ML17150A092

Transmittal of Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for 2016

ML17150A092
Person / Time
Site:	Davis Besse
Issue date:	05/11/2017
From:	Imlay D FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-17-140
Download: ML17150A092 (184)

Text

FE NOC' RrstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 N. State Route 2 Oak Harbor, Ohio 43449 May 11, 2017 L-17-140 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 10 CFR 50.36a Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2016 In accordance with 10 CFR 50.36a(a)(2), this letter transmits the combined 2016 Annual Radiological Environmental Operating Report (AREOR) and Radiological Effluent Release Report (RERR) for the period January 2016 through December 2016. These annual reports are submitted for the Davis-Besse Nuclear Power Station (DBNPS). The AREOR and the RERR must be submitted by May 15 of each year to satisfy the requirements of the DBNPS Technical Specifications 5.6.1 and 5.6.2.

The Attachment provides a listing of the specific requirements detailed in the DBNPS Offsite Dose Calculation Manual (ODCM) and the portion of the ARE OR which was prepared to meet each requirement.

The following information is also provided only to the Document Control Desk. This information includes:

2016 RERR Meteorological Data (on Compact Disc)

Environmental, Inc. Midwest Laboratory, Monthly Progress Report for January through December 2016 which contains the 2016 Radiological Environmental Monitoring Program Sample Analysis Results (on Compact Disc)

Davis-Besse Offsite Dose Calculation Manual, Rev. 32 (on Compact Disc)

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Davis-Besse Nuclear Power Station, Unit 1 L-17-140 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.

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General Plant Manager, Nuclear Davis-Besse Nuclear Power Station vas/kaf

Attachment:

Summary Location(s) of Off-Site Dose Calculation Manual Requirements Contents in the Annual Radiological Environmental Operating Report

Enclosure:

Annual Radiological Environmental Operating Report, including the Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2016 cc:

Regional Administrator, NRG Region Ill DB-1 NRG Senior Resident Inspector DB-1 NRC/NRR Project Manager Branch Chief, Division of Reactor Safety, Branch 4 Utility Radiological Safety Board

L-17-140 Attachment Page 1 of 1 Summary Location(s) of Off-Site Dose Calculation Manual Requirements Contents in the Annual Radiological Environmental Operating Report Description of Requirement Summaries, interpretations, and analyses of trends of the radiological environmental surveillance activities, and an assessment of the observed impacts of the plant (pages 31 through 78 and Appendix C)

Results of the Land Use Census (pages 108 through 113)

Results of the analysis of radiological environmental samples and of environmental radiation measurements (Environmental, Inc. Midwest Laboratory, Monthly Progress Report for January through December 2016 (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 39 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-17-140 Enclosure Annual Radiological Environmental Operating Report, including the Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2016

( 1 Report follows)

2016 Annual Radiological Environmental Operating Report Radiologi el ease

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERA TING REPORT Davis-Besse Nuclear Power Station January 1, 2016 through December 31, 2016 Davis-Besse Nuclear Power Station May 2017

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report TABLE OF CONTENTS Title 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 Reactor Safety and Summary Radioactive Waste Description of the Davis-Besse Site References RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM Introduction Pre-Operational Surveillance Program Operational Surveillance Program Objectives Quality Assurance Program Description Sample Analysis Sample History Comparison IV VI viii 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 20 16 Annual Radiological Environmental Operating Report Title RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) 2016 Program Anomalies Atmospheric Monitoring Terrestrial Monitoring Aquatic Monitoring Direct Radiation Monitoring Conclusion References RADIOACTIVE EFFLUENT RELEASE REPORT Protection Standards 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 Program (PCP)

Borated Water Storage Tank Radionuclide Concentrations Onsite Groundwater Monitoring LAND USE CENSUS Program Design Methodology Results ii 36 36 43 53 65 76 76 79 79 80 81 82 83 84 85 85 85 86 86 86 86 87 88 88 88 103 108 108 109

Davis-Besse Nuclear Power Station 2016 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: REMP Sampling Summary iii 114 115 129 130 132 133 135 137 159 161

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report List of Tables Table Page Title Number Number Risk Factors: Estimated Decrease in Average Life Expectancy 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 Continuous and Batch Mode 16 92 Gaseous Effluents - Mixed Mode Releases - Batch Mode 17 93 Gaseous Effluents - Mixed Mode Releases - Continuous Mode 17 94 LLDs for Gaseous Effluents - Mixed Mode Releases 17 95 Liquid Effluents - Summation of All Releases 18 96 Liquid Effluents - Nuclides Released in Batch Releases 19 97 Liquid Effluents - Nuclides Released in Continuous Releases 19 99 Liquid Effluents - LLDs for Nuclides Released 19 100 Liquid Effluents - Solid Waste and Irradiated Fuel Shipments 20 101 2016 Groundwater Tritium Results 21 104 iv

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Title Doses Due to Gaseous Releases for January through December 2016 Doses Due to Liquid Releases for January through December 2016 Annual Dose to the Most Exposed (from all pathways) Member of the Public 2016 Closest Exposure Pathways Present in 2016 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters Summary of Meteorological Data Recovery for 2016 Summary of Meteorological Data Measured for 2016 Joint Frequency Distribution by Stability Class v

Table Page Number Number 22 106 23 107 24 107 25 111 26 113 27 119 28 120 29 125

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report List of Figures Description The Atom Principal Decay Scheme of the Uranium Series Range and Shielding Sources of Exposure to the Public Fission Diagram Fuel Rod, Fuel Assembly, Reactor Vessel Station Systems Dry Fuel Storage Module Arrangement Map of Area Surrounding Davis-Besse 2016 Airborne Gross Beta Air Sample Site Map Air Samples 5-mile Map Air Sample 25-mile Map Gross Beta Groundwater 1982-2016 Cs-137 in Soil 1972-2016 Terrestrial Site Map Terrestrial 5-mile Map Terrestrial 25-mile Map Gross Beta in Treated Surface Water 1972-2016 Gross Beta Concentration in Untreated Surface Water 1977-2016 Gross Beta in Fish 1972-2016 Aquatic Site Map Aquatic 5-mile Map Aquatic 25-mile Map Gamma Dose for Environmental TLDs 1973 - 2016 TLD Site Map TLD 5-mile Map TLD 25-mile Map Exposure Pathways VI Figure Page Number Number 2

3 3

4 4

8 5

12 6

13 7

15 8

21 9

22 10 38 11 40 12 41 13 42 14 45 15 48 16 50 17 51 18 52 19 54 20 57 21 60 22 62 23 63 24 64 25 66 26 73 27 74 28 75 29 82

Davis-Besse Nuclear Power Station 2016 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

Davis-Besse Nuclear Power Station 2016 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 (Da-vis-Besse) from January I through December 31, 2016. This report meets all of the requirements in NRC Regulatory Guide 4.8, Section 5.6 of Davis-Besse Technical Specifications, and Davis-Besse Offsite Dose Calculation Manual (ODCM) Section 7.1. Reports included are the Radio-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, Chem-ical Waste Management, and Waste Minimization and Recycling.

Radiological Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is established to monitor the ra-diological condition of the environment around Davis-Besse. The REMP is conducted in ac-cordance with NRC Regulatory Guide 4.8, Davis-Besse Technical Specifications, and the Davis-Besse ODCM, Section 6.0. This program includes the sampling and analysis of environmental samples and evaluation of the effects of releases of radioactivity on the environment.

Radiation levels and radioactivity have been monitored within a 25-mile radius around Davis-Besse since 1972. The REMP was established at Davis-Besse about five years before the Station became operational. This pre-operational sampling and analysis program provided data on radia-tion and radioactivity normally present in the area as natural background. Davis-Besse has con-tinued to monitor the environment by sampling air, groundwater, milk, 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 radi-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 allows 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 2016.

There were no missed ODCM samples or other ODCM sample anomalies during the year.

The results of the REMP indicate that Davis-Besse continues to be operated safely in accordance with applicable federal regulations. No significant increase above background radiation or radio-activity is attributed to the operation of Davis-Besse.

The sampling results are divided into four sections: atmospheric monitoring, terrestrial monitor-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 viii

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report cartridges are collected weekly. The 2016 indicator results were in close agreement with the samples collected at control locations.

Terrestrial monitoring includes analysis of milk, groundwater, fruits, vegetables, and soil sam-ples. 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 Wa-ter), Untreated Surface Water, fish and shoreline sediments collected onsite and in the vicinity of Lake Erie. In 2016, tritium was detected at one location at a concentration of 363 pCi/L, which is slightly over the detection limit of 330 pCi/L.

The 2016 results of analysis for fish, treated surface water and shoreline sediment indicate nor-mal background concentration of radionuclides and show no increase or build-up of radioactivity due to the operation of Davis-Besse.

Direct radiation averaged 15.1 mrem/91 days at indicator locations and 17.9 mrem/91 days at control locations, which is similar to results from previous years and indicates no influence on the surrounding environment from the operation of the plant during 2016.

The operation of Davis-Besse in 2016 caused no significant increase in the concentrations of ra-dionuclides or adverse effects on the quality of the environment surrounding the plant. Radioac-tivity released in the Station's effluents was well below the applicable federal regulatory limits.

The estimated radiation dose to the general public due to the operation of Davis-Besse in 2016 was well below all applicable regulatory limits.

In order to estimate radiation dose to the public, the pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is per-formed as part of the REMP. During the census, Station personnel travel every public road with-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 2016 was a garden in the West sector 0.97 miles from Davis-Besse, which is a change from 2015.

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, 2016. 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 radia-tion from Davis-Besse is not distinguishable from background. These doses represent an ex-tremely small fraction of the limits set by the NRC or the limits set in the ODCM.

Unplanned Releases There were no unplanned releases of liquid or gaseous radioactivity from Davis-Besse during 2016.

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Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP)

There was one revision to the ODCM in 2016 to incorporate the results of the 2015 Land Use Census.

There were no revisions of the PCP during 2016.

Groundwater Protection Initiative (NEI 07-07)

Davis-Besse began sampling wells near the plant in 2007 as part of an industry-wide Groundwa-ter Protection Initiative (GPI), which was established to ensure that there are no inadvertent re-leases 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 the spring and fall of each year. Selected wells are also sampled on a quarterly basis for trending due to an increase in groundwater tritium concen-tration identified in 2015 in multiple wells.

In March 2016, five out of eight wells sampled for trending indicated tritium concentrations greater than 2000 pCi/L. The April spring sampling campaign resulted in four out of twenty-two indicating tritium concentrations greater than 2000 pCi/L. Three out of seven wells sampled in July for trending indicated tritium greater than 2000 pCi/L. Only one well out of twenty-two sampled in October for the fal l campaign resulted in a tritium concentration greater than 2000 pCi/L. Well MW-34S was the location with the highest levels of tritium in all four sampling evolutions and declined during the year from 4477 pCi/L to 2242 pCi/L. Throughout 2016, prompt courtesy informational notifications were made to local, county and state officials follow-ing receipt of tritium results from the off-site vendor for well sample results greater than 2000 pCi/L.

All 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.

The 2016 results indicate a slowly decreasing trend in groundwater tritium across the Davis-Besse Site. 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 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 and precipitation. Two instrument-equipped meteorological towers are used to collect data. Data recovery for the five instruments that are operationally required by Davis-Besse Technical Re-quirements Manual was 99.29 % in 2016.

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Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report 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 Sta-tion liquid effluents back to Lake Erie. There were no National Pollutant Discharge Elimination System permit violations in 2016.

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 2016, the Davis-Besse Nuclear Power Station generated approximately 2,628 pounds of hazardous waste. Non-hazardous wastes generated include 2,096 gallons of used oil and 20,673 pounds of non-hazardous waste such as oil filters, resins and caulk, latex paints, and grout. As required by Su-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 collec-tion and recycling of paper. This program was expanded and reinforced during 1993 to include the recycling of paper, aluminum cans, cardboard, and metal. Paper and cardboard recycling typ-ically exceeds 50 tons annually. The scrap metal collected onsite is sold to scrap companies.

Appendices Appendix A contains results from the Inter-laboratory Comparison Program required by the Da-vis-Besse ODCM. Samples with known concentrations of radioisotopes are prepared by the En-vironmental Resources Associates (ERA), and then sent (with information on sample type and date of collection only) to the laboratory contracted by Davis-Besse to analyze its REMP sam-ples. The Environmental Resources Associates (ERA) compares results to known standards.

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Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report Appendix B contains data reporting conversions used in the REMP at Davis-Besse. The appen-dix provides an explanation of the format and computational methods used in reporting REMP data. Information on counting uncertainties and the calculations of averages and standard devia-tions are also provided.

Appendix C provides a REMP sampling summary from 2016. 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 C provides more specific information than that listed in this re-port. The information presented in Appendices A through C was provided by Environmental, Inc. Midwest Laboratory in their Final Progress Report to Davis-Besse (February 11, 2017).

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Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Introduction Nuclear power provides a clean and readily available source of energy. The operation of nuclear power stations has a very small impact on the environment. In fact, the Davis-Besse Nuclear Power Station is surrounded by hundreds of acres of marshland, which make up part of the Ottawa National Wildlife Refuge. In order to provide better understanding of this unique source of energy, back-ground information on basic radiation characteristics, risk assessment, reactor operation and effluent control is provided in this section.

Fundamentals The Atom All matter consists of atoms. Simply de-scribed, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, respec-tively (Figure I). The relatively large pro-tons and neutrons are packed tightly to-gether in a cluster at the center of the atom called the nucleus. Orbiting around the nu-cleus are one or more smaller electrons. In an electrically neutral atom the negative charges of the electrons are balanced by the positive charges of the protons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other. This holds the atom together.

Other attractive forces between the protons and neutrons keep the densely packed protons from repel-ling each other, and prevent the nucleus from breaking apart.

l r

Q Pl\\O"Tt>N Figure I: An atom consists of two parts: a nucleus conlaining 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 Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report Radiation and Radioactivity Isotopes and Radionuclides A group of identical atoms containing the same number of protons make up an element. In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms with one proton are hydrogen atoms, and all atoms with eight protons are oxygen atoms. How-ever, the number of neutrons in the nucleus of an element may vary. Atoms with the same num-ber of protons but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties, and many are stable or nonradioactive. An un-stable or radioactive isotope of an element is called a radioisotope, a radioactive atom, or a radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess energy is usually due to a surplus or deficit in the number of neutrons in the nucleus. Ra-dionuclides such as Uranium-238, Berylium-7 and Potassium-40 occur naturally. Others are man-made, such as lodine-1 31, Cesium-137, and Cobalt-60.

Radiation Radiation is simply the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radia-tion is another type of radiation and has similar properties to those of the examples listed above.

Ionizing radiation consists of both electromagnetic radiation and particulate radiation. Elec-tromagnetic radiation is energy with no measurable mass that travels with a wave-like motion through space. Included in this category are gamma rays and X-rays. Particulate radiation consists of tiny, fast moving particles which, if unhindered, travel in a straight line through space. The three types of particulate radiation of concern to us are alpha particles, 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 emission of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daugh-ter products that eventually result in a stable atom. The loss of energy and/or matter through radioactive decay may transform the atom into a chemically different element. For example, when Uranium-238 decays, it emits an alpha particle and, as a result, the atom loses 2 protons and 2 neutrons. As discussed previously, the number of protons in the nucleus of an atom de-termines its chemical identity. Therefore, when the Uranium-238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of Thorium-234. Thorium-234 is one of the 14 succes-sive daughter products of Uranium-238. Radon is another daughter product, and the series ends with stable Lead-206.

2

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report This example is part of a known radioactive decay series, called the Uranium series, which be-gins with Uranium-238 and ends with Lead-206 (Figure 2).

234Th 24 d 234pa 1.2 min 234u 2.5 x 105 Yr 23°Th 8.0 x 104 Yr 22sRa 1600 Yr 222Rn 3.82 d 21Bp 0 3.05 min 214Bi 19.7 min 214pb 26.8 min Figure 2: Principal Decay Scheme of the Uranium Series.

Half-life 214p 0 1.6x10-4 s 210pb 23 Yr Beta Decay Alpha Decay 2106 i 5.01 d 21op 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 half-lives. Those radioactive materials that are very active, emitting radiation more fre-quently tend to have comparably shorter half-lives. The length of time an atom remains radioac-tive 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 Jose 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 2016 Annual Radiological Environmental Operating Report atoms in that material to become ions, or charged particles. Normally, an atom has the same number of protons as electrons. Thus, the positive and negative charges cancel, and the atom is electrically neutral. When one or more electrons are removed an ion is formed. Ionization is one of the processes that may result in damage to biological systems.

Range and Shielding Particulate and electromagnetic radiation each travel through matter differently because of their different properties. Alpha particles contain 2 protons and 2 neutrons, are relatively large, and carry an electrical charge of +2. Alpha particles are ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its compara-tively large size, an alpha particle usually does not travel very far before it loses most of its ener-gy through collisions and interactions with other atoms. As a result, a sheet of paper or a few centimeters of air can easily stop alpha particles (Figure 3).

Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed of light (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1.

Because they are so small and have a low charge, they do not collide and interact as often as al-pha particles, so they can travel farther. Beta particles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood.

o" -

RADIOACTIVE MATERIAL PAPER ALUMINUM CONCRETE Figure 3 : As radiation travels, it collides and interacts with other atoms and loses energy. Alpha panicles can be stopped by a sheet of paper. and beta particles by a thin sheet of aluminum. Gamma radiation is shielded by highly dense materials such as lead. while hydrogenous materials (those containing hydrogen atoms). such as water and concrete. are used to stop neuttons.

Gamma rays are pure energy and travel at the speed of light. They have no measurable charge or mass, and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray finally loses all of its energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high-energy gamma radiation can travel a considerable distance, whereas low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of Lead or concrete may be needed to effectively shield gamma rays.

Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within operating nuclear power reactors. However, 4

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report neutrons are not of environmental concern since the neutron source at nuclear power stations is sealed within the containment building.

Because neutrons have no charge, they are able to pass very close to the nuclei of the material through which they are traveling. As a result, neutrons may be captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some of its energy. After a series of these deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal neutron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons.

Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron 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 Da-vis-Besse, concrete is used to form an effective neutron shield because it contains water mole-cules and can be easily molded around odd shapes.

Quantities and Units of Measurement There are several quantities and units of measurement used to describe radioactivity and its ef-fects. Three terms of particular usefulness are activity, absorbed dose, and dose equivalent.

Activity: Curie Activity is the number of atoms in a sample that disintegrate (decay) per unit of time. Each time an atom disintegrates, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms of a radioactive substance are decaying.

One curie indicates the disintegration of 37 billion atoms per second.

A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. For example, one gram (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 environmental samples. For instance, the microcurie (uCi) is equal to one millionth of a curie, while the picocurie (pCi) represents one trillionth of a curie.

5

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Absorbed Dose: Rad Absorbed dose is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation. The Rad (radiation absorbed dose) is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material (1 Rad = 100 erg/gm).

The rate of absorbed dose is usually given in Rad/hr.

If the biological effect of radiation is directly proportional to the energy deposited by radiation in an organism, the Rad would be a suitable measurement of the biological effect. However, bio-logical effects depend not only on the total energy deposited per gram of tissue, but on how this energy is distributed along its path. Experiments have shown that certain types of radiation are more damaging per unit path of travel than are others. Thus, another unit is needed to quantify the biological damage caused by ionizing radiation.

Dose Equivalent: Rem Biological damage due to alpha, beta, gamma and neutron radiation may result from the ioniza-tion caused by this radiation. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or X-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose, the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to a particular type of ionizing radia-tion. The dose equivalent is measured in rem (radiation equivalent man).

An example of this conversion from absorbed dose to dose equivalent uses the quality factor for alpha radiation, which is equal to 20. Thus, 1 Rad of alpha radiation is approximately equal to 20 rem. Beta and gamma radiation each have a quality factor of I, therefore one Rad of either beta or gamma radiation is approximately equal to one rem. Neutrons have a quality factor rang-ing from 2 to 10. One rem produces the same amount of biological damage, regardless of the source. In terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit, the 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 DOE.

Committed Effective Dose Equivalent (CEDE)

Committed effective dose equivalent is a measure of the dose received from any radioactive ma-terial taken into the body. It is calculated from the sum of the products of the committed dose 6

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report equivalent to the organ or tissue multiplied by the organ or tissue-weighting factor. CEDE ac-counts for all the dose delivered during the entire time the radioactive material is in the body.

Total Effective Dose Equivalent (TEDE)

Total effective dose equivalent is the sum of the deep dose equivalent (for dose from sources ex-ternal to the body) and the committed effective dose equivalent (for internal dose). Since they are both doses to the body, they are not tracked separately. The NRC limits occupational dose to a radiation worker to five rem (5,000 mrem) TEDE per year.

Sources of Radiation Background Radiation Radiation did not begin with the nuclear power industry, and occurs naturally on earth. It is probably the most "natural" thing in nature. Mankind has always lived with radiation and proba-bly always will. In fact, during every second of life, over 7,000 atoms undergo radioactive decay "naturally" in the body of the average adult. In addition, radioactive decay occurs naturally in soil, water, air and space. All these common sources of radiation contribute to the natural back-ground radiation to which we are all exposed.

The earth is being showered by a steady stream of high-energy gamma rays and particulate radia-tion that come from space known as cosmic radiation. The atmosphere shields us from most of this radiation, but everyone still receives about 20 to 50 mrem each year from this source. The thinner air at higher altitudes provides less protection against cosmic radiation. People living at higher altitudes or flying in an airplane are exposed to even higher levels cosmic radiation. Ra-dionuclides commonly found in the atmosphere as a result of cosmic ray interactions include Be-ryllium-7, Carbon-14, tritium (H-3), and Sodium-22.

Another common naturally occurring radionuclide is Potassium-40. About one-third of the ex-ternal and internal dose from naturally occurring background radiation is attributed to this radio-active isotope of potassium.

The major source of background radiation is Radon, a colorless, odorless, radioactive gas that results from the decay of Radium-226, a member of the Uranium-238 decay series. Since Urani-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 con-cerns stem from the exposure of the lungs to this radioactive gas. Radon emits alpha radiation when it decays, which can cause damage to internal tissues when inhaled. As a result, exposure to the lungs is a concern since the only recognized health effect associated with exposure to Ra-don is an increased risk of lung cancer. This effect has been seen when Radon is present at lev-els 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

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report Sources of Radiation Exposure to the US Population Nuclear Medicine 4Y.

Medical X-ra11s 11 Y.

Internal 11 Y.

Terrestrial 8Y.

Cosmic 8Y.

Consumer Products 3Y.

Other

<lY.

Radon 54Y.

Figure 4: The most significant annual dose received by an individual of the public is that received from naturally occurring radon. A very small annual dose to the public results from producing electricity by nuclear power (taken rrom the Health Physics Society, University ofMichigan, 2013).

Further information on Radon, its measurement, and actions to reduce the Radon concentration in buildings can be obtained by contacting the state Radon program office at the following ad-dress:

Ohio Department of Health Bureau of Environmental Health and Radiation Protection 246 North High Street Columbus, Ohio 43215 (614) 644-2727 (614) 466-0381 FAX The approximate average background radiation in this area is 620 mrem/year (Princeton Univer-sity, 2013).

Man-made Radiation In addition to naturally occurring cosmic radiation and radiation from naturally occurring radio-activity, people are also exposed to man-made radiation. The largest sources of exposure include medical x-rays and radioactive pharmaceuticals. Small doses are also received from consumer products such as televisions, smoke detectors, and fertilizers. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include Strontium-90, 8

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Cesium-137, and tritium. Less than one percent of the annual dose a member of the public re-ceives is a result of having electricity generated by nuclear power.

Health Effects of Radiation The effects of ionizing radiation on human health have been under study for more than one hun-dred 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 dif-ficult to relate the biological effects of irradiated laboratory animals to the potential health ef-fects on humans.

The effects of radiation on humans can be divided into two categories, somatic and genetic. So-matic effects are those which develop in the directly exposed individual, including an unborn child. Genetic effects are those which are observed in the offspring of the exposed individual.

Somatic effects can be divided further into acute and chronic effects. Acute effects develop shortly after exposure to large amount of radiation. Much study has been done with human pop-ulations that were exposed to ionizing radiation under various circumstances. These groups in-clude the survivors of the atomic bomb, persons undergoing medical radiation treatment, and early radiologists, who accumulated large doses of radiation, unaware of the potential hazards.

Chronic effects are a result of exposure to radiation over an extended period of time. Examples of such groups are clock dial painters, who ingested large amounts of Radium by "tipping" the paint brushes with their lips, and Uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (Uranium ore). The studies performed on these groups have increased our knowledge of the health effects from comparatively very large doses of radiation received over long periods of time.

Continuous exposure to low levels of radiation may produce somatic changes over an extended period of time. For example, someone may develop cancer from man-made radiation, back-ground radiation, or some other source not related to radiation. Because all illnesses caused by low level radiation can also be caused by other factors, it is virtually impossible to determine in-dividual health effects of low level radiation. Even though no effects have been observed at dos-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 expo-sure. The effects predicted in this manner have never been actually observed in any individuals exposed to low level radiation. Therefore, the most likely somatic effect of low level radiation is believed to be a small increased risk of cancer. Genetic effects could occur as a result of ioniz-ing radiation interacting with the genes in the human cells. Radiation (as well as common chem-icals) 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 occur. Spontaneous mutations and chemically induced mutations also have been observed. These mutated genes may be passed 9

Davis-Besse Nuclear Power Station 2016 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 driv-ing to work each day, they are less inclined to accept the risk inherent in producing electricity.

As with any industrial environment, it is not possible to guarantee a risk free environment. Thus, attention should be focused on taking steps to safeguard the public, on developing a realistic as-sessment of the risks, and on placing these risks in perspective. The perceptions of risk 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 can-cer-causing substances. These risks are larger and measurable compared to those presumed to be associated with exposure to low level, low dose radiation. Most of these risks are with us throughout 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 Unit-ed 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 l 0.0 years 5.8 years 2.7 years 5.0 years less than 12 minutes 10

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Benefits of Nuclear Power Nuclear power plays an important part in meeting today's electricity needs, and will continue to serve as an important source of electric energy well into the future. Today approximately twenty percent of the electricity produced in the United States is from nuclear powered electrical gener-ating 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 nucle-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, wa-ter is turned into steam. In a nuclear station, a reactor that contains a core of nuclear fuel, pri-marily 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.

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Davis-Besse Nuclear Power Station 2016 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 1he proper environment, this process can continue indefinitely in a chain reaction.

Nuclear Fuel The fissioning of one Uranium atom releases approximately 50 million times more energy than the combustion of a single Carbon atom common to all fossil fuels. Since a single small reactor fuel pellet contains trillions of atoms, each pellet can release an extremely large amount of ener-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 occurrences cannot sustain themselves because the freed neutrons either are absorbed by non-fissionable atoms or quickly decay. In contrast, a nuclear reactor minimizes neutron losses, thus sustaining the fission pro-cess by several means:

using fuel that is free of impurities that might absorb the free neutrons, enriching the concentration of the rarer fissionable isotope of Uranium (U-235) relative to the concentration of U-238, a more common isotope that does not fis-sion easily, slowing down 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 2016 Annual Radiological Environmental Operating Report After the Uranium ore is separated from the earth and rock, it is concentrated in a milling pro-cess. After milling the ore to a granular form and dissolving out the Uranium with acid, the Ura-nium is converted to Uranium hexafluoride (UF6). UF6 is a chemical form of Uranium that exists as a gas at temperatures slightly above room temperature. The UF6 is then highly purified and shipped to an enrichment facility where gaseous diffusion converters increase the concen-tration of U-235. The enriched gaseous 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 con-stitute the fuel cladding. The fuel cladding is highly resistant to heat, radiation, and corrosion.

When the tubes are filled with fuel pellets, they are called fuel rods.

The Reactor Core Two hundred eight fuel rods comprise a single fuel assembly. The Reactor core at Davis-Besse contains 177 of these fuel assemblies, each approximately 14 feet tall and 2,000 pounds in weight. In addition to the fuel rods, the fuel assembly also contains 16 vacant holes for the inser-tion of control rods, and one vacant hole for an incore-monitoring probe. This probe monitors temperature and neutron levels in the fuel assembly. The Davis-Besse reactor vessel, which con-tains all the fuel assemblies, weighs 838,000 pounds, has a diameter of 14 feet, is 39 feet high, and has steel walls that are 8 Y2 inches thick.

REACTOR VESSEL Figure 6: The reactor core at Davis-Besse contains 177 fuel assemblies. Each assembly contains 208 fuel rods.

Each fuel rod is filled with approximately five pounds offuel pellets. Each pellet is approximately 3/8 inch diame-ter and 5/8 inch long.

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Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Fission Control Raising or lowering control rod assemblies into the reactor core controls the fission rate. Each assembly consists of "fingers" containing Silver, Indium, and Cadmium metals that absorb free neutrons, thus disrupting the fission chain reaction. When control rod assemblies are slowly withdrawn from the core, The fission process begins and heat is produced. If the control rod as-semblies are inserted rapidly into the reactor core, as occurs during a plant "trip", the chain reac-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 reac-tors (LWRs) because their coolant, or medium to transfer heat, is ordinary water, which con-tains the light isotope of Hydrogen.

Some reactors use the heavy isotope of Hydrogen (deuterium) in the reactor coolant. Such reactors are called heavy water reactors (HWRs).

In BWRs, water passes through the core and boils into steam. The steam passes through separa-tors, which remove water droplets. The steam then travels to dryers before entering the turbine.

After passing though the turbine the steam is condensed back into water and returns to the core to repeat the cycle.

