Text

Annual Environmental and Effluent Release Report for the Year 2015
	ML16125A251
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Site:	Perry
Issue date:	04/29/2016
From:	Hamilton D; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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Ml16125A306	List: L-16-151, Annual Environmental and Effluent Release Report for the Year 2015;
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FE NOC' RrstEnergy Nuclear Operating cbmpany David B. Hamilton Vice President April 29, 2016 L-16-151 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440 Annual Environmental and Effluent Release Report Perry Nuclear Power Plant P.O. Box 97 10 Center Road.

Perry, Ohio 44081 440-280-5382 1 OCFR50.36(a)

Enclosed is the Annual Environmental and Effluent Release Report for the Perry Nuclear Power Plant (PNPP) for the period of January 1, 2015 through December 31, 2015. This document includes the radiological environmental operating report, radioactive effluent release report, and the non-radiological environmental operating report which satisfies the requirements of the PNPP Technical Specifications (TS), the PNPP Offsite Dose Calculation Manual (ODCM), and the Environmental Protection Plan, Appendix 8 of the PNPP Operating License. Also enclosed are two corrected pages.to 2014 Annual Environmental and Effluent Release Report.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas Veitch, Chemistry Manager at (440) 280-5188.

Sincerely, David Hamilton Vice President

Enclosures:

A PNPP 2015 Annual Environmental and Effluent Release Report 8

Corrections to the 2014 PNPP Annual Environmental and Effluent Release Report cc:

NRC Project Manager NRC Resident Inspector NRC Region Ill

Enclosure A L-16-151 PNPP 2015 Annual Environmental and Effluent Release Report

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT for the Perry Nuclear Power Plant PREPARED BY:

CHEMISTRY SECTION PERRY NUCLEAR POWER PLANT FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY, OHIO APRIL, 2015

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table of Contents EXECUTIVE

SUMMARY

.......................................................................................... 1.

Radioactive Effluent Releases....................................................................................... 1 Radiological Environmental Monitoring.......................................................................... 2 Land Use Census.......................................................................................................... 2 Clam/Mussel Monitoring......*......................................................................................... 2 Herbicide Use.................................................................................... :........................... 3 Special Environmental Reports..................................................................................... 3 INTRODUCTION...................................................................................................... 3 Radiation Fundamentals................................................................................................ 3 Radiation and Radioactivity..............................................,............................................ 4 Units of Measure....................................................................................................... :... 5 Lower Limit of Detection............. ~..................................*............................................... 5 Other Sources of Radiation Dose to the U.S. Population............................................... 5 Environmental Radionuclides........................................................................................ 7 RADIOACTIVE EFFLUENT RELEASES.................................................................. 7 Introduction................................................................................................................... 7 Regulatory Limits........................................................................................................... 8 Liquid Effluents.......................................................................... :................................... 8 Gaseous Effluents......................................................................................................... 9 Independent Spent Fuel Storage Installation................................................................ 10 Release Summary........................................................................................................ 10 Meteorological Data..................................................................... ~............................... 17 Dose Assessment............................................................................................. ~.......... 17 CARBON-14 SUPPLEMENTAL INFORMATION.................................................... 21 GROUNDWATER MONITORING PROGRAM............................................. :......... 21 RADIOLOGICAL ENVIRONMENTAL MONITORING............................................. 24 Introduction.................................................................. :............................................... 24 Sampling Locations...................................... :............................................................... 24 Sample Analysis........................................................................................................... 30 Sampling Program........................................................................................................ 31 Program Changes *************************************************************:****"***********************:.............. 31 Atmospheric Monitoring................................................................................................ 31 Terrestrial Monitoring................................................................................................... 32 Aquatic Monitoring........................................................................................................ 33 Direct Radiation Monitoring.......................................................................................... 34 Conclusion................................................................................................................... 35 Inter-Laboratory Cross-Check Comparison Program.................................................... 36 Land Use Census......................................................................................................... 37 CLAM/MUSSEL MONITORING.............................................................................. 40 Introduction.................................................................................................................. 40 Corbicula Program....................................................................................................... 40 Dreissena Program...................................................................................................... 41 HERBICIDE APPLICATIONS................................................................................. 42 SPECIAL REPORTS.............................................................................................. 43 NP DES Permit Exceedances....................................................................................... 43 Environmental Protection Plan..................................................................................... 43 Environmental Impact Evaluations............................................................................... 43 Table of Contents Page i

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Appendices Appendix A: 2015 Inter-Laboratory Cross Check Comparison Program Results Appendix B: 2015 REMP Data Summary Reports Appendix C: 2015 REMP Detailed Data Report Appendix D: Corrections to Previous AEERR Appendix E: Abnormal Releases Appendix F: ODCM Non-Compliances Appendix G: ODCM Changes Appendix H: Changes to the Process Control Program Table of Contents Page ii

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT EXECUTIVE

SUMMARY

The Annual Environmental and Effluent Release Report (AEERR) details the results of environmental and effluent monitoring programs conducted at the Perry Nuclear Power Plant (PNPP) from January 01 through December 31, 2015. This report meets all of the requirements in PNPP Technical Specifications, the Offsite Dose Calculation Manual (ODCM), the Environmental Protection Plan (EPP) and Regulatory Guide 1.21. It incorporates the requirements of the Annual Radioactive Effluent Release Report (ARERR),

the Annual Radiological Environmental Operating Report (AREOR) and the Annual Environmental Operating Report (AEOR). Report topics include radioactive effluent releases, radiological environmental monitoring, land use census, clam/mussel monitoring, herbicide use, and special reports. The results of the environmental and effluent programs indicate that the operations of the PNPP did not result in any significant environmental impact.

RADIOACTIVE EFFLUENT RELEASES During the normal operation of a nuclear power plant, small quantities of radioactivity are released to the environment in liquid and gaseous effluents. Radioactive material is also shipped offsite as solid waste. PNPP maintains a comprehensive program to control and monitor the release of radioactive materials from the site in accordance with Nuclear Regulatory Commission (NRC) release regulations.

The dose to the general public from the plant's liquid and gaseous effluents was below regulatory limits. The calculated maximum individual whole body dose potentially received by an individual resulting from PNPP liquid effluents was 1.02E-03 mrem(0.03% of the regulatory limit). The calculated maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents (excluding C-14) was 8.21 E-03 mrem (0.16% of the regulatory limit).

Radioactivity released to the environment in the form of gaseous Carbon-14 (C-14) was estimated based on plant type and power production. The calculation is based on an industry initiative supported by the Nuclear Energy lnstih1te (NEI), the Electric Power Research Institute (EPRI) and the NRC. The calculated hypothetical maximum individual whole body dose potentially received by an individual resulting from PNPP gaseous effluents including C-14 is 2.6E-01 mrem (5.2% of the limit). Refer to page 21 for additional C-14 information.

The summation of the hypothetical maximum individual dose from effluents is less than 1 %

of the total dose an individual living in the PNPP area receives from all sources of manmade and background radiation.

Shipments of solid waste consisted of waste generated during water treatment, radioactive material generated during normal daily operations and maintenance, and irradiated components. PNPP complied with regulations governing radioactive shipments of solid radioactive waste.

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING The Radiological Environmental Monitoring Program (REMP) was established in 1981 to monitor the radiological conditions in the environment around PNPP. The REMP is conducted in accordance with PNPP ODCM. This program includes the collection and analysis of environmental samples and evaluation of results.

The REMP was established at PNPP six (6) years before the plant became operational.

This pre-operational program was designed to provide data on background radiation and radioactivity normally present in the area. PNPP has continued to monitor the environment during plant operation by collecting and analyzing samples of air, milk, fish, vegetation, water and sediment, as well as by measuring radiation directly. The results of the REMP program indicate adequate control of radioactivity released from PNPP effluents. These results also demonstrate that PNPP complies with federal regulations.

Air samples were collected to monitor the radioactivity in the atmosphere; the results showed normal background radionuclide concentrations.

Terrestrial monitoring included the analysis of milk and vegetation; the results indicated concentrations of radioactivity similar to that found in previous years. Analyses of vegetation samples detected only natural radioactivity similar to those observed in previous years and indicated no radioactiyity attributable to the operation of PNPP.

Aquatic monitoring included the collection and analyses of water, fish, and shoreline sediments. The analytical results for water, fish and sediment samples showed normal background radionuclide concentrations..

Direct radiation measurements showed no discernible change from previous years. The indicator locations averaged 12.5 mrem/quarter and control locations averaged 12.3 mrem/quarter. Radiation dose in the area of PNPP was similar to the radiation dose measured at locations greater than ten (10) miles away from PNPP.

Based on these results, the operation of the PNPP resulted in no me.asureable increas~ in the radionuclide concentrations observed in the environment.

~

LAND USE CENSUS In order to estimate radiation dose attributable to the operation of PNPP, the potential pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual Land Use Census is performed as part of the REMP.

During the census, PNPP personnel travel public roads within a five (5) mile radius of the plant to locate key radiological exposure pathways. These key pathways include the nearest resident, garden, and milk animal in each of the ten meteorological land sectors that surround the plant. The information obtained from the census is entered into a computer program, that is used to assess the hypothetical dose to members of the public.

The predominant land use within the census area continues to be rural and/or agricultural.

CLAM/MUSSEL MONITORING Clam and mussel shells can clog plant piping and components that use water from Lake Erie. For this reason, sampling for clams and mussels has been conducted in Lake Erie near PNPP since 1971. The monitoring is specifically for Corbicula (Asiatic clams) since their introduction into the Great Lakes in 1981, and for Dreissena (zebra mussels) since I

Pc;ige 2

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT their discovery in Lake Erie in 1989. Since no Corbicula have ever been found at PNPP, routine Corbicula monitoring will provide early detection capability if this pest species arrives at PNPP. The Dreissena program includes both monitoring and control and is directed at minimizing the mussel's impact on plant operation. As in past years, this program has successfully prevented Dreissena from causing any significant operational problems at PNPP.

HERBICIDE USE The use of herbicides on the PNPP site is monitored to ensure compliance with Ohio Environmental Protection Agency (OEPA) requirements and to protect the site's natural areas. Based on weekly inspections, herbicide use has not had a negative impact on the environment around the plant.

SPECIAL ENVIRONMENTAL REPORTS Significant environmental events (e.g. spills, releases), noncompliance with environmental regulations (e.g., OEPA discharge limits), and changes hi plant design or operation that affect the environment are reported to regulatory agencies as they occur. Three (3) reports

, were submitted in 2015. See page 43 for details.

INTRODUCTION Nuclear energy provides an alternative energy source, which is readily available and has very limited impact upon the environment. To more fully understand nuclear energy as a source of generating electricity, it is helpful to understand basic radiation concepts and its occurrence of radioactivity in nature.

RADIATION FUNDAMENTALS Atoms are the basic building blocks of all matter. Simply described, atoms are made up of positively and negatively charged particles and particles which are neutral. These particles are called protons, electrons, and neutrons, respectively. The relatively large protons and neutrons are packed together in the center of the atom called the nucleus. Orbiting around the nucleus are one or more smaller electrons. In an electrically neutral atom, the positively charged protons in the nucleus balance the negatively charged electrons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other, which helps hold the atom together. Other attractive forces between the protons.and neutrons keep the densely packed protons from repelling each other and prevent the nucleus from breaking apart.

Atoms with the same number of protons in their nuclei make up an element. The number of neutrons in the nuclei of an element may vary. Atoms with the same number of protons but different numbers of neutrons are called isotopes. All isotopes of the same element have the same chemical properties and many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radionuclide. Radionuclides contain an excess amount of energy in the nucleus, which is usually due to an excess number of neutrons.

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Radioactive atoms attempt to reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of energy from an atom's nucleus through the emission of alpha and beta particles and gamma rays. Radionuclides vary greatly in the rate in which they decay. The length of time an atom remains radioactive is defined in terms of its half-life. Half-life is defined as the time required for a radioactive substance to lose half its activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years.

RADIATION AND RADIOACTIVITY Radioactive decay is a process in which the nucleus of an unstable atom becomes more stable by spontaneously emitting energy. Radiation refers to the energy that is released when radioactive decay occurs within the nucleus. This section includes a discussion on the three (3) primary forms of radiation produced by radioactive decay.

. Alpha.Particles Alpha particles consist of two protons and two neutrons and have a positive charge.

Because of their charge and large size, alpha particles do not travel very far when released (less than 4 inches in air). They are unable to penetrate any solid material, such as paper or skin, to any significant depth. However, if alpha particles are released inside the body, they can damage the soft internal tissues because they deposit all their energy in a small area.

Beta Particles Beta particles have the same characteristics as electrons but originate from the nucleus.

They are much smaller than alpha particles and travel at nearly the speed of light, thus they travel longer distances than alpha particles. External beta radiation primarily affects the skin. Because of their electrical charge, beta particles are stopped by paper, plastic or thin metal.

Gamma Rays Gamma rays are bundles of electromagnetic energy called photons. They are similar to visible light, but at a much higher energy. Gamma rays can travel long distances in air and are often released during radioactive decay along with alpha and beta particles.

Potassium-40 is an example of a naturally occurring radionuclide found in all humans that emits a gamma ray when it decays.

Interaction with Matter When radiation interacts with other materials, it affects the atoms of those materials principally by removing the negatively charged electrons out of their orbits. This causes an atom to lose its electrical neutrality and become positively charged. An atom that is charged, either positively or negatively, is called an ion, and the radiation is called ionizing radiation.

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT UNITS OF MEASURE Some of the units of measure used in this report require explanation.

Activity Activity is the number of atoms in a material that decay per unit of time. Each time an atom decays, radiation is emitted. A curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms per second. Smaller units of the curie are often used in this report. Two common units are the microcurie (µCi), one millionth of a curie, and the picocurie (pCi), one trillionth of a curie. The mass, or weight, of radioactive material, which would result in one ( 1) curie of activity, depends on the disintegration rate.

For example, one gram of radium-226 is equivalent to one ( 1) curie of activity. It would require about 1.5 million grams of natural uranium, however, to equal one (1) curie.

Dose Biological damage due to alpha, beta, and gamma radiation may result from the ionization caused by these types of radiation. Some types of radiation, especially alpha particles that cause dense local ionization, can result in much more biological damage for the same energy imparted than does gamma or beta radiation. A quality factor therefore 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 (as measured in rads), the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type of ionizing radiation. The dose equivalent is measured in terms of the Roentgen Equivalent Man (rem). When discussing environmental radiation effects, the rem is a large unit; therefore, a smaller unit, the millirem (mrem) is often used. One mrem is equivalent to 1/1000 of a rem.

LOWER LIMIT OF DETECTION Sample results are often reported as below the Lower Limit of Detection (LLD). The LLD for an analysis is the smallest amount of radioactive material that will show a positive result for which there can be a 95% confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as less than the LLD (<LLD), it means that no radioactivity was detected. Had radioactivity been present at (or above) the stated LLD value, it statistically would have been detected. The NRC has established the required LLD values for environmental and effluent sample analyses.

OTHER SOURCES OF RADIATION DOSE TO THE U.S. POPULATION This section discusses the doses that the average American typically receives each year from naturally occurring background radiation and all other sources of radiation. With the information presented in this section, the reader can compar~ the doses received from Nuclear Power Plant (NPP) effluents with the doses received from natural, medical, and other sources of radiation. This comparison provides some context to the concept of radiation dose effects.

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT In March 2009, the National Council on Radiation Protection and Measurements (NCRP) published Report No. 160 as an update to the 1987 NCRP Report No. 93, Ionizing Radiation Exposure of the Population of the United States (Refs. 30, 31 ). Report No. 160 describes the doses to the U.S. population from all sources of ionizing radiation for 2006, the most recent data available at the time the NCRP report was written. The NCRP report also includes information on the variability of those doses from one individual to another.

The NCRP estimated that the average person in the United States receives about 620 mrem of radiation dose each year. NCRP Report No. 160 describes each of the sources of radiation that contribute to this dose, including:

Naturally occurring sources (natural background) such as cosmic radiation from space, terrestrial radiation from radioactive materials in the earth, and naturally occurring radioactive materials in the food people eat and in the air people breathe; Medical sources from diagnosis and treatment of health disorders using radioactive pharmaceuticals and radiation-producing equipment; Consumer products (such as household smoke detectors);

Industrial processes, security devices, educational tools, and research activities; and Exposures of workers that result from their occupations.

Indus.trial RB.don & tMron (background) 37%

in~s Close w w trom nt1*nfpOl\\"'1'~t1 en

~ o.1%

Occ pa11on

[OOl.'<fe-s owes ro i¥Olleel's fl'001 IWCil!olf P<i"!'ltf ~ fill lilr!WI

<()1%

Consumer 2%

ConwintlOnal radiography I fluGIOScopy (medical) 5%

Space (bactgrou11d) 5%

I t rvcntional tlouroscopy (m dical) 7%

Figure 1 T

stria!

(baci<.'l)round) 3%

Nuclear medicine

(~d lca l )

2%

Sources of Radiation Exposure to the U.S. Population compV d tomograplly c dical) 24%

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 1 shows the contribution of various sources of exposure to the total collective effective dose and the total effective dose per individual in the U.S. population for 2006.

