28 113 35 8 0 0 184 21 98 17 2 0 0 138 46 53 76 53 23 28 13 0 0 0 0 146 147 70 32 24 154 261 152 .68 138 167 22 62 76 0 0 7 0 0 314 493 427 ST ABILITY CLASS F BETWEEN 250.0 AND 35.0 FEET 13 89 112 21 4 0 239 5 47 64 5 0 0 121 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET 7 27 31 7 2 0 74 9 18 29 7 1 0 64 9 20 19 8 0 0 56 334 1200 803 257 17 2 2614 SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50 -7.49 7.50 -12.49 12.50 -18.49 18.50 -24.49 >24.49 TOTAL 3 0 1 0 0 0 4 2 2 0 0 0 5 0 2 2 2 0 0 6 5 11 2 0 0 0 18 5 17 5 0 0 0 27 7 36 3 0 0 0 46 18 25 0 0 0 0 43 127 63 78 74 29 67 148 0 1 4 0 0 0 0 0 0 0 0 0 92 146 226 31 50 12 0 0 0 93 20 33 4 0 0 0 57 9 35 7 0 0 0 51 7 8 3 0 0 0 18 4 3 5 0 0 0 12 4 1 0 0 0 6 3 330 467 51 2 0 0 853 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH *** ANNUAL *** ST ABILITY CLASS G BETWEEN 250.0 AND 35.0 FEET JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50 -7.49 7.50-12.49 12.50 -18.49 18.50 -24.49 >24.49 TOTAL 0 0 0 0 0 0 0 0 2 0 0 0 0 2 0 0 0 0 0 0 0 1 8 1 0 0 0 10 STABILITY BASED ON: DELTA T WIND MEASURED AT: WIND THRESHOLD AT: 35.0FEET l.OOMPH 6 11 0 0 0 0 17 6 21 0 0 0 0 27 7 9 0 0 0 0 16 18 7 0 0 0 0 25 36 31 0 0 0 0 67 ST ABILITY CLASS ALL BETWEEN 250.0 AND 35.0 FEET 52 44 0 0 0 0 96 17 22 0 0 0 0 39 5 3 0 0 0 0 8 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET v 8 3 0 0 0 0 11 3 0 0 0 0 4 0 3 0 0 0 0 3 2 0 0 0 0 0 2 0 159 167 1 0 0 0 327 SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50 -7.49 7.50-12.49 12.50-18.49 18.50 -24.49 >24.49 TOTAL 14 71 90 65 12 9 261 12 109 106 125 30 3 385 9 101 192 100 36 7 445 14 211 359 75 41 13 713 51 306 248 33 4 1 643 39 250 51 2 0 0 342 81 155 39 6 0 0 281 128 145' 209 140 358 57 144 22 35 0 0 0 0 364 746 167 90 609 375 343 507 138 37] 1 78 0 16 1258 1437 45 211 381 256 101 23 1017 33 132 202 89 25 0 481 23 78 111 54 8 0 274 18 78 137 117 22 0 372 23 70 115 64 7 0 279 4 973 3254 3082 1552 365 72 9302 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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.

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 control and beach formation.

Revetments are built with a gradual slope, which causes waves to dissipate 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 water 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 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 importance 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 before continuing their migration.

The Black Swamp Bird Observatory, a volunteer research group, tures, 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, 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. Over two dozen eagles have fledged from these two nests since 1994. Ohio has gone from a low of 4 nesting eagle pairs statewide in 1978 to setting new hatch records every year for over three decades. 129 Davis-Besse Nuclear Power Station 2015 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, tion, electrolysis and demineralization to produce high-purity water used in many of the Station'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 water. The next step of the process is reverse osmosis, where pressure is used to remove certain impurities 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 mineralization process before being sent to storage. Domestic Water When Davis-Besse began operation over 35 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 ter to Davis-Besse.

Carroll Township Water and Wastewater District follow all applicable latory 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 . I 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.

• Zebra mussels have not caused any significant problems at Davis-Besse due to effective biocide . control. At present, the mussel populations are declining.

130 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Algae Control 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 cufating 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 ational challenges.

Wastewater Treatment Plant (WWTP) Operation The WWTP operation is supervised by an Ohio licensed Wastewater Operator.

Wastewater erated by site personnel is treated in an onsite extended aeration package treatment facility 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. ygen 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 organisms necessary for continued treatment, and is pumped back to the aeration tank to c;ligest incoming wastewater.

The effluent leaving the plant is drained to the wastewater basin (NPDES Outfall 601) where further treatment takes place. National Pollutant Discharge Elimination System (NPDES) Reporting The Ohio Environmental Protection Agency (OEP A) has established limits on the amount of 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 2IB00011 *JD. 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 Outfall 002 Area Runoff: Discharge to Toussaint River 131 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 2015 NPDES Summary There were two National Pollutant Discharge Elimination System (NPDES) violations in 2015. On October 2, 2015 Total Residual Oxidants (TRO) measured 0.19 parts per million (PPM) at Outfall 001. This concentration exceeded the permit limitation of 0.05 PPM. On December 17, 2015 Total Residual Chlorine (TRC) measured 0.29 PPM at Outfall 001.This concentration exceeded the permit limitation of 0.2 PPM. In both instances, the Station rination System was isolated until chlorine concentration was restored to below permit tions. 132 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Chemical Waste Management The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes erated at the Davis-Besse Nuclear Power Station was developed to ensure wastes are managed and disposed of in accordance with all applicable state and federal regulations.

Resource Conservation and Recovery Act The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid 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 human health and the environment and to encourage the establishment of solid waste management, source recovery, and resource conservation systems. The intent of the hazardous waste ment 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 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 grams/month (220 lbs./month).

In 2015, the Davis-Besse Nuclear Power Station generated approximately 4,166 pounds of ardous waste. Non-hazardous waste generated in 2015 included 1,329 gallons of used oil and 21,488 pounds of other nonhazardous wastes such as oil filters, resins and caulks. RCR,A 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 throughout 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 inspected weekly by Environmental and Chemistry personnel.

All areas used for storage or lation 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 mulation area for employees to record the waste type and amount when chemicals are 133 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report added to the drum. This ensures that incompatible wastes are not mixed and also identifies 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 perfund) established a federal authority and source of funding for responding to spills and other releases of hazardous materials, pollutants and contaminants into the environment.

Superfund establishes , "reportable quantities" for several hundred hazardous materials and regulates the cleanup of abandoned hazardous waste disposal sites. Superfund Amendment and Reauthorization Act (SARA) ' Superfund was amended in October 1986 to establish new reporting programs dealing with emer-gency 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 icals are present in reportable quantities.

Annual SARA reports are submitted to local fire departments and state and local planning 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 USEP A with the authority to require testing of new chemical substances for potential health effects before they are introduced into the environment, and to regulate them where necessary.

This law would have little impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management system, very similar to the hazardous waste management system established under RCRA. In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers onsite. PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with non-PCB liquid. Retro-filling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with 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.

134 Davis-Besse Nuclear Power Station 2015 AnnuaLRadiological 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, cluding the Station Blackout Diesel Generator, the 2 Emergency Diesel Generators, the Emergency 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 V" legislation, an independent study identifying and quantifying all of the air pollution sources onsite was performed.

Of particular significance is asbestos removal from renovation and demolition projects for which USEP A has outlined specific regulations concerning handling, removal, environmental protection, and disposal.

Also, the cupational 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 ered a hazardous waste by RCRA, but the EPA does require special handling and disposal of this waste under the Clean Air Act. Transportation Safety Act The transportation of hazardous chemicals, including chemical waste, is regulated by the 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 ing, handling, labeling, marking, and placarding.

Before any wastes are transported off site, Besse must ensure that the wastes are identified, labeled and marked according to DOT tions, including verification that the vehicle has appropriate placards and it is in good operating condition.

135 Davis-Besse Nuclear Power Station 2015 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 provide protection from tank contents leaking and causing damage to the environment.

Additional standards require leak detection systems and performance standards for new tanks. At Davis-Besse two 40,000 gallon and one 8,000 gallon diesel fuel storage tanks are registered USTs. Spill Kits Spill control equipment is maintained throughout the Station at chemical storage areas and ardous chemical and oil use areas. Equipment in the kits may include chemical-resistant coveralls, gloves, boots, decontfilnination agents, absorbent cloth, goggles and warning signs. Waste Minimization and Recyding / Municipal Solid Waste (MSW) is normal trash produced by individuals at home and by industries.

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 majority 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, otherwise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing landfills by reducing the amount of MSW produced, by reusing certain waste material, and by recycling 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 duction, reuse, recycle approach to MSW management.

An active Investment Recovery Program has greatly contributed to the reduction of both hazardous and municipal waste generated by uating 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.

Pa,per and cardboard recycling is typically in excess of 50 tons annually.

This repre-. I sen ts 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 disposal. . Although scrap metal is not usually considered part of the MSW stream, Davis-Besse collects 1 and recycles scrap metals, which are sold at market price to a scrap dealer for resource recovery.

136 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report All Environmental, Inc.

• Jf/tli.. /""'\I Midwest Laboratory 1 700 Landwehr Road* Northbrook, IL 60062-2310 phone (847) 564-0700 *fax (847) 564-4517 NOTE: APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS 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. TU) lntercomparison 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, 2015 through December, 2015 137 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Appendix A lnterlaboratory 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 radionuclidi known to the issuing agency but not to participant laboratories.

The purpose of such a program is to pro 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 them to the issu 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 contrc 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 prograr 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 (Tl.Os), via International lntercomparison 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 sam 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 twelVI 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 Evaluatio1 Program. Results irt Table A-7 were obtained through participation in the environmental sample crosscheck progra1 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 cri* in Table A-3 is set at +/- 2 sigma. Out-of-limit results are explained directly below the result. A1 138 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION:

ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa Analysis Gamma Emitters Strontium-89b Strontium-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium lodine-131, lodine-129b Uranium-238, Nickel-63b Technetium-99b lron-55b Other Analyses b Level 5 to 100 pCi/liter or kg > 100 pCi/liter or kg 5 to 50 pCi/liter or kg > 50 pCi/liter or kg 2 to 30 pCi/liter or kg > 30 pCi/liter or kg 0.1 g/liter or kg s 20 pCi/liter . > 20 pCi/liter s 100 pCi/liter > 1 00 pCi/liter s 4,000 pCi/liter

> 4,000 pCi/liter 0.1 pCi/liter 0.1 pCi/liter, gram, or sample s 55 pCi/liter

> 55 pCi/liter s 35 pCi/liter

> 35 pCi/liter 50 to 100 pCi/liter

> 100 pCi/liter One standard deviation for single determination 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 5.0 pCi/liter 10% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value +/- 1cr = 169.85 x (known)0*0933 10% of known value 15% of known value 10% of known value 6 pCi/liter 10% of known value 6 pCi/liter 15% of known value 1 O pCi/liter 10% of known value 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limt. A2. 139 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-1. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERAt Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41.so 30.80 -48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/-4.69 82.50 69.30 -90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/-3.08 75.70 61.80 -83.30 Pass ERW-1448 4/6/2015 Cs-137 191.9 +/- 5.9 189.0 170.0 -210.0 Pass ERW-1448 4/6/2015 Co-60 85.05 +/-4.59 84.50 76.00 -95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 -238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05+/-1.90 42.60 22.10 -54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93+/-1.12 32.90 21 .30 -40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 -28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/-0.56 8.43 6.33 -9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56 -6.01 Pass ERW-1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770 -3,620 Pass ERW-5528 10/5/2015 Sr-89 34.76 +/-0.06 35.70 26.70 -42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 -36. 70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.57 62.30 50.69 -68.50 Pass ERW-5531 10/5/2015 Cs-137 163.1 +/-4.8 157.0 141 .0 -175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71.10 64.00 -80. 70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 113.0 -149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 -64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/- 0.04 36.60 24.1 0 -44.20 Pass ERW"5537 10/5/2015 1-131 25.54 +/- 0.60 26.30 21.90 -31.00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49 -8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46 -5.85 Fail ERW-5540e 10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 -5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 -62.40 Pass ERW-5543 10/5/2015 H-3 21,260 +/- 351 21,300 18,700 -23,400 Pass

• 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). b Unless otherwise indicated, the laboratory result is given as the mean +/-standard deviation for three determinations.

0 Results are as the known values, expected lab.oratory precision (1 sigma, 1 determination) and control limits as provided by ERA. d Ra-228 spike'was at a level close to the detection level. The high result was likely caused by interference Jrom short-lived Rn-222 daughters.

• The result of reanalysis (Compare to original result, footnoted "e" above). AH 140 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS0 4: Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance

• Environmental.

Inc. 2015-1 6/24/2015 30cm. 98.81 103.67 +/- 6.05 69.20 -128.50 Pass 2015-1 6/24/2015 30cm. 98.81 111.32 +/- 15.97 69.20 -128.50 Pass 2015-1 6/24/2015 60cm. 24.70 27.23+/-1.33 17.30 -32.10 Pass 2015-1 6/24/2015 60cm. 24.70 26.98 +/-4.98 17.30 -32.10 Pass 2015-1 6/24/2015 120 cm. 6.18 6.71 +/- 1.77 4.30 -8.00 Pass 2015-1 6/24/2015 120 cm. 6.18 6.78 +/-0.38 4.30 -8.00 Pass 2015-1 6/24/2015 120 cm. 6.18 6.43 +/- 2.00 4.30 -8.00 Pass 2015-1 6/24/2015 150 cm. 3.95 4.13 +/- 0.72 2.80 -5.10 Pass 2015-1 6/24/2015 150 cm. 3.95 4.12 +/- 1.36 2.80 -5.10 Pass 2015-1 6/24/2015 150 cm. 3.95 4.50 +/- 1.51 2.80 -5.10 Pass 2015-1 6/24/2015 180 cm. 2.74 3.27 +/- 0.28 1.90 -3.60 Pass 2015-1 6/24/2015 180 cm. 2.74 3.05+/-1.11 1.90 -3.60 Pass 2015-1 6/24/2()15 180 cm. 2.74 3.14 +/-0.18 1.90 -3.60 Pass A2-1 141 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4: Dy Cards). b mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Acceptance d Environmental.

Inc. 2015-2 12/15/2015 Spike 1 138.0 118.5 +/- 2.1 -0.14 Pass 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 -0.13 Pass 2015-2 5/2015 Spike 3 138.0 121.9 +/- 1.9 -0.12 Pass 2015-2 12/15/2015 Spike 4 138.0 124.5 +/- 3.3 -0.10 Pass 2015-2 12/15/2015 Spike 5 138.0 126.5 +/- 3.2 -0.08 Pass 2015-2 12/15/2015 Spike 6 138.0 140.0 +/-4.2 0.01 Pass 2015-2 12/15/2015 Spike 7 138.0 128.2+/-1.2

-0.07 Pass 2015-2 12/15/2015 Spike 8 138.0 128.0 +/- 4.0 -0.07 Pass 2015-2 12/15/2015 Spike 9 138.0 124.9 +/- 5.1 -0.09 Pass 2015-2 12/15/2015 Spike 10 138.0 122.9 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 12 138.0 119.0 +/- 3.4 -0.14 Pass 2015-2 12/15/2015 Spike 13 138.0 123.0 +/-2.7 -0.11 Pass 2015-2 12/15/2015 Spike 14 138.0 125.4 +/- 2.0 -0.09 Pass 2015-2 12/15/2015 Spike 15 138.0 122.0 +/- 3.1 -0.12 Pass 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 -0.12 Pass 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 -0.14 Pass 2015-2 12/15/2015 Spike 18 138.0 117.0 +/-2.3 -0.15 Pass 2015-2 12/15/2015 Spike 19 13RO 120.8 +/- 2.6 -0.12 Pass 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 -0.11 Pass Mean (Spike 1-20) 123.4 0.11 Pass Standard Deviation (Spike 1-20) 5.0 0.04 Pass

• TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) 0 Performance Quotient (P) is calculated as ((reported dose -conventially true value) + conventially true value) where the conventially true value is the delivered dose. d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15. e Tables A2.1 and A2.2 assume 1 roentgen=

1 rem (per NRG -Health Physics Positions Based on 10 CFR Part 20 -Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015). A2-2 142 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-3. In-House "Spiked" Samples Lab Code b W-020315 W-021215 W-021215 SPW-687 SPAP-689 SPAP-691 SPAP-691 SPW-693 SPW-693 SPW-693 SPW-693 SPMl-697 SPMl-697 SPMl-697 SPMl-697 SPW-699 W-031115 W-030215 SPF-1040 SPF-1040 SPW-1036 SPW-1374 W-040815 W-040815 SPW-1038 W-2165 W-2165 W-2165 W-2165 W-2165 W-2392 W-2392 W-2392 W-2392 W-042415 W-050715 W-050715 W-061215 W-061215 U-2982 U-3200 W-70915 W-70915 SPAP-3859 SPAP-3861 Date 2/3/2015 2/12/2015 2/12/2015 2/27/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/25/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/11 /2015 3/2/2015 3/16/2015

3/16/2015

3/25/2015 4/6/2015 4/8/2015 4/8/2015 4/13/2015 4/20/2015 4/20/2015

4/20/2015

4/20/2015 4/20/2015 4/13/2015

4/13/2015

4/13/2015 4/13/2015 4/24/2015 517/2015 517/2015 6/12/2015 6/12/2015 6/9/2015 6/9/2015 7/9/2015 7/9/2015 7/21/2015 7/21/2015 Analysis Ra-226 Gr. Alpha Gr. Beta Ni-63 Gr. Beta Cs-134 Cs-137 Cs-134 Cs-137 Sr-89 Sr-90 Cs-134 Cs-137 Sr-89 Sr-90 H-3 Ra-226 Ra-228 Cs-134 Cs-137 Fe-55 U-238 Gr. Alpha Gr. Beta C-14 H-3 Sr-89 Sr-90 Cs-134 Cs-137 H-3 Ni-63 Cs-134 Cs-137 Ra-226 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Beta H-3 Gr. Alpha Gr. Beta Gr. Beta *1 Cs-134 Concentration (pCi/L)a Laboratory results 2s, n=1 c 16.19 +/- 0.42 18.38 +/- 0.39 27.98 +/- 0.32 239.6 +/- 3.5 42.37 +/- 3.50 1.77 +/- 0.61 83.02 +/- 2.60 44.30 +/- 2.53 74.82 +/- 3.50 87.45 +/- 3.62 37.22 +/- 1.55 96.67 +/- 7.74 78.51 +/- 7.02 72.98 +/- 4.86 39.17 +/- 1.51 59,592 +/- 703 13.73 +/- 0.35 32.79 +/- 2.31 787.5 +/- 9.2 2,599 +/- 24 1,792 +/- 63 46.03 +/- 2.25 20.18 +/- 0.42 29.70 +/- 0.33 3,497 +/- 9 5550 +/- 226 90.70 +/- 8.20 76.80 +/- 2.00 62.40 +/- 6.40 91.30+/-7.70 5032 +/- 214 222.4 +/- 3.8 53.26 +/- 5.01 91.90 +/- 7.76 12.52 +/- 0.39 19.05 +/- 0.41 27.30 +/- 0.32 20.72 +/- 0.44 28.51 +/- 0.33 500.1 +/- 5.1 2229 +/- 424 18.76 +/- 0.40 29.71 +/- 0.33 41.59 +/- 0.12 1.69 +/- 0.60 A3-1 143 Known Activity 16.70 20.10 30.90 202.4 43.61 1.90 97.20 53.40 73.80 87.48 38.10 107.00 73.84 87.48 38.10 58,445 16.70 31.44 840.0 2,360 1961 41.70 20.10 30.90 4,734 5,780 108.70 75.90 57.30 84.00 5780 202.0 57.30 84.20 16.70 20.10 30.90 20.10 30.90 604.0 2346 20.10 30.90 43.61 1.69 Control Limits d 13.36 -20.04 16.08 -24.12 24.72 -37.08 161.9 -242.9 34.89 -52.33 1.52 -2.28 77.76 -116.64 42.72 -64.08 59.04 -88.56 69.98 -104.98 30.48 -45.72 85.60 -128.40 59.07 -88.61 69.98 -104.98 30.48 -45.72 46,756 -70,134 13.36 -20.04 25.15 -37.73 672.0 -1,008.0 1,888 -2,832 1,569 -2,353 25.02 -58.38 16.08 -24.12 24.72 -37.08 2,840 -6,628 3,468 -8,092 65.22 -152.18 4$.54 -106.26 34.38 -80.22 50.40 -117.60 3468 -8092 121.2 -282.8 34.38 -80.22 50.52 -117.88 10.02 -23.38 12.06 -28.14 18.54 -43.26 12.06 -28.14 18.54 -43.26 362.4 -845.6 1408 -3284 12.1 -28.1 18.5 -43.3 26.17 -61.05 1.0 -2.4 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass. Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-3. In-House "Spiked" Samples Concentration

(!:!Ci/Lt Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 ° Limitsd Acce!:!tance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 -135.03 Pass SPMl-3863 7/21/2015 Cs-134 38.21 +/- 5.12 47.02 28.21 -65.83 Pass SPMl-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 -102.45 Pass SPMl-3863 7/21/2015 Sr-90 41.05+/-1.62 37.78 22.67 -52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 -65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 -102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 -52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319 -80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 -565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 -754.7 Pass SPMl-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 -6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 -56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 -44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5+/-115.9 740.0 444.0 -1036.0 Pass SPF-4104 7/29/2015 Cs-137 2,469 +/- 59 2,340 1,404 -3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06 -28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58

+/- 0.32 30.90 18.54 -43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 -23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06 -28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 -43.26 Pass W-091415 9/14/2016 Gr. Alpha 19.35 +/- 0.51 20.10 12.06 -28.14 Pass W-091415 9/14/2016 Gr. Beta 31.53 +/- 0.35 30.90 18.54 -43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02 -23.38 Pass W-100615 10/6/2016 Gr. Alpha 20.62 +/- 0.43 20.10 12.06 -28.14 Pass W-100615 10/6/2016 Gr. Beta 29.35 +/- 0.33 30.90 18.54 -43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280 -7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52 -138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 -116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 -23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86 -44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738 -15,723 Pass W-6086,6087 11 /18/2015 Cs-134 92.98 +/- 7.29 96.25 57.75 -134.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76 -116.12 Pass W-112515 11 /25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06 -28.14 Pass W-112515 11 /25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54 -43.26 Pass W-120715 1217/2015 Fe-55 2,431 +/- 97 2,319 1,391 -3,247 Pass W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06 -28.14 Pass W-120815 12/8/2015 Gr. Beta 29.50 +/- 0.33 30.90 18.54 -43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02 -23.38 Pass

• Liquid sample results are reported in pCi/Liter, air filters{ pCi/m3), charcoal {pCi/charcoal canister), and solid samples {pCi/kg).

b Laboratory codes : W {Water), Ml (milk), AP {air filter), SO {soil), VE {vegetation), CH {charcoal canister), F (fish), U {urine). 0 Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2s. NOTE: For fish, Jello is used for the spike matrix. For vegetation, cabbage is used for the spike matrix. A3-2 144

. Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)0 Lab Code Sample Date Analysisb Laborato!l'.

results (4.66cr) Acceptance Type LLD Activityc Criteria (4.66 cr) W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/- 0.02 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/- 0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/- 0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74+/-1.42 20 ' SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785+/-1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/- 0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1.57 +/- 3.55 *10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/- 3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/-0.33 SPMl-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/-2.24 10 SPMl-696 Milk 3/212015 Cs-137 4.36 -0.25 +/-2.24 10 SPMl-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMl-696 Milk 3/2/2015 Sr-90 0.49 0.98 +/- 0.32 SPW-698 Water 3/2/2015 H-3 "144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/- 368.1 1000 SPW-1037 Water 3/16/2015 C-14 8.94 2.16 +/-5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1.00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/- 0.25 2 W-050715 Water 5/7/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/-0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/-0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 : 0.009 0.000 +/- 0.005 0.05 SPMl-3862 Milk 7/21/2015 Cs-134 3.13 1.56+/-1.74 10 SPMl-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMl-3862 Milk 7/21/2015 Sr-89 2.17 -1.30 +/- 2.05 5 SPMl-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 SPW-3870 Water 7/21/2015 Sr-89 2.28 -0.42 +/- 1.80 5 SPW-3870 Water 7/21/2015 Sr-90 0.84 0.25 +/-0.42 A4-1 145 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-4. In-House "Blank" Samples Concentration (pCi/Lt Lab Code Sample Date Analysisb LaboratO!)'.

results (4.66crl Acceptance Type LLD Activity 0 Criteria (4.66 cr) SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77+/-1.82 20 SPW-3876 Water . 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52+/-10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51.3 +/-83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/-8.06 100 W-081015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015 Ra-226 0.03 0.03 +/- 0.02 2 W-090615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/- 0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/- 0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/-0.52 4 W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/- 0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/-0.29 2 W-120815 Water 12/8/2015 Gr. Beta 0.76 0.17 +/-.0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2

• Liquid sample results are reported in pCi/Liter, air filters( pCi/m 3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b l-131(G);

iodine-131 as analyzed by gamma spectroscopy.

0 Activity reported is a net activity result. A4-2 146 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Lab Code CF-62,63 CF-62,63 CF-62,63 CF-62,63 SG-83,84 SG-83,84 SG-83,84 SG-83,84 SG-83,84 SG-83,84 SG-83,84 AP-011215A/B WW-315,316 DW-60010,60011

DW-60010,60011 SG-336,337 SG-336,337 SG-336,337 AP-020415A/B AP-021115A/B DW-60023,60024 DW-60023,60024 S-799,800 S-799,800 S-799,800 S-799,800 S-799,800 SG-834,835 SG-834,835 DW-60031,60032 DW-60036,60037 DW-60036,60031 DW-60048,60049

DW-60048,60049 AP-1169, 1170 DW-60069,60070 AP-040915 WW-2394,2395 SG-1847,1848 SG-1847,1848

SG-1847,1848 XWW-2267,2268 XWW-2078,2079 Date 1/7/2015 1/7/2015 1/7/2015 1/7/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/27/2015

1/28/2015 1/28/2015 1/30/2015 1/30/2015 1/30/2015 2/4/2015 2/11/2015 2/26/2015 2/26/2015 2/26/2015 2/26/2015 2/26/2015 2/26/2015 2/26/2015 2/2/2015 2/2/2015 3/4/2015 3/4/2015 3/4/2015 3/4/2015 3/4/2015 3/19/2015 4/8/2015 4/9/2015 4/13/2015 4/20/2015

4/20/2015

4/20/2015 4/23/2015 4/27/2015 Analysis Gr. Beta Be-7 K-40 Sr-90 K-40 Tl-208 Pb-212 Pb-214 Bi-214 Ra-226 Ac-228 Gr. Beta H-3 Ra-226 Ra-228 Bi-214 Pb-214 Ac-228 Gr. Beta Gr. Beta Ra-226 Ra-228 K-40 Tl-208 Pb-212 Bi-212 Ac-228 Gr. Alpha Gr. Beta Gr. Alpha Ra-226 Ra-228 Ra-226 Ra-228 Be-7 Gr. Alpha Gr. Beta H-3 K-40 Pb-214 Ac-228 H-3 H-3 First Result 5.72+/-0.12 0.915 +/- 0.135 3.97 +/- 0.28 0.017 +/- 0.006 10.11 +/- 1.42 0.57 +/-0.07 1.73 +/-0.10 13.33 +/- 0.33 13.48 +/- 0.39 25.68 +/-2.19 13.33 +/-0.59 0.025 +/- 0.004 1,961 +/- 178 1.25 +/- 0.14 2.00 +/-0.66 6.63 +/-0.20 6.45 +/-0.19 4.43 +/-0.24 0.021 +/- 0.004 0.034 +/- 0.004 1.52 +/- 0.15 0.97 +/- 0.48 11.96 +/-0.98 0.36 +/-0.04 0.92 +/-0.06 1.26 +/- 0.45 1.35 +/- 0.22 113.3 +/- 6.3 82.27 +/-2.79 185.4 +/- 7.4 6.89 +/- 0.34 4.43 +/- 0.73 0.84 +/-0.10 0.68 +/- 0.41 0.20 +/- 0.02 3.58 +/- 0.88 0.027 +/- 0.005 1,628 +/- 139 3.24+/-1.18 5.80 +/- 0.22 5.26 +/- 0.51 6,584 +/-244 359.0 +/-89.6 A5-1 147 Concentration (pCi/L)" Second Result 5.78 +/-0.12 0.919 +/- 0.102 3.88 +/- 0.23 0.011 +/- 0.006 9.69+/-1.20 0.56 +/- 0.06 1.58 +/- 0.09 13.88 +/- 0.28 13.45 +/- 0.29 26.22+/-1.53 12.86 +/- 0.43 0.023 +/- 0.004 1,868+/-174 1.40 +/-0.15 1.39 +/- 0.60 6.45 +/- 0.45 6.45 +/- 0.37 4.20 +/- 0.58 0.019 +/- 0.035 0.040 +/- 0.047 1.51 +/- 0.15 1.66 +/- 0.58 11.49 +/- 0.82 0.31 +/- 0.04 0.91 +/- 0.06 1.50 +/- 0.40 1.23 +/- 0.17 117.2 +/- 2.8 84.33 +/- 2.74 177.0 +/- 7.2 6.88 +/- 0.32 4.41 +/- 0.72 0.94 +/- 0.11 1.42 +/- 0.58 0.24 +/- 0.10 3.92 +/- 0.88 0.023 +/- 0.005 1,695 +/- 141 1.99 +/- 0.76 6.23 +/- 0.76 5.00 +/- 0.42 6,164 +/-237 418.7 +/-92.3 Averaged Result 5.75 +/- 0.42 0.917 +/-0.15 3.92 +/- 0.33 0.014 +/- 0.004 9.90+/-1.16 0.57 +/- 0.05 1.65 +/-0.13 13.61 +/- 0.22 13.47 +/- 0.24 25.95+/-1.34 13.09 +/- 0.36 0.024 +/- 0.003 1,915+/-124 1.33 +/- 0.10 1.70 +/- 0.45 6.54 +/- 0.21 6.45 +/- 0.21 4.32 +/-0.31 0.035 +/- 0.020 0.037 +/- 0.003 1.52 +/- 0.11 1.32 +/- 0.38 11.72 +/- 0.64 0.34 +/- 0.03 0.91 +/- 0.05 1.38 +/- 0.30 1.29 +/- 0.14 115.2 +/-3.4 83.30+/-1.96 181.2 +/-5.2 6.89 +/-0.23 4.42 +/- 0.51 0.89 +/-0.07 1.05 +/- 0.36 0.22 +/- 0.07 3.75 +/- 0.62 0.025 +/- 0.003 1,662 +/- 99 2.62 +/- 0.70 6.02 +/- 0.40 5.13 +/- 0.33 6,374+/-170 388.9 +/- 64.3 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Lab Code XWW-2162,2163 SG-1868, 1869 SG-1868, 1869 SG-1868, 1869 SG-1868, 1869 AP-042915 DW-60076,60077 AP-050515 AP-051115 DW-60087,60088 DW-60087,60088 SG-2436,2437 SG-2436,2437 SG-2436,2437 SG-2458,2459 SG-2458,2459 DW-60095,60096 AP-052715 8"2627,2628 S-2627,2628 S-2627,2628 S-2605,2606 S-2605,2606 S-2605,2606 S-2605,2606 S-2858,2859 S-2858,2859 S-2858,2859 AP-060315 DW-30107,30108 SG-2900,2901 SG-2900,2901 AP-061515 XWW-3173,3174 AP-062215 S-3216,3217 S-3216,3217 VE-3300,3301 VE-3300,3301 AP-062915 WW-3632,3633 Date 4/28/2015 4/28/2015 4/28/2015 4/28/2015 4/28/2015 4/29/2015 5/4/2015 5/5/2015 5/11/2015 5/14/2015 5/14/2015 5/15/2015 5/15/2015 5/15/2015 5/19/2015 5/19/2015 5/26/2015 5/27/2015 5/29/2015 5/29/2015 5/29/2015 6/1/2015 6/1/2015 6/1/2015 6/1/2015 6/2/2015 6/2/2015 6/2/2015 6/3/2015 6/8/2015 6/9/2015 6/9/2015 6/15/2015 6/18/2015 6/22/2015 6/24/2015 6/24/2015 6/24/2015 6/24/2015 6/29/2015