In PWRs, the reactor water or coolant is pressurized to prevent it from boiling. The reactor wa-ter is then pumped to a steam generator (heat exchanger) where its heat is transferred to a sec-ondary water supply. The secondary water inside the steam generator boils into steam, which is then used to turn the turbine. This steam is then condensed back into water and returned to the steam generator. Davis-Besse uses a PWR design.

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

14

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Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Station Systems Containment Building and Fission Product Release Barriers The Containment building houses the reactor vessel, the Pressurizer, two steam generators, the Reactor Coolant Pumps and Reactor Coolant System piping. The building is constructed of an inner 1-1/2 inch thick steel liner or Containment vessel, and the Shield Building with steel-reinforced concrete walls 2 feet thick. The shield building protects the containment vessel from a variety of environmental factors and provides an area for a negative pressure boundary around the steel Containment vessel. In the event that the integrity of the Containment vessel is compromised (e.g., a crack develops), this negative pressure boundary ensures that any airborne radioactive contamination present in the containment vessel is prevented from leaking out into the environment. 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 Containment vessel is the third in a series of barriers that prevent the release of fission products in the unlikely event of an accident. The first barrier to the release of fission products is the fuel cladding itself. The second barrier is the walls of the primary system, i.e. the reactor vessel, steam generator and associated piping.

The Steam Generators The steam generators perform the same function as a boiler at a fossil-fueled power station.

The steam generator uses the heat of the primary coolant inside the steam generator tubes to boil the secondary side feedwater (secondary coolant). Fission heat from the reactor core is trans-ferred to the steam generator in order to provide the steam necessary to drive the turbine. How-ever, heat must also be removed from the core even after reactor shutdown in order to prevent damage to the fuel cladding. Therefore, pumps maintain a continuous flow of coolant through the reactor and steam generator. Primary loop water (green in Figure 7) exits the reactor at ap-proximately 606°F, passes through the steam generator, transferring some of its heat energy to the Secondary loop water (blue in Figure 7) without actually coming in contact with it. Prima-ry coolant water exits the steam generator at approximately 558°F to be circulated back into the reactor where it is again heated to 606°F as it passes up through the fuel assemblies. Under or-dinary conditions, water inside the primary system would boil long before it reached such tem-peratures. However, it is kept under a pressure of approximately 2,200 pounds-per-square-inch (psi) at all times. This prevents the water from boiling and is the reason the reactor at Davis-Besse is called a Pressurized Water Reactor. Secondary loop water enters the base of the steam generator at approximately 450°F and under I, I 00 psi pressure. At this pressure, the water can easily boil into steam as it passes over the tubes containing the primary coolant water.

Both the primary and the secondary coolant water are considered closed loop systems. This means that they are designed not to come in physical contact with one another. Rather, the cool-ing water in each loop transfers heat energy by convection. Convection is a method of heat transfer that can occur between two fluid media. It is the same process by which radiators are used to heat homes. The water circulating inside the radiator is separated from the air (a "fluid" medium) by the metal piping.

16

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report The Turbine Generator The turbine, main generator, and the condenser are all housed in what is commonly referred to as the Turbine Building. The purpose of the turbine is to convert the thermal energy of the steam produced in the steam generator (referred to as main steam, red in Figure 7) to rotational energy of the turbine generator shaft. The turbine at Davis-Besse is actually composed of one six-stage high-pressure turbine and two seven-stage low-pressure turbines aligned on a common shaft. A turbine stage refers to a set of blades. Steam enters at the center of each turbine and moves outward along the shaft in opposite directions through each successive stage of blading.

As the steam passes over the turbine blades, it loses pressure. Thus, the blades must be propor-tionally larger in successive stages to extract enough energy from the steam to rotate the shaft at the correct speed.

The purpose of the main generator is to convert the rotational energy of the shaft to electrical energy for commercial usage and support of station systems. The main generator is composed of two parts, a stationary stator that contains coils of copper conductors, and a rotor that sup-plies a rotating magnetic field within the coils of the stator. Electrical current is generated in the stator portion of the main generator. From this point, the electric current passes through a series of transformers for transmission and use throughout northern Ohio.

The Condenser After the spent steam in the secondary loop (blue in Figure 7) passes through the High and Low Pressure Turbines, it is collected in the condenser, which is several stories tall and contains more than 70,000 small tubes. Circulating Water (yellow in Figure 7) goes to the Cooling Tower after passing through the tubes inside the Condenser. As the steam from the Low Pres-sure Turbines passes over these tubes, it is cooled and condensed. The condensed water is then purified and reheated before being circulated back into the steam generator again in a closed loop system. Circulating water forms the third (or tertiary) and final loop of cooling water used at the Davis-Besse Station.

Similar to the primary to secondary interface, the secondary-to-tertiary interface is based on a closed-loop design. The Circulating Water, which is pumped through the tubes in the Water Box, is able to cool the water in the Condenser by the processes of conduction and convection.

Even in the event of a primary-to-secondary leak, the water vapor exiting the Davis-Besse Cool-ing Tower would remain non-radioactive. Closed loops are an integral part of the design of any nuclear facility. This feature greatly reduces the chance of environmental impact from Station operation.

The Cooling Tower The Cooling Tower at Davis-Besse is easily the most noticeable feature of the plant. The tower stands 493 feet high and the diameter of the base is 411 feet. Two nine-foot diameter pipes circu-late 480,000 gallons of water per minute to the tower. Its purpose is to recycle water from the Condenser by cooling and returning it.

17

Davis-Besse Nuclear Power Station 2016 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. Depend-ing on the severity of the loss of pressure inside the Primary System, the ECCS will automatical-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 Sys-tem.

The violet system illustrated in Figure 7 is responsible for maintaining the Primary Coolant wa-ter in a liquid state. It accomplishes this by adjusting the pressure inside the Primary System.

Heaters inside the Pressurizer tum water into steam. This steam takes up more space inside the Pressurizer, 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 Tur-bine Building along with the Turbine, Main Generator, and the Condenser.

18

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Reactor Safety and Summary Nuclear power plants are inherently safe, not only by the laws of physics, but by design. Nuclear power plants cannot explode like a bomb, because the concentration of fissionable material is far less than is necessary for such a nuclear explosion. Also, many safety features are equipped with several backup systems to ensure that any possible accident would be prevented from causing a serious health or safety threat to the public, or serious impact on the local environment. Davis-Besse, like all U.S. nuclear units, has many overlapping, or redundant safety features. If one sys-tem should fail, there are still back-up systems to assure the safe operation of the Station. Dur-ing normal operation, the Reactor Control System regulates the power output by adjusting the position of the control rods. The Reactor can be automatically shut down by a separate Reactor Protection System, which causes all the control rod assemblies to be quickly and completely inserted into the Reactor core, stopping the chain reaction. To guard against the possibility of a Loss of Coolant Accident, the Emergency Core Cooling System is designed to pump reserve wa-ter into the reactor automatically if the reactor coolant pressure drops below a predetermined level.

The Davis-Besse Nuclear Power Station was designed, constructed, and is operated to produce a reliable, safe, and environmentally sound source of electricity.

Radioactive Waste Many of the activities we depend on in our everyday lives produce radioactive waste by-products. Nuclear energy, industrial processes, and medical treatments are some of these activi-ties. These by-products are managed and disposed of under strict requirements set by the federal government. With the exception of used nuclear fuel assemblies, these by-products produced at commercial power plants are referred to as low level radioactive waste.

Low Level Radioactive Waste Low level radioactive waste consists of ordinary trash and other items that have become contam-inated with radioactive materials 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 natu-rally-occurring radioactive materials. Most low level activity in radioactive waste decay to background levels within months or years. Nearly all activity diminishes to stable materials in less than 300 years.

Davis-Besse currently transports low-level radioactive waste to Tennessee for processing, after which it is shipped to Utah or Texas for disposal. Davis-Besse has the capacity to store low-level waste produced on site for several years in the Low Level Radioactive Waste Storage Fa-cility, should this facility close.

Davis-Besse added the Old Steam Generator Storage Facility (OSGSF) in 2011 to house the Re-actor Vessel Closure Head, Service Support Structure and Control Rod Drive mechanisms re-moved during the l 7M outage. Two Steam Generators and two Reactor Coolant System Hot 19

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Leg 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 an-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 ves-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 moni-tor the dose rates and tritium.

High Level Nuclear Waste Like any industrial or scientific process, nuclear energy does produce waste. The most radioac-tive is defined as "high-level" waste (because it has high levels of radioactivity). Ninety-nine percent of high-level waste from nuclear plants is used nuclear fuel. The fuel undergoes certain changes during fission. Most of the fragments of fission, pieces that are left over after the atom is split, are radioactive. After a period of time, the fission fragments trapped in the fuel assem-blies reduce the efficiency of the chain reaction. The oldest fuel assemblies are removed from the reactor and replaced with fresh fuel at 24 month intervals.

High-level nuclear waste volumes are small. Davis-Besse produces about 30 tons of used fuel every 24 months. All the used fuel produced by all America's nuclear energy plants since the first plant started operating over 30 years ago would cover an area the size of a football field about five yards deep. All of America's nuclear plants combined produce only 3,000 tons of used fuel each year. By contrast, the U.S. produces about 300,000,000 tons of chemical waste annually. Also, nuclear waste slowly loses its radioactivity, but some chemical waste remains hazardous indefinitely.

Davis-Besse presently stores most of its used fuel in a steel-lined water-filled concrete vault in-side the plant. The Department of Energy (DOE) 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 developed, 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 be-gan 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 fa-cilities 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, Minneso-ta, Virginia, Wisconsin and South Carolina, to name a few. Figure 8 below illustrates the Dry Fuel Storage module arrangement at Davis-Besse.

In 2001, work was performed to increase the storage capacity of the Spent Fuel Pool. The pool remains the same size, however, removing old storage racks and replacing them with new ones changed the configuration of storage. This allows the site to safely hold all the fuel used during its 40 years of expected life. This modification was completed in April of 2002 and no addition-al spent fuel has been transferred to the canisters since that time.

20

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report

z:

w w

a:

1:5 0 a:

iii Figure 8: Dry Fuel Storage Module Arrangement 21

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Description of the Davis-Besse Site The Davis-Besse site is located in Carroll Township of Ottawa County, Ohio. It is on the south-western shore of Lake Erie, just north of the Toussaint River. The site lies north and east of Ohio State Route 2, approximately l 0 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 consist-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

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report The immediate area near Davis-Besse is sparsely populated. The most recent Census was com-pleted in the year 20 I 0 and 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 major resort area of the county is farther east, around Port Clinton, Lakeside, and the Bass Is-lands.

The majority of non-marsh areas around the Davis-Besse site are used for farming. The major crops include soybeans, corn, wheat, oats, hay, fruits and vegetables. Meat and dairy animals are not major sources of income in the area. The main industries within five miles of the site are lo-cated 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 recrea-tional areas within 10 miles of the Station. These include Magee Marsh, Turtle Creek and Crane Creek Wildlife Research Station. Magee Marsh and Turtle Creek lie between three and six miles WNW of the Station. Magee Marsh is a wildlife preserve that allows public fishing, nature study, and a controlled hunting season. Turtle Creek 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 op-erated by the U.S. Fish and Wildlife Service, lies four to nine miles WNW of the Site, immedi-ately west of Magee Marsh.

23

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report References

1. "Basic Radiation Protection Criteria," Report No. 39, National Council on Radiation Protec-tion and Measurement, Washington, D.C. (January 1971).

2. "Cesium-I 37 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 I 976).

6. "Exposure of the Population in the United States and Canada from Natural Background Ra-diation," Report No. 94, National Council on Radiation Protection and Measurements, Wash-ington, D.C. (December I 987).

7. "Health Effects of Exposure to Low Levels oflonizing Radiation: BEIR V," Committee on the Biological Effects of Ionizing Radiations, Board on Radiation Effects Research Commis-sion on Life Sciences, National Research Council, National Academy Press, Washington, D.C. (1990).

8. Hendee, William R., and Doege, Theodore C., "Origin and Health Risks of Indoor Radon,"

Seminars in Nuclear Medicine, Vol. XVIII, No. 1, American Medical Association, Chicago, IL. (January I 987).

9. Hurley, P., "Living with Nuclear Radiation," University of Michigan Press, Ann Arbor, Ml.

(1982).

I 0. "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 I 986).

I I. Introduction to Davis-Besse Nuclear Power Station Plant Technology, July 1992, Rev. 4, Pg.2-9.

12. "Ionizing Radiation Exposure of the Population of the United States," Report No. 93, Na-tional Council on Radiation Protection and Measurements, Washington, D.C. (September I 987).

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 2016 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. (De-cember 1987).

17. "Radiation Protection Standards," Department of Environmental Sciences and Physiology and the Office of Continuing Education, Harvard School Of Public Health, Boston, MA. (Ju-ly 1989).

18. Radiological Environmental Monitoring Report for Three Mile Island Station," GPU Nuclear Corporation, Middletown, PA. (1985).

19. "Sources, Effects and Risk oflonizing 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 I 0, 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 I 979).

24. Site Environmental Report, Fernald Environmental Management Project, United States De-partment of Energy (June I 993).

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 Measure-ments, Washington, D.C. (1984).

27. Nuclear Energy Institute (NEI) website, www.nei.org.

25

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Introduction The Radiological Environmental Monitoring Program (REMP) was established at Davis-Besse for several reasons: to provide a supplementary check on the adequacy of containment and effluent controls, to assess the radiological impact of the Station's operation on the surrounding area, and to determine compliance with applicable radiation protection guides and standards. The REMP was established in 1972, five years before the Station became operational. This pre-operational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of Davis-Besse. After Davis-Besse became operational in 1977, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas.

A variety of environmental samples are collected as part of the REMP at Davis-Besse. The se-lection of sample types is based on the established critical pathways for the transfer of radionu-clides through the environment to humans. The selection of sampling locations is based on sample availability, local meteorological and hydrological characteristics, local population char-acteristics, and land usage in the area of interest. The selection of sampling frequencies for the various environmental media is based on the radionuclides of interest, their respective half-lives, and their effect in both biological and physical environments.

A description of the REMP at Davis-Besse is provided in the following section. In addition, a brief history of analytical results for each sample type collected since 1972, and a more detailed summary of the analyses performed during this reporting period is also provided.

Pre-operational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental moni-toring prior to constructing the facility. This pre-operational surveillance program is for the col-lection of data needed to identify critical pathways, including selection of radioisotope and sample media combinations for the surveillance conducted after facility operations begin. Ra-dio-chemical analyses performed on samples should include nuclides that are expected to be re-leased during normal facility operations, as well as typical fallout radionuclides and natural background radioactivity. All environmental media with a potential to be affected by facility operation, as well as those media directly in the critical pathways, should be sampled during the pre-operational phase of the environmental surveillance program.

The pre-operational surveillance design, including nuclide/media combinations, sampling fre-quencies and locations, collection techniques and radiochemical analyses performed, should be carefully considered and incorporated in the design of the operational surveillance program. In 26

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report this manner, data can be compared in a variety of ways (for example: from year to year, location to location, etc.) in order to detect any radiological impact the faci lity has on the surrounding environment. 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 use in I 977. 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 wi ll continue after the Station has reached the end of its economic viability and de-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 Sta-tion's Technical Specifications and Offsite Dose Calculation Manual to determine whether any significant increase in the concentration of radio-nuclides in critical pathways occurs to identify and evaluate the buildup, if any, of radionuclides in the local envi-ronment, or any changes in normal background radiation levels to verify the adequacy of Station controls for the release of radioactive mate-rials Quality Assurance An important part of the environmental monitoring program at Davis-Besse is the Quality Assurance (QA) Program, which is conducted in accordance with the guidelines specified in NRC Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs". The QA Program is designed to identify possible deficiencies in the REMP so that corrective actions can be initiated promptly. Davis-Besse's Quality Assurance program also provides confidence in the results of the REMP through:

performing regular audits (investigations) of the REMP, including a careful examination of sample collection techniques and record keeping performing audits of contractor laboratories which analyze the environmental samples requiring analytical contractor laboratories to participate in the United States Environmental Protection Agency Cross Check Program requiring analytical contractor laboratories to split samples for separate analy-sis followed by a comparison of results splitting samples prior to analysis by independent laboratories, and then com-paring the results for agreement 27

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report requiring analytical contractor laboratories to perform in-house spiked sample analyses Quality Assessment audits and inspections of the Davis-Besse REMP are performed by the FirstEnergy Nuclear Operating Company QA Department and the NRC. In addition, the Ohio Department of Health (OOH) also performs independent environmental monitoring in the vicini-ty of Davis-Besse. The types of samples collected and list of sampling locations used by the OOH 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 quali-ty of the laboratories' analytical procedures and data generated.

In 1987, environmental sampling personnel at Davis-Besse incorporated their own QA program into the REMP. Duplicate samples, called quality control samples, were collected at several lo-cations. These duplicate samples were assigned different identification numbers than the num-bers assigned to the routine samples. This ensured that the analytical laboratory would not know the samples were identical. The laboratory results from analysis of the quality control samples and the routine samples could then be compared for agreement. Quality control sampling has been integrated into the program and has become an important part of the REMP since 1987.

Quality control sampling locations are changed frequently in order to duplicate as many sam-pling locations as possible, and to ensure the contractor laboratory has no way of correctly pair-ing a quality control sample with its routine sample counterpart.

Program Description The Radiological Env.ironmental 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 Sta-tion Operating Procedures. Samples are collected weekly, monthly, quarterly, semiannually, or annually, depending upon the sample type and nature of the radionuclides of interest. Environ-mental 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 are those which would be most likely to display the effects caused by the operation of Davis-Besse, and are located within five miles of the station. Control locations are those which should be unaffected by Station operations, and are more than five miles from the Station. Data from 28

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report indicator locations are compared with data from the control locations. This comparison allows REMP personnel to take into account naturally-occurring background radiation or fallout from weapons testing in evaluating any radiological impact Davis-Besse has on the surrounding envi-ronment. Data from indicator and control locations are also compared with pre-operational data to determine whether significant variations or trends exist.

Since 1987 the REMP has been reviewed and modified to develop a comprehensive sampling program adjusted to the current needs of the utility. Modifications have included additions of sampling locations above the minimum amount required in the ODCM and increasing the num-ber of analyses performed on each sample. In addition to adding new locations, duplicate or Quality Control (QC) sample collection is performed to verify the accuracy of the lab analyzing the environmental samples. These additional samples are referred to as the REMP Enhancement Samples. Approximately 2,000 samples were collected and over 2,300 analyses were performed during 20 I 6. In addition, I 5% of the sampling locations were quality control sampling loca-tions. Table 3 shows the number of the sampling location and number collected for each type.

29

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 2: Sample Codes and Collection Frequencies Sample Type Airborne Particulate Airborne Iodine Thermo luminescent Dosimeter Milk Groundwater Broad leaf Vegetation Surface Water - Treated Surface Water -

Untreated Fish Shoreline Sediment Soil Fruit Sample Code AP AI TLD MIL WW BLY SWT swu FIS SEO SOI PRU 30 Collection Frequency Weekly Weekly Quarterly, Annually Monthly (semi-monthly during grazing season)

Quarterly (when available)

Monthly (when available)

Weekly Weekly Annually Semiannually Annually Annually

Davis-Besse Nuclear Power Station 2016 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 Atmos12heric Airborne Particulates C/W 10 530 0

Airborne Radioiodine C/W 10 530 0

Terrestrial Milk (Jan.-Dec.)

G/M 12 0

Groundwater GIQ**

3 8

0 Broad leaf Vegetation G/M 4

13 0

Fruit GIA 3

3 0

Soil GIA 10 10 0

Aquatic Treated Comp/WM 3

156 0

Surface Water G/WM(a) 1 52 0

Untreated G/WM(a) 3 156 0

Surface Water Comp/WM 3

156 0

Fish (2 species)

GIA 2

4 0

Shoreline Sediments G/SA 5

10 0

Direct Radiation Thermo luminescent C/Q(a) 88 351 l(b)

Dosimeters (TLD)

C/A(a) 88 88 0

• 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 (a) Includes quality control location. SWU and SWT QC included in weekly grab sample/composited monthly (b) Non-ODCM TLD missed sample 31

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Sample Analysis When environmental samples are analyzed, several types of measurements may be performed to provide information about the radionuclides present. The major analyses that are performed on environmental samples collected for the Davis-Besse REMP include:

Gross beta analysis measures the total amount of beta emitting radioactive material present in a sample. Beta radiation may be released by many different radionuclides. Since beta decay gives a continuous energy spectrum rather than the discrete lines or "peaks" associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal concentra-tions of beta emitting radionuclides; it does not identify specific radionuclides. Gross beta anal-ysis merely acts as a tool to identify samples that may require further analysis.

Gamma spectral analysis provides more specific information than gross beta analysis. Gamma spectral analysis identifies each gamma emitting radionuclide present in the sample, and the amount of each nuclide present. Each radionuclide has a very specific "fingerprint" that allows for swift and accurate identification. For example, gamma spectral analysis can be used to iden-tify the presence and amount of Iodine-131 in a sample. Iodine-131 is a man-made radioactive isotope of Iodine that may be present in the environment as a result of fallout from nuclear weapons testing, routine medical uses in diagnostic tests, and routine releases from nuclear pow-er stations.

Tritium analysis indicates whether a sample contains the radionuclide tritium (H-3) and the amount present. As discussed in the Introduction section, tritium is an isotope of Hydrogen that emits low energy beta particles.

Strontium analysis identifies the presence and amount of Strontium-89 and Strontium-90 in a sample. These man-made radionuclides are found in the environment as a result of fallout from nuclear weapons testing. Strontium is usually incorporated into the pool of the biosphere. In other words, it accumulates in living organisms, where it is stored in the bone tissue. The princi-pal Strontium exposure pathway is via milk produced by cattle grazed on pastures exposed to deposition from airborne releases.

Gamma Doses measured by thermoluminescent dosimeters while in the field are determined by a special laboratory procedure. Table 4 provides a list of the analyses performed on 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 as less than LLD (<LLD), it means that the radioactivity is so low that it cannot be accurately measured with any degree of confidence by a particular method for an individual analysis.

32

Davis-Besse Nuclear Power Station 2016 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-I 31 Gamma Spectroscopy Iodine-I 31 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 20 16 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 earlier years. Generally, the results of sample analyses are compared with pre-operational and operational data. Additionally, the results of indicator and control locations are also com-pared. This allows REMP personnel to track and trend the radionuclides present in the environ-ment, 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 de-tected, it is investigated to determine whether it is attributable to the operation of Davis-Besse, or to some other source such as nuclear weapons testing.

34

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Atmospheric Monitoring Airborne Particulates: No radioactive particulates have been detected as a result of Davis-Besse's operation. Only natural and fallout radioactivity from nuclear weapons 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. The lodine-1 31 concentrations detected at control and indicator locations during 2016 were similar.

Terrestrial Monitoring:

Groundwater: Tritium was not detected above the lower limit of detection dur-ing 2016 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 Fuku-shima Daiichi Nuclear Station disaster in 2011. No Jodine-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. One tritium sample indicated 363 pCi/L in REMP Sur-face Water during 2016. This is slightly greater than the <330 pCi/L detection limit.

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 2016 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Thermoluminescent Dosimeters (TLDs): The annual gamma TLD dose rates for the current reporting period averaged 54.3 millirem/year at Indicator locations, and 62.4 millirem/year at Control locations. No increase above natural background radiation at-tributable to the operation of Davis-Besse has been observed.

2016 Program Anomalies In late 2015, elevated Gross Beta resu Its at the T-1 1 Ottawa County Regional Water Intake Fa-ci lity was identified and documented in the 2015 Davis-Besse Annual Radiological Environmen-tal Operating Report. This was not attributed to power plant operations as indicated by T-3 Site Boundary, near the mouth of the Toussaint River into Lake Erie sample point, indicating normal gross beta results. The elevated results at T-11 were attributed to potassium. This potassium was likely due to fertilizer runoff into the mouth of the Portage River which is located near the T-11 sample point. The elevated trend continued through April 2016 before sharply declining back to typical values(< 3 pCi/L) for the remainder of the year. Gross Beta is not a reportable radioac-tivity concentration per the ODCM. All ODCM-required REMP samples were collected.

Abnormal Releases There were no abnormal liquid or gaseous releases occurring during 2016.

Atmospheric Monitoring Air Samples Environmental air sampling is conducted to detect any increase in the concentration of airborne radionuclides that may be inhaled by humans or serve as an external radiation source. Inhaled radionuclides may be absorbed from the lungs, gastrointestinal tract, or from the skin. Air sam-ples collected by the Davis-Besse REMP include airborne particulate and airborne radioiodine.

Samples are collected weekly with low volume vacuum pumps, which draw a continuous sample through a glass fiber filter and charcoal cartridge at a rate of approximately one cubic foot per minute. Airborne particulate samples are collected on 47 mm diameter filters. Charcoal car-tridges are installed downstream of the particulate filters to sample for the airborne radio iodine.

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 re-ceipt by the contract laboratory.

36

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Airborne Particulate Davis-Besse has ten continuous air samplers that monitor for air particulate and iodine. There are six indicator locations including four around the site boundary (T-1, T-2, T-3, and T-4), one at Sand Beach (T-7), and another at a local farm (T-8). There are four control locations, Oak Harbor (T-9), Port Clinton (T-11 ), Toledo (T-12) and Crane Creek (T-27). Gross beta analysis is performed on each of the weekly samples.

Each quarter, the filters from each location are combined (composite) and analyzed for gamma-emitting radionuclides, Strontium-89 and Strontium-90. Beta-emitting radionuclides were de-tected at an average concentration of 0.026 pCi/m3 at indicator locations and 0.027 pCi/m3 at control locations. Beryllium-7 was the only gamma-emitting radionuclide detected by the gam-ma spectroscopic analysis of the quarterly composites.

Beryllium-7 is a naturally-occurring radionuclide produced in the upper atmosphere by cosmic radiation. No other gamma-emitting radionuclides were detected above their respective LLDs.

Strontium-89 and Strontium-90 were not detected above their LLDs. These results show no ad-verse change in radioactivity in air samples attributable to the operation of the Davis-Besse Nu-clear Power Station in 2016.

37

M E 0

Q.

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report 2016 Airborne Gross Beta

-+-Control Indicator 0.035 0.03 0.025 0.02 O.Q15 O.Q1 0.005 Jan.

Feb.

Mar.

April May June July Aug.

Sept.

Oct.

Nov.

Dec.

Month Figure 10: Concentrations of beta-emitting radionuclides in airborne particulate samples were nearly identical at indicator and control locations during 2016.

Airborne Iodine-131 Airborne Iodine-131 samples are collected at the same ten locations as the airborne particulate samples. Charcoal cartridges are placed downstream of the particulate filters. These cartridges are collected weekly, sealed in separate collection bags and sent to the laboratory for gamma analysis.

38

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 5: Air Monitoring Locations Sample Location Type of Number Location Location Description T-1

• Site boundary, 0.6 miles ENE of Station T-2*

1 Site boundary, 0.9 miles E of Station T-3*

1 Site boundary, 1.4 miles ESE of Station T-4 1

Site boundary, 0.8 miles S of Station T-7*

Sand Beach, main entrance, 0.9 miles NW of Station T-8 Earl Moore Farm, 2.7 miles WSW of Station T-9 c

Oak Harbor Substation, 6.8 miles SW of Station T-11

• c Port Clinton Water Treatment Plant, 9.5 miles SE of Station T-12 c

Toledo Water Treatment Plant, 20.7 miles WNW of Station T-27 c

Crane Creek, 5.3 miles WNW of Station I= Indicator C = Control

• denotes ODCM-required sample 39

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Davis-Besse Nuclear Power Station 2016 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 sam-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 Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere Cesium-137, a manmade radionuclide which has been deposited in the environment, (for example, in surface soils) as a result of fallout from nu-clear weapons testing and routine releases from nuclear facilities Potassium-40, a naturally occurring radionuclide normally found throughout the environment (including in the human body)

Fallout radionuclides from nuclear weapons testing, including Stronti-um-89, Stronti um-90, Cesium-13 7, Cerium-141, Cerium-144, and Ruthe-nium-I 06. These radionuclides may also be released in minute amounts from nuclear facilities.

The radionuclides listed above are expected to be present in many of the environmental samples collected in the vicinity of the Davis-Besse Station. The contribution of radionuclides from the operation of Davis-Besse is assessed by comparing sample results with pre-operational data, op-erational data from previous years, control location data, and the types and amounts of radioac-tivity normally released from the Station in liquid and gaseous effluents.

Milk Samples Milk sampling is a valuable tool in environmental surveillance because it provides a direct basis for assessing the buildup of radionuclides in the environment that may be ingested by humans.

Milk is collected and analyzed because it is one of the few foods commonly consumed soon after production. The milk pathway involves the deposition of radionuclides from atmospheric releas-es onto forage consumed by cows. The radionuclides present in the forage-eating cow are incor-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

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report within five miles of the station, efforts will be made to include them in the milk sampling pro-gram as indicator sites.

The 2016 milk samples were analyzed for Strontium-89, Strontium-90, Iodine-131, other gam-ma-emitting radionuclides, stable Calcium and Potassium. A total of 12 milk samples were col-lected in 2016. Strontium-89 was not detected above its LLD of 0.6 pCi/I. The annual average concentration of Strontium-90 was 0.74 pCi/I. The annual average concentration was similar to those measured in previous years.

Iodine-131 was not detected in any of the milk sample above the LLD of 0.5 pCi/I. The concen-trations of Barium-140 and Cesium-1 37 were below their respective LLDs in all samples collect-ed.

Since the chemistries of Calcium and Strontium are similar, as are Potassium and Cesium, organ-isms tend to deposit Cesium radioisotopes in muscle tissue and Strontium radioisotopes in bones.