Larger contributors to dose are represented by proportionally larger slices of the pie. Doses to the public from NPPs are included in the industrial category; doses to workers from nuclear power generation are included in the category of occupational dose. Doses to the public due,to effluents from NPPs are less than 0.1 % (one-tenth of one percent) of what the average person receives each year from all other sources of radiation.

ENVIRONMENTAL RADIONUCLIDES Many radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. These radionuclides are expected to be present in many of the environmental samples collected in the vicinity of PNPP. Some of the radionuclides normally present include:.

Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere, Potassium-40, a naturally occurring radionuclide normally found in humans and throughout the environment, and Radionuclides from nuclear weapons testing fallout, including tritium and Cesium-137.

Tritium due to the interaction of Nitrogen in the air and cosmic rays..

Beryllium-7 and Potassium-40 are common in REMP samples. Since they are naturally occurring and are expected to be present, positive results for these radionuclides are not discussed in the section for the Sampling Program results. These radionuclides are included; however, in Appendix A, 2015 Inter-Laboratory Cross Check Comparison Program Results.

RADIOACTIVE EFFLUENT RELEASES INTRODUCTION The source of radioactive material in a nuclear power plant is the generation of fission products (e.g., noble gas, iodine, and particulate) or neutron aCtivation of water and corrosion products (e.g., tritium and cobalt). The majority of the fission products generated remain within the nuclear fuel pellet and fuel cladding. Most fission products that escape from the fuel cladding, as well as the majority of the activated corrosion products, are

,removed by plant processing equipment.,

During the normal operation of a nuclear power plant, small amounts of radioactive material are released in the form of solids, liquids, and gases. PNPP was designed, and is operated in such a manner as to control and m.onitor these effluent releases. Effluents are controlled to ensure any radioactivity released to the environment is minimal and within regulatory limits. Effluent release programs include the operation of monitoring systems, in-plant sampling and analysis, quality assurance, and detailed procedures covering all aspects of effluent monitoring.

The liquid and gaseous radioactive waste treatment systems at PNPP are designed to collect and process these wastes in order to remove most of the radioactivity. Effluent monitoring systems are used to provide continuous indication of the radioactivity present Page 7

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT and are sensitive enough to measure several orders of magnitude lower than the release limits. This monitoring equipment is equipped with alarms and indicators in the plant control room. The alarms are set to provide warnings to alert plant operators when radioactivity levels reach a small fraction of the limits. The waste streams are sampled and analyzed to identify and quantify the radionuclides being released to the environment.

Gaseous effluent release data is coupled with on-site meteorological data in order to calculate the dose to the general public. Devices are maintained at various locations*

around PNPP to continuously sample the air in the surrounding environment. Frequent samples of other environmental media are also taken to determine if any radioactive material deposition has occurred. The Radiological Environmental Monitoring Program (REMP) is described in detail later in this report.

Generation of solid waste is controlled to identify opportunities for minimization. Limiting the amount of material taken into the plant, sorting material as radioactive or non-radioactive waste, and incinerating waste help to lower the volume of radioactive solid waste generated. After vendor processing, solid waste is shipped to a licensed burial site.

REGULATORY LIMITS The Nuclear Regulatory Commission has established limits for liquid and gaseous effluents that comply with:

Title 10 of the Code of Federal Regulations, Part 20, Standards for Protection Against Radiation, Appendix B; Title 10 of the Code of Federal Regulations, Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix I; Title 10 of the Code of Federal Regulations, Part 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS Title 40 of the Code of Federal Regulations, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations These limits were incorporated into the PNPP Technical Specifications, and subsequently into the PNPP ODCM. The ODCM prescribes the maximum doses and dose rates due to radioactive effluents resulting from the operation of PNPP. These limits are defined in several ways to limit the overall impact on persons living near the. plant. Since there are no other fuel sources nearthe PNPP, the 40CFR190 limits, which are described below, were not exceeded.

The 40CFR190 limit for whole body dose is 25 mrem. For 2015, the total whole body dose to a member of the general public, considering all sectors, was 0.26 millirem. This value was determined by summing the annual whole body doses from liquid and gaseous radioactive effluents and the annual gaseous Carbon-14 dose.. Since the direct radiation dose, as determined by TLD, was indistinguishab.le from natural background (see Figure 8, page 35), it was not included in the calculation.

LIQUID EFFLUENTS The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 1 OCFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble.gases, as required by the ODCM.

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT For dissolved or entrained noble gases, the concentration is limited to a concentration of 2.0E-04 µCi/ml. These values are the maximum effluent concentrations.

The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:

During any calendar quarter:

Less than or equal to 1.5 mrem to the whole body, and Less than or equal to 5 mrem to any organ During any calendar year:

Less than or equal to 3 mrem to the whole body, and Less than or equal to 10 mrem to any organ GASEOUS EFFLUENTS The dose rate due to radioactive materials released in gaseous effluerits from the site to*

areas at and beyond the site boundary shall be limited to th~ following as required by the ODCM:

Noble gases:

Less than or equal to 500 mrem per year to the whole body, and Less than or equal to 3000 mrem per year to the skin lodine-131, lodine-133, Tritium, and all radionuclides in particulate form with haif lives*

greater than eight days:*

Les,s than or equal to 1500 mrem per year to any* organ Air dose due to noble gases to areas at, and beyond the site boundary, shall be limited to the following:

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation, and Less than or equal to 10 mrad for beta radiation During any calendar year:

Less than or equal to 10 mrad for gamma radiation, and Less than or equal to 20 mrad for beta radiation Dose to a member of the public from lodine-131, lodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 7.5 mrem to any organ per any calendar quarter, and Less than or equal to 15 mrem to any organ per any calendar year The PNPP ODCM does not contain a concentration limit f6r gaseous effluents. For this reason, effluent concentrations are not used to calculate maximum release rates for gaseous effluents.

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT INDEPENDENT SPENT FUEL STORAGE INSTALLATION During any calendar year:

Less than or equal to 25 mrem whole body* dose; Less than or equal to 75 mrem thyroid dose; and Less than or equal to 25 mrem to any other critical organ.

RELEASE

SUMMARY

Effluents are sampled and analyzed to identify both the type and quantity of radionuclides present. This information is combined with effluent path flow measurements to determine the composition, concentration, and dose contribution of the radioactive effluents.

Liquid Effluents The PNPP liquid radioactive waste system is designed to collect and treat all radioactive liquid waste produced in the plant. The treatment process used for radioactive liquid waste depends on its physical and chemical properties. It is designed to reduce the concentration of radioactive material in the liquid by filtration to remove suspended solids and demineralization to remove dissolved solids. Normally, the effluent from the liquid radioactive waste system is returned to plant systems. To reduce the volume of water stored in plant systems; however, the processed liquid effluent may be discharged from the plant via a contrqlled release. In this case,.effluent activity and dose calculations are performed prior to and after discharging this processed water to Lake Erie to ensure regulatory compliance and dose minimization principles are maintained.

Liquid radioactive waste system effluents may be intermittently released, which are considered to be "batch" releases. Table 1 provides information on the number and duration of these releases.

T bl 1 L" "d B t h R I a e. IQUI ac e eases Quart~r 1 Quarter 2 Quarter 3 Quarter4 Number of batch releases 13 14 0

0 Total time period for batch releases, min 3.09E+03 3.45E+03 NA NA Maximum time for a batch release, min 3.61E+02 3.45E+02 NA NA Average time period for a batch release, min 2.38E+02 2.46E+02 NA NA Minimum time for a batch release, min 1.60E+01 2.20E+02 NA NA Table 2 provides information on the nuclide composition for the liquid radioactive effluent system releases. If a radionuclide was not present at a level "greater than or equal to the LLD" (~LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, LLDs were met, or were below the levels required by the ODCM. Table 2a provides information specific to radioactive effluent batch releases and Table 2b provides information specific to continuous radioactive effluent releases.

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 2: Summation of All Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter4 Est. Total Error,(%)

A. Fission and Activation Products

1. Total Released, Ci,

!?.83E-03 8.91E-03 2.81E-05 8.79E-05 1.00E+01 (excluding tritium, gases, alpha) 2 Average Diluted Concentration, µCi/ml

3.15E-10 4.78E-10 1.05E-12 4.62E-12

3. Percent of Applicable Limit, %

7.06E-03 1.17E-02 3.16E-05 1.21E-04 B. Tritium

1. Total Released, Ci 2.76E+OO 2.53E+OO 1.27E-02 1.55E-01 1.00E+01

2. Averaae Diluted Concentration, uCi/mL 1.49E-07 1.36E-07 4.75E-10 8.15E-09

3. Percent of Applicable Limit, %

1.49E-02 1.36E-02 4.75E-05 8.15E-04 C. Dissolved and Entrained Gases

1. Total Released, Ci 3.93E-03

<LLD

<LLD 1.00E+01

2. Averaae Diluted Concentration, uCi/mL 2.12E-10 NA NA NA

3. Percent of Aoolicable Limit, %

1.06E-04 NA NA NA

(

D. Gross Alpha Activity, Ci 2.10E-07

<LLD 4.27E-07

<LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 2.44E+07 2.46E+07 2.31E+07 2.30E+07 dilution)

F. Dilution Water Volume Used, Liters 1.85E+10 1.86E+10 2.68E+10 1.90E+10

<LLD - Less than the lower limit of detection

Average diluted concentrations are based on total volume of water released during quarter.

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2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 2a: Summation of Batch Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error, (%)

A.

Fission and Activation Products Total Released, Ci 5.51E-03 8.86E-03 1.00E+01 (excludinq tritium, qases, alpha)

B.

Tritium Total Released, Ci 2.75E+OO 2.52E+OO 1.00E+01

c.

Dissolved and Entrained Gases Total Released, Ci 3.93E-03

<LLD 1.00E+01 D.

Gross Aloha Activitv, Ci

<LLD

<LLD 1.00E+01 E.

Waste Volume Released, Liters (prior to 1.72E+06 1.80E+06 dilution)

<LLD - Less than the lower limit of detection Table 2b: Summation of Continuous Liquid Effluent Releases Quarter 1 Quarter 2 Quarter 3 Quarter4 Est. Total Error,(%)

A.

Fission and Activation Products Total Released, Ci 3.23E-04 4.59E-05 2.81E-05 8.79E-05 1.00E+01 (excludina tritium, oases, aloha)

B.

Tritium Total Released, Ci 1.46E-02 1.25E-02 1.27E-02 1.55E-01 1.00E+01

c.

Dissolved and Entrained Gases Total Released, Ci

<LLD

<LLD 1.00E+01 D. Gross Alpha Activitv, Ci 2.10E-07

<LLD 4.27E~07

<LLD 1.00E+01 E. Waste Volume Released, Liters (prior to 2.26E+07 2.28E+07 2.31E+07 2.30E+07 dilution)

<LLD - Less than the lower limit of detection Page 12

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 3 lists the total number of curies (Ci) of each radionuclide present in liquid effluent releases for each quarter. If a radionuclide was not present at a level "greater than or equal to the Ll,..D" (;:::LLD), then the value is expressed as "less than the LLD" (<LLD). In each case, the LLDs were either met, or were below the levels required by the ODCM.

Table 3 Radioactive Liquid Effluent Nuclide Composition Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium I Ci 2.76E+OO 2.53E+OO 1.27E-02 1.55E-01 5.46E+OO Chromium-51 Ci 1.16E-03 1.78E-04

<LLD

<LLD 1.34E-03 Mani:ianese-54 Ci 5.18E-04 1.79E-03 3.04E-06 2.90E-06 2.31E-03 lron-55 Ci

<LLD

<LLD lron-59 Ci

<LLD

<LLD Cobalt-58 Ci 2.86E-04 4.31E-04

<LLD 1.94E-05 7.37E-04 Cobalt-60 Ci 3.58E-03 6.01E-03 2.51E-05 6.56E-05 9.67E-03 Zinc-65 Ci

<LLD 8.42E-05

<LLD

<LLD 8.42E-05 Strontium-89 Ci

<LLD

<LLD Strontium-90 Ci

<LLD

<LLD Molybdenum~99 Ci

<LLD

<LLD Silver-11 Om Ci 2.57E-04 4.15E-04

<LLD

<LLD 6.72E-04 Tin-113 Ci 1.86E-08

<LLD

<LLD 1.86E-08 lodine-131 Ci

<LLD

<LLD Cesium-134 Ci 8.96E-06

<LLD

<LLD 8.96E-06 Cesium-137 Ci 2.78E-05

<LLD

<LLD 2.78E-05 Cerium-141 Ci

<LLD

<LLD Cerium-144 Ci

<LLD

<LLD Xenon-133 Ci 3.93E-03

<LLD

<LLD 3.93E-03 Gross Alpha Ci 2.10E-07

<LLD 4.27E-07

<LLD 6.37E-07

<LLD - Less than the lower limit of detection Page 13

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Gaseous Effluents Gaseous effluents are made up of fission and activation gases, iodine and particulate releases. Gaseous effluents from PNPP exit the plant via one of four effluent vents. Each of these four effluent vents contains radiation detectors that continuously monitor the air to ensure that the levels of radioactivity released are below regulatory limits. Samples are also collected and analyzed on a periodic basis to ensure regulatory compliance. Gaseous effluents released from PNPP are considered continuous and at ground level.

In 2013 PNPP increased the volume of air captured when sampling for tritium in gaseous effluents. This has increased the detection capability (LLD) by a factor of 20. Gaseous effluent tritium releases are now being detected where before they were too dilute to measure. This has resulted in a reported increase in tritium released over previous years.

A summation of all gaseous radioactive effluent releases is given in Table 4.

Table 4: Summation of All Gaseous Effluents Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error,%

A. Fission and Activation Products

1. Total Released, Ci 5.58E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+01

2. Averai:ie Release Rate, µCi/sec 7.18E+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Percent of Applicable Limit, %

N/A NIA N/A N/A B. Iodine

1. Total lodine-131 Released, Ci 1.27E-04 0.00E+OO O.OOE+OO O.OOE+OO 1.00E+01

2. Average Release Rate, µCi/sec 1.63E-05 O.OOE+OO O.OOE+OO O.OOE+OO

3. Percent of Applicable Limit, %

N/A N/A N/A N/A C. Particulates with Half-Lives > 8 days

1. Total Released, Ci O.OOE+OO 9.58E-05 O.OOE+OO O.OOE+OO 1.00E+01

2. Averaae Release Rate, µCi/sec O.OOE+OO 1.22E-05 O.OOE+OO O.OOE+OO

3. Percent of Applicable Limit, %

N/A N/A N/A N/A D. Alpha Activity, Ci 4.82E-07 2.?0E-06 6.69E-07 1.59E-07 1.00E+01 E. Tritium

1. Total Released, Ci 1.68E+OO 1.79E-01 1.30E+OO 6.42E-01 1.00E+01

2. Averaae Release Rate, uCi/sec 2.16E-01 2.28E-02 1.63E-01 8.0BE-02

3. Percent of Applicable Limit, %

N/A N/A N/A N/A F. Carbon-14, Ci 3.25E+OO 3.40E+OO 4.74E+OO 4.76E+OO 1.00E+01

<LLD - Less than the lower limit of detection N/A - Not Applicable, the ODCM does not have a release rate limit for gaseous effluents.

Carbon-14 activity was calculated based on power production and using the EPRI provided Spreadsheet.

Page 14

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT The radionuclide composition of all gaseous radioactive effluents for a continuous-mode, ground-level release is given in Table 5. If a radionuclide was not present at a level "greater than or equal to the LLD," then the value is expressed as "less than the LLD"

(<LLD). In each case, LLDs were met or were below the levels required by the ODCM.

f Discussion of C-14 doses is listed on page 21, Carbon-14 supplemental information.

Table 5: Radioactive Gaseous Effluent Nuclide Composition Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual

1.

Fission and Activation Gases Tritium Ci 1.68E+OO 1.79E-01 1.30E+OO 6.42E-01 3.80E+OO Krvpton-85m Ci 2.85E+OO

<LLD

<LLD 2.85E+OO Kfvpton-87 Ci

<LLD

<LLD Krvoton-88 Ci 1.38E+OO

<LLD

<LLD 1.38E+OO Xenon-133m Ci

<LLD

<LLD I

<LLD Xenon-133 Ci 5.01E+01

<LLD

<LLD 5.01E+01 Xenon-135 Ci 1.43E+OO

<LLD

<LLD 1.43E+OO Xenon-138 Ci

<LLD

<LLD Total for Period Ci 5.75E+01 1.79E-01 1.30E+OO 6.42E-01 5.96E+01

2.

Iodine/Halogens lodine-131 Ci 1.27E-04

<LLD

<LLD 1.27E-04 lodine-133 Ci

<LLD

<LLD Total for Period Ci 1.27E-04

<LLD

<LLD 1.27E-04

3.