6/30/2015 Analysis H-3 Gr. Alpha Gr. Beta Pb-214 Ra-228 Gr. Beta Ra-228 Gr. Beta Gr. Beta Ra-226 Ra-228 Pb-214 Ra-228 Gr. Alpha Pb-214 Ra-228 Gr. Alpha Gr. Beta Pb-214 Ac-228 Cs-137 Ac-228 Ra-226 K-40 Cs-137 Cs-137 Be-7 K-40 Gr. Beta Gr. Alpha Ac-228 Pb-214 Gr. Beta H-3 Gr. Beta K-40 Be-7 Be-7 K-40 Gr. Beta H-3 First Result 4,408 +/- 201 47.57 +/- 3.63 50.90+/-1.94 13.80 +/- 0.52 20.10 +/- 0.92 0.014 +/- 0.003 2.89 +/- 0.61 0.026 +/- 0.004 0.006 +/- 0.005 1.58 +/- 0.17 0.94 +/- 0.50 22.90 +/-2.31 47.95 +/- 0.61 267.8 +/- 7.9 75.00 +/- 1.66, 41.10 +/-0.92 1.34 +/- 0.69 0.010 +/- 0.003 0.85 +/-0.07 0.85 +/-0.14 0.07 +/-0.02 0.42 +/- 0.06 0.44 +/- 0.03 10.89 +/- 0.51 0.05 +/- 0.01 34.30 +/- 16.05 1501 +/- 264 22,122 +/- 658 0.022 +/- 0.004 1.34 +/- 0.82 10.22 +/- 1.36 7.55 +/- 0.43 0.022 +/- 0.004 841.9+/-123.6 0.023 +/- 0.004 10.38 +/- 0.51 3.65 +/- 0.24 0.78 +/- 0.15 29.12 +/- 0.62 0.023 +/- 0.005 5,169 +/-225 A5-2 148 Concentration (pCi/L)" Second Result 4,242+/-198 43.61 +/- 3.58 51.90 +/-2.02 13.54 +/- 0.62 22.10+/-1.29 0.014 +/- 0.003 2.45 +/- 0.57 0.025 +/- 0.004 0.010 +/- 0.005 1.52 +/-0.17 0.94 +/- 0.50 24.10 +/- 2.43 47.80 +/- 0.71 254.6 +/- 7.6 77.70+/-1.75 40.80 +/- 0.83 0.91 +/- 0.62 0.010 +/- 0.003 0.85 +/- 0.07 1.08 +/- 0.12 0.07 +/- 0.02 0.38 +/-0.07 0.49 +/- 0.03 11.40 +/- 0.48 0.05 +/- 0.01 40.66 +/- 17.79 1171 +/-214 20,987 +/- 600 0.021 +/- 0.004 1.47 +/-0.85 8.32+/-1.07 7.27 +/- 0.41 0.021 +/- 0.004 799.3 +/- 122.4 0.018 +/- 0.004 10.51 +/- 0.53 3.38 +/- 0.27 0.83 +/- 0.23 29.36 +/- 0.64 0.023 +/- 0.005 5,058 +/-223 Averaged Result 4,325 +/- 141 45.59 +/- 2.55 51.40+/-1.40 13.67 +/- 0.40 21.10 +/-0.79 0.014 +/- 0.002 2.67 +/- 0.42 0.026 +/- 0.003 0.008 +/- 0.004 1.55 +/- 0.12 0.94 +/- 0.35 23.50 +/- 1.68 47.88 +/- 0.47 261.2 +/- 5.5 76.35 +/- 1.21 40.95 +/- 0.62 1.13 +/- 0.46 0.010 +/- 0.002 0.85 +/- 0.05 0.97 +/- 0.09 0.07 +/- 0.01 0.40 +/- 0.05 0.47 +/- 0.02 11.15 +/- 0.35 0.05 +/- O.D1 37.48 +/- 11.98 1336 +/- 170 21,555 +/-445 0.022 +/- 0.003 1.41 +/- 0.59 9.27 +/- 0.87 7.41 +/- 0.30 0.022 +/- 0.003 820.6 +/- 87.0 0.020 +/- 0.003 10.45 +/- 0.37 3.52 +/- 0.18 0.81 +/- 0.14 29.24 +/- 0.45 0.023 +/- 0.003 5,114+/-158 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Lab Code AP-3822, 3823 AP-3969, 3970 WW-3632, 3633 W-4368, 4369 W-4368, 4369 Date 7/1/2015 7/1/2015 7/6/2015 7/6/2015 7/6/2015 DW-60138, 60139 7/7/2015 DW-60138, 60139 7/7/2015 WW-4158, 4159 7/9/2015 Ml-2902, 2903 7/10/2015 SG-3533, 3534 7 /10/2015 DW-60150, 60151 7/10/2015 DW-60150, 60151 7/10/2015 VE-3716, 3717 7/14/2015 Ml-3759, 3760 7/15/2015 Ml-3759, 3760 7/15/2015 AP-072115 7/21/2015 VE-4053, 4054 7/21/2015 VE-4053, 4054 7/21/2015 AP-4200, 4201 7/29/2015 AP-4200, 4201 7/29/2015 W-4137, 4138 7/31/2015 XWW-4431, 4432 SG-4305, 4306 AP-081015 AP-081115 VE-4452, 4453 AP-081715 DW-60195,60196

DW-60195,60196 DW-60198, 60199 VE-4578, 4579 SW-4662, 4663 DW-60212, 60213 LW-4788, 4789 AP-083115 AP-4875, 4876 VE-5083, 5084 VE-5083, 5084 VE-5167, 5168 VE-5167, 5168 BS-5188, 5189 F-5419, 5420 DW-60238, 60239 DW-60238, 60239 AP-092215A/B WW-5398, 5399 AP-6007, 6008 8/5/2015 8/6/2015 8/10/2015 8/11/2015 8/11/2015 8/17/2015 8/17/2015 8/17/2015 8/17/2015

8/18/2015 8/25/2015 8/25/2015

8/27/2015 8/31/2015 9/3/2015 9/14/2015 9/14/2015

9/16/2015 9/16/2015 9/16/2015 9/17/2015 9/18/2015 9/18/2015 9/22/2015 9/22/2015

9/28/2015 Analysis Be-7 Be-7 H-3 Gr. Alpha Gr. Beta Ra-226 Ra-228 H-3 K-40 Gr. Alpha Ra-226 Ra-228 K-40 K-40 Sr-90 Gr. Beta Be-7 K-40 Be-7 K-40 Ra-226 H-3 Ra-228 Gr. Beta Gr. Beta K-40 Gr. Beta Ra-226 Ra-228 Gr. Alpha K-40 H-3 Ra-226 )Gr. Beta Gr. Beta Be-7 Be-7 K-40 Be-7 K-40 K-40 K-40 Ra-226 Ra-228 Gr. Beta H-3 Be-7 First Result 0.075 +/- 0.011 0.063 +/- 0.008 5,169 +/- 225. 26.70 +/- 4.00 34.62 +/- 2.10 0.07 +/- 0.04 1.04 +/- 0.41 138.8 +/- 82.4 1271 +/- 118 238.0 +/- 8.2 1.53 +/- 0.16 2.68 +/- 0.68 3.85 +/- 0.33 1819 +/- 127 1.00 +/- 0.36 0.022 +/- 0.004 0.52 +/-0.15 8.00 +/- 0.42 1.06 +/- 0.12 5.03 +/- 0.24 0.58 +/- 0.13 4,773 +/- 213 10.34 +/- 0.58 0.038 +/- 0.005 0.024 +/- 0.004 3.77 +/- 0.29 0.030 +/- 0.005 0.39 +/-0.10 1.43 +/- 0.51 2.93 +/- 0.94 4.14 +/- 0.25 351.3 +/- 89.8 0.09 +/- 0.07 0.97 +/- 0.51 0.032 +/- 0.005 0.294 +/- 0.125 0.47 +/- 0.23 6.20 +/- 0.51 0.40 +/-0.11 3.56 +/- 0.27 9.69 +/- 0.51 3.48 +/- 0.47 1.93 +/- 0.23 4.44 +/- 0.78 0.021 +/- 0.004 1,857 +/- 145 0.08 +/- 0.01 A5-3 149 Concentration (pCi/L)" Second Result 0.068 +/- 0.012 0.064 +/- 0.010 5,058 +/- 223 24.10 +/- 3.90 33.30 +/- 2.02 0.11 +/- 0.05 1.15 +/-0.47 174.0 +/-84.1 1308+/-115 249.5 +/- 8.5 1.49 +/-0.12 1.89 +/- 0.62 3.71 +/- 0.31 1764+/-140 0.61 +/- 0.32 0.027 +/- 0.004 0.49 +/- 0.11 7.61 +/- 0.31 0.96 +/- 0.11 4.96 +/- 0.23 0.45 +/- 0.14 4,915 +/-216 11.46 +/- 0.62 0.039 +/- 0.005 0.020 +/- 0.004 3.78 +/- 0.26 0.030 +/- 0.005 0.37 +/- 0.10 1.97 +/- 0.61 2.11 +/- 0.96 4.32 +/- 0.24 415.6 +/- 92,8 0.10 +/- 0.08 1.68 +/- 0.59 0.031 +/- 0.005 0.202 +/- 0.109 0.56 +/- 0.19 6.36 +/- 0.50 0.41 +/- 0.10 3.91 +/- 0.24 10.51 +/- 0.52 3.49 +/- 0.56 2.31 +/- 0.26 5.61 +/- 0.84 0.025 +/- 0.004 1,846+/-144 0.08 +/- 0.01 Averaged Result 0.072 +/- 0.008 0.063 +/- 0.006 5, 114 +/- 159 25.40 +/-2.79 33.96+/-1.46 0.09 +/- 0.03 1.10 +/-0.31 156.4 +/- 58.9 1289 +/- 82 243.8 +/- 5.9 1.51 +/- 0.10 2.29 +/- 0.46 3.78 +/- 0.23 1791 +/- 94 0.80 +/- 0.24 0.024 +/- 0.003 0.50 +/- 0.09 7.81 +/- 0.26 1.01 +/- 0.08 4.99 +/- 0.16 0.52 +/- 0.10 4,844+/-152 10.90 +/- 0.42 0.039 0.004 0.022 0.003 3.77 +/- 0.20 0.030 +/- 0.003 0.38 +/- 0.07 1.70 +/- 0.40 2.52 +/- 0.67 4.23 +/- 0.17 383.4 +/- 64.6 0.10 +/- 0.05 1.32 +/- 0.39 0.031 +/- 0.003 0.248 +/- 0.083 0.52 +/- 0.15 6.28 +/- 0.36 0.41 +/- 0.07 3.74+/-0.18 10.10 +/- 0.36 3.49 +/- 0.36 2.12 +/-0.17 5:03 +/- 0.57 0.023 +/- 0.00 1,852+/-102 0.08 +/- 0.01 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration

{!::!Ci/Lt Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XW-7490, 7491 9/29/2015 Ni-63 2,332 +/- 233 2,108 +/-211 2,220+/-157 Pass WW-5377, 5378 9/30/2015 H-3 220.0 +/- 84.6 197.0 +/- 83.5 208.5 +/- 59.4 Pass AP-6028, 6029 9/30/2015 Be-7 0.073 +/- 0.009 0.083 +/- 0.012 0.078 +/- 0.007 Pass G-5461,2 10/1/2015 Be-7 2.02 +/- 0.32 1.98 +/- 0.25 2.00 +/- 0.20 Pass G-5461,2 10/1/2015 K-40 8.77 +/- 0.66 9.31 +/- 0.59 9.04 +/- 0.44 Pass S0-5482, 5483 10/1/2015 Ac-228 0.76 +/-0.12 0.74 +/- 0.30 0.75 +/-0.16 Pass S0-5482, 5483 10/1/2015 Bi-214 0.53 +/- 0.04 0.52 +/- 0.04 0.52 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Cs-137 *, 0.12 +/- 0.03 0.12 +/- 0.03 0.12 +/- 0.02 Pass S0-5482, 5483 10/1/2015 K-40 2.17+/-0.73 2.10 +/-0.72 2.13 +/- 0.51 Pass S0-5482, 5483 10/1/2015 Pb-214 0.57 +/- 0.04 0.55 +/- 0.04 0.56 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Ra-226 1.45 +/- 0.27 1.46 +/- 0.30 1.45 +/- 0.20 Pass S0-5482, 5483 10/1/2015 Tl-208 0.24 +/- 0.03 0.25 +/- 0.03 0.24 +/- 0.02 Pass WW-5524, 5525 10/5/2015 H-3 1,192+/-123 1,318 +/- 127 1,255 +/- 89 Pass AP-5881, 5882 10/5/2015 Be-7 0.078 +/- 0.008 0.085 +/- 0.011 0.082 +/- 0.007 Pass AP-5881, 5882 10/5/2015 K-40 0.009 +/- 0.004 0.010 +/- 0.006 0.010 +/- 0.004 Pass SG-6400,1 10/5/2015 Gr.Alpha 19.09 +/-3.14 19.45 +/- 3.25 19.27 +/-2.26 Pass SG-6400,1 10/5/2015 Gr. Beta 31.36 +/- 2.08 29:80 +/- 2.13 30.58 +/- 1.49 Pass VE-5923, 5924 10/1212015 K-40 4.29 +/- 0.29 4.13 +/-0.33 4.21 +/- 0.22 Pass SS-5818, 5819 10/14/2015 Ac-228 0.20 +/- 0.06 0.24 +/- 0.06 0.22 +/- 0.04 Pass SS-5818, 5819 10/14/2015 Cs-137 0.03 +/- 0.02 0.02 +/- 0.01 0.03 +/- 0.01 Pass SS-5818, 5819 10/14/2015 Gr. Beta 8.10 +/- 0.87 8.08 +/- 0.96 8.09 +/- 0.65 Pass SS-5818, 5819 10/14/2015 Pb-212 0.19 +/- 0.03 0.17 +/- 0.02 0.18 +/- 0.02 Pass SS-5818, 5819 10/14/2015 Ra-226 0.47 +/- 0.24 0.45 +/- 0.19 0.46 +/-0.15 Pass SS-5818, 581.9 10/14/2015 Tl-208 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Pass DW-60251, 60252 10/15/2015 Ra-226 0.56 +/-0.12 0.50 +/- 0.08 0.53 +/- 0.07 Pass DW-60251, 60252 10/15/2015 Ra-228 0.79 +/- 0.48 1.16 +/- 0.59 0.98 +/- 0.38 Pass S0-5944, 5945 10/21/2015 Ac-228 1.08 +/-0.15 1.14 +/- 0.15 1.11 +/- 0.10 Pass S0-5944, 5945 10/21/2015 Bi-214 0.89 +/- 0.08 0.82 +/- 0.06 0.85 +/-0.05 Pass S0-5944, 5945 10/21/2015 Cs-137 0.06 +/- 0.02 0.08 +/- 0.03 0.07 +/-0.02 Pass S0-5944, 5945 10/21/2015 Pb-212 1.06 +/- 0.06 0.99 +/- 0.05 1.03 +/-0.04 Pass S0-5944, 5945 10/21/2015 Pb-214 1.00 +/- 0.09 0.89 +/- 0.06 0.95 +/-0.05 Pass S0-5944, 5945 10/21/2015 Ra-226 2.13 +/-0.43 2.16 +/-0.37 2.14 +/-0.28 Pass S0-5944, 5945 10/21/2015 Tl-208 0.36 +/- 0.04 0.34 +/- 0.04 0.35 +/-0.03 Pass S-6175, 6176 10/23/2015 K-40 16.86+/-1.92 14.28+/-1.66 15.57+/-1.27 Pass XWW-6196, 6197 10/26/2015 H-3 2,856+/-170 2,815 +/- 169 2,836+/-120 Pass S0-6259, 6260 10/28/2015 Ac-228 0.60 +/- 0.10 0.53 +/- 0.08 0.57 +/- 0.07 Pass S0-6259, 6260 10/28/2015 Bi-214 0.40 +/- 0.06 0.50 +/- 0.05 0.45 +/-0.04 Pass S0-6259, 6260 10/28/2015 Cs-137 0.17 +/- 0.03 0.19 +/- 0.03 0.18 +/-0.02 Pass S0-6259, 6260 10/28/2015 Gr. Beta 21.6+/-1.1 23.36 +/- 1.21 22.48 +/-0.82 Pass S0-6259, 6260 10/28/2015 Pb-212 0.53 +/- 0.04 0.49 +/- 0.04 0.51 +/- 0.03 Pass S0-6259, 6260 10/28/2015 Tl-208 0.16 +/- 0.03 0.19 +/- 0.04 0.18 +/- 0.02 Pass A5-4 150 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration

(!;!Ci/L)" Averaged Lab Code Date First Result Second Result Result LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 . Ml-6484, 6485 11/11/2015 K-40 1,384 +/-82 1,432 +/- 89 1,408 +/- 60 S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 +/- 0.03 0.17 +/- 0.02 S0-6841, 6842 11/24/2015 K-40 13.62 +/- 0.76 13.67 +/- 0.69 13.64 +/- 0.51 WW-6978, 6979 11/30/2015 H-3 569.0 +/-97.7 480.3 +/- 93.9 524.7 +/- 67.8 SW-6936, 6937 12110/2015 H-3 151.9 +/- 80.0 176.2 +/- 81.2 164.0 +/- 57.0 SW-7017, 7018 12110/2015 H-3 584.3 +/-98.7 451.6 +/- 93.9 518.0 +/- 68.1 LW-7020, 7021 12110/2015 H-3 236.9 +/-84.2 285.6 +/- 86.5 261.2 +/- 60.3 AP-7351, 7352 12129/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 AP-7414, 7415 12130/2015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 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. Acce(;!tance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil, sediment (pCi/g). A5-5 151 ,-

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits 0 Acceptance MAS0-975 2/1/2015 Ni-63 341 +/- 18 448 314 -582 Pass MAS0-975 2/1/2015 Sr-90 523+/-12 653 457 -849 Pass MAS0-975 2/1/2015 Tc-99 614+/-12 867 607 -1,127 Pass MAS0-975 2/1/2015 Cs-134 533 +/-6 678 475 -881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/-2.5 0.0 NA 0 Pass MAS0-975 2/1/2015 Co-57 0.5+/-1.0 0.0 NA 0 Pass MAS0-975 2/1/2015 Co-60 741 +/- 8 817 572 -1,062 Pass MAS0-975 2/1/2015 Mn-54 1,153+/-9 1,198 839 -1,557 Pass MAS0-975 2/1/2015 Zn-65 892+/-18 1064 745 -1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 -0.850 Pass MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 23.5 16.5 -30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4 -24.8 Pass MAW-969 d 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 -38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA 0 Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 -732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82 -8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA 0 Pass MAW-969

• 2/1/2015 Ni-63 2.9 +/-3.0 0.00 NA 0 Pass MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 18.3 12.8 -23.8 Pass MAW-969 2/1/2015 Tc-99 3.40 .+/- 0.60 3.18 2.23 -4.13 Pass MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NAe Pass MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 0.148 0.104 -0.192 Pass MAW-969 2/1/2015 U-238 0.84 +/- 0.09 0.97 0.68 -1.26 Pass MAW-969 2/1/2015 Sr-90 9.40+/-1.30 9.48 6.64 -12.32 Pass MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAW-947 2/1/2015 1-129 1.26 +/- 0.12 1.49 1.04 -1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 -0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 -1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA 0 Pass MAAP-978 1 2/1/2015 Co-57 0.04 +/-0.04 1.51 1.06 -1.96 Fail* MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA 0 Pass MAAP-978 2/1/2015 Mn-54 1.11 +/- 0.08 1.02 0.71 -1.33 Pass MAAP-978' 2/1/2015 Zn-65 0.83 +/-0.10 0.83 0.58 -1.08 Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA 0 Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059 -0. i 10 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 O.Q16 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- O.Q18 0.099 0.069 -0.129 Pass A6-1 152 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLEA*6.

Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-981 2/1/2015 Sr-89 38.1+/-1.0 47.5 33.3 -61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 -9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/-0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/-0.04 0.00 NAC Pass MAVE-972 2/1/2015 Co-60 3.89 +/-0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/-0.07 0.00 NAC Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NAC Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 I 0.000 NAC Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 ' 0.085 0.059 -0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 -0.129 Pass MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 -61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 -9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/-0.04 0.00 NAC Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/-0.07 0.00 NAC Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NAC Pass MAS0-4903 8/1/2015 Ni-63 556+/-18 682 477 -887 Pass MAS0-4903 9 8/1/2015 Sr-90 231 +/- 7 425 298 -553 Fail MAS0-4903 9 8/1/2015 Sr-90 352+/-10 425 298 -553 Pass MAS0-4903 h 8/1/2015 Tc-99 411 +/- 11 631 442 -820 Fail MAS0-4903 8/1/2015 Cs-134 833+/-10 1,010 707 -1,313 Pass MAS0-4903 8/1/2015 Cs-137 808+/-11 809.00 566 -1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052+/-10 1,180 826 -1,534 Pass MAS0-4903 8/1/2015 Co-60 2 +/-2 1.3 NA 0 Pass MAS0-4903 8/1/2015 Mn-54 1,331 +/- 13 1,340 938 -1,742 Pass MAS0-4903 8/1/2015 Zn-65 686+/-15 662 463 -861 Pass A6-2 153 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report ', TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 -30.0 MAW-5007 8/1/2015 Cs-137 -0.4 +/- 0.1 0.0 NAC MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6 -27.0 MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12.0 -22.2 MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216.0 151.0 -281.0 MAW-5007; 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 -17.0 MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 -20.3 MAW-5007 8/1/2015 Ni-63 9.i +/- 2.6 8.6 6.0 -11.1 MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7 -18.1 MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 5.03 -9.35 MAW-5007 8/1/2015 Sr-90 4.8o +/- o.so 4.80 3.36 -6.24 MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13 -0.73 MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 -5.28 MAW-5007 8/1/2015 1-129 1.42 +/- 0.13 1.49 1.04 -1.94 MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79 -5.17 MMP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 0.74 -1.37 MMP-4907 8/1/2015 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 -1.53 MMP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78 -2.34 MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 4.06 -7.54 MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NAC MAVE-4901 8/1/2015 Co-57 7.74 +/- 0.18 6.62 4.63 -8.61 MAVE-4901 8/1/2015 Co-60 4.84 +/- 0.15 4.56 3.19 -5.93 MAVE-4901 5 Mn-54 8.25 +/- 0.25 7.68 5.38 -9.98 MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 3.82 -7.10

• Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and 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. d Lab result was 27.84. Data entry error resulted in a non-acceptable result.

• Provided in the series for "sensitivity evaluation".

MAPEP does not provide control limits. 1 Lab result was 1.58. Data entry error resulted in a non-acceptable result. 9 The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

h The complex sample matrix is interfering with yield calculations causing a failed low result. An investigation is in process to determine a more reliable yield determination.

1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.

AB-3 154 Acceptance Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLEA-7.

lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)8* Concentration

{pCi/q b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/-2.2 49.8 30.7 -67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61.2 -98.8 Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/-34.7 909.0 578.0 -1, 130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312+/-12.

1, 170 879 -1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/- 48.2 836.0 259.0 -1630.0 Pass ERAP-1091 3/16/2015 Mn-54 <2.7 <50 0.0 -50.0 Pass ERAP-1091 3/16/2015 Pu-238 51.0 +/-3.9 52.1 35.7 -68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3+/-1.3 40.3 29.20 -52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 -145.0 Pass ERAP-1091 3/16/2015 U-233/234 . 29.0 +/- 1.2 34.3 21.3 -51.7 Pass ERAP-1091 3/16/2015 U-238 31.0+/-1.1 34.0 22.0 -47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 -1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/-0.7 62.2 ' 20.8 -96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/-0.8 58.4 36.9 -85.1 Pass ERS0-1098 3/16/2015 Am-241 1571.8 +/- 209.6 1,500 878 -1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 -1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/-455.7 1,780 474 -2,620 Pass ERS0-1098 3/16/2015 Bi-214 3466.9 +/- 86.9 4,430 2,670 -6,380 Pass ERS0-1098 3/16/2015 Co-60 1779.8 +/-41.0 1,880 1 ,270 -2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180 -7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/-41.9 1,490 1, 140 -1 ,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/-380 10,700 7,810 -14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 -1,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/-41 1,230 806 -1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/- 93 4,530 2,640 -6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 -1,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1,185+/-140 1,210 791 -1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724+/-125 1,940 740 -3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/-948 3,890 1,230 -7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/- 226 3,920 2,400 -5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/- 232 3,890 2,410 -4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680 -9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11.5 119.0 42.2 -184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/- 4.8 158.0 90.5 -234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900 -14, 700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/-266 4,340 2,650 -5,770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 -2,120 Pass A7-1 155 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLEA-7.

lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a. Concentration (eCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceetance ERVE-1100 e 3/16/2015 Co-60 1,030 +/- 29 1,540 1,060

-2, 150 Fail ERVE-1100 1 3/16/2015 Co-60 1,684 +/- 48 1,540 1,060 -2, 150 Pass ERVE-1100 e 3/16/2015 Cs-134 1,615 +/- 27 2,650 1,700 -3,440 Fail ERVE-1100 1 3/16/2015 Cs-134 2,554 +/-49 2,650 1,700 -3,440 Pass ERVE-1100 e 3/16/2015 Cs-137 1,248 +/- 29 1,810 1,310 -2,520 Fail ERVE-1100 1 3/16/2015 Cs-137 2,078 +/- 68 1,810 1,310 -2,520 Pass ERVE-1100 e 3/16/2015 K-40 22,037 +/-463 30,900 22,300 -43,400 Fail ERVE-1100 1 3/16/2015 K-40 34,895 +/-764 30,900 22,300 -43,400 Pass ERVE-1100 e 3/16/2015 Mn-54 <13.8 <300 0.0 -300.0 Pass ERVE-1100 1 3/16/2015 Mn-54 <24.4 <300 0.0 -300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/-232 3,680 2, 190 -5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/-240 4,180 2,570 -5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/-326 6,590 3,760 -8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653+/-153 3,150 2,070 -4,050 Pass ERVE-1100 3/16/2015 U-238 2,717+/-163 3,130 2,090 -3,980 Pass ERVE-1100 e 3/16/2015 Zn-65 <94.6 1,090 786 -1,530 Fail ERVE-1100 1 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 -1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/- 4.0 46.0 31.0 -61.7 Pass ERW-1103 3/16/2015 Co-60 1,217+/-17 1,250 1,090 -1,460 Pass ERW-1103 3/16/2015 Cs-134 1,121 +/- 18 1,260 925 -1,450 Pass ERW-1103 3/16/2015 Cs-137 1,332 +/- 31 1,360 1,150 -1,630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 -100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5+/-1.6 72.4 53.6 -90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/-7.8 184.0 143.0

-232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/-4.9 97.7 66.6 -108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 -79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7 -75.2 Pass ERW-1103 3/16/2015 Zn-65 1, 191 +/- 136 1,180 984 -1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149+/-144 1,070 638 -1,450 Pass ERW-1103 3/16/2015 Sr-90 860.0 +/- 37.0 912.0 594.0 -1,210.0 Pass

• 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: ERW (water), ERAP (air filter), ERSO (soil), ERVE (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.

• Technician error weighing sample caused submitted gamma results to be understated and outside the control limits.(low) 1 The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above). 9 The results of reanalysis were outside the control limits (low). h Sample ERW-3742 was ordered from ERA to determine why ERW-1103 results for Pu-239 were outside the acceptable range. The results for ERW-3742 were acceptable.

No reason for the unacceptable results for ERW-3742 was determined.

A7-2 156

, Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report APPENDIX B DATA REPORTING CONVENTIONS B-1 157 Davis-Besse Nuclear Power Station 2015 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 = 2cr 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 4.66cr uncertainty for a background sample. 3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. : 3.1 Individual results: For two analysis results; x 1 +/- s 1 and x 2 +/- s 2 Reported result: x +/- s; where x = (1/2) (x 1 + x 2) ands= (1/2) s; + 3.2. Individual results: Reported result: < L, where L = lower of L 1 and L 2 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 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 x 1 , x 2 *** xn are defined as follows: S=

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. 158 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report APPENDIX C SUPPLEMENTAL ANALYSES C-1 159 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report C-1. Supplemental Analyses.

Units: pCi/L Location T-24 01-14-Date Collected 16 Lab Code TMI-201 1-131 < 0.4 Sr-89 < 0;6 Sr-90 < 0.5 K-40 1142 +/- 158 Cs-134 < 6.3 Cs-137 < 5.4 Ba-La-140

< 3.8 Ca (g/L) 1.00 Sr-90/g Ca < 0.50 K (g/L) 1.39 +/- 0.19 Cs-137/g K < 3.86 160 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report APPENDIX D REMP SAMPLING

SUMMARY

161 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Location of Facility Ottawa, Ohio ( County, State ) Indicator Sample Type and Locations Type Number of LLDb Mean (F)c (Units) Analyses*

Ranoec 0.028 Airborne GB 520 0.003 (312/312)

(0.012-Particulates 0.062) (pCi/m 3) Sr-89 40 0.0015 <LLD Sr-90 40 0.0009 <LLD GS 40 0.076 Be-7 0.015 (24/24) (0.055-0.103) K-40 0.029 <LLD Nb-95 0.0015 <LLD Zr-95 0.0026 <LLD Ru-103 0.0013 <LLD Ru-106 0.0111 <LLD Cs-134 0.0014 <LLD Cs-137 0.0014 <LLD Ce-141 0.0027 <LLD Ce-144 0.0064 <LLD Airborne Iodine 1-131 520 0.07 <LLD (pCi/m 3) TLD 14.5 (Quarterly)

Gamma 350 1.0 (306/306) (mR/91 days) ( 7.7-25.9)

TLD (Quarterly)

Gamma 4 1.0 7.2 (4/4) (mR/91 days) ( 6.2-8.5) (Shield) ' TLD 56.2 (Annual) Gamma 86 1.0 (75/75) (mR/365 ( 34.9-days) 77.9) TLD (Annual) Gamma 1 1.0 24.9 (1/1) (mR/365 days) (Shield) 162 Docket No. Reporting Period Location with Highest Annual Mean Mean (F)c Locationd Ranoec T-11, Ottawa County 0.03 (52/52) WTP, 9.5 mi. (0.013-SE 0.078) ----T-11, Ottawa County 0.083 (4/4) WTP, 9.5mi. (0.060-SE 0.099) --------------------T-8, Farm 23.4 (4/4) 2.7mi.WSW (21.1-25.9)

--T-124 79.3 (1/1) 6.5mi.SSW --50-346 January-December, 2015 Control Number Locations Non-Mean (F)c Routine Ranoec Results* 0.028 (208/208) 0 (0.010-0.078) <LLD 0 <LLD 0 0.077 (16/16) 0 (0.056-0.099) <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 17.5 (44/44) 0 ( 10.5-24.4)

None 0 64.2 (11/11) 0 ( 49.0-79.3)

None 0 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Location of Facility Ottawa, Ohio (County, State) Indicator Sample Type and Locations Type Number of LLDb Mean (F)0 (Units) Analyses*

Ranoe 0 Milk (pCi/L) 1-131 12 0.5 none Sr-89 12 0.6 none Sr-90 12 0.7 none GS 12 K-40 100 none Cs-134 6.2 none Cs-137 6.7 none Ba-La-140 7.5 none (g/L) Ca 12 . 0.50 none (g/L) K (stable) 12 none (pCi/g) Sr-90/Ca 12 none (pCi/g) Cs-137/K 12 0.89 none Ground Water GB(TR) 8 2.1 3.3 (4/5) (pCi/L) (2.1-6.2)

H-3 8 330 <LLD Sr-89 8 1.4 <LLD Sr-90 8 0.8 <LLD GS Mn-54 15 <LLD Fe-59 30 <LLD Co-58 15 <LLD Co-60 15 <LLD Zn-65 30 <LLD Zr-95 15 <LLD Cs-134 10 <LLD 163

• Docket No. Reporting Period Location with Highest Annual Mean Mean (F)0 Locationd Rahoe 0 T-24, Sandusky 1.0 20.2mi. SE (1/12) ----T-24, Sandusky 1367 (12112) 20.2mi. SE (1209-1594)

---

T-24, Sandusky 0.98 (12112) 21.0mi. SE (0.87-1.18)

T-24, Sandusky 1.67 (12112) 21.0mi. SE (1.47-1.94)

T-24, Sandusky (0/12) 21.0 mi. SE (-) --T-27A, Magee Marsh 1.9 (3/3) 5.3mi. WNW (1.0-2.5)--------------------50-346 January-December, 2015 Control Number Locations Non-Mean (F)0 Routine Range 0 Results* 1.0 0 (1/12) <LLD 0 <LLD 0 1367 (12112) 0 (1209-1594)

<LLD 0 <LLD 0 <LLD 0 0.98 (12/12) 0 (0.87-1.18) 1.67 (12/12) 0 (1.47-1.94)

(0/12) 0 (-) <LLD 0 2.4 (1/3) <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Cs-137 10 <LLD Ba-La-140 15 <LLD Table 4.5 . Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses*

Soil GS (pCi/g dry) Be-7 K-40 Mn-54 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 Fruits and Sr-89 Vegetables Sr-90 (pCi/gwet)

GS K-40 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ce-141 Ce-144 Broad Leaf Sr-89 Vegetation Sr-90 (pCi/gwet)

GS 10 3 3 3 8 8 8 Davis-Besse Nuclear Power Station Ottawa, Ohio ( County, State ) Indicator Locations LLDb Mean (F)0 Ranae 0 0.29 <LLD 0.10 9.85 (6/6) (4.14-19.65) 0.032 <LLD 0.043 <LLD 0.037 <LLD 0.028 <LLD 0.24 <LLD 0.025 <LLD 0.016 0.12 (4/6) (0.034-0.30) 0.076 <LLD 0.17 <LLD 0.004 <LLD 0.001 <LLD 0.50 1.07 (2/2} (1.05-1.08} 0.006 <LLD 0.012 <LLD 0.020 <LLD 0.006 <LLD 0.005 <LLD 0.016 <LLD 0.052 <LLD 0.007 <LLD 0.003 <LLD 164 ---

-Docket No. Reporting Period Location with Highest Annual Mean Mean (F)0 Locationd Ranae 0 ----T-9, Oak Harbor 20.76 (1/1) 6.8mi. SW ------------T-8, Farm 0.3 (1/1) 2.7mi.WSW

---

T-8, Residence 1.08 (1/1} 2.7mi.WSW ------------------50-346 <LLD

<LLD 0 0 January-December, 2015 Control Number Locations Non-Mean (F)0 Routine Ranae 0 Results* <LLD 0 17.87 (3/4) 0 (14.61-20.76) <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 0.09 (4/4) (0.054-0.13) 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 1.58(1.1) 0 <LLD 0 <LLD 0 '<:LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report K-40 0.50 2.59 (5/5) T-19 2.59 (5/5) 1.86 (3/3) 0 (2.05-B. Skinner, 1.0 2.95) mi.W (2.05-2.95)

(1.51-2.10)

Nb-95 0.007 <LLD --<LLD 0 Zr-95 0.012 <LLD --<LLD 0 1-131 0.022 <LLD --<LLD 0 Cs-134 0.006 <LLD --<LLD 0 Cs-137 0.006 <LLD --<LLD 0 Ce-141 O.D19 <LLD --<LLD 0 Ce-144 0.046 <LLD --<LLD 0 165 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units) Analvses*

Treated GB(TR) 35 Surface Water (pCi/L) H-3 12 Sr-89 16 Sr-90 16 GS 16 Mn-54 Fe-59 Co-58 Co-60 Zn-65 I Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Untreated GB(TR) 48 Surface Water (pCi/L) H-3 48 Sr-89 16 Sr-90 16 GS 48 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Davis-Besse Nuclear Power Station Ottawa, Ohio ( County, State ) Indicator Locations Mean LLDb (F)C Ranae 0 1.8 2.3 (5/12) (1.8-2.7) 330 <LLD 0.8 <LLD 0.8 <LLD 15 <LLD 30 <LLD 15 <LLD 15 <LLD 30 <LLD 15 <LLD 10 <LLD 10 <LLD 15 <LLD Docket No. Reporting Period Location with Highest Annual Mean Mean (F)0 Locationd Ranae 0 T-12, Water Treatment 3.0 (4/11) Plant, 23.5 mi. WNW (2.1-4.5)

---

2.6 T-11, Ottawa Cly. 0.9 (22/24) WTP 18.0 (12/12) (1.4-5.1) 9.5 mi. SE (1.0-53.0) 553 T-22, Carroll 330 (4/24) Twnshp WP 602 (3/12) 3.0mi. NW (536-721) 0.7 <LLD --0.6 <LLD --15 <LLD --30 <LLD --15 <LLD --15 <LLD --30 <LLD --15 <LLD --10 <LLD --10 <LLD --15 <LLD --.166 50-346 January-December, 2015 Control Number Locations Non-Mean (F)0 Routine Ranae 0 Results* 2.6 (9/23) 0 (1.8-4.5)

<LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 10.3 (22/24) 0 (1.0-53.0)

<LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Location of Facility Ottawa, Ohio ( County, State ) Indicator Sample Type and Locations Mean Type Number of LLDb (F)C (Units) Analvses*

Ranae 0 Fish GB 6 0.10 3.55 (3/3) (pCi/g (3.12-wet) 3.77) GS 6 K-40 0.10 2.76 (3/3) (2.36-3.45) Mn-54 0.026 <LLD Fe-59 0.14 <LLD Co-58 0.033 <LLD Co-60 0.021 <LLD Zn-65 0.048 <LLD Cs-134 0.022 <LLD Cs-137 0.024 <LLD ., Shoreline GS 8 11.10 Sediments K-40 0.10 (6/6) (8.13-(pCi/g dry) 12.46) Mn-54 0.032 <LLD Co-58 0.035 <LLD Co-60 0.015 <LLD Cs-134 0.026 <LLD Cs-137 0.024 <LLD

• GB = gross beta, GS = gamma scan. Docket No. Reporting Period Location with Highest Annual Mean Mean (F)0 Locationd Ranae 0 T-35, Lake Erie 3.83 (3/3) > 10mi. (3.56-4.23)

T-35, Lake Erie 3.14 (3/3) > 10 mi. (2.43-3.86)

---

( ----------T-4, Site Boundary 12.06 (2/2) 0.8mi.S (11.65-12.46)

---

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample. 50-346 50-346 Control Locations Mean (F)0 Ranae 0 3.83 (3/3) (3.56-4.23)

<-3.14 (3/3) (2.43-3.86)

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 10.73 (2/2) (10.48-10.98)

<LLD

<LLD <LLD <LLD <LLD Number Non-Routine Results* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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 ..