In order to detect the potential environmental accumulation of these radionuclides, the ratios of the Strontium radioactivity (pCi/I) to the concentration of Calcium (g/I), and the Cesium radioac-tivity (pCi/I) compared to the concentration of Potassium (g/I) were monitored in milk. These ratios are compared to standard values to determine if buildup is occurring. No statistically sig-nificant variations in the ratios were observed.

Table 6: Milk Monitoring Location Sample Location 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 such as Ruthenium-I 06 have a potential to seep through the soil and could reach groundwater. Davis-Besse does not discharge its liquid effluents directly to the ground.

REMP personnel sample local wells on a quarterly basis to ensure early detection of any adverse impact on the local groundwater supplies due to Station operation. In addition, a quality control sample is collected when the wells are sampled. The groundwater samples are analyzed for beta-emitting radionuclides, tritium, Strontium-89, Strontium-90 and gamma-emitting radionuclides.

During the fall of 1998, the Carroll Township Water Plant began operation and offered residents a reliable, inexpensive source of high-quality drinking water. This facility has replaced all of the drinking water wells near Davis-Besse, as verified by the Ottawa County Health Department, and the indicator groundwater sampling was discontinued for a year. Since that time, two beach wells were located within five miles of the Station. Although the residents are seasonal and only 44

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report use the township system for their drinking water needs, these wells were added to our sampling program as Indicator locations. The gross beta averaged 1.8 pCi/I at Indicator sites and 2.5 pCi/I at the Control site, T-27A. REMP Groundwater samples were not affected by the operation of the Davis-Besse Nuclear Power Station.

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Year Figure 14: Shown above are the annual averages for gross beta in groundwater from 1982-2016. There were no indicator samples available in 2000 and no control samples available in 2009.

45

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report Table 7: Groundwater Monitoring Locations Sample Location Number T-27A Type of Location c

Location Description Crane Creek T-225 Long Beach and Park, 1.5 mi NW of Station T-226 Allen residence, 1.6 miles NW of Station C = control I = indicator Broadleaf Vegetation and Fruit Samples Fruits and broad leaf vegetation also represent a direct pathway to humans. Fruits and broad leaf vegetation may become contaminated by deposition of airborne radioactivity (nuclear weapons fallout or airborne releases from nuclear facilities), or from irrigation water drawn from lake wa-ter which receives liquid effluents (hospitals, nuclear facilities, etc.). Radionuclides from the soil may be absorbed by the roots of the plants and become incorporated into the edible portions.

During the growing season, edible broadleaf vegetation samples, such as kale and cabbage, are collected from gardens and farms in the vicinity of the Station. Fruit, typically apples, is collect-ed from orchards in the vicinity of Davis-Besse, and a control sample is collected, as well.

In 2016, broadleaf vegetation samples were collected at three indicator locations (T-17, T-19, and T-227) and one control location (T-37). Fruit samples were collected at two indicator loca-tions (T-8 and T-25) and one control location (T-209). Broadleaf vegetation was collected once per month during the growing season and consisted of cabbage. The fruit that was collected was apples. All samples were analyzed for gamma-emitting radionuclides, Strontium-89, Strontium-90, and Iodine-131.

Iodine-131 was not detected above the LLD of 0.058 pCi/g (wet) in any broadleafvegetation nor above the LLD of 0.047 pCi/g (wet) in fruit samples. The only gamma-emitting radionuclide detected in the fruit and broadleaf vegetation samples was Potassium-40, which is naturally oc-curring. Results of broadleaf vegetation and fruit samples were similar to results observed in previous years. Strontium-89 and Strontium-90 were not detected in any sample above their re-spective LLDs (0.006 and 0.005 pCi/I wet) in broad leaf vegetation samples at control and indica-tor locations. Strontium-89 and Strontium-90 were not detected in any sample above their respective LLDs (0.002 and 0.001 pCi/I wet) in fruit samples at control and indicator locations.

Operation of Davis-Besse had no observable adverse radiological effect on the surrounding envi-ronment in 2016.

46

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 8: Broadleaf Vegetation and Fruit Locations Sample Location Number T-8 T-17 T-19*

T-25 T-37*

T-209 T-227*

Type of Location I

I c

c I = indicator, C = control

• denotes ODCM-required sample Soil Samples Location Description Moore Farm, 2.7 miles WSW of Station (FRU)

D. Thompson, 1.82 mile SSE of station (BL V)

L. Bowyer Jr., 1.0 mile W of Station (BL V)

Witt Farm, 1.6 miles S of Station (FRU)

Bench Farm, 13.0 miles SW of Station (BLV)

Roving Control Fruit location (FRU)

B. Edge, 1.8 miles SSE of station (BL V)

Soil samples are generally collected once a year adjacent to our ten continuous air samplers. On-ly the top layer of soil is sampled in an effort to identify possible trends in the local environmen-tal nuclide concentration caused by atmospheric deposition of fallout and station-released radionuclides. Generally, the sites are relatively undisturbed, so that the sample will be repre-sentative of the actual deposition in the area. Ideally, there should be little or no vegetation pre-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 testing 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 2016. 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 ana-lyzed for gamma-emitting radionuclides. The only gamma emitter detected (in addition to natu-rally occurring Be-7 and K-40) was Cs-137.

Cs-137 was found in Indicator and Control locations at average concentrations of 0.07 pCi/g (dry) and 0.10 pCi/g (dry), respectively. The concentrations were similar to that observed in previous years.

47

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Cs-137 in Soil 1972-2016 1.2,----------;::==================::;-----------,

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N Year Figure 15: The concentration ofCesium-137 in soil has steadily declined in recent years. The peak seen in 1978 was due to fallout from nuclear weapons testing.

48

Davis-Besse Nuclear Power Station 20 I 6 Annual Radiological Environmental Operating Report Sample Location Type of Number Location T-1 I

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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 Substation, 6.8 miles SW of Station Port Clinton Water Treatment Plant, 9.5 miles SE of Station Toledo Water Treatment Plant, 20.7 miles WNW of Station Crane Creek, 5.3 miles WNW of Station 49

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Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Aquatic Monitoring Radionuclides may be present in Lake Erie from many sources including atmospheric deposition, run-off/soil erosion, and releases of radioactive material in liquid effluents from hospitals or nu-clear facilities. These sources provide two forms of potential exposure to radiation, external and internal. External exposure can occur from the surface of the water, shoreline sediments and from immersion (swimming) in the water. Internal exposure can occur from ingestion of radio-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 consump-tion. Radiochemical analysis of this processed water provides a direct basis for assessing the dose to humans from ingestion of drinking water.

Samples of treated surface water were collected from one indicator (T-22B) and two control lo-cations (T-11 and T-12). These locations include the water treatment facilities for Carroll Town-ship, Port Clinton and Toledo. Samples were collected weekly and composited monthly. The monthly composites were analyzed for beta-emitting radionuclides.

The samples were also composited in a quarterly sample and analyzed for Strontium-89, Strontium-90, gamma-emitting radionuclides, and tritium. One QC sample was collected each month from one of the three rou-tine sites on an alternating location basis.

53

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report The annual average of beta-emitting radionuclides for indicator and control locations was 2.8 and 3.1 pCi/I, respectively. These results are similar to previous years. Tritium was not detected above the LLD of 330 pCi/I during 2016. Strontium-89 was not detected above the LLD of 1.2 pCi/I. Strontium-90 activity was not detected above its LLD of 0. 7 pCi/I. These results are simi-lar to those of previous years and indicate no adverse impact on the environment resulting from the operation of Davis-Besse during 2016.

Each month, weekly quality control samples were collected at different locations. The results of the analyses from the quality control samples were within statistical agreement with the routine samples.

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N Year Figure 19: Since 1974, the annual concentrations of beta emitting radionuclides in treated surface water samples collected from indicator locations have been consistent with those from control locations. Davis-Besse has had no measurable radiological impact on treated surface water used to make drinking water.

54

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 10: Treated Surface Water Locations Sample Location Number T-11*

T-12 T-22B*

T-143 1 = indicator C = control QC = quality control Type of Location c

c QC

• denotes ODCM-required sample 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, sampled at Davis-Besse REMP Jab Quality Control Site 55

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Untreated Surface Water Sampling and analysis of untreated surface water provides a method of assessing the dose to hu-mans from external exposure from the lake surface as well as from immersion in the water. It also provides information on the radionuclides present, which may affect drinking water, fish, and irrigated crops.

Routine Program The routine program is the basic sampling program that is performed year round. Untreated wa-ter samples are collected from water intakes used by nearby water treatment plants. Routine samples are collected at Port Clinton, Toledo 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, triti-um, and gamma-emitting radionuclides. The samples are also composited quarterly and ana-lyzed for Strontium-89 and Strontium-90. One QC sample was collected each month from one of the three routine sites on an alternating location basis.

56

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Sample Results Each month, weekly composited quality control samples of untreated water were analyzed from different locations. For the routine untreated surface water samples that are composited weekly, the beta emitting radionuclides had an average concentration of 2.1 pCi/L at indicator locations during 2016. Control locations averaged 10.3 pCi/L during this period. The results of the T-11 control sample point located at the Ottawa County Regional Water Treatment Plant began show-ing elevated Gross Beta results in August of 2015 and continued through April of2016. As was discussed in the Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report, the elevated Gross Beta sample results were verified to be potassium by ICP analysis. The potassium may be attributed to fertilizer runoff into the Portage River. The Site Boundary, ESE of the station (directly up stream of T-11) did not indicate any anomalous Gross Beta results. This would conclude that the DBNPS is not the source of the elevated Gross Beta results at the Ottawa County facility. The maximum monthly Gross Beta concentration at T-11 after April 2016 was 2.7 pCi/L. Gross Beta in Untreated Surface Water is not a reportable radio-activity concentration per the Offsite Dose Calculation Manual.

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Davis-Besse Nuclear Power Station 2016 Annual Radiological 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 c

c I

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• denotes ODCM-required sample Location Description Site boundary, 1.4 miles ESE of Station Ottawa County Regional 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 Township Water Plant, State Route 2, 2.1 miles NW of Station Roving Quality Control Site 58

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Shoreline Sediment The sampling of shoreline sediments can provide an indication of the accumulation of insoluble radionuclides which could lead to internal exposure to humans through the ingestion of fish, through re-suspension into drinking water supplies, or as an external radiation source from shoreline exposure to fishermen and swimmers.

Samples of deposited sediments in water along the shore were collected at various times from three indicator sites (T-3, T-4, and T-132) and one control location (T-27). Samples were ana-lyzed for gamma-emitting radionuclides. Naturally occurring Potassium-40 was detected at both control and indicator locations. These results are similar to previous years.

Table 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 miles S of Station Crane Creek, 5.3 miles WNW of Station Lake Erie, 1.0 miles E of Station 59

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Fish Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and second-arily to serve as indicators of radioactivity in the aquatic ecosystem. The principal nuclides that may be detected in fish include naturally-occurring Potassium-40, as well as Cesium-137, and Strontium-90. Depending upon the feeding habit of the species (e.g., bottom-feeder versus pred-ator), results from sample analyses may vary.

Davis-Besse collected two species of fish from sampling locations near the Station's liquid dis-charge point and more than ten miles away from the Station where fish populations would not be expected to be impacted by the Station operation. Walleye are collected because of being a pop-ular recreational fish and white perch and white bass are collected because their importance as a commercial fish.

The average concentration of beta-emitting radionuclides in ODCM-required fish was similar for indicator and control locations (3.47 pCi/g and 2.73 pCi/g wet weight, respectively). No gamma emitters were detected above their respective LLDs.

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N Figure 21: Average concentrations of beta-emitting radionuclides (pCi/gram) in fish samples were similar at indicator and control locations, and were comparable to results of previous years.

60

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 13: Fish Locations Sample Location Number T-33*

T-35*

Type of Location I

c I = indicator C= control

• Denotes ODCM-required sample Location Description Lake Erie, within 5 miles radius of Station Lake Erie, greater than 10 mile radius of Station 61

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Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Thermoluminescent Dosimeters Radionuclides present in the air and deposited on the ground may directly irradiate individuals.

Direct radiation levels at and around Davis-Besse are constantly monitored by thermo-luminescent dosimeters (TLDs). TLDs are small devices which store radiation dose information.

The TLDs used at Davis-Besse contain a Sulfate:Dysprosium (CaS04:Dy) card with four main readout areas. Multiple readout areas are used to ensure the precision of the measurements.

Thermoluminescence is a process in which ionizing radiation interacts with phosphor, which is the sensitive material in the TLD. Energy is trapped in the TLD material and can be stored for several months or years. This provides an excellent method to measure the dose received over long periods of time. The energy that was stored in the TLD as a result of interaction with radia-tion is released and measured by a controlled heating process in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy in the form of light. The amount of light detected is directly proportional to the amount of radiation to which the TLD was exposed.

The reading process re-zeroes the TLD and prepares it for reuse.

TLD Collection Davis-Besse has 88 TLD locations (77 indicator and 11 control locations). TLDs are collected and replaced on a quarterly and annual basis. Nineteen QC TLDs are also collected on this schedule. There are a total of 381 TLDs in the environment surrounding Davis-Besse. By col-lecting them on a quarterly and annual basis from a single site, each measurement serves as a quality control check on the other. All ODCM quarterly and annual TLDs placed in the field were retrieved and evaluated during the current reporting period.

In 2016, the average dose equivalent for quarterly TLDs at indicator locations was 15.I mrem/91 days, and for control locations was 17.9 mrern/91 days. The average dose equiva-lent for annual TLDs in 2016 was 54.3 mrem/366 days at indicator locations and 62.4 mrem/366 days for control locations.

Quality Control TLDs Duplicate TLDs have been placed at 18 sites. These TLDs are placed in the field at the same time and location as some of the routine TLDs, but are assigned quality control site numbers.

This allows us to take several measurements at the location without the laboratory being aware that they are the same. A comparison of the quality control and routine results provides a meth-od to check the accuracy of the measurements. The average dose equivalent of indicator quality control TLDs averaged 14.0 mrern/91 days while the quality control TLDs at control locations yielded an average dose equivalent of 17.7 mrem/91 days.

65

Davis-Besse Nuclear Power Station 201 6 Annual Radiological Environmental Operating Report Direct Radiation Monitoring Ill >-

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66

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations Sample Location Type of Number Location T-1

• I T-2*

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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 Ottawa County Regional 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 2016 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Number T-43 T-44 T-45 T-46*

T-47*

T-48*

T-49 T-50*

T-51 T-52*

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T-55*

T-60 T-62 T-65 T-66 T-67*

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T-69 Type of Location c

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Location Description Site boundary, 0.5 miles SW of Station Site boundary, 0.5 miles WSW of Station Site boundary, 0.5 miles WNW of Station Site boundary, 0.5 miles NW of Station Site boundary, 0.5 miles N of Station Site boundary, 0.5 miles NE of Station Site boundary, 0.5 miles NE of Station Erie Industrial Park, Port Clinton, 4.5 miles SE of Station Siren Pole, 5.5 miles SSE of Station Miller Farm, 3.7 miles S of Station Nixon Farm, 4.5 miles S of Station McNutt residence, 4.8 miles SW of Station King Farm, 4.5 miles W of Station Site boundary, 0.3 miles S of Station Site boundary, 1.0 mile SE of Station Site boundary, 0.3 miles E of Station Site boundary, 0.3 miles ENE of Station Site boundary, 0.3 miles NNW of Station Site boundary, 0.5 miles WNW of Station Site boundary, 0.4 miles W of Station 68

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Number T-71 T-73 T-74 T-75 T-76 T-80 T-81 T-82 T-83 T-84 T-85 T-86 T-88 T-87 T-89 T-90 T-91

• T-92 T-93 T-94 T-95 Type of Location I

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c Location Description Site boundary, 0.1 mile NNW of Station Site boundary, 0.1 mile WSW of Station Site boundary, 0.1 mile SSW of Station Site boundary, 0.2 mile SSE of Station Site boundary, 0.1 mile SE of Station Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control in lead pig DBAB Annex Quality Control Site Site Personnel Processing Facility State Route 2 and Rankie Road, 2.5 miles SSE Locust Point Road, 2.7 miles WNW of Station Twelfth Street, Sand Beach, 0.6 miles NNE of Station State Route 2, 1.8 miles WNW of Station State Route 579, 9.3 miles W of Station 69

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

Sample Location Number T-100 T-111 T-112*

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I Location Description Ottawa County Highway Garage, Oak Harbor, 6.0 miles S of Station Toussaint North Road, 8.3 miles WSW of Station Thompson Road, 1.5 miles SSW of Station Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site Quality Control Site State Route 19, 2.0 miles W of Station Duff Washa and Humphrey Road, 1.7 miles W of Station Zetzer Road, 1.6 miles WSW of Station 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 Camp Perry Western and Rymers Road, 4.0 miles SSE of Station 70

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

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

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c QC I

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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 2016 Annual Radiological Environmental Operating Report Table 14: Thermoluminescent Dosimeter Locations (continued)

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Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Conclusion The Radiological Environmental Monitoring Program at Davis-Besse is conducted to determine the radiological impact, if any, of the Station's operation on the environment. Radionuclide con-centrations measured at indicator locations were compared with concentrations measured at con-trol locations in previous operational studies and in the pre-operational surveillance program.

These comparisons indicate normal concentrations of radioactivity in all environmental samples collected in 2016. Davis-Besse's operation in 2016 indicated no adverse radiological impact on the residents and environment surrounding the station. The results of the sample analyses per-formed during the period of January through December 2016 are summarized in Appendix C of this report.

References

1. "Cesium-137 from the Environment to Man: Metabolism and Dose," Report No. 52, National Council on Radiation Protection and Measurement, Washington, D.C. (January 1977).

2. "Environmental Radiation Measurements," Report No. 50, National Council on Radiation Protection and Measurement, Washington, D.C. (December 1976).

3. "Exposure of the Population in the United States and Canada from Natural Background Ra-diation," Report No. 94, National Council on Radiation Protection and Measurement, Wash-ington, D.C. (December 1987).

4. "A Guide for Environmental Radiological Surveillance at U.S. Department of Energy Instal-lations," DOE/EP-0023, Department of Energy, Washington, D.C. (July 1981 ).

5. "Ionizing Radiation Exposure of the Population of the United States," Report No. 93, Na-tional Council on Radiation Protection and Measurement, Washington, D.C. (September 1987).

6. "Natural Background Radiation in the United States," Report No. 45, National Council on Radiation Protection and Measurement, Washington, D.C. (November 1975).

7. "Numerical Guides for Design Objectives and Limiting Conditions for Operation to meet the Criterion 'As Low As Reasonably Achievable' for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents," Code of Federal Regulations, Title 10 Energy, Part 50 "Domestic Licensing of Production and Utilization Facilities," Appendix 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. (De-cember 1987).

76

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report I 0. "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 Thermo-luminescent 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. NUREG-0475, "Radiological Environmental Monitoring by NRC Licensees for Routine Op-erations of Nuclear Facilities," US NRC (September 1978).

15. "Standards for Protection Against Radiation," Code of Federal Regulations, Title 10, Energy, Part 20 (1993).

16. Teledyne Isotopes Midwest Laboratory, "Operational Radiological Monitoring for the Davis-Besse Nuclear Power Station Unit No. I, 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 Moni-toring for the Davis-Besse Power Station Unit No. l," Oak Harbor, OH (1972-1977).

20. Toledo Edison Company, "Davis-Besse: Nuclear Energy for Northern Ohio."

21. Toledo Edison Company, Davis-Besse Nuclear Power Station, Unit No. 1, Radiological Ef-fluent Technical Specifications, Volume 1, Appendix A to License No. NPF-3. (Note - re-located to Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP),

Amendment 170, dated 3/9/92).

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 Mon-itoring Program," S-72N.

24. Davis-Besse Nuclear Power Station, "Radiological Environmental Monitoring Program,"

DB-CN-00015.

77

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report

25. Davis-Besse Nuclear Power Station, "Radiological Environmental Monitoring Quarterly, Semiannual, and Annual Sampling", DB-CN-03004.

26. Davis-Besse Nuclear Power Station, "Radiological Monitoring Weekly, Semimonthly, and Monthly Sampling," DB-CN-03005.

27. Davis-Besse Nuclear Power Station, "REMP Enhancement Sampling," DB-CN-10101.

28. Toledo Edison Company, "Updated Safety Analysis for the Offsite Radiological Monitoring Program," USAR 11.6, Revision 14, (1992).

29. Davis-Besse Nuclear Power Station, "Annual Radiological Environmental Operating Report Preparation and Submittal," DB-CN-00014.

30. Davis-Besse Nuclear Power Station, "Preparation of Radioactive Effluent Release Report,"

DB-CN-00012.

31. Davis-Besse Nuclear Power Station, "Offsite Dose Calculation Manual."

32. "Tritium in the Environment," Report No. 62, National Council on Radiation Protection and Measurements, Washington, D.C. (March 1979).

33. NEI 07-07, "Industry Ground Water Protection Initiative - Final Guidance Document,"

August, 2007.

34. "Groundwater Monitoring Well Installation & Monitoring Report Davis-Besse Nuclear Pow-er Station Oak Harbor, Ohio," Environmental Resources Management, March 18, 2008.

78

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2016 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 Reg-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 de-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 amounts of radioactive fission products and trace amounts of the component and structure surfaces, which have been activated, are present in the primary coolant water. The three types ofradioactive 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 to release.

Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primary coolant system. These liquids are collected through a series of floor and equip-ment drains and sumps. All liquids of this nature are monitored 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 and Xe-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive noble gases re-leased. They are readily dispersed in the atmosphere.

79

Davis-Besse Nuclear Power Station 2016 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 sys-tems, minimize their discharge. The predominant radioiodine released is Iodine-131 with a half-life of approximately eight days. The main contribution of radioactive Iodine to human dose is to the thyroid gland, where the body concentrates Iodine.

The principal radioactive particulates released are fission products (e.g., Cesium-134 and 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 efflu-ent and environmental programs, and procedures covering all aspects of effluent and environmen-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 is equipped with alarms and indicators in the control room. The alarm setpoints are low enough 80

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report 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 com-puters that record its data. Coupled with the effluent release data, the meteorological data are used to calculate the dose to the public. Beyond the plant, devices maintained in conjunction with the Radiological Environmental Monitoring Program continuously sample the air in the sur-rounding environment. Frequent samples of other environmental media, such as water and vege-tation, are taken to determine if buildup of deposited radioactive material has occurred in the area.

Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to 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 environ-ment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An annual aver-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 2016 Annual Radiological Environmental Operating Report Consumed By Animals II Qc:::::::J c

Diluted By AtmllSphere Airborne Relea~s Figure 29: The exposure pathways shown here are monitored through the Radiological Environmental Monitoring Program (REMP) and are considered when calculating doses to the public.

Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure route that will provide, for a specific radionu-clide, the greatest dose to a population, or to a specific group of the population called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, or other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ.

Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body exposure to ra-diation involves the exposure of all organs. Most background exposures are of this form. Both radioactive and non-radioactive elements can enter the body through inhalation or ingestion.

When they do, they are usually not evenly distributed. For example, Iodine concentrates in the thyroid gland, Cesium collects in muscle and liver tissue, and Strontium collects in the bone.

The total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the length of time that the radionuclide remains there. Some 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 20 16 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 path-ways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation, food consumption). The dose due to radioactive material released in liquid effluents is calculated 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, 2016.

Summation of the quantities of radioactive material released in gaseous and liquid efflu-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:

• l.06E-02 mrem, maximum individual whole body dose

• l. l lE-02 mrem, maximum individual significant organ dose (GI-LLI))

Gaseous Effluents:

Noble Gas:

• 4.76E-05 mrem, whole body

• 7.42E-05 mrad, skin Iodine - 131, Tritium, and Particulates with Half-l ives greater than 8 Days:

• 2.84E-02 mrem, whole body dose

• 2.84E-02 mrem, significant organ dose (lung)

Carbon-14:

2. l 3E-O 1 mrem, whole body l.03E+OO mrem, significant organ dose (bone)

These doses are a small fraction of the limits set by the NRC in the Davis-Besse ODCM. Addi-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 effluents, the additional pathways include the Turbine Building drains via the settling basins. Re-leases via these pathways are included in the normal release tables in this report.

83

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating 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 rnrem TEDE per year.

• Released at a rate such that the total dose to the skin will be less than or equal to 3000 mrem per year.

Iodine-I 3 I, 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 per year.

In accordance with I OCFR50, 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 IOCFR50, 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 2.61 Ci of C-14 in the form of C02 released from Davis-Besse through the Station Vent during 2016.

Liquid Effluents In accordance with 1 OCFR50, Appendix I, Sec llA, 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 rnrem 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 2016 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 l OCFR20, 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 l E-05 uCi/ml of air (submersion dose) con-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 gamma energies (E) for gaseous efflu-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 of Total Activity Fission and Activation Gases:

These gases, excluding tritium, are collected in Marinelli beakers specially modified for gas sam-pling, 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 quantifi-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. Quan-tification of each gamma-emitting radionuclide present in liquid samples is via gamma spectros-copy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system.

85

Davis-Besse Nuclear Power Station 20 16 Annual Radiological Environmental Operating Report Batch Releases Liquid from 111116 through 12/31/16

1. Number of batch releases:

2. Total time period for the batch releases:

3. Maximum time period for a batch release:

4. Minimum time period for a batch release:

5. Average time period for a batch release:

Gaseous from 111/16 through 12/31/16 I. 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 91 152.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 176 minutes 78 minutes 101.8 minutes 16 437.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 198.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 205 minutes There were no abnormal gaseous releases of radioactivity from the station during 2016.

There were no abnormal liquid releases of radioactivity from the station during 2016.

Percent of ODCM Release Limits The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent of limits, for January I, 2016 through December 31, 2016.

PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January I, 2016-December 31, 2016 faaseous Noble gases (gamma) 4.33E-05 mrad 10 rnrad 4.33E-04 Noble gases (beta) 7.42E-05 mrad 20 mrad 3.71E-04 1-131, tritium and particulates 2.84E-02 mrem 15 mrem l.89E-Ol C-14 9.36E-Ol rnrem 20 rnrem 4.68E+OO Report Period: January 1, 2016 - December 31, 2016 (liquid)

Total body l.06E-02 mrem 3 rnrem 3.53E-Ol Organ (GILLI) 1.1 lE-02 mrem 10 mrem l.l lE-01 Sources of Input Data

• Water Usage: Survey of Water Treatment Plants (DSR-95-00347)

• 0-50 mile meat, milk, vegetable production, and population data was taken from 1982 Annual Environmental Operating Report entitled, "Evaluation of Compliance with Appendix I to 1 OCFR50: Updated Population, Agricultural, Meat - Animal, and Milk Production Data Tables for 1982". This evaluation was based on the 1980 86

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Census, the Agricultural Ministry of Ontario 1980 report entitled "Agricultural Sta-tistics and Livestock Marketing Account", the Agricultural Ministry of Ontario re-port entitled "Agricultural Statistics for Ontario, Publication 21, 1980," the Michi-gan Department of Agriculture report entitled "Michigan Agricultural Statistics, 1981 ", and the Ohio Crop Reporting Service report entitled "Ohio Agricultural Sta-tistics, 1981 ".

• Gaseous and liquid source terms: Tables 15 through 19 of this report.

• Location of the nearest individuals and pathways by sector within 5 miles, see Land Use Census Section of the report.

• Population of the 50-mile Radius of Davis-Besse (DSR-95-00398).

Dose to Public Due to Activities Inside the Site Boundary In accordance with ODCM Section 7.2, the Radioactive Effluent Release Report includes an as-sessment of radiation doses from radioactivity released in liquid and gaseous effluents to members of the public from activities inside the site boundary.

The Pavilion and Training Center pond are accessible to employees and their families. The Pavil-ion may be accessible to the public for certain social activities. The Training Center pond allows employees and their families to periodically 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 purposes of assessing the dose to members of the public in accordance with ODCM Section 7.2, the following exposure assumptions are used:

Exposure time for maximally-exposed visitors is 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> (1 hr/day, 5 day/ week, 50 wk/yr)

Annual average meteorological dispersion (conservative, default use of maximum site boundary dispersion).

For direct "shine" from the Independent Spent Fuel Storage Installation (ISFSI), 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. There-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 1 OCFR20.

87

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Inoperable Radioactive Effluent Monitoring Equipment Waste Gas System Discharge Radiation Element RE 18228 was out of service from September 20 through December 31, 2016. Following a Waste Gas release, RE1822B indicator was found to be failed to zero counts (O.OOEO). Troubleshooting attempts in late 2016 did not successfully identify the cause or extent of the failure. ODCM requirements for REI 822B were fulfilled by a redundant monitor during this period. No compensatory samples were required.

Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP)

The ODCM was revised in April 2016 to incorporate the latest Land Use Census information.

There were no changes to the Process Control Program during 2016.

Borated Water Storage Tank Radionuclide Concentrations During the reporting period of 2016, 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 I.

88

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 15 Gaseous Effluents - Summation of All Releases Nuclide Fission and Activation Gases Total Release Average Release Rate for Period Percent of applicable limits Iodines Total Iodines (l-131)

Average Release Rate for Period Percent of applicable limits Particulates Particulates with half-lives greater than 8 days Average Release Rate for Period Percent of applicable limits Gross Alpha Activity Tritium Total Release Average Release Rate for Period Percent of applicable limits Carbon-14 Total Release Unit Ci uCilsec NIA Ci uCilsec NIA Ci uCilsec NIA Ci Ci uCilsec NIA Ci 1st Qtr 2016 6.0SE-02 6.76E-03 O.OOE+OO NIA O.OOE+OO NIA O.OOE+OO l.06E+OI l.19E+OO 8.23E-01 2nd Qtr 2016 l.68E-03 7.66E-05 O.OOE+OO NIA 2.81E-05 l.28E-06 O.OOE+OO l.91E+Ol 8.75E-01

5. l 7E-01 3rd Qtr 2016 4.92E-02 2.24E-03 O.OOE+OO NIA 8.43E-05 3.84E-06 O.OOE+OO l.24E+Ol 5.64E-01 l.07E+OO Est.