Particulates Manganese-54 Ci

<LLD

<LLD lron-59 Ci

<LLD

<LLD Cobalt-58 Ci

<LLD

<LLD Cobalt-60 Ci

<LLD

<LLD Zinc-65 Ci

<LLD

<LLD Strontium-89 Ci

<LLD 9.58E-05

<LLD

<LLD 9.58E-05 Molvbdenum-99 Ci

<LLD

<LLD Cesium-134 Ci

<LLD

<LLD Cesium-137 Ci

<LLD

<LLD Cerium-141 Ci

<LLD

<LLD Cerium-144 Ci

<LLD

<LLD Total for Period Ci

<LLD 9.58E-05

<LLD

<LLD 9.58E-05

<LLD - Less than the lower limit of detectipn Page 15

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Solid Waste All solid radioactive waste from PNPP was processed and combined with waste from several other utilities by intermediate vendors (Energy Solutions and Erwin Resin Solutions). This waste was ultimately sent to Clive, Utah disposal facilities for burial.

Table 6: Solid Waste Shipped Offsite for Burial or Disposal

1. Type of Solid Waste Shipped Volume Activity Est. Total Error (m3)

(Ci)

(%)

a. Resins, Filters and Evaporator Bottoms 1.19E+02 4.58E+02

+/-25

b. Dry Active Waste 1.69E+03 1.85E+OO

+/-25

c. Irradiated components, control rods, etc.

O.OOE+OO O.OOE+OO

+/-25

d. Other Waste O.OOE+OO O.OOE+OO

+/-25

2. Estimate of Major (1) Nuclide Composition (by type Radionuclide Abundance Est. Total of waste)

(%)

Error, (%)

a. Resins, Filters and Evaporator Bottoms Mn-54 4.17

+/-25 Fe-55 20.39 Co-58 1.84 Co-60 64.45 Zn-65 6.56

b. Dry Active Waste Mn-54 2.34

+/-25 Fe-55 32.31 Co-60 61.79 Ni-63 1.21

c. Irradiated Components, Control Rods, etc.

N/A N/A N/A

d. Other Waste N/A N/A N/A (1) - "Major" is defined as any individual radionuclide identified as >1 % of the waste type abundance.

3.

Solid Waste Disposition Number of Mode of Transportation Destination Shipments 65 Hittman Transport EnerQv Solutions Bear Creek Operations 2

Hittman Transport Enemv Solutions Gallaher Operations 3

Hittman Transport Erwin Resin Solutions, LLC 151 T.C. Runnion Road 2

Miller Transfer and RiaainQ Enemv Solutions Bear Creek Operations 1

Specialtv Transport Inc.

Enemv Solutions Bear Creek Operations 1

Tri State Motor Transit Enerav Solutions Bear Creek Operations Page 16

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT METEOROLOGICAL DATA The Meteorological Monitoring System at PNPP consists of a 60-meter tower equipped with two independent systems for measuring wind speed, wind direction, and temperature at both 10-meter and 60-meter heights. The tower also has instrumentation to measure dew point and barometric pressure. Data is logged from the tower through separate data loggers, and transmitted to a common plant computer. This system compiles the data and calculates a variety of atmospheric parameters, communicates with the Meteorological Information Dose Assessment System (MIDAS), and sends data over communication links

to the plant Coqtrol Room.

A detailed report of the monthly and annual operation of the PNPP Meteorological Monitoring Program is produced under separate cover. For 2015, the report substantiates the quality and quantity of meteorological data collected in accordance with applicable regulatory guidance.

DOSE ASSESSMENT The maximum concentration for any radioactive release is controlled by the limits set forth in Title 10 of the Code of Federal Regulations, Part 20 (1 OCFR20). Sampling, analyzing, processing, and monitoring the effluent stream ensures compliance with these concentration limits. Dose limit compliance is verified through periodic dose assessment calculations. Some dose calculations are conservatively performed for a hypothetical individual who is assumed to reside on the site boundary at the highe~t potential qose location all year. This person, called the "maximum individual", would incur the maximum potential dose from direct exposure (air plus ground plus water), inhalation, and ingestion of water, milk, vegetation, and fish. Because no one actually meets these criteria, th~ actual dose received by a real membe( of the public is significantly less than what is calculated for this hypothetical individuai.

Dose calculations for this maximum individual at the site boundary are performed for two cases. First, they are performed using data for a 360 degree radius around the plant site (land and water based meteorological sectors); even though some of these sectors are over Lake Erie, which has no permanent residents. The second calculation is performed considering only those sectors around the plant in which people reside (land-bas~d meteorolo~ical sectors).

The calculated hypothetical, maximum individual dose values at the site boundary are provided in Table 7. This table considers all meteorologiqal sectors around PNPP and provides either the whole body or worst-cas~. organ dose values.

Page 17

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 7: Maximum Yearly Individual Site Boundary Dose, Considering All Sectors Type of Dose Organ Estimated Limit

% of Limit Dose, (mrem)

Liquid Effluent Whole body 1.02E-03 3.0E+OO 3.4E-02 GI Tract 1.50E-03 1.0E+01 1.5E-02 Noble Gas Air Dose 5.75E-02 1.0E+01 5.?E-01 Gamma-mrad Air Dose 5.81 E-02 2.0E+01 2.9E-01 Beta-mrad Noble Gas Whole body 8.21 E-03 5.0E+OO 1.6E-01 Skin 1.76E-02 1.5E+01 1.2E-01 Particulate & Iodine Thyroid 2.00E-03 1.5E+01 1.3E-02 Carbon-14

Whole Body 2.59E-01 5.0E+OO 5.2E+OO

C-14 dose calculated at nearest garden.

The calculated hypothetical, maximum 50-mile radius population dose values at the site r boundary are provided in Table 8. This table considers all meteorological sectors around PNPP and provides either the whole body or worst-case, organ dose values.

Table 8: Population Yearly Dose, Considering All Sectors out to 50 miles.

Organ Estimated Dose (person-rem)

Liquid Effluent Whole body 1.4E-01 Thyroid 6.4E-02 Gaseous Effluent Wholebodv 8.4E-04 Thyroid 8.8E-04 Page 18

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 9 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors.

Table 9: Maximum Yearly Individual Site Boundary Dose, Considering Only Land Sectors Type of Dose Organ Estimated Limit

% of Limit Dose, (mrem)

Liquid Effluent Whole Body 1.02E-03 3.0E+OO 3.4E-02 GI Tract 1.50E-03 1.0E+01 1.5E-02 Noble Gas Air Dose 2.51E-03 1.0E+01 2.5E-02 Gamma-mrad Air Dose 2.65E-03 2.0E+01 1.3E-02 Beta'-mrad Noble Gas Whole Body 1.92E-04 5.0E+OO 3.8E-03 Skin 4.01E-04 1.5E+01 2.7E-03 Particulate & Iodine Thyroid 1.79E-04 1.5E+01 1.2E-03 Carbon-14

Whole Body 2.59E-01 5.0E+OO 5.2E+OO

C-14 dose calculated at nearest garden.

Other dose calculations are performed for a hypothetical individual who is assumed to be inside the site boundary for some specified amount of time. This person would receive the maximum dose during the time spent inside site boundary. Because no one actually meets the criteria established for these conservative calculations, the actual dose received by a member of the public is significantly less than what is calculated for this hypothetical individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.

The highest hypothetical dose from liquid effluents to a member of the public inside the site boundary is to a person who is fishing on Lake Erie from the shore on PNPP property. The calculations assume that this person will spend 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year fishing, with a liquid dilution factor of 10. The ratio of the exposure pathway to the doses calculated for offsite locations yields the dose values shown in Table 10.

Table 10: Maximum Site Dose from Liquid Effluents Whole Body Dose, Organ Dose (mrem)

(mrem)

First Quarter 2.6E-04 3.0E-04 Second Quarter 5.2E-04 6.1E-04 Third Quarter 1.5E-06 1.7E-06 Fourth Quarter 5.2E-06 6.1E-06 Annual 8.1E-04 9.4E-04 Page 19

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Although several cases were evaluated to determine the highest hypothetical dose from gaseous effluents to members of the public inside site boundary, the activity inside the site boundary with the highest dose potential is also shoreline fishing. The cases evaluated included traversing a public road within the site boundary, shoreline fishing (assuming fishing 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year), non-plant related training, car-pooling, and job interviews. The maximum on-site gaseous doses generated are shown in Table 11.

Table 11: Maximum Site Dose from Gaseous Effluents Whole Body Dose, Organ Dose (mrem)

(mrem)

First Quarter 9.6E-04 2.0E-03 Second Quarter 5.9E-06 1.2E-05 Third Quarter 5.9E-05 5.9E-05 Fourth Quarter 3.6E-05 3.6E-05 Annual 1.1E-03 2.1E-03 An average whole body dose to individual members of the public at or beyond the site boundary is then determined by combining the dose from gaseous and liquid radiological effluents. The dose from gaseous radiological effluents is based upon the population that lives within 50 miles of PNPP. The dose from liquid radiological effluents is determined for the population that receives drinking water from intakes within 50 miles of PNPP. The results of this calculation are provided in Table 12.

Table 12: Average Individual Whole Body Dose Liquid Effluents Gaseous Effluents (mrem)

(mrem)

First Quarter 3.2E-05 2.2E-07 Second Quarter 2.4E-05 1.0E-08 Third Quarter 3.5E-08 9.6E-08 Fourth Quarter 1.5E-06 1.9E-08 Annual 5.BE-05 3.5E-07 Page 20

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CARBON-14 SUPPLEMENTAL INFORMATION Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. C-14 is released primarily from BWRs through the off-gas system in the form of carbon dioxide (C02). The quantity of gaseous C-14 released to the environment can be estimated using a C-14 source term scaling factor based on power generation.

The U.S. Nuclear Regulatory Commission (NRC) requires an assessment of gaseous C-14 dose impact to a member of the public resulting from routine releases in radiological effluents. Prior to 2011, the industry did not estimate the dose impact of C-14 releases.

Since the dose contribution had been considered negligible compared to the dose impact from effluent releases of noble gases, tritium, particulates and radioiodines. At PNPP, improvements over the years in effluent management practices and fuel performance have resulted in a decrease in the concentration and changes in the distribution of gaseous radionuclides released to the environment.

This report contains estimates of the gaseous C-14 radioactivity released and the resulting public dose resulting from this release. This calculation is done using a spreadsheet provided by EPRI and is based on power production. This method for estimating C-14 release has been endorsed by the NRC. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste at PNPP is not required. Refer to Table 4 and Table 9 for C-14 estimated release values and doses.

GROUNDWATER MONITORING PROGRAM Based on the Environmental Resource Management hydrogeology study, twelve (12) monitoring wells were recommended for the site. Since most groundwater flow drains north towards Lake Erie, the majority of wells are drilled there. A set of control wells was drilled south of the plant, to assess what a typical groundwater profile would be.

There are 4 sets of triplet wells installed at each location. Each triplet has a shallow well of approximately 25 feet, a mid-depth well of approximately 50 feet, and a deep well of approximately 75 feet. These 3 depths are designated A, B and C, from shallowest to deepest, respectively. Refer to Figure 2 for locations of Groundwater wells 1A through 4C.

These wells encompass the groundwater monitoring locations at PNPP.

Page 21

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Manholes G

~

G 2

Piezometers 2A 2C OQ QGroundwaterWells lfi

~

................................... ~~

____ __.I *................................................. ~

N Figure 2: Underdrain System and Groundwater Monitoring Wells

.. :e Page 22

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT The monitoring wells are sampled twice annually, in spring and fall. The sampling is done twice yearly by personnel from FirstEnergy's BETA Laboratories. The samples are shipped to Midwest Laboratories in Illinois. Midwest analyzes the sample for gamma isotopic and tritium. Any positive result less than 500 pCi/L is considered as background activity and not due to plant operations. The ODCM reporting level for tritium in an environmental water sample is 20,000 pCi/L. There was no indication of any effluent releases via groundwater.

T bl 13 S a e ummary o f O ns1te G roun d water s amples Monitoring Well Spring Fall H-3, oCi/L H-3, oCi/L 1A

<LLD

<LLD 18

<LLD

<LLD 1C

<LLD

<LLD 2A

<LLD

<LLD 28

<LLD

<LLD 2C

<LLD

<LLD 3A 189

<LLD 38

<LLD

<LLD 3C

<LLD

<LLD 4A

<LLD 231 48

<LLD

<LLD 4C

<LLD

<LLD Page 23

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING INTRODUCTION The Radiological Environmental Monitoring Program (REMP) was established at PNPP for several reasons. First, it verifies the adequacy of plant design and operation to control radioactive materials and limit effluent releases. Second, it assesses the radiological impact, if any, that the plant has had on the surrounding environment. Third, it ensures compliance with regulatory guidelines. The REMP is conducted in accordance with the PNPP Operating License, Appendix B, Technical Specifications and the ODCM. The Nuclear Regulatory Commission (NRC) established the REMP requirements.

A variety of samples are collected as part of the PNPP REMP. The selection of sample types, locations, and collection frequency are based on many things. Potential pathways for the transfer of radionuclides through the environment to humans, sample availability, local meteorology, population characteristics, land use and NRC requirements are all factors.

To ensure that the REMP data are meaningful and useful, detailed sampling methods and procedures are followed. This ensures that samples are collected in the same manner and from the same locations each time. All samples are packaged on site, and then shipped to an independent vendor laboratory for analysis. The vendor laboratory analyzes the samples and reports results to the PNPP Chemistry Unit staff, the Lake County General Health District, and the State of Ohio Department of Health. Additionally the Lake County General Health District obtains monthly "split" samples of milk, water and vegetation. This permits an independent verification of PNPP's radiological environmental monitoring program.

SAMPLING LOCATIONS REMP samples are collected at numerous locations, both on site and up to 20.6 miles away from the plant. Sampling locations are divided into two general categories: indicator and control. Indicator locations are those that monitor for any environmental impact due to plant operations. They are relatively close to the plant. Control locations are those that are unaffected by plant operation; they are a greater distance from the plant and in the least prevalent wind directions. Data obtained from the indicator locations are compared with data from the control locations. This comparison allows naturally occurring background radiation to be taken into account when evaluating any radiological impact PNPP may have had on the environment. Table 14, Figure 3, Figure 4 and Figure 5 identify the PNPP REMP sampling locations.

Many REMP samples are collected in addition to those required by the PNPP ODCM. The ODCM requirements for each sample type are discussed in more detail later in the report.

Page 24

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 14: REMP Sampling Locations Location#

Description Miles Direction Media (1) 1 Chapel Road 3.2 ENE TLD, AIP 2

Kanda Garden 2.0 ENE Food Products 3

Meteorological Tower 1.0 SE TLD, AIP 4

Site Boundary 0.7 s

TLD, AIP 5

Quincy Substation 0.6 SW TLD, AIP 6

Concord Service Center 11.1 SSW TLD, AIP 7

Site Boundary 0.6 NE TLD, AIP 8

Site Boundary 0.7 E

TLD 9

Site Boundary 0.7 ESE TLD 10 Site Boundary 0.6 SSE TLD 11 Parmly Rd.

0.6 SSW TLD 12 Site Boundary 0.6 WSW TLD 13 Madison-on-the-Lake 4.6 ENE TLD 14 Hubbard Rd.

4.9 E

TLD 15 Eagle St. Substation 5.1 ESE TLD 16 Eubank Garden 0.9 s

Food Products 18 Kijauskas Farm (goat) 2.6 E

Food Products, Milk 19 Goodfield Dairy 9.2 s

Milk 20 Rainbow Farms 1.9 E

Food Products 21 Hardy Rd.

5.1 WSW TLD 23 High St. Substation 7.9 WSW TLD 24 St. Clair Ave.

15.0 SW TLD 25 Offshore - PNPP 2.0 NNW Fish discharge 28 CEI Ashtabula Plant 20.6 ENE Water Intake 29 River Rd.

4.5 SSE TLD 30 Lane Rd.

4.9 SSW TLD 31 Wood and River Rd.

4.9 SE TLD 32 Offshore - Mentor 15.8 WSW Fish 33 River Rd.

4.7 s

TLD 34 PNPP Intake 0.2 NW Water Page 25

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Location#

Description Miles Direction Media (1) 35 Site Boundary 0.7 E

TLD, AIP 36 Lake County Water Plant 4.0 WSW TLD, Water 37 Gerlica Farm 1.6 ENE Food Products 39 Painesville Purification 8.3 w

Water Plant 51 Rettqer Milk Farm (cow) 9.7 s

Milk 53 Great Lakes Nuclear 0.7 WSW TLD Services 54 Hale Rd. School 4.7 SW TLD 55 Center Rd.

2.5 s

TLD 56 Madison High School 4.0 ESE TLD 57 Perry HiQh School 1.7 s

TLD 58 Antioch Rd.

0.8 ENE TLD 59 Lake Shoreline at Green 4.0 ENE Water Rd.

60 Lake Shoreline at Perry 1.0 WSW Water Park 64 Northwest Drain Mouth 0.4 WNW Sediment 66 Lake Shore, Metropolitan 1.4 NE Sediment Park 70 H&H Farm Stand 17.1 SSW Food Products (1)

AIP =Air, Iodine and Particulate TLD = Thermoluminescent Dosimeter Page 26

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT NN\\V

~ -T NNE

" 'NW ENE E

" 'SW ESE SE SS\\\\'

s SSE 0

2 MILES Figure 3: REMP Sampling Locations within Two Miles of Plant Site Page 27

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 0

2 3

4 5

IOM IL Figure 4: REMP Sampling Locations between Two and Eight Miles of the Plant Site Page 28

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 5: REMP Sampling Locations Greater Than Eight Miles from the Plant Site Page 29

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT SAMPLE ANALYSIS When environmental samples are analyzed for radioactivity, several types of measurements are performed to provide information about the types of radiation and radionuclides present.