• Non-routine results are those which exceed ten times the control station value. 167 END OF REPORT FE NOCŽ " FirstEnergy Nuclear Operating Company May 10, 2016 L-16-134 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 . Davis-Besse Nuclear Power Station 5501 N. State Route 2 Oak Harbor. Ohio 43449 10 CFR 50.36a Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear: Power Station -201-Q :*; ' .. ' . In accordance 1 O CFR .50.36a(a)(2), this the combined 2015 Annual Radiological Environmental Operating Report (AREOR) and Radiological Effluent Release Report (RERR) for the period January 2015 through December 2015. These annual reports are submitted for the Qavis-Besse Nuclear 'Power Station (DBNPS). The AREOR and the RERR must be s.ubmitted 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 ARE OR which was prepared to meet each requirement.

The following information is also,provided only tb the Pocument Control Desk. This information includes:

• 2015 RERR Meteorological Data (on Co_mpact Disc)

• Environmental, Inc. Midwest Laboratory, Mo1nthly Progress Report for January through December 2015 which contains the 2015 Radiological Environmental Monitoring Program Sample Analysis Results (on Compact Disc) -* Davis-Besse Offsite Dose Calculation Manual, Rev. 30 and 31 (on Compact Disc)

Davis-Besse Nuclear Power Station, Unit 1 L-16-134 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, at (419) 321-7374.

Sincerely, Douglas Director-Site Operations Davis-Besse Nuclear Power Station VAW/LTZ

Attachment:

Summary Location(s) of Off-Site Dose Calculation Manual Requ)rements 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 -2015 cc: Regional Administrator, NRC Region Ill 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-16-134 Attachment Page 1of1 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 78 and Appendix D)

• Results of the Land Use Census (pages 108 through 128)

• Results of the analysis of radiological environmental samples and of environmental radiation measurements (Environmental, Inc. Midwest Laboratory, Monthly Progress Report for January through December 2015 (pages 26 through 78))

• Summary description of the radiological environmental monitoring program (also pages 26 through 78)

• 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 75)

• 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-16-134 Enclosure Annual Radiological Environmental Operating Report, including the Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station -2015 (1 Report follows) 2015 Annual Radiological Environmental Operating Report Radiologi eleas ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Davis-Besse Nuclear Power Station January 1, 2015 through December 31, 2015 Davis-Besse Nuclear Power Station May2016 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE OF CONTENTS List of Tables List of Figures Executive Summary INTRODUCTION Fundamentals Radiation and Radioactivity Interaction with Matter Quantities and Units of Measurement Sources of Radiation Health Effects of Radiation Health Risks Benefits of Nuclear Power Nuclear Power Production Station Systems i Reactor Safety and Summary Radioactive Waste Description of the Davis-Besse Site References RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Introduction Pre-Operational Surveillance Program Operational Surveillance Program Objectives Quality Assurance Program Description Sample Analysis Sample History Comparison iv vi viii 1 2 3 5 7 9 10 11 11 16 19 19 22 24 26 26 27 27 28 32 34 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) 2015 Program Anomalies Atmospheric Monitoring Terrestrial Monitoring Aquatic Monitoring Direct Radiation Monitoring Conclusion References RADIOACTIVE EFFLUENT RELEASE REPORT Protection Stap.dards Sources of Radioactivity Released Processing and Monitoring Exposure Pathways Dose Assessment

• Results Regulatory Limits Effluent Concentration Limits Average Energy Measurements of Total Activity Batch Releases Abnormal Releases Percent of Offsite Dose Calculation Manual (ODCM) Release Limits Sources of Input Data Dose to Public Due to Activities Inside the Site Boundary Inoperable Radioactive Effluent Monitoring Equipment Changes to The ODCM and Process Control Plan (PCP) Borated Water Storage Tank Radionuclide Concentrations Onsite Groundwater Monitoring LAND USE CENSUS Program Design Methodology Results ii 36 36 43 53 66 76 76 79 79 80 81 82 83 84 85 85 85 85 86 86 86 87 87 88 88 103 108 108 109 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Title NON-RADIOLOGICAL ENVIRONMENTAL PROGRAMS Meteorological Monitoring On-Site Meteorological Monitoring Land and Wetlands Management Water Treatment Plant Operation Chemical Waste Management Other Environmental Regulating Acts Other Environmental Programs APPENDICES Appendix A: Interlaboratory Comparison Program Results Appendix B: Data Reporting Conventions Appendix C: Supplemental Analyses Appendix D: REMP Sampling Summary iii v 114 115 129 130 133 134 136 138 157 159 161 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report List of Tables Table Page. Title Number Number Risk Factors: Estimated Decrease in Average Life Expectancy 1 10 Sample Codes and Collection Frequencies 2 30 Sample Collection Summary 3 31 Radiochemical Analyses Performed on REMP Samples 4 33 Air Monitoring Locations 5 39 Milk Monitoring Location 6 44 Groundwater Monitoring Locations 7 '46 Broadleaf Vegetation and Fruit Locations 8 47 Soil Locations 9 49 Treated Surface Water Locations 10 55 Untreated Surface Water Locations 11 58 Shoreline Sediment Locations 12* 59 Fish Locations 13 61 Thermoluminescent Dosimeter Locations 14 67 Gaseous Effluents

-Summation of All Releases 15 89 Gaseous Effluents

-Ground Level Releases -Batch Mode 16 90 Gaseous Effluents

-Ground Level Releases -Continuous Mode 16 91 Ground Level Releases -LLDs for Coittinuous and Batch Mode 16 92 Gaseous Effluents

-Mixed Mode Releases -Batch Mode 17 93 Gaseous Effluents

-Mixed Mode Releases -Continuous Mode 17 94 LLDs fo:r Gaseous Effluents

-Mixed Mode Releases 17 95 Liquid Effluents

-Summation of All Releases 18 96 '--Liquid Effluents

-Nuclides Released in Batch Releases 19 97 iv Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Liquid Effluents

-Nuclides Released in Continuous Releases Liquid Effluents

-LLDs for Nuclides Released Liquid Effluents

-Solid Waste and Irradiated Fuel Shipments 2015 Groundwater Tritium Results Doses Due to Gaseous Releases for January through December 2015 Doses Due to Liquid Releases for January through December 2015 Annual Dose to the Most Exposed (from all pathways)

Member of the Public 2015 Closest Exposure Pathways Present in 2015 Pathway Locations and Corresponding Atmospheric Dispersion CXJQ) and Deposition (D/Q) Parameters Summary of Meteorological Data Recovery for 2015 Summary of Meteorological Data Measured for 2015 Joint Frequency Distribution by Stability Class v Table Number 19 19 20 21 22 23 24 25 26 27 28 29 Page Number 99 100 101 104 105 107 107 111 113 119 120 125 Davis-Besse Nuclear Power Station 2015 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 2015 Airborne Gross Beta 10 38 Air Sample Site Map 11 40 Air Samples 5-rnile Map 12 41 Air Sample 25-mile Map 13 42 Gross Beta Groundwater 1982-2015 14 45 -Cs-137 in Soil 1972-2015 15 48 Terrestrial Site Map 16 50 Terrestrial 5-mile Map 17 Terrestrial 25-rnile Map 18 52 Gross Beta in Treated Surface Water 1972-2015 19 54 Gross Beta Concentration in Untreated Surface Water 1977-2015 20 57 Gross Beta in Fish 1972-2015 21 60 Aquatic Site Map 22 62 Aquatic 5-rnile Map 23 63 Aquatic 25-rnile Map 24 64 Gamma Dose for Environmental TLDs 1973 2015 25 66 TLD Site Map 26 73 TLD 5-rnile Map 27 74 ,TLD 25-rnile Map 28 75 Exposure Pathways 29 82 vi Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Figure Page Description Number Number Davis-Besse Onsite Groundwater Monitoring H-3 Trends 30 105 Land Use Census Map 31 110 Wind Rose Annual Average 1 OOM 32 122 Wind Rose Annual Average 75M 33 123 Wind Rose Annual Average 1 OM 34 124 vii ( I Davis-Besse Nuclear Power Station 2015 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 vis-Besse) from January 1 through December 31, 2015. This report meets all of the requirements in NRC Regulatory Guide 4.8, Section 5.6 of Davis-Besse Technical Specifications, and Besse Offsite Dose Calculation Manual (ODCM) Section 7.1. Reports included are the logical 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, ical Waste Management, and Waste Minimization and Recycling.

Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is established to monitor the diological condition of the environment around Davis-Besse.

The REMP is conducted in cordance with NRC Regulatory Guide 4.8, Davis-Besse Technical Specifications, and the Besse ODCM, Section 6.0. This program includes the sampling and analysis of environmental samples and evaluation of the effects of releases of radioactivity on the environment.

Radiation levels and radioactivity have been monitored within a 25-mile radius around 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 tion and radioactivity normally present in the area as natural background.

Davis-Besse has tinued to monitor the environment by sampling air, groundwater, milk, fruit and vegetables, drinking water, surface water, fish, shoreline sediment, and by direct 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 further away from the Station and are expected to indicate the presence of only naturally occurring oactivity.

The results obtained from the.samples collected from indicator locations are compared with the results from those collected from control locations and with the concentrations present in the environment before Davis-Besse became operational.

This a119ws for the assessment of any impact the operation of Davis-Besse might have had on the surrounding environment.

Approximately 2,000 radiological environmental samples were collected and analyzed in 2015. 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 activity is attributed to the operation of Davis-Besse.

viii Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report The sampling results are divided into four sections:

atmospheric monitoring, terrestrial ing, aquatic monitoring and direct radiation monitoring.

Air samples are continuously collected 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 2015 indicator results were in close agreement with the samples collected at control locations.

Terrestrial monitoring includes analysis of milk, groundwater, meat, fruits, vegetables, and soil samples. Samples are collected onsite and up to twenty-five miles away, depending on the type of sample. Results of terrestrial sample analyses indicate concentrations of radioactivity 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 (Treated Surface ter), Untreated Surface Water, fish and shoreline sediments collected onsite and in the vicinity of Lake Erie. Tritium was detected at two locations with concentrations slightly over the detection limit of 330 pCi/l, the highest being 721 pCi/L in Untreated Surface Water samples during 2015. The 2015 results of analysis for fish, treated surface water and shoreline sediment indicate mal background concentration of radionuclides and show no increase or build-up of radioactivity due to the operation of Davis-Besse.

Direct radiation averaged 14.5 mrem/91 days at indicator locations and 17.5 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 2015. The operation of Davis-Besse in 2015 caused no significant increase in the concentrations of dionuclides or adverse effects on the quality of the environment surrounding the plant. 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 2015 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 formed as part of the REMP. During the census, Station personnel travel every public road in a radius of five miles of Davis-Besse to locate radiological exposure pathways (e.g., residences, 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 2015 was a garden in the Southwest sector 0.73 miles from Davis-Besse, this is a change from 2014. 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, 2015. The doses due to radioactivity released during this period were only a fraction of allowable per our operating license. 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 setin the ODCM. ix Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Unplanned Releases There were no unplanned releases of liquid or gaseous radioactivity from Davis-Besse during 2015. Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP) There were two revisions of the ODCM in 2015. The changes included the abandonment of RE8433 Station Effluent radiation monitor. Results of the 2014 Land Use Census were also dated. There were no revisions of the PCP during 2015. Groundwater Protection Initiative (NEI 07-07) Davis-Besse began sampling wells near the plant in 2007 as part of an industry-wide Groundwater Protection Initiative (GPI), which was established to ensure that there are no inadvertent releases of radioactivity from the plant which could affect offsite groundwater supplies.

In addition to several existing pre-construction era wells, sixteen new GPI ing 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. In January, seven out of ten wells indicated tritium concentrations of greater than 2000 pCi/L requiring courtesy notifications to local, county, and state officials.

Increased sampling frequency on selected wells was implemented in an attempt to identify the source of the groundwater contamination.

Based on the completion of a systematic evaluation of the identified potential leakage sources, The conclusion of the problem solving team was that the most probable cause was due to construction activities surrounding the removal of the Primary Water Storage Tank. Since the initial identification of elevated concentrations, well sampling results have indicated a decreasing trend over the year, indicating that the cause is intermittent and no longer active. In the area of highest concentrations, the concentration has decreased from 10,527 pCi/L in February to 2,866 pCi/L in December 2015 with the highest concentrations detected in the western wells within the Protected Area. The assumptions regarding groundwater flow and modeling remain valid that the flow does not impact areas outside the Owner Controlled Area and essentially discharges into the Intake Canal. There is no evidence that the tritium traved offsite or contributed to offsite dose. Additionally, the groundwater tritium sample results remain below the 30,000 pCi/L EPA limit described in the Davis-Besse Offsite Dose Calculation Manual for non-drinking water sources. 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 x Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 quirements Manual was 97.69 % in 2015. 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.

More than thirty 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 tion liquid effluents back to Lake Erie. There were two National Pollutant Discharge Elimination System permit violations in 2015. On October 2, 2015 Total Residual Oxidants (TRO) measured 0.19 parts per million (PPM) at Outfall 001. This concentration exceeded the permit limitation of 0.05 PPM. On December 17, 2015 Total Residual Chlorine (TRC) measured 0.29 PPM at Outfall 001. This concentration exceeded the permit limitation of 0.2 ppm. In both instances, the Station Chlorination System was isolated until chlorine concentration was restored to below permit tations. Chemical Waste Management The Chemical Waste Management Program at Davis-Besse was developed to ensure that the offsite disposal of non-radioactive hazardous and nonhazardous chemical wastes is performed in accordance with all applicable state and federal regulations.

Chemical waste disposal vendors contracted by Davis-Besse use advanced technology for offsite disposal, including recycling of chemical wastes, in order to protect human health and the environment.

In 2015, the Besse Nuclear Power Station generated approximately 4,166 pounds of hazardous waste. hazardous wastes generated include 1,329 gallons of used oil and 21,488 pounds of hazardous waste such as oil filters, resins and caulk, latex paints, and grout. As required by perfund Amendment and Reauthorization Act (SARA), Davis-Besse reported hazardous products and chemicals to local fire departments and local and state planning commissions.

As part of the program to remove PCB fluid from Davis-Besse, all electrical transformers have been retro-filled and reclassified as non-PCB transformers.

Waste Minimization and Recycling The Waste Minimization and Recycling Program at Davis-Besse began in 1991 with the 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 ically exceeds 50 tons annually.

The scrap metal collected onsite is sold to scrap companies.

xi Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Appendices Appendix A contains results from the Inter-laboratory Comparison Program required by the vis-Besse ODCM. Samples with known concentrations of radioisotopes are prepared by the vironmental 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 analyze 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 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 tions are also provided.

Appendix C contains supplemental analyses of a Toft' s Dairy milk control sample. Appendix D provides a REMP sampling summary from 2015. 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 (LLD)

• mean and range of results for control and indicator locations

• 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 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 11, 2016). xii Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Introduction Coal, oil, natural gas and hydropower are used to run this nation's electric generating stations; 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. 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 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 bf this unique source of energy, background 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 scribed, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, tively (Figure 1). The relatively large tons and neutrons are packed tightly gether in a cluster at the center of the atom called the nucleus. Orbiting around the 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 ling each other, and prevent the nucleus from breaking apart. 1 , 'I Q P!IOTON 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.

Davis-Besse NJ,lclear Power Station 2015 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. ever, the number of neutrons in the nucleus of an element may vary. Atoms with the same 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 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. 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 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. izing radiation consists of both electromagnetic radiation and particulate radiation. 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 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 sion of ionizing radiation.

Radioactive atonis may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several 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, 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 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 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 2015 Annual Radiological Environmental Operating Report This example is part of a known radioactive decay series, called the Uranium series, which gins with Uranium-238 and ends with Lead-206 (Figure 2). 238LJ 234LJ 4.5x10 9 Yr 2.5x10 5 Yr i 2a4pa i 1.2 min 234Th 2s0Th 24d 8.0 x 1 b 4 Yr i 22sRa 1600 Yr i 222Rn 3.82d i 21ap 0 3.05 min i 214Bi 19.7 min 214pb 26.8 min Figure 2: Principal Decay Scheme of the Uranium Series. Half-life 214p 0 1.6 x 10 4 s i 210pb 23 Yr Beta Decay Alpha Decay 210Bi 5.01 d 210p 0 138.4 d 206pb stable Most radio-nuclides 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 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 2015 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 om at speeds ranging from 2,000 to 20,000 miles per second. However, due to its comparatively large size, an alpha particle usually does not travel very far before it loses most of its energy through collisions and interactions with other atoms. As a result, a sheet of paper or a few timeters 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 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. o:> ,. f\ADIOACTIVE -MATERIAL 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, 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 interaction!i, 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 ma 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 sity. 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 2015 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 c;_harge, 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 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 vis-Besse, concrete is used to form an effective neutron shield because it contains water 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 fects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent.

Activity:

Curie ! Activity is the numqer of atoms in a sample that disintegrate (decay) per unit of tin;ie. 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 (I/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 samples .. For instance, the microcurie (uCi) is equal to one millionth of a curie, while the picocurie (pCi) represents one trillionth of a curie. 5 Davis-Besse Nuclear Power Station 2015 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, 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 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 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 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 millirem, is often used. One millirem (mrem) is equal to 1/1,000 of a rem. Deep Dose Equivalent (DDE) 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 terial taken into the body. It is calculated from the sum of the products of the committed dose 6 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report equivalent to the organ or tissue multiplied by the organ or tissue-weighting factor. CEDE counts for all the dose delivered during the entire time the radioactive m.aterial 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 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 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 ground radiation to which we are all exposed. The earth is being showered by a steady stream of high-energy gamma rays and particulate 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. dionuclides commonly found in the atmosphere as a result of cosmic ray interactions include ryllium-7, Carbon-14, tritium (H-3), and Sodium-22.

Another common naturally occurring raqionuclide is Potassium-40.

About one-third of the 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 um 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 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 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 Health Physics Society, University of Michigan, more than half of the radiation dose the average American receives is attributed to Radon. 7 Davi s-Besse Nuclear Power Station 2015 Annual Radiolo g ical Environmental Operating Report Sources of Radiation Exposure to the US Population Nuclear Medicine 4/. Medi c al X-rays 11 /. Intern a l 11 /. Cosmic 8/. Con s umer Products 3/. Other < 1 /. Radon 54/. Figure 4: The mo st 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 (taken from the Health Physics Society , University of Michigan , 2013). Further information on Radon , its measurement, and actions to reduce the Radon concentration in building s can be obtained by contacting the state Radon program office at the following dre ss: Ohio Department of Health, Bureau of Environmental Health 246 North High Street Columbus, Ohio 43215 (614) 644-272 7 (614) 466-0381 FAX The approximate average background radiation in this area i s 620 mrem/year (Princeton sity, 2013). Man-made Radiation In addition to naturally occurring cosmic radiation and radiation from naturally occurring radioactivity, people are also exposed to man-made radiation.

The largest sources of exposure include medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer product s suc h as televisions , smok e detector s, and fertilizers.

Fallout from nuclear weapons tests is a nother so urce of man-made exposure.

Fallout radionuclides include Strontium-90, 8 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Cesium-137, and tritium. Less than one percent of the annual dose a member of the public 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. 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, 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 dividual health effects of low level radiation.

Even though no effects have been observed at es 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 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 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 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 oc,cur. Spontaneous mutations and chemically induced mutations also have been observed.

These mutated genes may be passed 9 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 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 sessment of the risks, and on placing these risks in perspective.

The perceptions of risk associat-,ed 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 causing substances.

These risks are larger and measurable compared to those presumed to be sociated with exposure to low level, low dose radiation.

Most of these risks are with us 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%: Cigarette smoking: Heart Disease: Cancer: City living (non-rural):

All operating commercial nuclear power plants totaled: 1 pack/day 2 packs/day

3.6 years

7.0 years 10.0 years 5.8 years 2.7 years 5.0 years less than 12 minutes IO Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Benefits of Nuclear Power Nuclear power plays an important part in today's electricity needs, and will continue to serve as an important source of electric energy well into the future. Today more than twenty 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 1958, 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 ar 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, ter is turned into steam. In a nuclear station, a reactor that contains a core of nuclear fuel, ily uranium, replaces the furnace. Heat is produced when the atoms of Uranium are split inside the reactor. The process of splitting atoms is called fission. 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. 11 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 cpmmon to all fossil fuels. Since a single small reactor fuel pellet contains trillions of atoms, each pellet can release an extremely large amount of gy. 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 occurrence's 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 cess by severaf 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 sion easily,

• slowing down neutrons 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. 12 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report After the Uranium ore is separated from the earth and rock, it is concentrated in a milling cess. After milling the ore to a granular form and dissolving out the Uranium with acid, the nium is converted to Uranium hexafluoride (UF6). UF6 is a chemical form of Uranium that exists as a gas at tel,llperatures slightly above room temperature.

The UF6 is then highly purified and shipped to an enrichment facility where gaseous diffusiOn converters increase the . tration of U-235. The enriched gaseous UF6 is then converted into powdered Uranium dioxide (U02), a highly stable ceramic material.

The U02 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 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 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 Yz inches thick. Futtl Rod ..... ...... REAClOR VESSEi.. Figure 6: The at Besse contains 177 fuel assemblies.

Each 208 . Each fuel rod rs filled with approximately five pounds of fuel pellets. Each pellet rs approximately 3/8 mch diameter and 5/8 inch long. 13 /

Davis-Besse Nuclear Power Station 2015 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, fudium, and Cadmium metals that absorb-free neutrons, thus disrupting the fission chain reaction.

When control rod assemblies are slowly withdrawn from the core, The fission process begins and heat is produced.

If the control rod semblies are inserted rapidly into the -reactor core, as occurs during a plant "trip", the chain tion ceases. A slower acting (but more evenly distributed)'

method of fission control is achieved by the addition of a neutron poison to the reactor coolant water. At Davis-Besse, high-purity boric acid is concentrated or diluted in the coolant to achieve the desired level of fission. Boron-10 readily absorbs free neutrons, forming Boron-11, removing the absorbed neutrons from the chain reaction.

Reactor Types Virtually all of the commercial reactors in this country are either boiling water reactors (BWRs) or pressurized water reactors (PWRs). Both types are also called light water 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 tors, which remove water droplets.

The steam then travels to dryers before-entering the turbfoe. 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 ary water supply. The water inside the steam generator boils into steam, which is then used to tum the turbine. This steam is then condensed back into water and returned to the steam generator.

Davis-Besse uses a PWR design. The following paragraphs describe the various systems illustrated in Figure 7. Major systems in the Davis-Besse Station are assigned a different color in the figure. 14

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CONTAINMENT COOLING TOWER TURBINE BUILDING 0

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ti Pl < c;;* ti:; (t> "' "' (t> z c: n '"d 0 :i: (t> ..., Pl o. 0 ;:3 N 0 ...... Vt c:: !£. ;;o Pl 0.. 5* 0 ()Q r;* tr1 ;:3 < a* (t> ;:3 -g_ '-"'"-0 "O (t> ..., ;:3 ()Q ;;o (t> "O 0 ;::<

Davis-Besse Nuclear Power Station 2015 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 reinforced concrete walls 30 inches 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 radi-oactive 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 ferred to the steam generator in order to provide the steam necessary to drive the turbine. 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 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 actor where it is again heated to 606°F as it passes up through the fuel assemblies.

Under 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 inch (psi) at all times. This prevents the water from boiling and is the reason the reactor at vis-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 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. 16 Davis-Besse Nuclear Power Station 2015 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 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 ll;Se 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 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 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 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 late 480,000 gallons of water per minute to the tower. purpose is to recycle water from the Condenser by cooling and returning it. 17 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report

• After passing through the Condenser, the Circulating Water has warmed to approximately 100°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 through evaporation via the Cooling Tower. Even so, approximately 98 percent of the water drawn from Lake Erie for station operation can be recycled through the Cooling Tower for reuse. A small portion of the Circulating Water is discharged back to Lake Erie at essentially the same temperature it was withdrawn earlier. The slightly warmer water has no measureable adverse environmental impact on the area of lake surrounding 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. ing on the severity of the loss of pressure inside the Primary System, the ECCS will ly 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 tem. The violet system illustrated in Figure 7 is r,esponsible for maintaining the Primary Coolant water in a liquid state. It accomplishes this by adjusting the pressure inside the Primary System. ers inside the Pressurizer tum water into steam. This steam takes up more space inside the 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.

18 Davis-Besse Nuclear Power Station 2015 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. Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features.

If one 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 tion of the control rods. The Reactor can be automatically shut down by a separate Reactor 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 ter into reactor automatically if the reactor coolant pressure drops below a predetermined el. The Davis-Besse Nuclear Power Station was designed, constructed, and is operated to produce a reliable, safe, and environmentally sound source of electricity.

Radioactive Waste Many of the 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 ment. With the exception of used nuclear fuel assemblies, these by-products produced at mercial power plants are referred to as low level radioactive waste. Low Level Radioactive Waste Low level radioactive waste consists of ordinary trash and other items that have become inated with radioactive and can include 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 as rally-occurring radioactive materials.

Most low level activity in radioactive waste decay to ground 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 Barnwell, South Carolina for cessing, after which it is shipped to Utah for disposal.

Davis-Besse has the capacity to store level waste produced on site for several years in the Low Level Radioactive Waste Storage ity, should this facility close. Davis-Besse added the Old Steam Generator Storage Facility (OSGSF) in 2011 to house the actor Vessel _Closure Head, Service Support Structure and Control Rod Drive mechanisms moved during the 17M outage. Two Steam Generators and two Reactor Coolant System Hot Leg 19 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report piping sections were replaced during 18th Refueling Outage (18RFO) in 2014, and are also stored there. The reinforced concrete building is comprised of three sections, the largest of which contains the old steam generators and hot legs. The old reactor vessel head is kept in other bay. The sections of the building are completely enclosed with concrete for shielding.

The dose rates outside the walls of this section are at background levels. The third section is the tibule, which provides access to the other two sections.

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. High Level Nuclear Waste Like any industrial or scientific process, nuclear energy does produce waste. The most 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 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 ly. Also, nuclear waste slowly loses its radioactivity, but some chemical waste remains ous indefinitely.

Davis-Besse presently stores most of its used fuel in a steel-lined water-filled concrete vault 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 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, ia, Wisconsin and South Carolina, to name a few. Figure 8 below illustrates the Dry Fuel age 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 dqring the initial 40 years of expected life. This modification was completed in April of 2002. 20 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Figure 8: Dry Fuel Storage Module Arrangement 21 Davis-Besse Nuclear Power Station 2015 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 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. \ Lake .Erie Figure 9: Davis-Besse is near Oak Harbor, Port Clinton, and the Ottawa National Wildlife Refuge. The Davis-Besse site is mainly comprised of freshwater marsh land, with a small portion ing of farmland.

The marshes are part of a valuable ecological resource, providing a breeding ground for a variety of wildlife and a refuge for migratory birds. The site includes a tract known as Navarre Marsh, which was acquired from the U.S. Bureau of Sport Fisheries and Wildlife, Department of the Interior.

In 1971, Toledo Edison purchased the 188 acre Toussaint River Marsh. The Toussaint River Marsh is contiguous with the 610 acre Navarre Marsh section of the Ottawa National Wildlife Refuge. 22 I Davis-Besse Nuclear Power Station 2015 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 6,056

• Oak Harbor -7 miles south, population 2,759

• Rocky Ridge -7 miles west southwest, population 417

• Toledo (nearest major city) -25 miles west, population 287,208 There are some residences along the lakeshore used mainly as summer homes. However, the 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, com, 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 cated in Erie Industrial Park, about four miles southeast of the station. Most of the remaining marshes in the area have been maintained by private hunting clubs, the U.S. Fish and Wildlife Service, and the Ohio Department of Natural Resources, Division of Wildlife.

The State of Ohio Department of Natural Resources operates many wildlife and 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 is a wooded area at the southern end of Magee Marsh, which offers boating and fishing. Crane Creek is adjacent to Magee Marsh, and is a popular bird watching and hunting area. The Ottawa National Wildlife Refuge, which is ated by the U.S. Fish and Wildlife Service, lies four to nine miles WNW of the Site, immediately west of Magee Marsh. 23 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report References

1. "Basic Radiation Protection Criteria," Report No. 39, National Council on Radiation 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 diation," Report No. 94, National Council on Radiation Protection and Measurements, 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 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. XVID, 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, 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 2015 Annual Radiological Environmental Operating Report \ 14. "Nuclear Energy Emerges from 1980s 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. 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. ly 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, Fernald Environmental Management Project, United States partment of Energy (June 1993). 25. "Exposure from the Uranium Series with Emphasis on Radon and its Daughters" Report No. 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 ments, Washington, D.C. (1984). 25 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at 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 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. lection of sample types is based on the established critical pathways for the transfer of clides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population 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 Program The federal government requires nuclear facilities to conduct radiological environmental toring prior to constructing the facility.