4th Qtr Total%

2016 Error O.OOE+OO 2.5E+Ol NIA 0.00E+OO 2.SE+Ol NIA 4.49E-06 2.5E+Ol 5.71E-07 0.00E+OO 2.5E+Ol l.09E+OI 2.5E+Ol J.39E+OO l.07E+OO Note: The average release rate is taken over the entire quarter, not over the time the time period of the releases.

89

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 16 Gaseous Effluents - Ground Level Releases - Batch Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2016 2016 2016 2016 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 1-131 Ci

<LLD

<LLD

<LLD

<LLD 1-133 Ci

<LLD

<LLD

<LLD

<LLD 1-135 Ci

<LLD

<LLD

<LLD

<LLD Total for Period:

NIA NIA NIA NIA Particulates and Tritium H-3 Ci 6.86E-02 1.49E-04 6.27E-03 7.02E-04 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:

6.86E-02 1.49E-04 6.27E-03 7.02E-04 90

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 16 (Continued)

Gaseous Effluents - Ground Level Releases Continuous Mode lst Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2016 2016 2016 2016 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 1-131 Ci

<LLD

<LLD

<LLD

<LLD 1-133 Ci

<LLD

<LLD

<LLD

<LLD l-135 Ci

<LLD

<LLD

<LLD

<LLD Total for Period:

NIA NIA NIA NIA Particulates and Tritium H-3 Ci 1.32E-03 6.49E-04 5.63E-03 2.95E-03 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:

1.32E-03 6.49E-04 5.63E-03 2.95E-03 91

Davis-Besse Nuclear Power Station 2016 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.62E-06

µCi /ml Kr-85m

<7.26E-09

µCi/ml Kr-87

<1.80E-08

µCi/ml Kr-88

<l.86E-08

µCi/ml Xe-133

<l.50E-08

µCi/ml Xe-133m

<4.49E-08

µCi/ml Xe-135

<5.83E-09

µCi /ml Xe-135m

<6.06E-08

µCi/ml Xe-138

<6.59E-07

µCi/ml 1-131

<6.94E-15

µCi/ml 1-133

<l.03E-14

µCi/ml 1-135

<2.30E-14

µCi/ml Cs-134

<6.60E-15

µCi/ml Cs-137

<l.78E-14

µCi/ml Ba-140

<2.29E-14

µCi /ml La-140

<l.93E-14

µCi /ml Sr-89

<l.50E-15

µCi/ml Sr-90

<5.80E-16

µCi/ml Mn-54

<9.06E-15

µCi/ml Fe-59

<3.16E-14

µCi/ml Co-58

<l.16E-14

µCi/ml Co-60

<1.88E-14

µCi/ml Zn-65

<2.44E-14

µCi/ml Mo-99

<6.37E-14

µCi /ml Ce-141

<l.30E-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 2016 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-I 3 I Ci I-133 Ci 1-135 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 2016 2016 2.57E-02

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 4.28E-05

<LLD 3.37E-02 I.68E-03

<LLD

<LLD l.02E-03

<LLD

<LLD

<LLD

<LLD

<LLD 6.05E-02 1.68E-03

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD O.OOE+OO O.OOE+OO 3.49E-02 8.38E-03

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 3.49E-02 8.38E-03 3rd Qtr 2016

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 4.86E-02

<LLD 5.92E-04

<LLD

<LLD 4.92E-02

<LLD

<LLD

<LLD O.OOE+OO 8.21E-01

<LLD

<LLD

<LLD

<LLD

<LLD 8.21E-Ol 4th Qtr 2016

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 0.00+00

<LLD

<LLD

<LLD O.OOE+OO 4.97E-04

<LLD

<LLD

<LLD

<LLD

<LLD 4.97E-04

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 17 (Continued)

Gaseous Effluents - Mixed Mode Releases - Continuous Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2016 2016 2016 2016 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-1 35m Ci

<LLD

<LLD

<LLD

<LLD Xe-1 38 Ci

<LLD

<LLD

<LLD

<LLD Total for Period:

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines I-131 Ci

<LLD

<LLD

<LLD

<LLD 1-132 Ci

<LLD

<LLD

<LLD

<LLD I-133 Ci

<LLD

<LLD

<LLD

<LLD 1-135 Ci

<LLD

<LLD

<LLD

<LLD Total for Period:

0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO Particulates, Tritium Na-24 Ci

<LLD

<LLD l.98E-05

<LLD Co-57 Ci

<LLD 5.50E-06

<LLD

<LLD Co-58 Ci

<LLD 2.26E-05 5.76E-06 7.28E-07 Sr-89 Ci

<LLD

<LLD

<LLD

<LLD Sr-90 Ci

<LLD

<LLD

<LLD

<LLD Sb-124 Ci

<LLD

<LLD 5.87E-05 3.76E-06 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 l.06E+Ol I.91E+Ol l.15E+01 I.09E+01 Total for Period Ci l.06E+Ol l.91E+OI l.15E+Ol l.09E+OI Carbon-14 Ci 8.23E-Ol 5.17E-Ol I.07E+OO I.07E+OO 94

Davis-Besse Nuclear Power Station 20 I 6 Annual Radiological Environmental Operating Report Table 17 (Continued)

LLDs for Gaseous Effluents - Mixed Mode Releases Continuous Mode" Batch Mode" Kr-85

<l.63E-06

µCi/ml Ar-41

<2.26E-06 Kr-85m

<6.74E-09

µCi/ml Kr-85m

<8.93E-07 Kr-87

<l.80E-08

µCi /ml Kr-87

<2.45E-06 Kr-88

<l.86E-08

µCi /ml Kr-88

<3.55E-06 Xe-133

<l.50E-08

µCi/ml Xe-133

<l.61E-06 Xe-133m

<4.49E-08

µCi/ml Xe-133m

<6.38E-06 Xe-135

<5.83E-09

µCi/ml Xe-135

<6.72E-07 Xe-135m

<2.13E-07

µCi/ml Xe-135m

<1.48E-05 Xe-138

<6.59E-07

µCi/ml Xe-138

<3.37E-05 1-1 31

<6.94E-15

µCi/ml I-131

<8.38E-07 I-I 33

<l.03E-14

µCi/ml 1-133

<7.36E-07 1-135

<2.30E-14

µCi/ml 1-135

<l.25E-06 Cs-134

<6.60E-15

µCi/ml Sr-89

<1.50E-15 Cs-137

<l.78E-14

µCi/ml Sr-90

<5.80E-16 Ba-140

<2.29E-14

µCi/ml Cs-134

<l.02E-06 La-140

<l.93E-14

µCi/ml Cs-137

<8.60E-07 Sr-89

<1.50E-15

µCi/ml Ba-140

<3.00E-06 Sr-90

<5.80E-16 uCi/ml La-140

<l.15E-06 Mn-54

<9.06E-14

µCi/ml Fe-59

<3.16E-14

µCi/ml Co-58

<l.16E-14

µCi/ml Co-60

<l.88E-14

µCi/ml Zn-65

<2.44E-14

µCi/ml Mo-99

<6.37E-14

µCi/ml Ce-141

<l.30E-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 20 I 6 Annual Radiological Environmental Operating Report Table 18 Liquid Effluents - Summation of All Releases Type Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total 2016 2016 2016 2016

% Error Fission and Activation Products Total Release (without Tritium, Ci 1.39E-03 3.13E-02 2.88E-03 3.44E-03 2.0E+Ol Gases, Alpha)

Average Di I uted Concentration

µCi/ml

l. l 8E-10 2.76E-09 2.37E-10 2.87E-10 During Period*

Percent of 1 OCFR20 Limit 1.44E-03 1.44E-02 1.71 E-03 2.87E-03 Tritium Total Release Ci 1.45E+02 2.51E+01 5.03E+01 l.78E+03 2.0E+Ol Average Diluted Concentration

µCi/ml 1.23E-05 2.21E-06 4.14E-06 l.49E-04 During Period*

Percent of 1 OCFR20 Limit 1.23E+OO 2.21E-OI 4.14E-OI l.49E+OI Dissolved and Entrained Gases Total Release Ci 4.96E-04 6.98E-06 O.OOE+OO O.OOE+OO 2.0E+Ol Average Diluted Concentration

µCi/ml 4.21E-l l 6.17E-13 O.OOE+OO O.OOE+OO During Period*

Percent of I OCFR20 Limit 2.l IE-05 3.08E-07 O.OOE+OO O.OOE+OO Gross Al~ba 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 9.IOE+05 7.79E+05 3.61E+05 5.02E+05 2.0E+Ol Continuous liter l.37E+08 4.02E+07 7.02E+07 l.08E+08 2.0E+OI Volume of Dilution Water Batch liter 2.85E+08 2.43E+08 l.28E+08 l.91E+08 2.0E+OI Continuous liter 1.14E+IO l.IOE+IO l.20E+ IO

l. l 7E+IO 2.0E+Ol Total Volume of Water Released liter l.18E+IO l.13E+IO 1.22E+IO l.20E+ IO

• Tritium and alpha may be found in both continuous and batch releases. Average diluted concentrations are based on total volume of water released during the quarter. Fission and Activation products and Dissolved and Entrained Gases are nor-mally only detected in batch releases.

96

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 19 Liquid Effluents - Nuclides Released in Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2016 2016 2016 2016 Fission and Activation Products Na-24 Ci

<LLD I.89E-05

<LLD 1.74E-06 Cr-51 Ci

<LLD l.47E-04 9.26E-06 3.82E-05 Mn-54 Ci 6.90E-07 2.61E-05 2.23E-06 2.50E-06 Fe-55b Ci

<LLD l.40E-03

<LLD

<LLD Co-57 Ci 3.43E-06 7.44E-05 l.l 6E-05 l.24E-06 Co-58 Ci 1.01 E-03 2.0lE-02 2.01 E-03 l.61E-03 Fe-59 Ci

<LLD

<LLD

<LLD

<LLD Co-60 Ci 1.21 E-04 5.72E-04 9.43E-05 3.58E-05 Ni-63 Ci O.OOE+OO 6.31E-03 4.34E-04 O.OOE+OO 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 7.48E-07

<LLD Nb-95 Ci 1.34E-06 1.09E-05 l.08E-06 1.88E-06 Zr-95 Ci 1.63E-06 1.94E-06

<LLD

<LLD Nb-97 Ci 1.67E-06

<LLD 7.67E-07 1.83E-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 3.27E-05 6.92E-05 5.12E-05 3.05E-06 Sb-122 Ci 6.71E-07 6.32E-05

3. 1 OE-05 5.81E-06 Te-123M Ci

<LLD 9.61E-05 l.29E-06 8.85E-06 Sb-124 Ci

<LLD 2.25E-05 7.37E-06 3.67E-05 Sb-125 Ci 3.25E-05 5.24E-05 2.52E-06 4.84E-05 I-131 Ci

<LLD

<LLD

<LLD

<LLD 1-132 Ci

<LLD

<LLD

<LLD

<LLD Te-132 Ci

<LLD 1.19E-06

<LLD

<LLD Cs-134 Ci

<LLD

<LLD

<LLD

<LLD Cs-137 Ci 5.45E-05 2.48E-06 3.03E-05 9.98E-06 Cs-138 Ci

<LLD 3.35E-05

<LLD

<LLD 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 l.39E-03 3.13E-02 2.88E-03 3.44E-03 97

Davis-Besse Nuclear Power Station 20 I 6 Annual Radiological Environmental Operating Report Table 19 (continued)

Liquid Effluents - Nuclides Released In Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2016 2016 2016 2016 H-3 Ci l.45E+02 2.51 E+02 5.03E+Ol 1.27E+02 Dissolved and Entrained Gases Kr-85 Ci

<LLD

<LLD

<LLD

<LLD Xe-1 31m Ci

<LLD

<LLD

<LLD

<LLD Xe-1 33 Ci 4.94E-04 6.98E-06

<LLD

<LLD Xe-133m Ci

<LLD

<LLD

<LLD

<LLD Xe-1 35 Ci l.75E-06

<LLD

<LLD

<LLD Total for Period:

Ci 4.96E-04 6.98E-06 O.OOE+OO O.OOE+OO 98

Davis-Besse Nuclear Power Station 2016 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 Sr-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 Releases 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 2016 2016 2016 2016

<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 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

<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 2016 Annual Radiological Environmental Operating Report Table 19 (continued)

Liquid Effluents - LLDs for Nuclides Releaseda Cr-51

<8.0lE-07

µCi/ml Ar-41

<l.07E-08

µCi/ml Mn-54

<9.72E-09

µCi/ml 1-131

<l.07E-08

µCi/ml Fe-55b

<6.00E-07

µCi/ml Xe-131m

<4.0JE-07

µCi/ml Co-57

<9.02E-09

µCi/ml Xe-133

<2.42E-08

µCi/ml Co-58

<7.35E-09

µCi/ml Xe-133m

<6. l lE-08

µCi/ml Fe-59

<2.22E-08

µCi/ml Cs-134

< l.83E-09

µCi/ml Co-60

<1.15E-08

µCi/ml Xe-135

<9.66E-09

µCi/ml Zn-65

<1.53E-08

µCi/ml Cs-137

<9.50E-09

µCi/ml Kr-85

<2.29E-06

µCi/ml Ba-140

<2.42E-08

µCi/ml Sr-89b

<2.38E-08

µCi/ml La-140

<l.13E-08

µCi/ml Sr-90b

<7.80E-09

µCi/ml Ce-141

<l.47E-08

µCi/ml Sr-92

<2.23E-08

µCi/ml Ce-144

<6.76E-08

µCi/ml Zr-95

<l.88E-08

µCi/ml Zr-97

<1.06E-08

µCi/ml Tc-99m

<l.OlE-08

µCi/ml Mo-99

<4.92E-08

µCi/ml Ru-103

<8.90E-09

µCi/ml Ru-106

<8.61E-08

µCi/ml Ag-1 lOm

<8.25E-09

µCi/ml Sb-124

<6.79E-09

µCi/ml Sb-125

<2.63E-08

µCi/ml

• These radionuclides were not identified every quarter in concentrations above the lower limit of detection (LLD). LLDs are applicable to both batch and continuous modes due to identical sample and analysis methods.

b Quarterly composite sample 100

Davis-Besse Nuclear Power Station 20 I 6 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 3.82 E+Ol 2.SE+Ol evaporator bottoms, etc.

Ci 1.02 E+03 2.SE+Ol

b.

Dry compressible waste, m3 3.40 E+02 2.SE+OI contaminated equip., etc.

Ci 4.97 E-01 2.5E+OI

c.

Irradiated components, m3 control rods, etc.

Ci NIA NIA

d.

Filters m3 2.36 E-01 2.SE+OI Ci 7.56 E-02 2.5E+OI

e.

Others: Spent Resin Storage m3 1.64 E+Ol 2.SE+Ol Tanlc Liquor Ci 9.38 E+OO 2.SE+Ol

2. Estimate of major nuclide composition (by type of waste)

IYlli'.

Percent(%)

Est. Error, %

a.

Spent Resins Ni63 4.65 E+Ol 2.50E+01 cs131 3.98 E+Ol 2.50E+Ol Cs' 34 6.30 E+OO 2.50E+01 Co6o 4.17E+OO 2.50E+Ol Fess 2.45 E+OO 2.50E+Ol H3 2.52 E-01 2.50E+Ol Nis9 2.47 E-01 2.50E+Ol Coss 1.30 E-01 2.50E+Ol

b.

Dry compressible waste, contaminated H3 3.62 E+Ol 2.50E+Ol Ni63 3.25 E+Ol 2.50E+Ol Coss 1.19 E+Ol 2.50E+Ol equipment, etc.

Co6o 1.05 E+Ol 2.50E+Ol cs131 6.99 E+OO 2.50E+Ol Ce144 1.88 E+OO 2.50E+01

c.

None

d.

Filters Ni63 4.55 E+Ol 2.50E+Ol Co6o 1.93 E+Ol 2.50E+Ol Fess 1.80 E+Ol 2.50E+Ol Cs'37 1.42 E+Ol 2.50E+Ol cs134 2.59 E+OO 2.50E+Ol Ce144 2.66 E-01 2.50E+Ol Mns4 1.76 E-01 2.50E+Ol IOI

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report

e.

Others: Spent Resin Storage Taruc 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 B. IRRADIATED FUEL SHIPMENTS There were no shipments of irradiated fuel.

Coss H3 Ni63 Cs137 Co6o Fess Crs1 Nb95 zr95 c 14 Sb124 Ag11om Cos1 Mns4 14 Truck 5.15 E+OJ 2.43 E+OJ 1.04 E+OJ 4.69 E+OO 2.47 E+OO 1.64 E+OO 1.56 E+OO 1.31 E+OO 7.55 E-01 3.93 E-01 2.96 E-01 2.68 E-01 1.76 E-01 1.16 E-01 Energy Solutions, Oak Ridge, TN 2.50E+Ol 2.50E+OJ 2.50E+01 2.50E+01 2.50E+Ol 2.50E+OJ 2.50E+Ol 2.50E+OI 2.50E+OI 2.50E+Ol 2.50E+OI 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 m3) 385 m3 2

Truck EnergySolutions, Oak Ridge, TN for processing and disposal at WCS, Andrew TX Poly HJC 3.4 m3 4.81 m3 2

Truck EnergySolutions, Erwin, TN for processing and disposal at WCS, Andrew TX Poly HIC 3.40 m3 4.67 m3 102

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Onsite Groundwater Monitoring Davis-Besse began sampling wells near the plant in 2007 as part of an industry-wide Groundwater Protection Initiative (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 GPJ 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. There are a total of fifty groundwater wells on site that can be sampled to monitor groundwater flow and tritium concentration.

Davis-Besse's Groundwater Protection Program includes baseline annual spring and fall sampling of the sixteen monitoring wells installed in 2007. Additional wells can be sampled as needed if increased monitoring is warranted. An increasing trend of tritium in groundwater wells was identified in February 2015. The investigation determined that the most probable cause was due to construction activities surrounding removal of the Primary Water Storage Tank. Additional wells were added to the spring and fall sampling campaigns. The sampling frequency was increased to quarterly for selected wells to closely monitor and trend tritium values in vulnerable areas of the site and the sample results throughout 2016 continued to show an overall decreasing trend, as described below and in Table 21.

April and October were the spring and fall campaigns for Davis-Besse groundwater monitoring in 2016.

Additional sampling of selected wells was performed for trending. Table 21 contains the GPI monitoring well sample results for tritium.

Early spring (March) trend sampling resulted in five of eight wells indicating tritium concentrations of greater than 2,000 pCi/L.

The spring (April) full sampling schedule resulted in four of twenty-two wells indicating tritium concentrations of greater than 2,000 pCi/L.

Summer (July) trend sampling resulted in three of seven wells indicating tritium concentrations of greater than 2,000 pCi/L.

The fall (October) full sampling schedule resulted m one of twenty-two wells indicating a tritium concentration of greater than 2,000 pCi/L.

Courtesy notifications to local, county, and state officials were made following receipt of the sampling results for each of the four evolutions due to tritium greater than 2,000 pCi/L.

103

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 21 2016 Groundwater Tritium Results Year 2016 March April July October

[H-3),

[H-3),

[H-3),

[H-3),

Well No.

pCi/I pCi/I pCi/I pCi/I MW-100A 733 887 768 MW-100B 495 235 MW-100C 703

<180 MW-101A 393

<180 MW-101B 411

<180 MW-101C

<149

<180 MW-102A 501

<180 MW-102B 1061 1698 1221 MW-102C

<149

<180 MW-103A 543 503 MW-103B 646 680 MW-103C

<150

<180 MW-104A 392

<180 MW-104B 423 678 MW-104C

<149 192 MW-105A 1904 2249 1351 1373 MW-148 3461 3026 1169 MW-208 3019 1105 741 945 MW-218 3509 2077 750 1055 MW-308 3337 1993 3537 1254 MW-348 4477 3949 3642 2242 MW-378 2890 810 846 1153 104

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Davis Besse Onsite Groundwater Monitoring Program H-3 Trends

<200 pCi/L = Typical LLD 2'

u

~

5 -

• ~

J

(,)

0 u *a.

348 pCi/L = Pre-Operational Mean 2,000 pCi/L = NRC Required LLD 2,000 pCi/L = FENOC/NEI Communication Level 20,000 pCi/L = EPA Drinking Water Reporting Level 10000 1000 Typical LLD H-3 (<200 pCi/L)

Pre-Operational Mean H-3 (348 pCi/L)

NRG Required LLD H-3 (2,000 pCi/L)

EPA Drinking Water Reporting Level H-3 (20,000 pCi/L)

Max of All GWM Indicator Wells Figure 30 - Onsite Groundwater Monitoring Summary of Onsite Spills (> 100 gallons) and Notifications There were no identified onsite spills during 2016. Throughout 2016, the State of Ohio, Ottawa County, and local officials were kept updated on the groundwater monitoring sample results > 2000 pCi/L. There was one remaining groundwater well at the end of 2016 that resulted in notifications to the State, County and local officials.

Summary of Items Added to Decommissioning Files per 10 CFR 50.75(g)

The elevated tritium results described above and depicted in Table 21 were added to Decommissioning Files per 10 CFR 50.75(g).

105

Davis-Besse Nuclear Power Station 20 I 6 Annual Radiological Environmental Operating Report Table 22 Doses Due to Gaseous Releases for January through December 2016 Maximum Individual Dose Due to I-131, H-3 and Particulates with Half-Lives Greater than 8 days.

Whole Body Dose 2.84E-02 mrem Significant Organ Dose (lung) 2.84E-02 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 4.76E-05 mrem Skin Dose 7.42E-05 mrad Maximum Individual Dose Due to C-14 Whole Body Dose 2.13E-Ol mrem Significant Organ Dose (bone) 1.03E+OO mrem Population Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.

Total Integrated Population Dose l.39E-02 person-rem Average Dose to Individual in Population 6.38E-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 9.49E-06 person-rem Average Dose to Individual in Population 4.35E-09 mrem Population Dose Due to C-14 Total Integrated Population Dose 6.74E-02 person-rem Average Dose to Individual in Population 6.38E-06 mrem 106

Davis-Besse Nuclear Power Station 20 I 6 Annual Radiological Environmental Operating Report Table 23 Doses Due to Liquid Releases for January through December 2016 Maximum Individual Whole Body Dose Maximum Individual Significant Organ Dose (LIVER)

Population Dose Total Integrated Population Dose Average Dose to Individual l.06E-02 mrem

l. l lE-02 mrem l.64E+OO person-rem 7.49E-04 mrem Table 24 Annual Dose to The Most Exposed (from all pathways) Member of the Public 2016 Whole Body Dose*

Noble Gas Iodine, Tritium, Particulates C-14 Liquid Total Whole Body Dose Thyroid Dose Iodine, Tritium, Particulates Skin Dose Noble Gas Significant Organ Dose (LIVER)

Significant Organ Dose (C-14)

(bone)

Meteorological Data ANNUAL DOSE (mrem) 4.76E-05 2.84E-02 2.13E-Ol l.06E-02 3.90E-02 3.81E-02 8.16E-05 3.94E-02 l.03E+OO 40CFR190 LIMIT (mrem) 25 75 25 25 25 PERCENT OF LIMIT l.56E-01 5.08E-02 3.26E-04 l.58E-01 4.12E+OO Meteorological data, stored on a compact disk for January 1 through December 31, 2016, 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 2016 Annual Radiological Environmental Operating Report Land Use Census Program Design Each year a Land Use Census is conducted by Davis-Besse in order to update information neces-sary to estimate radiation dose to the general public and to determine if any modifications are necessary to the Radiological Environmental Monitoring Program (REMP). The Land Use 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 Cen-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 exposure from radionuclides deposited on the ground Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.

Vegetation Pathway - Internal exposure as a result of eating vegetables, fruit, etc.

which have a build up of deposited radioactive material or which have absorbed ra-dionuclides through the soil.

Milk Pathway - Internal exposure as a result of drinking milk, which may contain radioactive material as a result of a cow or goat grazing on a pasture contaminated by radionuclides.

Methodology The Land Use Census consists of recording and mapping the locations of the closest residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) in each meteorological sector within a five mile radius of Davis-Besse.

The surveillance portion of the 2016 Land Use Census was performed during the months of August through October. 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 broad leaf plants (such as lettuce and cabbage).

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.

108

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 mi-nute series of the relevant quadrangles) which has been divided into 16 equal sectors corresponding 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 One new pathway was recorded in the 2016 census:

S sector: A new garden was located at 3.10 miles distance from the plant.

The critical receptor is a garden in the W sector at 0.97 miles from Davis-Besse, which is a change from 2015.

The detailed list in Table 25 was used to update the database of the effluent dispersion model used in dose calculations. 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 each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). The ODCM describes the methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and in calcu-lating liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints.

109

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Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report N

NNE NE ENE, E, ESE SE SSE SSE

• S s

SSW SSW SW

• changed from 2015 Table 25 Closest Exposure Pathways Present in 2016 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 2016 Annual Radiological Environmental Operating Report WSW WSW w

w WNW NW NW NNW Table 25 (Continued)

Closest Exposure Pathways Present in 2016 Distance from Station (miles) 0.96 4.0 0.61 0.97 0.94 1.94 0.93 0.80 112 Closest Pathways 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 2016 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/M3)

(M-2)

N 0.55 Inhalation Child 3.23E-06 1.21E-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 0.67 Inhalation Child 5.32E-07 7.02E-09 WSW 4.0 Vegetation Child 4.33E-08 3.47E-10 w

0.97 Vegetation Child 6.05E-07 5.13E-09

• • WNW 0.94 Inhalation Child 5.40E-07

3. l 3E-09 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 2016 Land Use Census.

113

Davis-Besse Nuclear Power Station 2016 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 ofroutine operation of nuclear power stations on the surrounding environment. Both NRC regulations and the Davis-Besse Tech-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 Moni-toring Program at Davis-Besse has an extensive record of data with which to perform climate studies which are used to determine whether Davis-Besse has had any impact upon the local cli-mate. After extensive statistical comparative research the meteorological personnel have found no impact upon local climate or short-term weather patterns.

The Meteorological Monitoring Program also provides data that can be used by many other groups and programs such as the Radiological Environmental Monitoring Program, the Emergency Pre-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 evaluat-ing the radiological impact, if any, of radioactivity released in Station effluents. The meteorolog-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 calcu-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 calcu-lations, Forebay water level availability and plant work which needs certain environmental condi-tions to be met before work begins. Plant Security utilizes weather data in their routine planning and activities. Materials Management plans certain Plant shipments around adverse weather con-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. Detailed meteorological information is available upon request.

114

Davis-Besse Nuclear Power Station 2016 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 I 00 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 I 00 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 approxi-mately 3,000 feet SSW of the Cooling Tower and a 1 Om auxiliary tower located 100 feet west of the 100 m tower. Both are used to gather the meteorological data. The 1 OOm 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 in-struments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the 1 Om tower.

According to the Davis-Besse Nuclear Power Station Technical Requirements Manual, a minimum of five instruments are required to be operable at the two lower levels (75m and 1 Om) to measure temperature, wind speed, and wind direction. During 2016, average annual data recoveries for all required instruments were greater than 99.29 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 per-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 2016 Annual Radiological Environmental Operating Report Meteorological Data Handling and Reduction Each meteorological system, primary and backup, have two Campbell Scientific Data-loggers (model 21 XL) 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 me-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 protec-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 stor-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 27-29, which summarize meteorological data collected from the on-site monitoring program in 2016.

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 at the 100 meter and 7 5 meter levels during 2016 occurred on February 20, when it was measured at 46.55 mph and 44.62 mph respectively.

The maximum wind speed in 2016 at the 10 meter level occurred on March 16, when it reached 32.61 mph.

Figures 32-34 provide an annual sector graphic of average wind speed and percent frequency by direction measured at the three monitoring levels. Each wind sector graphic has two radial bars.

The darker bar represents the percent of time the wind blew from that direction. The hatched bar represents the average wind speed from that direction. Wind direction sectors are classified 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 2016 Annual Radiological Environmental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2016 are provided in Table

28. The parameters were measured at the 1 Om level; with differential temperatures taken from 1 OOm and 75m levels (Table 27). The yearly average ambient temperature was 52.99°F. The maximum temperature was 92.80°F on June 11 with a minimum temperature of2.72°F on Decem-ber 19. Yearly average differential temperatures were -0.432°F (JOOm), and -0.282°F (75m).

Maximum differential temperatures for 100 meter and 75m levels were 8.90°F on November 26 and 7.97°F on November 17 respectively.

Minimum differential temperatures were --4.00°F (1 OOm) on December 18 and -3.98°F (75m) on October 4. Differential temperatures are a meas-urement 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 2016 are provided in Table 28. These data are measured at the I Om level. The average dew point temperature was l l.33°F with a maximum dew point temperature of 38.46°F on July 22. The minimum dew point (dew point under 32°F is frost point) temperature was - 25.61°F on February 13. It is possible to have relative humidity above 100 percent, which is known as supersaturation. Conditions for su-persaturation 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 2016 are provided in Table 28.

Total precipitation for the year was 34.44 inches. The maximum daily precipitation total was 1.52 inches on September 17. There were many days in 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 The "Lake Breeze" condition 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 can occur during the daytime, usually during the summer, under the conditions in which the land surface heats up faster than the water and reaches warmer 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.