The major analyses that are performed are discussed below.

Gross beta activity measures the total amount of beta-emitting radioactivity present in a sample, and acts as a tool to identify samples that may require further analysis. Beta radiation may be released by many different radionuclides. Since beta decay results in a continuous energy spectrum rather than the discrete energy levels, or "peaks", associated with gamma radiation, identification of specific beta-emitting nuclides is more difficult.

Therefore, gross beta activity only indicates whether the sample contains normal or abnormal amounts of beta-emitting radioactivity; it does not specifically identify the radionuclides present.

Gamma spectral analysis provides more specific information than does the analysis for gross beta activity. Gamma spectral analysis identifies each radionuclide, and the amount of radioactivity, present in the sample emitting gamma radiation. Each radionuclide has a very specific "fingerprint" that allows for accurate identification and quantification.

Iodine activity analysis measures the amount of radioactive iodine present in a sample.

Some media (e.g. air sample charcoal cartridges) are analyzed directly by gamma spectral analysis. With other media (e.g. milk), the radioiodines are extracted by chemical separation before being analyzed by gamma spectral analysis.

Tritium activity analysis measures the amount of the radionuclide tritium (H-3) present in a sample. Tritium is an isotope of hydrogen that emits low-energy beta particles. Tritium occurs naturally and is also man-made.

Gamma doses received by Thermoluminescent Dosimeters (TLD) while in the field are determined by a special laboratory procedure. Thermoluminescence is a process by which ionizing radiation interacts with the sensitive phosphor material in the TLD. Energy is trapped in the TLD material and can be stored for months or years. This capability provides a method to measure the dose received over long periods of time. The amount of energy that was stored in the TLD as a result of interaction with radiation is released by a controlled heating process and measured in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy as light. The amount of light is directly proportional to the amount of radiation to which the TLD was exposed. Table 15 provides a list of the analyses performed on environmental samples collected for the PNPP REMP.

Sample results are often reported as less than the lower limit of detection(< LLD), which is defined as the smallest amount of radioactive material that will show a positive result for which there can be confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample analysis. When a measurement is reported as

< LLD, it means that no radioactivity was detected. The required detection limits for samples is determined by the sample media and the radionuclide that is being analyzed for and is listed in the ODCM. The NRC has established LLD values for REMP sample analyses. The vendor laboratory for REMP sample analyses complied with those values.

Page 30

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 15: REMP Sample Analyses Tvoe Sample Frequency Analysis Atmospheric Airborne Weekly & Quarterly Gross Beta Activity &

Monitoring Particulates Gamma Spectral Analysis Airborne Weekly lodine-131 Radioiodine Terrestrial Monthly &

Gamma Spectral Analysis &

Monitoring Milk Bi-Monthly when lodine-131 cows are on pasture Broad leaf Monthly during Gamma Spectral Analysis VeQetation QrowinQ season Aquatic Monitoring Water Monthly Gross Beta Activity &

Gamma Spectral Analysis Quarterly Tritium Activity Fish Annually Gamma Spectral Analysis Sediment Biannually Gamma Spectral Analysis Direct Radiation TLD Quarterly &

Gamma Dose Monitoring Annually SAMPLING PROGRAM The contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the environmental monitoring program with pre-operational data (i.e., data from before 1986), operational data from previous years, and control location data. The results for each sample type are discussed below and compared to historical data to determine if there are any observable trends. All results are expressed as concentrations. Refer to Appendix B, 2015 REMP Data Summary Reports for a detailed listing of these results. The NRC requires special reporting whenever sample analysis results exceed set limits. No values exceeded those limits.

PROGRAM CHANGES Due to shutdown of the Ashtabula power plant (location 28), the water control location was shifted to the Painesville Ohio Purification Plant (location 39).

The milking animal (goat) at location 18 died during the summer and the owner chose not to replace the animal. This removes the one milk sample that was in the vicinity of the PNPP.

There are no other milking animals in the vicinity of PNPP to use as a replacement.

ATMOSPHERIC MONITORING Air Air sampling is conducted to detect any increase in the concentration of airborne radionuclides. The PNPP REMP maintains an additional two (2) air sampling locations Page 31

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT above the five (5) locations (four indicators and one control) required by the ODCM. Six (6) of these locations are within four miles of the plant site; the seventh is used as a control location and is eleven miles from PNPP. Air sampling pumps draw continuous samples at a rate of approximately two cubic feet per minute. The air is drawn through glass fiber filters (to collect particulate material) and a charcoal cartridge (to adsorb iodine). The samples are collected on a weekly basis, 52 weeks a year, from each of the seven (7) air sampling stations.

Air samples are analyzed weekly for gross beta activity and radioiodine activity. The air samples are also analyzed by gamma spectral analysis quarterly. A total of 361 air particulate and 361 air radioiodine samples were collected and analyzed. Three samples were not collected, see Appendix F for explanation.

Gross beta activity was detected in all the air samples. The average gross beta activity for the indicator locations was 0.027 pCi/m3 and the controls was 0.028 pCi/m3. Historically, the concentration of gross beta in air has been essentially identical at indicator and control locations. Figure 6 reflects the average gross beta activity for 2015 and the previous years.

All radioiodine samples were less than the lower limit of detection for lodine-131.

Except for naturally occurring Beryllium-7, no radionuclides were identified in the quarterly gamma spectral analysis above the LLD values.

0.035 0.03 1

-...... 0.025 0

~ 0.02

~ 0.015 Vl Vl e 0.01

\\.9 0.005 0

2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year

Indicator

Control Figure 6: Annual Average Gross Beta Activity, in Air TERRESTRIAL MONITORING Collecting and analyzing samples of milk and food products provides data to assess the build-up of radionuclides that may be ingested by humans. The historical data from soil and vegetation samples provides information on atmospheric radionuclide deposition.

Page 32

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Milk Samples of milk are collected once each month from November through March, and twice each month from April through October. Sampling is increased during the summer because animals usually feed outside on pasture and not on stored feed. The PNPP REMP includes three (3) milk locations.

Since the milk sampling locations do not meet the requirements of the ODCM (only one milk-producing animal is located within the required distance vs. two required), broadleaf vegetation sampling (discussed below) is performed. Milk is collected from the available location to augment vegetation sampling.

Milk samples are analyzed by gamma spectral analysis for radioiodines and other radionuclides. A total of forty-six (46) milk samples were collected. With the exception of naturally occurring Potassium-40, no other radionuclides were detected.

Broadleaf Vegetation Because there are not a sufficient number of milk sampling locations, the PNPP REMP samples broadleaf vegetation. These samples are collected monthly during the growing season from six (6) gardens in the vicinity of PNPP and one control location 17.1 miles SSW from PNPP.

Sixty-nine (69) samples were collected and analyzed by gamma spectral analysis.

Four (4) vegetation types were grown and collected: mustard, collard greens, turnip greens and Swiss chard. Beryllium-? and Potassium-40, naturally-occurring radionuclides, were found in the samples, which is expected. No other radionuclides were detected.

AQUATIC MONITORING Radionuclides may be present in Lake Erie from many sources other than the PNPP. These sources include atmospheric deposition, run-off/soil erosion, and releases of radioactivity in liquid effluents from hospitals, universities or other industrial facilities. These sources provide two forms of potential radiation exposure, external and internal. External exposure can occur from contact with water or shoreline sediments, while internal exposure can occur from either direct ingestion of radionuclides or the transfer of radionuclides through the aquatic food chain. Direct ingestion can occur from drinking the water, while the transfer via the aquatic food chain occurs from the eventual consumption of aquatic organisms, such as fish. To monitor these pathways, PNPP samples water, shoreline sediments, and fish.

Water Water is sampled from five (5) locations along Lake Erie in the vicinity of the PNPP as required by the PNPP ODCM. Fifty-four (54) water samples were collected and analyzed for gross beta activity and gamma spectral analysis. From these monthly samples, eighteen (18) quarterly composite samples were analyzed for tritium activity.

Gross beta activity was detected in forty-seven (47) of the fifty-four (54) samples collected.

The indicator average gross beta activity was 1.5 pCi/L and the control average gross beta activity was 1.5 pCi/L. Refer to Figure 7 for the annual average gross beta activity for both indicator and control locations. No tritium or gamma activity was detected.

Page 33

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 4.5 4

_, 3.5 0

3 0..

~ 2.5 Q) co 2

Vl e 1.5 lD 1

0.5 0

1111111 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year

Indicator

Control Figure 7: Annual Average Gross Beta Activity, in Water Sediment Sampling shoreline sediments provides an indication of the accumulation of particulate radionuclides which may lead to an external radiation source to fishermen and swimmers from shoreline exposure. Sediment was sampled from two (2) locations.

Five (5) sediment samples were collected in 2015 and analyzed by gamma spectroscopy.

The only radionuclide detected was naturally occurring Potassium-40.

Fish Fish are analyzed primarily to quantify the radionuclide intake by humans, and secondarily to serve as indicators of radioactivity in the aquatic ecosystem. Fish are collected from two (2) locations annually during the fishing season as required by the ODCM. An important sport or commercial species is targeted, and only the fillets are sent to the laboratory for analysis.

Fourteen (14) fish samples were collected and analyzed - six (6) indicator and eight (8) control. The species were smallmouth bass, white perch, walleye, channel catfish, freshwater drum, white bass and tiger musky. Only naturally occurring Potassium-40 was detected in the samples.

DIRECT RADIATION MONITORING Thermoluminescent Dosimeter (TLD)

Environmental radiation is measured directly at twenty seven (27) locations around the PNPP site and two (2) control locations. The locations are positioned in two rings around the plant as well as at the site boundary. The inner ring is within a one-mile radius of the plant site; the outer ring is four miles to five miles from the plant. The control locations are over ten miles from the plant in the two least prevalent wind directions. Each location has three TLDs, two of which are changed quarterly and one is changed annually.

Page 34

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT A total of 261 TLDs were collected and analyzed. This includes 232 collected on a quarterly basis and twenty nine (29) collected annually. Annual TLDs are not required per the ODCM and are used for supplemental data only.

The annual average dose for all indicator locations was 57.1 mrem, with 59.1 mrem for the control locations.

The average quarterly dose for the indicator locations was 12.5 mrem, and 12.3 mrem for the control locations. Refer to Figure 8.

18 16 14

~ 12 t'.

~ 10 CT E" 8 Q) E 6 4

2 0

2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 Year

Indicator

Control Figure 8: Average Quarterly TLD Dose CONCLUSION There is no detectable radiological effect on the surrounding environment due to operation of the Perry Nuclear Power Plant.

Page 35

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT INTER-LABORATORY CROSS-CHECK COMPARISON PROGRAM Introduction The purpose of the Inter-laboratory Cross-Check Comparison Program is to provide an independent check on the vendor laboratory's analytical procedures. Samples with a known concentration of specific radionuclides are provided to the vendor laboratory. The vendor laboratory measures and reports the concentration of specified radionuclides. The known values are then compared to the vendor results. Results consistently outside established acceptance criteria indicate a need to check instruments or procedures. Regulatory Guide 4.15 specifically required that contractor laboratories that performed environmental measurement participate in the EPA's Environmental Radioactivity Laboratory Inter-Comparison Studies Program, or an equivalent program.

The EPA's program is no longer funded or offered. The reason that the EPA program was referenced in the regulatory guide is that the EPA standards were traceable to National Bureau of Standards (now known as National Institute Standard Technology). In response to this problem, ATI Environmental, Inc. (PNPP vendor lab) incorporated a program offered by Environmental Resource Associates (ERA Company), which covered the same analyses in the same matrix at the same frequency as the EPA program. The ERA Company has received NIST accreditation as an equivalent program. In addition to comparison cross checks performed with the ERA Company, the vendor laboratory routinely monitors the quality of their analyses by:

Analyzing "spiked" samples (samples with a specific quantity of radioactive material present in them) and Participating in the Department of Energy's Mixed Analyte Performance Program (MAPEP).

See Appendix A, for the vendor Inter-Laboratory Cross-Check Comparison Program Results.

Page 36

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT LAND USE CENSUS Introduction Each year a Land Use Census is conducted to identify the locations of the nearest milk animal, garden (of greater than 500 square feet), and residence in each of the meteorological sectors that is over land. Information gathered during the Land Use Census is used for off-site dose assessment and to update sampling locations for the REMP. The census is conducted by traveling all roads within a five-mile radius of the plant site, and recording and mapping the location of the nearest resident, milk animal and vegetable garden. The Land Use Census was conducted on September 26 2015. The census identified the garden, residence and milk animal locations tabulated in Tables 17, 18 and 19 and depicted in Figure 9. Note that the W, WNW, NW, NNW, N, and NNE sectors extend over Lake Erie, and are not included in the survey.

Discussions and Results In general, the predominant land use within the census area continues to be rural/

agricultural. In recent years however, it has been noted that tracts of land once used for farming are now being developed as mini-industrial parks and residential housing. This is reflected in the loss of available milking animals within a five mile radius of PNPP to support the REMP.

Table 17 identifies the nearest residences, by sector, to the PNPP. There were no changes from last year's Land Use Census.

Tabl 17 N e

ea res t R 0d es1 ence, B S t

iy ec or Sector Location Address Miles from Map Locator PNPP Number NE 4384 Lockwood 0.7 1

ENE 4602 Lockwood 1.1 2

E 2626 Antioch 1.0 3

ESE 2836 Antioch 1.1 4

SE 4495 North Ridqe 1.3 5

SSE 3119 Parmly 0.9 6

s 3121 Center 0.9 7

SSW 3850 Clark 0.9 8

SW 2997 Perry Park 1.2 9

WSW 3460 Parmlv 1.0 10 Page 37

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 18 identifies the nearest milking animal by sector, to the PNPP. There were no changes from last year's Land Use Census.

Tabl 18 N e

ea res t M"lk A.

I B S t

I nima, ;y ec or Sector Location Address Miles from Map Locator PNPP Number E

2591 McMackin Rd.

2.6 21 Table 19 lists the nearest gardens by sector to the PNPP consisting of at least 500 square feet. There were no changes from last year's Land Use Census.

Tabl 19 N e

ea res t G d B S t

ar en, iy ec or Sector Location Address Miles from Map Locator PNPP Number NE 2340 Hemlock 0.9 11 ENE 4630 Lockwood 1.1 12 E

2626 Antioch 1.0 3

ESE 2836 Antioch 1.1 4

SE 4671 North Ridge 1.3 15 SSE 4225 Red Mill Valley 1.1 16 s

3121 Center Rd.

0.9 7

SSW 3431 Perry Park 1.9 17 SW 3021 Perry Park 1.3 13 WSW 3460 Parmly 1.0 14 Page 38

5 Miles WSW 2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT SCAlE {Miles)

Lake Erie Ga Mien Re6tden~e

,, king Animal e Figure 9: Land Use Census Map Page 39

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CLAM/MUSSEL MONITORING INTRODUCTION Sampling for macro-invertebrates (clams and mussels) has been conducted in Lake Erie in the vicinity of PNPP, since 1971. The clam/mussel program currently focuses on two species: Corbicula fluminea (Asiatic clam) and Dreissena polymorpha (zebra mussel).

CORBICULA PROGRAM Monitoring specifically for Corbicula was initiated in response to an NRC bulletin and concerns of the Atomic Safety and Licensing Board. The monitoring was done as part of the Environmental Protection Plan (Operating License, Appendix B). The program consists of visually inspecting the raw water systems, when they are opened for maintenance. The purpose of this program is to detect Corbicula, should it appear at PNPP.

Monitoring Samples were collected from raw water systems and examined for shells and fragments. In addition to sample collections, plant components that use raw water are inspected when opened for maintenance or repair. Sample collection/inspection dates are listed in Table 20.

Table 20: Corbicula Monitoring Date Sample Location 3/12/2015 N34 - Turbine Lube Oil Cir.

3/15/2015 N71 - Circulatinq Water 3/15/2015 HP Condenser, North Box "C" 3/15/2015 HP Condenser, North Box "B" 3/15/2015 HP Condenser, North Box "A" 3/15/2015 HP Condenser, North Box "D" 3/16/2015 Div. 2 Diesel Generator Heat Exchanqer, Inlet 3/16/2015 P42-Emerqencv Closed Coolinq 3/16/2015 R46 - Div. 2 Diesel Generator Jacket Water Heat Exchanqer 3/16/2015 N34 -Turbine Lube Oil Cooler. 'A" 3/16/2015 Div.2 Diesel Generator Jacket Water. Heat Exchanger (West) 3/16/2015 Circulating Water Basin & Flumes 3/17/2015 N71 - Circulating Water 3/17/2015 Emergency Closed Cooling Heater "B" 6/15/201 5 Lube Oil Cooler 1 N34-B0001 A 7/20/2015 Fire Protection System Page 40

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 7/20/2015 Hvdrant No. 30 7/24/2015 Lube Oil Cooler 1 N34-B0001 B 8/10/2015 Lube Oil Cooler N34B1 B 8/10/2015 Lube Oil Cooler N3481 B 8/11/2015 Lube Oil Cooler 1N34-B0001A 8/13/2015 Fire Hydrant No. 28 9/1/2015 Lube Oil Cooler 1N3400001A 9/8/2015 Training Center Yard Piping, Order-200648596 9/14/2015 Lube Oil Cooler 1 N34-B001 - "B" 10/7/2015 Fire Protection System P54 in area of 54F5065 East side of P&R Building Cc;mclusions Although the presence of Corbicula was detected at the Eastlake Power Plant, it has not been demonstrated that their presence has created any operational problems at PNPP. As in the past, the monitoring program did not identify Corbicula in any sample collected.