This pre-operational surveillance program is for the lection of data needed to identify critical pathways, including selection of radioisotope and sample media combinations for the surveillance conducted after facility operations begin. ochemical analyses performed on samples should include nuclides that are expected to be 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 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 quencies and locations, collection techniques and radiochemical analyses performed, should be 26 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report carefully considered and incorporated in the design of the operational surveillance program. In this manner, data can be compared in a variety of ways (for example: from year to year, location to location, etc.) in order to detect any radiological impact the facility has on the surrounding vironment.

Data collection during the pre-operational phase should be planned to provide a comprehensive 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 u§e 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 economic viability and commissioning 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 tion's Technical Specifications and Offsite Dose Calculation Manual

• to determine whether any significant increase in the concentration of clides in critical pathways occurs

• to identify and evaluate the buildup, if any, of radionuclides in the local ronment, or any changes in normal background radiation levels

• to verify adequacy of Station controls for the release of radioactive 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 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 sis followed by a comparison of results 27 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report

• splitting samples prior to analysis by independent laboratories, and then paring the results for agreement

• 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 ty 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 ty of the laboratories' analytical procedures and data generated.

In 1987, environmental sampling personnyl at Davis-Besse incorporated their own QA 'program into the REMP. Duplicate samples, called quality control samples, were collected at several cations. These duplicate samples were assigned different identification numbers than the 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 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 and soil

• aquatic --including samples of treated and untreated surface water, fish, and shoreline sediments

• direct radiation

--measured by thermoluminescent dosimeters All environmental samples are labeled using a sampling code. Table 2 provides the sample codes and collection frequency for each sample type. . REMP samples are collected onsite and offsite up to 25 miles away from the Station. Sampling locations may be divided into two general categories:

indicator and control. Indicator locations 28 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report are those which would be most likely to display the effects caused by the operation of Besse, and are located within five miles of the station. Control locations are those which should 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 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 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 ronmental samples. These additional samples are referred to as the REMP Enhancement ples. Approximately 2,000 samples were collected and over 2,300 analyses were performed during 2015. 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. 29 Davis"Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report -', Table 2: Sample Codes *and Collection Frequencies Sample Collection Sample Type Code Frequency Airborne Particulate AP Weekly Ail-borne Iodine AI Weekly Thennoluminescent TLD Quarterly, Annually Dosimeter Milk MIL Monthly (semi-monthly during grazing season) Groundwater WW Quarterly (when available)

Broadleaf Vegetation BLV Monthly (when Surface Water -Treated SWT Weekly Surface Water -swu Weekly Untreated Fish FIS Annually Shoreline Sediment SED Semiannually Soil SOI Annually Fruit FRU Annually 30 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 3: Sample Collection Summary Sample Collection Number of Number of Number of Type Type*/ Locations Samples Samples (Remarks)

Frequency**

Collected Missed Atmospheric Airborne Particulates C/W 10 520 0 Airborne Radioiodine C/W 10 520 0 Terrestrial Milk (Jan.-Dec.)

G/M 1 12 0 Groundwater GIQ** 3 8 0 Broadleaf Vegetation G/M 3 8 0 Fruit GIA 3 3 0 Soil GIA 10 10 0 Aquatic Treated Comp/WM 3 156 0 Surface Water G/WM*** 1 51 1 Untreated G/WM*** 2 104 0 Surface Water Comp/WM 3 156 0 Fish (3 species) GIA 2 6 0 Shoreline Sediments GISA 5 8 0 Direct Radiation Thermoluminescent CIQ 88 350 2 Dosimeters (TLD) CIA 88 86 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 ***Includes quality control location.

SWU and SWT QC included in weekly grab sample/composited monthly Number of samples is the product oflocations times frequency.

Except for groundwater, broadleaf vegetation, fish. These are the number of samples available.

31 Davis-Besse Nuclear Power Station 2015 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 decay gives a continuous energy spectrum rather than the discrete lines or "peaks" associated with gamma radiation, identification 1 of specific beta emitting nuclides is much more difficult.

Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal tions of beta emitting radionuclides; it.does not identify specific radionuclides.

Gross beta sis merely acts as a tool to identify samples that may require further analysis .. Gamma spectral analysis provides more specific information than gross beta analysi$.

Gamma spectral analysis identifies each gamma emitting radionuclide present in the sample, and the amount of each nuclide present. Each radionuclide has a very specific "fingerprint" that allows for swift and accurate identification.

For example, gamma spectral analysis can be used to tify the presence and amount of lodine-131 in a sample. Iodine-131 is a man-made radioactive isotope of Iodine that may be present in the environment as a result of fallout from nuclear ons testing, routine medical uses in diagnostic tests, and routine releases from nuclear power tions. 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 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 environmen-. tal 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 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.

/ 32 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples Sample Type Atmospheric Monitoring Airborne Particulate Airborne Radioiodine Terrestrial Monitoring Milk Groundwater Broadleaf Vegetation and Fruits Soil Analyses Performed Gross Beta Gamma Spectroscopy Strontium-89 Strontium-90 Iodine-131 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 33 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4: Radiochemical Analyses Performed on REMP Samples (continued)

Sample Type Aquatic monitoring Untreated Surface Water Treated Surface Water Fish Shoreline Sediment Direct Radiation Monitoring Thermoluminescent Dosimeters Sample History Comparison Analyses Performed 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 Gamma Dose 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 er years. Generally, the results of sample analyses are compared with pre-operational and tional 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 ed to determine whether it is attributable to the operation of Davis-Besse, or to some other source such as nuclear weapons testing. 34 Davis-Besse Nuclear Power Station 2015 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 'Yeapons testing 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 at all ten air sample locations over a four-week period between March 22 and April 12, 2011 following the Fukushima Daiichi Nuclear Station disaster in Japan. There was virtually no difference in Iodine-131 concentration at control and tor locations during this period. Terrestrial Monitoring:

• Groundwater:

Tritium was not detected above the lower limit of detection during 2015 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.

Iodine was not detected in REMP milk samples following the shima Daiichi Nuclear Station disaster in 2011. No lodine-131 detected in any REMP samples was attributable to the operation of Davis-Besse.

'

• 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 Chernobyl 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.

Tritium was detected at two locations with concentrations slightly over the detection limit of 330 pCi/L, the hightest being 721 pCi/L in Untreated Surface Water samples during 2015.

• Fish: Only natural background radioactive material was detected.

• Shoreline Sediments:

Only natural background radiation, material from nuclear testing and the 1986 nuclear accident at Chernobyl have been detected.

35 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Direct Radiation Monitoring

• Thermoluminescent Dosimeters (TLDs): The annual gamma TLD dose rates for the current reporting period averaged 56.2 millirem/year at Indicator locations, and 63.8 millirem/year at Control locations.

No increase above natural background radiation tributable to the operation of Davis-Besse has been observed.

2015 Program Anomalies There has been elevated Gross Beta results at the T-i 1 Ottawa County Regional Water Intake Facility.

This is not attributed to normal power plant operations as indicated by T-3 Site ry, near mouth of Toussaint River sample point indicating normal gross beta results. The elevated results at T-11 were verified to be potassium by ICP analysis.

This potassium may be attributed to fertilizer runoff into the mouth of the Portage River which is located near the T-11 sample point. Gross Beta is not a reportable radioactivity concentration per the ODCM. The Site Boundary, ESE of the station did not indicate any anomalous Gross Beta results. This would. indicate that the DBNPS is not the source of the elevated Gross Beta results at the Ottawa, County facility.

All REMP samples were collected.

Abnormal Releases There were no abnormal liquid or gaseous releases occurring during 2015. 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 sorirce. Inhaled radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air ples collected by the Davis-Besse REMP include airborne particulate and airborne 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 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.

/ 36 D avis-B esse ucl ea r P ower St a tion 2015 Annual R adiologica l Environmental Op erati ng Rep o rt 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 i s performed on each of the weekly sa mple s. Each quarter , the filters from each location are combined (composite) and analyzed for gammaemitting radionuclides, Strontium-89 and Strontium-90.

Beta-emitting radionuclides were tected at an average concentration of 0.028 pCi/m 3 at both indicator and control location s. lium-7 was the only gamma-emitting radionuclide detected by the gamma s pectro s copic analysis of the quarterly compo s ite s. 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 verse change in radioactivity in air samples attributable to the operation of the Davi s-Bes se clear Power Station in 2015. 37

... 0 Q. Davi s-Be s se Nuclear Power Station 2015 Annual Radiol og ical Environmental Operating R e port Airborne Iodine-131 Airborne Iodine-131 samples are collected at the same ten location s a s the airborne particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly , sealed in s eparate collection bags and sent to the laboratory for gamma analy s is. 2015 Ai r borne Gross Beta 0.045 0.04 0.035 0.03 0.025 0.02 Ja n. Feb. M a r. Apri l May Ju ne Ju ly Aug. Sep t. Oct. av. Mom h I --+-Cootrol -+-Ind i cator I Figure 10. Concentration s of beta-emitting radionuclide s in airborne particulate s amples were nearly identical a t indicator and control location s during 2015. 38 De c_

Davi s-B esse Nuclear Power Station 2015 Annual Radiolo g ical Environmental Operating R e port Table 5: Air Monitoring Locations Sample Location Type of Number Location T-1

• I T-2* I T-3* I T-4 I T-7* I T-8 I T-9 c T-11

• c T-12 c T-27 c I= Indicator C = Control *denote s ODCM-required sam ple Location Description Site boundary, 0.6 miles ENE of Station Site boundary , 0.9 mile s E of Station Site boundary , 1.4 miles ESE of Station Site boundary, 0.8 mile s S of Station Sand Beach , main entrance, 0.9 miles NW of St a tion Earl Moore Farm, 2.7 miles WSW o f Station Oak Harbor Substation , 6.8 mile s SW of Station Port Clinton Water Treatment Plant , 9 .5 miles SE of Station Toledo Water Tr eatme nt Pl ant, 20.7 miles WNW of Station Crane Creek , 5.3 miles WNW of Station 39 DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AIR SAMPLES: SITE ' NW ' NNW N ' ' I ' I ' I I ' I I ' 0 0 ' I , < I , (/J I , I CD I # CD (/J (/J CD I I z I I c 0 , iD , , , 0 , , I , , , , -u I , 0 ---CD ---, ------V> -., .+ 0 ID w c 0 ' E :::J CD N 0 ---U1 ------l> l> ---:::J ---:::J ' ---c -"' ... 0 ... ---0 V> ---... ---:0 ... ---... 0 "O ' ... Q_ CD ' ... ... 0 ' ... I (/l I 0 ID -+ ESE I 0 CD I 0 :;:::: INDICATOR STATIONS I 0 I , '4J rri "O -.J :::J I ... < ... ' ... , A IR S A t.f>LE ... I.., 0 ... :::J ... I ... , 3 ... CD ... :::J ... , .+ ... 0 I ... , , I ... SW , 0 "O CD , , , , ' 0 , ' SE , .+ , ... I ' , ... , l :::J ' ID I ' , , :0 ' , CD , "O ' , 0 , , .+ DB' 04-02-16 DFN*F*/SCHEO/SK2817.0GN WNW ... . .. w .,, -'° c ' (1) N l> =i" .bo (/) u (1) en U1 ' 3 -(1) :;::: WSW 0 u D A V IS-BES S E NUCLEAR POWER STATION RADIOLOGICAL ENV I RONMENTAL MON IT ORING PROGRAM *****: .... . ci ci : er er ::r: .u .111 . er * <[ :o .. *. C r eek ...J ...J 0 er $*. er * .. j .. w er <[ .f * .... SW er 0 a.. B I ER *.RD( CARROLL z <[ ::::;; ...J INDICATOR STATIONS I w ID ' A I R SA lif>L E ci *****: w '-' z ::; a.. <[

• D. ** RD. SSW AIR SAMPLES: 5 MILE R A DIUS ci ci er er CAMP PERRY-er "'I llJ 1-**+-. :::J .<[ w *3: ...J ..... : <[ \I I .... :::J 0 111 .... z ..... 111 :::J 0 .... 1 63 ci er w .... <[ "' 0 er ID ****** SE DB* OFN*Fo/SCHED/SKZ8 1 6.DGN 0 ::J N 0 U1 l> ::J ::J c 0 :0 0 Q_ 0 0 '° 0 0 r'1 ::J < , 0 ::J 3 (1) ::J .+ 0 0 u (1) , 0 ::J '° :0 (1) u 0 , .+

M I C H Tl -'° c .., <D "" l> -* .., .l>. Vl N u N l]1 ' 3 -<D :;:::: 0 u *'. DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Or e oon w *. SW ,'Cl) *l,J " Ill ..... .*** CONTROL STATIONS ' AIR SAMPLE AIR SAMPLES: 5-25 M I LE RAD IUS .... SE SSW DB: 04-02-16 DFN*F:/SCHED

/SKZ815.DGN 0 0 < en I (IJ <D en en <D z c 0 <D 0 .., -0 0 "'-<D .., Vl ,.,. 0 ,.,. -* 0 :::J N 0 -l]1 l> :::J :::J c 0 ::0 0 Q_ 0 0 '° 0 0 rrt :::J < .., 0 :::J 3 <D :::J ,.,. 0 0 u <D .., 0 ,.,. :::J '° ::0 <D u 0 .., ,.,.

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Terrestrial Monitoring The collection and analysis of groundwater, milk, fruits and broad leaf vegetation provides data to assess the buildup of radionuclides that may be ingested by humans. The data from soil pling provides information on the deposition of radionuclides from the atmosphere.

Many radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. Some of the radionuclides present are:

• Tritium, present as a result of the interaction of cosmic radiation with the upper atmosphere and as a result of routine release from nuclear facilities

• B eryllium-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 clear weapons testing and routine releases from nuclear facilities

• Potassium-40, a naturally occurring radionuclide normally found out the environment (including in the human body)

• Fallout ra di on u clides 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, erational data from previous years, control location data, and the types and amounts of 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 es onto forage consumed by cows. The radionuclides present in the forage-eating cow are porated 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 sampled monthly in order to gather additional baseline data. If dairy animals are discovered 43 Davi s-Be sse Nuclear Power Station 2015 Annual R a diological Environmental Operatin g Report within five miles of the station, efforts will be made to include them in the milk sampling gram as indicator sites. The 2015 milk samples were analyzed for Strontium-89, Strontium-90, Iodine-131, other ma-emitting radionuclides , stable Calcium and Potassium.

A total of 12 milk samples were lected in 2015. Strontium-89 was not detected above its LLD of 0.6 pCi/l. The annual average concentration of Strontium-90 was 0.7 pCi/l. The annual average concentration was similar to those measured in previou s years. Iodine-131 was not detected in any of the milk sa mple above the LLD of 0.5 pCi/l. The trations of Barium-140 and Cesium-137 were below their respective LLDs in all samples collected. Since the chemistries of Calcium and Strontium are similar, as are Potassium and Cesium, 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/l) to the concentration of Calcium (g/l), and the Cesium tivity (pCi/l) compared to the concentration of Pota ss ium (g/l) were monitored in milk. These ratios are compared to standard values to determine if buildup is occurring.

No statistically nificant variations in the ratios were observed. Table 6: Milk Monitoring Location Sample Location Number T-24 C =Control Type of Location c Groundwater Samples Location Description Toft Dairy , Sandusky, 21.0 miles SE of Station Soil acts as a filter and an ion exchange medium for most radionuclides.

However , tritium and other radionuclides s uch as Ruthenium-I 06 ha ve a potential to seep through the soil and could reach groundwater.

Davis-Besse does not di sc harge its liquid effluents directly to the ground. REMP personnel sample local wells on a quarterly ba sis to ensure early detection of any adverse impact on the local groundwater supplies due to Station operation.

In addition , a quality control sample is collected when the wells are sampled. The groundwater samples are analyzed for emitting radionuclides, tritium, Strontium-89, Strontium-90 and gamma-emitting radionuclides.

During the fall of 1998, the Carroll Town s hip Water Plant began operation a nd offered residents a reliable, inexpensive source of high-qu ality drinking water. This facility ha s replaced all of the drinking water wells near Davi s-Be sse, as verified by the Ottawa County Health Department , and 44 Davis-Be sse Nuclear Power Station 2015 Annual Radiolo g ical Environmental Operating Report 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 3.5 pCi/l at Indicator sites and 1.8 pCi/l at the Control site, T-27 A. REMP Groundwater samples were not affected by the operation of the Davis-Besse Nuclear Power Station. Gross Beta Gro u nd Water 1 982-2015 u Q. 0 l8 al SJ gi 8 8 8 a N v <D (I) (I) (I) (I) (I) a a 0 0 0 0 0 0 0 N N N N N N N N N Year --I ndi cat or -tt-Contro l Figure 14: Shown above are the annual averages for gross beta in groundwater from 1982-2015. There were no cator sa mple s available in 2000 and no control sa mple s available in 2009. 45 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 7: Groundwater Monitoring Locations Sample Location Number T-27A T-225 T-226 C = control I = indicator Type of Location c I I Broadleaf Vegetation and Fruit Samples Location Description Crane Creek Long Beach and Park, 1.5 mi NW of Station Allen residence, 1.6 miles NW of Station 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 ter which receives liquid effluents (hospitals, nuclear facilities, etc.). Radionuclide s 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 ed from orchards in the vicinity of Da vis-Besse, and a control sample is collected, as well. In 2015, broadleaf vegetation samples were collected at two indicator locations (T-227 and T-19) and one control location (T-37). Fruit samp le s were collected at two indicator locations (T-8 and T-25) and one control location (T-209). Bro adleaf vegetation was collected once per month ing the growing season and consisted of cabbage. The fruit that was collected was apples. All samp le s were analyzed for gamma-emitting radionuclides, Strontium-89, Strontium-90, and dine-131.

Iodine-131 was not detected above the LLD of 0.022 pCi/g (wet) in any broadleaf vegetation nor above the LLD of 0.020 pCi/g (wet) in fruit samples. The only gamma-emitting radionuclide detected in the fruit and broadleaf vegetation samples was Pota ssi um-40 , which is naturally ring. Re sults 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 respective LLDs (0.004 and 0.001 pCi/l wet) in broadleaf vegetation samples at control and indicator locations.

Op erat ion of Davis-Besse had no observable adverse radiological effect on the surrounding environment in 2015. 46 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 8: Broadleaf Vegetation and Fruit Locations Sample Location Type of Number Location T-8 I T-19* I T-25 I T-37* c T-209 c I= indicator, C = control *denotes ODCM-required sample Soil Samples Location Description Moore Farm, 2.7 miles WSW of Station (F RU) L. Bowyer Jr., 1.0 mile W of Station (BLV) Witt Farm , 1.6 miles S of Station (FRU) Bench Farm, 13.0 miles SW of Station (BLV) Roving Control Fruit location (FRU) Soil samples are generally collected once a year adjacent to our ten continuous air samplers. ly the top layer of soil is sampled in an effort to identify possible trends in the local environmental nuclide concentration caused by atmospheric deposition of fallout and station-released radionuclides.

Generally, the sites are relatively undisturbed, so that the sample will be sentative of the actual deposition in the area. Ideally, there should be little or no vegetation sent, because the vegetation could affect the results of analyses.

Approximately five pounds of soil are taken from the top two inches at each site. Many naturally occurring radionuclides such as Beryllium-7 (Be-7), Potassium-40 (K-40) and fallout radionuclides from nuclear weapons ing are detected.

Fallout radionuclides that are often detected include Strontium-90 (Sr-90) and Cesium-137 (Cs-137).

Soil was collected at the ten sites in 2015. The indicator locations included T-1, T-2, T-3, T-4, T-7, and T-8. The control locations were T-9, T-11 , T-12 , and T-27. All soil samples were lyzed for gamma-emitting radionuclides.

The only gamma emitter detected (in addition to rally occurring Be-7 and K-40) was Cs-137. Cs-137 was found in Indicator and Control locations at average concentrations of 0.12 pCi/g (dry) and 0.09 pCi/g (dry), respectively.

The concentrations were similar to that observed in previous years. 47 E I! IOI ::. (.) Q, Da v i s-B esse ucl ear Po w er St a tion 2015 Annu al R a di o l og i ca l En v ironm e ntal Ope ra tin g Report Cs-137 i n Soil 1972-2015 1.2 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.0 N v <D CXl 0 N v <D CXl 0 N v <D CXl 0 N v <D CXl 0 N ..... ..... ..... ..... CXl CXl CXl CXl CXl O> O> Cl O> O> 0 0 0 0 0 --Year --I nd i cat o r --c on tro l Figure 15: The concentration of Cesium-137 in s oil has s teadily declined in recent years. The pe a k s een in 1978 wa s due to fallout from nuclear weapon s te s ting. 48 v CXl --

Davis-Be sse Nuclear Pow e r Station 2015 Annual Radiolo gica l Environmental Operating Report Sample Location Type of Number Location T-1 I T-2 I T-3 I T-4 I T-7 I T-8 I T-9 c T-11 c T-12 c T-27 c I = indicator C = control Table 9: Soil Locations 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 Sub statio n, 6.8 miles SW of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 20.7 mile s WNW of Station Crane Creek, 5.3 miles WNW of Station 49 NW ... ---,, '° w c ., ct> en -I ct> ., Ul ., 0 ct> (/) -+ ., 0 WSW (/l -+ ct> ; :;:: ; 0 ; "O ; SW I DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I ' I I ' ' ' ' I I ' ' ' ' ' NNW ' I I I I I I I I N I I I I I I I I I I I I I I I I I I I I TERRESTRIAL SAMPLES: SITE I # ---------------------... ... ------... ... ... ... ... ... ... ... ... INDICATOR STATIONS ... ... ... ... ... ... a SOIL ... I I ' ' ' ' ' SE ' ' ' E ------ESE ... ... ... ... I I ... I I I I ---I I ---I I I I 1 1-J -./ , ... DB* 04-02-1 6 DFN*F*/SCHED/SKZ817.0GN 0 0 < (/) 0 :J "' 0 ll1 )> :J :J c 0 ;o 0 0. 0 0 '° 0 0 rri :J < , 0 :J 3 ct> :J ..+ 0 0 "O ct> , 0 :J '° ;o ct> "O 0 , ..+

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• SOIL TERRESTRIAL SAMPLES: 5-25 MILE RADIUS .**¢ . .**"{> SE SSW DB: 04-0 2-16 DFN*F:/SCHED/SKZ815.DGN CJ 0 < (/) I Cll ro (/) (/) ro z c () (D 0 , "lJ 0 "' ro , Vl rl-0 rl-0 :::J N 0 Ul l> :::J :::J c 0 ::0 0 0. 0 0 '° () 0 rn :::J < , 0 :::J 3 ro :::J rl-0 0 "O ro , 0 rl--* :::J '° ::0 ro "O 0 , rl-Davi s-Be sse Nuclear Power Station 2015 Annual Radiological Environmental Operatin g Report -.. *"' 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 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, s horeline sediments and from immersion (swimming) in the water. Internal exposure can occur from ingestion of nuclides, 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 collects samples of 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 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 one indicator (T-22B) and two control tions (T-11 and T-12). These locations include the water treatment facilities for Carroll ship, Port Clinton and Toledo. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta-emitting radionuclides.

The sa mples were also posited in a quarterly sample and analyzed for Strontium-89 , Strontium-90, gamma-emitting dionuclides, and tritium. One QC sample was collected from a routine location , which changed each month. 53 5 4_5 4 3_5 3 5 2.5 0 a. 2 1.5 0 N ..... en -Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report The annual average of beta-emitting radionuclides for indicator and control location s was 2.3 and 2.6 pCi/l, respectively.

The se results are similar to previous years. Tritium was not detected above the LLD of 330 pCi/l during 2015. Strontium-89 was not detected above the LLD of 0.8 pCi/1. Strontium-90 activity was not detected above its LLD of 0.8 pCi/1. The se results are lar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse during 2015. 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. Gross Beta in Treated Surface Water 1972-2015

! CC> co 0 N

B :B N -a; co 8 N s 8 co S! N ..... ..... co co en (]) 0 0 -en en en en en (]) en en (]) 0 0 0 0 0 0 0 ---------N N N N N N N Year --I ndicator --control I Figure 19: Since 1974, the ann ual concentrations of beta emitting radionuclides in treated surface water samples collected from indicator locations have been consistent with those from control locations.

Da vis-Besse has had no measurable radiological impact on treated surface water used to make drinking water. 54 0 0 N N Davis-Be sse Nuclear Power Station 2015 Annual R a diological Environmental Operating Report Table 10: Treated Surface Water Locations Sample Location Number T-11

• T-12 T-22B* T-143 I = indicator C =control QC = qu a lit y control Type of Location c c I QC

• denotes ODCM-r eq uired sam ple Location Description 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, sa mpled at Davis-Besse REMP lab Quality Control Site 55 Davi s-Be sse Nuclear Power Station 2015 Annual Radiological Environmental Operatin g Report Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to humans from external exposure from the lake surface as well as 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 ter samples are collected from water intakes used by nearby water treatment plant s. Routine samples are collected at Port Clinton, Toledo and Carroll Township.

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. 56

.. D av i s-B esse N ucl ear P owe r S ta ti o n 2015 A nnu al R a di o l ogica l E n v i ro nm e nt a l Op era tin g R e p o rt Sample Results For the routine untreated s urface water s amples that a re composited weekly, the beta emitting radionuclides had an average concentration of 2.6 pCi/L at indicator locations during 2015. trol locations averaged 10.3 pCi/L during thi s period. Each month , weekl y compo s ited qualit y control s ample s of untreated w a ter were analyzed from different location s. The re s ult s of the T-11 control sa mple point located at the Ottawa County Regional Water Int a ke F a cility s tarted s ho wi ng ele va t e d Gro ss Bet a re s ul ts in Augu s t and ued through December.

Gro ss Beta in Untr e at e d Sur fa ce Water i s not a report a ble radioacti v it y concentration per the Off s ite Do s e Calculation M a nu a l. The ele v ated Gro ss Beta s ample result s were verified to be pota ss ium by ICP analy s i s. The pota ss ium ma y be attributed to fertilizer runoff into the Portage Ri v er which is near the T-11 sample point. The Site Boundary , ESE of the s tation did not indicate any anomalou s Gro ss Beta re s ult s. This would indicate that the DBNPS i s not the s ource o f the ele v ated Gro ss Beta re s ult s at the Ottawa County facility.

Gross Beta Concentration i n Untreated S u rface Water 1977-2015 0.0 ..... O> ;;; :a :;; a; l7l :;; 0 a t; -<") "' ..... ..... 0 0 0 0 0 0 0 0 N N N N N N N N Year I -+-Indicator

--contro l I Fi g ure 20: The ave rage concentration o f bet a-emittin g radionuclide s in Untr ea ted Surf a ce Water. 57 Davi s-Be sse Nuclear Power Station 2015 Annual Radiolo g ic a l Environmental Operating Report Table 11: Untreated Surface Water Locations Sample Location Number T-3 T-11

• T-12 T-22A* T-145 Type of Location I c c I QC I = indicator , C = co ntrol *denotes ODCM-requir e d sa mpl e Location Description Site boundary, 1.4 mile s ESE of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant , sample taken from intake crib, 12.6 miles NW of Station Carroll Town s hip Water Plant , State Route 2, 2.1 mile s NW of Station Roving Quality Control Site 58 Davi s-Be ss e Nuclear Power Station 2015 Annual Radiolo g ical Environmental Operating Report Shoreline Sediment The sampling of shoreline sediments can provide an indication of the accumulation of insoluble radionuclide s 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 line exposure to fi s hermen 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). Sample s were lyzed for gamma-emitting radionuclides.

Naturally occurring Potassium-40 was detected at both control and indicator locations. These re s ults are s imilar to previous years. Table 12: Shoreline Sediment Locations Sample Location Type of Number Location T-3 I T-4 I T-27* c T-132 I I = indicator C = control *Denotes ODCM-required sample Location Description Site boundary, 1.4 miles ESE of Station Site boundary, 0.8 mile s S of Station Crane Creek , 5 .3 miles WNW of Station Lake Erie , 1.0 miles E of Station 59 0 Da vis-B esse Nuclear Power Station 2015 Annual Radiolo gica l Environmental Operating Report Fish Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondarily to serve as indicators of radioactivity in the aquatic ecosystem.

The principal nuclides 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 s pecies (e.g., bottom-feeder versus ator), results from sa mple analyses may vary. Da v i s-Besse routinely collects three s pecies of fish once per year from sa mpling 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 ed because of being a popular recreational fish and white perch and white bass are collected cause their importance as a commercial fish. Carp are not ODCM-required samples, but are collected as enhancement sa mple s becau se they feed on the bottom where contaminants may tle. The average concentration of bet a-emitting radionuclides in ODCM-required fish was similar for indicator and control locations (3.55 pCi/g and 3.83 pCi/g wet weight, respectively).

No gamma emitters were detected above their respective LLDs. Gross Beta in F i s h 1972-2015

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---Ccntrnl I Fi g ure 21: Average conce nt rations of beta-emittin g radionuclides (pCi/gram) in fish sa mple s were s imilar at i nditor and control locations , and were comparable to results of previous years. 60 Davi s-Be ss e ucl e ar Power St a tion 2015 Annu a l R a diolo g i ca l En v ironm e nt a l Oper a tin g R e port Table 13: Fish Locations Sample Location Number T-33* T-35* Type of Location I c I = indicator C= control *Denote s ODCM-required sample Location Description Lake Erie, within 5 mile s radius of Station Lake Erie , greater than 10 mile radius of Station 61 DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AQUATIC SA MPL ES: S I TE ' I NW ' NNW I N ' ' ' ' ' ' CJ 0 < I I (/) I I I CD I (!) I (/) (/) (!) I z I c I 0 I , (!) , 0 , I , , " I , 0 " , ---(!) ------, ---Vl rl-0 ,, w 0 '° c E :J -, (1) "' 0 "' N ---U1 ---------)> ---:J )> ---:J c "' D ---"' c ' ---0 0 -------+ ' :u ' ' 0 n ' 0. ' ' Vl ' ' 0 ' -+ I 0 (!) IO ES E I 0 3:: INDICATOR STATIONS 0 0 I "O 1 t..J fTl ...., :J I i SHORELINE SEO I MENTS ' < I ' ' , I ii SURFACE ' I.._ 0 WAT E R TREATED ' :J , I ' I 3 'ft SURFACE ' (!) WATER UNTREATED

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Davis-Besse Nuclear Powe r Station 2015 Annual Radiologic al 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 luminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information.

The TLDs used at Davis-Besse contain a Sulfate:Dysprosium (CaS0 4: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 mea s ure the dose received over long periods of time. The energy that was stored in the TLD as a result of interaction with 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 proce ss re-zeroes the TLD and prepares it for reuse. TLD Collection Davis-Bes s e 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 381 TLDs in the environment surrounding Davi s-Be ss e. By lecting them on a quarterly and annual ba sis from a si ngle site, each measurement serv es 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 2015 , the average dose equivalent for quarterly TLDs at indicator locations was 14.5 rnrem/91 day s, and for control locations was 17.5 rnrem/91 days. The average dose lent for annual TLDs in 2015 was 56.2 rnrem/365 day s at indicator locations and 63.8 rnrem/365 days for control locations.