Lake and Forebay levels are monitored at Davis-Besse to observe, evaluate, predict and dissemi-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 to ensure 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 117

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report 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 2016 Annual Radiological Environmental Operating Report Table 27 Summary of Meteorological Data Recovery for the Davis-Besse Nuclear Power Station January 1, 2016 through December 31, 2016*

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2016 lOOm Wind Speed 97.98 97.84 100 96.25 100 100 100 JOO 100 100 86.67 100 98.26 1 OOM Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100 75M Wind Speed 97.98 97.84 100 96.25 100 100 100 100 100 100 100 100 99.35 75M Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100

!OM Wind Speed 97.98 97.84 100 96.25 100 100 100 100 100 100 100 100 99.35 1 OM Wind Direction 100 100 100 100 100 100 100 100 100 100 100 100 100 1 OM Ambient Air Temp 97.98 97.84 100 96.25 JOO 100 100 100 100 100 100 JOO 99.29 1 OM Dew Point Temp 97.98 97.84 100 96.25 100 100 99.33 100 100 100 100 99.33 99.24 Delta T (lOOM-IOM) 97.98 97.84 100 96.25 100 100 JOO 100 100 100 100 99.33 98.77 Delta T (75M-1 OM) 97.98 97.84 JOO 96.25 JOO 100 100 100 100 100 100 99.33 99.29 Joint lOOM Winds and Delta T (lOOM-lOM) 97.98 97.84 100 96.25 100 100 100 100 100 JOO 100 99.33 97.68 Joint 75M Winds and Delta T (1 OOM-1 OM) 97.98 97.84 100 96.25 100 100 100 JOO JOO 100 100 99.33 99.29 Joint 1 OM Winds and Delta T (75M-1 OM) 97.98 97.84 100 96.25 100 100 100 100 100 100 100 99.33 99.29

• All data for individual months expressed as percent of time instrument was operable during the month, divided by the maximum number of hours in that month that the instru-ment could be operable. Values for annual data recoveries equals the percent of time instrument was operable during the year, divided by the number of hours in the year that the instrument was operable.

119

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 28 Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1, 2016 through December 31, 2016 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2016 lOOMWIND Max Speed (mph) 39.06 46.55 43.52 39.58 29.00 29.12 27.53 28.42 32.16 34.70 37.30 36.96 46.55 Date of Max Speed 01/10 02/20 03/16 04/02 05114 06105 07113 08/16 09130 10/18 11/20 12/26 02/20 Min Speed (mph) 1.37 1.80 2.31 1.89 1.02 2.60 1.56 1.98 2.28 1.19 1.88 3.28 1.02 Date of Min Speed 01/22 02/15 03/21 04/18 05103 06/25 07/27 08/28 09/29 10/10 11 /07 12/06 05103 Ave Wind Speed 18.61 19.11 16.51 16.64 13.75 13.77 12.24 12.51 13.93 16.33 17.77 18.14 15.75 75MWIND Max Speed (mph) 37.62 44.62 41.87 38.39 28.67 27.15 25.15 26.20 30.42 33.48 35.34 34.95 44.62 Date of Max Speed 01110 02/20 03116 04/02 05/14 06105 07113 08/16 09130 10/18 11/20 12/26 02/20 Min Speed (mph) 1.22 1.46 2.69 2.47 1.36 2.14 1.02 1.25 2.21 1.41 1.1 I 2.84 1.02 Date of Min Speed 01/22 02/01 03/21 04/18 05103 06/25 07/27 08/02 09/04 10/10 11/03 12/06 07/27 Ave Wind Speed 16.98 17.92 15.31 15.35 12.52 12.74 11.31 11.47 12.70 14.89 15.76 16.61 14.44 lOMWIND Max Speed (mph) 26.64 32.19 32.61 26.84 19.99 19.10 14.82 17.23 20.64 24.55 23.21 24.49 32.61 Date of Max Speed 01/26 02/20 03116 04/02 05/14 06105 07115 08116 09/10 10/21 11 /20 12/26 03/16 Min Speed (mph) 0.44 1.19 1.76 1.59 0.74 1.03 1.42 1.19 1.07 1.61 1.34 1.73 0.44 Date of Min Speed 01/22 02/02 03/12 04/23 05/20 06/24 07/20 08/29 09/04 10/19 11106 12/24 01/22 Ave Wind Speed 10.53 11.51 9.40 9.97 9.54 7.99 6.73 6.31 7.15 8.53 8.83 10.42 8.72 120

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 28 (continued)

Summary of Meteorological Data Measured at Davis-Besse Nuclear Power Station January 1, 2016 through December 31, 2016 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2016 lOM AMBIENT TEMP Max (F) 56.46 65.19 70.60 71.90 86.35 92.80 90.48 87.73 90.13 82.18 78.90 62.65 92.80 Date of Max 01131 02/20 03/08 04/25 05/29 06/1 I 07/22 08/12 09/07 10/17 Il/01 12/26 06/11 Min (F) 5.02 5.82 19.61

23. 14 38.68 53.63 59.87 58.59 49.37 38.85 23.67 2.72 2.72 Date of Min 01118 02/13 03/02 04/10 05116 06/08 07103 08/22 09/27 10/28 11122 12/19 12/19 Ave Temp 28.25 32.68 42.98 44.87 59.99 71.03 75.69 75.22 69.10 57.88 47.03 29.61 52.99 lOM DEW POINT TEMP Mean (F)

-8.10

-4.95 2.96 4.23 15.09 23.31 28.71 29.89 24.76 16.14 7.71

-5.05 11.33 Max (F) 12.31 15.59 20.61 23.22 32.51 37.08 38.46 37.46 38.10 31.08 27.66 20.59 38.46 Date of Max 01/31 02/28 03/08 04/25 05/28 06/26 07/22 08/11 09/07 10/17 11101 12/26 07/22 Min (F)

-25.35

-25.61

-14.Il

-11.65

-1.68 9.57 17.50 18.93 8.80 3.42

-9.24

-24.40

-25.61 Date of Min 01118 02/13 03/02 04109 05116 06/08 07/03 08/22 09/27 10/22 11122 12119 02/13 PRECIPITATION Total (inches) 1.21 2.37 4.57 4.95 1.91 1.93 3.31 4.35 3.43 2.15 2.51 1.75 34.44 Max in One Day 0.65 1.37 1.19 1.16 0.43 0.56 0.89 1.45 1.52 0.62 1.33 0.50 1.52 Date 01/10 02/24 03/24 04105 05/02 06104 07/30 08/13 09/17 10/20 11/03 12112 09/17 121

Davis-Besse Nuclear Power Station 201 6 Annual Radiological Environmental Operating Report Figure 32 Wind Rose Annual Average 1 OOM N

SS'll moooo0t WJNf SPEFD ("11-'ll)

---

DIRECTTO r r '.jlJENCY

(")

DAVIS-BESSE ANNUAL 2016 100M LEVEL 122

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average 75M DAVIS-BESSE ANNUAL 2016 75M LEVEL 123

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Figure 34 Wind Rose Annual Average 1 OM SW~

SSW OOOOOOOOf WIN(] SPECO (M H)

DIRECl'lO J FREQJENCY

(~ )

N DAVIS-BESSE ANNUAL 2016 10M LEVEL 124

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 29 Joint Frequency Distribution by Stability Class DA VIS-BESSE NUCLEAR POWER STATION PROGRAM: JFD VERSION: F77-l.O DAVIS-BESSE 75-10 DT, NO BACKUP DATA PERIOD EXAMINED: 01 /01/16 - 12/31/16 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 SITE IDENTIFIER: 16 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

3 2

0 0

0 5

0 I

0 0

0 0

I 0

0 I

0 0

2 STABILITY BASED ON:

DELTA T WIND MEASURED AT:

35.0 FEET WIND THRESHOLD AT:

1.00 MPH 0

I 13 2

0 0

16 0

3 I

0 0

0 4

0 3

I 0

0 0

4 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 5

0 0

0 5

ST ABILITY CLASS B BETWEEN 250.0 AND 35.0 FEET 0

3 5

2 0

0 IO I

3 II 9

0 0

24 3

3 8

4 0

0 18 I

3 14 5

0 0

23 3

7 19 16 0

0 45 0

16 20 15 0

0 51 0

6 2

I 0

0 9

0 9

52 IOI 55 0

0 217 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)

CALM 1.01-3.49 3.50 - 7.49 7.50- 12.49 12.50 - 18.49 18.50 - 24.49

>24.49 TOTAL N

NNE NE ENE I

3 I

0 0

6 0

0 I

0 0

2 0

0 7

8 0

0 15 0

5 38 7

0 0

50 E

0 6

4 0

0 0

IO ESE SE SSE 0

I 5

0 0

0 6

0 0

4 0

0 0

4 0

0 0

0 0

0 0

125 S

SSW SW WSW W

WNW NW NNW TOTAL 0

I 6

0 0

0 7

0 2

20 12 0

0 34 0

7 48 29 4

89 I

2 19 12 4

39 I

8 7

5 I

0 22 0

5 11 7

I 0

24 0

7 10 7

0 0

24 0

5 8

0 0

0 13 0

3 50 191 89 IO 2

345

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 29 (Continued)

Joint Frequency Distribution by Stability Class DA VIS-BESSE NUCLEAR POWER ST A TION PROGRAM: JFD VERSION: F77-1.0 DAVIS-BESSE 75-10 DT, NO BACKUP SITE IDENTIFIER: 16 DATA PERJOD EXAMINED: 01/0I/16 - 12/31/16 STABILITY BASED ON:

DELTA T WIND MEASURED AT:

35.0 FEET WIND THRESHOLD AT:

1.00 MPH

• • • ANNUAL ***

ST ABILITY 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

CALM 1.01-3.49 0

0 0

0 0

0 0

0 0

0 2

I 3.50 - 7.49 2

19 25 10 I

0 5

10 4

9 2

7.50 - 12.49 I

18 57 14 0

3 4

32 34 16 5

12.50 - 18.49 0

4 8

6 I

0 0

0 0

14 36 14 8

18.50 - 24.49 I

0 0

0 0

0 0

0 0

I 6

4 2

>24.49 0

0 0

0 0

0 0

0 0

0 0

TOTAL 4

7 27 82 40 10 4

9 57 81 46 18 STABILITY CLASS D STABILITY BASED ON:

DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:

35.0 FEET WIND THRESHOLD AT:

1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)

N NNE NE ENE E

ESE SE SSE s

SSW SW WSW w

CALM I.OJ - 3.49 5

5 5

II 12 9

12 II 12 5

6 5

3.50 - 7.49 59 55 95 171 171 70 81 74 90 143 82 61 31 7.50 - 12.49 54 132 207 167 122 42 31 41 65 198 254 222 109 12.50 - 18.49 49 126 48 44 15 0

0 2

9 69 250 242 103 18.50 - 24.49 12 8

13 0

0 0

0 0

I 23 60 36 20

>24.49 0

0 0

0 0

0 0

0 0

0 13 5

0 TOTAL 175 326 368 387 319 124 121 129 176 445 664 572 268 126 WNW 0

6 13 5

I 0

25 WNW 13 44 81 16 0

155 NW NNW TOTAL 0

0 0

4 6

13 114 14 12 225 5

3 104 0

2 17 0

0 2

25 30 466 NW NNW TOTAL I

4 3

107 23 30 1249 59 76 1823 80 63 1181 15 23 227 5

24 186 196 4612

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 29 (Continued)

Joint Frequency Distribution by Stability Class DA VIS-BESSE NUCLEAR POWER STATION PROGRAM: JFD VERSION: F77-1.0 DA VIS-BESSE 75-10 OT, NO BACKUP SITE IDENTIFIER: 16 DATA PERIOD EXAMINED: 01 /01/16 - 12/31/16

• • • ANNUAL ***

ST ABILITY CLASS E STABILITY BASED ON:

DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:

35.0 FEET WIND THRESHOLD AT:

1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)

N NNE NE ENE E

ESE SE SSE s

SSW SW WSW w

WNW NW NNW TOTAL CALM 0

101-3.49 5

5 5

6 18 33 44 62 57 32 29 16 6

8 9

9 344 3.50 - 7.49 28 44 31 60 110 121 118 94 23 1 292 106 100 35 20 17 16 1423 7.50 - 12.49 8

17 14 29 30 8

7 18 90 214 119 84 33 24 33 17 745 12.50 - 18.49 I

8 I

0 4

0 4

7 31 51 97 29 II 2

9 I

256 18.50 - 24.49 0

0 0

0 0

0 0

0 0

4 33 3

2 0

0 0

42

>24.49 0

0 0

0 0

0 0

0 0

0 7

2 0

0 0

0 9

TOTAL 42 74 51 95 162 162 173 181 409 593 391 234 87 54 68 43 2819 STABILITY CLASS F ST ABILITY BASED ON:

DELTA T BETWEEN 250.0 AND 35.0 FEET WIND MEASURED AT:

35.0 FEET WIND THRESHOLD AT:

1.00 MPH JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)

N NNE NE ENE E

ESE SE SSE s

SSW SW WSW w

WNW NW NNW TOTAL CALM 1.01 - 3.49 2

2 2

5 II 33 76 82 44 32 14 I I 9

0 3

327 3.50 - 7.49 2

3 13 26 21 14 41 85 125 34 26 18 IO 3

3 425 127

Davis-Besse Nuclear Power Station 2016 Annual Radiological Environmental Operating Report Table 29 (Continued)

Joint Frequency Distribution by Stability Class DA VIS-BESSE NUCLEAR POWER STATION PROGRAM: JFD VERSION: F77-I.O DA VIS-BESSE 75-10 DT, NO BACKUP DATA PERIOD EXAMINED: 01 /01 /16 - 12/31/16 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 SITE IDENTIFIER: 16 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 I.OJ - 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 0

0 0

0 0

0 0

2 0

0 0

0 2

STABILITY BASED ON:

DELTA T WIND MEASURED AT:

35.0 FEET WIND THRESHOLD AT:

1.00 MPH 2

10 7

0 0

0 19 5

IO 4

0 0

0 19 4

9 0

0 0

0 13 9

7 0

0 0

0 16 18 4

0 0

0 0

22 28 20 0

0 0

0 48 22 34 0

0 0

0 56 ST ABILITY CLASS ALL BETWEEN 250.0 AND 35.0 FEET 10 3

0 0

0 0

13 7

2 0

0 0

0 9

5 I

0 0

0 0

6 2

0 0

0 0

0 2

3 I

0 0

0 0

4 0

0 0

0 0

0 0

11 5 103 II 0

0 0

230 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS AT 35.00 FEET SPEED (MPH)

N NNE NE ENE CALM 1.01-3.49 8

13 13 15 3.50 - 7.49 95 I 02 132 279 7.50 - 12.49 68 152 248 314 12.50- 18.49 51 139 66 59 18.50 - 24.49 13 8

13 0

>24.49 0

0 0

0 TOTAL 235 414 472 667 E

ESE SE SSE 39 60 95 168 35 1 235 22 1 213 179 57 47 62 20 0

5 9

0 0

0 0

0 0

0 0

589 352 368 452 128 s

SSW SW WSW W

WNW NW NNW TOTAL 178 110 77 432 609 239 172 480 471 40 150 421 I

28 103 0

0 22 823 1377 1333 49 203 350 301 47 9

959 30 98 168 132 25 0

453 23 6 1 Ill Ill 18 0

324 16 73 137 116 15 5

362 15 73 11 5 68 25 297 3

909 3416 3131 1688 296 37 9480

Davis-Besse Nuclear Power Station 2016 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. Davis-Besse is responsible for the maintenance and repair of the dikes and controlling the water levels in each of the pools.

A revetment is a retaining structure designed to hold water back for the purposes of erosion 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 organi-zations. The Ottawa National Wildlife Refuge, the Ohio Department of Natural Resources (ODNR), and the Black Swamp Bird Observatory work to preserve and enhance existing habitat.

Knowledge is gained through research and is used to help educate the public about the 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, cap-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, in-cluding deer, fox, coyote, beavers, muskrats, mink, rabbits, groundhogs, hawks, owls, ducks, geese, herons, snakes and turtles. American Bald Eagles chose the Navarre Marsh as a nesting site in late 1994, and fledged a healthy eaglet in July 1995. A second pair built a nest in 1999-2000. 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, filtra-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 de-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 wa-ter to Davis-Besse. Carroll Township Water and Wastewater District follow all applicable regu-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 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 Cir-culating 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 oper-ational challenges.

Wastewater Treatment Plant (WWTP) Operation The WWTP operation is supervised by an Ohio licensed Wastewater Operator. Wastewater gen-erated by site personnel is treated in an onsite extended aeration package treatment facility de-signed to accommodate up to 38,000 gallons per day. In the treatment process, wastewater from the various collection points around the site enters the facility through a grinder, from where it is distributed to the surge tanks of one or both of the treatment plants.

The wastewater is then pumped into aeration tanks, where it is digested by microorganisms. Ox-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 digest incoming wastewater. The effluent leaving the plant is drained to the wastewater basin (NPDES Outfall 60 I) where further treatment takes place.

National Pollutant Discharge Elimination System (NPDES) Reporting The Ohio Environmental Protection Agency (OEPA) has established limits on the amount of pol-lutants that Davis-Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 2IB0001 l *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 Source of Wastes: Storm water runoff, Circulating Water pump house sumps 131

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 2016 NPDES Summary During 2016, Davis-Besse Nuclear Power Station did not exceed any NPDES discharge limits.

Chemical Waste Management The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes gen-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 haz-ardous waste. Solid waste is defined as a solid, liquid, semi-solid, or contained gaseous material.

The major goals ofRCRA are to establish a hazardous waste regulatory program to protect human 132

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report health and the environment and to encourage the establishment of solid waste management, re-source recovery, and resource conservation systems. The intent of the hazardous waste manage-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 gen-erates, transports, stores, treats, or disposes of hazardous waste are subject to regulation under RCRA.

Under RCRA, there are essentially three categories of waste generators:

Large quantity Generators - A facility which generates 1,000 kilograms/month (2,200 lbs./month) or more.

Small quantity Generators - A facility which generates less than 1,000 kilograms/

month (2,200 lbs./month).

Conditionally Exempt Small Quantity Generators - A facility which generates 100 kilo-grams/month (220 lbs./month).

In 2016, the Davis-Besse Nuclear Power Station generated approximately 2,628 pounds of haz-ardous waste.

Non-hazardous waste generated in 2016 included 2,096 gallons of used oil and 20,673 pounds of other nonhazardous wastes such as oil filters, resins and caulks.

RCRA mandates other requirements such as the use of proper storage and shipping containers, labels, manifests, reports, personnel training, a spill control plan and an accident contingency plan. These are part of the Chemical Management Program at Davis-Besse. The following are completed as part of the hazardous waste management program and RCRA regulations:

Weekly Inspections of the Chemical Waste Accumulation Areas are designated 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 accumu-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 accu-mulation area for employees to record the waste type and amount when chemicals are added to the drum. This ensures that incompatible wastes are not mixed and also 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 Su-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.

133

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 chem-icals are present in reportable quantities.

Annual SARA reports are submitted to local fire departments and state and local planning com-missions by March 1 for the preceding calendar year.

Toxic Substances Control Act (TSCA)

The Toxic Substance Control Act (TSCA) was enacted to provide the USEPA with the authority to require testing of new chemical substances for potential health effects before they are 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 PCB-leaching solvents and allowing the solvent to circulate in the transformer during operation. The entire retro-fill process takes several years and will extract almost all of the PCB.

In all, Davis-Besse performed retro-fill activities on eleven PCB transformers between 1987 and 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors.

These capacitors are being replaced and disposed of during scheduled maintenance activities.

Clean Air Act The Clean Air Act identifies substances that are considered air pollutants. Davis-Besse holds an OEP A 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 the seven Davis-Besse diesel engines, including the Station Blackout Diesel Generator, the 2 Emergency Diesel Generators, the Emer-gency Response Facility Diesel Generator, the Miscellaneous Diesel, the Fire Pump Diesel, and the Diesel Driven Emergency Feedwater Pump. These sources are operated infrequently to verify their reliability, and would only be used in the event of an emergency.

134

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report In response to recent "Clean Air Act Title V" legislation, an independent study identifying and quantifying all of the air pollution sources onsite was performed. Of particular significance is asbestos removal from renovation and demolition projects for which USEPA has outlined specific regulations concerning handling, removal, environmental protection, and disposal. Also, the Oc-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 consid-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 Trans-portation Safety Act of 1976. These regulations are enforced by the United States Department of Transportation (DOT) and cover all aspects of transporting hazardous materials, including pack-ing, handling, labeling, marking, and placarding. Before any wastes are transported off site, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regula-tions, including verification that the vehicle has appropriate placards and it is in good operating condition.

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 haz-ardous chemical and oil use areas. Equipment in the kits may include chemical-resistant coveralls, gloves, boots, decontamination agents, absorbent cloth, goggles and warning signs.

Waste Minimization and Recycling Municipal Solid Waste (MSW) is normal trash produced by individuals at home and by 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 135

Davis-Besse Nuclear Power Station 2015 Annual Radiological Environmental Operating Report 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 re-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 eval-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. Paper and cardboard recycling is typically in excess of 50 tons annually. This repre-sents a large volume ofrecyclable 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 and recycles scrap metals, which are sold at market price to a scrap dealer for resource recovery.

136

~*L All E~vironmental, Inc.

lit~ J'""\\I Midwest Laboratory 700 Landwehr Road

• Northbrook. IL 60062-23 10 phone (847) 564-0100

• fox (847) 564-4!517 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. TLD 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, 2016 through December, 2016 137

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 radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

Results in Table A-1 were obtained through participation in the RAD PT Study Proficiency Testing Program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.

Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.

Complete analytical data for duplicate analyses is available upon request.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-7 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.

Out-of-limit results are explained directly below the result.

A1 138

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES 0

Analysis Gamma Emitters Strontium-89b Strontium-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium lodine-131,

lodine-1 29b 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

> 100 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 a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program", Fiscal Year, 1981-1982, EPA-600/4-81 -004.

" Laboratory limit.

A2 139 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

+/- 1o =

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 10 pCi/liter 10% of known value 20% of known value

TABLE A-1. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)".

RAD study Concentration (eCill)

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceetance ERW-1392 4/4/2016 Sr-89 43.5 +/- 4.3 48.2 37.8 - 55.6 Pass ERW-1392 4/4/2016 Sr-90 27.5 +/- 1.9 28.5 20.7 - 33.1 Pass ERW-1394 b 4/4/2016 Ba-133 65.2 +/- 3.8 58.8 48.7 - 64.9 Fail ERW-1394 c 4/4/2016 Ba-133 57.8 +/- 5.3 58.8 48.7 - 64.9 Pass ERW-1394 4/4/2016 Cs-134 43.7 +/- 3.0 43.3 34.6 - 47.6 Pass ERW-1394 4/4/2016 Cs-137 86.1 +/- 5.3 78.4 70.6 - 88.9 Pass ERW-1394 4/4/2016 Co-60 108 +/- 44 102 91.8 - 114 Pass ERW-1394 4/4/2016 Zn-65 240 +/- 13 214 193-251 Pass ERW-1397 4/4/2016 Gr. Alpha 52.0 +/- 2.2 62.7 32.9 - 77.8 Pass ERW-1397 4/4/2016 Gr. Beta 33.9+/-1.2 39.2 26.0 - 46.7 Pass ERW-1400 4/4/2016 1-131 24.7 +/- 0.6 26.6 22.1 - 31.3 Pass ERW-1402 4/4/2016 Ra-226 15.6 +/- 0.5 15.2 11.3 - 17.4 Pass ERW-1402 4/4/2016 Ra-228 5.28 +/- 0.76 5.19 3.12 - 6.93 Pass ERW-1403 4/4/2016 Uranium 4.02 +/- 0.42 4.64 3.39 - 5.68 Pass ERW-1405 4/4/2016 H-3 8,150 +/- 270 7,840 6,790 - 8,620 Pass SPW-2845 7/7/2015 Ba-133 60.3 +/- 5.7 64.7 53.9 - 71.2 Pass SPW-2845 7/7/2015 Cs-134 48.8 +/- 9.3 50.1 40.3 - 55.1 Pass SPW-2845 7/7/2015 Cs-137 101 +/- 8 89.8 80.8 - 101 Pass SPW-2845 717/2015 Co-60 65.1 +/- 5.8 59.9 53.9 - 68.4 Pass SPW-2845 7/7/2015 Zn-65 288 +/- 29 265 238-310 Pass ERW-3485 7/11/2016 Sr-89 43.3 +/- 6.5 53.3 42.3 - 60.9 Pass ERW-3485 7/11/2016 Sr-90 39.0 +/- 2.8 39.2 28.8 - 45.1 Pass ERW-3487 7/11/2016 Ba-133 83.3 +/- 4.9 82.9 69.7 - 91.2 Pass ERW-3487 7/11/2016 Cs-134 62.5 +/- 4.4 65.3 53.1 - 71.8 Pass ERW-3487 7/11/2016 Cs-137 98.1 +/- 5.6 95.2 85.7 - 107 Pass ERW-3487 7/11/2016 Co-60 122 +/- 5 117 105 -131 Pass ERW-3487 7/11/2016 Zn-65 124 +/- 9 113 102 - 134 Pass ERW-3490 7/11 /2016 Gr. Alpha 46.6 +/- 2.2 48.1 25.0 - 60.5 Pass ERW-3490 7/11/2016 Gr. Beta 26.8 +/- 1.1 28.6 18.2 - 36.4 Pass ERW-3492 7/11/2016 1-131 23.7+/-1.0 24.9 20.7 - 29.5 Pass ERW-3493 7/11/2016 Ra-226 12.9 +/- 0.4 12.3 9.2 - 14.2 Pass ERW-3493 7/11/2016 Ra-228 5.8 +/- 0.8 5.8 3.5 - 7.6 Pass ERW-3493 7/11/2016 Uranium 32.8 +/- 0.8 25.2 28.4 - 39.3 Pass ERW-3495 7/11/2016 H-3 12,400 +/- 334 12,400 10,800 - 13,600 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 No reason determined for failure of Ba-133 result.

0 The result of reanalysis (Compare to original result, footnoted "b" above).

140

TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). ab mrem Lab Code Irradiation Delivered Reported Performance c Date Descri~tion Dose Dose Quotient (P)

Acceptance d Environmental, Inc.

Group 1 2016-1 1017/2016 Spike 1 135.0 148.3 0.10 2016-1 1017/2016 Spike 2 135.0 144.3 0.07 2016-1 1017/2016 Spike 3 135.0 133.2

-0.01 2016-1 10/7/2016 Spike 4 135.0 139.6 0.03 2016-1 10/7/2016 Spike 5 135.0 128.4

-0.05 2016-1 10/7/2016 Spike 6 135.0 123.9

-0.08 2016-1 10/7/2016 Spike 7 135.0 124.0

-0.08 2016-1 10/7/2016 Spike 8 135.0 121.5

-0.10 2016-1 10/7/2016 Spike 9 135.0 148.3 0.10 2016-1 1017/2016 Spike 10 135.0 126.8

-0.06 2016-1 10/7/2016 Spike 11 135.0 123.3

-0.09 2016-1 10/7/2016 Spike 12 135.0 137.9 0.02 2016-1 1017/2016 Spike 13 135.0 126.0

-0.07 2016-1 10/7/2016 Spike 14 135.0 127.2

-0.06 2016-1 10/7/2016 Spike 15 135.0 144.5 0.07 2016-1 1017/2016 Spike 16 135.0 140.5 0.04 2016-1 10/7/2016 Spike 17 135.0 146.0 0.08 2016-1 10/7/2016 Spike 18 135.0 127.7

-0.05 2016-1 10/7/2016 Spike 19 135.0 146.8 0.09 2016-1 1017/2016 Spike 20 135.0 122.6

-0.09 2016-1 10/7/2016 Spike 21 135.0 108.6

-0.20 2016-1 1017/2016 Spike 22 135.0 119.6

-0.11 2016-1 10/7/2016 Spike 23 135.0 135.1 0.00 2016-1 10/7/2016 Spike 24 135.0 116.2

-0.14 2016-1 1017/2016 Spike 25 135.0 118.9

-0.12 2016-1 10/7/2016 Spike 26 135.0 128.5

-0.05 2016-1 10/7/2016 Spike 27 135.0 115.6

-0.14 2016-1 10/7/2016 Spike 28 135.0 126.4

-0.06 2016-1 10/7/2016 Spike 29 135.0 115.0

-0.15 2016-1 1017/2016 Spike 30 135.0 147.3 0.09 Mean (Spike 1-30) 130.4 0.03 Pass Standard Deviation (Spike 1-30) 11.5 0.09 Pass

• Table A-2 assumes 1 roentgen = 1 rem (NRC -Health Physics Questions and Answers 10 CFR Part 20 - Question 96 - Page Last Reviewed/Updated Thursday, October 01, 2015).

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.

0 Performance Quotient (P) is calculated as ((reported dose - conventially true value) + conventially true value) where the conventially true value is the delivered dose.

" 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.

141

TABLE A-2 Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). ab mrem Lab Code Irradiation Delivered Reported Performance c Date Descri~tion Dose Dose Quotient (P)

Acceptance d Environmental, Inc.

Group 2 2016-2 10/7/2016 Spike 31 87.0 83.0

-0.05 2016-2 101712016 Spike 32 87.0 88.3 0.01 2016-2 10/7/2016 Spike 33 87.0 83.1

-0.04 2016-2 101712016 Spike 34 87.0 81.4

-0.06 2016-2 10/7/2016 Spike 35 87.0 78.9

-0.09 2016-2 101712016 Spike 36 87.0 80.3

-0.08 2016-2 10/7/2016 Spike 37 87.0 101.1 0.16 2016-2 10/7/2016 Spike 38 87.0 78.3

-0.10 2016-2 10/7/2016 Spike 39 87.0 86.6 0.00 2016-2 10/7/2016 Spike 40 87.0 81.8

-0.06 2016-2 10/7/2016 Spike 41 87.0 84.8

-0.03 2016-2 10/7/2016 Spike 42 87.0 79.9

-0.08 2016-2 101712016 Spike 43 87.0 80.8

-0.07 2016-2 101712016 Spike 44 87.0 80.2

-0.08 2016-2 10/7/2016 Spike 45 87.0 82.7

-0.05 2016-2 10/7/2016 Spike 46 87.0 104.0 0.20 2016-2 10/7/2016 Spike 47 87.0 86.1

-0.01 2016-2 10/7/2016 Spike 48 87.0 104.0 0.20 2016-2 10/7/2016 Spike 49 87.0 86.1

-0.01 2016-2 101712016 Spike 50 87.0 90.8 0.04 2016-2 101712016 Spike 51 87.0 85.7

-0.01 2016-2 101712016 Spike 52 87.0 86.5

-0.01 2016-2 10/7/2016 Spike 53 87.0 86.4

-0.01 2016-2 101712016 Spike 54 87.0 92.6 0.06 2016-2 10/7/2016 Spike 55 87.0 88.6 0.02 2016-2 101712016 Spike 56 87.0 78.9

-0.09 2016-2 10/7/2016 Spike 57 87.0 82.6

-0.05 2016-2 10/7/2016 Spike 58 87.0 80.6

-0.07 2016-2 10/7/2016 Spike 59 87.0 89.9 0.03 2016-2 101712016 Spike 60 87.0 85.0

-0.02 Mean (Spike 31-60) 86.0 0.01 Pass Standard Deviation (Spike 31-60) 6.9 0.08 Pass

• Table A-2 assumes 1 roentgen = 1 rem (NRG -Health Physics Questions and Answers 10 CFR Part 20 - Question 96 - Page Last Reviewed/Updated Thursday, October 01, 2015).

0 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.

0 Performance Quotient (P) is calculated as ((reported dose - convenlially true value) + conventially true value) where the conventially true value is the delivered dose.

" 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.

142

TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activit;r:

Limits d Acce~tance SPW-290 1/21/2016 Sr-90 38.6 +/- 1.5 37.3 22.4 - 52.2 Pass SPW-292 1/21/2016 Sr-90 35.8 +/- 1.6 37.3 22.4 - 52.2 Pass SPW-294 1/21/2016 C-14 4,689 +/- 18 4,735 2,841 - 6,629 Pass SPW-414 2/1/2016 Ra-228 18.4 +/- 2.2 17.7 10.6 - 24.8 Pass W-020416 2/4/2016 Gr. Alpha 20.8 +/- 0.4 20.1 12.0 - 28.1 Pass W-020416 2/4/2016 Gr. Beta 29.7 +/- 0.3 28.9 17.3 - 40.4 Pass W-021716 2/17/2016 Ra-226 17.9 +/- 0.5 16.7 10.0 - 23.4 Pass W-030716 3/7/2016 Gr. Alpha 16.3 +/- 0.8 20.1 12.0 - 28.1 Pass W-030716 3/7/2016 Gr. Beta 27.0 +/- 0.7 28.9 17.3 - 40.4 Pass SPDW-70046 3/29/2016 Ra-226 13.4 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-1163 3/22/2016 Ra-228 4.2 +/- 0.7 4.4 2.6 - 6.2 Pass SPW-1235 3/29/2016 Gr. Alpha 21.0 +/- 0.4 20.1 12.0 - 28.1 Pass SPW-1235 3/29/2016 Gr. Beta 29.4 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-1739 4/21/2016 Ra-228 16.2 +/- 2.0 17.7 10.6 - 24.8 Pass SPW-2052 4/21/2016 Ra-226 16.0 +/- 0.5 16.7 10.0 - 23.4 Pass W-042616 4/21/2016 Fe-55 1,519+/-61 1,482 889 - 2,075 Pass SPW-1823 4/23/2016 Gr. Alpha 21.0 +/- 0.4 20.1 12.0 - 28.1 Pass SPW-1823 4/23/2016 Gr. Beta 26.6 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-1998 4/29/2016 Cs-134 35.9 +/- 6.0 36.2 21.7 - 50.6 Pass SPW-1998 4/29/2016 Cs-137 82.5 +/- 7.6 71.9 43.1 - 100.6 Pass SPW-2097 5/3/2016 H-3 3,349 +/- 184 3,280 1,968 - 4,592 Pass SPW-2132 5/4/2016 H-3 3,174 +/- 178 3,280 1,968 - 4,592 Pass SPW-2229 517/2016 H-3 3, 182 +/- 179 3,280 1,968 - 4,592 Pass SPW-2313 5/13/2016 H-3 3,183+/-179 3,280 1,968 - 4,592 Pass SPW-2341 5/13/2016 H-3 3,201 +/- 178 3,280 1,968 - 4,592 Pass SPW-2374 5/14/2016 H-3 3,037 +/- 175 3,280 1,968 - 4,592 Pass SPW-2411 5/17/2016 Sr-90 37.3 +/- 1.6 37.3 22.4 - 52.2 Pass SPW-2455 5/19/2016 Gr. Alpha 19.3 +/- 0.4 20.1 12.0-28.1 Pass SPW-2455 5/19/2016 Gr. Beta 28.6 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-2457 5/19/2016 U-238 48.2 +/- 2.4 41.7 25.0 - 58.4 Pass SPW-2504 5/20/2016 H-3 3,181 +/- 178 3,280 1,968 - 4,592 Pass SPW-2528 5/23/2016 H-3 2,998 +/- 175 3,280 1,968 - 4,592 Pass SPW-2566 5/24/2016 Gr. Alpha 19.8 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-2566 5/24/2016 Gr. Beta 30.4 +/- 0.3 28.9 17.3 - 40.4 Pass W-053116 4/29/2016 Cs-134 34.0 +/- 5.0 36.2 21.7 - 50.6 Pass W-053116 4/29/2016 Cs-137 78.8 +/- 7.0 71.9 43.1 - 100.6 Pass SPW-2704 6/1/2016 Sr-90 38.0 +/- 1.6 37.3 22.4 - 52.2 Pass SPW-2719 6/2/2016 Ra-228 18.1+/-2.1 17.7 10.6 - 24.8 Pass SPW-2749 6/3/2016 H-3 3,197 +/- 180 3,280 1,968 - 4,592 Pass SPW-2843 617/2016 H-3 3,133 +/- 179 3,280 1,968 - 4,592 Pass SPW-3227 6/17/2016 Ra-226 18.6 +/- 0.4 16.7 10.0 - 23.4 Pass W-061716 4/29/2016 Cs-134 37.3 +/- 8.2 36.2 21.7 - 50.6 Pass W-061716 4/29/2016 Cs-137 79.7 +/- 10.8 71.9 43.1 - 100.6 Pass SPW-3240 6/28/2016 Gr. Alpha 25.3 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-3240 6/28/2016 Gr. Beta 27.1 +/- 0.3 28.9 17.3 - 40.4 Pass 143

TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activit;i Limitsd Acceptance SPW-3241 7/1/2016 H-3 8,821 +/- 283 8,650 5,190 -12,110 Pass SPW-3309 7/1/2016 H-3 8,619 +/- 278 8,650 5,190 - 12,110 Pass SPW-3313 7/1/2016 Ra-228 16.6 +/- 2.0 17.7 10.6 - 24.8 Pass SPW-3328 7/6/2016 Sr-89 13.4 +/- 9.2 14.8 8.9 - 20.7 Pass SPW-3328 7/6/2016 Sr-90 12.3 +/- 1.3 11.4 6.8 - 16.0 Pass SPAP-3365 7/7/2016 Gr. Beta 39.7 +/- 0.1 42.2 25.3 - 59.0 Pass SPAP-3367 7/7/2016 Cs-134 1.2 +/- 0.7 1.2 0.7 - 1.7 Pass SPAP-3367 7/7/2016 Cs-137 94.4 +/- 2.8 94.0 56.4 -131.6 Pass SPW-3370 7/7/2016 C-14 4,444+/-17 4,735 2,841 - 6,629 Pass SPW-3373 7/7/2016 Ni-63 446 +/- 5 401 241 - 561 Pass SPW-3375 7/7/2016 Tc-99 545 +/- 9 539 324 - 755 Pass SPW-3519 7/14/2016 H-3 8,621 +/- 279 8650 5,190 - 12,110 Pass SPW-3688 6/29/2016 Ra-226 17.5 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-3711 7/20/2016 H-3 44,368 +/- 612 43,766 26,260 - 61,273 Pass SPW-3774 7/22/2016 H-3 45,259 +/- 619 43,766 26,260 - 61,273 Pass SPW-3776 7/22/2016 Gr. Alpha 23.3 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-3776 7/22/2016 Gr. Beta 27.5 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-3884 7/26/2016 H-3 45,850 +/- 623 43,766 26,260 - 61,273 Pass SPW-3950 7/28/2016 Ra-228 17.8+/-1.8 16.7 10 - 23 Pass SPW-3982 7/29/2016 H-3 45,273 +/- 619 43,766 26,260 - 61,273 Pass W-073016 4/29/2016 Cs-134 36.5 +/- 6.1 36.2 21.7 - 50.6 Pass W-073016 4/29/2016 Cs-1 37 80.6 +/- 7.5 71.9 43.1 - 100.6 Pass SPW-4134 8/4/2016 Ra-228 5.5 +/- 0.8 6.7 4.0 - 9.3 Pass SPW-4340 8/17/2016 Ra-228 19.9 +/- 2.0 16.7 10.0 - 23.4 Pass SPW-4386 7/15/2016 Ra-226 18.0 +/- 0.4 16.7 10.0 - 23.4 Pass W-082716 4/29/2016 Ra-228 32.5 +/- 5.2 36.2 21.7 - 50.6 Pass W-082716 4/29/2016 Ra-226 78.5 +/- 8.3 71.9 43.1 - 100.6 Pass SPW-4642 9/6/2016 U-238 45.8 +/- 2.5 41.7 25.0 - 58.4 Pass SPW-4999 9/26/2016 Sr-90 35.1 +/- 2.2 36.8 22.1 - 51.5 Pass SPW-5091 9/12/2016 Ra-226 18.2 +/- 0.4 16.7 10.0 - 23.4 Pass W-092716 4/29/2016 Cs-134 37.3 +/- 11.8 36.2 21.7 - 50.6 Pass W-092716 4/29/2016 Cs-137 78.3 +/- 11.2 71.9 43.1 - 100.6 Pass SPW-5165 9/30/2016 Gr. Alpha 22.2 +/- 0.4 20.1 12.0 -28.1 Pass SPW-5165 9/30/2016 Gr. Beta 27.2 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-5426 9/28/2016 Ra-226 18.2 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-5510 10/18/2016 H-3 44,398 +/- 618 43,766 26,260 - 61273 Pass SPW-5553 10/19/2016 U-238 50.0 +/- 2.6 41.7 25.0 - 58.4 Pass SPW-5555 10/19/2016 Ra-228 17.4+/-1.9 16.7 10.0 - 23.4 Pass SPW-5612 10/20/2016 H-3 44,681 +/- 622 43,766 26,260 - 61,273 Pass SPW-5741 10/25/2016 H-3 44,946 +/- 624 43,766 26,260 - 61,273 Pass SPU-5833 10/26/2016 H-3 10,018 +/- 946 8,622 5,173 - 12,071 Pass SPW-5862 10/28/2016 H-3 18,061 +/- 374 17,244 10,346 -24,141 Pass W-103116 4/29/2016 Cs-134 36.0 +/- 4.6 36.2 21.7 - 50.6 Pass W-103116 4/29/2016 Cs-137 81.1 +/- 7.3 71.9 43.1 -100.6 Pass 144

TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-5984 11 /2/2016 H-3 17,727 +/- 399 17,244 10,346 - 24,141 Pass SPW-6008 11 /4/2016 H-3 17,854 +/-402 17,244 10,346 - 24,141 Pass SPW-6124 11 /8/2016 Ra-228 14.4 +/- 1.9 16.0 9.6 - 22.4 Pass SPW-6132 11 /9/2016 H-3 18,135 +/- 374 17,243 10,346 - 24,140 Pass SPW-6135 10/12/2016 Ra-226 18.9 +/- 0.4 16.7 100 - 23.4 Pass SPW-6146 11/10/2016 H-3 17,488 +/- 398 17,243 10,346 - 24,140 Pass SPW-6222 11/12/2016 H-3 17,787 +/-408 17,243 10,346 - 24,140 Pass SPW-6318 11/16/2016 H-3 17,379 +/-408 17,243 10,346 - 24, 140 Pass SPW-6349 11/17/2016 H-3 17,893 +/- 371 17,243 10,346 - 24,140 Pass SPW-6424 11/19/2016 H-3 18,258 +/- 379 17,243 10,346 - 24,140 Pass W-112616 4/29/2016 Cs-134 35.0 +/- 6.0 36.2 21.7 - 50.6 Pass W-112616 4/29/2016 Cs-137 75.0 +/- 7.1 71.9 43.1 - 100.6 Pass SPW-6456 11 /28/2016 Sr-90 41.9+/-2.5 36.8 22.1 - 51.5 Pass SPW-6486 11/30/2016 Sr-90 35.6 +/- 2.2 36.6 21.9 - 51.2 Pass SPW-6490 11 /29/2016 Ra-226 18.8 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-6519 11/30/2016 Ni-63 438 +/- 4 400 240 - 560 Pass SPW-6527 12/1 /2016 U-238 49.5 +/- 2.5 41.7 25.0 - 58.4 Pass SPW-6616 12/3/2016 H-3 18,018 +/- 374 17,243 10,346 - 24,140 Pass SPW-6669 12/5/2016 H-3 18,237 +/- 377 17,243 10,346 - 24,140 Pass SPW-6735 12/9/2016 H-3 17,939 +/- 396 17,243 10,346 - 24,140 Pass SPW-6880 12/21/2016 H-3 17,835 +/- 396 17,243 10,346 - 24, 140 Pass SPW-6947 12/22/2016 Ni-63 450 +/- 4 400 240 - 560 Pass W-122316 4/29/2016 Cs-134 36.0 +/- 2.2 36.2 21.7 - 50.6 Pass W-122316 4/29/2016 Cs-134 76.1 +/- 2.9 71.9 43.1 - 100.6 Pass SPW-6948 12/30/2016 H-3 17,999 +/- 398 17,243 10,346 - 24,140 Pass SPW-6974 12/29/2016 Ra-226 17.6 +/- 0.4 16.7 10.0 - 23.4 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).

c Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2s.

NOTE: For fish, gelatin is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.

145

TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laborato!}'. results (4.66cr)

Acceptance Type LLD Activity° Criteria (4.66 cr)

SPW-289 Water 1/21/2016 Sr-90 0.55 0.28 +/- 0.29 SPW-291 Water 1/21/2016 Sr-90 0.61 0.15+/-0.30 1

SPW-293 Water 1/21/2016 C-14 147

-12 +/- 89 200 SPW-413 Water 2/1 /2016 Ra-228 0.86 1.86 +/- 0.60 2

W-020416 Water 2/4/2016 Gr. Alpha 0.43

-0.17 +/- 0.28 2

W-02041 6 Water 2/4/2016 Gr. Beta 0.73 0.36 +/- 0.53 4

W-020916 Water 2/9/2016 Ra-226 0.02 0.01 +/- 0.01 2

W-030716 Water 317/2016 Gr. Alpha 0.90

-0.36 +/- 0.32 2

W-030716 Water 317/2016 Gr. Beta 1.59

-0.62 +/- 0.71 4

SPDW-70045 Water 3/29/2016 Ra-226 0.03 0.01 +/- 0.02 2

SPDW-1234 Water 3/30/2016 Gr. Alpha 0.44

-0.05 +/- 0.30 2

SPDW-1234 Water 3/30/2016 Gr. Beta 0.79

-0.54 +/- 0.54 4

SPW-1738 Water 4/21 /2016 Ra-228 1.05 0.13 +/- 0.50 2

SPW-1822 Water 4/23/2016 Gr. Alpha 0.50

-0.18 +/- 0.33 2

SPW-1822 Water 4/23/2016 Gr. Beta 0.08

-0.35 +/- 0.51 4

SPW-2051 Water 4/12/2016 Ra-226 0.02 0.03 +/- 0.02 2

SPW-2069 Water 5/3/201 6 1-131 0.15 0.06 +/- 0.09 1

SPW-2133 Water 5/4/2016 H-3 148 55 +/- 76 200 SPW-2230 Water 517/2016 H-3 149

-11 +/- 73 200 SPW-2314 Water 5/13/2016 H-3 150

-29 +/- 72 200 SPW-2342 Water 5/13/2016 H-3 143 50 +/- 74 200 SPW-2364 Water 5/13/2016 1-131 0.22

-0.03 +/- 0.12 SPW-2375 Water 5/1 4/2016 H-3 146 1 +/- 70 200 SPW-241 0 Water 5/17/2016 Sr-90 0.59 0.10 +/- 0.29 SPW-2454 Water 5/19/2016 Gr. Alpha 0.47

-0.21 +/- 0.31 2

SPW-2454 Water 5/19/2016 Gr. Beta 0.77

-0.49 +/- 0.52 4

SPW-2456 Water 5/19/2016 U-238 0.15 0.00 +/- 0.09 SPW-2485 Water 5/20/2016 1-131 0.18

-0.01 +/- 0.10 SPW-2505 Water 5/20/2016 H-3 144 64 +/- 75 200 SPW-2529 Water 5/23/2016 H-3 152

-3 +/- 75 200 SPW-2530 Water 5/23/2016 Ra-228 0.96

-0.12 +/- 0.43 2

SPW-2565 Water 5/24/2016 Gr. Alpha 0.47 0.03 +/- 0.33 2

SPW-2565 Water 5/24/2016 Gr. Beta 0.77

-0.23 +/- 0.53 4

SPW-2703 Water 6/1 /2016 Sr-89 0.68

-0.13 +/- 0.50 5

SPW-2703 Water 6/1/2016 Sr-90 0.55 0.11 +/- 0.27 SPW-271 8 Water 6/2/201 6 Ra-228 0.67 0.23 +/- 0.34 2

SPW-2720 Water 6/2/2016 1-131 0.16 0.01 +/- 0.09 SPW-2750 Water 6/3/2016 H-3 151

-31 +/- 73 200 SPW-2844 Water 617/2016 H-3 148

-55 +/- 75 200 SPMl-2959 Milk 6/14/2016 1-131 0.16 0.09 +/-0.10 SPW-3137 Water 6/23/2016 1-131 0.15

-0.03 +/- 0.08 1

SPW-3226 Water 6/17/2016 Ra-226 0.02

-0.01 +/- 0.04 2

SPW-3239 Water 6/28/2016 Gr. Alpha 0.40

-0.15 +/- 0.26 2

SPW-3239 Water 6/28/2016 Gr. Beta 0.73 0.14 +/- 0.52 4

SPW-3687 Water 6/29/2016 Ra-226 0.04 0.03 +/- 0.03 2

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

• 1-131(G); iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net aclivity result.

146

TABLE A-4. In-House "Blank" Samples Lab Code Sample Type SPW-3312 Water SPW-3327 Water SPW-3327 Water SPAP-3364 AP SPW-3370 Water SPW-3372 Water SPW-3374 Water SPW-3710 Water SPW-3775 Water SPW-3775 Water SPW-3884 Water SPW-3949 Water SPW-3982 Water SPW-4133 Water SPW-4257 Water SPW-4339 Water SPW-4385 Water SPW-4641 SPW-4684 SPW-4872 SPW-4998 SPW-4998 SPW-5090 SPW-5164 SPW-5164 SPW-5425 SPW-5323 SPW-5552 SPW-5554 SPW-5611 SPW-5613 SPW-5613 SPW-5740 SPW-5743 SPW-5861 SPW-5983 SPW-6007 SPW-6131 SPW-6134 SPW-6145 SPW-6317 SPW-6348 SPW-6423 SPW-6455 SPW-6455 SPW-6489 Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Date 7/1/2016 7/6/2016 7/6/2016 717/2016 7/7/2016 7/7/2016 7/7/2016 7/20/2016 7/22/2016 7/22/2016 7/26/2016 7/28/2016 7/29/2016 8/4/2016 8/11/2016 8/17/2016 7/15/2016 9/6/2016 9/8/2016 9/16/2016 9/26/2016 9/26/2016 8/19/2016 9/30/2016 9/30/2016 9/28/2016 10/7/2016 10/19/2016 10/19/2016 10/20/2016 10/21/2016 10/21/2016 10/25/2016 10/25/2016 10/28/2016 11/2/2016 11/4/2016 11/9/2016 10/12/2016 11/10/2016 11/16/2016 11/17/2016 11/19/2016 11/28/2016 11/28/2016 11/29/2016 Analysis0 Ra-228 Sr-89 Sr-90 Gr.Beta C-14 Ni-63 Tc-99 H-3 Gr. Alpha Gr. Beta H-3 Ra-228 H-3 Ra-228 1-131 Ra-228 Ra-226 U-238 H-3 1-131 Sr-89 Sr-90 Ra-226 Gr. Alpha Gr. Beta Ra-226 H-3 U-238 Ra-228 H-3 Gr. Alpha Gr. Beta H-3 Sr-90 H-3 H-3 H-3 H-3 Ra-226 H-3 H-3 H-3 H-3 Sr-89 Sr-90 Ra-226 Concentration a Laboratory results (4.66cr)

LLD Activityc 0.67 0.67 0.60 0.002 115 122 6.07 147 0.73 0.45 151 0.76 145 0.80 0.17 0.73 0.09 0.21 151 0.21 0.54 0.53 0.03 0.46 0.74 0.02 157 0.18 0.72 153 0.76 0.42 154 1.26 179 156 156 180 0.05 171 180 182 181 0.58 0.67 0.03 0.35 +/- 0.35 0.51 +/- 0.51

-0.14 +/- 0.26 0.005 +/- 0.001 49 +/- 71 115 +/- 76 1.00 +/-3.70 35 +/- 75 0.41 +/- 0.53

-0.14 +/- 0.30

-1 +/- 73 0.32 +/- 0.39 49 +/- 75 0.26 +/- 0.40

-0.01 +/- 0.10 0.36 +/- 0.39 0.75 +/- 0.09 0.00+/-0.13 48 +/-78 0.05 +/- 0.11 0.06 +/- 0.39

-0.03 +/- 0.24 0.03 +/- 0.02

-0.05 +/- 0.32

-0.02 +/- 0.52 0.07 +/- 0.05

-12 +/- 75 0.00 +/- 0.11 0.22 +/- 0.36 67 +/- 80

-0.55 +/- 0.51 0.02 +/- 0.29

-2 +/-72 0.72 +/- 0.67 129 +/- 91 8 +/-78

-34 +/- 73 80 +/- 92

-0.02 +/- 0.12

-46 +/- 80

-43 +/- 82

-45 +/- 88 8 +/- 95

-0.15 +/- 0.46 0.09 +/- 0.32 0.03 +/- 0.02 Acceptance Criteria (4.66 er) 2 5

1 0.01 200 200 10 200 2

4 200 2

200 2

1 2

2 200 5

2 2

4 2

200 2

200 2

4 200 200 200 200 200 2

200 200 200 200 5

2

' Liquid sample results are reported in pCi/Liter, air filters ( pCiim'), charcoal (pCi/charcoal canister), and solid samples {pCi/g).

' l-131(G); iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net activity result.

147

TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysis" Laborato!}'. results (4.66cr~

Acceptance Type LLD Activity° Criteria (4.66 cr)

SPW-6529 Water 12/1/2016 1-131 0.18

-0.03 +/- 0. 10 SPW-6616 Water 12/3/2016 H-3 180 72 +/- 92 200 SPW-6670 Water 12/5/2016 H-3 174 28 +/- 92 200 SPW-6735 Water 12/9/2016 H-3 152 2 +/- 73 200 SPW-6792 Water 12/15/2016 1-131 0.17 0.03 +/- 0.12 SPW-6819 Water 12/16/2016 H-3 158 14 +/- 77 200 SPW-6879 Water 12/21/2016 H-3 147 80 +/- 75 200 SPW-6947 Water 12/22/201 6 Ni-63 93 26 +/- 57 200 SPW-6973 Water 12/29/2016 Ra-226 0.03 0.03 +/- 0.02 2

• Liquid sample results are reported in pCi/Liter, air filters ( pCiim\\ charcoal (pCi/charcoal canister), and solid samples (pCi/g).

0 l-131(G); iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net activity result.

148

TABLE A-5. In-House "Duplicate" Samples Lab Code AP-010416 SPS-62, 63 WW-1 25, 126 SPS-199, 200 SPS-199, 200 AP-011116 AP-011216 WW-262, 263 WW-346, 347 WW-283, 284 AP-011916 AP-012016 AP-020116 SWU-472, 473 SG-493, 494 SG-493, 494 SG-493, 494 AP-020816 AP-020916 SPS-619, 620 WW-640, 641 AP-021916 WW-822, 823 DW-70010, 70011 DW-70010, 70011 SW-934, 935 SPS-913, 914 SPS-913, 914 SPS-913, 914 SPS-913, 914 AP-030716 F-1303, 1304 SG-976, 977 SG-976, 977 PM-1094, 1095 Ml-1042,1043 DW-70023, 70024 DW-70023, 70024 DW-70014, 70015 DW-70026, 70027 DW-70038, 70039 DW-70035, 70036 DW-70035, 70036 AP-031516 AP-032116 AP-1218,1219 AP-1719,1720 AP-033016 SPS-1260, 1261 XW-1467, 1468 XWW-1530, 1531 AP-1827, 1828 AP-1323,1324 LW-1446,1447 Date 1/4/2016 117/2016 1/7/2016 117/2016 117/2016 1/11/2016 1/12/2016 1/14/2016 1/14/2016 1/18/2016 1/19/2016 1/20/2016 211 /2016 2/212016 2/6/2016 2/6/2016 2/6/2016 2/8/2016 2/9/2016 2/18/2016 2/18/2016 2/19/2016 2/26/2016 2/29/2016 2/29/2016 3/1/2016 3/3/2016 3/3/2016 3/3/2016 3/3/2016 317/2016 317/2016 3/8/2016 3/8/2016 3/9/2016 317/2016 317/2016 317/2016 317/2016 317/2016 3/8/2016 3/8/2016 3/8/2016 3/15/2016 3/21/2016 3/24/2016 3/28/2016 3/30/2016 3/30/2016 3/30/2016 3/30/2016 3/30/2016 3/31/2016 3/31/2016 Analysis Gr. Beta K-40 H-3 Cs-137 K-40 Gr. Beta Gr. Beta H-3 H-3 H-3 Gr. Beta Gr. Beta Gr. Beta Gr. Beta Ac-228 K-40 Pb-214 Gr. Beta Be-7 K-40 H-3 Gr. Beta H-3 Ra-226 Ra-228 Gr. Beta Cs-137 K-40 Ra-226 Ra-228 Gr. Beta K-40 Ra-226 Ra-228 K-40 K-40 Ra-226 Ra-228 Gr. Alpha Gr. Alpha Gr. Alpha Ra-226 Ra-228 Gr. Beta Gr. Beta Be-7 Be-7 Gr. Beta K-40 H-3 H-3 Be-7 Be-7 Gr. Beta First Result 0.044 +/- 0.006 21.1 +/- 1.9 659 +/- 102 0.09 +/- 0.02 7.60 +/- 0.60 0.024 +/- 0.005 0.030 +/- 0.004 153 +/- 78 1,036+/-117 437 +/- 92 0.042 +/- 0.005 0.023 +/- 0.003 0.023 +/- 0.005 4.37 +/- 0.47 2.10 +/- 0.20 5.79 +/- 0.57 1.84 +/- 0.11 0.020 +/- 0.004 0.032 +/- 0.005 20.0+/-1.8 90.1 +/- 75.0 0.021 +/- 0.003 2,770 +/- 173 4.88 +/- 0.29 3.00 +/- 0.77 0.94 +/- 0.52 0.08 +/- 0.03 17.45 +/- 0.94 1.02 +/- 0.08 1.09 +/- 0.15 0.018 +/- 0.005 3.320 +/- 0.475 6.75 +/- 0.25 9.21 +/- 0.49 14.01 +/- 0.68 1,684 +/- 124 3.40 +/- 0.43 4.46 +/- 0.83 13.38 +/- 1.58 3.46 +/- 0.79 1.14+/-0.89 0.47 +/- 0.10 0.56 +/- 0.45 0.014 +/- 0.003 0.014 +/- 0.004 0.135 +/- 0.065 0.075 +/- 0.008 0.023 +/- 0.004 18.00 +/- 1.92 310 +/- 87 198 +/- 84 0.069 +/- 0.011 0.206 +/- 0.120 2.36 +/- 0.93 149 Concentration '