DREISSENA PROGRAM Dreissena or zebra mussels were first discovered at PNPP in September 1988. The initial collection of nineteen (19) mussels was made as part of the Corbicula monitoring program.

The Dreissena monitoring program began in 1989, with monitoring and testing. The current con~rol program was designed and implemented in 1990.

Monitoring

In addition to visually inspecting the plant's raw water systems when they are opened for maintenance or repair, monitoring methods include the use of commercial divers and side-stream monitors. Commercial divers monitor mussel infestation <;luring the inspection of forebays, basins, and the intake and discharge structures. Divers have also been used to take underwater videotapes of the water basins and intake tunnel. -Side-stream monitors are

flow-through containers that receive water diverted from plant systems and are set up at two in-plant locations during the mussel season.

Treatment Chemicals used for mussel control included sodium hypochlorite and a commercial molluscicide. The chlorine is intermittently injected into the plant service water, emergency service water, and circulating water systems by metering sodium hypochlorite into each system's influent. Sodium bisulfite is added at the plant discharge structure for dechlorination prior to return into Lake Erie.

/

Page 41

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT The Ohio Environmental Protection Agency (OEPA) has approved the use of a commercial molluscicide. The chemical selected for use at the PNPP was alkyl-dimethyl-benzyl-ammonium chloride. Treatment was applied once in 2015. The active ingredients were detoxified by adsorption using bentonite clay prior to discharge into Lake Erie.

Results The effectiveness of the intermittent biocide treatment has been determined in several ways.

First, visual inspections of raw water system components are conducted when systems are open during maintenance or repair. In addition, settlement monitors were inspected for new settlement. No live settlement has been found in any plant *component to date.

The effectiveness of the application of the commercial molluscicide was measured by observing mortality of mussels placed in a flow-through container installed in plant service water and subjected to the chemical treatment. The observed mortality rate utilizing the flow-through container was 100%. To date, PNPP has had no significant problems related to zebra mussels.

Conclusions PNPP has taken the approach that the best method for avoiding problems with zebra mussels is preventive treatment of plant water systems. The current program of monitoring and chemical treatment will be continued to minimize the possibility that PNPP will experience future problems due to zebra mussels.

HERBICIDE APPLICATIONS Herbicides are used sparingly on the PNPP site. A request must be made to and approved by the PNPP Chemistry Unit prior to spraying to ensure that only approved chemicals are used, and only in approved areas. Each application was in compliance with the Ohio Environmental Protection Agency's rules and regulations. There were no adverse environmental impacts observed during weekly site environmental inspections as a result of these applications. The herbicides used were Round-Up Quick Pro, Brushmaster, Trimec, Finale and Pronto. For each application, the type of weed to be treated dictated the herbicide and concentration to be used. Table 21 provides quantity for each chemical used.

The quantity represents the amount of herbicide applied, prior to any dilution.

T bl 21 H b" "d A I"

a e er 1c1 e

>p 1cat1ons Chemical Amount (gal)

Round-Up Quick Pro 16.0 Brush master 6.1 Trimec992 27.1 Finale 25.8 Pronto 39.5 Page 42

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT SPECIAL REPORTS NPDES PERMIT EXCEEDANCES The Ohio Environmental Protection Agency (OEPA) issues the National Pollutant Discharge Elimination System (NPDES) permit. It establishes monitoring requirements and limits for discharges from the PNPP. It also specifies the locations from which the plant is allowed to discharge.

There were three NPDES exceedances at PNPP in 2015. Notifications were made to the Ohio EPA for each occurrence.

1.

On 8/12/15, prior to commencing zebra mussel treatment, a feed hose ruptured spilling no more than 55 gallons of biocide (NALCO H150M) into Lake Erie. The cause for the hose rupture could not be determined.

2.

On 8/22/15, an excessive sodium hypochlorite feed rate into the Service Water system resulted in an NPDES violation for excessive Total Residual Chlorine at the Outfall structure. The cause for the event was an inadequate procedure an'd inaccurate flow rate information. The corrective action was to revise the procedure and to use more accurate feed instrumentation.

3.

On 12/15/15,the Service Water chlorination skid drain valve SW-2 was opened which drained more than 100 gallons of sodium hypochlorite to the Service Water intake structure that resulted in an NPDES violation. The cause for this event was operating a valve outside of procedure guidance. The corrective action was to lock closed the improperly opened valve.

ENVIRONMENTAL PROTECTION PLAN The Environmental Protection Plan (EPP), which is Appendix B of the PNPP Operating License, requires a non-radiological environmental monitoring and reporting program be established at the PNPP.

Other.than the non-compliance NPDES report (mentioned above) no other reports were submitted in 2015.

ENVIRONMENTAL IMPACT EVALUATIONS All proposed changes to the PNPP design or operation, as well as tests or experiments, must be evaluated for potential environmental impacts in accordance with the EPP and administrative quality assurance procedures.

Approval was obtained from regulatory agencies for minor stream modifications. The modifications were done for flood control purposes as a part of the required changes due to the Fukushima event.

Page 43

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Appendix A Inter-Laboratory Cross Check Comparison Program Results

~~L All Environmental, Inc.

llt't1( /""\\I Midwest Laborato..y

- 700 Landwehr Road* Northbrook, IL 60062-2310 phona (847) 564-0700 *fax (847) 564-4517 NOTE:

APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. 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, 2015 through December, 2015

(

Appendix A lnterlaboratorv 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 environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by 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 Tabl~ A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

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

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

A1

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES8 Analysis Gamma Emitters Strontium-89b Strontium-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium lodine-131, lodine-129b Uranium-238, Nickel-63b Technetium-99b lron-55b Other Analyses b Level 5 to 100 pCi/liter or kg

> 100 pCi/liter or kg 5 to 50 pCi/liter or kg

> 50 pCi/liter or kg 2 to 30 pCi/liter or kg

> 30 pCi/liter or kg

~ 0.1 g/liter or kg s 20 pCi/liter

> 20 pCi/liter s 100 pCi/liter

> 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.

b Laboratory limit.

A2 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% bf 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

\\

TABLEA-1. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b

Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 - 71.20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41.90 30.80 - 48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/- 3.08 75.70 61.80 - 83.30 Pass ERW-1448 4/6/2015 Cs-137 191.9 +/-5.9 189.0 170.0 - 210.0 Pass ERW-1448 4/6/2015 Co-60 85.05 +/-4.59 84.50 76.00 - 95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 - 238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05+/-1.90 42.60 22.10 - 54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93+/-1.12 32.90 21.30 - 40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 - 28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/- 0.56 8.43 6.33 -9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56 -6.01 Pass ERW-1456 4/6/2015 Uranium 5.98 +/-0.31 6.59 4.99 - 7.83 Pass ERW-1461 4/6/2015 H-3 3,254+/-180 3280 2,770 - 3,620 Pass ERW-5528 10/5/2015 Sr-89 34.76 +/- 0.06 35.70 26.70 - 42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 Pass ERW-5531 10/5/2015 Ba-133

'30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.57 62.30 50.69 - 68.50 Pass ERW-5531 10/5/2015 Cs-137 163.1 +/- 4.8 157.0 141.0 -175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71.10 64.00 - 80.70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 113.0 -149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 - 64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/- 0.04 36.60 24.10 - 44.20 Pass ERW-5537

' 10/5/2015 1-131

/

25.54 +/- 0.60 26.30 21.90 - 31.00 Pass ERW-5540 10/5/2015 Ra-226' 7.32 +/- 0.37 7.29'*

5.49 - 8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46 - 5.85 Fail ERW-5540e 10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 - 5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20

45. 70 - 62.40 Pass ERW-5543 10/5/2015 H-3 21,260 +/- 351 21,300 18,700 - 23,400 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.

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

A1-1

TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards).

a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental. Inc.

2015-1 6/24/2015 30cm.

98.81 103.67 +/- 6.05 69.20 -128.50 Pass 2015-1 6/24/2015 30cm.

98.81 111.32+/-15.97 69.20 -128.50 Pass 2015-1 6/24/2015 60cm.

24.70 27.23 +/- 1.33 17.30 -32.10 Pass 2015-1 6/24/2015 60cm.

24.70 26.98 +/- 4.98 17.30 -32.10 Pass 2015-1 6/24/2015 120 cm.

6.18 6.71 +/-1.77 4.30 -8.00 Pass 2015-1 6/24/2015 120 cm.

6.18 6.78 +/- 0.38 4.30 -8.00 Pass 2015-1 6/24/2015 120 cm.

6.18 6.43 +/- 2.00 4.30 -8.00 Pass 2015-1 6/24/2015 150 cm.

3.95 4.13 +/-0.72 2.80 - 5.10 Pass 2015-1 6/24/2015 150 cm.

3.95 4.12+/-1.36 2.80 - 5.10 Pass 2015-1 6/24/2015 150 cm.

3.95 4.50 +/- 1.51 2.80 - 5.10 Pass 2015-1 6/24/2015 180 cm.

2.74 3.27 +/- 0.28 1.90 - 3.60 Pass 2015-1 6/24/2015 180 cm.

2.74 3.05 +/- 1.11 1.90 - 3.60 Pass 2015-1 6/24/2015 180 cm.

2.74 3.14 +/- 0.18 1.90 - 3.60 Pass A2-1

TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). b mrem Lab Code Irradiation Delivered Reported Performance 0

Date Description Dose Dose Quotient (P)

Acceptance d Environmental. Inc.

2015-2 12/15/2015 Spike 1 138.0 118.5 +/- 2.1

-0.14 Pass 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6

-0.13 Pass 2015-2 12/15/2015 Spike 3 138.0 121.9+/-1.9

-0.12 Pass 2015-2 12/15/2015 Spike 4 138.0 124.5 +/- 3.3

-0.10 Pass 2015-2 12/15/2015 Spike 5 138.0 126.5 +/- 3.2

-0.08 Pass 2015-2 12/15/2015 Spike 6 138.0 140.0 +/- 4.2 0.01 Pass 2015-2 12/15/2015 Spike 7 138.0 128.2 +/- 1.2

-0.07 Pass 2015-2 12/15/2015 Spike 8 138.0 128.0 +/- 4.0

-0.07 Pass 2015-2 12/15/2015 Spike 9 138.0 124.9 +/-5.1

-0.09 Pass 2015-2 12/15/2015 Spike 10 138.0 122.9 +/- 3.0

-0.11 Pass 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0

-0.11 Pass 2015-2 12/15/2015 Spike 12 138.0 119.0 +/- 3.4

-0.14 Pass 2015-2 12/15/2015 Spike 13 138.0 123.0 +/- 2.7

-0.11 Pass 2015-2 12/15/2015 Spike 14 138.0 125.4 +/- 2.0

-0.09 Pass 2015-2 12/15/2015 Spike 15 138.0 122.0 +/- 3.1

-0.12 Pass 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0

-0.12 Pass 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1

-0.14 Pass 2015-2 12/15/2015 Spike 18 138.0 117.0 +/-2.3

-0.15 Pass 2015-2 12/15/2015 Spike 19 138.0 120.8 +/- 2.6

-0.12 Pass 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0

-0.11 Pass Mean (Spike 1-20) 123.4 0.11 Pass Standard Deviation (Spike 1-20) 5.0 0.04 Pass

TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N 13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) 0 Performance Quotient (P) is calculated as ((reported dose - conventially true value) + conventially true value) where the conventially true value is the delivered dose.

d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.

e Tables A2.1 and A2.2 assume 1 roentgen = 1 rem (per NRC -Health Physics Positions Based on 1 O CFR Part 20 - Question 96 - Page Last Reviewed/Updated Thursday, October 01, 2015).

A2-2

TABLE A-3. In-House "Spiked" Samples Lab Code b W-020315 W-021215 W-021215 SPW-687 SPAP-689 SPAP-691 SPAP-691 -

SPW-693 SPW-693 SPW-693 SPW-693 SPMl-697 SPMl-697 SPMl-697 SPMl-697 SPW-699 W-031115 W-030215 SPF-1040 SPF-1040 SPW-1036 SPW-1374 W-040815 W-040815 SPW-1038 W-2165 W-2165 W-2165 W-2165 W-2165 W-2392 W-2392 W-2392' W-2392 W-042415 W-050715 W-050715 W-061215 W-061215 U-2982 U-3200 w.70915 W-70915 SPAP-3859 SPAP-3861 Date Analysis 213/2015 Ra-226 211212015 Gr. Alpha 2112/2015 Gr. Beta 2127/2015 Ni-63 3/212015 Gr. Beta 3/212015 Cs-134 3/212015 Cs-137 3/212015 Cs-134 3/212015 Cs-137 3/212015 Sr-89 3/25/2015 Sr-90 3/212015 Cs-134 3/212015 Cs-137 3/212015 Sr-89 3/212015 Sr-90 3/212015 H-3 3/11 /2015 Ra-226 3/212015 Ra-228 3/16/2015 Cs-134 3/16/2015 Cs-137 3/25/2015 Fe-55 4/6/2015 U-238 4/8/2015 Gr. Alpha 4/8/2015 Gr. Beta 4/13/2015 C-14 4/20/2015 H-3 4/20/2015 Sr-89 4/20/2015 Sr-90 4/20/2015 Cs-134 4/20/2015 Cs-137 4/13/2015 H-3 4/13/2015 Ni-63 4/13/2015 Cs-134 4/13/2015 Cs-137 4/24/2015 Ra-226 5/7/2015 Gr. Alpha 5/7/2015 Gr. Beta 6/12/2015 Gr. Alpha 6/12/2015 Gr. Beta 6/9/2015 Gr. Beta 6/9/2015 H-3 7/9/2015 Gr. Alpha 7/9/2015 Gr. Beta 7/21/2015 Gr. Beta 7/21/2015 Cs-134 Concentration (pCi/L)"

Laboratory results

, 2s, n=1 c 16.19 +/- 0.42 18.38 +/- 0.39 27.98 +/- 0.32 239.6 +/- 3.5 42.37 +/- 3.50 1.77 +/- 0.61 83.02 +/- 2.60 44.30 +/-2.53 74.82 +/- 3.50 87.45 +/- 3.62 37.22 +/- 1.55 96.67 +/- 7.74 78.51 +/- 7.02 72.98 +/-4.86 39.17 +/- 1.51 59,592 +/- 703 13.73 +/- 0.35 32.79 +/- 2.31 787.5 +/- 9.2 2,599 +/- 24 1,792 +/-63 46.03 +/-2.25 20.18 +/- 0.42 29.70 +/- 0.33 3,497 +/- 9 5550 +/- 226 90.70 +/- 8.20 76.80 +/- 2.00 62.40 +/- 6.40 91.30 +/- 7.70 5032 +/- 214 222.4 +/- 3.8 53.26 +/- 5.01 91.90 +/- 7.76 1,2.52 +/- 0.39 19.<;>5 +/- 0.41 27.30 +/- 0.32 20.72 +/- 0.44 28.51 +/- 0.33 500.1 +/- 5.1 '

2229 +/-424 18.76 +/- 0.40 29.71 +/- 0.33 41.59 +/- 0.12 1.69 +/- 0.60 A3-1 Known Activity 16.70 20.10 30.90 202.4 43.61 1.90 97.20 53.40 73.80 87A8 38.10 107.00 73.84 87.48 38.10 58,445 16.70 31.44 84Q.O 2,360 1961 41.70 20.10 30.90 4,734 5,780 108.70 75.90 57.30 84.00 5780 202.0 57.30 84.20 16.70 20.10 30.90 20.10 30.90 604.0 2346 20.10 30.90 43.61 1.69 Control Limits d 13.36 - 20.04 16.08 -24.12 24.72 - 37.08 161.9-242.9 34.89 - 52.33 1.52 -2.28 77.76 - 116.64 42.72 - 64.08 59.04 - 88.56 69.98 - 104.98 30.48 - 45.72 85.60 - 128.40 59.07 - 88.61 69.98 - 104.98 30.48 - 45.72 46,756 - 70,134 13.36 - 20.04 25.15 - 37.73 672.0 - 1,008.0 1,888 - 2,832 1,569 - 2,353 25.02 - 58.38 16.08-24.12 24.72 - 37.08 2,840 - 6,628 3,468 - 8,092 65.22 - 152.18 45.54 - 106.26 34.38 - 80.22 50.40 - 117.60 3468 - 8092 121.2 - 282.8 34.38 - 80.22 50.52 - 117.88 10.02 - 23.38 12.06-28.14 18.54 - 43.26 12.06 - 28.14 18.54 - 43.26 362.4 - 845.6 1408 -3284 12.1 -28.1 18.5 -43.3 26.17 -61.05 1.0 -2.4 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)"

Lab Code b Date Analysis Laboratory results Known Control 2s,n=1c Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 - 135.03 Pass SPMl-3863 7/21/2015 Cs-134 38.21 +/- 5.12 47.02 28.21 - 65.83 Pass SPMl-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 - 102.45 Pass SPMl-3863 7/21/2015 Sr-90 41.05 +/- 1.62 37.78 22.67 - 52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 - 65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 - 102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 - 52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319 - 80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 - 565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 - 754.7 Pass SPMl-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 - 6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 - 56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 - 44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5 +/- 115.9 740.0 444.0 - 1036.0 Pass SPF-4104 7/29/2015 Cs-137 2,469 +/- 59 2,340 1,404 - 3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06 - 28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58 +/- 0.32 30.90 18.54 - 43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 - 23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06 - 28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 - 43.26 Pass W-091415 9/14/2016 Gr. Alpha 19.35 +/- 0.51 20.10 12.06 -28.14 Pass W-091415 9/14/2016 Gr. Beta 31.53 +/- 0.35 30.90 18.54 - 43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02 - 23.38 Pass W-100615 10/6/2016 Gr. Alpha 20.62 +/- 0.43 20.10 12.06 -28.14 Pass W-100615 10/6/2016 Gr. Beta 29.35 +/- 0.33 30.90 18.54 - 43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280 - 7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52 - 138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 - 116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 - 23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86 - 44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738 - 15,723 Pass W-6086,6087 11/18/2015 Cs-134 92.98 +/- 7.29 96.25 57.75 - 134.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76 - 116.12 Pass W-112515 11/25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06 -28.14 Pass W-112515 11/25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54 - 43.26 Pass W-120715 12/7/2015 Fe-55 2,431 +/- 97 2,319 1,391 - 3,247 Pass W-120815 12/8/2015 Gr.Alpha 20.72 +/- 0.43 20.10 12.06 - 28.14 Pass W-120815 12/8/2015 Gr. Beta 29.50 +/- 0.33 30.90 18.54 - 43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02 - 23.38 Pass

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

b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).