Quality Control TLDs Duplicate TLDs have been placed at 18 sites. The se TLD s 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 measurement s at the location without the laboratory being aware that they are the same. A compari so n 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 13.4 rnrem/91 days while the quality control TLD s at control location s yielded an average dose equivalent of 16.5 rnrem/91 days. 65 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Gamma Dose for E n vironmental TLOs 1973-2015

• ii' 1:1 e E f E 8 Ol ;! ie 00 l!j Cb l8 8 Sl 8 ;!; :g 0 t--Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 0 0 0 N N N N N N N Year --I n d i cator --c o n tr o l Figure 25: The similarity between indicator and control results demonstrates that the operation of Davi s-Be sse ha s not caused any abnormal gamma dose. 66 .,,. 0 0 N N Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations Sample Location Type of Number Location T-1 * *1 T-2* I T-3* I T-4* I T-5* I T-6

• I .T-7* I T-8* I T-9 c T-10* I T-11

• c T-12* c T-24 c T-27 c T-38 I T-39 I T-40* I T-41* I T-42* 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 Site boundary, 0.5 miles W of Station Site boundary, 0.5 miles NNE of Station Sand Beach entrance, 0.9 miles NW of Statiom Moore Farm, 2.7 miles WSW of Station Oak Harbor Substation, 6.8 miles SW of Station 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 67 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location T-43 I T-44 I T-45 I T-46* I T-47* I T-48* I T-49 I T-50* I T-51 c T-52* I T-53 I T-54* I T-55* I T-60 I T-62 I T-65 I T-66 I T-67* I T-68* I T-69 I Location Description Site boundary, 0.5 miles SW of Station Site boundary, 0.5 miles WSW of Station Site boundary, 0.5 miles W"NW 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 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) miles ENE of Station Site boundary, 0.3 miles N"NW of Station Site boundary, 0.5 miles W"NW of Station Site boundary, 0.4 miles W of Station 68 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number* Location Location Description T-71 I Site boundary, 0.1 mile NNW of Station T-73 I Site boundary, 0.1 mile WSW of Station T-74 I Site boundary, 0.1 mile SSW of Station T-75 I Site boundary, 0.2 mile SSE of Station T-76 I Site boundary, 0.1 mile SE of Station T-80 QC Quality Control Site T-81 QC Quality Control Site T-82 QC Quality Control Site T-83 QC Quality Control Site T-84 QC Quality Control Site T-85 QC Quality Control Site T-86 QC Quality Control Site T-88 QC Qualicy Control Site T-87 QC Quality Control in lead pig DBAB Annex T-89 QC Quality Control Site T-90 I Site Personnel Processing Facility T-91

• I State Route 2 and Rankie Road, 2.5 miles SSE T-92 I Locust Point Road, 2.7 miles WNW of Station T-93 I Twelfth Street, Sand Beach, 0.6 miles NNE of Station T-94 I State Route 2, 1.8 miles WNW of Station T-95 c State Route 579, 9.3 miles W of Station 69 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Type of Number Location T-100 -c T-111 c T-112* I T-113 QC T-114 QC T-115 QC T-116 QC T-117 QC T-118 QC T-119 QC T-120 QC T-121 I T-122 I T-123 I T-124 c T-125 I T-126 I T-127 I Location Description 9ttawa 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 t 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 Lake Street, Ottawa Co. Agricultural Complex 5.5 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 r -Camp Perry Western and Rymers Road, 4.0 miles SSE of Station 70 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations Sample Location Number T-128 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 Type of Location I I I I I I c I I I I I I I I 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. 71 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Number T-211 T-212 T-213 T-214 T-215 T-216 T-217 T-218 T-219 T-220 T-221 T-222 T-223 T-224

• I = Indicator C =Control QC = Quality Control Type of Location I I I I I I I I I I c I I I *denotes ODCM-required TLD Location Description Site boundary, 0.79 miles E of Station Site boundary, 1.2 miles ESE of Station Site boundary, 0.6 miles SSW of Station Site boundary, 0.7 miles SW of Station Site boundary, 0.5 miles W of Station Site boundary, 0.7 miles NW of station Salem-Carroll Rd., 4.7 miles SSW of Station Toussaint East Rd., 4.0 miles WSW of Station Toussaint Portage Rd., 4.8 miles WSW of Station Duff-Washa Rd., 4.8 miles W of Station Magee Marsh, 5 .1 miles WNW of Station Turtle Creek Access, 3.7 miles WNW of Station Lawrence Rd., 5.0 miles SE of Station Erie Industrial Park, 4.4 miles SE of Station 72 NW ..,, '° c ' Cl> N en -...) (JJ ---< ,---0 Ul -+ Cl> :,;: 0 u SW , DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM \ \ \ \ \ \ \ T-206 (!)' NNW \ I I I I I I I I N I T-207 1 1 T-208 (!) (!) I I I I I I , , , SERVICE ;' ; ; , B LOC. , T-66 T L D S AM P L ES: S IT E ; ; ;;; (!) ---------' ' ' ---' ' ' ' ---------INDICATOR STATIONS I I 1 T-'11 I CD I I I I 'i" THERMOLUMINESCENT DOSIMETER

< TLD I \ \ \ \ \ E ---------' ' ' ' ' ' SE ---ESE ' ' ' ' T-'10 (!) ' ' ' , , , , ------, , , I I I 1 '41 ...., I.._ I D B* 0 4-0 2-1 6 D F N*F*/S CHEO/SKZ811.DGN 0 0 < (/I ' CD Cl> (/I (/I Cl> z c 0 Cl> 0 , -u 0 , Ul .+ 0 0 ::J N 0 lJ1 )> ::J ::J c 0 :u 0 0. 0 0 '° 0 0 [Tl ::J < , 0 ::J 3 Cl> ::J .+ 0 0 u Cl> , 0 .+ ::J '° :u Cl> u 0 , .+

,., -* '° c -, CD N ..... ..... --< .b r Cl U1 3 -CD 3:: 0 "O WNW ... ... w WSW DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . ......... . -' -' 0 *o :o:: *:r: :u

• Vl *O:: * <[ :o Rusho .* j .. 0 0:: SW .s'. TLD SAMPLES: 5 MILE RADI U S 0 0:: 0 0:: CAM P PERRY-T -53.CD CD T *52 'f-126 BIER * ** Ro ,* a .. er vi CAR.ROLL . * ** RD. T *21 7 SALEM-0 >-INDICATOR STATIONS <D THERMOLUMIMESCEMT DOS I METER <TLD l z <[ :::? -' I w al *** ct: . .. .<[ w .;.: -' *>-: <[ z ..... Vl 0 >-D 0:: w <[ "" 0 0:: al SE DB* D .. 02-16 DFN*F*I SCHED/SKZ816.DG N -u 0 , l/l ..... 0 0 ::J N D U1 l> ::J ::J c 0 ;o 0 0. 0 0 '° () 0 fTl ::J < , 0 ::J 3 CD ::J ..... 0 0 "O CD , 0 ..... ::J '° ;o CD "O 0 , .....

M I C H .,, -'° c , <D N a:> -..J __, r "' 0 N "' .. ' 3 -<D :;:: 0 "O DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Or-e oon ... ."!J .*** SW CONTROL STATIONS THERMOLUMINES C ENT "-!...'DOSIMETER

<TLD I TLD SAMPLES: 5-25 MILE RAD I US .**°¢ .. **{> SE SSW 08: 04-02-16 D FN*F:/SCHED/SKZ815.D GN 0 0 < (/I I CD <D (/I (/I <D z c 0 <D 0 , Cl 0 "' <D , Vl ..+ 0 ..+ 0 :::J N 0 -"' )> :::J :::J c 0 ::0 0 0. 0 0 '° 0 0 ,,., :::J < , 0 :::J 3 <D :::J ..+ 0 0 "O <D , 0 ..+ -* :::J '° ::0 <D "O 0 , ..+

Davis-Besse Nuclear Power Station 2015 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 cort-) centrations measured at indicator locations were compared with concentrations measured at trol locations in previous operational studies and in the pre-operational surveillance program. These comparisons indicate normal concentrations of radioactivity in all environmental samples collected in 2015. Davis-Besse's operation in 2015 indicated no adverse radiological impact on the residents and environment surrounding the station. The results of the sample' analyses formed during the period. of January through December 2015 are summarized in Appendix 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 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 diation," Report No. 94, National Council on Radiation Protection and Measurement, ington, D.C. (December 1987). 4. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy 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, 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 I (1988). 8. "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," American National Standards Institute, Inc., ANSI-N45-1975, New York, New York (1975). 9. "Public Radiation Exposure from Nuclear Power Generation in the United States," Report No. 92, National Council on Radiation Protection and Measurement, Washington, D.C. cember 1987). 76 Davis-Besse Nuclear Power Station 2015 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 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 Besse Nuclear Power Station Unit No.l, 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", (2000-2014) 19. Teledyne Isotopes Midwest Laboratory, "Pre-operational Environmental Radiological 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 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 itoring Program," S-72N. 24. Davis-Besse Nuclear Power Station, "Radiological Environmental Monitoring Program," DB-CN-00015.

77 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 25. Davis-Besse Nuclear Power Station, "Radiological Environmental Monit,oring 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 Op(frating 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 er Station Oak Harbor, Ohio", Environmental Resources Management, March 18, 2008. 78 , /

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2015 Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ionizing radiation were recognized and efforts were made to establish radiation protection standards.

The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recom-. mendations have been given legislative authority by being published in the Code of Federal ulations 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 general public. "Reasonably achievable" means that exposure.reduction is based on sound economic cisions 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 amoµnts of radioactive fission products and trace amounts of the component and structure surfaces, which have been activated, are present in the primary coolant water. The three types of radioactive material released are noble gases, Iodine and particulates, and tritium.

• The noble gas fission products in the primary coolant are given off as a gas *when the coolant is depressurized.

These gases are then collected by a system designed for gas collection and stored for radioactive decay prior t<? 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 ment drains and sumps. All liquids of this nature are mqnitored and processed, if necessary, prior to release. 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 ofradiation exposure to the body. Xe-133 andXe-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive noble gases leased. They are readily dispersed in the atmosphere.

79 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 tems, minimize their discharge.

The predominant radioiodine released is Iodine-131 with a 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 Cesium-137) and activation products (e.g., Cobalt-58 and Cobalt-60).

Radioactive Cesium and Cobalt 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 neutron interaction with deuterium (also a Hydrogen isotope) present in the water and with the Boron in the primary coolant. When tritium, in the form of water or water vapor, is ingested or inhaled 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 cosmic 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 exposure pathway is through ingestion of produce which has incorporated C-14 into plant matter via the chemical form of C02 during 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 systems, in-plant and environmental sampling and analysis programs, quality assurance programs for ent and environmental programs, and procedures covering all aspects of effluent and tal 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 80 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure the limits will not be exceeded.

If a monitor alarms, a release from a tank is automatically stopped. All wastes are sampled prior to release and analyzed to identify the specific concentrations of radionuclides.

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 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 rounding environment.

Frequent samples of other environmental media, such as water and tation, are taken to determine if buildup of dep'Osited radioactive material has occurred in the area. Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to radioactive materiaL The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the ment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An annual age of the water flow, wind speed, and wind direction are used to evaluate how the radionuclides will be distributed in an area for gaseous or liquid releases.

An important factor in evaluating the exposure pathways is the use of the environment.

Many factors are considered such as dietary intake of 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, deposition of radioactive material on plants, deposition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents involves pathways such as drinking water, fish, and direct exposure from the lake at the shoreline while swimming.

81 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report

• • • -..... ,..*.. . ..

Diluted By Atmosphere Ail'llorne Releases 'Consumed By Consumed By Animals II "_,;v By Man -By Man MAN R l.J"'-."-. Drillldng Sllareline0 ExiillSUre f.Al(E 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 by many different pathways, some result in more dose than others. The critical pathway is the exposure _route that will provide, for a specific clide, the greatest dose to a population, or to a specific group of the population called the critical gtoup. 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 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 radionuclides 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. 82 Davis-Besse Nuclear Power Station 2015 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 calculated 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 exposure ways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation, food I 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 dilution 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, 2015.

• Summation of the quantities of radioactive material released in gaseous and liquid ents (Tables 15-19)

• Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites (Table 20) During this reporting period, the estimated maximum individual offsite dose due to radioactivity released in effluents was: Liquid Effluents:

• 4.86E-03 mrem, maximum individual whole body

• 5.41E-03 mrem, maximum individual significant organ dose (liver) Gaseous Effluents:

Noble Gas:

• 5.04E-04 mrem, whole body

• 7.40E-04 mrad, skin Iodine -131, Tritium, and Particulates with Half-lives greater than 8 Days:

• 3.lSE-02 mrem, whole body dose _

• 3.lSE-02 mrem, significant organ dose (liver) Carbon-14:

• 2.60E-01 mrem, whole body

• 0.127E+Ol mrem, significant organ dose (bone) These doses are a small fraction of the limits set by the NRC in the Davis-Besse ODCM. tional 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 83' Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report effluents, the additional pathways include the Turbine Building drains via the settling basins. leases 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. I

• Released at a rate such that the total dose to the skin will be less than or equal to 300Q 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 10CFR50, Appendix I, Sec. IIB. 1, air dose due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

• Less than or equal to 10 mrad total for gamma radiation and less than or equal to 20 mrad total for beta radiation in any calendar year. ' In accordance with 10CFR50, Appendix I, Sec. IIC, dose to a member of the public from Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be 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 3.19 Ci of C-14 in the form of C02 released from Davis-Besse through the Station Vent during 2015. 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. 84 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 2, Columns 1 and 2, with the most restrictive 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 lE-05 uCi/ml of air (submersion dose) verted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication

2. Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release-of fission and activation products to less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the.skin.

Therefore, the average beta and gamina energies (E) for gaseous ents as described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable.

Measurements ofTotal Activity Fission and Activation Gases: These gases, excluding tritium, are collected in: Marinelli beakers specially modified for gas sam'." piing, 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 cation of each radionuclide present on the filter paper is performed by using gamma spectroscopy.

Liquid Effluents Liquid effluents are collected in a Marinelli beaker and counted on a germanium detector. _tification of each gamma-emitting radionuclide present in liquid samples is via gamma copy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system. Batch Releases Liquid from 1/1/15 through 12/31/15 1. Number of batch releases:

62 2. Total time period for the batch releases:

164.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 3. Maximum time period for a batch release: 243 minutes 4. Minimum time period for a batch release: 81 minutes 5. Average time period for a batch release: 160 minutes 85 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Gaseous from 1/1/15 through 12/31/15 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: ,,. Abnormal Releases 5 481.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 447.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 213 minutes There were no abnormal gaseous releases of radioactivity from the station during 2015. There were no abnormal liquid releases of radioactivity from the station during 2015. Percent of ODCM Release Limits The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent oflimits, for January 1, 2015 through December 31, 2015. PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1, 2015-December 31, 2015 (gaseous)

Noble gases (gamma) 3 .46E-05 mrad 10 mrad 3.46E-04 Noble gases (beta) 6.12E-05 mrad 20mrad 3.06E-04 I-131, tritium and particulates 2.24E-03 mrem 15 mrerri 1.49E-02 C-14 5 .35E-02 mrem 20mrem 2.68E-03 Report Period: January 1, 2015 -December 31, 2015 (liquid) Total body 4.42E-03 mrem 3mrem 1.47E-01 Organ (GILLI) 3.48E-03 mrem 10 mrem 3.48E-02 Sources of Input Data

• Water Usage: Survey of Water Treatment Plants (DSR-95-0034

7)

• 0-50 mile meat, milk, vegetable production, and population data was taken from 1982 Annual Environmental Operating R,eport entitled, "Evaluation of Compliance with Appendix I to 10CFR50: Updated Population, Agricultural, Meat -Animal, and Milk Production Data Tables for 1982". This evaluation was based on the 1980 Census, the Agricultural Ministry of Ontario 1980 report entitled "Agricultural tistics and Livestock Marketing Account", the Agricultural Ministry of Ontario port entitled "Agricultural Statistics for Ontario, Publication 21, 1980", the gan Department of Agriculture report entitled "Michigan Agricultural Statistics, 1981 ", and the Ohio Crop Reporting Service report entitled "Ohio Agricultural tistics, 1981 ".

• Gaseous and liquid source terms: Tables 16 through 19 of this report. 86 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating 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 sessment of radiation doses from radioactivity released in liquid and gaseous effluents to members of the public from activities inside the site boundary.

The Pavilion and Training Center pond are accessible to employees and their families.

The ion may be accessible to the public for certain social activities.

The Training Center 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 boundary dose. For poses 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), default 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 public for activities inside the site boundary.

This dose would be at least a factor of 35 times 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 occur. fore, the _modeling of the ODCM conservatively estimates the maximum potential dose to members of the public.

• The Old Steam Generator Storage Facility (OSGSF) provides long-term storage for two Once Through Steam Generators, two Reactor Coolant System Hot Leg Piping sections, one Reactor Vessel Closure Head (with Control Rod Drive Mechanisms and Service Support Structure).

The OSGSF is designed so that 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 10CFR20 (See page 19). Inoperable Radioactive Effluent Monitoring Equipment All required radioactive effluent monitoring equipment was in service during 2015. There was no radioactive effluent equipment out of service for more than 30 days. 87 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Procedure (PCP) There were two revisions to the ODCM during 2015. The first change was to update the ODCM with the latest Land Use Census information.The second change was related to the abandonment of RE8433 Collection Box Outlet to the Lake Radiation Monitor. RE8433 was a Non-Required Radiation Monitor. There were no changes to the Process Control Procedure Manual during 2015. Borated Water Storage Tank Radionuclide Concentrations During the reporting period of 2015, 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. 88 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Nuclide Table 15 Gaseous Effluents

-Summation of All Releases Unit 1st Qtr 2015 2nd Qtr 2015 3rdQtr 2015 4th Qtr 2015 Est. Total% Error Fission and Activation Gases Total Release Ci 0.00E+OO 0.00E+OO 3.46E-01 7.48E-05 2.5E+Ol Average Release Rate for Period Percent of ODCM Limits Iodines Total Iodines (I-131) Average Release Rate for Period Percent of ODCM Limits Particulates Particulates with half-lives greater than 8 days Average Release Rate for Period Percent of ODCM Limits uCilsec NIA NIA 3.66E-02 9.48E-06 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Ci uCi/sec O.OOE+OO NIA O.OOE+OO NIA O.OOE+OO NIA 0.00E+OO NIA See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Ci 0.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO uCilsec NIA NIA NIA NIA See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination 2.5E+Ol 2.5E+Ol Gross Alpha Activity Ci O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 2.5E+Ol Tritium Total Release Average Release Rate for Period Percent of ODCM Limits Carbon-14 Total Release Ci uCi/sec 2.04E+Ol 2.56E+OO 1.44E+Ol l.83E+OO l.23E+Ol l.30E+OO l.17E+Ol 1.48E+OO See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Ci 2.65E+OO 2.65E+OO 2.65E+OO 2.65E+OO Note: The average release rate is taken over the entire quarter, not over the time the time period of the leases. 89 2.5E+Ol Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 16 Gaseous Effluents

-Ground Level Releases -Batch Mode 1st Qtr 2nd Qtr 3rdQtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 Fission Gases Kr-85 Ci <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD

<LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD

<LLD Xe-135 Ci <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD Xe-138 , Ci <LLD <LLD <LLD <LLD Total for Period: NIA NIA NIA NIA

\ Iodines I-131 Ci <LLD <LLD <LLD <LLD I-133 Ci <LLD <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD <LLD Total for Period: NIA NIA NIA NIA Particulates and Tritium H-3 Ci <LLD <LLD <LLD

<LLD Sr-89 Ci <LLD <LLD <LLD

<LLD Sr-90 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD

<LLD Cs-137 Ci <LLD <LLD <LLD <LLD Ba-La-140 Ci <LLD <LLD <LLD <LLD Total for Period: O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 90 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 16 (Continued)

Gaseous Effluents

-Ground Level Releases Continuous Mode 1st Qtr 2nd Qtr 3rdQtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 Fission Gases Kr-85 Ci <LLD <LLD <LLD

<LLD Kr-85m Ci <LLD <LLD <LLD

<LLD -Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD

<LLD Xe-133 Ci <LLD <LLD <LLD

<LLD Xe-135 Ci <LLD <LLD <LLD

<LLD Xe-135m Ci <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD Total for Period: NIA NIA NIA NIA Iodines I-131 Ci <LLD <LLD <LLD

<LLD I-133 Ci <LLD <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD

<LLD Total for Period: NIA NIA NIA NIA Particulates and Tritium H-3 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD

<LLD Cs-134 Ci <LLD <LLD <LLD

<LLD Cs-137 Ci <LLD <LLD <LLD <LLD Ba-La-140 Ci <LLD <LLD <LLD <LLD Total for Period: NIA NIA NIA NIA 91 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 16 (Continued)

Gaseous Effluents

-Ground Level Releases LLDs for Continuousb and Batcha Mode Ar-41 <5.lOE-09

µCi/ml Kr-85 <l.63E-06

µCi/ml Kr-85m <6.74E-09

µCi/ml Kr-87 <2.48E-08

µCi/ml Kr-88 <2.66E-08

µCi/ml Xe-133 <l.51E-08

µCi/ml

• Xe-133m <4.52E-08

µCi/ml Xe-135 <6.65E-09

µCi/ml Xe-135m <2.13E-07

µCi/ml Xe-138 <6.59E-07

µCi/ml I-131 <7.20E-15

µCi/ml I-133 <9.56E-15

µCi/ml I-135 <6.25E-14

µCi/ml Cs-134 <8.32E-15

µCi/ml Cs-137 <9.92E-15

µCi/ml Ba-140 <2.48E-14.

µCi/ml La-140 <7.lOE-15

µCi/ml Sr-89 <l.40E-15

µCi/ml Sr-90 <4.90E-16

µCi/ml Mn-54 <l.32E-14

µCi/ml Fe-59 <2.16E-14

µCi/ml Co-58 <l.69E-14

µCi/ml Co-60 <l.69E-14

µCi/ml Zn-65 <2.44E-14

µCi/ml Mo-99 <l.OOE-13

µCi/ml Ce-141 <1.17E-14

µCi/ml a Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, and Auxiliary Boiler Outage Release are listed as batch release. b Atmospheric Vent Valve weepage and Steam Packing Exhauster are continuous releases.

92 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 17 Gaseous Effluents

-Mixed Mode Releases Batch Mode Nuclide Unit Fission Gases Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci Total for*Period:

• Iodines I-131 Ci I-133 Ci I-135 Ci Total for Period: Ci *Particulates

& Tritium H-3 Ci Sr-89 Ci Sr-90 Ci Cs-134 Ci Cs-137 Ci Ba-La-140 Ci Total for Period: Ci

• Release of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Station Vent) 93 1st Qtr 2nd Qtr 2015 2015 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD O.OOE+OO O.OOE+OO <LLD <LLD <LLD <LLD

<LLD <LLD O.OOE+OO O.OOE+OO <LLD 4.45E-04 <LLD <LLD <LLD <LLD

<LLD <LLD <LLD <LLD

<LLD <LLD <LLD 4.45E-04 3rdQtr 2015 3.03E-01 <LLD <LLD <LLD <LLD <LLD 4.02E-02 <LLD 2.63E-03 <LLD <LLD 3.46E-01 <LLD <LLD <LLD O.OOE+OO l.37E+OO <LLD <LLD <LLD <LLD

<LLD l.37E+OO 4th Qtr 2015 <LLD <LLD <LLD <LLD <LLD <LLD 7.48E-05 <LLD

<LLD <LLD <LLD 7.48E-05 <LLD <LLD <LLD 0.00E+OO 5.98E-04 <LLD <LLD <LLD <LLD <LLD 5.98E-04 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 17 (Continued)

Gaseous Effluents

-Mixed Mode Releases -Continuous Mode 1st Qtr 2ndQtr 3rdQtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 Fission Gases Kr-85 Ci <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD

<LLD Xe-133m Ci <LLD <LLD <LLD

<LLD Xe-135 Ci <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD

<LLD Xe-138 Ci <LLD <LLD

<LLD <LLD Total for Period: 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO Iodines I-131 Ci <LLD <LLD <LLD

<LLD I-132 Ci <LLD <LLD <LLD <LLD I-133 Ci <LLD <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD

<LLD Total for Period:* O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO Particulates, Tritium Co-58 Ci <LLD <LLD <LLD

<LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD

<LLD <LLD Ba-La-140 Ci <LLD <LLD <LLD <LLD H-3 Ci 2.04E+Ol 1.44E+Ol l.09E+Ol l.17E+Ol Total for Period 2.04E+Ol 1.44E+Ol l.09E+Ol l.17E+Ol Carbon-14 Ci 2.65E+OO 2.65E+OO 2.65E+OO 2.65E+OO 94 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 17 (Continued)

LLDs for Gaseous Effluents

-Mixed Mode Releases Continuous Mode 3 BatchModea Kr-85 <l.63E-06

µCi/ml Ar-41 <1.38E-06 Kr-85m <6.74E-09

µCi/ml Kr-85m <9.40E-07 Kr-87 <2.48E-08

µCi/ml Kr-87 <2.lOE-06 Kr-88 <2.66E-08

µCi/ml Kr-88 <3.35E-06 Xe-133 <l.51E-08

µCi/ml Xe-133 <1.52E-06 Xe-133m <4.52E-08

µCi/ml Xe-133m <6.85E-06 Xe-135 <6.65E-09

µCi/ml Xe-135 <7.76E-07 Xe-135m <2.13E-07

µCi/ml Xe-135m <l.29E-05 Xe-138 <6.59E-07

µCi/ml Xe-138 <3.98E-05 I-131 <7.20E-15

µCi/ml I-131 <7.18E-07 I-133 <9.57E-15

µCi/ml I-133 <8.44E-07 I-135 <6.25E-14

µCi/ml I-135 <3.40E-06 Cs-134 <8.32E-15

µCi/ml Sr-89 <1.40E-15 Cs-137 <9.92E-15

µCi/ml Sr-90 <4.90E-16 Ba-140 <2.48E-14

µCi/ml Cs-134 <9.71E-07 La-140 <7.lOE-15

µCi/ml Cs-137 <8.60E-07 Sr-89 <1.40E-15

µCi/ml Ba-140 <2.85E-06 Sr-90 <4.90B-16 uCi/ml La-140 <L87E-06 Mn-54 <l.32E-14

µCi/ml Fe-59 <2.16E-14

µCi/ml Co-58 <l.69E-14

µCi/ml Co-60 <l.69E-14

µCi/ml Zn-65 <2.44E-14

µCi/ml Mo-99 <l.OOE-13

µCi/ml Ce-141 <1.17E-14

µCi/ml a These radionuclides were not identified in every quarter in concentrations above the lower limit of detection (LLD). 95 µCi/ml µCi/ml µCi/ml µCi/ml uCi/ml µCi/ml µCi/ml , µCi/ml µCi/ml µCi/ml µCi/ml µCi/ml . µCi/ml µCi/ml µCi/ml µCi/ml µCi/ml uCi/ml Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 18 Liquid Effluents

-Summation of All Releases Type Unit Fission and Activation Products Total Release (without Tritium, Ci Gases, Alpha) Average Diluted Concentration

µCi/ml During Period" 1st Qtr 2015 6.71E-05 5.63E-12 2nd Qtr 3rd Qtr 2015 2015 6.64E-04 4.42E-03 5.63E-11 3.74E-10 4th Qtr 2015 6.59E-04 9.69E-11 Est. Total % Error 2.0E+Ol Percent of ODCM Limits % See Supplemental information in ODCM Section 2.3, Re-lease Limits Percent of 1 Limit % 3.70E-05 7.69E-04 l.95E-03 9.20E-04 Tritium Total Release Ci 7.63E+Ol 2.51E+02 l.82E+02 3.10E+02 2.0E+Ol Average Diluted Concentration

µCi/ml 6.40E-06 2.13E-05 l.54E-05 2.58E-05 During Period" Percent of 10CFR20 Limit % 6.40E-01 2.13E+OO l.54E+OO 2.58E+OO Dissolved and Entrained Gases Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.61E-05 2.0E+Ol Average Diluted Concentration

µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO 7.17E-12 During Period" Percent of 1 OCFR20 Limit % O.OOE+OO O.OOE+OO O.OOE+OO 3.59E-06 Gross Alpha Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.0E+Ol Volume of Waste Released (prior to dilution)

Batch liter l.80E+05 4.69E+05 4.11E+05 6.30E+05 2.0E+Ol Continuous liter 5.62E+07 l.44E+08 8.16E+07 l.33E+08 2.0E+Ol Volume of Dilution Water Batch liter 1.07E+08 3.00E+08 2.15E+08 3.63E+08 2.0E+Ol Continuous liter l.18E+10 l.13E+10 l.15E+10 l.15E+10 2.0E+Ol Total Volume of Water Released liter l.19E+10 l.18E+10 l.18E+10 l.20E+10 *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 quartec Fission and Activation products and Dissolved and Entrained Gases are mally only detected in batch releases.

96 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 19 Liquid Effluents

-Nuclides Released in Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 Fission and Activation Products Na-24 Ci <LLD <LLD l.06E-06 <LLD Mn-54 Ci <LLD <LLD l.18E-04 6.41E-06 Fe-55b Ci <LLD <LLD l.73E-03 <LLD Co-57 Ci <LLD <LLD 7.59E-06 9.66E-07 Co-58 Ci 4.70E-06 4.64E-05 2.08E-04 4.62E-04 Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci l.71E-06 4.05E-05 2.63E-04 7.99E-05 Ni-63 Ci 4J4E-05 3.19E-04 l.93E-03 <LLD Zn-65 Ci <LLD <LLD <LLD <LLD Se-75 Ci <LLD <LLD <LLD , <LLD Br-82 Ci <LLD <LLD <LLD <LLD Sr-89b Ci <LLD <LLD <LLD <LLD Sr-90b Ci <LLD <LLD <LLD <LLD Sr-92 Ci <LLD <LLD <LLD <LLD* Nb-95 Ci <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD l.06E-06 Zr-97 Ci <LLD <LLD <LLD <LLD Mo-99 , Ci <LLD <LLD <LLD

<LLD Tc-99m Ci <LLD <LLD <LLD <LLD Ru-103 Ci <LLD <LLD <LLD <LLD Ru-105 Ci <LLD <LLD <LLD <LLD Ru-106 Ci <LLD <LLD <LLD <LLD Ag-llOm Ci l.61E-05 l.94E-04 7.36E-05 2.64E-05 Sb-122 Ci <LLD <LLD <LLD <LLD Sb-124 Ci <LLD 2.25E-05 7.37E-06 3.67E-05 Sb-125 Ci 2.69E-06 6.22E-06 2.82E-06 <LLD 1-131 Ci <LLD <LLD <LLD <LLD 1-132 Ci <LLD <LLD <LLD <LLD Te-132 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD l.71E-06 4.48E-06 3.09E-06 Cs-137 Ci 4.26E-07 3.41E-05 7.38E-05 4.23E-05 Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD Total for Period: Ci 6.71E-05 6.64E-04 4.42E-03 6.59E-04 97 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 19 (continued)

Liquid Effluents

-Nuclides Released In Batch Releases lstQtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2015 2015 2015 2015 H-3 Ci 7.62E+Ol 2.51E+02 l.82E+02 3.10E+02 Dissolved and Entrained Gases Kr-85 Ci <LLD <LLD <LLD

<LLD Xe-131m Ci <LLD <LLD <LLD-<LLD Xe-133 Ci <LLD <LLD <LLD 8.61E-05 Xe-133m Ci <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD Total for Period: Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.61E-05 98 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 19 (continued)

Liquid Effluents

-Nuclidesa Released Nuclide Fission and Activation Products Cr-51 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr-89b S'r-90b Nb-95 Zr-95 Mo-99 Tc-99m 1-131 Cs-134 Cs-137 Ba/La-140 Ce-141 Total for Period: Tritium Dissolved and Entrained Gases Xe-133 Xe-135 Total for Period: In Continuous Relec;ises Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 99 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr 2015 2015 2015 2015 <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 <LLD <LLD <LLD <LLD <LLD <LLD

<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO l.65E-01 2.86E-01 3.63E-02 6.00E-02 <LLD <LLD <LLD

<LLD <LLD <LLD <LLD

<LLD O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 19 (continued)

Liquid Effluents

-LLDs for Nuclides Released a Cr-51 <9.00E-08

µCi/ml Ar-41 <4.27E-09

µCi/ml Mn-54 <5.95E-09

µCi/ml I-131 <8.67E-09

µCi/ml Fe-55b <7.lOE-07

µCi/ml Xe-131m <4.27E-07

µCi/ml Co-57 <8.99E-09

µCi/ml Xe-133 <2.53E-08

µCi/ml Co-58 <7.06E-09

µCi/ml Xe-133m <8.30E-08

µCi/ml Fe-59 <2.22E-08

µCi/ml Cs-134 <8.27E-09

µCi/ml Co-60 <9.13E-09

µCi/ml Xe-135 <9.00E-09

µCi/ml Zn-65 <2.50E-08

µCi/ml Cs-137 <9.76E-09

µCi/ml Kr-85 <2.24E-06

µCi/ml Ba-140 <3.24E-08

µCi/ml Sr-89b <2.40E-08

µCi/ml La-140 <1.13E-08

µCi/ml Sr-90b <7.40E-09

µCi/ml Ce-141 <1.67E-08

µCi/ml Sr-92 <1.58E-08

µCi/ml Ce-144 <7.30E-08

µCi/ml Zr-95 <9.83E-09

µCi/ml Zr-97 <8.67E-09

µCi/ml Tc-99m <9.25E-09

µCi/ml Mo-99 <7.51E-08

µCi/ml Ru-103 <9.35E-09

µCi/ml Ru-106 <1.02E-07

µCi/ml Ag-llOm <1.03E-08

µCi/ml Sb-124 <7.97E-09

µCi/ml Sb-125 <3.32E-08

µCi/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 dueto identical sample and analysis methods. b Quarterly composite sample 100 \

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 20 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, m3 2.05E+Ol 2.5E+Ol evaporator bottoms, etc. Ci 5.15E+02 2.5E+Ol b. Dry compressible waste, m3 2.93E+02 2.5E+Ol contaminated equip., etc. Ci 2.96E+OO 2.5E+Ol c. Irradiated components, m3 NIA NIA control rods, etc. Ci d. Filters m3 4.56E-01 2.5E+Ol Ci 1.48E+OO 2.5E+Ol e. Others: Spent Resin Storage m3 2.29E+Ol 2.5E+Ol Tanlc Liquor Ci 8.94E+OO 2.5E+Ol 2. Estimate of major nuclide composition (by type of waste) Percent(%}

Est. Error, % a. Spent Resins Cs 137 3.98E+Ol 2.50E+Ol Ni63 3.59E+Ol 2.50E+Ol cs134 9.22E+OO 2.50E+Ol Co6o 6.75E+OO 2.50E+Ol Fess 4.28E+OO 2.50E+Ol Coss l.92E+OO 2.50E+Ol c14 l.56E+OO 2.50E+Ol Nis9 2.33E-01 2.50E+Ol H3 2.27E-01 2.50E+Ol b. Dry compressible waste, contaminated Cs 137 2.72E+Ol 2.50E+Ol equipment, etc. Ni63 2.25E+Ol 2.50E+Ol Fess l.25E+Ol 2.50E+Ol Ag11om l.04E+Ol 2.50E+Ol Co6o 8.20E+OO 2.50E+Ol Cs134 7.92E+OO 2.50E+Ol Coss 5.37E+OO 2.50E+Ol H3 2.89E+OO 2.50E+Ol c14 2.04E+OO 2.50E+Ol Mns4 3.34E-01 2.50E+Ol ce144 2.72E-01 2.50E+Ol Tc99 l.07E-01 2.50E+Ol c. None 101 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report d. Filters e. Others: Spent Resin Storage Tank Liquor 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 Coss Co6o Ni63 Fess c14 Aguom zr95 Cs 137 H3 Ni63 Coss cs131 Co6o Ag110m Fess Cl4 Nis9 16 Truck 6.46E+Ol l.35E+Ol 8.25E+OO 7.07E+OO 3.88E+OO l.35E+OO l.14E+OO l.20E-01 5.66E+Ol l.58E+Ol 1.47E+Ol 5.15E+OO 3.0lE+OO 2.18E+OO l.73E+OO 7.31E-01 l.OlE-01 Energy Solutions, Oak Ridge, TN 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol for processing and disposal at Energy Solutions, Clive UT Metal boxes (assorted sizes, 1.4-35.4 m 3) 320m 3 7 Truck Energy Solutions, Oak Ridge, TN for processing and disposal at WCS, Andrew TX Poly HIC 3.40 m 3 16.8 m 3

• 1 Truck Energy Solutions, Barnwell, SC for processing and disposal at WCS, Andrew TX Poly HIC 1.16 m 3 0.21 m 3 102 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report B. IRRADIATED FUEL SHIPMENTS There were no shipments of irradiated fuel. Onsite Groundwater Monitoring Davis-Besse began sampling wells near the plant in 2007 as part of an industry-wide Groundwater Protection Initiative (GPI), which was established to ensure that there are no inadvertent releases of radioactivity from the plant which could affect offsite groundwater supplies.

In addition to several existing pre-construction era wells, sixteen new GPI monitoring 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. In January, seven out of ten wells indicated tritium concentrations of greater than 2,000 pCi/L requiring courtesy notifications to local, county, and state officials.

Increased sampling frequency on selected wells was implemented in an attempt to identify the source of the groundwater contamination.

A Problem Solving and Decision Making Team (PSDM) was also formed. Based on the completion of detailed Failure Mode Analyses, the potential pathways have been evaluated and refuted through inspection.

The conclusion of the PSDM Team was that the most probable cause was due to construction activities surrounding the removal of the Primary Water Storage Tank. Since the initial identification of elevated concentrations, well sampling results have indicated an overall decreasing trend over the year, indicating that the cause is intermittent and no longer active. The area of highest concentrations, the concentration has decreased from 10,527 pCi/L in February to 2866 pCi/L in December 2015, with the highest concentration detected in the western wells within the Protected Area. The assumptions regarding groundwater flow and modeling remain valid that the flow does not impact areas outside the Owner Controlled Area and essentially discharges into the Intake Canal. There is no evidence that the tritium traveled offsite or contributed to offsite dose. Additionally, the groundwater tritium sample results remain below the 30,000 pCi/l EPA limit described in the Besse Offsite Dose Calculation Manual for non-drinking water sources. Table 21 contains the Davis-Besse GPI monitoring well sample results for tritium for 2015. 103 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 21. 2015 Groundwater Tritium Results Year 2015 January February March April May June August September October December Well No. [H*3], [H*3], [H*3], [H-3], [H*3], [H*3], [H*3], [H-3], pCi/I [H-3], [H-3], pCi/I . pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I MW-100A 192 <185 850 1742 1146 MW-1008 <185 405 MW-100C <185 <150 MW-101A 302 <150 MW-1018 <183 296 281 MW-101C <147 <150 MW-102A <185 <150 MW-1028 417 2114 1411 1080 MW-102C <185 <150 MW-103A 538 283 MW-1038 311 229 287 MW-103C <185 <150 MW-104A <147 <150 MW-1048 <185 531 MW-104C <185 <150 MW-105A 2578 2648 3085 2798 2876 2588 2625 2566 2026 MW-128 5202 8899 8388 7695 7410 4793 4122

' 3989 MW-148 4736 5485 5850 5825 6166 5952 MW-158 997 1372 1756 1973 2298 2377 MW-188 356 258 386 474 MW-198 953 708 2533 1340 5608 3670 MW-208 7492 8688 7658 6584 6981 6488 6246 3429 3836 3736 MW-218 7938 8608 6141 5739 5332 4773 2509 2856 2866 MW-228 10527 9552 * * * * * *

• MW-238 2563 3792 3225 5259 4642 3726 MW-308 3248 2406 3237 2508 5109 4533 3847 3411 3450 MW-318 6726 6186 7394 6013 6464 4524 MW-328 4512 3777 7124 6617 6427 4222 MW-338 1961 4993 891 4803 5556 5535 MW-348 2379 2917 4716 4621 4951 5106 4651 4591 4462 MW-378 3597 4052 4408 3909 4011 3713 3448 3083 2904 MW-398 2563 552 4808 483 842 999 April and September are the Spring and Fall campaigns; all other results are trending data. Seven *wells remained >2000 pCi/L in 2015. *MW-22S was removed for construction.

MW-20S,MW-21S, and MW23S are in the vicinity and provide adequate groundwater monitoring information.

104 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report ;J 10000 *5 <.J 0 -a. 1000 F i g u re 30 -Onsite Groundwater Monitoring Davis Besse O nsit e Grou n d wat er M on it or i ng P r o gram H-3 Tr e nd s <200 p C i/L"' T ypica l L L D 348 pCi/L = Pre-O perationa l Mean 2 , 000 pC i/L = NR C Req uired L L D Pre Uperat o ral Mean H 2 (HW p<..: 1.L) 2 , 000 p C i/L = FEN O C/NEI C om m u n ication La v el 20,00 0 pCi/L = E PA Reporting Leve l ____ __..._..._

___ .....;._-"-------'

--Nl<C Hequ u ed LLUH 3

>U I LJ Summary of Onsite Spills(> 100 gallons) and Notifications There were no identified onsite spills during 2015. Throughout 2015 , the State , County , and local officals were kept updated on the groundwater monitoring sample results >2 , 000 pCi/L and the Besse problem solving plans/progress.There were s e v en remaining groundwater well s with elevated tritium results where notifications

/updates to State , County and local officials were being made at the end of 2015. Summary of Items Added to Decommissioning Files per 10 CFR 50.75(g) The elevated tritium level described above wa s added to Decommi ss ioning File s per 10 CPR 50.75(g). 105 Davis-Besse Nuclear Power Station 2015 Annual RadiologiCal Environmental Operating Report Table 22 Doses Due to Gaseous Releases for January through December 2015 Maximum Individual Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days. Whole Body Dose 3 .15E-02 mrem Significant Organ Dose (liver) 3.15E-02 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 5.04E-04 mrem Skin Dose 7.40E-04 mrad Maximum Individual Dose Due to C-14 Whole Body Dose 5.35E-02 mrem Significant Organ Dose (bone) 2.68E-01 mrem Population Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days. Total Integrated Population Dose l .53E-02 person-rem Average Dose to Individual in Population 7.0lE-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 7.69E-05 person-rem Average Dose to Individual in Population 3.52E-08 mrem Population Dose Due to C-14 Total Integrated Population Dose 8.09E-02 person-rem Average Dose to Individual in Population 3.70E-05 mrem 106 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 23 Doses Due to Liquid Releases for January through December 2015 Maximum Individual Whole Body Dose Maximum Individual Significant Organ Dose (LIVER) Population Dose Total Integrated Population Dose Average Dose to Individual 5.08E-04 mrem 6.23E-04 mrem 7.31E-01 person-rem 3.35E-04 mrem Table 24 Annual Dose to The Most Exposed (from all pathways)

Member of the Public 2015 ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem) (mrem) LIMIT Whole Body Dose* Noble Gas 5.04E-04 Iodine, Tritium, Particulates 3.15E-02 C-14 2.61E-01 Liquid 4.86E-03 Total Whole Body Dose 3.68E-02 25 l.47E-01 Thyroid Dose Iodine, Tritium, Particulates 3.53E-02 75 4.71E-02 Skin Dose Noble Gas 7.40E-04 25 2.96E-03 Significant Organ Dose 3.69E-02 25 1.48E-Ol (LIVER) Significant Organ Dose (C-14) 1.263 25 5.05E+OO (bone) Meteorological Data Meteorological data, stored on a compact disk for January 1 through December 31, 2015, 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.

107 Davis-Besse Nuclear Power Station 2015 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 sary to estimate radiation dose to the. general public and to determine if ar;tY modifications are necessary to the Radiological Environmental Monitoring Program (REMP). The Land Use Census is required by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis-Besse Nuclear Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use sus Data. The Land Use Census identifies gaseous pathways by which radioactive material may reach the general population around Davis-Besse.

The information gathered during the Land Use Census for dose assessment and input into the REMP ensure these programs are as current as possible.

The pathways of concern are listed below:

• Inhalation Pathway -Internal exposure as a result of breathing radionuclides carried in the air.

• Ground Exposure Pathway -External exp,osure 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 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 meteorological sector within a five mile radius of Davis-Besse.

The surveillance portion of the 2015 Land Use Census was performed during the months of July and August. 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 bage). Each residence is tabulated as being an inhalation pathway, as well as ground and plume exposure pathways.

Each garden is tabulated as a vegetation pathway. All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7 .5 nute series of the relevant quadrangles) which has been divided into 16 equal sectors corresponding 108 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report to the 16 cardinal compass points (Figure 31 ). If available, the closest residence, milk animal, and vegetable garden in each sector are determined by measuring the distance from each to the Station Vent at Davis-Besse.

Results l The following changes in the pathways were recorded in the 2015 census: S sector: A new garden was located at 3 .10 miles distance from the plant. SW sector: A new garden was located at 0.70 miles distance from the plant. WNW sector: A new garden was located at 2.32 miles distance from the plant. The critical receptor is a garden in the SW sector at 0.70 miles from Davis-Besse, which is a change from 2014. The detailed list in Table 25 was used to update the database of the effluent dispersion model used '\ in dose Table 25 is divided by sectors and lists the distance (in miles) of the closest pathway in each. Table 26 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and _deposition (D/Q) parameters for *?ach 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 lating liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints.

109

.,, <Cl c -, CD "" r 0 :J 0. 0 c (/) CD (") CD :J (/) c (/) 3: 0 " DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM WNW ... . .. **:* ... c:i Cl: w ... WSW SW s*. BIE R -..RD,: CLOSEST SITES To Da v Is-Be ss e With in Se ctor" 1111 RESIDENCE 1111 VEGETABLE GARDEN PRI MARY PATHWA YS WITHI N A 5 MIL E RADI US RD. c:i .. ******: w c:i c:i c:i Cl: Cl: Cl: C AMP PE R R Y-D w". ::i: a:. c:i I-w*. Cl: ii ::::i 0 * ** RD. "' z Cl: I-<( .. 'j'; z c:i ::::i .<( Cl: ******* ...J w .31: w ::i: "' w ...J .,_ ::::i I-CD : <( 0 <( I-"' 0 Cl: CD SSW SE OB: 0'-02-1 6 O F N*F:/SCH EO/SKZ 816.0 GN 0 :J N 0 U1 )> :J :J c 0 ::0 0 0. 0 0 '° 0 0 fT'I :J < -, 0 :J :J ... 0 0 " CD -, 0 ... :J '° ::0 CD " 0 -, ...

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report N NNE NE ENE,E,ESE SE SSE SSE *S s SSW SSW SW *changed from 2014 Table 25 Closest Exposure Pathways Present in 2015 Distance from Station (miles) 0.55 0.55 0.56 NIA 4.94 1.82 0.93 3.10 0.68 3.5 0.61 0.67 111 Closest Pathways Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Located over Lake Erie Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure *Plume Exposure ./

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report *SW WSW WSW w w WNW *WNW NW NW NNW

• changed from 2014 Table 25 (Continued)

Closest Exposure Pathways Present in 2015 Distance from Station (miles) 0.70 0.96 4.0 0.61 0.97 0.94 .\ 2.32 1.94 0.93 0.80 112 ClOsest Pathways Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Vegetation Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 26 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters SECTOR MILES CRITICAL AGE X/Q D/Q PATHWAY GROUP (SEC/M 3) (M-2) N 0.55 Inhalation Child 3.23E-06 l.21E-08 NNE 0.55 Inhalation Child 4.06E-06 2.12E-08 . NE 0.56 Inhalation Child 3.13E-06 . 2.27E-08 *ENE *E .._ __ *ESE SE 4.94 Inhalation Child l.90E-08 l.83E-10 SSE 1.82 Vegetation Child 7.52E-08 8.30E-10 **S 3.10 Vegetation Child 2.84E-08 2.55E-10 SSW 3.5 Vegetation Child 2.74E-08 2.35E-10 **SW 0.7 Vegetation Child 4.56E-07 1.57E-08 WSW 4.0 Vegetation Child. 4.33E.;08 3.47E-10 w 0.97 Vegetation Child 6.05E-07 5.13E-09 **WNW 2.32 Vegetation Child 1.40E-07 6.56E-10 NW 1.94 Vegetation Child l.84E-07 6.74E-10 NNW 0.80 Inhalation Child 9.54E-07 3.51E-09 *Since these sectors are located over marsh areas and Lake Erie, no ingestion pathways are present. **Changed from 2014 Land Use Census. 113 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Non-Radiological Environmental Programs Meteorological Monitoring 1 The Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nuclear power stations on the surrounding environment.

Both NRC regulations and the Davis-Besse nical 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 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 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 Emergency paredness Program, Site Chemistry, Plant Operations, Nuclear Security, Materials Management and Industrial Safety, as well as other plant personnel and members of the surrounding community.

The Radiological Environmental Monitoring Program uses meteorological data to aid in ing the radiological impact, if any, of radioactivity released in Station effluents.

The ical 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 late 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 lations, Forebay water level availability and plant work which needs certain environmental 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 ditions 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 unsafe 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 relation to the Plant and personnel.

1. More detailed weather information is available upon request. 114 Davis-Besse N1,1clear Power Station 2015 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 100 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Dew Point Precipitation Meteorological Instrumentation BACKUP 100 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Solar Incidence The meteorological system consists of one monitoring site located at an elevation of 577 feet above mean sea level (IGLD 1955)*. It contains a 100 meter (m) free-standing tower located about 3,000 feet SSW of the Cooling Tower and a lOm auxiliary tower located 100 feet west of the 100 m tower. Both are used to gather the meteorological data. The lOOm tower has primary and backup instruments for wind speed and wind direction at lOOm and 75m. The lOOm tower also measures differential temperature (delta Ts): 100-lOm and 75-lOm. The lOm tower has instruments for wind speed and wind direction.

Precipitation is measured by a tipping bucket rain gauge located near the base of the lOm tower. According to the Davis-Besse Nuclear Power Station Technical Requirements Manual, a minimum . of five instruments are required to be operable at the two lower levels (75m and lOm) to measure temperature, wind speed, and wind direction.

During 2015, average annual data recoveries for all required instruments were greater than 97 .69 percent. Minor losses of data occurred during routine instrument maintenance, calibration, and data validation.

Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly.

Data is reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required.

Tower instrumentation maintenance and semiannual calibrations are formed 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 115 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Meteorological Data Handling and Reduc.tion 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 system is designed the same as the primary; so to lose all meteorological data the primary and backup teorological 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 tion, 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 age 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 scrutinized 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 27-30, which summarize meteorological data collected from the site monitoring program in 2015. 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 relate to defined past climatological wind patterns reported in Davis-Besse's Updated Safety Analysis Report. The maximum measured sustained wind speed for 2015 occurred on June 27, when they were measured at 50.29 mph at the lOOm level, 47.83 mph on June 27 at the 75m level, and 32.59 mph on June 27 at the lOm level. Figures 32-34 give an annual sector graphic of average wind speed and percent frequency by 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 resents the average wind speed from that direction.

Wind direction sectors are classified using Pasquill Stabilities.

Percent calms (less than or equal to 1.0 mph) are shown in the middle of the wind sector graphic. 116 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2015 are given in Table 29. These data are measured at the 1 Om level; with differential temperatures taken from 1 OOm and 75m levels. The yearly average ambient temperature was 48.74°F. The maximum temperature was 89.07°F on September 07, 2015 with a minimum temperature of-8.57°F on ruary 20, 2015. Yearly average differential temperatures were -0.009°F (lOOm), and -0.272°F (75m). Maximum differential temperatures for 100 meter and 75m levels were 10.97°F on June 27, 2015. Minimum differential temperatures for lOOm and 75m levels were -21.94 °F on October 22, 2015 (lOOm) and-4.000 on May 31, 2015 (75m). 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 2015 are provided in Table 29. These data are measured at the 1 Om level. The average dew point temperature was

• 5.90°F with a maximum dew point temperature of 45.47°F on May 11, 2015. 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 -36.07°F on February 20, 2015. It is sible to have relative humidity above 100 percent, which is known as supersaturation.

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 2015 are given in Table 28. Total precipitation for the year was 30.89 inches. The maximum daily precipitation total was 2.91 inches on June 27, 2015. 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 the unlikely event of an unplanned 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 reaches higher temperatures than the temperature of 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 denser cold air descending over the lake. This starts a wind circulation which draws air from the water to the land during the daytime, creating a "Lake Breeze" effect. This event could be problematic if a release were to occur, because diffusion would be slow, thus creating an adverse atmosphere to the area surrounding the site. 117 Davis-Besse Nuclear Power Station 2015 Annual Radlological Environmental Operating Report Lake and Forebay levels are monitored at Davis-Besse to observe, evaluate, predict and nate high or low lake level information.

This data is critical to the operation 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 of 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 routes. 118 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 27 Summary of Meteorological Data Recovery For The Davis-Besse Nuclear Power Station January 1, 2015 through December 31, 2015 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2015 lOOm Wind Speed 96.37 95.98 100 96.11 100 100 100 100 99.72 96.91 100 100 98.55 1 OQM Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100 75M Wind Speed 96.37 95.98 100 96.11 97.31 100 100 100 99.72 100 100 100 98.81 75M Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100 1 OM Wind Speed 96.37 95.98 100 96.11 97.31 100 100 100 99.72 100 100 100 98.81 1 OM Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100 lOM Ambient Air Temp 96.37 95.98 100 96.11 97.31 100 99.87 100 99.72 100 100 100 98.80 lOM Dew Point Temp 96.37 95.98 100 96.11 97.31 99.58 99.87 100 99.72 100 100 100 98.77 Delta T (lOOM-lOM) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 100 100 100 97.69 Delta T (75M-10M) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 100 100 100 97.69 Joint lOOM Winds and Delta T (lOOM-lOM) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 96.91 100 100 97.43 Joint 75M Winds and Delta T (lOOM-lOM) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 100 100 100 97.69 Joint lOM Winds and Delta T (75M-10M) 96.37 95.98 100 96.11 97.31 100 86.83 100 99.72 100 100 100 97.69 *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 ment could be operable.

V aloes 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.

119 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 28 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1, 2015 through December 31, 2015 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2015 lOOMWIND Max Speed (mph) 35.66 38.74 33.65 41.57 39.17 50.29 26.85 32.50 35.74 41.37 44.28 47.98 50.29 Date of Max Speed 01/01 02/01 03/29 04/21 05/31 06/27 07/14 08/03 09/29 10/03 11112 12/28 06/27 Min Speed (mph) 2.37 1.86 2.37 1.97 2.63 1.99 2.14 1.82 3.02 2.05 1.66 2.00 1.66 Date of Min Speed 01130 02/16 03/20 . 04/29 05/10 06/20 07/27 08/09 09106 10/06 11108 12/12 11/08 Ave Wind Speed 17.64 16.21 15.70 17.08 15.50 15.54 12.04 12.63 14.70 18.57 18.48 18.05 16.13 75MWIND Max Speed (mph) 34.59 35.92 32.10 38.97 37.60 47.83 24.06 29.81 29.22 40.47 42.56 46.86 47.83 Date of Max Speed 01/01 02/01 03/25 04/21 05/31 06/27 07/14 08/03 09/29 10/03 11/12 12/28 06/27 Min Speed (mph) 2.28 1.57 2.39 1.56 2.21 2.17 2.09 2.23 3.01 2.00 2.16 2.00 1.56 Date of Min Speed 01/25 02/16 03/20 04/03 05/10 06/20 07/27 08/21 09/29 10/06 11/08 12115 04/03 Ave Wind Speed 16.20 14.90 14.29 15.64 14.01 14.45 11.13 11.67 13.08 17.10 16.89 16.35 14.75 lOMWIND Max Speed (mph) 26.97 24.56 23.68 29.68 25.65 32.59 19.73 22.51 24.68 25.05 31.61 26.87 32.59 Date of Max Speed 01101 02/02 03/25 04/21 05/31 06/27 07115 08/03 09/29 10/29 11/12 12/28 06/27 Min Speed (mph) 1.27 1.43 0.92 0.81 0.96 1.04 .1.07 1.01 0.77 1.21 1.24 1.09 0.77 Date of Min Speed 01/26 02/16 03/23 04/29 05/14 06/03 07/26 08/31 09/24 10/25 11104 12/22 09/24 Ave Wind Speed 10.79 9.17 8.59 9.86 8.26 9.05 ,' 6.68 6.75 7.37 10.03 9.70 9.57 8.95 120 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 28 (continued)

Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station

• January 1, 2015 through December 31, 2015 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2015 lOM AMBIENT TEMP Max (F) 43.72 43.98 60.24 74.47 87.43 85.85 88.30 88.20 89.07 79.03 73.90 66.48 89.07 --Date of Max 01/17 02/08 03/16 04/13 05/08 06/10 07/29 08/02 09/07 10/12 11104 12/12 09/07 Min (F) -3.84 -8.57 4.16 29.96 42.94 49.53 59.76 56.56 49.36 33.37 21.91 23.32 DateofMin 01108 02/20 03/06 04/04 05/20 06/01 07/16 08/28 09/13 10/17 11/23 12/20 02120 Ave Temp 21.94 14.77 33.02 47.95 63.46 68.36 72.13 71.10 69.15 55.55 47.71 42.04 48.74 lOM DEW POINT TEMP *Mean (F) -13.34 -18.44

-5.35 8.70 16.50 21.76 23.89 23.44 22.13 11.45 5.77 3.06 6.88 Max (F) 4.64 2.97 12.81 16.62 45.47 32.01 34.41 33.17 35.45 26.31 24.92 20.38 45.47 DateofMax 01/04 02/08 03/16 04/22 05/11 06/15 07/29 08/16 09/07 10/12 11/04 12112 05/11 Min (F) -37.66 -36.07 -26.42 -10.03 -10.99 8.51 15.03 14.12 7.96 -4.91 -11.88 -12.18 -36.07 Date of Min 01/08 02/20 03/06 04/04 05/12 06/01 07/04 08/26 09/13 10/17 11/23 12120 02/20 PRECIPITATION Total (inches) 2.04 1.17 0.93 2.53 2.04 6.56* 3.19 2.90 3.61 1.91 1.59 2.42 30.89* Max in One Day 1.05 0.37 0.34 1.17 1.05 2.91 1.86 0.88 1.21 1.04 0.54 0.92 2.91 Date 01103 02/04 03/26 04/09 05/03 06/27 07/09 08/03 09/03 10/28 11118 12128 06/27 *Note: Rain Data missing for period of 6-11-15 thru 6-17-15 due to clogged Rain Gauge (CR 2015-08348).

NOAA data showed 0.17" on 6-12-15, 0.23" on 6-13-15, 1.01" on 6-15-15 and 0.30" on 6-16-15. 121 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Ope rating Rep ort Figure 32 Wind Rose Annual Average lOOM txX>OQOOOj W I ND s::iEED ( PH) DIRECT ON ft) DAVIS-BESS ANNUAL 2015 100M LEVEL 122 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average 75M t2229@000!

WI r: SPE E.O (MPH: ---e DIRECTJO N FR EOu-CY '"' DAVIS-BESSE ANNUA L 2015 75M LEVEL 123 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Figure 34 Wind Rose Annual Average 1 OM IX)OOOOOOOOl w:NO SPEED (MPH) ---*DIRECTION rRCClUC"4CY (X) DAVIS-BESSE ANNUAL *2015 10M LEVEL 124 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 29 Joint Frequency Distribution by Stability Class STABILITY BASED ON: DELTA T WIND MEASURED AT: 35;0 FEET WIND THRESHOLD AT: 1.00 MPH * *** ANNUAL *** ST ABILITY CLASS A BETWEEN 250.0 AND 35.0 FEET JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 0 3.50 -7.49 24 7.50 -12.49 13 12.50 -18.49 0 18.50 -24.49 0 >24.49 2 TOTAL 39 0 11 1 3 4 0 19 0 5 0 7 4 17 0 2 27 10 5 3 47 STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH 4 10 2 0 0 17 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 2 12 5 0 0 0 18 STABILITY CLASS B BETWEEN 250.0 AND 35.0 FEET 0 18 7 4 0 0 29 0 14 30 11 1 0 56 0 6 20 13 0 0 39 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET 0 5 10 11 4 0 30 1 11 7 6 0 0 25 1 10 14 14 0 0 39 0 5 7 6 0 0 18 0 4 127 153 87 18 6 395 SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 0 3.50-7.49 4 7.50 -12.49 10 12.50 -18.49 6 18.50 -24.49 0 >24.49 0 TOTAL 20 17 4 0 0 0 22 0 5 5 0 12 0 6 52 9 3 0 70 0 14 2 0 0 17 0 0 0 0 2 DAVIS-BESSE ENVIRONMENTAL COMPLIANCE UNIT 0 2 0 0 0 0 2 125 0 0 4 8 1 0 1 0 0 0 0 5 10 0 19 12 2 0 0 33 17 24 16 3 0 61 1 6 14 8 5 4 38 0 3 8 1 0 0 12 3 10 0 0 15 5 19 3 0 0 28 0 7 11 2 0 0 20 0 5 108 186 52 12 4 367 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH * *** ANNUAL***

• • • ANNUAL *** STABILITY CLASS C BETWEEN 250.0 AND 35.0 FEET JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50-7.49 7.50 -12.49 12.50 -18.49 18.50 -24.49 >24.49 TOTAL 0 4 5 0 0 IO 0 IO 4 7 0 0 21 0 8 19 1 0 0 28 16 52 8 0 0 77 STABILITY BASED ON: DELTA T WIND MEASURED AT: WIND THRESHOLD AT: 35.0FEET 1.00MPH 1 9 23 3 0 0 36 0 8 2 0 0 0 IO 3 2 0 0 0 6 0 1 0 0 0 0 4 11 2 2 0 0 19 ST ABILITY CLASS D BETWEEN 250.0 AND 35.0 FEET 21 24 8 0 0 19 53 43 IO 2 54 128 0 7 28 20 12 8 75 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET 0 4 13 5 2 0 24 0 6 IO 6 0 0 22 0 8 13 12 0 0 33 0 6 17 6 0 0 29 0 9 141 267 121 24 11 573 SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 4 4 6 5 IO 3.50-7.49 33 51 67 112 151 7.50-12.49 54 81 148 193 161 12.50 -18.49 47 112 83 44 18 18.50 -24.49 11 25 31 32 4 >24.49 5 3 6 IO TOTAL 154 276 341' 396 345 5 86 28 0 0 0 119 9 40 14 5 0 0 68 126 11 46 26 9 0 0 92 20 8 16 75 98 101 67 158 221 10 62 225 0 1 57 0 0 13 172 327 633 6 11 67 35 203 IOO 194 67 80 19 11 0 561 232 6 20 50 34 6 0 116 3 31 57 81 21 0 193 8 31 60 42 7 0 148 0 132 I044 1621 1033 294 49 4173 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH *** ANNUAL *** STABILITY CLASS E BETWEEN 250.0 AND 35.0 FEET JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50-7.49 7.50 -12.49 12.50 -18.49 18.50 -24.49 >24.49 TOTAL 7 6 7 12 1 34 5 16 15 3 0 40 3 14 18 6 0 0 41 2 56 32 4 1 0 95 STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH 28 113 35 8 0 0 184 21 98 17 2 0 0 138 46 53 76 53 23 28 13 0 0 0 0 146 147 70 32 24 154 261 152 .68 138 167 22 62 76 0 0 7 0 0 314 493 427 ST ABILITY CLASS F BETWEEN 250.0 AND 35.0 FEET 13 89 112 21 4 0 239 5 47 64 5 0 0 121 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET 7 27 31 7 2 0 74 9 18 29 7 1 0 64 9 20 19 8 0 0 56 334 1200 803 257 17 2 2614 SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50 -7.49 7.50 -12.49 12.50 -18.49 18.50 -24.49 >24.49 TOTAL 3 0 1 0 0 0 4 2 2 0 0 0 5 0 2 2 2 0 0 6 5 11 2 0 0 0 18 5 17 5 0 0 0 27 7 36 3 0 0 0 46 18 25 0 0 0 0 43 127 63 78 74 29 67 148 0 1 4 0 0 0 0 0 0 0 0 0 92 146 226 31 50 12 0 0 0 93 20 33 4 0 0 0 57 9 35 7 0 0 0 51 7 8 3 0 0 0 18 4 3 5 0 0 0 12 4 1 0 0 0 6 3 330 467 51 2 0 0 853 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report STABILITY BASED ON: DELTA T WIND MEASURED AT: 35.0 FEET WIND THRESHOLD AT: 1.00 MPH *** ANNUAL *** ST ABILITY CLASS G BETWEEN 250.0 AND 35.0 FEET JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50 -7.49 7.50-12.49 12.50 -18.49 18.50 -24.49 >24.49 TOTAL 0 0 0 0 0 0 0 0 2 0 0 0 0 2 0 0 0 0 0 0 0 1 8 1 0 0 0 10 STABILITY BASED ON: DELTA T WIND MEASURED AT: WIND THRESHOLD AT: 35.0FEET l.OOMPH 6 11 0 0 0 0 17 6 21 0 0 0 0 27 7 9 0 0 0 0 16 18 7 0 0 0 0 25 36 31 0 0 0 0 67 ST ABILITY CLASS ALL BETWEEN 250.0 AND 35.0 FEET 52 44 0 0 0 0 96 17 22 0 0 0 0 39 5 3 0 0 0 0 8 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET v 8 3 0 0 0 0 11 3 0 0 0 0 4 0 3 0 0 0 0 3 2 0 0 0 0 0 2 0 159 167 1 0 0 0 327 SPEED (MPH) N NNE NE ENE E ESE SE SSE s SSW SW WSW W WNW NW NNW TOTAL CALM 1.01 -3.49 3.50 -7.49 7.50-12.49 12.50-18.49 18.50 -24.49 >24.49 TOTAL 14 71 90 65 12 9 261 12 109 106 125 30 3 385 9 101 192 100 36 7 445 14 211 359 75 41 13 713 51 306 248 33 4 1 643 39 250 51 2 0 0 342 81 155 39 6 0 0 281 128 145' 209 140 358 57 144 22 35 0 0 0 0 364 746 167 90 609 375 343 507 138 37] 1 78 0 16 1258 1437 45 211 381 256 101 23 1017 33 132 202 89 25 0 481 23 78 111 54 8 0 274 18 78 137 117 22 0 372 23 70 115 64 7 0 279 4 973 3254 3082 1552 365 72 9302 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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.

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 control and beach formation.

Revetments are built with a gradual slope, which causes waves to dissipate 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 water 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 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 importance 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 before continuing their migration.

The Black Swamp Bird Observatory, a volunteer research group, tures, 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, 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. Over two dozen eagles have fledged from these two nests since 1994. Ohio has gone from a low of 4 nesting eagle pairs statewide in 1978 to setting new hatch records every year for over three decades. 129 Davis-Besse Nuclear Power Station 2015 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, tion, electrolysis and demineralization to produce high-purity water used in many of the Station'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 water. The next step of the process is reverse osmosis, where pressure is used to remove certain impurities 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 mineralization process before being sent to storage. Domestic Water When Davis-Besse began operation over 35 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 ter to Davis-Besse.

Carroll Township Water and Wastewater District follow all applicable latory 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 . I 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.

• Zebra mussels have not caused any significant problems at Davis-Besse due to effective biocide . control. At present, the mussel populations are declining.

130 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Algae Control 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 cufating 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 ational challenges.

Wastewater Treatment Plant (WWTP) Operation The WWTP operation is supervised by an Ohio licensed Wastewater Operator.

Wastewater erated by site personnel is treated in an onsite extended aeration package treatment facility 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. ygen 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 organisms necessary for continued treatment, and is pumped back to the aeration tank to c;ligest incoming wastewater.

The effluent leaving the plant is drained to the wastewater basin (NPDES Outfall 601) where further treatment takes place. National Pollutant Discharge Elimination System (NPDES) Reporting The Ohio Environmental Protection Agency (OEP A) has established limits on the amount of 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 2IB00011 *JD. 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 Outfall 002 Area Runoff: Discharge to Toussaint River 131 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 2015 NPDES Summary There were two National Pollutant Discharge Elimination System (NPDES) violations in 2015. On October 2, 2015 Total Residual Oxidants (TRO) measured 0.19 parts per million (PPM) at Outfall 001. This concentration exceeded the permit limitation of 0.05 PPM. On December 17, 2015 Total Residual Chlorine (TRC) measured 0.29 PPM at Outfall 001.This concentration exceeded the permit limitation of 0.2 PPM. In both instances, the Station rination System was isolated until chlorine concentration was restored to below permit tions. 132 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Chemical Waste Management The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes erated at the Davis-Besse Nuclear Power Station was developed to ensure wastes are managed and disposed of in accordance with all applicable state and federal regulations.

Resource Conservation and Recovery Act The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid 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 human health and the environment and to encourage the establishment of solid waste management, source recovery, and resource conservation systems. The intent of the hazardous waste ment 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 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 grams/month (220 lbs./month).

In 2015, the Davis-Besse Nuclear Power Station generated approximately 4,166 pounds of ardous waste. Non-hazardous waste generated in 2015 included 1,329 gallons of used oil and 21,488 pounds of other nonhazardous wastes such as oil filters, resins and caulks. RCR,A 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 throughout 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 inspected weekly by Environmental and Chemistry personnel.

All areas used for storage or lation 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 mulation area for employees to record the waste type and amount when chemicals are 133 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report added to the drum. This ensures that incompatible wastes are not mixed and also identifies 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 perfund) established a federal authority and source of funding for responding to spills and other releases of hazardous materials, pollutants and contaminants into the environment.

Superfund establishes , "reportable quantities" for several hundred hazardous materials and regulates the cleanup of abandoned hazardous waste disposal sites. Superfund Amendment and Reauthorization Act (SARA) ' Superfund was amended in October 1986 to establish new reporting programs dealing with emer-gency 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 icals are present in reportable quantities.

Annual SARA reports are submitted to local fire departments and state and local planning 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 USEP A with the authority to require testing of new chemical substances for potential health effects before they are introduced into the environment, and to regulate them where necessary.

This law would have little impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management system, very similar to the hazardous waste management system established under RCRA. In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers onsite. PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with non-PCB liquid. Retro-filling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with 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.

134 Davis-Besse Nuclear Power Station 2015 AnnuaLRadiological 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, cluding the Station Blackout Diesel Generator, the 2 Emergency Diesel Generators, the Emergency 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 V" legislation, an independent study identifying and quantifying all of the air pollution sources onsite was performed.

Of particular significance is asbestos removal from renovation and demolition projects for which USEP A has outlined specific regulations concerning handling, removal, environmental protection, and disposal.

Also, the cupational 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 ered a hazardous waste by RCRA, but the EPA does require special handling and disposal of this waste under the Clean Air Act. Transportation Safety Act The transportation of hazardous chemicals, including chemical waste, is regulated by the 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 ing, handling, labeling, marking, and placarding.

Before any wastes are transported off site, Besse must ensure that the wastes are identified, labeled and marked according to DOT tions, including verification that the vehicle has appropriate placards and it is in good operating condition.

135 Davis-Besse Nuclear Power Station 2015 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 provide protection from tank contents leaking and causing damage to the environment.

Additional standards require leak detection systems and performance standards for new tanks. At Davis-Besse two 40,000 gallon and one 8,000 gallon diesel fuel storage tanks are registered USTs. Spill Kits Spill control equipment is maintained throughout the Station at chemical storage areas and ardous chemical and oil use areas. Equipment in the kits may include chemical-resistant coveralls, gloves, boots, decontfilnination agents, absorbent cloth, goggles and warning signs. Waste Minimization and Recyding / Municipal Solid Waste (MSW) is normal trash produced by individuals at home and by industries.

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 majority 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, otherwise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing landfills by reducing the amount of MSW produced, by reusing certain waste material, and by recycling 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 duction, reuse, recycle approach to MSW management.

An active Investment Recovery Program has greatly contributed to the reduction of both hazardous and municipal waste generated by uating 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.

Pa,per and cardboard recycling is typically in excess of 50 tons annually.

This repre-. I sen ts 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 disposal. . Although scrap metal is not usually considered part of the MSW stream, Davis-Besse collects 1 and recycles scrap metals, which are sold at market price to a scrap dealer for resource recovery.

136 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report All Environmental, Inc.

• Jf/tli.. /""'\I Midwest Laboratory 1 700 Landwehr Road* Northbrook, IL 60062-2310 phone (847) 564-0700 *fax (847) 564-4517 NOTE: APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS 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. TU) lntercomparison 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, 2015 through December, 2015 137 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Appendix A lnterlaboratory 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 radionuclidi known to the issuing agency but not to participant laboratories.

The purpose of such a program is to pro 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 them to the issu 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 contrc 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 prograr 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 (Tl.Os), via International lntercomparison 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 sam 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 twelVI 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 Evaluatio1 Program. Results irt Table A-7 were obtained through participation in the environmental sample crosscheck progra1 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 cri* in Table A-3 is set at +/- 2 sigma. Out-of-limit results are explained directly below the result. A1 138 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION:

ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa Analysis Gamma Emitters Strontium-89b Strontium-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium lodine-131, lodine-129b Uranium-238, Nickel-63b Technetium-99b lron-55b Other Analyses b Level 5 to 100 pCi/liter or kg > 100 pCi/liter or kg 5 to 50 pCi/liter or kg > 50 pCi/liter or kg 2 to 30 pCi/liter or kg > 30 pCi/liter or kg 0.1 g/liter or kg s 20 pCi/liter . > 20 pCi/liter s 100 pCi/liter > 1 00 pCi/liter s 4,000 pCi/liter

> 4,000 pCi/liter 0.1 pCi/liter 0.1 pCi/liter, gram, or sample s 55 pCi/liter

> 55 pCi/liter s 35 pCi/liter

> 35 pCi/liter 50 to 100 pCi/liter

> 100 pCi/liter One standard deviation for single determination 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 5.0 pCi/liter 10% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value +/- 1cr = 169.85 x (known)0*0933 10% of known value 15% of known value 10% of known value 6 pCi/liter 10% of known value 6 pCi/liter 15% of known value 1 O pCi/liter 10% of known value 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limt. A2. 139 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-1. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERAt Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41.so 30.80 -48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/-4.69 82.50 69.30 -90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/-3.08 75.70 61.80 -83.30 Pass ERW-1448 4/6/2015 Cs-137 191.9 +/- 5.9 189.0 170.0 -210.0 Pass ERW-1448 4/6/2015 Co-60 85.05 +/-4.59 84.50 76.00 -95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 -238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05+/-1.90 42.60 22.10 -54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93+/-1.12 32.90 21 .30 -40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 -28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/-0.56 8.43 6.33 -9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56 -6.01 Pass ERW-1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770 -3,620 Pass ERW-5528 10/5/2015 Sr-89 34.76 +/-0.06 35.70 26.70 -42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 -36. 70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.57 62.30 50.69 -68.50 Pass ERW-5531 10/5/2015 Cs-137 163.1 +/-4.8 157.0 141 .0 -175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71.10 64.00 -80. 70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 113.0 -149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 -64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/- 0.04 36.60 24.1 0 -44.20 Pass ERW"5537 10/5/2015 1-131 25.54 +/- 0.60 26.30 21.90 -31.00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49 -8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46 -5.85 Fail ERW-5540e 10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 -5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 -62.40 Pass ERW-5543 10/5/2015 H-3 21,260 +/- 351 21,300 18,700 -23,400 Pass

• 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). b Unless otherwise indicated, the laboratory result is given as the mean +/-standard deviation for three determinations.

0 Results are as the known values, expected lab.oratory precision (1 sigma, 1 determination) and control limits as provided by ERA. d Ra-228 spike'was at a level close to the detection level. The high result was likely caused by interference Jrom short-lived Rn-222 daughters.

• The result of reanalysis (Compare to original result, footnoted "e" above). AH 140 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS0 4: Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance

• Environmental.

Inc. 2015-1 6/24/2015 30cm. 98.81 103.67 +/- 6.05 69.20 -128.50 Pass 2015-1 6/24/2015 30cm. 98.81 111.32 +/- 15.97 69.20 -128.50 Pass 2015-1 6/24/2015 60cm. 24.70 27.23+/-1.33 17.30 -32.10 Pass 2015-1 6/24/2015 60cm. 24.70 26.98 +/-4.98 17.30 -32.10 Pass 2015-1 6/24/2015 120 cm. 6.18 6.71 +/- 1.77 4.30 -8.00 Pass 2015-1 6/24/2015 120 cm. 6.18 6.78 +/-0.38 4.30 -8.00 Pass 2015-1 6/24/2015 120 cm. 6.18 6.43 +/- 2.00 4.30 -8.00 Pass 2015-1 6/24/2015 150 cm. 3.95 4.13 +/- 0.72 2.80 -5.10 Pass 2015-1 6/24/2015 150 cm. 3.95 4.12 +/- 1.36 2.80 -5.10 Pass 2015-1 6/24/2015 150 cm. 3.95 4.50 +/- 1.51 2.80 -5.10 Pass 2015-1 6/24/2015 180 cm. 2.74 3.27 +/- 0.28 1.90 -3.60 Pass 2015-1 6/24/2015 180 cm. 2.74 3.05+/-1.11 1.90 -3.60 Pass 2015-1 6/24/2()15 180 cm. 2.74 3.14 +/-0.18 1.90 -3.60 Pass A2-1 141 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4: Dy Cards). b mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Acceptance d Environmental.

Inc. 2015-2 12/15/2015 Spike 1 138.0 118.5 +/- 2.1 -0.14 Pass 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 -0.13 Pass 2015-2 5/2015 Spike 3 138.0 121.9 +/- 1.9 -0.12 Pass 2015-2 12/15/2015 Spike 4 138.0 124.5 +/- 3.3 -0.10 Pass 2015-2 12/15/2015 Spike 5 138.0 126.5 +/- 3.2 -0.08 Pass 2015-2 12/15/2015 Spike 6 138.0 140.0 +/-4.2 0.01 Pass 2015-2 12/15/2015 Spike 7 138.0 128.2+/-1.2

-0.07 Pass 2015-2 12/15/2015 Spike 8 138.0 128.0 +/- 4.0 -0.07 Pass 2015-2 12/15/2015 Spike 9 138.0 124.9 +/- 5.1 -0.09 Pass 2015-2 12/15/2015 Spike 10 138.0 122.9 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 12 138.0 119.0 +/- 3.4 -0.14 Pass 2015-2 12/15/2015 Spike 13 138.0 123.0 +/-2.7 -0.11 Pass 2015-2 12/15/2015 Spike 14 138.0 125.4 +/- 2.0 -0.09 Pass 2015-2 12/15/2015 Spike 15 138.0 122.0 +/- 3.1 -0.12 Pass 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 -0.12 Pass 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 -0.14 Pass 2015-2 12/15/2015 Spike 18 138.0 117.0 +/-2.3 -0.15 Pass 2015-2 12/15/2015 Spike 19 13RO 120.8 +/- 2.6 -0.12 Pass 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 -0.11 Pass Mean (Spike 1-20) 123.4 0.11 Pass Standard Deviation (Spike 1-20) 5.0 0.04 Pass

• TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) 0 Performance Quotient (P) is calculated as ((reported dose -conventially true value) + conventially true value) where the conventially true value is the delivered dose. d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15. e Tables A2.1 and A2.2 assume 1 roentgen=

1 rem (per NRG -Health Physics Positions Based on 10 CFR Part 20 -Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015). A2-2 142 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-3. In-House "Spiked" Samples Lab Code b W-020315 W-021215 W-021215 SPW-687 SPAP-689 SPAP-691 SPAP-691 SPW-693 SPW-693 SPW-693 SPW-693 SPMl-697 SPMl-697 SPMl-697 SPMl-697 SPW-699 W-031115 W-030215 SPF-1040 SPF-1040 SPW-1036 SPW-1374 W-040815 W-040815 SPW-1038 W-2165 W-2165 W-2165 W-2165 W-2165 W-2392 W-2392 W-2392 W-2392 W-042415 W-050715 W-050715 W-061215 W-061215 U-2982 U-3200 W-70915 W-70915 SPAP-3859 SPAP-3861 Date 2/3/2015 2/12/2015 2/12/2015 2/27/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/25/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/11 /2015 3/2/2015 3/16/2015

3/16/2015

3/25/2015 4/6/2015 4/8/2015 4/8/2015 4/13/2015 4/20/2015 4/20/2015

4/20/2015

4/20/2015 4/20/2015 4/13/2015

4/13/2015

4/13/2015 4/13/2015 4/24/2015 517/2015 517/2015 6/12/2015 6/12/2015 6/9/2015 6/9/2015 7/9/2015 7/9/2015 7/21/2015 7/21/2015 Analysis Ra-226 Gr. Alpha Gr. Beta Ni-63 Gr. Beta Cs-134 Cs-137 Cs-134 Cs-137 Sr-89 Sr-90 Cs-134 Cs-137 Sr-89 Sr-90 H-3 Ra-226 Ra-228 Cs-134 Cs-137 Fe-55 U-238 Gr. Alpha Gr. Beta C-14 H-3 Sr-89 Sr-90 Cs-134 Cs-137 H-3 Ni-63 Cs-134 Cs-137 Ra-226 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Beta H-3 Gr. Alpha Gr. Beta Gr. Beta *1 Cs-134 Concentration (pCi/L)a Laboratory results 2s, n=1 c 16.19 +/- 0.42 18.38 +/- 0.39 27.98 +/- 0.32 239.6 +/- 3.5 42.37 +/- 3.50 1.77 +/- 0.61 83.02 +/- 2.60 44.30 +/- 2.53 74.82 +/- 3.50 87.45 +/- 3.62 37.22 +/- 1.55 96.67 +/- 7.74 78.51 +/- 7.02 72.98 +/- 4.86 39.17 +/- 1.51 59,592 +/- 703 13.73 +/- 0.35 32.79 +/- 2.31 787.5 +/- 9.2 2,599 +/- 24 1,792 +/- 63 46.03 +/- 2.25 20.18 +/- 0.42 29.70 +/- 0.33 3,497 +/- 9 5550 +/- 226 90.70 +/- 8.20 76.80 +/- 2.00 62.40 +/- 6.40 91.30+/-7.70 5032 +/- 214 222.4 +/- 3.8 53.26 +/- 5.01 91.90 +/- 7.76 12.52 +/- 0.39 19.05 +/- 0.41 27.30 +/- 0.32 20.72 +/- 0.44 28.51 +/- 0.33 500.1 +/- 5.1 2229 +/- 424 18.76 +/- 0.40 29.71 +/- 0.33 41.59 +/- 0.12 1.69 +/- 0.60 A3-1 143 Known Activity 16.70 20.10 30.90 202.4 43.61 1.90 97.20 53.40 73.80 87.48 38.10 107.00 73.84 87.48 38.10 58,445 16.70 31.44 840.0 2,360 1961 41.70 20.10 30.90 4,734 5,780 108.70 75.90 57.30 84.00 5780 202.0 57.30 84.20 16.70 20.10 30.90 20.10 30.90 604.0 2346 20.10 30.90 43.61 1.69 Control Limits d 13.36 -20.04 16.08 -24.12 24.72 -37.08 161.9 -242.9 34.89 -52.33 1.52 -2.28 77.76 -116.64 42.72 -64.08 59.04 -88.56 69.98 -104.98 30.48 -45.72 85.60 -128.40 59.07 -88.61 69.98 -104.98 30.48 -45.72 46,756 -70,134 13.36 -20.04 25.15 -37.73 672.0 -1,008.0 1,888 -2,832 1,569 -2,353 25.02 -58.38 16.08 -24.12 24.72 -37.08 2,840 -6,628 3,468 -8,092 65.22 -152.18 4$.54 -106.26 34.38 -80.22 50.40 -117.60 3468 -8092 121.2 -282.8 34.38 -80.22 50.52 -117.88 10.02 -23.38 12.06 -28.14 18.54 -43.26 12.06 -28.14 18.54 -43.26 362.4 -845.6 1408 -3284 12.1 -28.1 18.5 -43.3 26.17 -61.05 1.0 -2.4 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass. Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-3. In-House "Spiked" Samples Concentration

(!:!Ci/Lt Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 ° Limitsd Acce!:!tance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 -135.03 Pass SPMl-3863 7/21/2015 Cs-134 38.21 +/- 5.12 47.02 28.21 -65.83 Pass SPMl-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 -102.45 Pass SPMl-3863 7/21/2015 Sr-90 41.05+/-1.62 37.78 22.67 -52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 -65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 -102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 -52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319 -80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 -565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 -754.7 Pass SPMl-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 -6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 -56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 -44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5+/-115.9 740.0 444.0 -1036.0 Pass SPF-4104 7/29/2015 Cs-137 2,469 +/- 59 2,340 1,404 -3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06 -28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58

+/- 0.32 30.90 18.54 -43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 -23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06 -28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 -43.26 Pass W-091415 9/14/2016 Gr. Alpha 19.35 +/- 0.51 20.10 12.06 -28.14 Pass W-091415 9/14/2016 Gr. Beta 31.53 +/- 0.35 30.90 18.54 -43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02 -23.38 Pass W-100615 10/6/2016 Gr. Alpha 20.62 +/- 0.43 20.10 12.06 -28.14 Pass W-100615 10/6/2016 Gr. Beta 29.35 +/- 0.33 30.90 18.54 -43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280 -7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52 -138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 -116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 -23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86 -44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738 -15,723 Pass W-6086,6087 11 /18/2015 Cs-134 92.98 +/- 7.29 96.25 57.75 -134.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76 -116.12 Pass W-112515 11 /25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06 -28.14 Pass W-112515 11 /25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54 -43.26 Pass W-120715 1217/2015 Fe-55 2,431 +/- 97 2,319 1,391 -3,247 Pass W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06 -28.14 Pass W-120815 12/8/2015 Gr. Beta 29.50 +/- 0.33 30.90 18.54 -43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02 -23.38 Pass

• Liquid sample results are reported in pCi/Liter, air filters{ pCi/m3), charcoal {pCi/charcoal canister), and solid samples {pCi/kg).

b Laboratory codes : W {Water), Ml (milk), AP {air filter), SO {soil), VE {vegetation), CH {charcoal canister), F (fish), U {urine). 0 Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2s. NOTE: For fish, Jello is used for the spike matrix. For vegetation, cabbage is used for the spike matrix. A3-2 144

. Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)0 Lab Code Sample Date Analysisb Laborato!l'.

results (4.66cr) Acceptance Type LLD Activityc Criteria (4.66 cr) W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/- 0.02 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/- 0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/- 0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74+/-1.42 20 ' SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785+/-1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/- 0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1.57 +/- 3.55 *10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/- 3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/-0.33 SPMl-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/-2.24 10 SPMl-696 Milk 3/212015 Cs-137 4.36 -0.25 +/-2.24 10 SPMl-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMl-696 Milk 3/2/2015 Sr-90 0.49 0.98 +/- 0.32 SPW-698 Water 3/2/2015 H-3 "144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/- 368.1 1000 SPW-1037 Water 3/16/2015 C-14 8.94 2.16 +/-5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1.00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/- 0.25 2 W-050715 Water 5/7/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/-0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/-0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 : 0.009 0.000 +/- 0.005 0.05 SPMl-3862 Milk 7/21/2015 Cs-134 3.13 1.56+/-1.74 10 SPMl-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMl-3862 Milk 7/21/2015 Sr-89 2.17 -1.30 +/- 2.05 5 SPMl-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 SPW-3870 Water 7/21/2015 Sr-89 2.28 -0.42 +/- 1.80 5 SPW-3870 Water 7/21/2015 Sr-90 0.84 0.25 +/-0.42 A4-1 145 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-4. In-House "Blank" Samples Concentration (pCi/Lt Lab Code Sample Date Analysisb LaboratO!)'.

results (4.66crl Acceptance Type LLD Activity 0 Criteria (4.66 cr) SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77+/-1.82 20 SPW-3876 Water . 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52+/-10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51.3 +/-83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/-8.06 100 W-081015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015 Ra-226 0.03 0.03 +/- 0.02 2 W-090615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/- 0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/- 0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/-0.52 4 W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/- 0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/-0.29 2 W-120815 Water 12/8/2015 Gr. Beta 0.76 0.17 +/-.0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2

• Liquid sample results are reported in pCi/Liter, air filters( pCi/m 3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b l-131(G);

iodine-131 as analyzed by gamma spectroscopy.

0 Activity reported is a net activity result. A4-2 146 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Lab Code CF-62,63 CF-62,63 CF-62,63 CF-62,63 SG-83,84 SG-83,84 SG-83,84 SG-83,84 SG-83,84 SG-83,84 SG-83,84 AP-011215A/B WW-315,316 DW-60010,60011

DW-60010,60011 SG-336,337 SG-336,337 SG-336,337 AP-020415A/B AP-021115A/B DW-60023,60024 DW-60023,60024 S-799,800 S-799,800 S-799,800 S-799,800 S-799,800 SG-834,835 SG-834,835 DW-60031,60032 DW-60036,60037 DW-60036,60031 DW-60048,60049

DW-60048,60049 AP-1169, 1170 DW-60069,60070 AP-040915 WW-2394,2395 SG-1847,1848 SG-1847,1848

SG-1847,1848 XWW-2267,2268 XWW-2078,2079 Date 1/7/2015 1/7/2015 1/7/2015 1/7/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/12/2015 1/27/2015

1/28/2015 1/28/2015 1/30/2015 1/30/2015 1/30/2015 2/4/2015 2/11/2015 2/26/2015 2/26/2015 2/26/2015 2/26/2015 2/26/2015 2/26/2015 2/26/2015 2/2/2015 2/2/2015 3/4/2015 3/4/2015 3/4/2015 3/4/2015 3/4/2015 3/19/2015 4/8/2015 4/9/2015 4/13/2015 4/20/2015

4/20/2015

4/20/2015 4/23/2015 4/27/2015 Analysis Gr. Beta Be-7 K-40 Sr-90 K-40 Tl-208 Pb-212 Pb-214 Bi-214 Ra-226 Ac-228 Gr. Beta H-3 Ra-226 Ra-228 Bi-214 Pb-214 Ac-228 Gr. Beta Gr. Beta Ra-226 Ra-228 K-40 Tl-208 Pb-212 Bi-212 Ac-228 Gr. Alpha Gr. Beta Gr. Alpha Ra-226 Ra-228 Ra-226 Ra-228 Be-7 Gr. Alpha Gr. Beta H-3 K-40 Pb-214 Ac-228 H-3 H-3 First Result 5.72+/-0.12 0.915 +/- 0.135 3.97 +/- 0.28 0.017 +/- 0.006 10.11 +/- 1.42 0.57 +/-0.07 1.73 +/-0.10 13.33 +/- 0.33 13.48 +/- 0.39 25.68 +/-2.19 13.33 +/-0.59 0.025 +/- 0.004 1,961 +/- 178 1.25 +/- 0.14 2.00 +/-0.66 6.63 +/-0.20 6.45 +/-0.19 4.43 +/-0.24 0.021 +/- 0.004 0.034 +/- 0.004 1.52 +/- 0.15 0.97 +/- 0.48 11.96 +/-0.98 0.36 +/-0.04 0.92 +/-0.06 1.26 +/- 0.45 1.35 +/- 0.22 113.3 +/- 6.3 82.27 +/-2.79 185.4 +/- 7.4 6.89 +/- 0.34 4.43 +/- 0.73 0.84 +/-0.10 0.68 +/- 0.41 0.20 +/- 0.02 3.58 +/- 0.88 0.027 +/- 0.005 1,628 +/- 139 3.24+/-1.18 5.80 +/- 0.22 5.26 +/- 0.51 6,584 +/-244 359.0 +/-89.6 A5-1 147 Concentration (pCi/L)" Second Result 5.78 +/-0.12 0.919 +/- 0.102 3.88 +/- 0.23 0.011 +/- 0.006 9.69+/-1.20 0.56 +/- 0.06 1.58 +/- 0.09 13.88 +/- 0.28 13.45 +/- 0.29 26.22+/-1.53 12.86 +/- 0.43 0.023 +/- 0.004 1,868+/-174 1.40 +/-0.15 1.39 +/- 0.60 6.45 +/- 0.45 6.45 +/- 0.37 4.20 +/- 0.58 0.019 +/- 0.035 0.040 +/- 0.047 1.51 +/- 0.15 1.66 +/- 0.58 11.49 +/- 0.82 0.31 +/- 0.04 0.91 +/- 0.06 1.50 +/- 0.40 1.23 +/- 0.17 117.2 +/- 2.8 84.33 +/- 2.74 177.0 +/- 7.2 6.88 +/- 0.32 4.41 +/- 0.72 0.94 +/- 0.11 1.42 +/- 0.58 0.24 +/- 0.10 3.92 +/- 0.88 0.023 +/- 0.005 1,695 +/- 141 1.99 +/- 0.76 6.23 +/- 0.76 5.00 +/- 0.42 6,164 +/-237 418.7 +/-92.3 Averaged Result 5.75 +/- 0.42 0.917 +/-0.15 3.92 +/- 0.33 0.014 +/- 0.004 9.90+/-1.16 0.57 +/- 0.05 1.65 +/-0.13 13.61 +/- 0.22 13.47 +/- 0.24 25.95+/-1.34 13.09 +/- 0.36 0.024 +/- 0.003 1,915+/-124 1.33 +/- 0.10 1.70 +/- 0.45 6.54 +/- 0.21 6.45 +/- 0.21 4.32 +/-0.31 0.035 +/- 0.020 0.037 +/- 0.003 1.52 +/- 0.11 1.32 +/- 0.38 11.72 +/- 0.64 0.34 +/- 0.03 0.91 +/- 0.05 1.38 +/- 0.30 1.29 +/- 0.14 115.2 +/-3.4 83.30+/-1.96 181.2 +/-5.2 6.89 +/-0.23 4.42 +/- 0.51 0.89 +/-0.07 1.05 +/- 0.36 0.22 +/- 0.07 3.75 +/- 0.62 0.025 +/- 0.003 1,662 +/- 99 2.62 +/- 0.70 6.02 +/- 0.40 5.13 +/- 0.33 6,374+/-170 388.9 +/- 64.3 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Lab Code XWW-2162,2163 SG-1868, 1869 SG-1868, 1869 SG-1868, 1869 SG-1868, 1869 AP-042915 DW-60076,60077 AP-050515 AP-051115 DW-60087,60088 DW-60087,60088 SG-2436,2437 SG-2436,2437 SG-2436,2437 SG-2458,2459 SG-2458,2459 DW-60095,60096 AP-052715 8"2627,2628 S-2627,2628 S-2627,2628 S-2605,2606 S-2605,2606 S-2605,2606 S-2605,2606 S-2858,2859 S-2858,2859 S-2858,2859 AP-060315 DW-30107,30108 SG-2900,2901 SG-2900,2901 AP-061515 XWW-3173,3174 AP-062215 S-3216,3217 S-3216,3217 VE-3300,3301 VE-3300,3301 AP-062915 WW-3632,3633 Date 4/28/2015 4/28/2015 4/28/2015 4/28/2015 4/28/2015 4/29/2015 5/4/2015 5/5/2015 5/11/2015 5/14/2015 5/14/2015 5/15/2015 5/15/2015 5/15/2015 5/19/2015 5/19/2015 5/26/2015 5/27/2015 5/29/2015 5/29/2015 5/29/2015 6/1/2015 6/1/2015 6/1/2015 6/1/2015 6/2/2015 6/2/2015 6/2/2015 6/3/2015 6/8/2015 6/9/2015 6/9/2015 6/15/2015 6/18/2015 6/22/2015 6/24/2015 6/24/2015 6/24/2015 6/24/2015 6/29/2015

6/30/2015 Analysis H-3 Gr. Alpha Gr. Beta Pb-214 Ra-228 Gr. Beta Ra-228 Gr. Beta Gr. Beta Ra-226 Ra-228 Pb-214 Ra-228 Gr. Alpha Pb-214 Ra-228 Gr. Alpha Gr. Beta Pb-214 Ac-228 Cs-137 Ac-228 Ra-226 K-40 Cs-137 Cs-137 Be-7 K-40 Gr. Beta Gr. Alpha Ac-228 Pb-214 Gr. Beta H-3 Gr. Beta K-40 Be-7 Be-7 K-40 Gr. Beta H-3 First Result 4,408 +/- 201 47.57 +/- 3.63 50.90+/-1.94 13.80 +/- 0.52 20.10 +/- 0.92 0.014 +/- 0.003 2.89 +/- 0.61 0.026 +/- 0.004 0.006 +/- 0.005 1.58 +/- 0.17 0.94 +/- 0.50 22.90 +/-2.31 47.95 +/- 0.61 267.8 +/- 7.9 75.00 +/- 1.66, 41.10 +/-0.92 1.34 +/- 0.69 0.010 +/- 0.003 0.85 +/-0.07 0.85 +/-0.14 0.07 +/-0.02 0.42 +/- 0.06 0.44 +/- 0.03 10.89 +/- 0.51 0.05 +/- 0.01 34.30 +/- 16.05 1501 +/- 264 22,122 +/- 658 0.022 +/- 0.004 1.34 +/- 0.82 10.22 +/- 1.36 7.55 +/- 0.43 0.022 +/- 0.004 841.9+/-123.6 0.023 +/- 0.004 10.38 +/- 0.51 3.65 +/- 0.24 0.78 +/- 0.15 29.12 +/- 0.62 0.023 +/- 0.005 5,169 +/-225 A5-2 148 Concentration (pCi/L)" Second Result 4,242+/-198 43.61 +/- 3.58 51.90 +/-2.02 13.54 +/- 0.62 22.10+/-1.29 0.014 +/- 0.003 2.45 +/- 0.57 0.025 +/- 0.004 0.010 +/- 0.005 1.52 +/-0.17 0.94 +/- 0.50 24.10 +/- 2.43 47.80 +/- 0.71 254.6 +/- 7.6 77.70+/-1.75 40.80 +/- 0.83 0.91 +/- 0.62 0.010 +/- 0.003 0.85 +/- 0.07 1.08 +/- 0.12 0.07 +/- 0.02 0.38 +/-0.07 0.49 +/- 0.03 11.40 +/- 0.48 0.05 +/- 0.01 40.66 +/- 17.79 1171 +/-214 20,987 +/- 600 0.021 +/- 0.004 1.47 +/-0.85 8.32+/-1.07 7.27 +/- 0.41 0.021 +/- 0.004 799.3 +/- 122.4 0.018 +/- 0.004 10.51 +/- 0.53 3.38 +/- 0.27 0.83 +/- 0.23 29.36 +/- 0.64 0.023 +/- 0.005 5,058 +/-223 Averaged Result 4,325 +/- 141 45.59 +/- 2.55 51.40+/-1.40 13.67 +/- 0.40 21.10 +/-0.79 0.014 +/- 0.002 2.67 +/- 0.42 0.026 +/- 0.003 0.008 +/- 0.004 1.55 +/- 0.12 0.94 +/- 0.35 23.50 +/- 1.68 47.88 +/- 0.47 261.2 +/- 5.5 76.35 +/- 1.21 40.95 +/- 0.62 1.13 +/- 0.46 0.010 +/- 0.002 0.85 +/- 0.05 0.97 +/- 0.09 0.07 +/- 0.01 0.40 +/- 0.05 0.47 +/- 0.02 11.15 +/- 0.35 0.05 +/- O.D1 37.48 +/- 11.98 1336 +/- 170 21,555 +/-445 0.022 +/- 0.003 1.41 +/- 0.59 9.27 +/- 0.87 7.41 +/- 0.30 0.022 +/- 0.003 820.6 +/- 87.0 0.020 +/- 0.003 10.45 +/- 0.37 3.52 +/- 0.18 0.81 +/- 0.14 29.24 +/- 0.45 0.023 +/- 0.003 5,114+/-158 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Lab Code AP-3822, 3823 AP-3969, 3970 WW-3632, 3633 W-4368, 4369 W-4368, 4369 Date 7/1/2015 7/1/2015 7/6/2015 7/6/2015 7/6/2015 DW-60138, 60139 7/7/2015 DW-60138, 60139 7/7/2015 WW-4158, 4159 7/9/2015 Ml-2902, 2903 7/10/2015 SG-3533, 3534 7 /10/2015 DW-60150, 60151 7/10/2015 DW-60150, 60151 7/10/2015 VE-3716, 3717 7/14/2015 Ml-3759, 3760 7/15/2015 Ml-3759, 3760 7/15/2015 AP-072115 7/21/2015 VE-4053, 4054 7/21/2015 VE-4053, 4054 7/21/2015 AP-4200, 4201 7/29/2015 AP-4200, 4201 7/29/2015 W-4137, 4138 7/31/2015 XWW-4431, 4432 SG-4305, 4306 AP-081015 AP-081115 VE-4452, 4453 AP-081715 DW-60195,60196

DW-60195,60196 DW-60198, 60199 VE-4578, 4579 SW-4662, 4663 DW-60212, 60213 LW-4788, 4789 AP-083115 AP-4875, 4876 VE-5083, 5084 VE-5083, 5084 VE-5167, 5168 VE-5167, 5168 BS-5188, 5189 F-5419, 5420 DW-60238, 60239 DW-60238, 60239 AP-092215A/B WW-5398, 5399 AP-6007, 6008 8/5/2015 8/6/2015 8/10/2015 8/11/2015 8/11/2015 8/17/2015 8/17/2015 8/17/2015 8/17/2015

8/18/2015 8/25/2015 8/25/2015

8/27/2015 8/31/2015 9/3/2015 9/14/2015 9/14/2015

9/16/2015 9/16/2015 9/16/2015 9/17/2015 9/18/2015 9/18/2015 9/22/2015 9/22/2015

9/28/2015 Analysis Be-7 Be-7 H-3 Gr. Alpha Gr. Beta Ra-226 Ra-228 H-3 K-40 Gr. Alpha Ra-226 Ra-228 K-40 K-40 Sr-90 Gr. Beta Be-7 K-40 Be-7 K-40 Ra-226 H-3 Ra-228 Gr. Beta Gr. Beta K-40 Gr. Beta Ra-226 Ra-228 Gr. Alpha K-40 H-3 Ra-226 )Gr. Beta Gr. Beta Be-7 Be-7 K-40 Be-7 K-40 K-40 K-40 Ra-226 Ra-228 Gr. Beta H-3 Be-7 First Result 0.075 +/- 0.011 0.063 +/- 0.008 5,169 +/- 225. 26.70 +/- 4.00 34.62 +/- 2.10 0.07 +/- 0.04 1.04 +/- 0.41 138.8 +/- 82.4 1271 +/- 118 238.0 +/- 8.2 1.53 +/- 0.16 2.68 +/- 0.68 3.85 +/- 0.33 1819 +/- 127 1.00 +/- 0.36 0.022 +/- 0.004 0.52 +/-0.15 8.00 +/- 0.42 1.06 +/- 0.12 5.03 +/- 0.24 0.58 +/- 0.13 4,773 +/- 213 10.34 +/- 0.58 0.038 +/- 0.005 0.024 +/- 0.004 3.77 +/- 0.29 0.030 +/- 0.005 0.39 +/-0.10 1.43 +/- 0.51 2.93 +/- 0.94 4.14 +/- 0.25 351.3 +/- 89.8 0.09 +/- 0.07 0.97 +/- 0.51 0.032 +/- 0.005 0.294 +/- 0.125 0.47 +/- 0.23 6.20 +/- 0.51 0.40 +/-0.11 3.56 +/- 0.27 9.69 +/- 0.51 3.48 +/- 0.47 1.93 +/- 0.23 4.44 +/- 0.78 0.021 +/- 0.004 1,857 +/- 145 0.08 +/- 0.01 A5-3 149 Concentration (pCi/L)" Second Result 0.068 +/- 0.012 0.064 +/- 0.010 5,058 +/- 223 24.10 +/- 3.90 33.30 +/- 2.02 0.11 +/- 0.05 1.15 +/-0.47 174.0 +/-84.1 1308+/-115 249.5 +/- 8.5 1.49 +/-0.12 1.89 +/- 0.62 3.71 +/- 0.31 1764+/-140 0.61 +/- 0.32 0.027 +/- 0.004 0.49 +/- 0.11 7.61 +/- 0.31 0.96 +/- 0.11 4.96 +/- 0.23 0.45 +/- 0.14 4,915 +/-216 11.46 +/- 0.62 0.039 +/- 0.005 0.020 +/- 0.004 3.78 +/- 0.26 0.030 +/- 0.005 0.37 +/- 0.10 1.97 +/- 0.61 2.11 +/- 0.96 4.32 +/- 0.24 415.6 +/- 92,8 0.10 +/- 0.08 1.68 +/- 0.59 0.031 +/- 0.005 0.202 +/- 0.109 0.56 +/- 0.19 6.36 +/- 0.50 0.41 +/- 0.10 3.91 +/- 0.24 10.51 +/- 0.52 3.49 +/- 0.56 2.31 +/- 0.26 5.61 +/- 0.84 0.025 +/- 0.004 1,846+/-144 0.08 +/- 0.01 Averaged Result 0.072 +/- 0.008 0.063 +/- 0.006 5, 114 +/- 159 25.40 +/-2.79 33.96+/-1.46 0.09 +/- 0.03 1.10 +/-0.31 156.4 +/- 58.9 1289 +/- 82 243.8 +/- 5.9 1.51 +/- 0.10 2.29 +/- 0.46 3.78 +/- 0.23 1791 +/- 94 0.80 +/- 0.24 0.024 +/- 0.003 0.50 +/- 0.09 7.81 +/- 0.26 1.01 +/- 0.08 4.99 +/- 0.16 0.52 +/- 0.10 4,844+/-152 10.90 +/- 0.42 0.039 0.004 0.022 0.003 3.77 +/- 0.20 0.030 +/- 0.003 0.38 +/- 0.07 1.70 +/- 0.40 2.52 +/- 0.67 4.23 +/- 0.17 383.4 +/- 64.6 0.10 +/- 0.05 1.32 +/- 0.39 0.031 +/- 0.003 0.248 +/- 0.083 0.52 +/- 0.15 6.28 +/- 0.36 0.41 +/- 0.07 3.74+/-0.18 10.10 +/- 0.36 3.49 +/- 0.36 2.12 +/-0.17 5:03 +/- 0.57 0.023 +/- 0.00 1,852+/-102 0.08 +/- 0.01 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration

{!::!Ci/Lt Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XW-7490, 7491 9/29/2015 Ni-63 2,332 +/- 233 2,108 +/-211 2,220+/-157 Pass WW-5377, 5378 9/30/2015 H-3 220.0 +/- 84.6 197.0 +/- 83.5 208.5 +/- 59.4 Pass AP-6028, 6029 9/30/2015 Be-7 0.073 +/- 0.009 0.083 +/- 0.012 0.078 +/- 0.007 Pass G-5461,2 10/1/2015 Be-7 2.02 +/- 0.32 1.98 +/- 0.25 2.00 +/- 0.20 Pass G-5461,2 10/1/2015 K-40 8.77 +/- 0.66 9.31 +/- 0.59 9.04 +/- 0.44 Pass S0-5482, 5483 10/1/2015 Ac-228 0.76 +/-0.12 0.74 +/- 0.30 0.75 +/-0.16 Pass S0-5482, 5483 10/1/2015 Bi-214 0.53 +/- 0.04 0.52 +/- 0.04 0.52 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Cs-137 *, 0.12 +/- 0.03 0.12 +/- 0.03 0.12 +/- 0.02 Pass S0-5482, 5483 10/1/2015 K-40 2.17+/-0.73 2.10 +/-0.72 2.13 +/- 0.51 Pass S0-5482, 5483 10/1/2015 Pb-214 0.57 +/- 0.04 0.55 +/- 0.04 0.56 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Ra-226 1.45 +/- 0.27 1.46 +/- 0.30 1.45 +/- 0.20 Pass S0-5482, 5483 10/1/2015 Tl-208 0.24 +/- 0.03 0.25 +/- 0.03 0.24 +/- 0.02 Pass WW-5524, 5525 10/5/2015 H-3 1,192+/-123 1,318 +/- 127 1,255 +/- 89 Pass AP-5881, 5882 10/5/2015 Be-7 0.078 +/- 0.008 0.085 +/- 0.011 0.082 +/- 0.007 Pass AP-5881, 5882 10/5/2015 K-40 0.009 +/- 0.004 0.010 +/- 0.006 0.010 +/- 0.004 Pass SG-6400,1 10/5/2015 Gr.Alpha 19.09 +/-3.14 19.45 +/- 3.25 19.27 +/-2.26 Pass SG-6400,1 10/5/2015 Gr. Beta 31.36 +/- 2.08 29:80 +/- 2.13 30.58 +/- 1.49 Pass VE-5923, 5924 10/1212015 K-40 4.29 +/- 0.29 4.13 +/-0.33 4.21 +/- 0.22 Pass SS-5818, 5819 10/14/2015 Ac-228 0.20 +/- 0.06 0.24 +/- 0.06 0.22 +/- 0.04 Pass SS-5818, 5819 10/14/2015 Cs-137 0.03 +/- 0.02 0.02 +/- 0.01 0.03 +/- 0.01 Pass SS-5818, 5819 10/14/2015 Gr. Beta 8.10 +/- 0.87 8.08 +/- 0.96 8.09 +/- 0.65 Pass SS-5818, 5819 10/14/2015 Pb-212 0.19 +/- 0.03 0.17 +/- 0.02 0.18 +/- 0.02 Pass SS-5818, 5819 10/14/2015 Ra-226 0.47 +/- 0.24 0.45 +/- 0.19 0.46 +/-0.15 Pass SS-5818, 581.9 10/14/2015 Tl-208 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Pass DW-60251, 60252 10/15/2015 Ra-226 0.56 +/-0.12 0.50 +/- 0.08 0.53 +/- 0.07 Pass DW-60251, 60252 10/15/2015 Ra-228 0.79 +/- 0.48 1.16 +/- 0.59 0.98 +/- 0.38 Pass S0-5944, 5945 10/21/2015 Ac-228 1.08 +/-0.15 1.14 +/- 0.15 1.11 +/- 0.10 Pass S0-5944, 5945 10/21/2015 Bi-214 0.89 +/- 0.08 0.82 +/- 0.06 0.85 +/-0.05 Pass S0-5944, 5945 10/21/2015 Cs-137 0.06 +/- 0.02 0.08 +/- 0.03 0.07 +/-0.02 Pass S0-5944, 5945 10/21/2015 Pb-212 1.06 +/- 0.06 0.99 +/- 0.05 1.03 +/-0.04 Pass S0-5944, 5945 10/21/2015 Pb-214 1.00 +/- 0.09 0.89 +/- 0.06 0.95 +/-0.05 Pass S0-5944, 5945 10/21/2015 Ra-226 2.13 +/-0.43 2.16 +/-0.37 2.14 +/-0.28 Pass S0-5944, 5945 10/21/2015 Tl-208 0.36 +/- 0.04 0.34 +/- 0.04 0.35 +/-0.03 Pass S-6175, 6176 10/23/2015 K-40 16.86+/-1.92 14.28+/-1.66 15.57+/-1.27 Pass XWW-6196, 6197 10/26/2015 H-3 2,856+/-170 2,815 +/- 169 2,836+/-120 Pass S0-6259, 6260 10/28/2015 Ac-228 0.60 +/- 0.10 0.53 +/- 0.08 0.57 +/- 0.07 Pass S0-6259, 6260 10/28/2015 Bi-214 0.40 +/- 0.06 0.50 +/- 0.05 0.45 +/-0.04 Pass S0-6259, 6260 10/28/2015 Cs-137 0.17 +/- 0.03 0.19 +/- 0.03 0.18 +/-0.02 Pass S0-6259, 6260 10/28/2015 Gr. Beta 21.6+/-1.1 23.36 +/- 1.21 22.48 +/-0.82 Pass S0-6259, 6260 10/28/2015 Pb-212 0.53 +/- 0.04 0.49 +/- 0.04 0.51 +/- 0.03 Pass S0-6259, 6260 10/28/2015 Tl-208 0.16 +/- 0.03 0.19 +/- 0.04 0.18 +/- 0.02 Pass A5-4 150 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-5. In-House "Duplicate" Samples Concentration

(!;!Ci/L)" Averaged Lab Code Date First Result Second Result Result LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 . Ml-6484, 6485 11/11/2015 K-40 1,384 +/-82 1,432 +/- 89 1,408 +/- 60 S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 +/- 0.03 0.17 +/- 0.02 S0-6841, 6842 11/24/2015 K-40 13.62 +/- 0.76 13.67 +/- 0.69 13.64 +/- 0.51 WW-6978, 6979 11/30/2015 H-3 569.0 +/-97.7 480.3 +/- 93.9 524.7 +/- 67.8 SW-6936, 6937 12110/2015 H-3 151.9 +/- 80.0 176.2 +/- 81.2 164.0 +/- 57.0 SW-7017, 7018 12110/2015 H-3 584.3 +/-98.7 451.6 +/- 93.9 518.0 +/- 68.1 LW-7020, 7021 12110/2015 H-3 236.9 +/-84.2 285.6 +/- 86.5 261.2 +/- 60.3 AP-7351, 7352 12129/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 AP-7414, 7415 12130/2015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 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. Acce(;!tance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil, sediment (pCi/g). A5-5 151 ,-

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits 0 Acceptance MAS0-975 2/1/2015 Ni-63 341 +/- 18 448 314 -582 Pass MAS0-975 2/1/2015 Sr-90 523+/-12 653 457 -849 Pass MAS0-975 2/1/2015 Tc-99 614+/-12 867 607 -1,127 Pass MAS0-975 2/1/2015 Cs-134 533 +/-6 678 475 -881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/-2.5 0.0 NA 0 Pass MAS0-975 2/1/2015 Co-57 0.5+/-1.0 0.0 NA 0 Pass MAS0-975 2/1/2015 Co-60 741 +/- 8 817 572 -1,062 Pass MAS0-975 2/1/2015 Mn-54 1,153+/-9 1,198 839 -1,557 Pass MAS0-975 2/1/2015 Zn-65 892+/-18 1064 745 -1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 -0.850 Pass MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 23.5 16.5 -30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4 -24.8 Pass MAW-969 d 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 -38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA 0 Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 -732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82 -8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA 0 Pass MAW-969

• 2/1/2015 Ni-63 2.9 +/-3.0 0.00 NA 0 Pass MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 18.3 12.8 -23.8 Pass MAW-969 2/1/2015 Tc-99 3.40 .+/- 0.60 3.18 2.23 -4.13 Pass MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NAe Pass MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 0.148 0.104 -0.192 Pass MAW-969 2/1/2015 U-238 0.84 +/- 0.09 0.97 0.68 -1.26 Pass MAW-969 2/1/2015 Sr-90 9.40+/-1.30 9.48 6.64 -12.32 Pass MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAW-947 2/1/2015 1-129 1.26 +/- 0.12 1.49 1.04 -1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 -0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 -1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA 0 Pass MAAP-978 1 2/1/2015 Co-57 0.04 +/-0.04 1.51 1.06 -1.96 Fail* MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA 0 Pass MAAP-978 2/1/2015 Mn-54 1.11 +/- 0.08 1.02 0.71 -1.33 Pass MAAP-978' 2/1/2015 Zn-65 0.83 +/-0.10 0.83 0.58 -1.08 Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA 0 Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059 -0. i 10 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 O.Q16 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- O.Q18 0.099 0.069 -0.129 Pass A6-1 152 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLEA*6.

Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-981 2/1/2015 Sr-89 38.1+/-1.0 47.5 33.3 -61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 -9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/-0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/-0.04 0.00 NAC Pass MAVE-972 2/1/2015 Co-60 3.89 +/-0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/-0.07 0.00 NAC Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NAC Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 I 0.000 NAC Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 ' 0.085 0.059 -0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 -0.129 Pass MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 -61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 -9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/-0.04 0.00 NAC Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/-0.07 0.00 NAC Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NAC Pass MAS0-4903 8/1/2015 Ni-63 556+/-18 682 477 -887 Pass MAS0-4903 9 8/1/2015 Sr-90 231 +/- 7 425 298 -553 Fail MAS0-4903 9 8/1/2015 Sr-90 352+/-10 425 298 -553 Pass MAS0-4903 h 8/1/2015 Tc-99 411 +/- 11 631 442 -820 Fail MAS0-4903 8/1/2015 Cs-134 833+/-10 1,010 707 -1,313 Pass MAS0-4903 8/1/2015 Cs-137 808+/-11 809.00 566 -1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052+/-10 1,180 826 -1,534 Pass MAS0-4903 8/1/2015 Co-60 2 +/-2 1.3 NA 0 Pass MAS0-4903 8/1/2015 Mn-54 1,331 +/- 13 1,340 938 -1,742 Pass MAS0-4903 8/1/2015 Zn-65 686+/-15 662 463 -861 Pass A6-2 153 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report ', TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 -30.0 MAW-5007 8/1/2015 Cs-137 -0.4 +/- 0.1 0.0 NAC MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6 -27.0 MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12.0 -22.2 MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216.0 151.0 -281.0 MAW-5007; 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 -17.0 MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 -20.3 MAW-5007 8/1/2015 Ni-63 9.i +/- 2.6 8.6 6.0 -11.1 MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7 -18.1 MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 5.03 -9.35 MAW-5007 8/1/2015 Sr-90 4.8o +/- o.so 4.80 3.36 -6.24 MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13 -0.73 MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 -5.28 MAW-5007 8/1/2015 1-129 1.42 +/- 0.13 1.49 1.04 -1.94 MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79 -5.17 MMP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 0.74 -1.37 MMP-4907 8/1/2015 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 -1.53 MMP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78 -2.34 MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 4.06 -7.54 MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NAC MAVE-4901 8/1/2015 Co-57 7.74 +/- 0.18 6.62 4.63 -8.61 MAVE-4901 8/1/2015 Co-60 4.84 +/- 0.15 4.56 3.19 -5.93 MAVE-4901 5 Mn-54 8.25 +/- 0.25 7.68 5.38 -9.98 MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 3.82 -7.10

• Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and 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. d Lab result was 27.84. Data entry error resulted in a non-acceptable result.

• Provided in the series for "sensitivity evaluation".

MAPEP does not provide control limits. 1 Lab result was 1.58. Data entry error resulted in a non-acceptable result. 9 The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

h The complex sample matrix is interfering with yield calculations causing a failed low result. An investigation is in process to determine a more reliable yield determination.

1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.

AB-3 154 Acceptance Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLEA-7.

lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)8* Concentration

{pCi/q b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/-2.2 49.8 30.7 -67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61.2 -98.8 Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/-34.7 909.0 578.0 -1, 130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312+/-12.

1, 170 879 -1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/- 48.2 836.0 259.0 -1630.0 Pass ERAP-1091 3/16/2015 Mn-54 <2.7 <50 0.0 -50.0 Pass ERAP-1091 3/16/2015 Pu-238 51.0 +/-3.9 52.1 35.7 -68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3+/-1.3 40.3 29.20 -52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 -145.0 Pass ERAP-1091 3/16/2015 U-233/234 . 29.0 +/- 1.2 34.3 21.3 -51.7 Pass ERAP-1091 3/16/2015 U-238 31.0+/-1.1 34.0 22.0 -47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 -1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/-0.7 62.2 ' 20.8 -96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/-0.8 58.4 36.9 -85.1 Pass ERS0-1098 3/16/2015 Am-241 1571.8 +/- 209.6 1,500 878 -1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 -1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/-455.7 1,780 474 -2,620 Pass ERS0-1098 3/16/2015 Bi-214 3466.9 +/- 86.9 4,430 2,670 -6,380 Pass ERS0-1098 3/16/2015 Co-60 1779.8 +/-41.0 1,880 1 ,270 -2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180 -7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/-41.9 1,490 1, 140 -1 ,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/-380 10,700 7,810 -14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 -1,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/-41 1,230 806 -1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/- 93 4,530 2,640 -6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 -1,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1,185+/-140 1,210 791 -1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724+/-125 1,940 740 -3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/-948 3,890 1,230 -7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/- 226 3,920 2,400 -5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/- 232 3,890 2,410 -4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680 -9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11.5 119.0 42.2 -184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/- 4.8 158.0 90.5 -234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900 -14, 700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/-266 4,340 2,650 -5,770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 -2,120 Pass A7-1 155 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report TABLEA-7.

lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a. Concentration (eCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceetance ERVE-1100 e 3/16/2015 Co-60 1,030 +/- 29 1,540 1,060

-2, 150 Fail ERVE-1100 1 3/16/2015 Co-60 1,684 +/- 48 1,540 1,060 -2, 150 Pass ERVE-1100 e 3/16/2015 Cs-134 1,615 +/- 27 2,650 1,700 -3,440 Fail ERVE-1100 1 3/16/2015 Cs-134 2,554 +/-49 2,650 1,700 -3,440 Pass ERVE-1100 e 3/16/2015 Cs-137 1,248 +/- 29 1,810 1,310 -2,520 Fail ERVE-1100 1 3/16/2015 Cs-137 2,078 +/- 68 1,810 1,310 -2,520 Pass ERVE-1100 e 3/16/2015 K-40 22,037 +/-463 30,900 22,300 -43,400 Fail ERVE-1100 1 3/16/2015 K-40 34,895 +/-764 30,900 22,300 -43,400 Pass ERVE-1100 e 3/16/2015 Mn-54 <13.8 <300 0.0 -300.0 Pass ERVE-1100 1 3/16/2015 Mn-54 <24.4 <300 0.0 -300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/-232 3,680 2, 190 -5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/-240 4,180 2,570 -5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/-326 6,590 3,760 -8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653+/-153 3,150 2,070 -4,050 Pass ERVE-1100 3/16/2015 U-238 2,717+/-163 3,130 2,090 -3,980 Pass ERVE-1100 e 3/16/2015 Zn-65 <94.6 1,090 786 -1,530 Fail ERVE-1100 1 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 -1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/- 4.0 46.0 31.0 -61.7 Pass ERW-1103 3/16/2015 Co-60 1,217+/-17 1,250 1,090 -1,460 Pass ERW-1103 3/16/2015 Cs-134 1,121 +/- 18 1,260 925 -1,450 Pass ERW-1103 3/16/2015 Cs-137 1,332 +/- 31 1,360 1,150 -1,630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 -100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5+/-1.6 72.4 53.6 -90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/-7.8 184.0 143.0

-232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/-4.9 97.7 66.6 -108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 -79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7 -75.2 Pass ERW-1103 3/16/2015 Zn-65 1, 191 +/- 136 1,180 984 -1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149+/-144 1,070 638 -1,450 Pass ERW-1103 3/16/2015 Sr-90 860.0 +/- 37.0 912.0 594.0 -1,210.0 Pass

• 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: ERW (water), ERAP (air filter), ERSO (soil), ERVE (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.

• Technician error weighing sample caused submitted gamma results to be understated and outside the control limits.(low) 1 The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above). 9 The results of reanalysis were outside the control limits (low). h Sample ERW-3742 was ordered from ERA to determine why ERW-1103 results for Pu-239 were outside the acceptable range. The results for ERW-3742 were acceptable.

No reason for the unacceptable results for ERW-3742 was determined.

A7-2 156

, Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report APPENDIX B DATA REPORTING CONVENTIONS B-1 157 Davis-Besse Nuclear Power Station 2015 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 = 2cr 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 4.66cr uncertainty for a background sample. 3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. : 3.1 Individual results: For two analysis results; x 1 +/- s 1 and x 2 +/- s 2 Reported result: x +/- s; where x = (1/2) (x 1 + x 2) ands= (1/2) s; + 3.2. Individual results: Reported result: < L, where L = lower of L 1 and L 2 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 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 x 1 , x 2 *** xn are defined as follows: S=

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. 158 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report APPENDIX C SUPPLEMENTAL ANALYSES C-1 159 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report C-1. Supplemental Analyses.

Units: pCi/L Location T-24 01-14-Date Collected 16 Lab Code TMI-201 1-131 < 0.4 Sr-89 < 0;6 Sr-90 < 0.5 K-40 1142 +/- 158 Cs-134 < 6.3 Cs-137 < 5.4 Ba-La-140

< 3.8 Ca (g/L) 1.00 Sr-90/g Ca < 0.50 K (g/L) 1.39 +/- 0.19 Cs-137/g K < 3.86 160 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report APPENDIX D REMP SAMPLING

SUMMARY

161 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Location of Facility Ottawa, Ohio ( County, State ) Indicator Sample Type and Locations Type Number of LLDb Mean (F)c (Units) Analyses*

Ranoec 0.028 Airborne GB 520 0.003 (312/312)

(0.012-Particulates 0.062) (pCi/m 3) Sr-89 40 0.0015 <LLD Sr-90 40 0.0009 <LLD GS 40 0.076 Be-7 0.015 (24/24) (0.055-0.103) K-40 0.029 <LLD Nb-95 0.0015 <LLD Zr-95 0.0026 <LLD Ru-103 0.0013 <LLD Ru-106 0.0111 <LLD Cs-134 0.0014 <LLD Cs-137 0.0014 <LLD Ce-141 0.0027 <LLD Ce-144 0.0064 <LLD Airborne Iodine 1-131 520 0.07 <LLD (pCi/m 3) TLD 14.5 (Quarterly)

Gamma 350 1.0 (306/306) (mR/91 days) ( 7.7-25.9)

TLD (Quarterly)

Gamma 4 1.0 7.2 (4/4) (mR/91 days) ( 6.2-8.5) (Shield) ' TLD 56.2 (Annual) Gamma 86 1.0 (75/75) (mR/365 ( 34.9-days) 77.9) TLD (Annual) Gamma 1 1.0 24.9 (1/1) (mR/365 days) (Shield) 162 Docket No. Reporting Period Location with Highest Annual Mean Mean (F)c Locationd Ranoec T-11, Ottawa County 0.03 (52/52) WTP, 9.5 mi. (0.013-SE 0.078) ----T-11, Ottawa County 0.083 (4/4) WTP, 9.5mi. (0.060-SE 0.099) --------------------T-8, Farm 23.4 (4/4) 2.7mi.WSW (21.1-25.9)

--T-124 79.3 (1/1) 6.5mi.SSW --50-346 January-December, 2015 Control Number Locations Non-Mean (F)c Routine Ranoec Results* 0.028 (208/208) 0 (0.010-0.078) <LLD 0 <LLD 0 0.077 (16/16) 0 (0.056-0.099) <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 17.5 (44/44) 0 ( 10.5-24.4)

None 0 64.2 (11/11) 0 ( 49.0-79.3)

None 0 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Location of Facility Ottawa, Ohio (County, State) Indicator Sample Type and Locations Type Number of LLDb Mean (F)0 (Units) Analyses*

Ranoe 0 Milk (pCi/L) 1-131 12 0.5 none Sr-89 12 0.6 none Sr-90 12 0.7 none GS 12 K-40 100 none Cs-134 6.2 none Cs-137 6.7 none Ba-La-140 7.5 none (g/L) Ca 12 . 0.50 none (g/L) K (stable) 12 none (pCi/g) Sr-90/Ca 12 none (pCi/g) Cs-137/K 12 0.89 none Ground Water GB(TR) 8 2.1 3.3 (4/5) (pCi/L) (2.1-6.2)

H-3 8 330 <LLD Sr-89 8 1.4 <LLD Sr-90 8 0.8 <LLD GS Mn-54 15 <LLD Fe-59 30 <LLD Co-58 15 <LLD Co-60 15 <LLD Zn-65 30 <LLD Zr-95 15 <LLD Cs-134 10 <LLD 163

• Docket No. Reporting Period Location with Highest Annual Mean Mean (F)0 Locationd Rahoe 0 T-24, Sandusky 1.0 20.2mi. SE (1/12) ----T-24, Sandusky 1367 (12112) 20.2mi. SE (1209-1594)

---

T-24, Sandusky 0.98 (12112) 21.0mi. SE (0.87-1.18)

T-24, Sandusky 1.67 (12112) 21.0mi. SE (1.47-1.94)

T-24, Sandusky (0/12) 21.0 mi. SE (-) --T-27A, Magee Marsh 1.9 (3/3) 5.3mi. WNW (1.0-2.5)--------------------50-346 January-December, 2015 Control Number Locations Non-Mean (F)0 Routine Range 0 Results* 1.0 0 (1/12) <LLD 0 <LLD 0 1367 (12112) 0 (1209-1594)

<LLD 0 <LLD 0 <LLD 0 0.98 (12/12) 0 (0.87-1.18) 1.67 (12/12) 0 (1.47-1.94)

(0/12) 0 (-) <LLD 0 2.4 (1/3) <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Cs-137 10 <LLD Ba-La-140 15 <LLD Table 4.5 . Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses*

Soil GS (pCi/g dry) Be-7 K-40 Mn-54 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 Fruits and Sr-89 Vegetables Sr-90 (pCi/gwet)

GS K-40 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ce-141 Ce-144 Broad Leaf Sr-89 Vegetation Sr-90 (pCi/gwet)

GS 10 3 3 3 8 8 8 Davis-Besse Nuclear Power Station Ottawa, Ohio ( County, State ) Indicator Locations LLDb Mean (F)0 Ranae 0 0.29 <LLD 0.10 9.85 (6/6) (4.14-19.65) 0.032 <LLD 0.043 <LLD 0.037 <LLD 0.028 <LLD 0.24 <LLD 0.025 <LLD 0.016 0.12 (4/6) (0.034-0.30) 0.076 <LLD 0.17 <LLD 0.004 <LLD 0.001 <LLD 0.50 1.07 (2/2} (1.05-1.08} 0.006 <LLD 0.012 <LLD 0.020 <LLD 0.006 <LLD 0.005 <LLD 0.016 <LLD 0.052 <LLD 0.007 <LLD 0.003 <LLD 164 ---

-Docket No. Reporting Period Location with Highest Annual Mean Mean (F)0 Locationd Ranae 0 ----T-9, Oak Harbor 20.76 (1/1) 6.8mi. SW ------------T-8, Farm 0.3 (1/1) 2.7mi.WSW

---

T-8, Residence 1.08 (1/1} 2.7mi.WSW ------------------50-346 <LLD

<LLD 0 0 January-December, 2015 Control Number Locations Non-Mean (F)0 Routine Ranae 0 Results* <LLD 0 17.87 (3/4) 0 (14.61-20.76) <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 0.09 (4/4) (0.054-0.13) 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 1.58(1.1) 0 <LLD 0 <LLD 0 '<:LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report K-40 0.50 2.59 (5/5) T-19 2.59 (5/5) 1.86 (3/3) 0 (2.05-B. Skinner, 1.0 2.95) mi.W (2.05-2.95)

(1.51-2.10)

Nb-95 0.007 <LLD --<LLD 0 Zr-95 0.012 <LLD --<LLD 0 1-131 0.022 <LLD --<LLD 0 Cs-134 0.006 <LLD --<LLD 0 Cs-137 0.006 <LLD --<LLD 0 Ce-141 O.D19 <LLD --<LLD 0 Ce-144 0.046 <LLD --<LLD 0 165 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units) Analvses*

Treated GB(TR) 35 Surface Water (pCi/L) H-3 12 Sr-89 16 Sr-90 16 GS 16 Mn-54 Fe-59 Co-58 Co-60 Zn-65 I Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Untreated GB(TR) 48 Surface Water (pCi/L) H-3 48 Sr-89 16 Sr-90 16 GS 48 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Davis-Besse Nuclear Power Station Ottawa, Ohio ( County, State ) Indicator Locations Mean LLDb (F)C Ranae 0 1.8 2.3 (5/12) (1.8-2.7) 330 <LLD 0.8 <LLD 0.8 <LLD 15 <LLD 30 <LLD 15 <LLD 15 <LLD 30 <LLD 15 <LLD 10 <LLD 10 <LLD 15 <LLD Docket No. Reporting Period Location with Highest Annual Mean Mean (F)0 Locationd Ranae 0 T-12, Water Treatment 3.0 (4/11) Plant, 23.5 mi. WNW (2.1-4.5)

---

2.6 T-11, Ottawa Cly. 0.9 (22/24) WTP 18.0 (12/12) (1.4-5.1) 9.5 mi. SE (1.0-53.0) 553 T-22, Carroll 330 (4/24) Twnshp WP 602 (3/12) 3.0mi. NW (536-721) 0.7 <LLD --0.6 <LLD --15 <LLD --30 <LLD --15 <LLD --15 <LLD --30 <LLD --15 <LLD --10 <LLD --10 <LLD --15 <LLD --.166 50-346 January-December, 2015 Control Number Locations Non-Mean (F)0 Routine Ranae 0 Results* 2.6 (9/23) 0 (1.8-4.5)

<LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 10.3 (22/24) 0 (1.0-53.0)

<LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 <LLD 0 Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Location of Facility Ottawa, Ohio ( County, State ) Indicator Sample Type and Locations Mean Type Number of LLDb (F)C (Units) Analvses*

Ranae 0 Fish GB 6 0.10 3.55 (3/3) (pCi/g (3.12-wet) 3.77) GS 6 K-40 0.10 2.76 (3/3) (2.36-3.45) Mn-54 0.026 <LLD Fe-59 0.14 <LLD Co-58 0.033 <LLD Co-60 0.021 <LLD Zn-65 0.048 <LLD Cs-134 0.022 <LLD Cs-137 0.024 <LLD ., Shoreline GS 8 11.10 Sediments K-40 0.10 (6/6) (8.13-(pCi/g dry) 12.46) Mn-54 0.032 <LLD Co-58 0.035 <LLD Co-60 0.015 <LLD Cs-134 0.026 <LLD Cs-137 0.024 <LLD

• GB = gross beta, GS = gamma scan. Docket No. Reporting Period Location with Highest Annual Mean Mean (F)0 Locationd Ranae 0 T-35, Lake Erie 3.83 (3/3) > 10mi. (3.56-4.23)

T-35, Lake Erie 3.14 (3/3) > 10 mi. (2.43-3.86)

---

( ----------T-4, Site Boundary 12.06 (2/2) 0.8mi.S (11.65-12.46)

---

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample. 50-346 50-346 Control Locations Mean (F)0 Ranae 0 3.83 (3/3) (3.56-4.23)

<-3.14 (3/3) (2.43-3.86)

<LLD <LLD <LLD <LLD <LLD <LLD <LLD 10.73 (2/2) (10.48-10.98)

<LLD

<LLD <LLD <LLD <LLD Number Non-Routine Results* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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 ..

• Non-routine results are those which exceed ten times the control station value. 167 END OF REPORT