Second Result 0.051 +/- 0.006 21.2 +/- 2.1 748 +/- 106 0.08 +/- 0.03 8.62 +/- 0.62 0.027 +/- 0.005 0.034 +/- 0.004 141 +/- 78 959 +/- 115 427 +/- 91 0.037 +/- 0.004 0.030 +/- 0.004 0.023 +/- 0.005 4.60 +/- 0.49 2.13 +/- 0.20 5.50 +/- 0.69 1.91 +/- 0.11 0.019 +/- 0.004 0.041 +/- 0.006 19.1 +/- 1.6 153.6 +/- 78.4 0.025 +/- 0.004 2,974 +/- 178 4.93 +/- 0.28 1.90 +/- 0.62 1.36 +/- 0.60 0.10 +/- 0.03 16.83 +/- 0.95 1.13 +/- 0.17 1.13 +/- 0.17 0.021 +/- 0.005 3.508 +/- 0.396 6.28 +/- 0.22 9.09 +/- 0.49 14.47 +/- 0.72 1,804+/-119 2.68 +/- 0.35 5.74 +/- 0.94 11.40 +/- 1.43 3.08 +/-0.74 1.73 +/- 0.95 0.45 +/- 0.09 0.47 +/- 0.44 0.016 +/- 0.004 0.020 +/- 0.004 0.167 +/-0.081 0.076 +/- 0.007 0.025 +/- 0.004 19.67 +/- 1.77 295 +/- 86 162 +/- 82 0.072 +/- 0.011 0.197 +/- 0.091 2.23 +/- 1.01 Averaged Result 0.047 +/- 0.004 21.2 +/- 1.4 703 +/- 74 0.08 +/- 0.02 8.11 +/- 0.43 0.026 +/- 0.003 0.032 +/- 0.003 147 +/- 55 997 +/- 82 432 +/- 65 0.040 +/- 0.003 0.027 +/- 0.002 0.023 +/- 0.004 4.49 +/- 0.34 2.12+/-0.14 5.65 +/- 0.45 1.88 +/- 0.08 0.020 +/- 0.003 0.036 +/- 0.004 19.5 +/- 1.2 121.8 +/- 54.2 0.023 +/- 0.002 2,872 +/- 124 4.91 +/- 0.20 2.45 +/- 0.49 1.15 +/- 0.40 0.09 +/- 0.02 17.14 +/- 0.67 1.07 +/- 0.09 1.11 +/- 0.11 0.019 +/- 0.003 3.414 +/- 0.309 6.52 +/- 0.17 9.15 +/- 0.35 14.24 +/- 0.49 1,744 +/- 86 3.04 +/- 0.28 5.10 +/- 0.63 12.39+/-1.07 3.27 +/- 0.54 1.44 +/- 0.65 0.46 +/- 0.07 0.52 +/- 0.31 0.015 +/- 0.002 0.017 +/- 0.003 0.151 +/- 0.052 0.076 +/- 0.005 0.024 +/- 0.003 18.84 +/- 1.30 303 +/- 61 180 +/- 59 0.071 +/- 0.008 0.202 +/- 0.076 2.29 +/- 0.69 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 Pass Pass Pass Pass Pass Pass Pass

TABLE A-5. In-House "Duplicate" Samples Lab Code WW-1740,1741 SPS-1344, 1345 SPS-1344, 1345 SPS-1344, 1345 SPS-1 344, 1345 P-1509, 1510 AP-041116 SS-1551, 1552 SS-1551, 1552 SS-1551, 1552 SS-1551,1552 SS-1551,1552 SS-1551,1552 SS-1551,1552 SS-1593,1594 WW-1677, 1678 WW-1783,1784 BS-1804,1805 WW-2021,2022 XWW-2240, 2241 XWW-2109, 2110 SPS-2130, 2131 AP-042516 BS-2065, 2066 AP-042716 SPS-1999, 2000 S0-2153,2154 S0-2153,2154 S0-2153,2154 S0-2153,2154 W-2394,2395 VE-2284,2285 AP-051016 SG-2261, 2262 SG-2261, 2262 BS-2439, 2440 WW-2534,2535 AP-051716 SPS-2945, 2946 SPS-2945, 2946 SPS-2578, 2579 AP-052516 G-2642,2643 S0-2663, 2664 S0-2663, 2664 S0-2663, 2664 S0-2663, 2664 S0-2663, 2664 S0-2663, 2664 SPS-2817, 2818 DW-70091, 70092 DW-70091, 70092 BS-2925,2926 SPS-2796, 2797 SPS-2882, 2883 SPS-2882, 2883 DW-70102, 70103 Date 4/2/2016 4/4/2016 4/4/2016 4/4/2016 4/4/2016 4/8/2016 4/11 /2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/14/2016 4/14/2016 4/18/2016 4/18/2016 4/18/2016 4/19/2016 4/25/2016 4/25/2016 4/25/2016 4/27/2016 4/28/2016 5/2/2016 5/2/2016 5/2/2016 5/2/2016 5/5/2016 5/9/2016 5/10/2016 5/10/2016 5/10/2016 5/12/2016 5/16/2016 5/17/2016 5/19/2016 5/19/2016 5/24/2016 5/25/2016 5/26/2016 5/26/2016 5/26/2016 5/26/2016 5/26/2016 5/26/2016 5/26/2016 5/31/2016 6/1/2016 6/1/2016 6/3/2016 6/2/2016 617/2016 617/2016 6/13/2016 Analysis H-3 K-40 Pb-214 Ac-228 Cs-137 H-3 Gr. Beta Gr. Beta K-40 Tl-208 Bi-214 Pb-212 Ra-226 Ac-228 K-40 Ra-226 H-3 K-40 H-3 H-3 H-3 K-40 Gr. Beta K-40 Gr. Beta K-40 K-40 Cs-137 Ra-226 Pb-214 H-3 K-40 Gr. Beta Ac-228 Pb-214 K-40 H-3 Gr. Beta K-40 Be-7 Pb-214 Gr. Beta Be-7 Cs-137 K-40 Tl-208 Pb-212 Ra-226 Ac-228 K-40 Ra-226 Ra-228 K-40 K-40 K-40 Be-7 Ra-226 First Result 21,162 +/- 120 17.98 +/- 0.93 1.12+/-0.09 1.23 +/- 0.15 0.13 +/- 0.03 1,084 +/- 120 0.020 +/- 0.004 8.71 +/- 1.11 3.50 +/- 0.25 0.05 +/- 0.02 0.10 +/- 0.02 0.13 +/- 0.02 0.35 +/-0.17 0.16 +/- 0.05 14.80 +/- 0.73 0.23 +/- 0.13 768 +/- 111 0.79 +/- 0.02 5,548 +/- 221 638 +/- 104 3461 +/- 185 7.80 +/- 0.84 0.020 +/- 0.004 14.40 +/- 1.50 0.023 +/- 0.003 19.84 +/- 1.76 21.80 +/- 0.81 0.11 +/- 0.03 1.50 +/- 0.29 0.56 +/- 0.06 736 +/- 106 3.50 +/- 0.25 0.020 +/- 0.005 34.4+/-1.2 29.5 +/- 3.0 9.96 +/- 0.91 14,342 +/- 354 0.014 +/- 0.004 30.71 +/- 0.74 1.55 +/- 0.24 0.96 +/- 0.12 0.022 +/- 0.004 0.443 +/- 0.178 0.08 +/- 0.03 12.44 +/- 0.68 0.13 +/- 0.02 0.43 +/- 0.04 1.19 +/-0.34 0.45 +/- 0.09 12.10 +/- 0.70 5.61 +/- 0.29 1.45 +/- 0.58 7.74 +/- 0.44 20.91 +/- 2.38 14.64 +/- 0.52 2.00 +/- 0.25 0.34 +/- 0.09 150 Concentration

• Second Result 21,091 +/- 427 17.14+/-0.96 1.04 +/- 0.08 1.33 +/- 0.19 0.13 +/- 0.03 1,038+/-119 0.019 +/- 0.004 8.88+/-1.13 3.06 +/- 0.28 0.05 +/- 0.02 0.09 +/- 0.02 0.11 +/- 0.02 0.30 +/- 0.17 0.17 +/- 0.05 14.89 +/- 0.78 0.35 +/- 0.15 632 +/- 107 0.87 +/- 0.19 5,707 +/- 224 543 +/- 101 3250 +/- 180 6.80 +/- 0.60 0.023 +/- 0.004 14.72+/-1.19 0.019 +/- 0.003 18.963 +/- 2.42 21.17 +/- 0.85 0.11 +/- 0.07 1.22 +/- 0.29 0.57 +/- 0.06 631 +/- 102 3.06 +/- 0.28 0.018 +/- 0.005 34.4 +/- 1.4 31.9 +/- 3.3 10.27 +/- 0.76 14,613 +/- 357 0.015 +/- 0.004 31.75 +/- 0.78 1.90 +/- 0.35 0.80 +/- 0.14 0.022 +/- 0.004 0.247 +/- 0.247 0.07 +/- 0.03 11.64 +/- 0.63 0.14+/-0.03 0.41 +/- 0.04 0.87 +/- 0.28 0.53 +/-0.10 11.05 +/- 0.70 5.53 +/- 0.30 1.91 +/- 0.62 7.86 +/- 0.42 21.16 +/- 1.82 14.60 +/- 0.52 1.94 +/- 0.20 0.36 +/- 0.08 Averaged Result 21,126 +/- 222 17.56 +/- 0.67 1.08 +/- 0.06 1.28 +/-0.12 0.13 +/- 0.02 1,061 +/- 85 0.019 +/- 0.003 8.80 +/- 0.79 3.28 +/- 0.19 0.05 +/- 0.01 0.10 +/- 0.02 0.12 +/- 0.01 0.32 +/- 0.12 0.17 +/- 0.04 14.85 +/- 0.53 0.29 +/- 0.10 700 +/- 77 0.83 +/- 0.10 5,627 +/- 157 591 +/- 72 3356 +/- 129 7.30 +/- 0.52 0.022 +/- 0.003 14.56 +/- 0.96 0.021 +/- 0.002 19.40 +/- 1.50 21.48 +/- 0.59 0.11+/-0.04 1.36 +/- 0.21 0.57 +/- 0.04 683 +/- 74 3.28 +/- 0.19 0.019 +/- 0.003 34.4 +/- 0.9 30.7 +/- 2.2 10.11 +/- 0.59 14,477 +/- 252 0.014 +/- 0.003 31.23 +/- 0.54 1.73 +/- 0.21 0.88 +/- 0.09 0.022 +/- 0.003 0.345 +/- 0.152 0.07 +/- 0.02 12.04 +/- 0.46 0.14 +/- 0.02 0.42 +/- 0.03 1.03 +/- 0.22 0.49 +/- 0.07 11.58+/-0.49 5.57 +/- 0.21 1.68 +/- 0.42 7.80 +/- 0.30 21.04 +/- 1.50 14.62 +/- 0.37 1.97+/-0.16 0.35 +/- 0.06 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 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

TABLE A-5. In-House "Duplicate" Samples Lab Code DW-70102, 70103 AP-061416 SG-3144, 3145 SG-3144, 3145 SPS-3165, 3166 SPS-3323, 3324 WW-3231, 3232 AP-3830,3831 AP-070516A AP-070516B XWW-3605,3606 DW-70135,70136 DW-70132,70133 DW-701 32,70133 AP-071216 DW-70150,70151 SPS-3649,3650 SPS-3649,3650 SPS-3649,3650 SPS-3649,3650 AP-071816 DW-70163,70164 WW-3761,3762 SPS-4003,4004 AP-072516 VE-3936,3937 VE-3936,3937 VE-3936,3937 VE-3959,3960 VE-3959,3960 VE-3959,3960 DW-70169,70170 DW-70169,70170 AP-080116 SS-4131,4132 SS-4131,4132 SPS-4087,4088 WW-4976,4977 SPS-4266,4267 AP-081616 VE-4399,4400 VE-4399,4400 WW-5394,5395 SPS-4441,4442 AP-082216 VE-4462,4463 VE-4462,4463 WW-4594,4595 WW-4663,4664 SPS-4529,4530 AP-083016A AP-083016B VE-4615,4616 Date 6/1 3/2016 6/14/2016 6/17/2016 6/17/2016 6/22/2016 6/24/2016 6/27/2016 6/29/2016 7/5/201 6 7/5/2016 717/2016 7/8/2016 7/8/2016 7/8/2016 7/12/2016 7/14/2016 7/15/2016 7/15/2016 7/15/2016 7/15/2016 7/18/2016 7/19/2016 7/20/2016 7/23/2016 7/25/2016 7/25/2016 7/25/2016 7/25/2016 7/27/2016 7/27/2016 7/27/2016 7/28/2016 7/28/2016 8/1/2016 8/1/2016 8/1/2016 8/2/2016 8/4/2016 8/10/2016 8/16/2016 8/18/2016 8/1 8/2016 8/18/2016 8/22/2016 8/22/201 6 8/22/2016 8/22/2016 8/26/2016 8/26/2016 8/26/2016 8/30/2016 8/30/2016 8/3 1/2016 Analysis Ra-228 Gr. Beta Be-7 K-40 K-40 K-40 H-3 Gr. Beta Gr. Beta Gr. Beta H-3 Gr. Alpha Ra-226 Ra-228 Gr. Beta Gr. Alpha Cs-137 K-40 Pb-214 Ac-228 Gr. Beta Gr. Alpha H-3 K-40 Gr. Beta Sr-90 Be-7 K-40 Sr-90 Be-7 K-40 Ra-226 Ra-228 Gr. Beta K-40 Cs-137 K-40 H-3 K-40 Gr. Beta K-40 Be-7 H-3 K-40 Gr. Beta Be-7 K-40 H-3 H-3 K-40 Gr. Beta Gr. Beta K-40 First Result 0.93 +/- 0.47 0.026 +/- 0.004 2.23 +/- 0.12 7.57 +/- 0.25 21.14+/-2.27 18.67 +/- 1.57 414 +/- 104 0.088 +/- 0.01 2 0.018 +/- 0.002 0.025 +/- 0.005 3,316 +/- 186 3.68 +/- 1.01 1.32 +/- 0.14 3.92 +/- 0.94 0.014 +/- 0.004 5.00 +/- 1.06 0.12 +/- 0.03 16.68 +/- 0.79 1.20 +/- 0.08 1.28+/-0.16 0.022 +/- 0.005 1.08 +/- 0.66 347 +/- 90 7.15+/-1.59 0.023 +/- 0.004 0.048 +/- 0.007 0.49 +/- 0.15 4.70 +/- 0.35 0.002 +/- 0.002 0.30 +/- 0.14 4.01 +/- 0.37 0.83 +/- 0.11 1.85 +/- 0.63 0.029 +/- 0.003 12.47 +/- 0.71 0.10 +/- 0.03 17.06 +/- 1.58 17,043 +/- 390 1.06 +/- 0.47 0.029 +/- 0.005 3.85 +/- 0.23 0.30 +/- 0.08 947 +/- 122 20.55 +/- 2.23 0.021 +/- 0.005 0.91 +/- 0.09 7.48 +/- 0.26 675 +/- 107 607 +/- 104 21.98 +/- 2.52 0.030 +/- 0.003 0.032 +/- 0.009 2.96 +/- 0.16 151 Concentration '

Second Result 1.11 +/- 0.53 0.023 +/- 0.004 2.24 +/- 0.12 7.09 +/- 0.23 22.88 +/- 1.60 21.53+/-1.65 498 +/- 108 0.093 +/- 0.015 0.014 +/- 0.002 0.026 +/- 0.005 3,316 +/- 181 2.76 +/- 0.98 1.11 +/- 0.15 2.94 +/- 0.90 0.018 +/- 0.004 4.43 +/- 1.04 0.1 2 +/- 0.03 16.52 +/- 0.86 1.17 +/- 0.08 1.28 +/- 0.16 0.024 +/- 0.005 1.36 +/- 0.70 466 +/- 96 6.86 +/- 1.21 0.020 +/- 0.004 0.058 +/- 0.010 0.51 +/- 0.15 4.86 +/- 0.37 0.003 +/- 0.001 0.25 +/- 0.12 4.16 +/- 0.34 0.69 +/- 0.11 1.31 +/- 0.84 0.033 +/- 0.003 13.24 +/- 0.81 0.13 +/- 0.04 19.5 +/- 1.97 16,821 +/- 388 1.69 +/- 0.52 0.025 +/- 0.004 3.27 +/- 0.41 0.45 +/- 0.20 846 +/- 119 19.69 +/- 1.74 0.015 +/- 0.005 0.89 +/- 0.11 7.60 +/- 0.23 788 +/- 111 501 +/- 100 21.85 +/- 1.56 0.035 +/- 0.004 0.026 +/- 0.004 3.11+/-0.1 7 Averaged Result 1.02 +/- 0.35 0.024 +/- 0.003 2.24 +/- 0.08 7.33 +/- 0.17 22.01 +/- 1.39 20.10 +/- 1.14 456 +/- 75 0.091 +/- 0.010 0.016 +/- 0.002 0.025 +/- 0.004 3,316 +/- 130 3.22 +/- 0.70 1.22+/-0.10 3.43 +/- 0.65 O.D16 +/- 0.003 4.72 +/- 0.74 0.12 +/- 0.02 16.6 +/- 0.58 1.19 +/- 0.06 1.28 +/- 0.11 0.023 +/- 0.003 1.22 +/- 0.48 407 +/- 66 7.00 +/- 1.00 0.022 +/- 0.003 0.053 +/- 0.006 0.50 +/- 0.10 4.78 +/- 0.25 0.003 +/- 0.001 0.27 +/- 0.09 4.08 +/- 0.25 0.76 +/- 0.08 1.58 +/- 0.53 0.031 +/- 0.002 12.86 +/- 0.54 0.12 +/-0.02 18.28 +/- 1.26 16,932 +/- 275 1.375 +/- 0.35 0.027 +/- 0.003 3.56 +/- 0.24 0.37 +/- 0.11 896 +/- 85 20.1 2+/-1.41 0.018 +/- 0.003 0.90 +/- 0.07 7.54 +/- 0.17 731 +/- 77 554 +/- 72 21.92 +/- 1.48 0.033 +/- 0.002 0.029 +/- 0.005 3.03 +/- 0.11 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 Pass Pass Pass Pass Pass Pass

TABLE A-5. In-House "Duplicate" Samples Lab Code AP-090216 AP-090616 Ml-4751,4752 Ml-4751,4752 SW-4772,4773 WW-5285,5286 Ml-4826,4827 VE-4868,4869 VE-4868,4869 CF-4934,4935 CF-4934,4935 AP-09201 6 DW-70196,70197 F-4955,4956 VE-5044,5045 VE-5044,5045 WW-5219,5220 SPS-5087,5088 AP-092716 AP-5660,5661 AP-5681,5682 VE-5110,5111 AP-5154,5155 AP-5702,5703 Ml-5264,5265 Ml-5264,5265 SS-5547,5548 SS-554 7, 5548 SS-5547,5548 SS-5547,5548 SS-5547,5548 SS-5547,5548 AP-101116 WW-5526.5527 WW-5639,5640 WW-5723,5724 F-5811,5812 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 SS-5879,5880 SS-5879,5880 LW-6072,6073 BS-6009, 6010 BS-6009, 6010 F-6211,6212 F-6211,6212 DW-70230, 70231 DW-70230, 70231 F-6093,6094 Date 9/2/2016 9/6/2016 917/2016 917/2016 9/8/2016 9/13/2016 9/14/201 6 9/15/2016 9/15/2016 9/19/2016 9/19/2016 9/20/2016 9/20/2016 9/20/2016 9/20/2016 9/20/2016 9/20/2016 9/23/2016 9/27/2016 9/28/2016 9/27/2016 9/28/2016 9/29/2016 9/30/2016 10/4/2016 10/4/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/19/2016 10/18/2016 10/20/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/25/2016 10/25/2016 10/27/2016 10/27/2016 10/27/2016 10/28/2016 10/28/2016 10/28/2016 10/28/2016 10/31/2016 Analysis Gr. Beta Gr. Beta K-40 Sr-90 H-3 H-3 K-40 Gr. Beta K-40 K-40 Be-7 Gr. Beta Gr. Alpha K-40 Be-7 K-40 H-3 K-40 Gr. Beta Be-7 Be-7 K-40 Be-7 Be-7 K-40 Sr-90 Gr. Beta K-40 Tl-208 Bi-214 Pb-212 Ac-228 Gr. Beta H-3 H-3 H-3 K-40 Cs-137 K-40 Tl-208 Pb-212 Bi-214 Ac-228 Ra-226 Gr. Beta K-40 Cs-137 Gr. Beta Cs-137 K-40 Gr. Beta K-40 Ra-226 Ra-228 K-40 First Result 0.022 +/- 0.004 0.023 +/- 0.005 1,693+/-112 1.23 +/- 0.38 196 +/- 91 18,010 +/- 400 1,372.6 +/- 105 2.50 +/- 0.06 2.20 +/- 0.17 11.47 +/- 0.82 0.43 +/- 0.22 0.021 +/- 0.004 13.8 +/- 1.36 3.40 +/- 0.44 0.46 +/- 0.05 4.37 +/- 0.12 63,744 +/- 743 21.04 +/- 2.32 0.031 +/- 0.005 0.093 +/- 0.014 0.079 +/- 0.019 1.82+/-0.15 0.237 +/- 0.116 0.084 +/- 0.015 1,636+/-128 2.00 +/- 0.44 11.27 +/- 1.19 8.03 +/- 0.45 0.04 +/- 0.02 0.14 +/- 0.03 0.12 +/- 0.02 0.10 +/- 0.05 0.032 +/- 0.004 18,865 +/- 408 192 +/- 103 36,012 +/- 560 0.91 +/- 0.30 0.05 +/- 0.02 9.82 +/- 0.60 0.10 +/- 0.02 0.32 +/- 0.03 0.20 +/- 0.04 0.41 +/- 0.08 0.45 +/- 0.23 16.49 +/- 1.01 14.94 +/- 0.83 0.06 +/- 0.03 0.88 +/- 0.49 0.14 +/-0.08 17.04 +/- 1.58 3.25 +/- 0.07 2.45 +/- 0.33 4.00 +/- 0.20 5.30 +/- 0.80 3.77 +/- 0.50 152 Concentration '

Second Result 0.027 +/- 0.004 0.023 +/- 0.005 1,760 +/- 99 1.00 +/- 0.33 236 +/- 93 18,686 +/- 407 1, 198.1 +/- 97 2.57 +/- 0.06 2.30 +/- 0.17 11.76 +/- 0.50 0.46 +/- 0.13 0.017 +/- 0.004 15.28+/-1.36 2.86 +/- 0.39 0.50 +/- 0.11 4.68 +/- 0.24 64,755 +/- 749 18.84 +/- 1.88 0.032 +/- 0.005 0.086 +/- 0.019 0.071 +/- 0.015 2.14 +/-0.18 0.195 +/- 0.096 0.070 +/- 0.018 1,610 +/- 124 1.28 +/- 0.37 9.47 +/- 1.20 7.23 +/- 0.46 0.04 +/- 0.02 0.12 +/- 0.03 0.11 +/- 0.02 0.16 +/- 0.05 0.028 +/- 0.004 18,904 +/- 408 52 +/- 98 36,207 +/- 561 0.75 +/- 0.22 0.03 +/- 0.02 10.77 +/- 0.61 0.14 +/- 0.03 0.33 +/- 0.03 0.27 +/- 0.04 0.48 +/- 0.09 0.61 +/- 0.27 17.71 +/- 1.03 15.26 +/- 0.84 0.09 +/- 0.04 1.53 +/- 0.56 0.13 +/- 0.06 18.30+/-1.42 3.27 +/- 0.07 2.49 +/- 0.37 4.10 +/- 0.30 5.20 +/- 0.80 3.51 +/- 0.44 Averaged Result 0.024 +/- 0.003 0.023 +/- 0.003 1,726 +/-75 1.11 +/- 0.25 216 +/- 65 18,348 +/- 286 1,285.4 +/- 71 2.53 +/- 0.04 2.25+/-0.12 11.61 +/- 0.48 0.45 +/- 0.13 0.019 +/- 0.003 14.54 +/- 0.96 3.13 +/- 0.30 0.48 +/- 0.06 4.53 +/- 0.13 64,250 +/- 527 19.94 +/- 1.49 0.031 +/- 0.003 0.089 +/- 0.012 0.075 +/- 0.012 1.98+/-0.12 0.216 +/- 0.075 0.077 +/- 0.012 1,623 +/- 89 1.64 +/- 0.29 10.37 +/- 0.84 7.63 +/- 0.32 0.04 +/- 0.01 0.13+/-0.02 0.11 +/-0.01 0.13 +/-0.04 0.030 +/- 0.003 18,884 +/- 289 122 +/- 71 36,110 +/-396 0.83 +/- 0.19 0.04 +/- 0.02 10.29 +/- 0.43 0.12 +/- 0.02 0.32 +/- 0.02 0.23 +/- 0.03 0.44 +/- 0.06 0.53 +/- 0.18 17.10 +/- 0.72 15.10 +/- 0.59 0.08 +/- 0.02 1.21 +/- 0.37 0.13 +/-0.05 17.67 +/- 1.06 3.26 +/- 0.05 2.47 +/- 0.25 4.05 +/- 0.18 5.25 +/- 0.57 3.64 +/- 0.33 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 Pass Pass Pass Pass Pass Pass Pass Pass

TABLE A-5. In-House "Duplicate" Samples Concentration '

Averaged Lab Code Date Anal~s is First Result Second Result Result Acce~ta nce AP-110116 11/1/2016 Gr. Beta 0.021 +/- 0.004 0.024 +/- 0.004 0.023 +/- 0.003 Pass S-5963, 5964 11/1/2016 K-40 20.35 +/- 2.29 18.59 +/- 1.90 19.47 +/- 1.49 Pass SG-6119, 6120 11/1/2016 Ac-228 5.70 +/- 0.44 6.28 +/- 0.57 5.99 +/- 0.36 Pass SG-6119, 6120 11/1/2016 Gr. Alpha 21.59 +/- 1.88 24.35 +/- 1.93 22.97 +/- 1.35 Pass SG-6119, 6120 11/1/2016 K-40 4.89+/-1.10 5.90 +/- 1.08 5.40 +/- 0.77 Pass SG-6119, 6120 11/1/2016 Pb-214 3.99 +/- 0.21 4.35 +/- 0.32 4.17 +/- 0.19 Pass S-6051, 6052 11/4/2016 K-40 7.05 +/- 0.60 7.56 +/- 0.53 7.31 +/- 0.40 Pass WW-6297, 6298 11/8/2016 H-3 207 +/- 98 165 +/- 97 186 +/- 69 Pass WW-6341,6342 11/8/2016 H-3 1,356+/- 140 1,404 +/- 141 1,380 +/- 99 Pass S0-6406,6407 11/9/2016 Cs-137 0.36 +/- 0.04 0.43 +/- 0.05 0.40 +/- 0.03 Pass S0-6406,6407 11/9/2016 K-40 10.90 +/- 0.68 11.29+/-0.74 11.09 +/- 0.50 Pass AP-111416 11/14/2016 Gr. Beta 0.024 +/- 0.005 0.021 +/- 0.006 0.022 +/- 0.004 Pass WW-6829,6830 11/15/2016 H-3 39,982 +/- 589 40,315 +/- 591 40, 149 +/- 417 Pass DW-70239, 70240 11/17/2016 Gr. Alpha 7.99+/-1.15 6.41 +/-1.05 7.20 +/- 0.78 Pass AP-112216 11/22/2016 Gr. Beta 0.049 +/- 0.005 0.045 +/- 0.005 0.047 +/- 0.003 Pass S-6473, 6474 11/24/2016 K-40 19.37+/-1.97 23.80 +/- 3.54 21.58 +/- 2.02 Pass SG-6938, 6939 11/28/2016 Ac-228 18.99 +/- 0.59 19.92 +/- 0.79 19.46 +/- 0.49 Pass SG-6938, 6939 11/28/2016 Pb-214 15.28 +/- 0.34 14.96 +/- 0.43 15.12 +/- 0.27 Pass AP-120116 12/1/2016 Gr. Beta 0.029 +/- 0.003 0.030 +/- 0.003 0.030 +/- 0.002 Pass F-6567,6568 12/1/2016 K-40 3.76 +/- 0.40 3.83 +/- 0.46 3.80 +/- 0.30 Pass S-6522, 6523 12/1/2016 Ac-228 1.08 +/-0.13 1.29 +/- 0.16 1.19+/-0.10 Pass S-6522, 6523 12/1/2016 Pb-214 1.00 +/- 0.08 1.01 +/- 0.09 1.01 +/- 0.06 Pass S-6609, 6610 12/1/2016 K-40 15.57 +/- 1.01 15.99 +/-0.78 15.78 +/- 0.64 Pass S-6718, 6719 1217/2016 K-40 18.19 +/- 2.13 18.76 +/- 1.80 18.48 +/- 1.39 Pass WW-6784, 6785 1217/2016 H-3 922 +/- 117 905+/-116 914 +/- 82 Pass AP-121216 12/12/2016 Gr. Beta 0.026 +/- 0.005 0.028 +/- 0.005 0.027 +/- 0.003 Pass AP-7178,7179 1/3/2017 Be-7 0.047 +/- 0.015 0.062 +/- 0.017 0.054 +/- 0.012 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

• Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil and sediment (pCi/g).

153

TABLEA-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-1053 2/1/2016 Ni-63 1,206 +/- 20 1250 875 - 1625 Pass MAS0-1053 2/1/2016 Sr-90 0.65 +/- 1.27 0.00 NA c Pass MAS0-1053 2/1/2016 Tc-99 0.1 +/- 5.5 0.0 NA c Pass MAS0-1 053 2/1/2016 Cs-134 908 +/- 26 1030 721 - 1339 Pass MAS0-1053 2/1/2016 Cs-137 0.10 +/- 6.20 0.00 NA c Pass MAS0-1053 2/1/2016 Co-57 1058 +/- 26 992 694 - 1290 Pass MAS0-1053 2/1/2016 Co-60 1229 +/- 28 1190 833 - 1547 Pass MAS0-1053 2/1/2016 Mn-54 1235 +/- 43 1160 812 - 1508 Pass MAS0-1053 2/1/2016 Zn-65 753 +/- 64 692 484 - 900 Pass MAS0-1053 2/1/2016 K-40 753 +/- 140 607 425 - 789 Pass MAS0-1053 2/1/2016 Am-241 79 +/- 6 103 72 - 134 Pass MAS0-1053 2/1/2016 Pu-238 73.9 +/- 9.2 63.6 44.5 - 82.7 Pass MAS0-1053 2/1/2016 Pu-239/240 0.76 +/- 1.34 0.21 NA d Pass MAS0-1053 2/1/2016 U-234/233 45.0 +/- 5.1 45.9 32.1 - 59.7 Pass MAS0-1053 2/1/2016 U-238 129 +/- 9 146 102 - 190 Pass MAW-989 2/1/2016 Am-241 0.018 +/- 0.015 0.00 NA c Pass MAW-989 2/1/2016 H-3 0.2 +/- 2.8 0.0 NA c Pass MAW-989 2/1/2016 Ni-63 12.8 +/- 2.7 12.3 8.6 - 16.0 Pass MAW-989 2/1/2016 Sr-90 8.70 +/- 1.20 8.74 6.12 -11.36 Pass MAW-989 2/1/2016 Tc-99

-1.1 +/- 0.6 0.0 NA c Pass MAW-989 2/1/2016 Cs-134 15.5 +/- 0.3 16.1 11.3 +/- 20.9 Pass MAW-989 2/1/2016 Cs-137 23.7 +/- 0.5 21.2 14.8 - 27.6 Pass MAW-989° 2/1/2016 Co-57 1.38 +/- 0.12 0.00 NA c Fail MAW-989 2/1/2016 Co-60 12.5 +/- 0.3 11.8 8.3 - 15.3 Pass MAW-989 2/1/2016 Mn-54 12.2 +/- 0.4 11.1 7.8 - 14.4 Pass MAW-989 2/1/2016 Zn-65 15.7 +/- 0.7 13.6 9.5 - 17.7 Pass MAW-989 2/1/2016 K-40 288 +/- 5 251 176 - 326 Pass MAW-989 2/1/2016 Fe-55 17.3 +/- 7.0 16.2 11.3 -21.1 Pass MAW-989 2/1/2016 Ra-226 0.710 +/- 0.070 0.718 0.503 - 0.933 Pass MAW-989 2/1/2016 Pu-238 1.280 +/- 0.110 1.244 0.871 +/- 1.617 Pass MAW-989 2/1/2016 Pu-239/240 0.640 +/- 0.080 0.641 0.449 - 0.833 Pass MAW-989 2/1/2016 U-234/233 1.39+/-0.12 1.48 1.04 -1.92 Pass MAW-989 2/1/2016 U-238 1.43+/-0.12 1.53 1.07 -1.99 Pass MAW-893 2/1/2016 Gross Alpha 0.600 +/- 0.050 0.673 0.202 -1.144 Pass MAW-893 2/1/2016 Gross Beta 2.10 +/- 0.06 2.15 1.08 - 3.23 Pass MAW-896 2/1/2016 1-129 3.67 +/- 0.20 3.85 2.70 - 5.01 Pass MAAP-1056 2/1/2016 Gross Alpha 0.39 +/- 0.05 1.20 0.36 - 2.04 Pass MAAP-1056 2/1/2016 Gross Beta 1.03 +/- 0.07 0.79 0.40 -1.19 Pass 154

TABLE A-fi. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits 0

Acceptance MAAP-1057 2/1/2016 Sr-90 1.34 +/- 0.15 1.38 0.97+/-1.79 Pass MAAP-1057 2/1/2016 Cs-134

-0.01 +/- 0.03 0.00 NA c Pass MAAP-1057 2/1/2016 Cs-137 2.57 +/- 0.10 2.30 1.61 - 2.99 Pass MAAP-1057 2/1/2016 Co-57 3.01 +/- 0.06 2.94 2.06 - 3.82 Pass MAAP-1057 2/1/2016 Co-fiO 4.28 +/-0.10 4.02 2.81 - 5.23 Pass MAAP-1 057 2/1/2016 Mn-54 4.90 +/- 0.13 4.53 3.17 - 5.89 Pass MAAP-1 057 2/1/2016 Zn-65 4.09 +/- 0.18 3.57 2.50 - 4.64 Pass MAAP-1057 2/1/2016 Am-241 0.059 +/- 0.015 0.0805 0.0564 - 0.1047 Pass MAAP-1057 2/1/2016 Pu-238 0.066 +/- 0.020 0.0637 0.0446 - 0.0828 Pass MAAP-1 057 2/1/2016 Pu-239/240 0.074 +/- 0.020 0.099 NA d Pass MAAP-1057 2/1/2016 U-234/233 0.151 +/- 0.026 0.165 0.116 -0.215 Pass MAAP-1057 2/1/2016 U-238 0.160 +/- 0.026 0.172 0.120-0.224 Pass MAVE-1050 2/1 /2016 Cs-134 9.83 +/- 0.19 10.62 7.43 - 13.81 Pass MAVE-1050 2/1/2016 Cs-137 6.06 +/-0.19 5.62 3.93 - 7.31 Pass MAVE-1050 2/1/2016 Co-57 13.8 +/- 0.2 11.8 8.3 - 15.3 Pass MAVE-1050 2/1/2016 Co-60 0.022 +/- 0.040 0.00 NA 0

Pass MAVE-1050 2/1/2016 Mn-54 0.009 +/- 0.044 0.000 NA c Pass MAVE-1050 2/1/2016 Zn-f35 10.67 +/- 0.39 9.60 6.70 - 12.50 Pass MAS0-4780r 8/1/2016 Ni-63 648 +/- 14 990 693 - 1287 Fail MAS0-47809 8/1/2016 Ni-63 902 +/- 46 990 693 - 1287 Pass MAS0-4780 8/1/2016 Sr-90 757 +/- 16 894 626 - 1162 Pass MAS0-4780 8/1/2016 Tc-99 559 +/- 12 556 389 - 723 Pass MAS0-4780 8/1/2016 Cs-134 0.93 +/- 2.92 0.00 NA c Pass MAS0-4780 8/1/2016 Cs-137 1061 +/- 12 1067 747 - 1387 Pass MAS0-4780 8/1/2016 Co-57 1178 +/- 8 1190 833 - 1547 Pass MAS0-4780 8/1/2016 Co-fiO 841 +/- 9 851 596 -1106 Pass MAS0-4780 8/1/2016 Mn-54 0.69 +/- 2.53 0.00 NA 0

Pass MAS0-4780 8/1/2016 Zn-f35 724 +/- 19 695 487 - 904 Pass MAS0-4780 8/1/2016 K-40 566 +/- 52 588 412 - 764 Pass MAS0-4780 8/1/2016 Am-241 0.494 +/- 0.698 0.000 NA c Pass MAS0-4780 8/1/2016 Pu-238 69.7 +/- 7.4 70.4 49.3 - 91.5 Pass MAS0-4780 8/1/2016 Pu-239/240 53.9 +/- 6.3 53.8 37.7 -69.9 Pass MAS0-4780h 8/1/2016 U-233/234 46.8 +/- 3.9 122 85 - 159 Fail MAS0-4780h 8/1/2016 U-238 46.6 +/- 3.9 121 85 - 157 Fail MAW-4776 8/1/2016 1-129 4.40 +/- 0.20 4.54 3.18 - 5.90 Pass MAVE-4782 8/1/2016 Cs-134

-0.01 +/- 0.05 0.00 NA c Pass MAVE-4782 8/1/2016 Cs-137 6.18 +/-0.20 5.54 3.88 - 7.20 Pass MAVE-4782 8/1/2016 Co-57 8.13 +/-0.16 6.81 4.77 - 8.85 Pass MAVE-4782 8/1/2016 Co-fiO 5.30 +/-0.15 4.86 3.40 - 6.32 Pass MAVE-4782 8/1/2016 Mn-54 8.08 +/- 0.24 7.27 5.09 - 9.45 Pass MAVE-4782 8/1/2016 Zn-65 6.24 +/- 0.36 5.40 3.78 - 7.02 Pass 155

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits 0

Acceptance MAAP-4784 8/1/2016 Sr-90 1.18 +/- 0.10 1.03 0.72 - 1.34 Pass MAAP-4784 8/1/2016 Cs-134 1.58 +/- 0.08 2.04 1.43 - 2.65 Pass MAAP-4784 8/1/2016 Cs-137 1.85 +/- 0.09 1.78 1.25 - 2.31 Pass MAAP-4784 8/1/2016 Co-57 2.39 +/- 0.52 2.48 1.74 -3.22 Pass MAAP-4784 8/1/2016 Co-60 3.22 +/- 0.08 3.26 2.28 - 4.24 Pass MAAP-4784 8/1/2016 Mn-54 2.82 +/- 0.12 2.75 1.93 - 3.58 Pass MAAP-4784 8/1/2016 Zn-65

-0 015 +/- 0.062 0.00 NA c Pass MAAP-4784 8/1/2016 Am-241

-0.001 +/- 0.006 0.00 NA c Pass MAAP-4784 8/1/2016 Pu-238 0.075 +/- 0.022 0.069 0.049 - 0.090 Pass MAAP-4784 8/1/2016 Pu-239/240 0.048 +/- 0.015 0.054 0.038 - 0.070 Pass MAAP-4784 8/1/2016 U-234/233 0.151 +/- 0.036 0.150 0.105 - 0.195 Pass MAAP-4784 8/1/2016 U-238 0.147 +/- 0.034 0.156 0.109-0.203 Pass MAW-4778 8/1/2016 H-3 365 +/- 11 334 234 - 434 Pass MAW-4778 8/1/2016 Fe-55 23.6 +/- 16.3 21.5 15.1 +/- 28.0 Pass MAW-4778 8/1/2016 Ni-63 17.0 +/- 2.8 17.2 12.0 +/- 22.4 Pass MAW-4778 8/1/2016 Sr-90 0.17+/-0.28 0.00 NA c Pass MAW-4778 8/1/2016 Tc-99 9.50 +/- 0.41 11.60 8.10 -15.10 Pass MAW-4778 8/1/2016 Cs-134 22.6 +/- 0.4 23.9 16.7 - 31.1 Pass MAW-4778 8/1/2016 Cs-137 0.018 +/- 0.117 0.00 NA c Pass MAW-4778 8/1/2016 Co-57 27.6 +/- 0.2 27.3 19.1 +/- 35.5 Pass MAW-4778 8/1/2016 Co-60 0.018 +/- 0.090 0.00 NA c Pass MAW-4778 8/1/2016 Mn-54 16.2 +/- 0.4 14.8 10.4 - 19.2 Pass MAW-4778 8/1/2016 Zn-65 19.3 +/- 0.7 17.4 12.2 - 22.6 Pass MAW-4778 8/1/2016 K-40 286 +/- 6 252 176 - 328 Pass MAW-4778 8/1/2016 Ra-226 1.48 +/- 0.09 1.33 0.93 - 1.73 Pass MAW-4778 8/1/2016 Pu-238 1.09 +/- 0.13 1.13 0.79 - 1.47 Pass MAW-4778 8/1/2016 Pu-239/240 0.003 +/- 0.011 0.016 NAd Pass MAW-4778 8/1/2016 U-234/233 1.80 +/- 0.13 1.86 1.30 - 2.42 Pass MAW-4778 8/1/2016 U-238 1.77 +/- 0.13 1.92 1.34 - 2.50 Pass MAW-4778 8/1/2016 Am-241 0.678 +/- 0.086 0.814 0.570 +/- 1.058 Pass

• Results are reported in units of Bq/kg (soil), Bq/L (water) or Bqltotal 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 Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.

• The laboratory properly identified the Sn-75 interfering peak in the vicinity of Co-57 and stated so in the comment field. MA PEP requires results to be reported as an activity with an uncertainty. Since the calculated uncertainty was less than the activity MAPEP interpreted the submitted result as a "false positive" resulting in a failure.

1 Original analysis for Ni-63 failed.

g Reanalysis with a smaller aliquot resulted in acceptable results. An investigation is in process to identify better techniques for analyzing samples with complex matrices.

h MAPEP states that samples contain two fractions of Uranium; one that is soluble in concentrated HN03 and HCI acid and one that is "fundamentally insoluble in these acids". They also state that HF treatment can not assure complete dissolution.

Results are consistent with measuring the soluble fonm.

156

TABLE A-7. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)*.

MRAD Stud Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERAP-1101 3/14/2016 Am-241 37.3 45.9 28.3 - 62.1 Pass ERAP-11 01 3/14/2016 Co-60 637 623 482 - 778 Pass ERAP-11 01 3/14/2016 Cs-1 34 251 304 193 - 377 Pass ERAP-1 101 3/14/2016 Cs-137 1,273 1, 150 864 - 1,510 Pass ERAP-1 101 3/14/2016 Fe-55

< 162 126 39.1 - 246 Pass ERAP-1101 3/14/2016 Mn-54

< 2.64

< 50.0 0.00 - 50.0 Pass ERAP-11 01 3/14/2016 Pu-238 68.0 70.5 48.3 - 92.7 Pass ERAP-1101 3/14/2016 Pu-239/240 54.1 54.8 39.70 - 71.60 Pass ERAP-1101 3/14/2016 Sr-90 139 150 73.3 - 225.0 Pass ERAP-1101 3/14/2016 U-233/234 59.3 64.8 40.2 - 97.7 Pass ERAP-1 101 3/14/2016 U-238 55.5 64.2 41.5-88.8 Pass ERAP-1101 3/14/2016 Zn-65 428 356 255 - 492 Pass ERAP-11 01 3/14/2016 Gr. Alpha 98.0 70.1 23.5 - 109 Pass ERAP-1101 3/14/2016 Gr. Beta 78.6 54.4 34.4 - 79.3 Pass ERS0-1105 3/14/2016 Am-241 1,030 1,360 796 - 1,770 Pass ERS0-1105 3/14/2016 Ac-228 1,540 1,240 795 - 1,720 Pass ERS0-1105 3/14/2016 Bi-212 1,550 1,240 330 - 1,820 Pass ERS0-1105 3/14/2016 Bi-214 3,100 3,530 2, 130 - 5,080 Pass ERS0-1105 3/14/2016 Co-60 5,600 5,490 3,710 - 7,560 Pass ERS0-1105 3/14/2016 Cs-134 3,030 3,450 2,260 - 4, 140 Pass ERS0-1105 3/14/2016 Cs-137 4,440 4,310 3,300 - 5,550 Pass ERS0-1105 3/14/2016 K-40 10,300 10,600 7,740 - 14,200 Pass ERS0-1105 3/14/2016 Mn-54

< 50.8

< 1000 0.0 - 1,000 Pass ERS0-1105 3/14/2016 Pb-212 1,140 1,240 812 - 1,730 Pass ERS0-1105 3/14/2016 Pb-214 3,190 3,710 2, 170 - 5,530 Pass ERS0-1105 3/14/2016 Pu-238 680 658 396 - 908 Pass ERS0-1105 3/14/2016 Pu-239/240 460 496 324 - 0,685 Pass ERS0-1105 3/14/2016 Sr-90 7,740 8,560 3,260 - 13,500 Pass ERS0-1105 3/14/2016 Th-234 3,630 3,430 1,080 - 6,450 Pass ERS0-1105 3/14/2016 U-233/234 3,090 3,460 2, 110 - 4,430 Pass ERS0-1105 3/14/2016 U-238 3,280 3,430 2,120 -4,350 Pass ERS0-1105 3/14/2016 Zn-65 2,940 2,450 1,950 - 3,260 Pass ERW-1115 3/14/2016 Gr. Alpha 105.0 117.0 41.5 - 181.0 Pass ERW-1115 3/14/2016 Gr. Beta 76.2 75.5 43.2 - 112.0 Pass ERW-1117 3/14/2016 H-3 8,870 8,650 5,800 - 12,300 Pass 157

TABLE A-7. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) 8 MRAD Stud Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Result Limits Acce~tance ERVE-1 108 3/14/2016 Am-241 1,930 2,120 1,300 - 2,820 Pass ERVE-1108 3/14/2016 Cm-244 1,294 1,560 764 - 2,430 Pass ERVE-1 108 3/14/2016 Co-60 1,164 1,100 759 - 1,540 Pass ERVE-1 108 3/14/2016 Cs-134 1,056 1,070 687 - 1,390 Pass ERVE-1108 3/14/2016 Cs-137 930 838 608 - 1,170 Pass ERVE-1108 3/14/2016 K-40 32,200 31,000 22,400 - 43,500 Pass ERVE-1108 3/14/2016 Mn-54

< 24.5

< 300 0.00 - 300 Pass ERVE-1108 3/14/2016 Zn-65 3,320 2,820 2,030 - 3,960 Pass ERVE-1108 3/14/2016 Pu-238 3,410 2,810 1,680 - 3,850 Pass ERVE-1108 3/14/2016 Pu-239/240 4,120 3,640 2,230 - 5,010 Pass ERVE-1108 3/14/2016 Sr-90 8,120 8,710 4,960 - 11,500 Pass ERVE-1108 3/14/2016 U-233/234 4,350 4,160 2,740 - 5,340 Pass ERVE-1108 3/14/2016 U-238 4,220 4,120 2,750 - 5,230 Pass ERW-1111 3/14/2016 Am-241 113 121 81.5 -1 62 Pass ERW-1111 3/14/2016 Co-60 1,120 1,050 912 - 1,230 Pass ERW-11 11 3/14/2016 Cs-134 806 842 618 - 968 Pass ERW-1111 3/14/2016 Cs-137 1,190 1,100 934 - 1,320 Pass ERW-1111 3/14/2016 Mn-54

< 5.89

< 100 0.00 - 100 Pass ERW-1111 3/14/2016 Pu-238 159 138 102 - 172 Pass ERW-1111 3/14/2016 Pu-239/240 113 98.7 76.6 - 124 Pass ERW-1111 3/14/2016 U-233/234 46.9 52.7 39.6 - 68.0 Pass ERW-1111 3/14/2016 U-238 50.4 52.3 39.9 - 64.2 Pass ERW-1111 3/14/2016 Zn-65 1,160 1,010 842 - 1,270 Pass ERW-1111 3/14/2016 Fe-55 1,600 1,650 984 - 2,240 Pass ERW-1111 3/14/2016 Sr-90 430 434 283 - 574 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).

" 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 Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

158

APPENDIX B DAT A REPORTING CONVENTIONS 159

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; x1 +/- s1 and x2 +/- s2 Reported result:

x +/- s; where x = (1/2) (x1 + x2) ands= (1/2) ~ s1 2 + s; 3.2.

Individual results:

< L1, < L2 Reported result: < L, where L = lower of L1 and L2 3.3.

Individual results:

x +/- s, < L Reported result:

x +/- s if x ;:: L; < L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for e~ample, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s" of a set of n numbers x1, x2... xn are defined as follows:

--~

s- -\\JnT 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2.

If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.

160

APPENDIX C REMP SAMPLING

SUMMARY

161

TABLE C: Davis-Besse Nuclear Power Station REMP Sampling Summary January-December 2016 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)0 Mean (F)0 Mean (F)0 Routine

!Units\\

Analyses*

Ranqe0 Locationd Ranqe0 Ranqe0 Results*

0.026 0.027 Airborne GB 530 0.003 (318/318)

T-9, Oak Harbor 0.028 (52/52)

(212/212) 0 Particulates (0.012-0.062) 6.8 mi. SW (0.014-0.052)

(0.012-0.060)

(pCi/m3)

Sr-89 40 0.0015

< LLD

<LLD 0

Sr-90 40 0.0007

<LLD

<LLD 0

GS 40 Be-7 0.015 0.077 (24/24)

T-1, Site Boundary 0.083 (4/4) 0.078 (16/16) 0 (0.056-0.10) 0.6 mi. ENE (0.072-0.097)

(0.048-0.11)

K-40 0.025

< LLD

< LLD 0

Nb-95 0.0019

< LLD

< LLD 0

Zr-95 0.0021

< LLD

< LLD 0

Ru-103 0.0015

<LLD

<LLD 0

Ru-106 0.0101

< LLD

<LLD 0

Cs-134 0.0012

<LLD

< LLD 0

Cs-137 0.0013

< LLD

<LLD 0

Ce-141 0.0024

< LLD

<LLD 0

Ce-144 0.0064

< LLD

<LLD 0

Airborne Iodine 1-131 530 0.07

< LLD

< LLD 0

(pCi/m3)

TLD 15.1 (Quarterly)

Gamma 351 1.0 (307/307)

T-8, Farm 24.6 (4/4) 17.9 (44/44) 0 (mR/91 days)

(7.8-25.7) 2.7 mi. WSW (23.6-25.7)

(13.1-23.4)

TLD (Quarterly)

Gamma 4

1.0 6.6 (4/4)

None 0

(mR/91 days)

(5.7-7.3)

(Shield)

TLD (Annual)

Gamma 88 1.0 54.3 (77/77)

T-27, Magee Marsh 81.2(1/1) 62.4 (11/11) 0 Wildlife Area, 5.3 mi.

(mR/365 days)

(36.4-81.1)

SW (46.9-81.2)

TLD (Annual)

Gamma 1

1.0 21.0 (1/1)

None 0

(mR/365 days)

(Shield) 162

TABLE C: Davis-Besse Nuclear Power Station REMP Sampling Summary January-December 2016 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine IUnitsl Analvses*

Ranaec Locationd Ranaec Ranaec Results*

Milk (pCi/L) 1-131 12 0.5 none

<LLD 0

Sr-89 12 0.6 none

<LLD 0

Sr-90 12 0.6 none T-24, Sandusky 0.74 (5/12) 0.74 (5/12) 0 21.0 mi. SE (0.7-0.9)

(0.7-0.9)

GS 12 K-40 100 none T-24, Sandusky 1319.1 (12/12) 1319.1 (12/12) 0 21.0 mi. SE (1208-1417)

(1208-1417)

Cs-134 4.1 none

<LLD 0

Cs-137 4.1 none

<LLD 0

Ba-La-140 9.3 none

<LLD 0

(g/L)

Ca 12 0.50 none T-24, Sandusky 1.01 (12/12) 1.01 (12/12) 0 21.0 mi. SE (0.90-1.12)

(0.90-1.12)

(g/L)

K (stable) 12 none T-24, Sandusky 1.61 (12/12) 1.67 (12/12) 0 21.0 mi. SE (1.47-1.73)

(1.48-1.71)

(pCi/g)

Sr-90/Ca 12 none T-24, Sandusky 0.73 (5/12) 0.73 (5/12) 0 21.0 mi. SE (0.063-0.92)

(0.063-0.92)

(pCi/g)

Cs-137/K 12 0.89 none

<LLD 0

Ground Water GB(TR) 8 1.8 (4/4)

T-226, Residence 2.9 (1/1) 2.53 (1/3) 0 (pCi/L)

(0.9-2.9) 2.3 mi. NW (2.9-2.9)

(1.7-3.0)

H-3 8

330

<LLD

<LLD 0

Sr-89 8

1.7

<LLD

<LLD 0

Sr-90 8

0.7

<LLD

<LLD 0

GS Mn-54 15

<LLD

<LLD 0

Fe-59 30

<LLD

<LLD 0

Co-58 15

<LLD

<LLD 0

Co-60 15

<LLD

<LLD 0

Zn-65 30

<LLD

<LLD 0

Zr-95 15

<LLD

<LLD 0

Cs-134 10

<LLD

<LLD 0

Cs-137 10

<LLD

<LLD 0

Ba-La-140 15

<LLD

<LLD 0

163

TABLE C: Davis-Besse Nuclear Power Station REMP Sampling Summary January-December 2016 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)<

Mean (F)<

Mean (F)<

Routine (Units)

Analyses*

Ranc:ie<

Location" Ranc:ie<

Ranc:ie<

Results*

Soil GS 10 (pCi/g dry)

Be-7 0.67 0.82 (1/6)

T-8, Farm 0.82 (1/6) 0.78 (1/4) 0 (0.82-0.82) 2.7mi. WSW (0.78-0.78)

K-40 0.10 11.35 (6/6)

T-8, Farm 23.74 (1/1) 19.02 (4/4) 0 (6.03-23.74) 2.7mi. WSW (14.74-21.96)

Mn-54 0.041

< LLD

< LLD 0

Nb-95 0.120

<LLD

<LLD 0

Zr-95 0.117

<LLD

<LLD 0

Ru-103 0.08

<LLD

<LLD 0

Ru-106 0.31

<LLD

<LLD 0

Cs-134 0.039

<LLD

<LLD 0

T-12, Water Cs-1 37 0.027 0.07 (3/6)

Treatment 0.16 (1/1) 0.10 (4/4)

Plant, 23.5 mi.

(0.057-0.88)

WNW (0.048-0.16) 0 Ce-141 0.183

<LLD

<LLD 0

Ce-144 0.23

<LLD

<LLD 0

Fruits and Sr-89 3

0.002

<LLD

<LLD 0

Vegetables Sr-90 3

0.001

<LLD

<LLD 0

(pCi/g wet)

GS 3

K-40 0.50 1.51 (2/2)

T-209, Residence 1.75 (1/1) 1.75 (1.1) 0 (1.47-1.55) 7.5mi. SW Nb-95 0.008

<LLD

<LLD 0

Zr-95 0.010

<LLD

<LLD 0

1-131 0.047

<LLD

<LLD 0

Cs-134 0.007

<LLD

<LLD 0

Cs-137 0.006

<LLD

<LLD 0

Ce-141 0.021

<LLD

<LLD 0

Ce-144 0.062

<LLD

<LLD 0

Broad Leaf Sr-89 13 0.006

<LLD

<LLD 0

Vegetation Sr-90 13 0.005

<LLD

<LLD 0

(pCi/gwet)

GS 13 K-40 0.50 2.38 (10/10)

T-17, Residence 2.64 (3/3) 2.03 (3/3) 0 (1.69-3.11) 1.82 mi. SSE (2.26-3.11)

(1.71-2.41)

Nb-95 0.014

<LLD

<LLD 0

Zr-95 0.019

<LLD

<LLD 0

Continued on next page 164

TABLE C: Davis-Besse Nuclear Power Station REMP Sampling Summary January-December 2016 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)'

Mean (F)'

Mean (F}° Routine (Units\\

Analvses*

Ranae' Locationd Ranae' Ranae' Results*

Broad Leaf Vegetation 1-131 0.058

<LLD

< LLD 0

(pCi/g wet)

Cs-134 0.013

< LLD

<LLD 0

- continued -

Cs-137 0.011

<LLD

< LLD 0

Ce-141 0.026

<LLD

< LLD 0

Ce-144 0.063

<LLD

< LLD 0

T-11, Ottawa Cly.

Treated GB (TR) 36 1.8 2.8 (5/12)

WTP 3.4 (5/12) 3.1 (8/24) 0 Surface Water (2.1-3.6) 9.5 mi. SE (1.9-8.1)

(1.9-8.1)

(pCi/L)

H-3 12 330

<LLD

<LLD 0

Sr-89 16 1.2

<LLD

< LLD 0

Sr-90 16 0.7

<LLD

< LLD 0

GS 12 Mn-54 15

<LLD

<LLD 0

Fe-59 30

<LLD

<LLD 0

Co-58 15

<LLD

< LLD 0

Co-60 15

<LLD

< LLD 0

Zn-65 30

<LLD

< LLD 0

Zr-Nb-95 15

<LLD

< LLD 0

Cs-134 10

< LLD

<LLD 0

Cs-137 10

<LLD

<LLD 0

Ba-La-140 15

< LLD

< LLD 0

T-11, Ottawa Cly.

Untreated GB (TR) 48 1.1 2.1 (24/24)

WTP 17.5 (12/12) 10.3 (22/24) 0 Surface Water (1.2-3.4) 9.5 mi. SE (1.3-50.0)

(1.0-53.0)

(pCi/L)

H-3 48 330 363 (1/24)

T-3, Site Boundary 363 (1/12)

< LLD 0

1.4 mi. ESE Sr-89 16 1.2

< LLD

<LLD 0

Sr-90 16 0.9

< LLD

<LLD 0

GS 48 Mn-54 15

< LLD

< LLD 0

Fe-59 30

<LLD

< LLD 0

Co-58 15

<LLD

<LLD 0

Co-60 15

< LLD

<LLD 0

Zn-65 30

<LLD

<LLD 0

Zr-Nb-95 15

<LLD

< LLD 0

Cs-134 10

<LLD

< LLD 0

Cs-137 10

<LLD

< LLD 0

Ba-La-140 15

< LLD

< LLD 0

165

TABLE C: Davis-Besse Nuclear Power Station REMP Sampling Summary January-December 2016 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units)

Analvses*

Ranaec Locationd Ranaec Ranaec Results*

Fish GB 4

0.10 3.47 (2/2)

T-33, Lake Erie 3.47 (2/2) 2.73 (2/2) 0 (pCi/g wet)

(2.88-4.06)

< 5mi.

(2.88-4.06)

(2.51-2.94)

GS 4

K-40 0.10 2.93 (2/2)

T-33, Lake Erie 2.93 (2/2) 2.2 (2/2) 0 (2.63-3.22)

<5 mi.

(2.63-3.22)

(1.86-2.53)

Mn-54 0.019

<LLD

< LLD 0

Fe-59 1.310

< LLD

<LLD 0

Co-58 1.190

< LLD

<LLD 0

Co-60 0.014

< LLD

< LLD 0

Zn-65 0.040

< LLD

<LLD 0

Cs-134 0.018

< LLD

< LLD 0

Cs-137 0.016

< LLD

< LLD 0

Shoreline GS 8

Sediments K-40 0.10 11.38 (6/6)

T -4, Site Boundary 14.73 (2/2) 11.1 4 (2/2) 0 (pCi/g dry)

(7.31-16.39) 0.8mi. S (13.07-16.39)

(10.59-11.68)

Mn-54 0.023

< LLD

<LLD 0

Co-58 0.034

< LLD

<LLD 0

Co-60 0.020

< LLD

<LLD 0

Cs-134 0.023

< LLD

<LLD 0

Cs-137 0.025 0.072 (1 /1)

T -4, Site Boundary 0.072 (1/1)

< LLD 0

0.8mi. S

• GB = gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).

d Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

• Non-routine results are those which exceed ten times the control station value.

166