0 Results are based on single determinations.

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

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

A3-2

TABLE A-4. In-House "Blank" Samples Concentration {pCi/L) 8 Lab Code Sample Date Analysisb Laboratory results {4.66cr)

Acceptance Type LLD Activityc Criteria (4.66 cr)

W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/- 0.02 1

W-021215 Water 2/12/2015 Gr. Alpha 0.47

-0.37 +/- 0.30 2

W-021215 Water 2/12/2015 Gr. Beta 0.76

-0.62 +/- 0.51 4

SPW-686 Water 2/27/2015 Ni-63 2.36

-0.74+/-1.42 20 SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003

-0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006

-0.785 +/- 1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/- 0.38 2

SPW-692 Water 3/2/2015 Cs-134 6.70

-1.57 +/- 3.55 10 SPW-692 Water 3/2/2015 Cs-137 6.18

-0.15 +/- 3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61

-0.51 +/- 0.51 5

SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/- 0.33 1

SPMl-696 Milk 3/2/2015 Ci:;-134 3.75

-0.25 +/-2.24 10 SPMl-696 Milk 3/2/2015 Cs-137 4.36

-0.25 +/-2.24 10 SPMl-696 Milk 3/2/2015 Sr-89 0.80

-0.40 +/- 0.84 5

SPMl-696 Milk 3/2/2015 Sr-90 0.49 0.9& +/- 0.32 1

SPW-698 Water 3/2/2015 H~3 144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/- 368.1 1000 SPW-1037 Water 3/16/2015 C-14 8.94 2.16 +/- 5.47

~00 SPF-1039 Fish 3/16/2015 Cs-134 13.54

-1.00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2

W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 1

W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-05071.5 Water 517/2015 Gr. Alpha 0.38

-0.10 +/- 0.25 2

W-050715 Water 517/2015 Gr. Beta 0.74

-0.14 +/- 0.51 4

W-061215 Water 6/12/2015 Gr. Alpha 0.42

-0.10 +/- 0.29 2

W-061215 Water 6/12/2015 Gr. Beta 0.75

-0.04 +/- 0.53 4

SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 '+/- 0.002 2

SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 0.009 0.000 +/- 0.005 0.05 SPMl-3862 Milk 7/21/2015 Cs-134 3.13 '

1.56+/-1.74 10 SPMl-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMl-3862 Milk 7/21/2015 Sr-89 2.17

-1.30 +/- 2.05 5

SPMl-3862 Milk 7/21/2015 Sr-90.

0.90 0.74 +/- 0.50 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 SPW-3870 Water 7/21/2015 Sr-89 2.28

-0.42 +/- 1.80 5

SPW-3870 Water 7/21/2015 Sr-90 0.84 0.25 +/- 0.42 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66cr)

Acceptance Type LLD Activityc Criteria (4.66 cr)

SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77+/-1.82 20 SPW-3876 Water 7/21/2015 Tc-99 5.49

-3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52 +/- 10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51.3 +/- 83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17

-37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/- 8.06 100 W-081015 Water 8/10/2015 Gr. Alpha 0.48

-0.10 +/- 0.33 2

W-081015 Water 8/10/2015 Gr. Beta 0.78

-0.18. +/- 0.54 4

W-081815 Water 8/18/2015 Ra-226 0.03 0.03 +/- 0.02 2

W-090615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2

W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4

W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30.

2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/- 0.54 4

W-100615 Water 10/6/2015 Gr. Alpha 0.41

-0.15 +/- 0.27 2

W-100615 Water 10/6/2015 Gr. Beta 0.75

-0.12 +/- 0.52 4

W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/- 0.30 2

W-112515 Water 11/25/2015 Gr. Beta 0.7.8

-0.31 +/- 0.54 4

W-120815 Water 12/8/2015 Gr. Alpha 0.42

-0.08 +/- 0.29 2

W-120815 Water 12/8/2015 Gr. Beta 0.76 0.17 +/- 0.54 4

W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2

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

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

0 Activity reported is a net activity result.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-62,63 1/7/2015 Gr. Beta 5.72 +/-0.12 5.78 +/- 0.12 5.75 +/- 0.42 Pass CF-62,63 1/7/2015 Be-7 0.915 +/- 0.135 0.919 +/- 0.102 0.917 +/- 0.15 Pass CF-62,63 1/7/2015 K-40 3.97 +/- 0.28 3.88 +/- 0.23 3.92 +/- 0.33 Pass CF-62,63 1/7/2015 Sr-90 0.017 +/- 0.006 0.011. +/- 0.006 0.014 +/- 0.004 Pass SG-83,84 1/12/2015 K-40 10.11+/-1.42 9.69+/-1.20 9.90 +/- 1.16 Pass SG-83,84 1/12/2015 Tl-208 0.57 +/- 0.07 0.56 +/- 0.06 0.57 +/- 0.05 Pass SG-83,84 1/12/2015 Pb-212 1.73+/-0.10 1.58 +/- 0.09 1.65 +/- 0.13 Pass SG-83,84 1/12/2015 Pb-214 13.33 +/- 0.33 13.88 +/- 0.28 13.61 +/- 0.22 Pass SG-83,84 1/12/2015 Bi-214 13.48 +/- 0.39 13.45 +/- 0.29 13.47 +/- 0.24 Pass SG-83,84 1/12/2015 Ra-226 25.68 +/- 2.19 26.22 +/- 1.53 25.95+/-1.34 Pass SG-83,84 1/12/2015 Ac-228 13.33 +/- 0.59 12.86 +/- 0.43 13.09 +/- 0.36 Pass AP-011215AfB 1/12/2015 Gr. Beta 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.003 Pass WW-315,316 1/27/2015 H-3 1,961 +/- 178 1,868 +/- 174 1,915 +/- 124 Pass DW-60010,60011 1/28/2015 Ra-226 1.25 +/- 0.14 1.40 +/- 0.15 1.33 +/- 0.10 Pass DW"60010,60011 1/28/2015 Ra-228 2.00 +/- 0.66 1.39 +/- 0.60 1.70 +/- 0.45 Pass SG-336,337 1/30/2015 Bi-214 6.63 +/- 0.20 6.45 +/- 0.45 6.54 +/- 0.21 Pass SG-336,337 1/30/2015 Pb-214 6.45 +/- 0.19 6.45 +/- 0.37 6.45 +/- 0.21 Pass SG-336,337 1/30/2015 Ac-228 4.43 +/- 0.24 4.20 +/- 0.58 4.32 +/- 0.31 Pass AP-020415AfB 2/4/2015 Gr. Beta 0.021 +/- 0.004 0.019 +/- 0.035 0.035 +/- 0.020 Pass AP-021115AfB 2/11/2015 Gr. Beta 0.034 +/- 0.004 0.040 +/- 0.047 0.037 +/- 0.003 Pass DW-60023,60024 2/26/2015 Ra-226 1.52 +/- 0.15 1.51 +/- 0.15 1.52 +/-0.11 Pass DW-60023,60024 2/26/2015 Ra-228 0.97 +/- 0.48 1.66 +/- 0.58 1.32 +/- 0.38 Pass S-799,800 2/26/2015 K-40 11.96 +/- 0.98 11.49 +/- 0.82 11.72 +/- 0.64 Pass S-799,800 2/26/2015 Tl-208 0.36 +/- 0.04 0.31 +/- 0.04 0.34 +/- 0.03 Pass S-799,800 2/26/2015 Pb-212 0.92 +/- 0.06 0.91 +/- 0.06 0.91'+/-0.05 Pass S-799,800 2/26/2015 Bi-212 1.26 +/- 0.45 1.50 +/- 0.40 1.38 +/- 0.30 Pass S-799,800 2/26/2015 Ac-228 1.35 +/- 0.22 1.23 +/- 0.17 1.29 +/- 0.14 Pass SG-834,835 2/2/2015 Gr. Alpha 113.3 +/- 6.3 117.2+/-2.8 115.2 +/- 3.4 Pass SG-834,835 2/2/2015 Gr. Beta 82.27 +/- 2.79 84.33 +/- 2.74 83.30+/-1.96 Pass DW-60031,60032 3/4/2015 Gr. Alpha 185.4 +/- 7.4 177.0 +/- 7.2 181.2 +/- 5.2 Pass DW-60036,60037 3/4/2015 Ra-226 6.89 +/- 0.34 6.88 +/- 0.32 6.89 +/- 0.23 Pass DW-60036,60037 3/4/2015 Ra-228 4.43 +/- 0.73 4.41 +/- 0.72 4.42 +/- 0.51 Pass DW-60048,60049 3/4/2015 Ra-226 0.84 +/- 0.10 0.94 +/- 0.11 0.89 +/- 0.07 Pass DW-60048,60049 3/4/2015 Ra-228 0.68 +/- 0.41 1.42 +/- 0.58 1.05 +/- 0.36 Pass AP-1169, 1170 3/19/2015 Be-7 0.20 +/- 0.02 0.24 +/- 0.10 0.22 +/- 0.07 Pass DW-60069,60070 4/8/2015 Gr. Alpha 3.58 +/- 0.88 3.92 +/- 0.88 3.75 +/- 0.62 Pass AP-040915 4/9/2015 Gr. Beta 0.027 +/- 0.005 0.023 +/- 0.005 0.025 +/- 0.003 Pass WW-2394,2395 4/13/2015 H-3 1,628 +/- 139 1,695+/-141 1,662 +/- 99 Pass SG-1847,1848 4/20/2015 K-40 3.24 +/- 1.18 1.99 +/- 0.76 2.62 +/- 0.70 Pass SG-1847, 1848 4/20/2015 Pb-214 5.80 +/- 0.22 6.23 +/- 0.76 6.02 +/- 0.40 Pass SG-1847, 1848 4/20/2015 Ac-228 5.26 +/- 0.51 5.00 +/- 0.42 5.13 +/- 0.33 Pass XWW-2267,2268 4/23/2015 H-3 6,584 +/- 244 6,164 +/- 237 6,374 +/- 170 Pass XWW-2078,2079 4/27/2015 H-3 359.0 +/- 89.6 418.7 +/- 92.3 388.9 +/- 64.3 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XWW-2162,2163 4/28/2015 H-3 4,408 +/- 201 4,242 +/- 198 4,325 +/- 141 Pass SG-1868, 1869 4/28/2015 Gr. Alpha 47.57 +/- 3.63 43.61 +/- 3.58 45.59 +/- 2.55 Pass SG-1868,1869 4/28/2015 Gr. Beta 50.90 +/- 1.94 51.90 +/- 2.02 51.40+/-1.40 Pass SG-1868, 1869 4/28/2015 Pb-214 13.80 +/- 0.52 13.54 +/- 0.62 13.67 +/- 0.40 Pass SG-1868,1869 4/28/2015 Ra-228 20.10 +/- 0.92 22.10+/-1.29 21.10 +/- 0.79 Pass AP-042915 4/29/2015 Gr. Beta 0.014 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 Pass DW-60076,60077 5/4/2015 Ra-228 2.89 +/- 0.61 2.45 +/- 0.57 2.67 +/- 0.42 Pass AP-050515 5/5/2015 Gr. Beta 0.026 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.003 Pass AP-051115 5/11/2015 Gr. Beta 0.006 +/- 0.005 0.010 +/- 0.005 0.008 +/- 0.004 Pass DW-60087,60088 5/14/2015 Ra-226 1.58 +/- 0.17 1.52 +/- 0.17 1.55 +/-0.12 Pass DW-60087,60088 5/14/2015 Ra-228 0.94 +/- 0.50 0.94 +/- 0.50 0.94 +/- 0.35 Pass SG-2436,2437 5/15/2015 Pb-214 22.90 +/- 2.31 24.10 +/- 2.43 23.50 +/- 1.68 Pass SG-2436,2437 5/15/2015 Ra-228 47.95 +/- 0.61 47.80 +/- 0.71 47.88 +/- 0.47 Pass SG-2436,2437 5/15/2015 Gr. Alpha 267.8 +/- 7.9 254.6 +/- 7.6 261.2 +/-5.5 Pass SG-2458,2459 5/19/2015 Pb-214 75.00 +/- 1.66 77.70 +/- 1.75 76.35+/-1.21 Pass SG-2458,2459 5/19/2015 Ra-228 41.10 +/- 0.92 40.80 +/- 0.83 40.95 +/- 0.62 Pass DW-60095,60096 5/26/2015 Gr. Alpha 1.34 +/- 0.69 0.91 +/- 0.62 1.13 +/- 0.46 Pass AP-052715 5/27/2015 Gr. Beta 0.010 +/- 0.003 0.010 +/- 0.003 0.010 +/- 0.002 Pass S-2627,2628 5/29/2015 Pb-214 0.85 +/- 0.07 0.85 +/- 0.07 0.85 +/- 0.05 Pass S-2627,2628 5/29/2015 Ac-228 0.85 +/- 0.14 1.08 +/- 0.12 0.97 +/- 0.09 Pass S-2627,2628 5/29/2015 Cs-137 0.07 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass S-2605,2606 6/1/2015 Ac-228 0.42 +/- 0.06 0.38 +/- 0.07 0.40 +/- 0.05 Pass S-2605,2606 6/1/2015 Ra-226 0.44 +/- 0.03 0.49 +/- 0.03 0.47 +/- 0.02 Pass S-2605,2606 6/1/2015 K-40 10.89 +/- 0.51 11.40 +/- 0.48 11.15 +/- 0.35 Pass S-2605,2606 6/1/2015 Cs-137 0.05 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 Pass S-2858,2859 6/2/2015 Cs-137 34.30 +/- 16.05 40.66 +/- 17.79 37.48 +/- 11.98 Pass S-2858,2859 6/2/2015 Be-7 1501 +/- 264 1171+/-214 1336 +/- 170 Pass S-2858,2859 6/2/2015 K-40 22,122 +/- 658 20,987 +/- 600 21,555 +/- 445 Pass AP-060315 6/3/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass DW-30107,30108 6/8/2015 Gr. Alpha 1.34 +/- 0.82 1.47 +/- 0.85 1.41 +/- 0.59 Pass SG-2900,2901 6/9/2015 Ac-228 10.22 +/- 1.36 8.32 +/- 1.07 9.27 +/- 0.87 Pass SG-2900,2901 6/9/2015 Pb-214 7.55 +/- 0.43 7.27 +/- 0.41 7.41 +/- 0.30 Pass AP-061515 6/15/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass XWW-3173,3174 6/18/2015 H-3 841.9 +/- 123.6 799.3 +/- 122.4 820.6 +/- 87.0 Pass AP-062215 6/22/2015 Gr. Beta 0.023 +/- 0.004 0.018 +/- 0.004 0.020 +/- 0.003 Pass S-3216,3217 6/24/2015 K-40 10.38 +/- 0.51 10.51 +/- 0.53 10.45 +/- 0.37 Pass S-3216,3217 6/24/2015 Be-7 3.65 +/- 0.24 3.38 +/- 0.27 3.52 +/- 0.18 Pass VE-3300,3301 6/24/2015 Be-7 0.78 +/- 0.15 0.83 +/- 0.23 0.81 +/- 0.14 Pass VE-3300,3301 6/24/2015 K-40 29.12 +/- 0.62 29.36 +/- 0.64 29.24 +/- 0.45 Pass AP-062915 6/29/2015 Gr. Beta 0.023 +/- 0.005 0.023 +/- 0.005 0.023 +/- 0.003 Pass WW-3632,3633 6/30/2015 H-3 5,169 +/- 225 5,058 +/- 223 5,114+/-158 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Lab Code AP-3822, 3823 AP-3969, 3970 WW-3632, 3633 W-4368, 4369 W-4368, 4369 DW-60138, 60139 DW-60138, 60139 WW-4158, 4159 Date 7/1/2015 7/1/2015 7/6/2015 7/6/2015 7/6/2015 7/7/2015 7/7/2015 7/9/2015 Ml-2902, 2903 7/10/2015 SG-3533, 3534 7/10/2015 DW-60150, 60151 7/10/2015 DW-60150, 60151 7/10/2015 VE-3716, 3717 Ml-3759, 3760 Ml-3759, 3760 AP-072115 VE-4053, 4054 VE-4053, 4054 AP-4200, 4201 AP-4200, 4201 W-4137, 4138 XWW-4431, 4432 SG-4305, 4306 AP-081015 AP-081115 VE-4452, 4453 AP-081715 7/14/2015 7/15/2015 7/15/2015 7/21/2015 7/21/2015 7/21/2015 7/29/2015 7/29/2015 7/31/2015 8/5/2015 8/6/2015 8/10/2015 8/11/2015 8/11/2015 8/17/2015 DW-60195, 60196 8/17/2015 DW-60195, 60196 8/17/2015 DW-60198, 60199 8/17/2015 VE-4578, 4579 8/18/2015 SW-4662, 4663 DW-60212, 60213 LW-4788, 4789 AP-083115 AP-4875, 4876 VE-5083, 5084 VE-5083, 5084 VE-5167, 5168 VE-5167, 5168 BS-5188, 5189 F-5419, 5420 DW-60238, 60239 DW-60238, 60239 AP-092215A/B WW-5398, 5399 AP-6007, 6008 8/25/2015 8/25/2015 8/27/2015 8/31/2015 9/3/2015 9/14/2015 9/14/2015 9/16/2015 9/16/2015 9/16/2015 9/17/2015 9/18/2015 9/18/2015 9/22/2015 9/22/2015 9/28/2015 Analysis Be-7 Be-7 H-3 Gr. Alpha Gr. Beta Ra-226 Ra-228 H-3 K-40 Gr. Alpha Ra-226 Ra-228 K-40 K-40 Sr-90 Gr. Beta Be-7 K-40 Be-7 K-40 Ra-226 H-3 Ra-228 Gr. Beta Gr. Beta K-40 Gr. Beta Ra-226 Ra-228

' Gr.Alpha K-40 H-3 Ra-226 Gr. Beta Gr. Beta Be-7 Be-7 K-40 Be-7 K-40 K-40 K-40 Ra-226 Ra-228 Gr. Beta H-3 Be-7 Concentration (pCi/L}

3 First Result 0.075 +/- 0.011 0.063 +/- 0.008 5,169 +/- 225 26.70 +/-4.00 34.62 +/- 2.10 0.07 +/- 0.04 1.04 +/- 0.41 138.8 +/- 82.4 1271 +/- 118 238.0 +/- 8.2 1.53 +/-0.16 2.68 +/- 0.68 3.85 +/- 0.33 1819 +/- 127 1.00 +/- 0.36 0.022 +/- 0.004 0.52 +/- 0.15 8.00 +/- 0.42 1.06+/-0.12 5.03 +/- 0.24 0.58 +/- 0.13 4,773 +/-213 10.34 +/- 0.58 0.038 +/- 0.005 0.024 +/- 0.004 3.77 +/- 0.29 0.030 +/- 0.005 0.39 +/- 0.10 1.43 +/- 0.51 2.93 +/- 0.94 4.14 +/- 0.25 351.3 +/- 89.8 0.09 +/- 0.07 0.97 +/- 0.51 0.032 +/- 0.005 0.294 +/- 0.125 0.47 +/- 0.23 6.20 +/- 0.51 0.40 +/- 0.11 3.56 +/- 0.27 9.69 +/- 0.51 3.48 +/- 0.47 1.93 +/- 0.23 4.44 +/- 0.78 0.021 +/- 0.004 1,857 +/- 145 0.08 +/- 0.01 A5-3 Second Result 0.068 +/- 0.012 0.064 +/- 0.010 5,058 +/- 223 24.10 +/- 3.90 33.30 +/- 2.02 0.11 +/- 0.05 1.15+/-0.47 174.0 +/- 84.1 1308 +/- 115 249.5 +/- 8.5 1.49+/-0.12 1.89 +/- 0.62 3.71 +/- 0.31 1764+/-140 0.61 +/- 0.32 0.027 +/- 0.004 0.49 +/- 0.11 7.61 +/- 0.31 0.96 +/- 0.11 4.96 +/- 0.23 0.45 +/- 0.14 4,915 +/- 216 11.46 +/- 0.62 0.039 +/- 0.005 0.020 +/- 0.004 3.78 +/- 0.26 0.030 +/- 0.005 0.37 +/- 0.10 1.97 +/- 0.61 2.11 +/- 0.96 4.32 +/- 0.24 415.6 +/- 92.8 0.10 +/- 0.08 1.68 +/- 0.59 0.031 +/- 0.005 0.202 +/- 0.109 0.56 +/- 0.19 6.36 +/- 0.50 0.41+/-0.10 3.91 +/- 0.24 10.51 +/- 0.52 3.49 +/- 0.56 2.31 +/- 0.26 5.61 +/- 0.84 0.025 +/- 0.004 1,846+/-144 0.08 +/- 0:01 Averaged Result 0.072 +/- 0.008 0.063 +/- 0.006 5,114+/-159 25.40 +/- 2.79 33.96 +/- 1.46 0.09 +/- 0.03 1.10 +/- 0.31 156.4 +/- 58.9 1289 +/- 82 243.8 +/- 5.9 1.51+/-0.10 2.29 +/- 0.46 3.78 +/- 0.23 1791 +/- 94 0.80 +/- 0.24 0.024 +/- 0.003 0.50 +/- 0.09 7.81 +/- 0.26 1.01 +/- 0.08 4.99 +/- 0.16 0.52 +/- 0.10 I

4,844 +/- 152 10.90 +/- 0.42 0.039 0.004 0.022 0.003 3.77 +/- 0.20 0.030 +/- 0.003 0.38 +/- 0.07 1.70 +/-0.40 2.52 +/- 0.67 4.23 +/- 0.17 383.4 +/- 64.6 0.10 +/- 0.05 1.32 +/- 0.39 0.031 +/- 0.003 0.248 +/- 0.083 0.52 +/- 0.15 6.28 +/- 0.36 0.41 +/- 0.07 3.74 +/- 0.18 10.10 +/- 0.36 3.49 +/- 0.36 2.12 +/- 0.17 5.03 +/- 0.57 0.023 +/- 0.00 1,852 +/- 102 0.08 +/- 0.01 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XW-7490, 7491 9/29/2015 Ni-63 2,332 +/- 233 2,108+/-211 2,220+/-157 Pass WW-5377, 5378 9/30/2015 H-3 220.0 +/- 84.6 197.0 +/- 83.5 208.5 +/- 59.4 Pass AP-6028, 6029 9/30/2015 Be-7 0.073 +/- 0.009 0.083 +/- 0.012 0.078 +/- 0.007 Pass G-5461,2 10/1/2015 Be-7 2.02 +/- 0.32 1.98 +/- 0.25 2.00 +/- 0.20 Pass G-5461,2 10/1/2015 K-40 8.77 +/-0.66 9.31 +/- 0.59 9.04 +/- 0.44 Pass S0-5482, 5483 10/1/2015 Ac-228 0.76 +/- 0.12 0.74 +/- 0.30 0.75 +/- 0.16 Pass S0-5482, 5483 10/1/2015 Bi-214 0.53 +/- 0.04 0.52 +/- 0.04 0.52 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Cs-137 0.12 +/- 0.03 0.12 +/- 0.03 0.12 +/- 0.02 Pass S0-5482, 5483 10/1/2015 K-40 2.17 +/-0.73 2.10+/-0.72 2.13 +/- 0.51 Pass S0-5482, 5483 10/1/2015 Pb-214 0.57 +/- 0.04 0.55 +/- 0.04 0.56 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Ra-226 1.45 +/- 0.27 1.46 +/- 0.30 1.45 +/- 0.20 Pass S0-5482, 5483 10/1/2015 Tl-208 0.24 +/- 0.03 0.25 +/- 0.03 0.24 +/- 0.02 Pass WW-5524, 5525 10/5/2015 H-3 1,192+/-123 1,318 +/- 127 1,255 +/- 89 Pass AP-5881, 5882 10/5/2015 Be-7 0.078 +/- 0.008 0.085 +/- 0.011 0.082 +/- 0.007 Pass AP-5881, 5882 10/5/2015 K-40 0.009 +/- 0.004 0.010 +/- 0.006 0.010 +/- 0.004 Pass SG-6400,1 10/5/2015 Gr. Alpha 19.09 +/- 3.14 19.45 +/- 3.25 19.27 +/- 2.26 Pass SG-6400,1 10/5/2015 Gr. Beta 31.36 +/- 2.08 29.80 +/- 2.13 30.58 +/- 1.49 Pass VE-5923, 5924 10/12/2015 K-40 4.29 +/- 0.29 4.13 +/- 0.33 4.21 +/- 0.22 Pass SS-5818, 5819.

10/14/2015 Ac-228 0.20 +/- 0.06 0.24 +/- 0.06 0.22 +/- 0.04 Pass SS-5818, 5819 10/14/2015 Cs-137 0.03 +/- 0.02 0.02 +/- 0.01 0.03 +/- 0.01 Pass SS-5818, 5819 10/14/2015 Gr. Beta 8.10 +/- 0.87 8.08 +/- 0.96 8.09 +/- 0.65 Pass SS-5818, 5819 10/14/2015 Pb-212 0.19 +/- 0.03 0.17 +/- 0.02 0.18 +/- 0.02 Pass SS-5818, 5819 10/14/2015 Ra-226 0.47 +/- 0.24 0.45 +/- 0.19 0.46 +/- 0.15 Pass SS-5818, 5819 10/14/2015 Tl-208 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Pass DW-60251, 60252 10/15/2015 Ra-226 0.56 +/- 0.12 0.50 +/- 0.08 0.53 +/- 0.07 Pass DW-60251, 60252 10/15/2015 Ra-228 0.79 +/- 0.48 1.16 +/- 0.59 0.98 +/- 0.38 Pass S0-5944, 5945 10/21/2015 Ac-228 1.08 +/- 0.15 1.14+/-0.15 1.11 +/- 0.10 Pass S0-5944, 5945 10/21/2015 Bi-214 0.89 +/- 0.08 0.82 +/- 0.06 0.85 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Cs-137 0.06 +/- 0.02 0.08 +/- 0.03 0.07 +/- 0.02 Pass S0-5944, 5945 10/21/2015 Pb-212 1.06 +/- 0.06 0.99 +/- 0.05 1.03 +/- 0.04 Pass S0-5944, 5945 10/21/2015 Pb-214 1.00 +/- 0.09 0.89 +/- 0.06 0.95 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Ra-226 2.13 +/- 0.43 2.16 +/- 0.37 2.14 +/- 0.28 Pass S0-5944, 5945 10/21/2015 Tl-208 0.36 +/- 0.04 0.34 +/- 0.04 0.35 +/- 0.03 Pass S-6175, 6176 10/23/2015 K-40 16.86 +/- 1.92 14.28+/-1.66 15.57 +/- 1.27 Pass XWW-6196, 6197 10/26/2015 H-3 2,856 +/- 170 2,815 +/- 169 2,836 +/- 120 Pass S0-6259, 6260 10/28/2015 Ac-228 0.60 +/- 0.10 0.53 +/- 0.08 0.57 +/- 0.07 Pass S0-6259, 6260 10/28/2015 Bi-214 0.40 +/- 0.06 0.50 +/- 0.05 0.45 +/- 0.04 Pass S0-6259, 6260 10/28/2015 Cs-137 0.17 +/- 0.03 0.19 +/- 0.03 0.18 +/- 0.02 Pass S0-6259, 6260 10/28/2015 Gr. Beta 21.6 +/- 1.1 23.36 +/- 1.21 22.48 +/- 0.82 Pass S0-6259, 6260 10/28/2015 Pb-212 0.53 +/- 0.04 0.49 +/- 0.04 0.51 +/- 0.03 Pass S0-6259, 6260 10/28/2015 Tl-208 0.16 +/- 0.03 0.19 +/- 0.04 0.18 +/- 0.02 Pass A5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 Ml-6484, 6485 11/11/2015 K-40 1,384 +/- 82 1,432 +/- 89 1,408 +/- 60 S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 +/- 0.03 0.17 +/- 0.02 S0-6841, 6842 11/24/2015 K-40 13.62 +/- 0.76 13.67 +/- 0.69 13.64 +/- 0.51 WW-6978, 6979 11/30/2015 H-3 569.0 +/- 97.7 480.3 +/- 93.9 524.7 +/- 67.8 SW-6936, 6937 12/10/2015 H-3 151.9 +/- 80.0 176.2 +/- 81.2 164.0 +/- 57.0 SW-7017, 7018 12/10/2015 H-3 584.3 +/- 98.7 451.6 +/- 93.9 518.0 +/- 68.1 LW-7020, 7021 12/10/2015 H-3 236.9 +/- 84.2 285.6 +/- 86.5 261.2 +/- 60.3 AP-7351, 7352 12/29/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 AP-7414, 7415 12/30/2015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

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

A5-5

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 2/1/2015 Ni-63 341 +/- 18 448 314 - 582 Pass MAS0-975 2/1/2015 Sr-90 523+/-12 653 457 - 849 Pass MAS0-975 2/1/2015 Tc-99 614 +/- 12 867 607 -1,127 Pass MAS0-975 2/1/2015 Cs-134 533 +/-6 678 475 - 881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 2/1/2015 Co-57 0.5 +/- 1.0 0.0 NA c Pass MAS0-975 2/1/2015 Co-60 741 +/- 8 817 572 -1,062 Pass MAS0-975 2/1/2015 Mn-54 1,153 +/- 9 1,198 839 -1,557 Pass MAS0-975 2/1/2015 Zn-65 892+/-18 1064 745 - 1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 23.5 16.5 - 30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4 - 24.8 Pass MAW-969 d 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 -38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 - 732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82 -8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 0.00 NA c Pass MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 18.3 12.8 - 23.8 Pass MAW-969 2/1/2015 Tc-99

. 3.40 +/- 0.60 3.18 2.23 - 4.13 Pass MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NA" Pass MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 2/1/2015 U-233/234 0.1,so +/- o.o4o 0.148 0.104 -0.192 Pass MAW-969 2/1/2015 U-238 0.84 +/- 0.09 0.97 0.68 - 1.26 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 2/1/2015 Gr.Alpha 0.66 +/- 0.05 1.07 0.32 - 1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAW-947 2/1/2015 1-129 1.26+/-0.12 1.49 1.04-1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 - 0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA c Pass MAAP-978 1 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06 - 1.96 Fail MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 2/1/2015 Mn-54 1.11 +/- 0.08 1.02 0.71 - 1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 0.83 0.58 -1.08 Pass MAAP-978 2/1/2015 Pu-238

-0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059 - 0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 -0.129 Pass A6-1

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 - 61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/-0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr.Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 - 9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 - 7.22

.Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA c Pass MAAP-978 2/1/2015 Pu-238

-0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059 - 0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 - 0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 - 0.129 Pass MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 -61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/-0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr.Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/-0.13 7.32

.5.12 -9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 - 7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- O.Q7 0.00 NA c Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA c Pass MAS0-4903 8/1/2015 Ni-63 556+/-18 682 477 -887 Pass MAS0-4903 9 8/1/2015 Sr-90 231 +/-7 425 298 -553 Fail MAS0-4903 9 8/1/2015 Sr-90 352+/-10 425 298 -553 Pass MAS0-4903 h 8/1/2015 Tc-99 411+/-11 631 442 -820 Fail MAS0-4903 8/1/2015 Cs-134 833 +/- 10 1,010 707 -1,313 Pass MAS0-4903 8/1/2015 Cs-137 808+/-11 809.00 566 -1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052+/-10 1,180 826 -1,534 Pass MAS0-4903 8/1/2015 Co-60 2 +/-2 1.3 NAe Pass MAS0-4903 8/1/2015 Mn-54 1,331+/-13 1,340 938 -1,742 Pass MAS0-4903 8/1/2015 Zn-65 686+/-15 662 463 -861 Pass A6-2

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 - 30.0 Pass MAW-5007 8/1/2015 Cs-137

-0.4 +/- 0.1 0.0 NAC Pass MAW-5007 8/1/2015 Co-57 21.8 +/-0.4 20.8 14.6 -27.0 Pass MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12.0 -22.2 Pass MAW-5007 8/1/2015 H-3 227.5 +/-8.9 216.0 151.0 - 281.0 Pass MAW-5007; 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 -17.0 Fail MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 -20.3 Pass MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.6 6.0 -11.1 Pass MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7-18.1 Pass MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 5.03 -9.35 Pass MAW-5007 8/1/2015 Sr-90 4.80 +/-0.50 4.80 3.36 -6.24 Pass MAW-5007 8/1/2015 Gr.Alpha 0.41 +/- 0.04 0.43 0.13 - 0.73 Pass MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 -5.28 Pass MAW-5007 8/1/2015 1-129 1.42 +/- 0.13 1.49 1.04 -1.94' Pass MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79 -5.17 Pass*

MAAP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 0.74 -1.37 Pass MAAP-4907 8/1/2015 Gr.Alpha 0.30 +/- 0.04 0.90 0.27 -1.53 Pass MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78 -2.34 Pass MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 4.06 - 7.54 Pass MAVE-4901 8/1/2015 Cs-137

-0.02 +/- 0.06 0.00 NA c Pass MAVE-4901 8/1/2015 Co-57 7.74 +/- 0.18 6.62 4.63 -8.61 Pass MAVE-4901 8/1/2015 Co-60 4.84 +/- 0.15 4.56 3.19 - 5.93 Pass MAVE-4901 8/1/2015 Mn-54 8.25 +/- 0.25 7.68 5.38 - 9.98 Pass MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 3.82 - 7.10 Pass

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

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

0 MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

d Lab result was 27.84. Data entry error resulted in a non-acceptable result.

Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.

1 Lab result was 1.58. Data entry er~or resulted in a non-acceptable result.

9 The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

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

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

A6-3

TABLE A-7. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates {ERA)a.

Concentration {pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Resultc Resultd Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/-2.2 49.8 30.7 - 67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61.2 -98.8 Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/- 34.7 909.0 578.0 - 1, 130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312+/-12 1,170 879 -1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/-48.2 836.0 259.0 - 1630.0 Pass ERAP-1091 3/16/2015 Mn-54

<2.7

<50

. 0.0 - 50.0 Pass ERAP-1091 3/16/2015 Pu-238.

51.0 +/- 3.9 52.1 35.7 -68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3+/-1.3 40.3 29.20 - 52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 -145.0 Pass ERAP-1091 3/16/2015 U-233/234 29.0+/-1.2 34.3 21.3 - 51.7 Pass ERAP-1091 3/16/2015 U-238 31.0+/-1.1 34.0 22.0 -47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 - 1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/- 0.7 62.2 20.8 - 96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.!3 +/- 0.8 58.4 36.9 - 85.1 Pass ERS0-1098 3/16/2015 Am-241 1571.8 +/- 209.6 1,500 878 -1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/-140.4 1,250 802 -1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/-455.7 1,780 474 -~,620 Pass ERS0-1098 3/16/2015 Bi-214 3466.9 +/- 86.9 4,430 2,670 - 6,380 Pass ERS0-1098 3/16/2015 Co-60 1779.8 +/-41.0 1,880 1,270 - 2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390*

4,180 -7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/-41.9 1,490 1,140 -1,920.

Pass ERS0-1098 3/16/2015 K-40 10,597 +/- 380 10,700 7,810 - 14,400 Pass ERS0-1098 3/16/2015 Mn-54

<62.2

< 1000 0.0 -1,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/-41 1,230 806 -1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/-93 4,530 2,640 - 6, 760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128,8 998.0 600.0 - 1,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1,185+/-140 1,210 791 -1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724+/-125 1,940 740 -3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/-948 3,890 1,230 - 7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/-226 3,920 2,400 - 5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/-232 3,890 2,410 - 4,930 Pass ERSOc1098 3/16/2015 Zn-65 7,362+/-145 7,130 5,680 - 9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4+/-11.5 119.0 42.2 -184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/- 4.8 158.0 90.5 -234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900 -14,700 Pass.

ERVE-1100 3/16/2015 Am-241 4,537 +/-266 4,340 2,650 - 5,770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 -2,120 Pass A7-1

TABLEA-7. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (f:!Ci/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Resultd Limits Acceptance ERVE-1100 ° 3/16/2015 Co-60 1,030 +/-29 1,540 1,060 - 2,150 Fail ERVE-1100 1 3/16/2015 Co-60 1,684 +/-48 1,540 1,060 -2,150 Pass ERVE-1100 ° 3/16/2015 Cs-134 1,615+/-27 2,650 1,700 - 3,440 Fail ERVE-1100 1 3/16/2015 Cs-134 2,554 +/-49 2,650 1,700 - 3,440 Pass ERVE-1100 ° 3/16/2015 Cs-137 1,248 +/- 29 1,810 1,310 -2,520 Fail ERVE-1100 1 3/16/2015 Cs-137 2,078 +/-68 1,810 1,310 - 2,520 Pass ERVE-1100 ° 3/16/2015 K-40 22,037 +/-463 30,900 22,300 - 43,400 Fail ERVE-1100 1 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 - 43,400 Pass ERVE-1100 ° 3/16/2015 Mn-54

<13.8

<300 0.0 - 300.0 Pass ERVE-1100 1 3/16/2015 Mn-54

<24.4

<300 0.0 -300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/-.232 3,680 2,190 -5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/- 240 4,180 2,570 - 5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/-326 6,590 3,760 - 8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653 +/- 153 3,150 2,070 - 4,050 Pass ERVE-1100 3/16/2015 U-238 2,717 +/- 163 3,130 2,090 - 3,980 Pass ERVE-1100 ° 3/16/2015 Zn-65

<94.6 1,090 786 -1,530 Fail ERVE-1100 1 3/16/2015 Zn-65 1,306 +/-75 1,090 786 -1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/-4.0 46.0 31.0 -61.7 Pass ERW-1103 3/16/2015 Co-60 1,217 +/-17 1,250 1,090 - 1,460 Pass ERW-1103 3/16/2015 Cs-134 1,121 +/- 18 1,260 925 -1,450 Pass ERW-1103 3/16/2015 Cs-137 1,332 +/- 31 1,360 1,150 -1,630 Pass ERW-1103 3/16/2015 Mn-54

<3.7

<100 0.00 - 100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5+/-1.6 72.4 53.6 - 90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/-7.8 184.0 143.0 - 232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/-4.9 97.7 66.6 -108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 - 79.7 Pass ERW-t103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7 - 75.2 Pass ERW-1103 3/16/2015 Zn-65 1,191 +/- 136 1,180 984 -1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149+/-144 1,070 638 -1,450 Pass ERW-1103 3/16/2015 Sr-90 860.0 +/-37.0 912.0 594.0 - 1,210.0 Pass

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

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

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.

Technician error weighing sample caused submitted gamma results to be understated and outside the control limits.(low) 1 The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above).

9 The results of reanalysis were outside the control limits (low).

h Sample ERW-3742 was ordered from ERA to determine why ERW-1103 results for Pu-239 were outside the acceptable range.

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

A?-2

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Appendix B 2015 REMP Data Summary Reports

Environmental Radiological Monitoring *Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2015 Mean for All Mean for Indicator Location with Hi~ hest Annual Mean Mean for Control Pathway Type and Locations Locations Mean Locations Sampled Total Number Lower Limit of Location#

of Analyses Detection (LLD)

Detected/Collected Detected/Collected Distance &

Detected/Collected Detected/Collected Units Performed Direction Range Range Range Range 0.063 0.062 6

0.072 0.072 Air Be-7 N/A 28/28 24/24 11.1 4/4 414 pCi/m3 28 0.046 - 0.088 0.046 - 0.087 SSW 0.057 - 0.088 0.057 - 0.088

\\

<LLD

<LLD Air Co-58 N/A 0 /28 0/24 0/4 pCi/m3 28

<LLD

<LLD Air Co-60 N/A 0/28 0 /24 014 pCi/m3 28

<LLD

<LLD Air Cs-134 0.037 0 / 28 0 / 24 014 pCi/m3 28

<LLD

<LLD Air Cs-137 0.045 0 /28 0 /24 014 pCi/m3 28 0.027 0.027 6

0.028 0.028 Air Gross Beta 0.0075 361/361 309/309 11.1 52/52 52/52 pCi/m3 361 0.006 - 0.065 0.006 - 0.065 SSW 0.008-0.064 0.008-0.064

<LLD

<LLD Air 1-131 0.05 0/361 0/309 0/52 pCi/m3 361 B-1

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2015 Mean for All Mean for Indicator Location with Hii hest Annual Mean Mean for Control Pathway Type and Locations Locations Mean Locations Sampled Total Number Lower Limit of Location#

of Analyses Detection (LLD)

Detected/Collected Detected/Collected Distance &

Detected/Collected Detected/Collected Units Performed Direction Range Range Ranae Range 1148.7 1007.5 32 1289.8 1289.8 Fish K-40 N/A 12/14 6/6 15.8 6/8 6/8 pCi/kg wet 14 585 -1889 585 -1202 WSW 786 -1889 786 -1889

<LLD

<LLD Fish Mn-54 94 0/14 016 0/8 pCi/kg wet 14

<LLD

<LLD Fish Fe-59 195 0/14 0/6 0/8 pCi/kg wet 14

<LLD

<LLD Fish Co-58 97 0/14 016 0/8 pCi/kg wet 14

<LLD

<LLD Fish Co-60 97 0/14 016 0/8 pCi/kg wet 14

<LLD

<LLD Fish Zn-65 195 0/14 016 0/8 pCi/kg wet 14

<LLD

<LLD Fish Cs-134 97 0/14 0/6 0/8 pCi/kg wet 14 B-2

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2015 Mean for All Mean for Indicator Location with Hi~ hest Annual Mean Mean for Control Pathway Type and Locations Locations Mean Locations Sampled Total Number Lower Limit of Location#

of Analyses Detection (LLD)

Detected/Collected Detected/Collected Distance &

Detected/Collected Detected/Collected Units Performed Range Range Direction Ranae Range

<LLD

<LLD Fish Cs-137 112 0/14 016 0/8 pCi/kg wet 14 Broad leaf 469.0 469.0 70 637.4 637.4 Vegetation Be-7 N/A 45/69 45/57 17.1 10/12 10/12 pCi/kg wet 69 150 - 1169 150 - 1169 SSW 237-1169 237 -1169 Broadleaf 5210.0 4954.4 70 6424.5 6424.5 Vegetation K-40 N/A 69/69 57/57 17.1 12/12 12/12 pCi/kg wet 69 2793-12725 2793-9638 SSW 4498-12725 4498 -12725 Broadleaf

<LLD

<LLD Vegetation Co-58 N/A 0/69 0/57 0/12 pCi/kg wet 69 Broad leaf

<LLD

<LLD Vegetation Co-60 N/A 0/69 0/57 0/12 pCi/kg wet 69 Broad leaf

<LLD

<LLD Vegetation 1-131 45 0/69 0/57 0/12 pCi/kg wet 69 Broad leaf

<LLD

<LLD Vegetation Cs-134 45 0/69 0/57 0/12 pCi/kg wet 69 B-3

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2015 Mean for All Mean for Indicator Location with Hi( hest Annual Mean Mean for Control Pathway Type and Locations Locations Mean Locations Sampled Total Number Lower Limit of Location#

of Analyses Detection (LLD)

Detected/Collected Detected/Collected Distance &

Detected/Collected Detected/Collected Units Performed Direction Range Range Ranae Range Broad leaf

<LLD

<LLD Cs-137 Vegetation 60 0169 0/57 0/12 pCi/kg wet 69 1393.3 1764.3 18 1764.3 1320.7 Milk K-40 N/A 46/46 27127 2.6 8/8 19/19 pCi/L 46 717 -1923 1196 -1923 E

1350 -1923 717-1445

<LLD

<LLD Milk 1-131 0.8 0/46 0127 0/19 pCi/L 46

<LLD

<LLD Milk Cs-134 11 0/46 0127 0/19 pCi/L 46

<LLD

<LLD Milk Cs-137 13 0/46 0/27 0/19 pCi/L 46

<LLD

<LLD Milk Ba-140 45 0/46 0/27 0/19 pCi/L 46

<LLD

<LLD Milk La-140 11 0/46 0/27 0/19 pCi/L 46 B-4

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Povver Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2015 Mean for All Mean for Indicator Location with Hi~ hest Annual Mean Mean for Control Pathway Type and Locations Locations Mean Locations Sampled Total Number Lower Limit of Location#

of Analyses Detection (LLD)

Detected/Collected Detected/Collected Distance &

Detected/Collected Detected/Collected Units Performed Direction Range Range Range Range 6502.0 6502.0 66 6849.7 NA Sediment K-40 N/A 5/5 5/5 1.4 3/3 NA pCi/kg wet 5

2268-9693 2268-9693 NE 6423-7272 NA

<LLD

<LLD NA Sediment Co-58 50 0/5 0/5 NA pCi/kg wet 5

NA

<LLD

<LLD NA Sediment Co-60 40 0/5 0/5 NA pCi/kg wet 5

NA

<LLD

<LLD NA Sediment Cs-134 112 0/5 0/5 NA pCi/kg wet 5

NA

<LLD

<LLD NA Sediment Cs-137 135 0/5 0/5 NA pCi/kg wet 5

NA 12.0 12.0 33 16.3 11.4 TLD (E)

Direct 1.0 116/116 108/108 4.7 4/4 8/8 mR/91 days 116 5.9 -19.0 5.9 -19.0 s

12.1 -19.0 8.0 -13.0 12.9 12.9 29 17.0 13.1 TLD (Q)

Direct 1.0 116/116 108/108 4.5 4/4 8/8 mR/91 days 116 8.0 -19.8 8.0 - 19.8 SSE 15.6-18.5 12.0 -14.1 B-5

Environmental Radiological Monitoring Program A.nnual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2015 Mean for All Mean for Indicator Location with Hi! hest Annual Mean Mean for Control Pathway Type and Locations Locations Mean Locations Sampled Total Number Lower Limit of Location#

of Analyses Detection (LLD)

Detected/Collected Detected/Collected Distance &

Detected/Collected Detected/Collected Units Performed Range Range Direction Range Range 57.2 57.1 33 71.2 59.1 TLD Direct 1.0 29/29 27/27 4.7 1/1 2/2 mR/365 days 29 48.4-71.2 48.4-71.2.

s 71.2-71.2 54.8-63.4 1.5 1.5 28 1.9 1.5 Water Gross Beta 3.0 47/54 32/42 20.6 6/6 11/12 pCi/L 54 0.9-2.7 0.9-2.7 ENE 1.0 - 2.6 0.9-2.6

<LLD

<LLD Water H-3 1500 0/18 0/14 0/4 pCi/L 18

<LLD

<LLD Water Mn-54 11 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water Fe-59 I

22 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water Co-58 11 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water Co-60 11 0/54 0/42 0/12 pCi/L 54 B-6

Environmental Radiological Monitoring Program Annual Summary Perry Nuclear Power Plant Docket Number 50-440/50-441 Lake County, Ohio Reporting Period: 2015 Mean for All Mean for Indicator Location with Hi~ hest Annual Mean Mean for Control Pathway Type and Locations Locations Mean Locations Sampled Total Number Lower Limit of Location#

of Analyses Detection (LLD)

Detected/Collected Detected/Collected Distance &

Detected/Collected Detected/Collected Units Performed Direction Range Range RanQe Range

<LLD

<LLD Water Zn-65 22 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water Zr-95 22 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water Nb-95 11 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water Cs-134 11 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water Cs-137 13 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water Ba-140 45 0/54 0/42 0/12 pCi/L 54

<LLD

<LLD Water La-140 11 0/54 0/42 0/12 pCi/L 54

This value is the LLD that is met by the vendor and is lower than required by the ODCM B-7

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Appendix C 2015 REMP Detailed Data Report

FE NOC' RrstEnergy Nuclear Operating cbmpany David B. Hamilton Vice President April 29, 2016 L-16-151 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440 Annual Environmental and Effluent Release Report Perry Nuclear Power Plant P.O. Box 97 10 Center Road.

Perry, Ohio 44081 440-280-5382 1 OCFR50.36(a)

Enclosed is the Annual Environmental and Effluent Release Report for the Perry Nuclear Power Plant (PNPP) for the period of January 1, 2015 through December 31, 2015. This document includes the radiological environmental operating report, radioactive effluent release report, and the non-radiological environmental operating report which satisfies the requirements of the PNPP Technical Specifications (TS), the PNPP Offsite Dose Calculation Manual (ODCM), and the Environmental Protection Plan, Appendix 8 of the PNPP Operating License. Also enclosed are two corrected pages.to 2014 Annual Environmental and Effluent Release Report.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas Veitch, Chemistry Manager at (440) 280-5188.

Sincerely, David Hamilton Vice President

Enclosures:

A PNPP 2015 Annual Environmental and Effluent Release Report 8

Corrections to the 2014 PNPP Annual Environmental and Effluent Release Report cc:

NRC Project Manager NRC Resident Inspector NRC Region Ill

Enclosure A L-16-151 PNPP 2015 Annual Environmental and Effluent Release Report

2015 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT for the Perry Nuclear Power Plant PREPARED BY: