ML21120A105

Submittal of Annual Radioactive Environmental Operating Report for 2020

ML21120A105
Person / Time
Site:	Oyster Creek
Issue date:	04/30/2021
From:	Sterdis A Holtec
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML21120A105 (147)

Text

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 Technical Specification 6.9.1.b 10 CFR 50 Appendix I April 30, 2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 Docket No. 50-219

Subject:

Annual Radioactive Environmental Operating Report for 2020 Enclosed with this cover letter is the Annual Radioactive Environmental Operating Report for the calendar year 2020 for the Oyster Creek Nuclear Generating Station. This submittal is made in accordance with Oyster Creek Nuclear Generating Station Technical Specification 6.9.1.b, Annual Radiological Environmental Operating Report.

There are no regulatory commitments in this letter.

Should you have any questions or require further information, please contact Kevin Wolf, Radiation Protection and Chemistry Manager, at (609) 971-4051.

Respectfully, Digitally signed by Andrea Sterdis Andrea DN: cn=Andrea Sterdis, c=US, o=Holtec Decommissioning International, ou=HDI, Sterdis email=a.sterdis@holtec.com Date: 2021.04.30 10:41:44 -04'00' Andrea L. Sterdis Vice President, Regulatory and Environmental Affairs Holtec Decommissioning International, LLC cc:

USNRC Regional Administrator, Region I USNRC Project Manager, NMSS - Oyster Creek Nuclear Generating Station USNRC Region I, Lead Inspector - Oyster Creek Nuclear Generating Station Assistant Commissioner, Air Quality, Energy and Sustainability, NJ DEP Principal Engineer, American Nuclear Insurers Assistant Director Radiation Protection Element, NJ Bureau of Nuclear Engineering HDI-21-OC-035

Docket No: 50-219 OYSTER CREEK GENERATING STATION UNIT 1 Annual Radiological Environmental Operating Report 1 January through 31 December 2020 Prepared By Teledyne Brown Engineering Environmental Services IIIII HOLTEC DECOMMISSIONING INTERNATIONAL Oyster Creek Generating Station Forked River, NJ 08731 April 2021

Intentionally left blank Table of Contents Preface ................................................................................................................................ 1 I. Summary and Conclusions ............................................................................................ 11 II. Introduction ................................................................................................................... 13 A. Objectives of the REMP .................................................................................... 13 B. Implementation of the Objectives ...................................................................... 13 C. Discussion ......................................................................................................... 14 III. Program Description .................................................................................................... 16 A. Sample Collection.............................................................................................. 16 B. Sample Analysis ................................................................................................ 17 C. Data Interpretation............................................................................................. 18 D. Program Exceptions .......................................................................................... 19 E. Program Changes ............................................................................................. 21 IV. Results and Discussion ............................................................................................... 22 A. Aquatic Environment ......................................................................................... 22 B. Atmospheric Environment ................................................................................. 25 C. Ambient Gamma Radiation ............................................................................... 28 D. Land Use Survey............................................................................................... 29 E. Summary of Results - Inter-laboratory Comparison Program .......................... 30 V. References ................................................................................................................... 32 VI. Errata ........................................................................................................................... 32 i

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Oyster Creek Generating Station, 2020 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Table B-1 Location Designation and Identification System for the Oyster Creek Generating Station Table B-2 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Oyster Creek Generating Station, 2020 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Oyster Creek Generating Station, 2020 Figures Figure B-1 Locations of REMP Stations within a 1-mile radius of the Oyster Creek Generating Station, 2020 Figure B-2 Locations of REMP Stations within a 1 to 5-mile radius of the Oyster Creek Generating Station, 2020 Figure B-3 Locations of REMP Stations greater than 5 miles from the Oyster Creek Generating Station, 2020 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-I.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-I.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-II.1 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-II.2 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-II.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-III.1 Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 ii

Table C-III.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-IV.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-IV.2 Concentrations of Gamma Emitters in Clam and Crab Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-VI.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-VI.2 Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-VI.3 Concentrations of Strontium in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-VI.4 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-VII.1 Concentrations of I-131 in Air Iodine Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-VIII.1 Concentrations of Strontium and Gamma Emitters in Vegetation Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table C-IX.1 Quarterly OSLD Results for Oyster Creek Generating Station, 2020 Table C-IX.2 Mean Quarterly OSLD Results for the Site Boundary, Intermediate, Special Interest, and Control Locations for Oyster Creek Generating Station, 2020 Table C-IX.3 Summary of the Ambient Dosimetry Program for Oyster Creek Generating Station, 2020 Figures Figure C-1 Mean Cobalt-60 Concentration in Clams Oyster Creek Generating Station, 1983 - 2020 Figure C-2 Mean Cobalt-60 Concentration in Aquatic Sediment Oyster Creek Generating Station, 1984 - 2020 Figure C-3 Mean Cesium-137 Concentration in Aquatic Sediment Oyster Creek Generating Station, 1984 - 2020 Figure C-4 Mean Weekly Gross Beta Concentrations in Air Particulates Oyster Creek Generating Station, 2008 - 2020 iii

Figure C-5 Mean Monthly Gross Beta Concentrations in Air Particulates Oyster Creek Generating Station, 1984 - 2020 Figure C-6 Mean Quarterly OSLD Gamma Dose Oyster Creek Generating Station, 2020 Appendix D Data Tables - QC Laboratory Tables Table D-I.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity Of Oyster Creek Generating Station, 2020 Table D-I.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table D-II.1 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table D-II.2 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table D-III.1 Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table D-III.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table D-IV.1 Concentrations of Gamma Emitters in Clam Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table D-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Table D-VI.1 Concentrations of Strontium and Gamma Emitters in Vegetation Samples Collected in the Vicinity of Oyster Creek Generating Station, 2020 Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2020 Table E-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2020 Table E-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2020 Table E-4 Interlaboratory Comparison Crosscheck Program, New York Department of Health (ELAP), Environmental, Inc., 2020 Table E-5 DOEs Mixed Analyte Performance Evaluation Program (MAPEP),

Environmental, Inc., 2020 iv

Table E-6 Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) RAD Study, Environmental, Inc., 2020 Appendix F Errata Data Appendix G Annual Radiological Groundwater Protection Program Report (ARGPPR) v

Intentionally left blank Preface The nuclear power industry uses terms and concepts that may be unfamiliar to all readers of this report. This section of the report is intended to help the reader better understand some of these terms and concepts. In this section, we will discuss radiation and exposure pathways. This section is intended only to give a basic understanding of these subjects to hopefully allow the reader to better understand the data provided within the report.

Every nuclear power station is required to submit two reports annually, the Annual Radioactive Effluents Release Report (ARERR) and the Annual Radiological Environmental Operating Report (AREOR). The following information is provided in both reports for Oyster Creek Generating Station.

Understanding Radiation Radiation is simply defined as the process of emitting radiant energy in the form of waves or particles. Radiation can be categorized as ionizing or non-ionizing radiation.

If the radiation has enough energy to displace electrons from an atom it is termed ionizing radiation. Typically you will see a warning sign where there is a potential to be exposed to man-made ionizing radiation. These signs normally have the trefoil symbol on a yellow background.

DANGER RADIOACTIVE AA AA

. MATERIALS Example Radiological warning signs People do not always recognize non-ionizing radiation as a form of radiation, such as light, heat given off from a stove, radiowaves and microwaves. In our report we focus on the ionizing radiation that is produced at a nuclear power plant though it is important to note that ionizing radiation comes from many sources. In fact, the amount of ionizing radiation an average person is exposed to due to operation of a nuclear power plant is a 1

very small fraction of the total ionizing radiation they will be exposed to in their lifetime and will be discussed later.

From this point forward we will only be discussing ionizing radiation but we will just use the term radiation.

Since this report discusses radiation in different forms and different pathways we first need to understand where the radiation comes from that we report. Radiation comes from atoms. So, what are atoms and how does radiation come from atoms?

You may have seen a Periodic Table of the Elements Group>1 2 3 4 5 6 7 8 9 101112131415161718 em The Periodic Table of the Elements 1-

, F?- .1 UJ a " T T T TTT?T n T-$Ei£@"@wmm 88 109 110 . f2:

7 I E Mt Ds Lv TsJ L__anthanides I i 5395 M 61 l l i l " l " l .

60 m WW IIIIIII IIIIIII I This table lists all the elements found on earth. An atom is the smallest part of an element that maintains the characteristics of that element. An atom is made up of three parts, protons, neutrons and electrons.

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The number of protons in an atom determines the element. A hydrogen atom will always have one proton while an oxygen atom will always have eight protons. The protons are clustered with the neutrons at the center of the atom and this is called the nucleus. Orbiting around the nucleus are the relatively small electrons. Neutrons do not have an electrical charge, protons have a positive charge while electrons have a negative charge. In an electrically neutral atom, the negative and positive charges are balanced. Atoms of the same element that have a different number of neutrons in their nucleus are called isotopes.

Isotopes are atoms that have the same number of protons but different number of neutrons. They all have the same chemical properties and many isotopes are nonradioactive or stable while other isotopes may be unstable and are radioactive.

Radioactive isotopes can be called a radionuclide, a radioisotope or simply called a radioactive atom. A radionuclide usually contains an excess amount of energy in the nucleus usually due to a deficit or excess of neutrons in the nucleus.

There are two basic ways radionuclides are produced at a nuclear power plant. The first way is a direct result of the fission process and the radionuclides created through this process are termed fission products. Fission occurs when a very large atom, such as U-235 (Uranium-235) and Pu-239 (Plutonium-239), absorbs a neutron into its nucleus making the atom unstable. In this instance the atom can actually split into smaller atoms, this splitting of the atom is called fission. When fission occurs there is also a large amount of energy released from the atom in the form of heat which is what is used to produce the steam that will spin the turbines to produce electricity at a nuclear power plant.

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The second way a radionuclide is produced at a nuclear power plant is through a process called activation and the radionuclides produced in this method are termed activation products. Water passes through the core where the fission process is occurring. This water is used to both produce the steam to turn the turbines and to cool the reactor. Though the water passing through the core is considered to be very pure water, there is always some other material within the water. This material typically comes from the material used in the plants construction. As the water passes through the core, the material is exposed to the fission process and the radiation within the core can react with the material causing it to become unstable, creating a radionuclide. The atoms in the water itself can become activated and create radionuclides.

Over time, radioactive atoms will reach a stable state and no longer be radioactive. To do this they must release the excess energy. The release of excess energy can be in different forms and is called radioactive decay and the energy released is called radiation. The time it takes for a radionuclide to become stable is measured in units called half-lives. A half-life is the amount of time it takes for half of the original radioactivity to decay. Each radionuclide has a specific half-life. Some half-lives can be very long and are measured in years while others may be very short and are measured in seconds.

Half-life 1000 800 The amount of time it takes for half of the original radioactivity to decay Activity 400 200 1 half-life 2 half-lives 3 half-lives 4 half-lives In this report, you will see radionuclides listed such as K-40 (potassium-40) and Co-60 (cobalt-60). The letter(s) represents the element and the number represents the specific isotope of that element and is the number of protons and neutrons in the 4

nucleus of that radionuclide. You may hear the term naturally occurring radionuclide which refers to radionuclides that naturally occur in nature such as K-40. There are man-made radionuclides such as Co-60 that we are concerned with since these man-made radionuclides result as a by-product when generating electricity at a nuclear power plant. There are other ways man-made radionuclides are produced, such as detonating nuclear weapons, and this is important to note since nuclear weapons testing deposited these man-made radionuclides into the environment and some are still present today. There is a discussion in the AREOR for the radionculides Cs-137, Sr-89 and Sr-90. The reason we only see some of the radionuclides today is due to the fact that some of the radionuclides released into the environment had relatively short half-lives and all the atoms have decayed to a stable state while other radionuclides have relatively long half-lives and will be measurable in the environment for years to come.

Sources of Radiation People are exposed to radiation every day of their lives and have been since the dawn of mankind. Some of this radiation is naturally occurring while some is man-made.

There are many factors that will determine the amount of radiation an individual will be exposed to such as where you live, medical treatments, etc. Below are examples of some of the typical sources of radiation an individual is exposed to in a year.

Sources of Radlatlen Exposure In the U.$.

Cosmic (Space) - 5% Radon and I. ;..

. .  : Theron - 31% Induairial and Terrestnal (Sell) - 3% Dompatiunal lntamal - 5% (0.1%

Consumer - 2%

Nuclear Medicine 12 %

- Natural Sources - 50% - Manmada Sources - 50%

~31a millirem {0.31 rem] ~31a milliram {0.31 rarn]

Sun-Dal'ICRPIDep-Dlt"n. 160W]

Mmkmi"lbm"n"mpmmmmmmg Adapted with permission of the National Council on Radiation Protection and Measurements, http://NCRPonline.org As you can see from the graph, the largest natural source of radiation is due to Radon.

That is because essentially all air contains Radon. Cosmic and Internal make up the 5

next largest natural sources of radiation. Cosmic radiation comes from the sun and stars and there are multiple factors which can impact the amount of cosmic radiation you are exposed to such as the elevation at which you live and the amount of air travel you take a year. The internal natural source of radiation mainly comes from two sources. Technically, all organic material is slightly radioactive due to C-14 (carbon-14),

including humans and the food we eat. C-14 makes up a percentage of the carbon in all organic material. Another contributor to the internal natural source is K-40 (potassium-40). Potassium is present in many of the foods we eat, such as brazil nuts, bananas, carrots and red meat. The smallest natural source listed is terrestrial. Soil and rocks contain radioactive materials such as Radium and Uranium. The amount of terrestrial radiation you are exposed to depends on where you live. The map below shows terrestrial exposure levels across the United States. The radiation released from nuclear power plants is included in the Industrial and Occupational slice and is listed as

<0.1%.

Terrestrial Gamma-Rayr Exposure at 1m above ground auuns ordain: Ui"uhginlmmnhl"hh"lismim Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to radioactive material. The major pathways of concern are those which could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive material released into the environment and how the environment is used. The way radioactive material is transported in the environment includes consideration of physical factors, such as the hydrological (water) and 6

meteorological (weather) characteristics of the area. An annual average of the water flow, wind speed, and wind direction are used to evaluate how the radionuclides will be distributed in an area for gaseous or liquid releases. An important factor in evaluating the exposure pathways is the use of the environment. Many factors are considered such as dietary intake of residents, recreational use of the area, and the locations of homes and farms in the area.

The external and internal exposure pathways considered are shown in Figure 2.1. The release of radioactive gaseous effluents involves pathways such as external whole-body exposure, deposition of radioactive material on plants, deposition on soil, inhalation by animals destined for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents involves pathways such as drinking water, fish, and direct exposure from the water at the shoreline while swimming.

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

Figure 2.1 External and Internal Exposure Pathways Radiaion Exposuelo

\ Deposied Materia Drinkirg Suiace Watera' Groundwaer This simple diagram demonstrates some potential exposure pathways from Oyster Creek Generating Station.

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Radiation Risk U.S. radiation protection standards are based on the premise that any radiation exposure carries some risk. There is a risk whether the radiation exposure is due to man-made sources or natural sources. There have been many studies performed trying to determine the level of risk. The following graph is an example of one study that tries to relate risk from many different factors. This graph represents risk as Days of Lost Life Expectancy. All the categories are averaged over the entire population except Male Smokers, Female Smokers and individuals that are overweight. Those risks are only for people that fall into those categories. The category for Nuclear Power is a government estimate based on all radioactivity releases from nuclear power, including accidents and wastes.

Days of Lost Life Expectancy Smoking Male Heart Disease Smoking Female Cancer Every 10 lbs overweight l

Stroke Motor Vehicle Accident Air Pollution Radon Chemical Residue in Foods Drowning Hurricanes and Tornadoes Lightning Nuclear Power O 500 1000 1500 2000 2500 3000 Days of Lost Life Expectancy Hurricanes and Tornadoes Lightning Nuclear Power Adapted from the article by Bernard L. Cohen, Ph.D. in the Journal of American Physicians and Surgeons Volume 8 Number 2 Summer 2003. The full article can be found at http://www.jpands.org/vol8no2/cohen.pdf 8

Annual Reports All nuclear power plants are required to perform sampling of both the potential release paths from the plant and the potential exposure pathways in the environment. The results of this sampling are required to be reported annually to the Nuclear Regulatory Commission (NRC) and made available to the public. There are two reports generated annually, the Annual Radioactive Effluents Release Report (ARERR) and the Annual Radiological Environmental Operating Report (AREOR). The ARERR summarizes all of the effluents released from the plant and quantifies the doses to the public from these effluents. The AREOR summarizes the results of the samples obtained in the environment looking at all the potential exposure pathways by sampling different media such as air, vegetation, direct radiation, etc. These two reports are related in that the results should be aligned. The AREOR should validate that the effluent program is accurate. The ARERR and AREOR together ensure Nuclear Power Plants are operating in a manner that adequately protects the public and the environment.

In the reports, there are four different but interrelated units for measuring radioactivity, exposure, absorbed dose, and dose equivalent. Together, they are used to properly capture both the amount of radiation and its effects on humans.

• Radioactivity refers to the amount of ionizing radiation released by a material.

The units of measure for radioactivity used within the AREOR and ARERR are the curie (Ci). Small fractions of the Ci often have a prefix, such as microCurie (Ci) that means 1/1,000,000. That means there are 1,000,000 Ci in one Ci.

Due to the extremely low levels of radioactivity in the environment, the unit commonly used for these samples is the picocurie (pCi). A pCi is 1/1,000,000 of a µCi; there are 1,000,000 pCi in a µCi. There are 1,000,000,000,000 pCi in a Ci.

• Exposure describes the amount of radiation traveling through the air. The units of measure for exposure used within the AREOR and ARERR are the roentgen (R). Traditionally direct radiation monitors placed around the site are measured in milliroentgen (mR), 1/1,000 of one R.

• Absorbed dose describes the amount of radiation absorbed by an object or person. The units of measure for absorbed dose used within the AREOR and ARERR are the rad. Noble gas air doses are reported by the site are measured in millirad (mrad), 1/1,000 of one rad.

• Dose equivalent (or effective dose) combines the amount of radiation absorbed and the health effects of that type of radiation. The units used within the AREOR and ARERR are the roentgen equivalent man (rem). Regulations require doses to the whole body, specific organ, and direct radiation to be reported in millirem (mrem), 1/1,000 of one rem.

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Typically releases from nuclear power plants are so low that the samples taken in the environment are below the detection levels required to be met by all nuclear power plants. There are some radionuclides identified in the environment during the routine sampling, but this is typically background radiation from nuclear weapons testing and events such as Chernobyl and these radionuclides are discussed in the AREOR.

Each report lists the types of samples that are collected and the analyses performed.

Different types of media may be used at one sample location looking for specific radionuclides. For example, at our gaseous effluent release points we use different media to collect samples for particulates, iodines, noble gases and tritium. There are also examples where a sample collected on one media is analyzed differently depending on the radionuclide for which the sample is being analyzed.

These annual reports, and much more information related to nuclear power, are available on the NRC website at www.nrc.gov.

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I. Summary and Conclusions On July 1st 2019, ownership of the Oyster Creek Nuclear Power Station and transfer of the station and decommissioning license from Exelon Generation Company, LLC to Oyster Creek Environmental Protection, LLC (OCEP) as the licensed owner and Holtec Decommissioning International, LLC (HDI) as the licensed operator, was completed. Exelon had determined that transitioning operational nuclear plants to decommissioning nuclear plants targeted for permanent shutdown was not aligned with its core objectives and actively sought buyers who would assume ownership and complete decommissioning and license termination.

This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Oyster Creek Generating Station (OCGS) by Holtec Decommissioning International, LLC (HDI) covers the period 01 January 2020 through 31 December 2020. During that time period, a total of 1,134 analyses were performed on 837 samples. In assessing all the data gathered for this report and comparing these results with historical data, it was concluded that the decommissioning of OCGS had no adverse radiological impact on the environment.

REMP-designated surface water samples were analyzed for concentrations of tritium and gamma emitting nuclides. No tritium, fission or activation products were detected in any of the surface water samples collected as part of the Radiological Environmental Monitoring Program during 2020.

REMP-designated drinking water samples were analyzed for concentrations of gross beta, tritium, and gamma emitting nuclides. The preoperational environmental monitoring program did not include analysis of drinking water for gross beta. No tritium or fission or activation products were detected in any of the drinking water samples collected.

REMP-designated groundwater samples were analyzed for concentrations of tritium and gamma emitting nuclides. No tritium and no fission or activation products were detected in REMP groundwater samples.

Fish (predator and bottom feeder), clams, crabs, and sediment samples were analyzed for concentrations of gamma emitting nuclides. No OCGS-produced fission or activation products were detected in fish, clams, crabs or sediment samples.

Air particulate samples were analyzed for concentrations of gross beta, gamma emitting nuclides, strontium-89 (Sr-89), and strontium-90 (Sr-90). Gross beta and cosmogenic beryllium-7 (Be-7) were detected at levels consistent with those detected in previous years. No fission or activation products were detected.

Sr-89 and Sr-90 analyses were performed on quarterly composites of air particulate samples. All Sr-89 and Sr-90 results were below the MDC.

Iodine-131 (I-131) analyses were performed weekly on air samples during the 1st quarter of 2020. All results were less than the minimum detectable concentration.

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Vegetation samples were analyzed for gamma emitting nuclides, Sr-89, and Sr-90. Concentrations of naturally occurring potassium-40 (K-40) were consistent with those detected in previous years. No fission or activation products were detected. All Sr-89 results were below the minimum detectable activity. Sr-90 activity was at levels consistent with those detected in previous years at both control and indicator stations and can be attributed to historical nuclear weapons testing and the Chernobyl accident.

Environmental gamma radiation measurements were performed quarterly using Optically Stimulated Luminescence Dosimeters (OSLD). Beginning in calendar year 2012, Exelon (the previous plant owner) began using OSLDs and discontinued the use of Thermoluminescent Dosimetry (TLD). There were two main reasons for this change. First, OSLDs have minimal fade over a quarterly time period. Fade is where the dose on the dosimeter drifts lower over time.

Second, OSLDs may be re-read if necessary. TLDs are reset to zero after they are read. Levels detected were consistent with those observed in previous years. The maximum dose to any member of the public attributable to radioactive effluents and direct radiation from the OCGS was less than the 25 mRem/year limit established by the United States Environmental Protection Agency (EPA).

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II. Introduction The Oyster Creek Generating Station (OCGS) is a non-operational single unit nuclear power plant owned and operated by HDI. OCGS is located on the Atlantic Coastal Plain Physiographic Province in Ocean County, New Jersey, about 60 miles south of Newark, 9 miles south of Toms River, and 35 miles north of Atlantic City. It lies approximately 2 miles inland from the Barnegat Bay. The Oyster Creek Site is approximately 152 acres located west of U.S. Highway Route 9 between the south branch of the Forked River and the Oyster Creek. Most of the Site is identified as Block 100, Lot 4.02 in Lacey Township according to a 2018 American Land Title Association (ALTA)/National Society of Professional Surveyors (NSPS) land title survey. The site includes a small land area south of the Discharge Canal identified as Block 4, Lot 43 in Ocean Township. A perimeter security fence surrounds the restricted /protected area of the site. The site description is changed to reflect the current decommissioning site boundaries.

The site location is part of the New Jersey shore area with its relatively flat topography and extensive freshwater and saltwater marshlands. The South Branch of Forked River runs across the northern side of the site and Oyster Creek partly borders the southern side.

A preoperational Radiological Environmental Monitoring Program (REMP) for OCGS was established in 1966 and continued prior to the plant becoming operational in 1969. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Landauer and Environmental Inc. (Midwest Labs) on samples collected during the period 01 January 2020 through 31 December 2020.

A. Objectives of the REMP The objectives of the REMP are to:

1. Provide data on measurable levels of radiation and radioactive materials in and beyond the site environs

2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure

3. Validate the effluent computer model that predicts radioactive material concentrations at populated off-site locations

4. Fulfill the obligations of the radiological surveillance sections of Oyster Creeks Offsite Dose Calculation Manual (ODCM)

B. Implementation of the Objectives The implementation of the objectives is accomplished by:

1. Identifying significant exposure pathways

2. Establishing baseline radiological data for media within those pathways

3. Continuously monitoring those media before, during and after terminating Station operation to assess Station radiological effects (if any) on the public, plant workers and the environment 13

C. Discussion

1. General Program The Radiological Environmental Monitoring Program (REMP) was established in 1966, before the plant became operational. This preoperational surveillance program was established to describe and quantify the radioactivity, and its variability, in the area prior to the operation of OCGS. After OCGS became operational in 1969, the operational surveillance program continued to measure radiation and radioactivity in the surrounding areas.

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

2. Preoperational Surveillance Program The federal government requires nuclear facilities to conduct radiological environmental monitoring prior to constructing the facility. This preoperational surveillance program is aimed at collecting the data needed to identify pathways, including selection of the radioisotope and sample media combinations to be included in the environmental surveillance program conducted after facility operation begins.

Radiochemical analyses performed on the environmental samples should include not only those nuclides expected to be released during facility operation but should also include typical radionuclides from nuclear weapons testing and natural background radioactivity. All environmental media with a potential to be affected by facility operation as well as those media directly in the major pathways, should be sampled on at least an annual basis during the preoperational phase of the environmental surveillance program.

The preoperational surveillance design, including nuclide/media combinations, sampling frequencies and locations, collection techniques, and radioanalyses performed, should be carefully considered and incorporated in the design of the operational surveillance program. In this manner, data can be compared in a variety of ways (for example, from year to year, location to location, etc.) in order to detect any radiological impact the facility has on the surrounding environment. Data collection during the preoperational phase should be planned to provide a comprehensive database for evaluating any future changes in the environment surrounding the nuclear facility.

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OCGS began its preoperational environmental surveillance program three years before the plant began operating in 1969. Data accumulated during those early years provide an extensive database from which environmental monitoring personnel are able to identify trends in the radiological characteristics of the local environment. The environmental surveillance program at OCGS will continue after the plant has reached the end of its economically useful life and decommissioning has begun.

3. Consideration of Plant Effluents Effluents are strictly monitored to ensure that radioactivity released to the environment is as low as reasonably achievable (ALARA) and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance programs for effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring.

Both radiological environmental and effluent monitoring indicate that the operation of OCGS does not result in significant radiation exposure of the people or the environment surrounding OCGS and is well below the applicable levels set by the Nuclear Regulatory Commission (NRC) and the EPA.

Environmental sampling of airborne iodine and particulates showed no radioactivity attributable to the operation of OCGS.

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III. Program Description A. Sample Collection Samples for the OCGS REMP were collected for HDI by on-site personnel and Normandeau Associates, Incorporated. This section describes the general collection methods used to obtain environmental samples for the OCGS REMP in 2020. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1, B-2, and B-3, Appendix B. The collection procedures are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, groundwater, fish, clams, crabs, and sediment. One gallon water samples were collected monthly from two surface water locations (33 and 94), semiannually at two surface water locations (23 and 24), monthly from four drinking water wells (1N, 1S, 37, and

38) and quarterly from 2 groundwater stations (MW-24-3A and W-3C).

Control locations were 94 and 37. All samples were collected in plastic bottles, which were rinsed at least twice with source water prior to collection.

Fish samples comprising the flesh of two groups, bottom feeder and predator, were collected semiannually at three locations (33, 93 and 94 [control]). Clams were collected semiannually from three locations (23, 24, and 94 [control]).

Two annual crab samples were collected from two locations (33 and 93).

Sediment samples were collected at four locations semiannually (23, 24, 33, and 94 [control]).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate and airborne iodine. Airborne iodine and particulate samples were collected and analyzed weekly at eight locations (C, 3, 20, 66, 71, 72, 73, and 111). The control location was C. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis. After the first quarter of 2020, the sample interval was changed to bi-weekly from weekly. See Program Changes for more detail.

Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of garden vegetation. No commercial dairy operations and no dairy animals producing milk for human consumption are located within a 5-mile radius of the plant. Therefore, vegetation samples were collected in lieu of milk. Vegetation samples were collected, when available, at four locations (35, 36, 66 and 115). Station 36 is the control location as it is 24 miles northwest of the plant in the lowest X/Q sector, beyond any influence of the 16

plant when the plant was operating, and while it is permanently shut down for decommissioning. All samples were collected in 18 x 24 new unused plastic bags and shipped promptly to the laboratory.

Ambient Gamma Radiation Direct radiation measurements were made using Al2O3:C Optically Stimulated Luminescence Dosimetry (OSLD). Exelon Nuclear (the previous plant owner) changed the dosimetry used for environmental monitoring. Beginning in calendar year 2012, Exelon began using OSLDs and discontinued the use of Thermoluminescent Dosimetry (TLD). There were two main reasons for this change. First, OSLDs are subject to minimal fade. Fade is where the dose on the dosimeter drifts lower over time. Second, OSLDs may be re-read if necessary. TLDs are reset to zero after they are read. The OSLDs were placed on and around the OCGS site and were categorized as follows:

An inner ring consisting of 19 locations (1, T1, 51, 52, 53, 54, 55, 56, 57, 58, 59, 61, 62, 63, 64, 65, 66, 112 and 113) near the site boundary.

An outer ring consisting of 21 locations (6, 8, 9, 22, 68, 73, 74, 75, 78, 79, 98, 99, 100, 101, 102, 103, 104, 106, 107, 109 and 110) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

Special interest stations consisting of 3 locations (71, 72 and 81) representing special interest areas such as population centers, state parks, etc.

Background (Control) stations consisting of one location (C) greater than 20 miles distant from the site.

Indicator OSLDs were placed systematically, with at least one station in each of 16 meteorological compass sectors in the general area of the site boundary. OSLDs were also placed in each meteorological sector in the 1 to 5 mile range, where reasonable highway access would permit, in areas of public interest and population centers. Background locations were located greater than twenty miles distant from the OCGS and generally in an upwind direction from the OCGS.

Two OSLDs were placed at each location approximately three to eight feet above ground level. The OSLDs were exchanged quarterly and sent to a vendor for analysis.

B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the OCGS REMP in 2020. The analytical procedures used by the laboratories are listed in Table B-3.

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In order to achieve the stated objectives, the current program includes the following analyses:

1. Concentrations of beta emitters in air particulates and drinking water

2. Concentrations of gamma emitters in surface water, drinking water, groundwater, fish, clams, crabs, sediment, air particulates and vegetation

3. Concentrations of tritium in REMP-designated surface water, drinking water and groundwater

4. Concentrations of I-131 in air iodine cartridges

5. Concentrations of strontium in air particulates and vegetation

6. Ambient gamma radiation levels at various locations around the OCGS C. Data Interpretation For trending purposes, the radiological and direct radiation data collected during 2020 were compared with data from past years. The results of environmental sampling show that radioactivity levels have not increased from the background radioactivity detected prior to the operation of OCGS. The operation of OCGS continues to have no measurable radiological impact upon the environment.

Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criterion for the presence of activity. All analyses were designed to achieve the required OCGS detection capabilities for environmental sample analysis.

The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity, 18

which results in a negative number. A less than MDC was reported in all cases where positive activity was not detected.

Gamma spectroscopy results for each type of sample were grouped as follows:

For surface, drinking water, and groundwater - 8 nuclides:

Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Cs-134 and Cs-137 were reported For fish - eight nuclides: K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-134, and Cs-137 were reported For clams - eight nuclides: K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-134, and Cs-137 were reported For crabs - eight nuclides: K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-134, and Cs-137 were reported For sediment - nine nuclides: Be-7, K-40, Mn-54, Co-58, Co-60, Cs-134, Cs-137, Ra-226, and Th-228 were reported For air particulates - six nuclides: Be-7, Mn-54, Co-58, Co-60, Cs-134, and Cs-137 were reported For air iodine cartridges - one nuclide: I-131 was reported For vegetation - four nuclides: Be-7, K-40, Cs-134 and Cs-137 were reported Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D. Program Exceptions For 2020, the OCGS REMP had a sample recovery rate in excess of 97%.

Exceptions are listed below:

Environmental Dosimetry

1. June, 2020: Station 6 (Lane Place, Lacey) - No 2nd quarter results due to loss of both dosimeters from Station 6. The dosimeters for the 3rd Quarter were deployed and recovered. Recovery of three of four quarters of OSLD data will not adversely affect the program.

Air

1. 01/15/20 & 02/12/20: Station C - Timer not running properly. Monitored for several weeks. Sample run times calculated from collection dates/times. Timer replaced 02/12/20.

2. 03/04/20: Station 111 - No valid sample due to pump not running.

Vanes replaced the same day and a new start time for the week.

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3. 04/22/20: Station C - No valid sample for Week 16 due to the station being turned off on 04/09/20. The air station was restarted that day.

4. 05/09/20: Station C - Timer not running properly. Sample run times calculated from collection dates/times. Timer replaced 05/20/20.

5. 05/20/20: Station 71 - No valid sample for Week 20 due to pump not running long enough to constitute a valid sample. Vanes replaced the same day.

6. 06/02/20: Stations 73 & C - No power due to storms the previous day.

All air samples valid. Breaker tripped at Station 73 and reset on 06/08/20.

7. 06/18/20: Station 111 - Pump not running; samples are valid. Pump replaced the same day.

8. 07/01/20: Station 72 - timer not running properly. Sample run times calculated from collection dates/times. Timer placed the same day.

9. 09/09/20: Station 66 - No valid sample for Week 36 due to safety concerns in sample collection. The main power line was disconnected from the utility pole. The sampler did not run long enough to constitute a valid sample. Power line reconnected 09/15/20.

10. 11/18/20: Station 73 - Pump not running due to tripped breaker.

Breaker was reset the same day.

Drinking Water Note: Stations 1S and 1N are on-site drinking water wells. Typically, only one well is in service at a time. They are only listed as deviations when there is not a sample for the monitoring period.

1. 2020: Station 1S was not operational for the entire year.

Fish/Crabs

1. June & October, 2020: Control Station 94 - no fish samples collected for spring & fall sampling. Per procedure ER-OCGS-14, fish are to be collected if available.

2. June, 2020: Station 93 collected only 1 species of fish.

3. October, 2020: Station 93 - no crabs available. As per procedure ER-OCGS-16, crabs are to be collected if available.

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Vegetation

1. 09/23/20: Stations 66 & 35 - Only 1 of 3 species collected at Station 66 and only 2 of 3 species collected at Station 35 due to the lateness of the growing season.

2. 10/2620: Stations 66 & 35 - No vegetation samples available at Station

66. Only 2 of 3 species collected at Station 35 due to the lateness of growing season.

Program exceptions are tracked by Oyster Creek staff and Normandeau and investigated to understand the causes of the program exception. Sampling and maintenance errors are reviewed with the personnel involved to prevent recurrence.

The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E. Program Changes In April, monthly water station samples changed from composite to grab samples. The number of active monthly water sample stations was reduced to 5. Air Station 3 was removed from the active sampling program for air particulates because it is further from the plant than plant effluents would be detected in a decommissioning facility. Active air station monitoring changed from weekly to bi-weekly beginning with the air samples deployed on April 9, 2020.

Sampling and analysis for I-131 was stopped in the first quarter of 2020. I-131 has a short half-life (8.0 days) and production of this isotope ceased when the plant permanently shut down in September 2018. In this interval, all the inventory of I-131 has undergone radioactive decay and is no longer present in OCGS effluents. Coincidentally with this change, the sample interval was changed from weekly to bi-weekly. I-131 has an 8 day half-life and sampling at a 14-day interval posed the risk of low levels of I-131 being missed in analysis. All of the particulate isotopes being analyzed for now have a half-life of greater than eight days and the same risk of missing low level contamination no longer exists.

Similarly, analysis of the short half-life Sr-89 isotope (50.5 days) is no longer performed for the same reason. Production of this fission product ceased in September 2018. Analysis for Sr-90 (29 year half-life) continues to be a part of the program at OCGS.

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IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken via grab sample methodology at two locations (33 and 94) on a monthly schedule. In addition, grab samples were collected semi-annually at two locations (23 and 24). Of these locations 23, 24, and 33, located downstream, could be affected by Oyster Creeks effluent releases. The following analyses were performed:

Tritium Surface water sampling began in 1966, and the samples were analyzed for tritium as well as other radioactivity. During this preoperational program, tritium was detected at an average concentration of 1,050 pCi/L.

At that time, counting instrumentation was not as sensitive as it now, and the minimum detectable concentration (MDC) was 1,000 pCi/L versus 200 pCi/L used through October, 2020. (The MDC was changed to 2,000 pCi/L in November, 2020). By comparing the 2020 sampling results to the decay- corrected average preoperational concentration reported in the 2007 Annual Radiological Environmental Operating Report (111 pCi/L), it can be seen that the inventory of tritium in the environment is due to fallout from past atmospheric nuclear weapons testing and is decreasing with time.

Samples from all locations were analyzed for tritium activity. No tritium activity was detected. (Table C-I.1, Appendix C)

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides.

All nuclides were less than the MDC. (Table C-I.2, Appendix C)

2. Drinking water Monthly samples were composited from monthly grab samples from six drinking water wells (1N, 1S, 37 and 38) through the 1st quarter of 2020.

A monthly grab sample was taken from May through December. Station 1, because it is located on the OCGS site, could potentially be affected by radioactive releases from the plant. Station 1 was split into two separate locations, 1N and 1S. Station 38, the Ocean Township Municipal Utility Authority Well, could potentially be affected by effluent releases from the OCGS. Given its distance from the facility (1.6 miles) and depth (approximately 360 feet), however, the probability of any OCGS-related impact is very small. Stations 37 and 39, Lacey Township Municipal Utility Authority wells, are not likely to be impacted by effluents from the OCGS.

These wells are located generally up-gradient of the regional groundwater flow direction (southeast). In addition, because of their depth (> 200 feet) 22

and distance from the site (2.2 and 3.5 miles respectively), they are unlikely to be affected by OCGS operations. The following analyses were performed:

Tritium Monthly samples from all locations were analyzed for tritium activity. No tritium activity was detected. Drinking water was sampled during the preoperational program and throughout the almost 50 years of the plants operational program. Tritium sampling results during the preoperational years, yielded results all less than the minimum detectable concentration of 1000 pCi/L. The 2020 results are all less than the MDC.

(Table C-II.1, Appendix C)

Gross Beta Monthly samples from all locations were analyzed for concentrations of total gross beta activity. Gross beta was detected in 21 of 36 samples and is attributed to natural sources and fallout residual from previous bomb testing. The values ranged from 1.6 to 4.5 pCi/L. (Table C-II.2, Appendix C)

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides.

All nuclides were less than the MDC. (Table C-II.3, Appendix C)

3. Groundwater The following analyses were performed:

Tritium Samples from all locations were analyzed for tritium activity. No tritium activity was detected. (Table C-III.1, Appendix C)

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-III.2, Appendix C). All nuclides were less than the MDC.

4. Fish Fish samples comprised of bottom feeder (summer flounder) and predator (American eel, white perch, silver perch, smooth dogfish, striped bass, and tautog) were collected at three locations (33, 93, and 94) semiannually when available. Locations 93 and 33 could be affected by Oyster Creeks effluent releases. The following analysis was performed:

Gamma Spectrometry The edible portions of fish samples from three locations were analyzed for gamma emitting nuclides. Naturally occurring K-40 was found at all 23

stations and ranged from 2,531 to 5,972 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were found. (Table C-IV.1, Appendix C)

No fish were sampled during the preoperational sampling program for OCGS.

5. Clams and Crabs Clams were collected at three locations (23, 24, and 94) semiannually when available. Crabs were collected at two locations (33 and 93) annually when available. Locations 23, 24, 33, and 93 could be affected by Oyster Creeks effluent releases. The following analysis was performed:

Gamma Spectrometry The edible portions of clam samples from all three locations were analyzed for gamma emitting nuclides. Naturally occurring K-40 was found at all stations and ranged from 1,198 to 2,657 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were found. (Table C-IV.2, Appendix C) Historical levels of Co-60 in clams are shown in Figure C-1, Appendix C. After 1986, all results were less than the Lower Limit of Detection (LLD).

Preoperational clam sample results for naturally occurring K-40 ranged from 600 to 9,800 pCi/kg wet, which are consistent with current sample results.

The edible portions of an annual crab sample were analyzed for gamma emitting nuclides. Naturally occurring K-40 was found at one location at a concentration of 2,063 pCi/kg wet, consistent with levels detected in previous years. No fission or activation products were found.

(Table C-IV.2, Appendix C)

Crabs were not sampled during the preoperational years of the OCGS environmental monitoring program.

6. Sediment Aquatic sediment samples were collected at four locations (23, 24, 33, and 94) semiannually. Of these locations, stations 23, 24, and 33 located downstream, could be affected by Oyster Creeks effluent releases. The following analysis was performed:

Gamma Spectrometry Sediment samples from all four locations were analyzed for gamma emitting nuclides. Naturally occurring K-40 was found at all stations and ranged from 615 to 19,230 pCi/kg dry. Naturally occurring Ra-226 was found at one location at a concentration of 4,319 pCi/kg dry. Naturally occurring Th-228 was found at all 4 stations and ranged from 108 to 875 24

pCi/kg wet. Cs-137 was not detected in any of the samples. No fission or activation products were found. (Table C-V.1, Appendix C)

The Figure C-3, Appendix C graph shows Cs-137 concentrations in sediment from 1984 through 2020 and Figure C-2, Appendix C graph shows Co-60 concentrations in sediment from 1984 through 2020.

The requirement for sampling sediment is a requirement of ODCM 3.12.1, Table 3.12.1-1.d. ODCM Table 3.12.1-2, Reporting Levels for Radioactive Concentrations in Environmental Samples Reporting Levels does not include requirements for sediment. CY-AA-170-1000, Radiological Environmental Monitoring Program and Meteorological Program Implementation, Attachment 1, Analytical Results Investigation Levels, includes sediment investigation level for Cs-137 of 1000E+00 pCi/kg dry.

While aquatic sediment sampling was part of the preoperational program, samples were not analyzed for gamma emitting nuclides until 1981.

In conclusion, the 2020 aquatic monitoring results for surface water, drinking water, groundwater, fish, clams, crabs, and sediment showed only naturally occurring radioactivity and were consistent with levels measured prior to the operation of OCGS, and with levels measured in past years. No radioactivity attributable to activities at OCGS was detected in any aquatic samples during 2020 and no adverse long-term trends are shown in the aquatic monitoring data.

B. Atmospheric Environment

1. Airborne

a. Air Particulates Continuous air particulate samples were collected from eight locations on a weekly basis until April 9, 2020. Bi-weekly sampling began with the period April9 - April 22, 2020. See Program Changes for more detail. The eight locations were separated into three groups: Group I represents locations near the OCGS site boundary (20, 66 and 111),

Group II represents the locations at an intermediate distance from the OCGS site (71, 72, and 73), and Group III represents the control and locations at a remote distance from OCGS (C and 3). The following analyses were performed:

Gross Beta Samples were analyzed for concentrations of beta emitters.

Detectable gross beta activity was observed at all locations.

Comparison of results among the three groups aids in determining the effects, if any, resulting from the operation of OCGS. The results from the Site Boundary locations (Group I) ranged from 5E-03 to 21E-03 pCi/m3 with a mean of 12E-03 pCi/m3. The results from the 25

Intermediate Distance locations (Group II) ranged from 5E-03 to 19E-03 pCi/m3 with a mean of 11E-03 pCi/m3. The results from the Distant locations (Group III) ranged from 7E-03 to 24E-03 pCi/m3 with a mean of 13E-03 pCi/m3. (Table C-VI.1 and C-VI.2, Appendix C)

The similarity of the results from the three groups indicates that there is no relationship between gross beta activity and distance from OCGS. These results are consistent with data from previous years and indicate no effects from the operation of OCGS (Figures C-4 and C-5, Appendix C).

Air sample filters have been analyzed for gross beta activity since the inception of the preoperational environmental monitoring program in 1966. The preoperational data values ranged from 1.90E-02 to 2.77E-01 pCi/m3. The 2020 gross beta activity values ranged from

<5E-03 to 24E-03 pCi/m3. The 2020 results are consistent with historical operational data (Figure C-5, Appendix C) and fall within the range of results observed during the preoperational period.

Strontium-89 and Strontium-90 Samples were composited quarterly and analyzed for Sr-89 and Sr-90. No strontium was detected in any of the samples.

(Table C-VI.3, Appendix C) These results are consistent with historical operational data. The preoperational environmental monitoring program did not include analysis of air samples for Sr-89 and Sr-90.

Gamma Spectrometry Samples were composited quarterly and analyzed for gamma emitting nuclides. Naturally occurring Be-7 due to cosmic ray activity was detected in 29 of 29 samples. The values ranged from 39E-03 to 83E-03 pCi/m3. All other nuclides were less than the MDC. (Table C-VI.4, Appendix C) These results are consistent with historical operational data. The preoperational environmental monitoring program did not include analysis of air samples for gamma emitting nuclides.

b. Airborne Iodine Continuous air samples were collected from eight (C, 3, 20, 66, 71, 72, 73, 111) locations and analyzed weekly for I-131 in the 1st quarter of 2020. After the first quarter, analysis for I-131 was eliminated. See Program Changes section for more detail Consistent with historical operational data, all results were less than the MDC for I-131. (Table C-VII.1, Appendix C)

The preoperational environmental monitoring program for OCGS did not include analysis of air media for I-131.

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In conclusion, the atmospheric monitoring data are consistent with preoperational and prior operational data and show no long-term trends in the environment attributable to the operation of OCGS.

2. Terrestrial

a. Vegetation Samples were collected from four locations (35, 36, 66 and 115) when available. The following analyses were performed:

Strontium-89 and Strontium-90 Vegetation samples from all locations were analyzed for concentrations of Sr-89 and Sr-90. All Sr-89 results were less than the MDC. Sr-90 was detected in 34 of 55 samples. The values ranged from 4.4 to 14.4 pCi/kg wet, which is consistent with historical data.

(Table C-VIII.1, Appendix C)

The following information on Sr-90 is available on the NRC web page under Backgrounder Radiation Protection and the Tooth Fairy Issue published in December of 2004:

The largest source of Sr-90 in the environment (~99%) is from weapons testing fallout. Approximately 16.8 million curies of Sr-90 were produced and globally dispersed in atmospheric nuclear weapons testing until 1980. As a result of the Chernobyl accident, approximately 216,000 curies of Sr-90 were released into the atmosphere. With a 28-year half-life, Sr-90 still remains in the environment at nominal levels.

The total annual release of Sr-90 into the atmosphere from all 103 commercial nuclear power plants operating in the United States is typically 1/1000th of a curie. (NUREG/CR-2907 Vol.12). At an individual nuclear power plant, the amount of Sr-90 is so low that it is usually at or below the minimum detectable activity of sensitive detection equipment.

Oyster Creek did not report any Sr-90 released in the Annual Radioactive Effluent Release Report as all analyses for Sr-90 performed were less than the minimum detectable concentration.

Gamma Spectrometry Vegetation samples from locations 35, 36, and 115 were analyzed for concentrations of gamma-emitting nuclides. Naturally occurring K-40 activity was found in all samples and ranged from 1,379 to 5,287 pCi/kg wet. Naturally occurring Be-7 was detected in 9 of 55 samples and ranged from 185 to 830 pCi/kg wet. All other nuclides were less than the MDC. (Table C-VIII.1, Appendix C)

Preoperational vegetation sample analyses did not include strontium 27

analyses or gamma spectroscopy.

Oyster Creek conducted a Cs-137 study in 2006/2007. A report was generated titled "Evaluation of Cesium-137 in Environmental Samples from the Amergen Property East of the Oyster Creek Generating Station". Below is an excerpt from that report:

The levels of Cs-137 observed in the soil and vegetation samples are consistent with environmental concentrations known to be attributable to fallout from historic nuclear weapons testing and the Chernobyl accident. In addition, the variability of Cs-137 concentrations in soil and vegetation on the farm property appears to be driven by a number of environmental factors. Cs-137 concentrations in soil were non-detectable.

Vegetation samples exhibited Cs-137 concentrations from non-detectable to 0.130 pCi/g, with a mean concentration of 0.078 pCi/g. For comparison, in the year 2000, as part of the confirmatory release survey for the adjacent Forked River site to the west of OCGS, the NRC reported that the maximum observed soil concentration of 0.53 pCi/g was not distinguishable from the variation in Cs-137 in the environment due to these fallout sources. The NRC also reported background Cs-137 concentrations in New Jersey coastal plain soils as high as 1.5 and 2.8 pCi/g. In addition, decay-corrected historic REMP data from a predominantly upwind location, nearly four miles from the OCGS, yields present-day Cs-137 concentrations ranging from 0.862 to 1.68 pCi/g.

In 2020, there was no Cs-137 identified in any vegetation samples, but it is not unusual for Cs-137 to be identified given the known environmental levels of this radionuclide attributable to atmospheric nuclear weapons testing and the Chernobyl accident.

In conclusion, terrestrial monitoring results for vegetation samples during 2020 showed only naturally-occurring radioactivity and radioactivity associated with fallout from past atmospheric nuclear weapons testing and Chernobyl. The radioactivity levels detected were consistent with levels measured in past years, and no radioactivity attributable to activities at OCGS was detected in any terrestrial samples. The terrestrial monitoring data show no adverse long-term trends in the terrestrial environment.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured using Optically Stimulated Luminenscence Dosimeters (OSLD). Forty-four OSLD locations were monitored around the site with all measurements below 25 mRem/yr. Results of background corrected OSLD measurements are summarized in Tables C-IX.1 to C-IX.3 and Figure C-6.

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The non-background corrected OSLD measurements ranged from 17.8 to 31.7 mR/standard quarter. In order to correct these results for background radiation, the mean of the dose rates measured at the background OSLD station (C) was subtracted from the dose measured at each indicator station.

The preoperational environmental monitoring program utilized film badges, the results of which are not comparable with the doses measured using thermoluminescent dosimeters or optically stimulated dosimeters during the operational REMP. In conclusion, the 2020 OSLD results are consistent with past operational measurements of direct radiation and demonstrate that the OCGS continues to be in compliance with the 40 CFR 190 limit on maximum dose to the public.

D. Land Use Survey A Land Use Survey, conducted in September 2020 around the Oyster Creek Generating Station (OCGS), was performed by Normandeau Associates, Inc.

for HDI. The survey is conducted annually to identify any changes from the previous year. The purpose of the survey is to identify the nearest residence and garden larger than 500 square feet within each meteorological sector, at a distance of 5 miles from the plant. Additionally, as part of the survey, Normandeau also looked for evidence of milk-producing animals for human consumption in each of the 16 meteorological sectors out to a distance of 5 miles from the OCGS. None were observed. The distance and direction of all locations from the OCGS Reactor Building were determined using Global Positioning System (GPS) technology. Thirty-three gardens identified in the 2019 report were not viable or determined to be too small to be considered this year. However, thirty-four new gardens, previously not identified, were noted within 3 miles of the facility during this years survey. The results of this survey are summarized below:

Distance in Feet from the OCGS Reactor Building Sector Residence (ft.) Garden* (ft.)

1 N 5,655 6,077 2 NNE 3,240 4,557 3 NE 3,245 3,932 4 ENE 5,704 6,486 5 E 6,549 1,758 6 ESE 3,189 2,081 7 SE 3,073 2,321 8 SSE 4,666 8,141 9 S 7,971 9,034 10 SSW 8,260 8,290 11 SW 9,285 9,776 12 WSW 10,713 12,354 13 W 22,191 None 14 WNW None None 15 NW 27,985 None 16 NNW 7,506 8,918

• Greater than 500 ft2 in size producing broad leaf vegetation 29

E. Summary of Results - Inter-laboratory Comparison Program The TBE Laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation, and water matrices for various analytes. The PE samples supplied by Analytics Inc., Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

A. Analytics Evaluation Criteria Analytics evaluation report provides a ratio of TBEs result and Analytics known value. Since flag values are not assigned by Analytics, TBE evaluates the reported ratios based on internal Quality Control (QC) requirements based on the DOE MAPEP criteria.

B. ERA Evaluation Criteria ERAs evaluation report provides an acceptance range for control and warning limits with associated flag values. ERAs acceptance limits are established per the United States Environmental Protection Agency (USEPA), National Environmental Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (PT) program requirements or ERAs standard operating procedure (SOP) for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

C. DOE Evaluation Criteria MAPEPs evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of performance:

• Acceptable (flag = A) - result within +/- 20% of the reference value

• Acceptable with Warning (flag = W) - result falls in the +/- 20% to +/-

30% of the reference value

• Not Acceptable (flag = N) - bias is greater than 30% of the reference value Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

For the TBE laboratory, 126 out of 133 analyses performed met the specified acceptance criteria. Seven analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program. A summary is found below:

30

1. The MAPEP February 2020 AP U-233/234 and U-238 results were evaluated as Not Acceptable. The reported value for U-233/234 was 0.0416 +/- 0.0102 Bq/sample and the known result was 0.075 Bq/sample (acceptance range 0.053 - 0.098). The reported value for U-238 was 0.0388 +/- 0.00991 Bq/sample and the known result was 0.078 Bq/sample (acceptance range 0.055 - 0.101). This sample was run as the workgroup duplicate and had relative percentage differences (RPDs) of 10.4% (U-234) and 11.7% (U-238). After the known results were obtained, the sample was relogged. The filter was completely digested with tracer added originally; the R1 results were almost identical. It was concluded that the recorded tracer amount was actually double, causing the results to be skewed. Lab worksheets have been modified to verify actual tracer amount vs. LIMS data. TBE changed vendors for this cross-check to ERA MRaDTM during the 2nd half of 2020. Results were acceptable at 97.8% for U-234 and 106% for U-238. (NCR 20-13)

2. The Analytics September 2020 milk Sr-89 result was evaluated as Not Acceptable. The reported value was 62.8 pCi/L and the known result was 95.4 (66%). All QC data was reviewed and there were no anomalies. This was the first failure for milk Sr-89 since 2013 and there have only been 3 upper/lower boundary warnings since that time. It is believed that there may have been some Sr-89 loss during sample prep. The December 2020 result was at 92% of the known. (NCR 20-19)

3. The ERA October 2020 water I-131 result was evaluated as Not Acceptable. The reported value was 22.9 pCi/L and the known result was 28.2 (acceptance range 23.5 - 33.1). The reported result was 81% of the known, which passes TBE QC criteria. This was the first failure for water I-131. (NCR 20-17)

4. The ERA October 2020 water Gross Alpha and Gross Beta results were evaluated as Not Acceptable. The reported/acceptable values and ranges are as follows:

Reported Known Range Gross Alpha 40.0 26.2 13.3 - 34.7 Gross Beta 47.5 69.1 48.0 - 76.0 All QC data was reviewed with no anomalies and a cause for failure could not be determined. This was the first failure for water Gross Beta. A Quick Response follow-up cross-check was analyzed as soon as possible with acceptable results at 96.8% for Gross Alpha and 102% for Gross Beta.

(NCR 20-18)

5. The MAPEP August 2020 soil Ni-63 result was evaluated as Not Acceptable. The reported value was 438 +/- 21.1 Bq/kg and the known result was 980 Bq/kg (acceptance range 686 - 1274). It is believed that some Ni-63 loss occurred during the sample prep step. (NCR 20- 20) 31

For the secondary QC samples, Environmental Inc., Midwest Laboratories (EIML) analyzed samples for H-3, Gross Alpha, Sr-89/90 and gamma nuclides. For these analyses, 46 of 46 analyses met the specified acceptance criteria.

The Inter-Laboratory Comparison Program provides evidence of in control counting systems and methods, and that the laboratories are producing accurate and reliable data.

V. References

1. HDI Offsite Dose Calculation Manual for Oyster Creek Generating Station, Procedure CY-OC-170-301.

2. United States Nuclear Regulatory Commission Branch Technical Position, An Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.

3 Pre-Operational Environmental Radiation Survey, Oyster Creek Nuclear Electric Generating Station, Jersey Central Power and Light Company, March 1968.

VI. Errata In the 2019 AREOR, Table C-VI.3 results for AP Sr-89 & Sr-90 were not updated from the previous year. All results were < MDC for both years. The correction is found in Appendix F.

32

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2020 NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER: 50-219 LOCATION OF FACILITY: OCEAN COUNTY, NJ REPORTING PERIOD: 2020 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER H-3 30 2000 <LLD <LLD - 0 (PCI/LITER)

GAMMA 30 MN-54 15 <LLD <LLD - 0 CO-58 15 <LLD <LLD - 0 FE-59 30 <LLD <LLD - 0 CO-60 15 <LLD <LLD - 0 ZN-65 30 <LLD <LLD - 0 ZR-95 30 <LLD <LLD - 0 CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 A-1 DRINKING WATER H-3 36 2000 <LLD <LLD - 0 (PCI/LITER)

GR-B 36 4 2.5 2.3 3.1 1N INDICATOR 0 (12/24) (9/12) (2/12) ON-SITE DOMESTIC WELL AT OCGS 1.6 - 4.5 1.8 - 3.5 1.8 - 4.5 0.2 MILES N OF SITE GAMMA 36 MN-54 15 <LLD <LLD - 0 CO-58 15 <LLD <LLD - 0 FE-59 30 <LLD <LLD - 0 CO-60 15 <LLD <LLD - 0 ZN-65 30 <LLD <LLD - 0 ZR-95 30 <LLD <LLD - 0 CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 GROUNDWATER H-3 8 2000 <LLD NA - 0 (PCI/LITER)

GAMMA 8 MN-54 15 <LLD NA - 0 CO-58 15 <LLD NA - 0 FE-59 30 <LLD NA - 0 CO-60 15 <LLD NA - 0 ZN-65 30 <LLD NA - 0 ZR-95 30 <LLD NA - 0 CS-134 15 <LLD NA - 0 CS-137 18 <LLD NA - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2020 NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER: 50-219 LOCATION OF FACILITY: OCEAN COUNTY, NJ REPORTING PERIOD: 2020 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS BOTTOM FEEDER GAMMA 2 (PCI/KG WET) K-40 NA 3813.5 NA 3813.5 33 INDICATOR 0 (2/2) (2/2) EAST OF RT 9 BRIDGE IN OCGS DISCHARGE 3515 - 4112 3515 - 4112 0.4 MILES ESE OF SITE MN-54 130 <LLD NA - 0 CO-58 130 <LLD NA - 0 FE-59 260 <LLD NA - 0 CO-60 130 <LLD NA - 0 ZN-65 260 <LLD NA - 0 CS-134 130 <LLD NA - 0 CS-137 150 <LLD NA - 0 A-2 PREDATOR GAMMA 11 (PCI/KG WET) K-40 NA 4004.9 NA 4288.7 93 INDICATOR 0 (11/11) (3/3) OCGS DISCHARGE CANAL 2531 - 5972 3258 - 5466 0.1 MILES WSW OF SITE MN-54 130 <LLD NA - 0 CO-58 130 <LLD NA - 0 FE-59 260 <LLD NA - 0 CO-60 130 <LLD NA - 0 ZN-65 260 <LLD NA - 0 CS-134 130 <LLD NA - 0 CS-137 150 <LLD NA - 0 CLAMS GAMMA 7 (PCI/KG WET) K-40 NA 1792.6 1829 2241 23 INDICATOR 0 (5/5) (2/2) (2/2) BARNEGAT BAY OFF STOUTS CREEK 1198 - 2657 1773 - 1885 1198 - 2657 3.6 MILES ENE OF SITE MN-54 130 <LLD <LLD - 0 CO-58 130 <LLD <LLD - 0 FE-59 260 <LLD <LLD - 0 CO-60 130 <LLD <LLD - 0 ZN-65 260 <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2020 NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER: 50-219 LOCATION OF FACILITY: OCEAN COUNTY, NJ REPORTING PERIOD: 2020 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS CRABS GAMMA 1 (PCI/KG WET) K-40 NA 2063 NA 2063 33 INDICATOR 0 (1/1) (1/1) EAST OF RT 9 BRIDGE IN OCGS DISCHARGE 0.4 MILES ESE OF SITE MN-54 130 <LLD NA - 0 CO-58 130 <LLD NA - 0 FE-59 260 <LLD NA - 0 CO-60 130 <LLD NA - 0 ZN-65 260 <LLD NA - 0 CS-134 130 <LLD NA - 0 CS-137 150 <LLD NA - 0 A-3 SEDIMENT GAMMA 10 (PCI/KG DRY) BE-7 NA <LLD <LLD - 0 K-40 NA 6858 16380 16380 94 CONTROL 0 (8/8) (2/2) (2/2) GREAT BAY/LITTLE EGG HARBOR 615 - 12190 13530 - 19230 13530 - 19230 20.0 MILES SSW OF SITE MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 CS-134 150 <LLD <LLD - 0 CS-137 180 <LLD <LLD - 0 Ra-226 NA 4319 <LLD 4319 24 INDICATOR 0 (1/8) (1/2) BARNEGAT BAY 2.1 MILES E OF SITE Th-226 NA 445 581 650 24 INDICATOR (8/8) (2/2) (2/2) BARNEGAT BAY 0 108 - 875 468 - 693 426 - 875 2.1 MILES E OF SITE AIR PARTICULATE GR-B 240 10 12 13 13 C CONTROL 0 (E-3 PCI/CU.METER) (184/195) (43/45) (31/32) JCP&L OFFICE - COOKSTOWN NJ 5 - 21 7 - 24 7 - 24 24.7 MILES NW OF SITE SR-89 22 10 <LLD <LLD - 0 SR-90 29 10 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2020 NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER: 50-219 LOCATION OF FACILITY: OCEAN COUNTY, NJ REPORTING PERIOD: 2020 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR PARTICULATE GAMMA 29 (E-3 PCI/CU.METER) BE-7 NA 55.1 62.9 64.6 C CONTROL 0 (24/24) (5/5) (4/4) JCP&L OFFICE - COOKSTOWN NJ 39 - 83 52 - 77 52 - 77 24.7 MILES NW OF SITE MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 CS-134 50 <LLD <LLD - 0 CS-137 60 <LLD <LLD - 0 AIR IODINE GAMMA 56 (E-3 PCI/CU.METER) I-131 70 <LLD <LLD - 0 A-4 VEGETATION SR-89 55 25 <LLD <LLD - 0 (PCI/KGWET)

SR-90 55 5 7.4 7.6 8.5 115 INDICATOR 0 (25/40) (9/15) (13/15) EAST OF SITE 4.4 - 14.4 4.5 - 14.2 4.6 - 14.4 0.3 MILES E OF SITE GAMMA 33 BE-7 NA 572.8 513.5 776.3 115 INDICATOR 0 (6/40) (3/15) (2/15) EAST OF SITE 185 - 782 343 - 830 771 - 782 0.4 MILES SE OF SITE K-40 NA 3202.3 3766.8 3874.3 QCA INDICATOR 0 (40/40) (15/15) (3/3) QC DUPLICATE SAMPLE 1379 - 5189 1583 - 5287 3026 - 4647 CS-134 60 <LLD <LLD - 0 CS-137 80 <LLD <LLD - 0 DIRECT RADIATION OSLD-QUARTERLY 381 NA 22.2 22.2 28.9 55 INDICATOR 0 (MILLIREM/STD.MO.) (377/377) (4/4) (4/4) SOUTHERN AREA STORES SECURITY FENCE 18.7 - 31.7 18.7 - 25.4 25.7 - 31.7 0.3 MILES W (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS

Intentionally left blank TABLE B-1: Location Designation and Identification System for the Oyster Creek Generating Station Sample Medium - APT = Air Particulate Clam = Clam AIO = Air Iodine OSLD = Optically Stimulated DW = Drinking Water Luminescence Dosimetry VEG = Vegetation Fish = Fish SWA = Surface Water Crab = Crab AQS = Aquatic Sediment GW = Ground Water Station Code - Stations Designation Distance - Distance from the OCGS in miles Azimuth - Azimuth with respect to the OCGS in degrees Description - Meteorological sector in which the station is located and a narrative description B-1

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Oyster Creek Generating Station, 2020 Sample Station Distance Azimuth Description Medium Code (miles) (degrees)

OSLD 1 0.4 219 SW of site at OCGS Fire Pond, Forked River, NJ DW 1N 0.2 349 On-site northern domestic well at OCGS, Forked River, NJ DW 1S 0.1 209 On-site southern domestic well at OCGS, Forked River, NJ APT, AIO 3 6.0 97 East of site, near old Coast Guard Station, Island Beach State Park OSLD 6 2.1 13 NNE of site, Lane Place, behind St. Pius Church, Forked River, NJ OSLD 8 2.3 177 South of site, Route 9 at the Waretown Substation, Waretown, NJ OSLD 9 2.0 230 WSW of site, west of where Route 532 and the Garden State Parkway meet, Waretown, NJ APT, AIO, OSLD C 24.7 313 NW of site, JCP&L office in rear parking lot, Cookstown, NJ APT, AIO 20 0.7 95 East of site, on Finninger Farm on south side of access road, Forked River, NJ B-2 OSLD 22 1.6 145 SE of site, on Long John Silver Way, Skippers Cove, Waretown, NJ ENE of site, Barnegat Bay off Stouts Creek, approximately 400 yards SE of SWA, CLAM, AQS 23 3.6 64 Flashing Light 1 SWA, CLAM, AQS 24 2.1 101 East of site, Barnegat Bay, approximately 250 yards SE of Flashing Light 3 SWA, AQS, 33 0.4 123 ESE of site, east of Route 9 Bridge in OCGS Discharge Canal FISH, CRAB VEG 35 0.4 111 ESE of site, east of Route 9 and north of the OCGS Discharge Canal, Forked River, NJ VEG 36 23.1 319 NW of site, at "U-Pick" Farm, New Egypt, NJ DW 37 2.2 18 NNE of Site, off Boox Road at Lacey MUA Pumping Station, Forked River, NJ DW 38 1.6 197 SSW of Site, on Route 532, at Ocean Township MUA Pumping Station, Waretown, NJ OSLD 51 0.4 358 North of site, on the access road to Forked River site, Forked River, NJ OSLD 52 0.3 333 NNW of site, on the access road to Forked River site, Forked River, NJ OSLD 53 0.3 309 NW of site, at sewage lift station on the access road to the Forked River site, Forked River, NJ

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Oyster Creek Generating Station, 2020 Sample Station Distance Azimuth Description Medium Code (miles) (degrees)

OSLD 54 0.3 288 WNW of site, on the access road to Forked River site, Forked River, NJ OSLD 55 0.3 263 West of site, on Southern Area Stores security fence, west of OCGS Switchyard, Forked River, NJ WSW of site, on utility pole east of Southern Area Stores, west of the OCGS Switchyard, OSLD 56 0.3 249 Forked River, NJ OSLD 57 0.3 206 SSW of site, on Southern Area Stores access road, Forked River, NJ OSLD 58 0.3 188 South of site, on Southern Area Stores access road, Forked River, NJ OSLD 59 0.3 166 SSE of site, on Southern Area Stores access road, Waretown, NJ OSLD 61 0.3 104 ESE of site, on Route 9 south of OCGS Main Entrance, Forked River, NJ OSLD 62 0.2 83 East of site, on Route 9 at access road to OCGS Main Gate, Forked River, NJ OSLD 63 0.2 70 ENE of site, on Route 9, between main gate and OCGS North Gate access road, Forked River, NJ B-3 OSLD 64 0.3 42 NE of site, on Route 9 North at entrance to Finninger Farm, Forked River, NJ OSLD 65 0.4 19 NNE of site, on Route 9 at Intake Canal Bridge, Forked River, NJ APT, AIO, 66 0.4 133 SE of site, east of Route 9 and south of the OCGS Discharge Canal, inside fence, Waretown, NJ OSLD, VEG OSLD 68 1.3 266 West of site, on Garden State Parkway North at mile marker 71.7, Lacey Township, NJ APT, AIO, OSLD 71 1.6 164 SSE of site, on Route 532 at the Waretown Municipal Building, Waretown, NJ APT, AIO, OSLD 72 1.9 25 NNE of site, on Lacey Road at Knights of Columbus Hall, Forked River, NJ APT, AIO, OSLD 73 1.8 108 ESE of site, on Bay Parkway, Sands Point Harbor, Waretown, NJ OSLD 74 1.8 88 East of site, Orlando Drive and Penguin Court, Forked River, NJ OSLD 75 2.0 71 ENE of site, Beach Blvd. and Maui Drive, Forked River, NJ OSLD 78 1.8 2 North of site, 1514 Arient Road, Forked River, NJ OSLD 79 2.9 160 SSE of site, Hightide Drive and Bonita Drive, Waretown, NJ

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Oyster Creek Generating Station, 2020 Sample Station Distance Azimuth Description Medium Code (miles) (degrees)

OSLD 81 3.5 201 SSW of site, on Rose Hill Road at intersection with Barnegat Boulevard, Barnegat, NJ FISH, CRAB 93 0.1 242 WSE of site, OCGS Discharge Canal between Pump Discharges and Route 9, Forked River, NJ SWA, AQS, 94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor CLAM, FISH OSLD 98 1.6 318 NW of site, on Garden State Parkway North at mile marker 73, Lacey Township, NJ OSLD 99 1.5 310 NW of site, on Garden State Parkway at mile marker 72.8, Lacey Township, NJ OSLD 100 1.4 43 NE of site, Yacht Basin Plaza South off Lakeside Dr., Lacey Township, NJ OSLD 101 1.6 49 NE of site, end of Lacey Rd. East, Lacey Township, NJ OSLD 102 2.4 344 NNW of site, end of Sheffield Dr., Barnegat Pines, Lacey Township, NJ OSLD 103 1.8 337 NNW of site, Llewellyn Pkwy., Barnegat Pines, Lacey Township, NJ B-4 OSLD 104 1.2 221 W of site, Rt. 532 West, before Garden State Parkway, Ocean Township, NJ OSLD 106 1.2 288 WNW of site, Garden State Parkway North beside mile marker 72.2, Lacey Township, NJ OSLD 107 1.3 301 WNW of site, Garden State Parkway North beside mile marker 72.5, Lacey Township, NJ OSLD 109 1.2 141 SE of site, Lighthouse Dr., Waretown, Ocean Township, NJ OSLD 110 1.5 127 SE of site, Tiller Dr. and Admiral Way, Waretown, Ocean Township, NJ OSLD 112 0.2 176 S of site, along southern access road OSLD 113 0.3 90 E of site, along Rt.9, North OSLD T1 0.4 219 SW of site, at OCGS Fire Pond, Forked River, NJ GW MW-24-3A 0.8 97 ESE of site, Finninger Farm on South side of access road, Lacey Township, NJ GW W-3C 0.4 112 ESE of site, Finninger Farm adjacent to Station 35, Lacey Township, NJ

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Oyster Creek Generating Station, 2020 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium ER-OCGS-06, Collection of water samples for TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Drinking Gamma radiological analysis Monthly samples 1 gallon Env. Inc., GS-01 Determination of gamma emitters by Water Spectroscopy CY-OC-120-1200, REMP sample collection gamma spectroscopy procedure - well water ER-OCGS-06, Collection of water samples for TBE, TBE-2011 Tritium in Drinking Water by Liquid Drinking radiological analysis Scintillation Tritium Monthly samples 1 gallon Water CY-OC-120-1200, REMP sample collection Env. Inc., T-02 Determination of tritium in water (direct procedure - well water method)

ER-OCGS-06, Collection of water samples for TBE, TBE-2012 Radioiodine in Various Matrices Drinking radiological analysis Iodine Monthly Samples 1 gallon Env. Inc., I-131-01 Determination of I-131 in water by anion water CY-OC-120-1200, REMP sample collection exchange procedure - well water ER-OCGS-06, Collection of water samples for B-5 Drinking radiological analysis TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Gross Beta Monthly Samples 1 gallon Water CY-OC-120-1200, REMP sample collection Various Matrices procedure - well water TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Surface Gamma ER-OCGS-06, Collection of water samples for Grab Sample 1 gallon Env. Inc., GS-01 Determination of gamma emitters by Water Spectroscopy radiological analysis gamma spectroscopy TBE, TBE-2011 Tritium in Drinking Water by Liquid Surface ER-OCGS-06, Collection of water samples for Scintillation Tritium Grab Sample 1 gallon Water radiological analysis Env. Inc., T-02 Determination of tritium in water (direct method)

ER-OCGS-06, Collection of water samples for TBE, TBE-2011 Tritium in Drinking Water by Liquid Groundwater Tritium Grab Sample 1 gallon radiological analysis Scintillation TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis ER-OCGS-06, Collection of water samples for Groundwater Gamma Grab Sample 1 gallon Env. Inc., GS-01 Determination of gamma emitters by radiological analysis gamma spectroscopy Semi-annual samples Gamma ER-OCGS-14, Collection of fish samples for Fish collected via hook and 250 grams (wet) TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Spectroscopy radiological analysis line technique and traps

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Oyster Creek Generating Station, 2020 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Semi-annual and annual Clams and Gamma ER-OCGS-16, Collection of clam and crab samples collected using 300 grams (wet) TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Crabs Spectroscopy samples for radiological analysis clam tongs and traps.

TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Gamma Semi-annual grab ER-OCGS-03, Collection of aquatic sediment Sediment 1000 grams (dry) Env. Inc., GS-01 Determination of gamma emitters by Spectroscopy samples samples for radiological analysis gamma spectroscopy One-week composite of 1 filter Air continuous air sampling ER-OCGS-05, Collection of air iodine and air (approximately 300 TBE, TBE-2008 Gross alpha and/or beta activity in various Gross Beta Particulates through glass fiber filter particulate samples for radiological analysis cubic meters matrices paper weekly)

TBE, TBE-2023 Compositing of samples 13 filters Air Gamma Quarterly composite of Env. Inc., AP-03 Procedure for compositing air (approximately TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Particulates Spectroscopy each station particulate filters for gamma spectroscopic 4000 cubic meters)

B-6 analysis 13 filters Air Quarterly composite of ER-OCGS-05, Collection of air iodine and air TBE, TBE-2018 Radiostrontium Analysis by Chemical Strontium-89/90 (approximately Particulates each station particulate samples for radiological analysis Separation 4000 cubic meters) 1 filter One-week composite of Gamma ER-OCGS-05, Collection of air iodine and air (approximately 300 Air Iodine continuous air sampling TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Spectroscopy particulate samples for radiological analysis cubic meters through charcoal filter weekly)

ER-OCGS-04, Collection of food products and TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Gamma Grab sample during Vegetation broadleaf vegetation samples for radiological 1000 grams Env. Inc., GS-01 Determination of gamma emitters by Spectroscopy growing season analysis gamma spectroscopy TBE, TBE-2018 Radiostrontium Analysis by Chemical ER-OCGS-04, Collection of food products and Separation Grab sample during Vegetation Strontium-89/90 broadleaf vegetation samples for radiological 1000 grams growing season Env. Inc., SR-05 Determination of Sr-89 and Sr-90 in Ashed analysis Samples Optically Quarterly OSLDs Stimulated comprised of two ER OCGS-02, Collection/Exchange of Field OSLD 2 dosimeters Landauer Incorporated Luminescence Al2O3:C Landauer Dosimeters for Radiological Analysis Dosimetry Incorporated elements.

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Figure B-3 Locations of REMP Stations greater than 5 miles from the Oyster Creek Generating Station, 2020 B-9

Intentionally left blank APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank Table C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 23 24 33 94 01/08/20 - 01/29/20 < 184 < 181 02/04/20 - 02/25/20 < 180 < 184 03/03/20 - 03/30/20 < 188 < 187 04/27/20 - 04/27/20 < 164 < 163 05/27/20 - 05/27/20 < 178 < 182 06/01/20 - 07/01/20 < 171 < 174 < 181 < 184 07/30/20 - 07/30/20 < 184 < 185 08/27/20 - 08/27/20 < 180 < 180 09/25/20 - 09/25/20 < 187 < 180 10/19/20 - 10/30/20 < 188 < 184 < 189 < 188 11/30/20 - 11/30/20 < 315 < 304 12/29/20 - 12/29/20 < 297 < 293 MEAN - - - -

C-1

Table C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 23 06/01/20 - 06/01/20 < 7 < 6 < 11 < 8 < 17 < 10 < 8 < 9 10/19/20 - 10/19/20 < 4 < 6 < 13 < 8 < 12 < 9 < 7 < 6 MEAN - - - - - - - -

24 06/01/20 - 06/01/20 < 8 < 6 < 12 < 9 < 15 < 11 < 10 < 8 10/20/20 - 10/20/20 < 7 < 6 < 13 < 6 < 12 < 12 < 7 < 7 MEAN - - - - - - - -

33 01/08/20 - 01/29/20 < 7 < 7 < 20 < 7 < 15 < 13 < 7 < 6 02/04/20 - 02/25/20 < 9 < 9 < 17 < 6 < 12 < 16 < 10 < 10 03/03/20 - 03/30/20 < 7 < 6 < 18 < 8 < 14 < 12 < 7 < 7 04/27/20 - 04/27/20 < 8 < 7 < 16 < 9 < 14 < 14 < 9 < 7 C-2 05/27/20 - 05/27/20 < 6 < 5 < 11 < 6 < 10 < 10 < 8 < 6 07/01/20 - 07/01/20 < 7 < 6 < 14 < 7 < 16 < 14 < 8 < 8 07/30/20 - 07/30/20 < 6 < 5 < 9 < 5 < 10 < 9 < 6 < 6 08/27/20 - 08/27/20 < 7 < 7 < 14 < 7 < 15 < 11 < 7 < 6 09/25/20 - 09/25/20 < 8 < 6 < 14 < 8 < 16 < 15 < 8 < 8 10/30/20 - 10/30/20 < 4 < 6 < 12 < 5 < 14 < 11 < 8 < 5 11/30/20 - 11/30/20 < 8 < 7 < 15 < 7 < 11 < 12 < 6 < 8 12/29/20 - 12/29/20 < 5 < 6 < 12 < 6 < 13 < 12 < 7 < 8 MEAN - - - - - - - -

94 01/08/20 - 01/29/20 < 7 < 8 < 19 < 9 < 15 < 14 < 8 < 7 02/04/20 - 02/25/20 < 7 < 7 < 13 < 8 < 11 < 11 < 8 < 6 03/03/20 - 03/30/20 < 8 < 6 < 15 < 8 < 14 < 12 < 9 < 8 04/27/20 - 04/27/20 < 5 < 5 < 9 < 6 < 12 < 9 < 7 < 5 05/27/20 - 05/27/20 < 5 < 6 < 14 < 8 < 11 < 12 < 7 < 7 07/01/20 - 07/01/20 < 8 < 8 < 17 < 11 < 17 < 11 < 9 < 9 07/30/20 - 07/30/20 < 5 < 6 < 15 < 11 < 14 < 11 < 7 < 7 08/27/20 - 08/27/20 < 6 < 6 < 11 < 7 < 11 < 10 < 6 < 6 09/25/20 - 09/25/20 < 8 < 8 < 21 < 6 < 18 < 13 < 10 < 10 10/30/20 - 10/30/20 < 7 < 7 < 12 < 6 < 14 < 14 < 8 < 7 11/30/20 - 11/30/20 < 6 < 7 < 16 < 6 < 12 < 12 < 9 < 8 12/29/20 - 12/29/20 < 6 < 5 < 9 < 7 < 11 < 11 < 6 < 7 MEAN - - - - - - - -

Table C-II.1 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 1N 1S 37 38 01/08/20 - 01/29/20 < 180 (1) < 181 < 184 02/04/20 - 02/26/20 < 178 (1) < 187 < 183 03/03/20 - 04/01/20 < 199 (1) < 185 < 187 04/01/20 - 04/30/20 < 162 (1) < 163 < 168 05/13/20 - 05/27/20 < 180 (1) < 180 < 183 06/03/20 - 07/01/20 < 185 (1) < 182 < 186 07/01/20 - 07/31/20 < 186 (1) < 182 < 185 08/05/20 - 08/31/20 < 180 (1) < 184 < 177 09/01/20 - 09/30/20 < 179 (1) < 183 < 180 10/01/20 - 10/30/20 < 176 (1) < 189 < 190 11/04/20 - 11/30/20 < 198 (1) < 320 < 320 12/01/20 - 12/29/20 < 312 (1) < 296 < 296 MEAN - - -

Table C-II.2 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 1N 1S 37 38 01/08/20 - 01/29/20 < 1.6 (1) 2.4 +/- 1.1 2.0 +/- 1.1 02/04/20 - 02/26/20 < 2.8 (1) 1.9 +/- 1.2 2.1 +/- 1.3 03/03/20 - 04/01/20 < 1.9 (1) < 1.4 1.6 +/- 1.0 04/01/20 - 04/30/20 4.5 +/- 1.2 (1) 3.5 +/- 1.1 2.2 +/- 1.1 05/13/20 - 05/27/20 < 1.6 (1) 1.8 +/- 1.1 2.0 +/- 1.1 06/03/20 - 07/01/20 < 1.8 (1) < 1.6 < 1.6 07/01/20 - 07/31/20 < 1.9 (1) 2.4 +/- 1.1 2.5 +/- 1.3 08/05/20 - 08/31/20 1.8 +/- 1.1 (1) 1.8 +/- 1.1 2.8 +/- 1.2 09/01/20 - 09/30/20 < 1.8 (1) 2.2 +/- 1.1 < 1.6 10/01/20 - 10/30/20 < 1.6 (1) 2.1 +/- 1.2 3.1 +/- 1.9 11/04/20 - 11/30/20 < 1.5 (1) 2.6 +/- 1.1 2.0 +/- 1.1 12/01/20 - 12/29/20 < 1.6 (1) < 1.7 2.9 +/- 1.3 MEAN +/- 2 STD DEV 3.1 +/- 3.8 2.3 +/- 1.1 2.3 +/- 0.9 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3

Table C-II.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 1N 01/09/20 - 01/29/20 < 6 < 6 < 12 < 7 < 14 < 10 < 7 < 6 02/05/20 - 02/26/20 < 9 < 8 < 15 < 9 < 17 < 14 < 9 < 8 03/03/20 - 04/01/20 < 5 < 5 < 8 < 5 < 9 < 7 < 5 < 5 04/01/20 - 04/14/20 < 3 < 3 < 7 < 3 < 7 < 6 < 3 < 3 05/13/20 - 05/13/20 < 2 < 2 < 5 < 2 < 4 < 4 < 2 < 2 06/03/20 - 06/03/20 < 2 < 2 < 5 < 1 < 3 < 4 < 2 < 2 07/01/20 - 07/01/20 < 2 < 3 < 7 < 2 < 5 < 5 < 2 < 2 08/05/20 - 08/05/20 < 3 < 2 < 6 < 3 < 5 < 5 < 3 < 3 09/01/20 - 09/01/20 < 3 < 3 < 7 < 3 < 5 < 6 < 2 < 3 10/01/20 - 10/01/20 < 5 < 6 < 12 < 6 < 12 < 9 < 6 < 6 11/04/20 - 11/04/20 < 6 < 6 < 13 < 6 < 15 < 10 < 7 < 6 12/01/20 - 12/01/20 < 6 < 8 < 14 < 7 < 7 < 12 < 8 < 6 MEAN - - - - - - - -

1S (1) 37 01/08/20 - 01/27/20 < 8 < 7 < 14 < 7 < 15 < 13 < 9 < 8 02/04/20 - 02/25/20 < 6 < 5 < 13 < 9 < 13 < 12 < 8 < 8 03/03/20 - 03/30/20 < 7 < 8 < 15 < 9 < 15 < 10 < 5 < 8 C-4 04/27/20 - 04/27/20 < 6 < 6 < 12 < 8 < 12 < 9 < 7 < 5 05/27/20 - 05/27/20 < 5 < 5 < 10 < 5 < 11 < 10 < 6 < 5 07/01/20 - 07/01/20 < 7 < 7 < 14 < 7 < 14 < 11 < 8 < 8 07/31/20 - 07/31/20 < 2 < 2 < 4 < 2 < 4 < 3 < 2 < 2 08/27/20 - 08/27/20 < 4 < 5 < 10 < 5 < 9 < 8 < 6 < 5 09/25/20 - 09/25/20 < 7 < 7 < 17 < 7 < 15 < 13 < 10 < 8 10/30/20 - 10/30/20 < 7 < 7 < 15 < 7 < 15 < 12 < 7 < 7 11/30/20 - 11/30/20 < 7 < 7 < 15 < 7 < 18 < 11 < 8 < 6 12/29/20 - 12/29/20 < 7 < 8 < 13 < 9 < 17 < 13 < 5 < 7 MEAN - - - - - - - -

38 01/15/20 - 01/29/20 < 5 < 4 < 11 < 5 < 14 < 10 < 6 < 5 02/05/20 - 02/25/20 < 4 < 4 < 8 < 4 < 9 < 8 < 4 < 4 03/03/20 - 03/30/20 < 5 < 4 < 13 < 7 < 11 < 13 < 6 < 6 04/30/20 - 04/30/20 < 5 < 6 < 11 < 6 < 10 < 10 < 5 < 6 05/27/20 - 05/27/20 < 4 < 5 < 13 < 7 < 11 < 11 < 6 < 7 07/01/20 - 07/01/20 < 6 < 6 < 11 < 6 < 14 < 10 < 7 < 5 07/30/20 - 07/30/20 < 7 < 7 < 16 < 7 < 14 < 12 < 8 < 8 08/31/20 - 08/31/20 < 6 < 7 < 14 < 7 < 12 < 11 < 9 < 7 09/30/20 - 09/30/20 < 5 < 5 < 8 < 4 < 11 < 11 < 5 < 5 10/30/20 - 10/30/20 < 7 < 7 < 12 < 8 < 14 < 12 < 6 < 5 11/30/20 - 11/30/20 < 8 < 6 < 13 < 7 < 15 < 9 < 7 < 6 12/29/20 - 12/29/20 < 7 < 6 < 11 < 9 < 15 < 14 < 5 < 6 MEAN - - - - - - - -

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-III.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD MW-24-3A W-3C 01/29/20 - 01/29/20 < 185 < 194 05/21/20 - 05/21/20 < 173 < 174 08/19/20 - 08/19/20 < 152 < 154 10/14/20 - 10/14/20 < 184 < 187 MEAN - -

C-5

Table C-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 MW-24-3A 01/29/20 - 01/29/20 < 5 < 6 < 14 < 4 < 15 < 10 < 6 < 5 05/21/20 - 05/21/20 < 7 < 8 < 15 < 7 < 17 < 13 < 7 < 8 08/19/20 - 08/19/20 < 8 < 7 < 7 < 7 < 18 < 11 < 9 < 8 10/14/20 - 10/14/20 < 8 < 6 < 14 < 8 < 15 < 12 < 7 < 7 MEAN - - - - - - - -

W-3C 01/29/20 - 01/29/20 < 7 < 6 < 11 < 7 < 17 < 13 < 7 < 7 05/21/20 - 05/21/20 < 7 < 7 < 13 < 8 < 16 < 12 < 9 < 10 08/19/20 - 08/19/20 < 7 < 8 < 15 < 9 < 18 < 12 < 8 < 8 10/14/20 - 10/14/20 < 4 < 6 < 15 < 7 < 14 < 11 < 8 < 6 MEAN - - - - - - - -

C-6

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 33 PREDATOR 06/01/20 2531 +/- 912 < 48 < 59 < 118 < 72 < 108 < 58 < 62 06/01/20 3740 +/- 867 < 60 < 44 < 93 < 51 < 107 < 40 < 57 06/01/20 4203 +/- 1108 < 72 < 74 < 137 < 70 < 147 < 70 < 63 10/19/20 3546 +/- 1000 < 33 < 45 < 106 < 72 < 109 < 63 < 55 10/19/20 4533 +/- 1156 < 74 < 66 < 154 < 70 < 114 < 73 < 76 10/19/20 5972 +/- 1313 < 68 < 82 < 164 < 100 < 162 < 89 < 68 10/19/20 3520 +/- 1202 < 66 < 65 < 108 < 93 < 130 < 64 < 84 10/19/20 3143 +/- 1061 < 68 < 70 < 102 < 62 < 131 < 75 < 81 MEAN +/- 2 STD DEV 3899 +/- 2074 - - - - - - -

33 BOTTOM FEEDER 06/01/20 3515 +/- 985 < 49 < 50 < 137 < 63 < 126 < 49 < 60 10/19/20 4112 +/- 1006 < 49 < 56 < 134 < 53 < 114 < 59 < 58 C-7 MEAN +/- 2 STD DEV 3814 +/- 844 - - - - - - -

93 PREDATOR 06/03/20 4142 +/- 1073 < 74 < 66 < 124 < 75 < 141 < 82 < 81 10/19/20 5466 +/- 1356 < 80 < 77 < 169 < 88 < 217 < 86 < 95 10/19/20 3258 +/- 1031 < 33 < 52 < 114 < 30 < 113 < 49 < 59 MEAN +/- 2 STD DEV 4289 +/- 2223 - - - - - - -

93 (1)

BOTTOMFEEDER 94 (1)

PREDATOR 94 (1)

BOTTOMFEEDER THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-IV.2 CONCENTRATIONS OF GAMMA EMITTERS IN CLAM AND CRAB SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 23 Clams 06/01/20 1825 +/- 1005 < 84 < 70 < 131 < 64 < 144 < 83 < 88 10/19/20 2657 +/- 872 < 66 < 58 < 121 < 56 < 105 < 54 < 42 MEAN +/- 2 STD DEV 2241 +/- 1177 - - - - - - -

24 Clams 06/01/20 1540 +/- 987 < 81 < 84 < 157 < 88 < 169 < 99 < 81 10/20/20 1743 +/- 755 < 53 < 37 < 130 < 30 < 109 < 54 < 44 MEAN +/- 2 STD DEV 1642 +/- 287 - - - - - - -

94 C-8 Clams 06/03/20 1885 +/- 854 < 69 < 61 < 136 < 51 < 148 < 73 < 65 10/21/20 1773 +/- 816 < 48 < 53 < 108 < 50 < 117 < 60 < 52 MEAN +/- 2 STD DEV 1829 +/- 158 - - - - - - -

33 Crabs 10/19/20 2063 +/- 796 < 59 < 25 < 103 < 28 < 98 < 63 < 54 MEAN +/- 2 STD DEV 2063 +/- 0 - - - - - - -

93 Crabs (1)

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-228 23 06/01/20 < 780 2051 +/- 865 < 76 < 88 < 79 < 90 < 93 < 1872 167 +/- 110 10/19/20 < 465 5679 +/- 1068 < 54 < 49 < 57 < 63 < 53 < 980 282 +/- 80 MEAN +/- 2 STD DEV - 3865 +/- 5131 - - - - - - 225 +/- 162 24 06/01/20 < 1012 8501 +/- 1707 < 121 < 112 < 127 < 145 < 121 4319 +/- 1838 875 +/- 197 10/20/20 < 382 9138 +/- 989 < 51 < 45 < 52 < 55 < 45 < 1054 426 +/- 87 MEAN +/- 2 STD DEV - 8820 +/- 901 - - - - - 4319 +/- 0 650 +/- 635 33 06/02/20 < 799 7560 +/- 1356 < 104 < 112 < 139 < 116 < 130 < 2492 507 +/- 171 10/20/20 < 207 615 +/- 339 < 29 < 28 < 24 < 33 < 29 < 577 108 +/- 38 C-9 MEAN +/- 2 STD DEV - 4088 +/- 9821 - - - - - 307 +/- 565 94 06/02/20 < 1300 19230 +/- 3085 < 145 < 121 < 165 < 130 < 145 < 2807 693 +/- 195 10/20/20 < 345 13530 +/- 1065 < 44 < 41 < 42 < 54 < 46 < 902 468 +/- 69 MEAN +/- 2 STD DEV - 16380 +/- 8061 - - - - - - 581 +/- 319 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-VI.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD 20 66 111 71 72 73 3 C 01/02/20 - 01/09/20 12 +/- 4 11 +/- 4 9 +/- 4 8 +/- 4 10 +/- 5 12 +/- 5 13 +/- 5 11 +/- 4 01/09/20 - 01/15/20 10 +/- 5 8 +/- 5 < 7 7 +/- 5 9 +/- 5 < 7 10 +/- 5 < 8 01/15/20 - 01/22/20 12 +/- 5 15 +/- 5 15 +/- 5 17 +/- 5 17 +/- 5 14 +/- 5 13 +/- 5 16 +/- 5 01/22/20 - 01/29/20 10 +/- 4 14 +/- 5 11 +/- 4 10 +/- 4 9 +/- 4 11 +/- 4 10 +/- 4 15 +/- 5 01/29/20 - 02/05/20 7 +/- 4 12 +/- 5 11 +/- 4 11 +/- 4 9 +/- 5 10 +/- 4 10 +/- 4 10 +/- 5 02/05/20 - 02/12/20 9 +/- 4 7 +/- 4 < 5 7 +/- 4 < 6 6 +/- 4 < 6 10 +/- 4 02/12/20 - 02/19/20 14 +/- 5 10 +/- 4 11 +/- 4 11 +/- 5 < 7 10 +/- 4 7 +/- 4 14 +/- 5 02/19/20 - 02/26/20 16 +/- 5 17 +/- 5 11 +/- 5 9 +/- 5 15 +/- 5 8 +/- 5 11 +/- 5 14 +/- 5 02/26/20 - 03/04/20 < 7 9 +/- 5 (1) 12 +/- 5 8 +/- 5 9 +/- 5 9 +/- 5 13 +/- 5 03/04/20 - 03/11/20 12 +/- 5 13 +/- 5 11 +/- 5 11 +/- 5 9 +/- 4 < 6 11 +/- 5 10 +/- 4 03/11/20 - 03/18/20 7 +/- 4 8 +/- 5 10 +/- 5 8 +/- 4 10 +/- 5 10 +/- 5 11 +/- 5 10 +/- 5 03/18/20 - 03/26/20 12 +/- 4 14 +/- 4 14 +/- 4 13 +/- 4 15 +/- 4 6 +/- 4 10 +/- 4 15 +/- 4 03/26/20 - 04/01/20 9 +/- 5 11 +/- 6 9 +/- 5 < 8 < 8 < 8 13 +/- 6 10 +/- 5 04/01/20 - 04/09/20 11 +/- 4 13 +/- 4 12 +/- 4 13 +/- 4 10 +/- 4 9 +/- 4 (1) 14 +/- 4 04/09/20 - 04/22/20 14 +/- 3 13 +/- 3 11 +/- 3 15 +/- 3 14 +/- 3 11 +/- 3 (1) (1) 04/22/20 - 05/06/20 7 +/- 2 5 +/- 2 7 +/- 2 8 +/- 2 8 +/- 2 8 +/- 2 (1) 7 +/- 2 05/06/20 - 05/20/20 10 +/- 3 9 +/- 3 11 +/- 3 (1) 11 +/- 3 9 +/- 3 (1) 12 +/- 3 05/20/20 - 06/04/20 5 +/- 2 6 +/- 2 6 +/- 2 7 +/- 2 7 +/- 2 5 +/- 2 (1) 10 +/- 2 06/04/20 - 06/18/20 11 +/- 3 < 3 9 +/- 3 11 +/- 3 9 +/- 3 8 +/- 3 (1) 12 +/- 3 06/18/20 - 07/01/20 13 +/- 3 17 +/- 3 12 +/- 3 14 +/- 3 11 +/- 3 11 +/- 3 (1) 11 +/- 3 07/01/20 - 07/15/20 11 +/- 3 12 +/- 3 10 +/- 3 10 +/- 3 11 +/- 3 9 +/- 3 (1) 12 +/- 3 07/15/20 - 07/30/20 18 +/- 3 19 +/- 3 19 +/- 3 18 +/- 3 19 +/- 3 15 +/- 3 (1) 18 +/- 3 07/30/20 - 08/12/20 13 +/- 3 14 +/- 3 15 +/- 3 12 +/- 3 13 +/- 3 12 +/- 3 (1) 14 +/- 3 08/12/20 - 08/27/20 18 +/- 3 21 +/- 3 17 +/- 3 19 +/- 3 19 +/- 3 16 +/- 3 (1) 20 +/- 3 08/27/20 - 09/09/20 12 +/- 3 (1) 13 +/- 3 11 +/- 3 17 +/- 3 11 +/- 3 (1) 13 +/- 3 09/09/20 - 09/22/20 11 +/- 3 12 +/- 4 9 +/- 3 12 +/- 3 11 +/- 3 9 +/- 3 (1) 13 +/- 3 09/22/20 - 10/06/20 17 +/- 3 18 +/- 3 20 +/- 3 14 +/- 3 19 +/- 3 13 +/- 3 (1) 21 +/- 3 10/06/20 - 10/21/20 15 +/- 3 13 +/- 3 19 +/- 3 15 +/- 3 18 +/- 3 14 +/- 3 (1) 18 +/- 3 10/21/20 - 11/05/20 10 +/- 2 10 +/- 2 9 +/- 2 9 +/- 2 8 +/- 2 11 +/- 2 (1) 9 +/- 2 11/05/20 - 11/18/20 17 +/- 3 17 +/- 3 19 +/- 3 19 +/- 3 18 +/- 3 15 +/- 4 (1) 24 +/- 4 11/18/20 - 12/03/20 13 +/- 3 12 +/- 3 16 +/- 3 13 +/- 3 15 +/- 3 12 +/- 3 (1) 15 +/- 3 12/03/20 - 12/15/20 12 +/- 3 11 +/- 3 12 +/- 3 9 +/- 3 12 +/- 3 9 +/- 3 (1) 12 +/- 3 12/15/20 - 12/29/20 11 +/- 3 8 +/- 2 10 +/- 3 10 +/- 3 12 +/- 3 11 +/- 3 (1) 12 +/- 3 MEAN +/- 2 STD DEV 12 +/- 6 12 +/- 8 12 +/- 7 12 +/- 7 12 +/- 8 10 +/- 5 11 +/- 4 13 +/- 7 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-10

Table C-VI.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - INTERMEDIATE DISTANCE LOCATIONS GROUP III - CONTROL LOCATIONS COLLECTION MEAN COLLECTION MEAN COLLECTION MEAN PERIOD MIN MAX +/- 2SD PERIOD MIN MAX +/- 2SD PERIOD MIN MAX +/- 2SD 01/02/20 - 01/29/20 8 15 11 +/- 5 01/02/20 - 01/29/20 7 17 11 +/- 7 01/02/20 - 01/29/20 10 16 13 +/- 5 01/29/20 - 02/26/20 7 17 11 +/- 6 01/29/20 - 02/26/20 6 15 10 +/- 5 01/29/20 - 02/26/20 7 14 11 +/- 5 02/26/20 - 04/01/20 7 14 11 +/- 4 02/26/20 - 03/26/20 6 15 10 +/- 5 02/26/20 - 04/01/20 9 15 11 +/- 4 04/01/20 - 05/06/20 5 14 10 +/- 6 04/01/20 - 05/06/20 8 15 11 +/- 5 04/01/20 - 05/06/20 7 14 10 +/- 10 05/06/20 - 06/04/20 5 11 8 +/- 5 05/06/20 - 06/04/20 5 11 8 +/- 4 05/06/20 - 06/04/20 10 12 11 +/- 2 06/04/20 - 07/01/20 9 17 12 +/- 5 06/04/20 - 07/01/20 8 14 11 +/- 4 06/04/20 - 07/01/20 11 12 11 +/- 1 07/01/20 - 07/30/20 10 19 15 +/- 8 07/01/20 - 07/30/20 9 19 14 +/- 8 07/01/20 - 07/30/20 12 18 15 +/- 9 07/30/20 - 08/27/20 13 21 16 +/- 6 07/30/20 - 08/27/20 12 19 15 +/- 7 07/30/20 - 08/27/20 14 20 17 +/- 8 08/27/20 - 09/22/20 9 13 11 +/- 3 08/27/20 - 09/22/20 9 17 12 +/- 5 08/27/20 - 09/22/20 13 13 13 +/- 0 C-11 09/22/20 - 11/05/20 9 20 14 +/- 9 09/22/20 - 11/05/20 8 19 13 +/- 7 09/22/20 - 11/05/20 9 21 16 +/- 12 11/05/20 - 12/03/20 12 19 16 +/- 5 11/05/20 - 12/03/20 12 19 15 +/- 5 11/05/20 - 12/03/20 15 24 20 +/- 13 12/03/20 - 12/29/20 8 12 11 +/- 3 12/03/20 - 12/29/20 9 12 10 +/- 2 12/03/20 - 12/29/20 12 12 12 +/- 1 01/02/20 - 12/29/20 5 21 12 +/- 7 01/02/20 - 12/29/20 5 19 11 +/- 7 01/02/20 - 12/29/20 7 24 13 +/- 7 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-VI.3 CONCENTRATIONS OF STRONTIUM IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD SR-89 SR-90 3 (1) 01/02/20 - 04/01/20 < 7 < 5 MEAN - -

20 01/02/20 - 04/01/20 < 7 < 6 04/01/20 - 07/01/20 < 7 < 6 07/01/20 - 09/22/20 < 8 < 7 09/22/20 - 12/29/20 < 6 MEAN - -

66 01/02/20 - 04/01/20 < 9 < 5 04/01/20 - 07/01/20 < 8 < 9 07/01/20 - 09/22/20 < 9 < 8 09/22/20 - 12/29/20 < 5 MEAN - -

71 01/02/20 - 04/01/20 < 8 < 6 04/01/20 - 07/01/20 < 7 < 10 07/01/20 - 09/22/20 < 8 < 8 09/22/20 - 12/29/20 < 6 MEAN - -

72 01/02/20 - 04/01/20 < 7 < 6 04/01/20 - 07/01/20 < 7 < 5 07/01/20 - 09/22/20 < 8 < 8 09/22/20 - 12/29/20 < 5 MEAN - -

73 01/02/20 - 04/01/20 < 8 < 7 04/01/20 - 07/01/20 < 8 < 8 07/01/20 - 09/22/20 < 7 < 8 09/22/20 - 12/29/20 < 5 MEAN - -

111 01/02/20 - 04/01/20 < 7 < 7 04/01/20 - 07/01/20 < 8 < 10 07/01/20 - 09/22/20 < 8 < 8 09/22/20 - 12/29/20 < 6 MEAN - -

C 01/02/20 - 04/01/20 < 6 < 5 04/01/20 - 07/01/20 < 8 < 7 07/01/20 - 09/22/20 < 5 < 8 09/22/20 - 12/29/20 < 5 MEAN - -

C-12

Table C-VI.4 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 3 (1) 01/02/20 - 04/01/20 56 +/- 15 < 2 < 1 < 2 < 2 < 2 MEAN +/- 2 STD DEV 56 +/- 0 - - - - -

20 01/02/20 - 04/01/20 58 +/- 14 < 2 < 2 < 2 < 2 < 1 04/01/20 - 07/01/20 61 +/- 17 < 2 < 2 < 2 < 2 < 2 07/01/20 - 09/22/20 53 +/- 20 < 2 < 2 < 2 < 2 < 2 09/22/20 - 12/29/20 48 +/- 16 < 1 < 1 < 2 < 1 < 2 MEAN +/- 2 STD DEV 55 +/- 12 - - - - -

66 01/02/20 - 04/01/20 46 +/- 15 < 2 < 2 < 2 < 2 < 2 04/01/20 - 07/01/20 50 +/- 24 < 3 < 3 < 2 < 3 < 3 07/01/20 - 09/22/20 55 +/- 36 < 6 < 7 < 6 < 6 < 5 09/22/20 - 12/29/20 39 +/- 18 < 2 < 2 < 2 < 2 < 2 MEAN +/- 2 STD DEV 48 +/- 13 - - - - -

71 01/02/20 - 04/01/20 48 +/- 16 < 2 < 2 < 1 < 2 < 1 04/01/20 - 07/01/20 64 +/- 15 < 2 < 3 < 2 < 2 < 2 07/01/20 - 09/22/20 65 +/- 19 < 3 < 3 < 4 < 3 < 3 09/22/20 - 12/29/20 45 +/- 14 < 2 < 2 < 2 < 3 < 2 MEAN +/- 2 STD DEV 56 +/- 21 - - - - -

72 01/02/20 - 04/01/20 55 +/- 18 < 2 < 2 < 3 < 2 < 2 04/01/20 - 07/01/20 59 +/- 15 < 1 < 2 < 3 < 1 < 2 07/01/20 - 09/22/20 61 +/- 26 < 2 < 3 < 2 < 3 < 2 09/22/20 - 12/29/20 58 +/- 15 < 3 < 2 < 3 < 2 < 2 MEAN +/- 2 STD DEV 58 +/- 5 - - - - -

73 01/02/20 - 04/01/20 47 +/- 15 < 2 < 2 < 3 < 2 < 2 04/01/20 - 07/01/20 59 +/- 17 < 1 < 2 < 2 < 3 < 2 07/01/20 - 09/22/20 48 +/- 29 < 3 < 4 < 4 < 3 < 3 09/22/20 - 12/29/20 48 +/- 15 < 2 < 2 < 2 < 1 < 2 MEAN +/- 2 STD DEV 50 +/- 12 - - - - -

111 01/02/20 - 04/01/20 47 +/- 19 < 3 < 2 < 3 < 2 < 2 04/01/20 - 07/01/20 66 +/- 18 < 2 < 2 < 2 < 1 < 2 07/01/20 - 09/22/20 83 +/- 22 < 1 < 2 < 2 < 3 < 2 09/22/20 - 12/29/20 58 +/- 16 < 2 < 2 < 2 < 1 < 2 MEAN +/- 2 STD DEV 63 +/- 31 - - - - -

C 01/02/20 - 04/01/20 59 +/- 13 < 2 < 2 < 3 < 2 < 2 04/01/20 - 07/01/20 72 +/- 32 < 3 < 4 < 3 < 3 < 4 07/01/20 - 09/22/20 76 +/- 25 < 3 < 3 < 2 < 3 < 3 09/22/20 - 12/29/20 52 +/- 13 < 2 < 2 < 3 < 2 < 2 MEAN +/- 2 STD DEV 65 +/- 23 - - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-13

Table C-VII.1 CONCENTRATIONS OF I-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD 20 66 111 71 72 73 3 C 12/26/19 - 01/09/20 < 23 < 23 < 22 < 23 < 19 < 10 < 21 < 22 01/09/20 - 01/15/20 < 58 < 59 < 56 < 58 < 23 < 25 < 22 < 20 01/15/20 - 01/22/20 < 30 < 31 < 29 < 30 < 45 < 17 < 42 < 45 01/22/20 - 01/29/20 < 43 < 43 < 41 < 42 < 17 < 18 < 31 < 33 01/29/20 - 02/05/20 < 36 < 36 < 34 < 36 < 31 < 30 < 30 < 22 02/05/20 - 02/12/20 < 9 < 18 < 17 < 17 < 20 < 18 < 19 < 17 02/12/20 - 02/19/20 < 27 < 27 < 26 < 27 < 24 < 14 < 34 < 36 MEAN - - - - - - - -

C-14

Table C-VIII.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Sr-89 Sr-90 Be-7 K-40 Cs-134 Cs-137 35 (1)

Cabbage 06/16/20 < 19 10.0 +/- 2.7 < 357 2427 +/- 628 < 47 < 46 Collards 06/16/20 < 21 < 5.0 < 419 4844 +/- 891 < 48 < 44 Kale 06/16/20 < 20 < 4.8 < 335 2632 +/- 688 < 43 < 40 Cabbage 07/22/20 < 18 < 3.5 < 153 1563 +/- 517 < 21 < 20 Collards 07/22/20 < 16 6.2 +/- 2.5 < 157 2179 +/- 341 < 19 < 18 Kale 07/22/20 < 20 < 3.4 < 163 3865 +/- 409 < 20 < 18 Cabbage 08/31/20 < 22 < 3.1 < 247 1379 +/- 455 < 25 < 25 Collards 08/31/20 < 19 < 4.2 732 +/- 340 4234 +/- 685 < 28 < 39 Cabbage 09/23/20 < 19 5.6 +/- 2.7 < 346 2712 +/- 680 < 36 < 36 Collards 09/23/20 < 20 5.4 +/- 2.5 < 410 3412 +/- 806 < 42 < 46 Cabbage 10/26/20 < 19 7.4 +/- 2.3 < 299 2113 +/- 527 < 38 < 36 Collards 10/26/20 < 21 < 3.2 452 +/- 172 2781 +/- 418 < 24 < 24 MEAN +/- 2 STD DEV - 6.9 +/- 3.8 592 +/- 396 2845 +/- 2115 - -

C-15 36 (Control)

Collards 06/16/20 < 20 5.4 +/- 2.4 < 194 4447 +/- 579 < 32 < 25 Kale 06/16/20 < 18 < 4.4 < 368 3520 +/- 871 < 47 < 41 Rape 06/16/20 < 22 4.5 +/- 2.2 < 223 4862 +/- 497 < 29 < 24 Cabbage 07/22/20 < 21 < 4.4 < 137 1583 +/- 356 < 21 < 24 Collards 07/22/20 < 20 5.6 +/- 2.2 < 228 4643 +/- 585 < 25 < 27 Kale 07/22/20 < 22 11.5 +/- 2.6 < 244 4263 +/- 657 < 32 < 26 Mustard Greens 08/31/20 < 20 < 4.4 367 +/- 277 3799 +/- 784 < 39 < 28 Collards 08/31/20 < 19 < 3.8 < 262 5287 +/- 651 < 29 < 28 Kale 08/31/20 < 25 < 4.6 < 265 2944 +/- 640 < 32 < 37 Cabbage 09/23/20 < 20 11.2 +/- 2.6 < 227 1899 +/- 425 < 22 < 23 Collards 09/23/20 < 21 14.2 +/- 3.6 < 238 4036 +/- 595 < 32 < 28 Kale 09/23/20 < 16 5.4 +/- 2.4 < 249 4448 +/- 589 < 28 < 29 Cabbage 10/26/20 < 22 < 4.0 < 199 2251 +/- 427 < 27 < 24 Collards 10/26/20 < 19 6.0 +/- 2.2 344 +/- 179 3792 +/- 481 < 24 < 23 Swiss Chard 10/26/20 < 24 4.8 +/- 2.6 830 +/- 280 4728 +/- 547 < 26 < 23 MEAN +/- 2 STD DEV - 7.6 +/- 7.3 514 +/- 549 3767 +/- 2252 - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-VIII.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Sr-89 Sr-90 Be-7 K-40 Cs-134 Cs-137 66 (1)

Cabbage 06/16/20 < 13 < 3.9 < 404 4444 +/- 909 < 48 < 53 Collards 06/16/20 < 21 < 3.8 < 239 4375 +/- 668 < 35 < 28 Kale 06/16/20 < 24 4.4 +/- 2.8 < 327 5112 +/- 846 < 54 < 39 Cabbage 07/22/20 < 18 < 3.1 < 306 2381 +/- 585 < 36 < 41 Collards 07/22/20 < 20 5.7 +/- 2.4 < 384 3737 +/- 697 < 36 < 29 Kale 07/22/20 < 19 5.6 +/- 2.7 < 426 5189 +/- 813 < 38 < 34 Cabbage 08/31/20 < 21 < 4.1 < 477 2875 +/- 655 < 38 < 40 Collards 08/31/20 < 23 < 4.4 516 +/- 312 2926 +/- 675 < 38 < 41 Kale 08/31/20 < 21 5.5 +/- 2.1 < 448 3745 +/- 754 < 42 < 51 Collards 09/23/20 < 19 < 4.3 < 326 3464 +/- 611 < 31 < 30 MEAN +/- 2 STD DEV - 5.3 +/- 1.2 516 +/- 0 3825 +/- 1902 - -

C-16 115 Cabbage 06/16/20 < 16 7.2 +/- 2.4 < 232 2938 +/- 562 < 33 < 40 Collards 06/16/20 < 18 9.2 +/- 2.8 < 328 4285 +/- 836 < 33 < 44 Kale 06/16/20 < 24 10.7 +/- 2.9 < 328 2939 +/- 608 < 39 < 38 Cabbage 07/22/20 < 19 8.0 +/- 2.6 < 301 2727 +/- 541 < 28 < 29 Collards 07/22/20 < 17 14.4 +/- 2.9 < 374 1806 +/- 590 < 34 < 42 Kale 07/22/20 < 13 11.4 +/- 3.2 < 356 4313 +/- 767 < 35 < 47 Cabbage 08/31/20 < 23 11.6 +/- 3.2 < 427 2062 +/- 578 < 48 < 44 Collards 08/31/20 < 19 < 4.0 < 425 3248 +/- 676 < 39 < 41 Kale 08/31/20 < 22 5.6 +/- 2.7 < 494 4017 +/- 848 < 60 < 46 Cabbage 09/23/20 < 19 4.6 +/- 2.5 < 252 1745 +/- 658 < 39 < 38 Collards 09/23/20 < 17 5.6 +/- 2.7 < 403 2773 +/- 709 < 42 < 43 Kale 09/23/20 < 20 < 3.5 < 322 3404 +/- 738 < 47 < 41 Cabbage 10/26/20 < 16 7.3 +/- 2.8 < 257 1711 +/- 468 < 34 < 34 Collards 10/26/20 < 22 8.2 +/- 2.5 782 +/- 243 2730 +/- 463 < 27 < 31 Kale 10/26/20 < 21 6.9 +/- 2.5 771 +/- 330 3383 +/- 778 < 46 < 49 MEAN +/- 2 STD DEV - 8.5 +/- 5.7 776 +/- 15 2939 +/- 1730 - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-IX.1 QUARTERLY OSLD RESULTS FOR OYSTER CREEK GENERATING STATION, 2020(1)

RESULTS IN UNITS OF MILLIREM/STD. QUARTER +/- 2 STANDARD DEVIATION STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC 1 22.9 +/- 3.6 22.5 25.2 20.8 23.2 6 21.6 +/- 3.6 22.3 (1) 19.5 22.9 8 21.1 +/- 4.5 21.1 24.1 18.7 20.5 9 20.7 +/- 2.3 20.6 22.1 19.3 20.7 C 22.2 +/- 3.6 22.5 24.25 19.9 22.3 22 24.7 +/- 4.3 24.4 27.0 21.9 25.6 51 24.3 +/- 5.6 23.0 28.2 21.8 24.1 52 25.3 +/- 4.7 25.3 27.8 22.2 26.1 53 23.5 +/- 4.8 23.4 26.6 20.7 23.3 54 20.5 +/- 4.4 19.2 23.6 18.7 20.4 55 28.9 +/- 4.9 28.6 31.7 25.7 29.5 56 26.1 +/- 4.8 25.3 29.3 23.5 26.3 57 21.5 +/- 3.2 21.7 22.4 19.3 22.8 58 20.4 +/- 3.7 21.6 21.8 17.8 20.6 59 22.8 +/- 4.2 21.7 26.0 21.6 22.0 61 21.6 +/- 2.6 20.5 23.4 20.8 21.7 62 22.4 +/- 4.2 22.5 24.7 19.6 22.8 63 21.9 +/- 2.7 21.6 23.3 20.1 22.6 64 22.4 +/- 3.7 21.9 24.6 20.2 23.0 65 22.8 +/- 3.6 21.4 24.8 21.2 23.9 66 21.0 +/- 2.8 21.3 22.4 19.1 21.0 68 20.1 +/- 2.0 19.9 21.2 18.8 20.5 71 21.6 +/- 2.7 21.2 23.5 20.4 21.3 72 22.2 +/- 4.1 21.4 25.1 20.2 22.1 73 21.3 +/- 4.4 21.1 22.8 18.4 23.1 74 21.9 +/- 2.7 21.6 23.9 20.8 21.4 75 23.3 +/- 4.1 23.1 25.9 20.8 23.5 78 22.4 +/- 3.5 22.6 24.6 20.3 22.2 79 22.9 +/- 3.8 22.9 25.0 20.4 23.2 81 22.5 +/- 3.7 22.6 24.3 19.9 23.2 98 20.7 +/- 4.1 19.6 23.5 18.8 21.1 99 20.3 +/- 3.9 20.0 22.6 17.9 20.8 T1 22.3 +/- 3.7 23.1 24.2 19.9 22.0 100 21.6 +/- 4.1 20.8 24.5 19.7 21.6 101 21.3 +/- 3.8 21.2 23.2 18.8 22.1 102 22.6 +/- 3.7 22.6 23.8 20.0 23.9 103 21.9 +/- 3.7 21.6 24.1 19.6 22.5 104 21.6 +/- 1.3 21.7 22.3 20.8 21.8 106 20.2 +/- 2.9 20.9 22.0 18.6 19.6 107 21.1 +/- 2.2 20.7 22.4 19.8 21.4 109 22.5 +/- 4.2 21.5 25.1 20.2 23.1 110 20.9 +/- 3.5 20.5 22.6 18.6 21.9 112 24.3 +/- 3.3 24.1 26.5 22.5 24.2 113 21.4 +/- 2.7 21.6 23.0 19.6 21.4 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (1)

Note: There are two (2) OSLD's posted at each indicator station for redundancy and data recovery. In reporting results, the average of the gross mean for the two readings is reported. There are four (4) single OSLD's posted at Control Station C and the average of the gross mean for the four readings is reported.

C-17

TABLE C-IX.2 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, INTERMEDIATE, SPECIAL INTEREST, AND CONTROL LOCATIONS FOR OYSTER CREEK GENERATING STATION, 2020(1)

RESULTS IN UNITS OF MILLIREM PER STANDARD QUARTER +/- 2 STANDARD DEVIATION STANDARD DEVIATIONS OF THE STATION DATA COLLECTION SITE BOUNDARY INTERMEDIATE SPECIAL INTEREST CONTROL PERIOD +/- 2 S.D. +/- 2 S.D. +/- 2 S.D. +/- 2 S.D.

JAN-MAR 22.6 +/- 4.1 21.5 +/- 2.4 21.7 +/- 1.5 22.5 +/- 0.0 APR-JUN 25.1 +/- 5.2 23.7 +/- 2.8 24.3 +/- 1.6 24.3 +/- 0.0 JUL-SEP 20.7 +/- 3.7 19.6 +/- 1.8 20.2 +/- 0.5 19.9 +/- 0.0 OCT-DEC 23.1 +/- 4.4 22.0 +/- 2.8 22.2 +/- 2.0 22.3 +/- 0.0 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF MILLIREM PER STANDARD QUARTER +/- 2 STANDARD DEVIATION SAMPLES PERIOD PERIOD PERIOD MEAN LOCATION ANALYZED MINIMUM MAXIMUM +/- 2 S.D.

C-18 SITE BOUNDARY 159 17.8 31.7 22.8 +/- 5.3 INTERMEDIATE 182 17.9 27.0 21.7 +/- 3.8 SPECIAL INTEREST 24 19.9 25.1 22.1 +/- 3.3 CONTROL 16 18.7 25.4 22.2 +/- 3.6 SITE BOUNDARY STATIONS - 1, 51, 52, 53, 54, 55, 56, 57, 58, 59, 61, 62, 63, 64, 65, 66, 112, 113, T1 INTERMEDIATE STATIONS - 6, 8, 9, 22, 68, 73, 74, 75, 78, 79, 98, 99, 100, 101, 102, 103, 104, 106, 107, 109, 110 SPECIAL INTEREST STATIONS - 71, 72, 81 CONTROL STATIONS - C (1)

Note: There are two (2) OSLD's posted at each indicator station for redundancy and data recovery. In reporting results, the average of the gross mean for the two readings is reported. There are four (4) single OSLD's posted at Control Station C and the average of the gross mean for the four readings is reported.

FIGURE C-1 MEAN COBALT-60 CONCENTRATION IN CLAMS OYSTER CREEK GENERATING STATION, 1983 - 2020 20 INDICATOR STATION BACKGROUND STATION 15 C-19 10 picoCuries per kilogram (wet) 5 0

1983 1992 2002 2011 2021 YEAR

• The year designations on the x-axis reflect multiple sampling periods in a given year, as well as historical changes in the number of sampling periods per year.

FIGURE C-2 MEAN COBALT-60 CONCENTRATION IN AQUATIC SEDIMENT OYSTER CREEK GENERATING STATION, 1984 - 2020 300 INDICATOR STATION MEAN BACKGROUND STATION MEAN 250 200 C-20 150 100 picoCuries per kilogram (dry) 50 0

1984 1986 1990 2002 2021 YEAR

• The year designations on the x-axis reflect multiple sampling periods in a given year, as well as historical changes in the number of sampling periods per year.

FIGURE C-3 MEAN CESIUM-137 CONCENTRATION IN AQUATIC SEDIMENT OYSTER CREEK GENERATING STATION, 1984 - 2020 600 INDICATOR BACKGROUND 400 C-21 200 picoCuries per kilogram (dry) 0 1984 1986 1990 2002 2021 YEAR

• The year designations on the x-axis reflect multiple sampling periods in a given year, as well as historical changes in the number of sampling periods per year.

FIGURE C-4 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES OYSTER CREEK GENERATING STATION, 2008 - 2020 0.05 Indicator Background 0.04 0.03 C-22 0.02 picoCuries per cubic meter 0.01 0

Date

FIGURE C-5 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES OYSTER CREEK GENERATING STATION, 1984 - 2020 0.17 Indicator Stations 0.15 Background Station*

CHERNOBYL ACCIDENT 0.13 0.11 C-23 0.09 0.07 0.05 picoCuries per cubic meter 0.03 0.01

-0.01 YEAR

• Data from Cookstown station ONLY after December 1996

FIGURE C-6 MEAN QUARTERLY OSLD GAMMA DOSE OYSTER CREEK GENERATING STATION, 2020 35.0 30.0 25.0 20.0 C-24 15.0 10.0 millirem per Standard Quarter 5.0 0.0 0 TO 2 MILES 2 TO 5 MILES OVER 5 MILES DISTANCE RING FROM PLANT 1Q20 2Q20 3Q20 4Q20 Oyster Creek's dosimetry changed from TLD to OSLD in 2012.

APPENDIX D DATA TABLES QC COMPARISON SAMPLES

The following section presents the results of data analysis performed by the QC laboratory, Environmental Inc. Duplicate samples were obtained from several locations and media and were split with the primary laboratory, Teledyne Brown Engineering (TBE) and the QC Laboratory.

Comparison of the results for all media were within expected ranges.

Table D-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 24 (TBE) QCA (TBE) OC-24 (EIML) 06/01/20 < 174 < 173 < 150 10/30/20 < 184 < 182 < 155 D-1

Table D-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 24 06/01/20 < 8 < 6 < 12 < 9 < 15 < 11 < 10 < 8 (TBE) 10/20/20 < 7 < 6 < 13 < 6 < 12 < 12 < 7 < 7 QCA 06/01/20 < 9 < 10 < 18 < 9 < 20 < 14 < 9 < 9 (TBE) 10/20/20 < 6 < 6 < 12 < 6 < 12 < 9 < 6 < 6 OC-24 06/01/20 < 4 < 3 < 5 < 4 < 8 < 8 < 3 < 4 (EIML) 10/20/20 < 5 < 3 < 4 < 3 < 12 < 7 < 4 < 4 D-2

Table D-II.1 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 1N (TBE) OC-QC1N (EIML) 01/09/20 - 01/29/20 < 180 < 153 02/05/20 - 02/26/20 < 178 < 157 03/03/20 - 04/01/20 < 199 < 158 04/01/20 - 04/14/20 < 162 < 153 05/13/20 - 05/13/20 < 180 < 160 06/03/20 - 06/03/20 < 185 < 159 07/01/20 - 07/01/20 < 186 < 158 08/05/20 - 08/05/20 < 180 < 159 09/01/20 - 09/01/20 < 179 < 159 10/01/20 - 10/01/20 < 176 < 158 11/04/20 - 11/04/20 < 198 < 155 12/01/20 - 12/01/20 < 312 < 155 D-3

Table D-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 1N 01/09/20 - 01/29/20 < 6 < 6 < 12 < 7 < 14 < 10 < 7 < 6 (TBE) 02/05/20 - 02/26/20 < 9 < 8 < 15 < 9 < 17 < 14 < 9 < 8 03/03/20 - 04/01/20 < 5 < 5 < 8 < 5 < 9 < 7 < 5 < 5 04/01/20 - 04/14/20 < 3 < 3 < 7 < 3 < 7 < 6 < 3 < 3 05/13/20 - 05/13/20 < 2 < 2 < 5 < 2 < 4 < 4 < 2 < 2 06/03/20 - 06/03/20 < 2 < 2 < 5 < 1 < 3 < 4 < 2 < 2 07/01/20 - 07/01/20 < 2 < 3 < 7 < 2 < 5 < 5 < 2 < 2 08/05/20 - 08/05/20 < 3 < 2 < 6 < 3 < 5 < 5 < 3 < 3 09/01/20 - 09/01/20 < 3 < 3 < 7 < 3 < 5 < 6 < 2 < 3 10/01/20 - 10/01/20 < 5 < 6 < 12 < 6 < 12 < 9 < 6 < 6 11/04/20 - 11/04/20 < 6 < 6 < 13 < 6 < 15 < 10 < 7 < 6 12/01/20 - 12/01/20 < 6 < 8 < 14 < 7 < 7 < 12 < 8 < 6 D-4 OC-QC1N 01/09/20 - 01/29/20 < 2 < 3 < 5 < 2 < 5 < 4 < 3 < 2 (EIML) 02/05/20 - 02/26/20 < 2 < 2 < 5 < 2 < 6 < 6 < 3 < 3 03/03/20 - 04/01/20 < 3 < 2 < 7 < 3 < 6 < 7 < 4 < 3 04/01/20 - 04/14/20 < 2 < 2 < 5 < 1 < 3 < 3 < 3 < 3 05/13/20 - 05/13/20 < 2 < 3 < 5 < 2 < 3 < 5 < 2 < 2 06/03/20 - 06/03/20 < 3 < 2 < 8 < 1 < 6 < 6 < 2 < 3 07/01/20 - 07/01/20 < 4 < 4 < 8 < 4 < 6 < 7 < 3 < 2 08/05/20 - 08/05/20 < 3 < 3 < 6 < 1 < 3 < 7 < 4 < 3 09/01/20 - 09/01/20 < 2 < 2 < 3 < 2 < 2 < 5 < 2 < 3 10/01/20 - 10/01/20 < 2 < 5 < 7 < 3 < 6 < 7 < 4 < 3 11/04/20 - 11/04/20 < 3 < 3 < 5 < 2 < 4 < 5 < 3 < 3 12/01/20 - 12/01/20 < 3 < 3 < 5 < 2 < 6 < 5 < 4 < 3

Table D-III.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD W-3C OC-W-3C (EIML) 01/29/20 - 01/29/20 < 194 < 153 05/21/20 - 05/21/20 < 174 < 160 D-5

Table D-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 W-3C 01/29/20 - 01/29/20 < 7 < 6 < 11 < 7 < 17 < 13 < 7 < 7 (TBE) 05/21/20 - 05/21/20 < 7 < 7 < 13 < 8 < 16 < 12 < 9 < 10 OC -W-3C (EIML) 01/29/20 - 01/29/20 < 4 < 3 < 4 < 3 < 6 < 5 < 3 < 2 05/21/20 - 05/21/20 < 1 < 2 < 2 < 2 < 2 < 3 < 1 < 2 D-6

Table D-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN CLAM SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 24 06/01/20 1540 +/- 987 < 81 < 84 < 157 < 88 < 169 < 99 < 81 (TBE)

QCA 06/01/20 1198 +/- 700 < 52 < 59 < 111 < 66 < 109 < 41 < 54 (TBE)

OC-24 06/01/20 1286 +/- 102 < 4 < 4 < 15 < 4 < 8 < 4 < 4 (EIML)

D-7 (1) No sample collected or analyzed

Table D-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-228 24 06/01/20 < 1012 8501 +/- 1707 < 121 < 112 < 127 < 145 < 121 4319 +/- 1838 875 +/- 197 (TBE) 10/20/20 < 382 9138 +/- 989 < 51 < 45 < 52 < 55 < 45 < 1054 426 +/- 87 QCA 06/01/20 < 948 9132 +/- 2159 < 137 < 113 < 125 < 142 < 122 < 1647 572 +/- 185 (TBE) 10/20/20 < 505 12190 +/- 1225 < 60 < 52 < 62 < 77 < 61 < 1186 625 +/- 99 OC-24 06/01/20 < 296 6752 +/- 633 < 28 < 19 < 22 < 22 < 23 1945 +/- 782 < 2116 (EIML) 10/20/20 < 295 13165 +/- 639 < 20 < 25 < 18 < 13 < 18 1523 +/- 639 < 1661 D-8 (1) No sample collected or analyzed

TABLE D-VI.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Sr-89 Sr-90 Be-7 K-40 Cs-134 Cs-137 36 (TBE)

Collards 08/31/20 < 19 < 3.8 < 262 5287 +/- 651 < 29 < 28 Kale 08/31/20 < 25 < 4.6 < 265 2944 +/- 640 < 32 < 37 Mustard Greens 08/31/20 < 20 < 4.4 367 +/- 277 3799 +/- 784 < 39 < 28 QCA (TBE)

Collards 08/31/20 < 18 4.8 +/- 2.4 < 189 4647 +/- 565 < 25 < 25 Kale 08/31/20 < 19 6.8 +/- 2.3 < 239 3950 +/- 707 < 35 < 36 Mustard Greens 08/31/20 < 23 6.0 +/- 2.5 185 +/- 175 3026 +/- 473 < 20 < 25 D-9 OC-36 (EIML)

Collards 08/31/20 < 4 < 3.0 < 109 4354 +/- 354 < 5 < 6 Kale 08/31/20 < 4 < 3.0 < 148 3799 +/- 352 < 10 < 10 Mustard Greens 08/31/20 < 4 < 4.0 248 +/- 131 4372 +/- 366 < 10 < 12

Intentionally left blank APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank Analytics Environmental Radioactivity Cross Check Program Table E-1 Teledyne Brown Engineering Environmental Services Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units TBE Value Evaluation (b)

Number Value (a) Known Result September 2020 E13247 Milk Sr-89 pCi/L 62.8 95.4 0.66 N(1)

Sr-90 pCi/L 12.0 12.8 0.94 A E13248 Milk Ce-141 pCi/L 156 150 1.04 A Co-58 pCi/L 172 180 0.96 A Co-60 pCi/L 369 379 0.97 A Cr-51 pCi/L 372 372 1.00 A Cs-134 pCi/L 171 200 0.85 A Cs-137 pCi/L 241 250 0.96 A Fe-59 pCi/L 217 200 1.08 A I-131 pCi/L 84.6 95.0 0.89 A Mn-54 pCi/L 175 180 0.97 A Zn-65 pCi/L 252 270 0.93 A E13249 Charcoal I-131 pCi 70.2 75.8 0.93 A E13250 AP Ce-141 pCi 101 101 1.00 A Co-58 pCi 111 120 0.92 A Co-60 pCi 249 254 0.98 A Cr-51 pCi 287 249 1.15 A Cs-134 pCi 114 134 0.85 A Cs-137 pCi 159 168 0.95 A Fe-59 pCi 127 134 0.95 A Mn-54 pCi 114 121 0.94 A Zn-65 pCi 168 181 0.93 A E13251 Soil Ce-141 pCi/g 0.241 0.191 1.26 W Co-58 pCi/g 0.211 0.228 0.93 A Co-60 pCi/g 0.466 0.481 0.97 A Cr-51 pCi/g 0.450 0.472 0.95 A Cs-134 pCi/g 0.273 0.254 1.07 A Cs-137 pCi/g 0.370 0.390 0.95 A Fe-59 pCi/g 0.233 0.254 0.92 A Mn-54 pCi/g 0.217 0.229 0.95 A Zn-65 pCi/g 0.368 0.343 1.07 A E13252 AP Sr-89 pCi 79.9 100.0 0.80 A Sr-90 pCi 12.1 13.4 0.90 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) See NCR 20-19 (Page 1 of 2)

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Analytics Environmental Radioactivity Cross Check Program Table E-1 Teledyne Brown Engineering Environmental Services Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units TBE Value Evaluation (b)

Number Value (a) Known Result December 2020 E13254 Milk Sr-89 pCi/L 82.2 89.7 0.92 A Sr-90 pCi/L 12.4 13.0 0.96 A E13255 Milk Ce-141 pCi/L 91.1 100 0.91 A Co-58 pCi/L 77.5 84.3 0.92 A Co-60 pCi/L 147 152 0.97 A Cr-51 pCi/L 259 253 1.02 A Cs-134 pCi/L 97.1 108 0.90 A Cs-137 pCi/L 117 127 0.92 A Fe-59 pCi/L 114 112 1.02 A I-131 pCi/L 84.3 91.9 0.92 A Mn-54 pCi/L 137 143 0.96 A Zn-65 pCi/L 175 190 0.92 A E13256 Charcoal I-131 pCi 70.2 78.2 0.90 A E13257A AP Ce-141 pCi 67.4 74.6 0.90 A Co-58 pCi 57.9 62.9 0.92 A Co-60 pCi 108 113 0.95 A Cr-51 pCi 162 189 0.86 A Cs-134 pCi 68.1 80.4 0.85 A Cs-137 pCi 82.4 95.0 0.87 A Fe-59 pCi 80.5 83.7 0.96 A Mn-54 pCi 102 107 0.95 A Zn-65 pCi 115 142 0.81 A E13258 Soil Ce-141 pCi/g 0.167 0.170 0.98 A Co-58 pCi/g 0.125 0.143 0.87 A Co-60 pCi/g 0.245 0.257 0.95 A Cr-51 pCi/g 0.393 0.429 0.92 A Cs-134 pCi/g 0.147 0.183 0.80 A Cs-137 pCi/g 0.260 0.288 0.90 A Fe-59 pCi/g 0.199 0.190 1.05 A Mn-54 pCi/g 0.229 0.243 0.94 A Zn-65 pCi/g 0.320 0.322 0.99 A E13259 AP Sr-89 pCi 85.0 78.6 1.08 A Sr-90 pCi 13.1 11.4 1.15 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (Page 2 of 2)

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DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Table E-2 Teledyne Brown Engineering Environmental Services Identification TBE Known Acceptance Month/Year Matrix Nuclide Units Evaluation (b)

Number Value Value (a) Range February 2020 20-GrF42 AP Gross Alpha Bq/sample 0.676 1.24 0.37 - 2.11 A Gross Beta Bq/sample 2.03 2.00 1.00 - 3.00 A 20-MaS42 Soil Ni-63 Bq/kg 0.01 (1) A Sr-90 Bq/kg 348 340 238 - 442 A 20-MaW42 Water Ni-63 Bq/L 11.6 11.1 7.8 - 14.4 A Pu-238 Bq/L 0.926 0.94 0.66 - 1.22 A Pu-239/240 Bq/L 0.712 0.737 0.516 - 0.958 A 20-RdF42 AP U-234/233 Bq/sample 0.0416 0.075 0.053 - 0.098 N(3)

U-238 Bq/sample 0.0388 0.078 0.055 - 0.101 N(3) 20-RdV42 Vegetation Cs-134 Bq/sample 3.23 3.82 2.67 - 4.97 A Cs-137 Bq/sample 2.64 2.77 1.94 - 3.60 A Co-57 Bq/sample 0.0281 (1) A Co-60 Bq/sample 2.62 2.79 1.95 - 3.63 A Mn-54 Bq/sample 4.3 4.58 3.21 - 5.95 A Sr-90 Bq/sample 0.396 0.492 0.344 - 0.640 A Zn-65 Bq/sample 3.93 3.79 2.65 - 4.93 A August 2020 20-GrF43 AP Gross Alpha Bq/sample 0.267 0.528 0.158 - 0.898 A Gross Beta Bq/sample 0.939 0.915 0.458 - 1.373 A 20-MaS43 Soil Ni-63 Bq/kg 438 980 686 - 1274 N(4)

Tc-99 Bq/kg 1.11 (1) A 20-MaW43 Water Ni-63 Bq/L 0.175 (1) A Tc-99 Bq/L 8.8 9.4 6.6 - 12.2 A 20-RdV43 Vegetation Cs-134 Bq/sample 3.635 4.94 3.46 - 6.42 W Cs-137 Bq/sample 0.0341 (1) A Co-57 Bq/sample 5.855 6.67 4.67 - 8.67 W Co-60 Bq/sample 3.122 4.13 2.89 - 5.37 W Mn-54 Bq/sample 4.524 5.84 4.09 - 7.59 A Sr-90 Bq/sample 1.01 1.39 0.97 - 1.81 W Zn-65 Bq/sample 4.706 6.38 4.47 - 8.29 W (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOE/MAPEP evaluation:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) False positive test (2) Sensitivity evaluation (3) See NCR 20-13 (4) See NCR 20-20 (Page 1 of 1)

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ERA Environmental Radioactivity Cross Check Program Table E-3 Teledyne Brown Engineering Environmental Services Identification Known Acceptance Month/Year Matrix Nuclide Units TBE Value Evaluation (b)

Number Value (a) Limits March 2020 MRAD-32 Water Am-241 pCi/L 52.5 45.3 31.1 - 57.9 A Fe-55 pCi/L 155 152 89.3 - 221 A Pu-238 pCi/L 34.0 36.4 21.9 - 47.2 A Pu-239 pCi/L 30.9 33.6 20.8 - 41.4 A April 2020 RAD-121 Water Ba-133 pCi/L 41.8 41.8 34.0- 46.7 A Cs-134 pCi/L 42.9 46.3 37.1 - 50.9 A Cs-137 pCi/L 226 234 211 - 259 A Co-60 pCi/L 52.4 50.3 45.3 - 57.9 A Zn-65 pCi/L 83.3 86.8 78.1 - 104 A GR-A pCi/L 20.1 23.6 11.9 - 31.6 A GR-B pCi/L 45.6 60.5 41.7 - 67.2 A U-Nat pCi/L 18.45 18.6 14.9 - 20.9 A H-3 pCi/L 14200 14100 12300 - 15500 A Sr-89 pCi/L 58.0 60.1 48.3 - 67.9 A Sr-90 pCi/L 34.1 44.7 33.0 - 51.2 A I-131 pCi/L 27.4 28.9 24.1 - 33.8 A September 2020 MRAD-33 Soil Sr-90 pCi/Kg 4360 4980 1550 - 7760 A AP Fe-55 pCi/Filter 189 407 149 - 649 A U-234 pCi/Filter 17.9 18.3 13.6 - 21.4 A U-238 pCi/Filter 19.1 18.1 13.7 - 21.6 A Water Am-241 pCi/L 160 176 121 - 225 A Fe-55 pCi/L 299 298 175 - 433 A Pu-238 pCi/L 200 191 115 - 247 A Pu-239 pCi/L 105 100 61.9 - 123 A October 2020 RAD-123 Water Ba-133 pCi/L 37.1 37.0 29.8 - 41.6 A Cs-134 pCi/L 50.6 52.7 42.5 - 58.0 A Cs-137 pCi/L 131 131 118 - 146 A Co-60 pCi/L 62.9 60.5 54.4 - 69.1 A Zn-65 pCi/L 167 162 146 - 191 A GR-A pCi/L 40.0 26.2 13.3 - 34.7 N(1)

GR-B pCi/L 47.5 69.1 48.0 - 76.0 N(1)

U-Nat pCi/L 17.2 20.3 16.3 - 22.7 A H-3 pCi/L 23800 23200 20,300 - 25,500 A Sr-89 pCi/L 41.1 43.3 33.4 - 50.5 A Sr-90 pCi/L 28.5 30.2 22.0 - 35.0 A I-131 pCi/L 22.9 28.2 23.5 - 33.1 N(2)

November 2020 QR111920K Water GR-A pCi/L 50.7 52.4 27.3 - 65.6 A GR-B pCi/L 24.9 24.3 15.0 - 32.3 A (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(b) ERA evaluation:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 20-18 (2) See NCR 20-17 (Page 1 of 1)

E-4

TABLE E-4 Interlaboratory Comparison Crosscheck Program New York Department of Health (ELAP)a Environmental, Inc., Midwest Laboratory (Relevant Nuclides Only)

Laboratory Known Acceptance Lab Code Date Analysis Acceptance Result Activity Limits NYW-3307 09/15/20 H-3 11,500 +/- 465 11,208 9,760 - 12,300 Pass NYW-3337 09/15/20 GR-A 43.7 +/- 2.5 64.9 34.0 - 80.4 Pass NYW-3337 09/15/20 Co-60 46.4 +/- 3.8 42.3 38.1 - 49.2 Pass NYW-3337 09/15/20 Zn-65 133 +/- 9.0 116 104 - 138 Pass NYW-3337 09/15/20 Cs-134 32.5 +/- 3.1 33.0 26.0 - 36.3 Pass NYW-3337 09/15/20 Cs-137 147 +/- 7.0 134 121 - 150 Pass a

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by the New York Department of Health Laboratory Approval Program (NY ELAP)

E-5 Page 1 of 1

TABLE E-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., Midwest Laboratory (Relevant Nuclides Only)

Concentration a Reference Laboratory Known Lab Code b Analysis Control Limits c Acceptance Date Result Activity MAW-536 02/01/20 GR-A 0.86 +/- 0.06 1 0.31 - 1.75 Pass MASO-662 02/01/20 Cs-134 955 +/- 9.0 1,114 780 -1,448 Pass MASO-662 02/01/20 Cs-137 1089 +/- 12 1,020 714 - 1,326 Pass MASO-662 02/01/20 Co-60 0.33 +/- 1.26 0 NA c Pass MASO-662 02/01/20 Mn-54 1,022 +/- 27 945 662 - 1,229 Pass MASO-662 02/01/20 K-40 710 +/- 42 625 438 - 813 Pass MAW-599 02/01/20 H-3 202 +/- 9.0 196 137 - 255 Pass MAW-599 02/01/20 Cs-134 16.1 +/- 0.3 18.5 13.0 - 24.1 Pass MAW-599 02/01/20 Cs-137 11.5 +/- 0.4 11.3 13.8 - 25.6 Pass MAW-599 02/01/20 Co-60 10.6 +/- 0.2 10.6 7.4 - 13.8 Pass MAW-599 02/01/20 Mn-54 20.5 +/- 0.4 19.6 13.7 - 25.5 Pass MAW-599 02/01/20 Zn-65 24.1 +/- 0.70 22.2 15.5 - 28.9 Pass MAW-599 02/01/20 Sr-90 0.07 +/- 0.18 0 NA c Pass MAVE-668 02/01/20 Cs-134 3.51 +/- 0.22 3.82 2.67 - 4.97 Pass MAVE-668 02/01/20 Cs-137 3.04 +/- 0.18 2.77 1.94 - 3.60 Pass MADW-3101 08/01/20 GR-A 0.57 +/- 0.4 0.62 0.19 - 1.05 Pass MASO-3179 08/01/20 Cs-134 599 +/- 7.0 710 497 - 923 Pass MASO-3179 08/01/20 Cs-137 3.33 +/- 4.81 0 NA c Pass MASO-3179 08/01/20 Co-60 965 +/- 9.0 1000 700 - 1,300 Pass MASO-3179 08/01/20 Mn-54 651 +/- 11 610 427 - 793 Pass MASO-3179 08/01/20 K-40 684 +/- 58 622 435 - 809 Pass MAW-3175 08/01/20 Cs-134 13.9 +/- 0.3 15.2 10.6 - 19.8 Pass MAW-3175 08/01/20 Cs-137 15.4 +/- 0.4 14.3 10.0 - 18.6 Pass MAW-3175 08/01/20 Co-60 12.5 +/- 0.3 12.2 8.5 - 15.9 Pass MAW-3175 08/01/20 Mn-54 0.07 +/- 0.17 0 NA c Pass MAW-3175 08/01/20 Zn-65 18.3 +/- 0.6 16.9 11.8 - 22.0 Pass MAVE-3185 08/01/20 Cs-134 4.73 +/- 0.10 4.94 3.46 - 6.42 Pass MAVE-3185 08/01/20 Cs-137 0.03 +/- 0.06 0 NA c Pass a

Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (vegetation) b Laboratory codes as follows: MAW (water), MASO (soil), MAVE (vegetation) c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

E-6 Page 1 of 1

TABLE E-6 Interlaboratory Comparison Crosscheck Program Environmental Resource Associates (ERA)a RAD Study Environmental, Inc., Midwest Laboratory (Relevant Nuclides Only)

Laboratory Lab Code Date Analysis ERA Result Control Limits Acceptance Result RAD-120 ERW-49 01/06/20 Cs-134 22.7 +/- 2.8 22.9 17.5 - 25.6 Pass ERW-49 01/06/20 Cs-137 225 +/- 8.0 220 198 - 244 Pass ERW-49 01/06/20 Co-60 94.6 +/- 4.6 91.2 82.1 - 103 Pass ERW-49 01/06/20 Zn-65 331 +/- 13 298 268 - 348 Pass ERW-49 01/06/20 GR-A 52.3 +/- 2.4 58.9 30.8 - 73.3 Pass ERW-49 01/06/20 H-3 18,200 +/- 408 17,800 15,600 - 19,600 Pass RAD-122 ERW-2297 07/06/20 Cs-134 19.8 +/- 2.4 22.3 17.0 - 25.0 Pass ERW-2297 07/06/20 Cs-137 73.2 +/- 5.4 73.0 65.7 - 83.0 Pass ERW-2297 07/06/20 Co-60 90.0 +/- 4.0 86.1 77.5 - 97.0 Pass ERW-2297 07/06/20 Zn-65 84.9 +/- 7.5 82.9 74.6 - 99.6 Pass ERW-2297 07/06/20 GR-A 40.3 +/- 2.2 52.4 27.3 - 65.6 Pass ERW-2297 07/06/20 H-3 21,100 +/- 400 20,300 17.800 - 22,300 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).

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Intentionally left blank APPENDIX F ERRATA DATA

Intentionally left blank For the 2019 AREOR, Sr-89 and Sr-90 results reported on Table C-VI.3 were not updated from the previous year. All results for both years were < MDC. The updated table is presented below:

Table C-Vl.3 CONCENTRATIONS OF STRONTIUM IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER t 2 SIGMA COLLECTION SITE PERIOD SR-as sn-90 3 01/02/19 - 04/03/19 <7 <5 04/03/19 - 07/02/19 <s <7 07/02/19 - 10/02/19 <6 <5 10/02/19 - 01/02/20 <7 <5 MEAN - -

20 01/16/19 - 04/03/19 <6 <9 04/03/19 - 07/02119 <7 <5 07/02/19 - 10/02/19 <7 <7 10/02/19 - 01/02/20 <6 <e MEAN . .

66 01/02/19 04/03/19 <7 <7 04/03/19 - 07/02/19 <a <9 07/02/19 - 10/02/19 <7 <6 10/02/19 - 01/02/20 <7 < I; MEAN -

71 01/02/19 - 04/03/19 <5 <5 04/03/19 - 07/02/19 <a <7 07/02/19 - 10/02/19 <5 <6 10/02/19 - 01/02/20 <6 <7 MEAN -

72 0110219 - 04/03/19 <6 <4 04/03/19 - 07/02/19 <9 <6 07/02/19 - 10/02/19 <6 <6 10/02/19 - 01/02/20 <6 <5 MEAN - -

73 01/02/19 - 04/03/19 <7 <7 04/03/19 - 07/02/19 <7 <6 07/02/19 - 10/02/19 <6 <6 10/02/19 - 01/02/20 <a <7 MEAN - -

111 01/02/19 - 04/03/19 <7 <6 04/03/19 - 07/02/19 <7 <5 07/02/19 - 10/02/19 <7 <5 10/02/19 - 01/02/20 <6 <5 MEAN - -

0 01/02/19 - 04/03/19 <6 <5 04/03/19 - 07/02/19 <9 <7 07/02/19 - 10/02/19 <7 <5 10/02/19 - 01/02/20 <7 <5 MEAN C-1 3 2019 OCGS AREOR REVISION 12/01/20 F-1

Intentionally left blank APPENDIX G ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank Docket No: 50-219 OYSTER CREEK GENERATING STATION UNIT 1 Annual Radiological Groundwater Protection Program Report 1 January through 31 December 2020 Prepared By Teledyne Brown Engineering Environmental Services IIIII HOLTEC DECOMMISSIONING INTERNATIONAL Oyster Creek Generating Station Forked River, NJ 08731 April 26, 2020

Intentionally left blank Table of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction...................................................................................................................... 2 A. Objectives of the RGPP ....................................................................................... 3 B. Implementation of the Objectives ........................................................................ 4 C. Program Description ............................................................................................ 4 D. Characteristics of Tritium (H-3)............................................................................ 5 III. Program Description....................................................................................................... 6 A. Sample Analysis .................................................................................................. 6 B. Data Interpretation ............................................................................................... 6 C. Background Analysis ......................................................................................... 7 IV. Results and Discussion................................................................................................ 9 A. Program Exceptions ............................................................................................ 9 B. Groundwater Results ........................................................................................... 9 C. Surface Water Results....................................................................................... 10 D. Precipitation Water Results ............................................................................... 10 E. Summary of Results - Inter-laboratory Comparison Program........................... 10 F. Leaks, Spills, and Releases ............................................................................... 10 G. Trends ............................................................................................................... 10 H. Investigations..................................................................................................... 11 I. Actions Taken ..................................................................................................... 11 V. References ................................................................................................................... 12 i

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2020 Figures Figure A-1 Sampling locations - Selected Cohansey and Cape May Formation Wells, Oyster Creek Generating Station, 2020 Security-Related Information: Detailed maps of the Oyster Creek Generating Station have been withheld from public disclosure under 10 CFR 2.390 and N.J.S.A. 47:1A-1.1 Appendix B Data Tables Tables Table B-I.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2020 Table B-I.2 Concentrations of Gamma Emitters in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2020 Table B-I.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2020 Table B-II.1 Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2020 Table B-II.2 Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2020 Table B-II.3 Concentrations of Hard-To-Detects in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2020 Table B-III.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2020 ii

I. Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP) conducted for the Oyster Creek Generating Station (OCGS) by Holtec Decommissioning International (HDI) covers the period 01 January 2020 through 31 December 2020.

This report covers groundwater and surface water samples collected from the environment, both on and off station property in 2020. In 2020, 480 analyses were performed on 142 samples from 42 locations.

There were three inadvertent releases of contaminated water into the groundwater during 2009 resulting in a plume located west of the turbine building, which is monitored via a series of monitoring wells.

No gamma emitting radionuclides were detected at any of the 35 groundwater well sample locations. Gamma-emitting nuclide K-40 was detected at a concentration of 186 pCi/L at 1 of the 3 surface water locations analyzed during 2020.

In the case of tritium, HDI specified that the laboratory achieve a lower limit of detection 10 times lower than the drinking water limit specified by the United States Environmental Protection Agency (USEPA) (2,000 pCi/l versus 20,000 pCi/l). As expected, tritium was detected in groundwater samples, although tritium concentrations have decreased substantially since 2009. The 2020 tritium concentrations varied from <147 to 2,240 pCi/l. The well with the highest concentration was MW-57I.

Surface water samples were collected from onsite and offsite monitoring locations during 2020. Tritium was not detected in any of the 23 samples.

Strontium-89 (Sr-89) and Strontium-90 (Sr-90) were not detected in any groundwater samples during 2020.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples in 2020. There were 42 samples taken from 20 groundwater well locations. Gross Alpha (dissolved) was detected in 12 samples. The concentrations ranged from 0.7 to 1.3 pCi/L. Gross Alpha (suspended) was detected in 14 samples and ranged from 1.8 to 18.4 pCi/L.

Gross Beta (dissolved) was detected in 31 samples and ranged from 1.0 to 19.5 pCi/L. Gross Beta (suspended) was detected in 21 samples and ranged from 2.0 to 23.4 pCi/L.

Hard-To-Detect (HTD) analyses were performed on one groundwater sample in 2020. These analyses included americium-241 (Am-241), cerium-242 (Ce-242),

cerium-243/244 (Ce-243/244), plutonium-238 (Pu-238), plutonium-239/240 (Pu-239/240), uranium-234 (U-234), uranium-235 (U-235), and uranium-238 (U-238).

U-234 was detected at a concentration of 2.5 pCi/L and U-238 was detected at a concentration of 2.3 pCi/L All other HTD analyses were less than the MDC.

II. Introduction On July 1st, 2019, ownership of the Oyster Creek Nuclear Generating Station and transfer of the license from Exelon Generation Company, LLC to Oyster Creek Environmental Protection, LLC (OCEP) as the licensed owner and Holtec Decommissioning International, LLC (HDI) as the licensed operator, was completed. OCEP and HDI are wholly-owned subsidiaries of Holtec International.

The Oyster Creek Nuclear Generating Station consisted of a single boiling water reactor (BWR) and turbine generator was capable of producing 650 megawatts of electricity. The Station operated under Nuclear Regulatory Commission (NRC) renewed facility operating license number DPR-16. Brackish water from Barnegat Bay is supplied to the circulating water system. The circulating water system is designed to supply a continuous flow of water from Barnegat Bay through the plant to remove the waste heat released by the power cycle in the Main Condenser. The circulating water system is comprised of the intake canal from Barnegat Bay to the plant, the Main Condenser Circulating Water System, the dilution plant, and the discharge canal to Barnegat Bay. The dilution plant portion of the system minimized the adverse effects of the thermal discharge on aquatic life in the discharge canal and Barnegat Bay.

The Station is located in the Atlantic Coastal Plain physiographic province.

Topography in the region of the Station is a slightly undulating coastal plain having low relief. The land surface gradually rises from sea level at Barnegat Bay, which is located east of the Station, to approximately 50 feet above mean sea level (AMSL) 2 miles inland. This region of the coastal plain has numerous tidal marshes and is incised by easterly flowing streams and creeks. Elevations at the Station property west of Route 9 range from approximately 0 to 15 feet AMSL immediately adjacent to the intake and discharge canals to slightly more than 30 feet AMSL in the northwest portion of the Station property. The 150-acre developed portion of the Site located within the "horseshoe" formed by the intake and discharge canals west of Route 9 has an approximate average elevation of 20 feet AMSL. In the immediate vicinity of the intake and discharge canals, the Station property slopes steeply down to the canal. The average elevation of the surface water level in the intake and discharge canals is approximately 1-foot AMSL. The ground surface is relatively level except for the steep slopes at areas adjacent to the intake and discharge canals.

The three shallowest stratigraphic units in the vicinity of the Oyster Creek area in descending order are the Cape May Formation, the Cohansey Formation, and the Kirkwood Formation. Some of the Station structures are constructed to depths of approximately 50 feet below ground surface (bgs). Excavations were completed from grade, through the fill, Cape May Formation, Upper Clay, and into the Cohansey Formation during construction. Consequently, the bottoms of some Station structures are completed within the Cohansey Formation and some structures breach the Upper Clay.

The Cape May Formation regionally has an average thickness of 40 feet and at OCGS, the Cape May is described as a light gray to tan, medium- to fine-grained sand, with trace to some silt and occasional coarse sand. It is generally poorly compacted. The Cape May Formation varies from 0 to 21 feet in thickness based on historical boring logs. The variation principally is due to the varying amount of material excavated and replaced by fill during Station construction. When present, the thickness of the Cape May generally ranges from 15 to 20 feet thick. The base of the Cape May generally is defined by the presence of a dark clay unit referred to as the Upper Clay unit. The Upper Clay is a stiff to hard, gray, plastic organic clay containing inclusions (also described as lenses or partings) of dense fine sand with trace to some organic silt. The deposits of fine sand within the Upper Clay layer have high relative densities and occur as lenses or inclusions.

The Cohansey Formation is primarily composed of a light-colored, fine- to very coarse-grained quartzose sand with lenses of silt and clay. Although most borings at the Station do not penetrate the entire Cohansey Formation, this formation appears to be approximately 60 to 80 feet thick at OCGS. A clay sequence, referred to at the Station as the "Lower Clay", marks the base of the Cohansey, which generally is present to approximately 90 to 100 feet bgs. The lower clay is a dense gray medium- to fine-grained sand containing trace to some organic silt and layers or inclusions of very stiff to hard gray organic clay. The thickness of the lower clay is estimated to be approximately 10 to 20 feet in the vicinity of OCGS.

The Cohansey Formation is underlain by the Kirkwood Formation which consists of several stratigraphic units. The Kirkwood Formation is described as a medium- to fine-grained sand with trace silt. The thickness of this formation beneath the Station is unknown. The south domestic supply well terminates in the Kirkwood at a depth of 310 feet bgs. The Kirkwood thickness in Ocean County ranges from approximately 300 to 400 feet.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2020.

A. Objectives of the RGPP The long-term objectives of the RGPP are as follows:

Ensure that the site characterization of geology and hydrology provides an understanding of predominant ground water gradients based upon current site conditions Identify site risk based on plant design and work practices Evaluate all structures, systems and components (SSC) that contain or could contain licensed material and for which there is a credible mechanism for the licensed material to reach groundwater Evaluate work practices that involve licensed material and for which there is a credible mechanism for the licensed material to reach groundwater Perform on-site monitoring to ensure timely detection of inadvertent radiological releases to ground water Understand background concentrations of radioactive analytes outside of the REMP, as required Evaluate return/re-use of previously discharged radioactive effluents in gaseous or liquid effluents that are returned from the environment to the operating nuclear power facility Ensure controls are established for the selection, installation and retirement of monitoring wells Perform remediation protocols to prevent migration of licensed material off-site and to minimize decommissioning impacts Ensure that records of leaks, spills, remediation efforts are retained and retrievable to meet the requirements of 10 CFR 50.75(g)

Ensure periodic communications are held on the RGPP with the designated State/Local officials Ensure timely verbal and written reporting occurs if there is an inadvertent release of licensed materials to the soil, groundwater or surface water Document and report all applicable RGPP data Identify and resolve deficiencies via the Decommissioning Corrective Action Program Perform program oversight to ensure effective implementation of the voluntary RGPP B. Implementation of the Objectives The objectives identified have been implemented at the Oyster Creek Generating Station through compliance with approved procedures EN-AA-408-4000, Radiological Groundwater Protection Program Implementation, and site specific procedure EN-OC-408-4160, RGPP Reference Material, for Oyster Creek Generating Station.

C. Program Description Samples for the OCGS site were collected for HDI by on-site personnel and Normandeau Associates, Inc. This section describes the general collection methods used to obtain environmental samples for the OCGS RGPP in 2020.

Sample locations can be found in Table A-1, Appendix A.

1. Sample Collection Samples of water are collected, managed, transported and analyzed in accordance with approved procedures. Both groundwater and surface water are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events.

2. Sample Analysis Samples are analyzed in accordance with approved procedures that are based on industry standards.

3. Quality Control Analytical laboratories are subject to internal quality assurance programs, industry cross-check programs, nuclear industry audits, as well as being certified by the State of New Jersey.

4. Data Interpretation Station personnel review and evaluate all analytical data deliverables as data is received. Analytical data results are reviewed by both station personnel and independent consultants, including a hydrogeologist, for adverse trends or changes to hydrogeologic conditions.

D. Characteristics of Tritium (H-3)

Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water."

The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through the skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 10 days.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors. Also, tritium was released into the atmosphere from Chernobyl in 1986. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

Tritium has a half-life of approximately 12.3 years. It decays spontaneously to Helium-3 (He-3). This radioactive decay releases a beta particle (18.6 keV low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

III. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Oyster Creek Generating Station RGPP in 2020. The sampling frequencies are increased if activity is detected.

In order to achieve the stated objectives, the current program includes the following analyses for groundwater, surface water, and precipitation water:

1. Gamma emitters

2. Strontium-89 and Strontium-90

3. Tritium

4. Gross Alpha (Dissolved and Suspended) and Gross Beta (Dissolved and Suspended)

5. Selected transuranics

6. Fe-55

7. Ni-63 B. Data Interpretation The radiological data collected prior to Oyster Creek Generating Station becoming operational, as well as background data from publicly available databases, were used as a baseline with which these operational data were compared. For the purpose of this report, Oyster Creek Generating Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criterion for the presence of activity. All analyses were designed to achieve the required OCGS detection capabilities for environmental sample analysis.

The minimum detectable concentration (MDC) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5%

probability of falsely concluding that a blank observation represents a "real" signal as an after the fact estimate of the presence of activity.

2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. Uncertainty comes from factors such as calibration standards, sample volume/weight measurements, or sampling uncertainty. The uncertainty of a measurement created by statistical process (counting error) is reported as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated.

Each counting result is reported and then followed with a plus or minus

(+/-) result of the estimated sample standard deviation (as TPU) that is obtained by propagating all sources of analytical uncertainty in measurements.

Analytical uncertainties are reported at the 95% confidence level.

C. Background Analysis

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others.

Additional detail may be found by consulting references.

a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, cosmogenic tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, lithogenic tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and Sr-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and peaked in 1963 with the signing of the limited test ban treaty. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment. Also, tritium was released into the atmosphere from Chernobyl in 1986.

b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. One publicly available database that provides tritium concentrations in precipitation is the USEPAs RadNet database. RadNet provides tritium precipitation concentration data for samples collected at stations throughout the U.S. from 1978 up to and including 1996.

Tritium concentrations in precipitation in New Jersey from 1978 through 1996 have ranged from 600 pCi/L in 1979 to 0 pCi/L in 1996, with an average of 185 pCi/L. Tritium concentrations in wells may still be above the 2000 pCi/l detection limit from the external causes described above. Water from previous years and decades is naturally captured in groundwater, so some well water sources today are affected by the surface water from the 1960s that was elevated in tritium.

c. Surface Water Data Tritium concentrations are routinely measured in surface water bodies, including Oyster Creek and the Delaware River. New Jersey surface water data between 1978 and 1998 averaged 185 pCi/L.

The USEPA RadNet surface water data typically has a reported Combined Standard Uncertainty of 2 standard deviations. This corresponds to a +/- 36 to +/-100 pCi/L confidence bound on each given reported measurement so that the typical surface water background data provided by RadNet may be subject to measurement uncertainty of up to 100 pCi/L.

The radio-analytical laboratory counts tritium results to an HDI-specified LLD of 200 pCi/L with a typical uncertainty of +/-100 pCi/L. Therefore, sample results reported by TBE near this LLD cannot be distinguished from natural background concentrations in surface water.

IV. Results and Discussion A. Program Exceptions There were no program exceptions in 2020. All samples required by station procedures were collected as required.

B. Groundwater Results Samples were collected from on-site locations in accordance with the station radiological groundwater protection program. As reported in the latest Hydrogeologic Investigation Report, groundwater flow is towards the intake and discharge canals.

Tritium Samples from 35 locations were analyzed for tritium activity. Tritium was detected in 10 of 119 samples. The values ranged from <147 to 2,240 pCi/L.

The well with the highest concentration was MW-57I.

(Table B-I.1, Appendix B)

Strontium Samples collected from onsite wells are analyzed for hard-to-detect (HTD) isotopes, including strontium to characterize the source of any contaminant.

Per station procedures, ongoing surveillance for HTD isotopes is required after initial negative findings to ensure a new source of contamination is not present.

Strontium-89 and Strontium-90 were not detected in any location sampled in 2020. (Table B-I.1, Appendix B)

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples in 2020. There were 42 samples taken from 20 groundwater well locations. Gross Alpha (dissolved) was detected in 12 samples. The concentrations ranged from 0.7 to 1.3 pCi/L. Gross Alpha (suspended) was detected in 14 samples and ranged from 1.8 to 18.4 pCi/L. Gross Beta (dissolved) was detected in 31 samples and ranged from 1.0 to 19.5 pCi/L. Gross Beta (suspended) was detected in 21 samples and ranged from 2.0 to 23.4 pCi/L. (Table B-I.1, Appendix B)

Gamma Emitters No gamma-emitting nuclides were detected in any groundwater sample in 2020. (Table B-I.2, Appendix B).

Hard-To-Detect Hard-To-Detect (HTD) analyses were performed on one groundwater sample in 2020. U-234 was detected at a concentration of 2.5 pCi/L and U-238 was detected at a concentration of 2.3 pCi/L All other HTD analyses were less than the MDC. (Table B-I.3, Appendix B)

C. Surface Water Results Samples were collected from on-site locations in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below:

Tritium Samples from 7 locations were analyzed for tritium activity. Tritium was found in 1 of 23 samples at a concentration of 211 pCi/L.

(Table B-II.1, Appendix B)

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions are not required on a routine basis and were not analyzed in 2020.

Gamma Emitters Gamma-emitting nuclide K-40 was detected at a concentration of 186 pCi/L in 1 of 3 samples analyzed during 2020. (Table B-II.2, Appendix B)

Hard-To-Detect Hard-To-Detect analyses are not required on a routine basis and were not analyzed in 2020.

D. Precipitation Water Results No precipitation samples were collected in 2020. (Table B-III.1, Appendix B)

E. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE and Environmental Inc.

(Midwest Labs) are presented in the 2020 Oyster Creek AREOR. This report is part of the AREOR.

F. Leaks, Spills, and Releases There were no abnormal liquid releases during 2020.

G. Trends Active remediation of tritium in groundwater due to the spills that occurred in 2009 was initiated in October 2010. Trending of the data due to active remediation is on-going. Continuous remediation was terminated in October 2019 with State of New Jersey concurrence. Overall, the station has seen a decreasing trend in tritium values to the point where ground water tritium is below the ODCM LLD (2,000 pCi/L) and the TBE lab MDL of 200 pCi/L in 33 monitoring wells.

H. Investigations GHD Services Inc. performed an independent assessment of the tritium plume. The results of their assessment can be found in References 1, 2 and 3.

I. Actions Taken

1. Compensatory Actions Active remediation of tritium in groundwater due to the spills that occurred in 2009 was initiated in October 2010. Due to the decrease in groundwater tritium as a result of the remediation project, continuous remediation was ceased in 2019. The Oyster Creek ODCM has provision to re-start remediation from this well, if necessary, via either continuous or batch discharge methods.

2. Installation of Monitoring Wells The following wells were installed in 2010 to better characterize and monitor the tritium plume and site hydrology:

Well Number Formation Well Installation Date W-58 I Cohansey July W-59 I Cohansey March W-60 I Cohansey July W-61 I Cohansey July W-62 Cape May March W-63 I Cohansey July W-64 Cape May March W-65 Cape May March W-66 I Cohansey July W-67 Cape May March W-68 I Cohansey July W-69 I Cohansey July W-70 I Cohansey July W-71 Cape May August W-72 Cape May August W-73 Cohansey October Pumping well

3. Actions to Recover/Reverse Plumes Oyster Creek Generating Station addressed the tritium in groundwater through continuous pumping of groundwater from of W-73 to the intake structure. Remediation of groundwater progressed to the stage where this program was terminated in the 4th quarter of 2019 with State of New Jersey concurrence. Should groundwater tritium levels regress initiating an adverse trend, the ODCM has provisions to restore ground water remediation using well 73 in batch or continuous mode.

V. References

1. Conestoga Rovers and Associates, Hydrogeologic Investigation Report, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 055875 (6), April 2011

2. Conestoga Rovers and Associates, Site Investigation Report, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 055875 (4), August 2009

3. Conestoga Rovers and Associates, Remedial Investigation Workplan, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 055875 (5),

October 2009 APPENDIX A LOCATION DESIGNATION

Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2020 Oyster Creek Generating Station RGPP Sample Point List RGPP Sample Well GPS Aquifer or Depth Sample Tritium Identification Location Coordinates Water Body (ft) Point Alert Value Number (Northing/Easting) Monitored Designation SW of MFOT 357380.76 MW-1A-2A 24.0 D 2,000 pCi/L Cape May Moat 575043.44 Roadway - NW 357598.17 MW-1I-1A 19.0 D 2,000 pCi/L Cape May of TWST 574412.70 Roadway - SE 357574.80 MW-1I-2A 17.5 D 2,000 pCi/L Cape May of TWST 574493.50 Roadway - 357297.90 MW-15K-1A 19.0 D 2,000 pCi/L Cape May Intake 574469.50 Yard - W of 357573.30 MW-16D 25.0 D 2,000 pCi/L Cape May MAC Building 574746.50 Surface SW-1 Intake Canal N/A N/A SW 2,000 pCi/L Water RT 9 South Surface SW-2 N/A N/A SW 2,000 pCi/L Bridge Water Surface SW-3 Fire Pond N/A N/A SW 2,000 pCi/L Water 358311.70 W-1A North Yard Area 50.0 B 2,000 pCi/L Cohansey 574679.00 Intake - Access 357173.00 24.0 W-3 D 2,000 pCi/L Cape May Road 574499.10 Intake - Access 357176.40 W-4 55.0 D 2,000 pCi/L Cohansey Road 574497.70 356913.30 SE of OCAB W-4A 575387.10 50.0 B 2,000 pCi/L Cohansey Building NW Yard area, 357510.95 W-5 near Fire Water 20.5 D 2,000 pCi/L Cape May 574374.05 Tank NW Yard - near 357514.02 W-6 52.0 D 2,000 pCi/L Cohansey Fire Water Tank 574373.77 Roadway - NE 357289.29 W-9 20.0 D 2,000 pCi/L Cape May of SAS Building 574892.74 Roadway - NE 357289.29 W-9 20.0 D 2,000 pCi/L Cape May of SAS Building 574892.74 NW of SAS 357286.29 W-10 60.0 D 2,000 pCi/L Cape May Building 574890.61 Yard - NW of 357669.10 W-12 20.0 D 2,000 pCi/L Cape May DWPC Building 574755.60 Yard - NW of 357666.00 W-13 50.0 D 2,000 pCi/L Cape May DWPC Building 574755.90 Yard - SW of 357702.41 W-14 53.0 D 2,000 pCi/L Cape May Warehouse 575018.75 Yard - SW of 357705.83 W-15 20.0 D 2,000 pCi/L Cape May Warehouse 575017.70 A-1

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2020 Oyster Creek Generating Station RGPP Sample Point List RGPP Sample Well GPS Aquifer or Depth Sample Tritium Identification Location Coordinates Water Body (ft) Point Alert Value Number (Northing/Easting) Monitored Designation Yard - E of 357967.26 W-16 20.0 D 2,000 pCi/L Cape May LLRW 574933.03 South of TB 357128.94 W-24 W of old 19.0 D 2,000 pCi/L Cape May 574650.77 Machine Shop South of TB 357196.14 W-34 W of old 40.0 D 2,000 pCi/L Cohansey 574649.43 Machine Shop Near Intake 357400.90 MW-52 20.0 D 2,000 pCi/L Cape May Structure 574353.00 Near end of CW 357272.80 MW-53 20.0 D 2,000 pCi/L Cape May discharge piping 574447.60 Near Intake 357276.20 MW-54 20.0 E 2,000 pCi/L Cape May Structure 574311.70 Between CST 357354.88 MW-55 and Intake 30.0 E 2,000 pCi/L Cape May 574440.07 Structure 357305.30 MW-56I By NaOCl tanks 52.0 E 2,000 pCi/L Cohansey 574465.50 Near Intake 357343.71 MW-57I 50.0 E 2,000 pCi/L Cohansey Structure 574373.89 Intake Roadway 357422.14 MW-59I 44.0 D 2,000 pCi/L Cohansey

- NW of CST 574406.38 Between CST 357328.64 MW-61I and Intake 72.0 E 2,000 pCi/L Cohansey 574444.45 Structure NW Corner of 357467.93 MW-62 25.0 D 2,000 pCi/L Cape May Turbine Bldg 574524.10 Near Intake 357343.96 MW-64 25.0 E 2,000 pCi/L Cape May Structure 574377.88 Intake Roadway 357421.00 MW-65 25.0 D 2,000 pCi/L Cape May

- NW of CST 574402.55 West side of 357401.99 MW-67 25.0 E 2,000 pCi/L Cape May Turbine Bldg 574540.38 SE of Reactor 357323.83 MW-68I 100.0 D 2,000 pCi/L Cohansey Bldg 574897.64 S of Reactor 357365.52 MW-71 25.0 D 2,000 pCi/L Cape May Bldg 574841.89 N of Reactor 357549.87 MW-72 25.0 D 2,000 pCi/L Cape May Bldg 574788.52 KEY: B = Background D = Detection E = Elevated I = Idle/Standby P = Plume L = Long-Term Shutdown SW = Surface Water A-2

Legend Shallow Wells COOS BN eonumimtian Nut Sampled Clean Well VDC canlsminalinn VOC and EN Conhmina"on 77 Deep Wells I BN Conn mlnslinn I Not Sammed I Clean Wall E C E A Boundary A. r-. an all. -:=r .u- u. l <<N umuxnnJVumuvubuwl:

Figure A-1 Sampling Locations - Selected Cohansey and Cape May Formation Wells, Oyster Creek Generating Station, 2020 A-3

Intentionally left blank APPENDIX B DATA TABLES

Intentionally left blank TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-1A-2A 05/21/20 < 176 MW-1I-1A 01/28/20 < 172 MW-1I-1A 05/20/20 < 171 < 7.7 < 0.8 < 0.4 1.8 +/- 1.0 2.4 +/- 0.6 < 1.6 MW-1I-1A 08/18/20 < 148 MW-1I-1A 10/14/20 < 176 MW-1I-2A 01/28/20 < 169 MW-1I-2A 05/20/20 < 179 < 3.2 < 0.8 < 0.3 < 0.6 1.0 +/- 0.5 < 1.7 MW-1I-2A 08/18/20 < 152 MW-1I-2A 10/14/20 < 177 MW-15K-1A 01/28/20 < 179 < 7.8 < 0.8 < 1.4 < 3.7 < 2.7 7.9 +/- 3.3 MW-15K-1A 05/19/20 < 171 < 4.0 < 0.6 < 0.8 4.2 +/- 1.2 2.7 +/- 1.2 2.9 +/- 1.3 MW-15K-1A 08/18/20 < 181 < 6.5 < 0.8 0.7 +/- 0.4 5.9 +/- 2.5 < 1.2 6.1 +/- 2.3 MW-15K-1A 10/13/20 < 171 < 7.5 < 0.8 < 0.6 < 3.6 3.1 +/- 0.9 10.7 +/- 2.8 MW-16D 01/29/20 < 171 MW-16D 05/20/20 < 174 < 4.3 < 0.7 < 0.7 < 0.6 2.5 +/- 0.8 < 1.7 MW-16D 05/20/20 Duplicate < 180 < 3.9 < 0.7 < 0.7 < 0.6 2.5 +/- 0.8 < 1.7 MW-16D 05/20/20 EIML < 157 < 0.5 < 0.5 < 0.8 (1)

MW-16D 08/19/20 < 151 MW-16D 10/13/20 < 177 MW-52 05/19/20 < 176 MW-53 05/19/20 Duplicate < 179 MW-54 05/19/20 283 +/- 120 MW-55 01/28/20 < 175 < 5.7 < 0.9 < 0.7 < 1.3 1.8 +/- 0.6 2.0 +/- 1.2 MW-55 05/19/20 < 179 < 3.2 < 0.8 < 0.4 < 1.8 1.3 +/- 0.7 3.4 +/- 1.8 MW-55 08/18/20 < 185 < 6.0 < 0.7 < 0.4 < 0.7 1.4 +/- 0.6 < 1.5 MW-55 10/13/20 < 184 < 6.6 < 0.8 < 0.6 < 1.1 1.3 +/- 0.6 < 1.5 MW-56I 01/28/20 < 178 < 6.9 < 0.8 < 0.6 1.9 +/- 1.1 4.5 +/- 0.8 < 1.6 MW-56I 05/19/20 < 177 < 6.0 < 0.9 < 0.3 < 1.4 4.1 +/- 0.7 < 2.2 MW-56I 08/18/20 458 +/- 130 < 2.8 < 0.7 < 0.4 < 0.7 3.0 +/- 0.7 < 3.2 MW-56I 10/13/20 939 +/- 166 < 6.8 < 0.8 < 0.9 < 1.2 4.5 +/- 0.9 2.3 +/- 1.1 MW-57I 01/28/20 668 +/- 141 < 7.1 < 0.9 < 1.4 < 1.6 19.5 +/- 1.6 4.0 +/- 1.4 MW-57I 05/19/20 555 +/- 133 < 5.8 < 0.8 < 0.7 5.7 +/- 1.8 4.9 +/- 1.2 6.9 +/- 1.6 MW-57I 08/18/20 738 +/- 148 < 5.1 < 0.7 < 0.6 2.4 +/- 1.2 8.5 +/- 1.1 4.0 +/- 1.4 MW-57I 10/13/20 2240 +/- 277 < 6.8 < 0.8 < 1.0 < 3.5 9.1 +/- 1.4 11.6 +/- 2.9 MW-59I 01/28/20 < 182 MW-59I 05/19/20 < 181 < 8.5 < 0.7 < 0.3 < 1.6 1.6 +/- 0.6 < 2.3 MW-59I 08/18/20 220 +/- 122 MW-59I 10/13/20 787 +/- 144 MW-61I 01/28/20 < 182 MW-61I 05/19/20 < 179 < 5.3 < 0.7 < 0.4 < 1.9 2.0 +/- 0.6 2.7 +/- 1.8 MW-61I 05/19/20 Duplicate < 178 < 6.0 < 0.8 < 0.3 < 1.8 2.0 +/- 0.6 3.8 +/- 1.8 MW-61I 05/19/20 EIML < 157 < 0.6 < 0.6 < 0.5 (1)

MW-61I 08/18/20 < 178 MW-61I 10/14/20 < 176 MW-62 01/28/20 < 180 MW-62 05/20/20 < 180 < 6.5 < 0.8 < 0.8 < 1.5 11.4 +/- 1.1 < 2.2 MW-62 08/18/20 < 181 MW-62 10/14/20 < 171 MW-64 01/28/20 < 178 MW-64 01/28/20 Duplicate < 179 MW-64 01/28/20 EIML < 153 MW-64 05/19/20 < 180 < 5.7 < 0.5 < 1.7 17.5 +/- 3.5 < 3.7 23.4 +/- 3.6 MW-64 05/19/20 Duplicate < 188 < 6.0 < 1.0 < 1.0 12.0 +/- 3.3 < 4.0 15.7 +/- 3.4 MW-64 05/19/20 EIML < 157 < 0.5 < 0.5 < 1.3 (1)

(1) Total Gross Alpha result reported (not dissolved/suspended)

B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-64 08/18/20 < 182 MW-64 08/18/20 Duplicate < 184 MW-64 08/18/20 EIML < 156 MW-64 10/13/20 < 172 MW-64 10/13/20 Duplicate < 180 MW-65 01/28/20 < 182 < 7.7 < 0.9 < 1.2 < 5.4 < 2.3 16.5 +/- 4.3 MW-65 05/19/20 < 175 < 4.7 < 0.7 < 3.5 18.4 +/- 5.2 < 8.3 22.4 +/- 6.6 MW-65 08/18/20 < 182 < 7.6 < 0.7 < 2.0 16.6 +/- 4.0 < 9.1 23.0 +/- 6.5 MW-65 10/13/20 < 189 < 7.3 < 0.8 < 1.6 7.1 +/- 2.0 < 2.3 11.4 +/- 2.0 MW-67 01/28/20 < 179 < 8.3 < 0.9 < 1.0 < 2.0 < 0.9 5.4 +/- 1.6 MW-67 05/20/20 < 180 < 6.3 < 0.8 < 0.5 < 1.8 4.0 +/- 0.7 < 2.4 MW-67 08/18/20 < 182 < 7.4 < 0.6 < 0.3 < 0.2 4.1 +/- 0.8 < 1.6 MW-67 10/14/20 197 +/- 118 < 8.3 < 0.9 < 0.5 < 0.5 4.7 +/- 0.7 < 1.7 MW-68I 08/19/20 < 178 MW-71 01/29/20 < 182 MW-71 01/29/20 Duplicate < 178 MW-71 01/28/20 EIML < 153 MW-71 05/21/20 < 180 < 7.6 < 0.8 < 0.7 < 2.3 < 1.3 < 3.0 MW-71 08/19/20 < 183 MW-71 08/19/20 Duplicate < 179 MW-71 08/19/20 EIML < 156 MW-71 10/13/20 < 194 MW-71 10/13/20 Duplicate < 190 MW-72 01/29/20 < 179 MW-72 05/20/20 < 180 < 7.9 < 0.8 < 0.5 < 1.3 2.3 +/- 0.7 < 2.2 MW-72 08/19/20 < 182 MW-72 10/13/20 < 190 W-1A 05/21/20 < 180 W-3 01/28/20 < 176 W-3 05/19/20 < 178 < 4.0 < 0.8 1.3 +/- 0.8 < 1.0 7.6 +/- 1.3 < 2.9 W-3 08/18/20 < 151 W-3 10/13/20 < 176 W-4 05/19/20 < 176 W-4A 05/21/20 < 178 W-5 01/28/20 < 171 W-5 01/28/20 Duplicate < 173 W-5 01/28/20 EIML < 153 W-5 05/20/20 < 177 < 8.0 < 0.9 < 0.4 < 0.6 2.3 +/- 0.7 < 1.7 W-5 05/20/20 Duplicate < 173 < 3.8 < 0.7 < 0.4 < 0.6 2.6 +/- 0.7 < 1.7 W-5 05/20/20 EIML < 157 < 0.6 < 0.6 < 0.5 (1)

W-5 08/18/20 < 152 W-5 08/18/20 Duplicate < 147 W-5 08/18/20 EIML < 156 W-5 10/14/20 < 181 W-5 10/14/20 Duplicate < 189 W-6 05/20/20 < 174 W-9 01/29/20 < 171 W-9 05/19/20 < 174 < 3.7 < 0.9 < 0.9 < 0.8 5.1 +/- 1.1 < 1.9 W-9 08/19/20 < 150 W-9 10/13/20 < 188 W-10 05/19/20 < 174 W-10 08/19/20 < 149 W-12 01/29/20 < 174 W-12 05/20/20 < 170 < 3.5 < 0.7 < 1.6 8.8 +/- 4.2 4.1 +/- 2.1 7.7 +/- 1.5 (1) Total Gross Alpha result reported (not dissolved/suspended)

B-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

W-12 08/19/20 < 186 W-12 10/13/20 < 194 W-13 05/20/20 < 174 W-14 05/20/20 < 180 W-15 05/20/20 < 169 W-16 05/20/20 < 178 W-24 05/21/20 < 175 W-34 01/28/20 < 178 W-34 05/19/20 < 175 < 4.0 < 0.6 < 0.3 < 0.6 < 0.9 < 1.7 W-34 08/18/20 < 186 W-34 10/13/20 < 198 B-3

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 MW-1A-2A 05/21/20 < 70 < 130 < 7 < 9 < 16 < 7 < 13 < 13 < 9 < 7 MW-1I-1A 05/20/20 < 68 < 118 < 7 < 8 < 16 < 8 < 13 < 12 < 8 < 8 MW-1I-2A 05/20/20 < 60 < 126 < 6 < 7 < 11 < 5 < 12 < 11 < 7 < 7 MW-15K-1A 01/28/20 < 15 < 16 < 2 < 2 < 4 < 2 < 4 < 3 < 2 < 2 MW-15K-1A 05/19/20 < 48 < 74 < 5 < 5 < 11 < 5 < 10 < 10 < 6 < 5 MW-15K-1A 08/18/20 < 56 < 120 < 7 < 6 < 11 < 8 < 13 < 16 < 8 < 7 MW-15K-1A 10/13/20 < 26 < 32 < 3 < 3 < 7 < 4 < 7 < 6 < 3 < 3 MW-16D 05/20/20 < 51 < 85 < 6 < 5 < 11 < 7 < 14 < 10 < 6 < 7 MW-16D 05/20/20 Duplicate < 59 < 96 < 5 < 5 < 11 < 6 < 10 < 10 < 5 < 5 MW-16D 05/20/20 EIML < 22 < 87 < 4 < 2 < 4 < 2 < 7 < 4 < 3 < 3 MW-52 05/19/20 < 43 < 109 < 5 < 5 < 12 < 5 < 9 < 10 < 5 < 6 MW-53 05/19/20 Duplicate < 49 < 100 < 5 < 7 < 9 < 7 < 12 < 10 < 5 < 5 MW-54 05/19/20 < 60 < 141 < 6 < 6 < 10 < 7 < 13 < 13 < 6 < 7 MW-55 01/28/20 < 17 < 20 < 2 < 2 < 4 < 2 < 4 < 3 < 2 < 2 MW-55 05/19/20 < 48 < 84 < 5 < 5 < 12 < 7 < 12 < 11 < 6 < 6 B-4 MW-55 08/18/20 < 69 < 129 < 6 < 7 < 17 < 8 < 14 < 12 < 8 < 7 MW-55 10/13/20 < 30 < 28 < 3 < 3 < 6 < 4 < 7 < 6 < 4 < 4 MW-56I 01/28/20 < 16 < 16 < 2 < 2 < 4 < 2 < 4 < 3 < 2 < 2 MW-56I 05/19/20 < 56 < 38 < 6 < 7 < 16 < 6 < 15 < 12 < 8 < 7 MW-56I 08/18/20 < 53 < 131 < 6 < 5 < 12 < 8 < 11 < 11 < 6 < 7 MW-56I 10/13/20 < 26 < 32 < 3 < 3 < 6 < 3 < 7 < 5 < 3 < 3 MW-57I 01/28/20 < 16 < 18 < 2 < 2 < 3 < 2 < 3 < 3 < 2 < 2 MW-57I 05/19/20 < 49 < 106 < 5 < 6 < 11 < 4 < 9 < 10 < 6 < 6 MW-57I 08/18/20 < 55 < 65 < 6 < 5 < 13 < 7 < 11 < 12 < 8 < 6 MW-57I 10/13/20 < 23 < 44 < 3 < 3 < 5 < 2 < 5 < 4 < 3 < 3 MW-59I 05/19/20 < 61 < 120 < 5 < 5 < 15 < 6 < 12 < 11 < 6 < 7 MW-61I 05/19/20 < 40 < 101 < 5 < 6 < 12 < 5 < 8 < 9 < 5 < 4 MW-61I 05/19/20 Duplicate < 56 < 144 < 7 < 7 < 14 < 8 < 12 < 14 < 7 < 7 MW-61I 05/19/20 EIML < 25 < 76 < 3 < 3 < 3 < 2 < 3 < 3 < 2 < 3 MW-62 05/20/20 < 54 < 122 < 6 < 7 < 15 < 6 < 14 < 9 < 6 < 6 MW-64 05/19/20 < 17 < 19 < 2 < 2 < 4 < 2 < 4 < 3 < 2 < 2 MW-64 05/19/20 Duplicate < 40 < 99 < 5 < 4 < 10 < 5 < 10 < 8 < 5 < 5 MW-64 05/19/20 EIML < 18 < 41 < 2 < 2 < 4 < 1 < 4 < 4 < 2 < 2 MW-65 01/28/20 < 15 < 15 < 2 < 2 < 4 < 2 < 3 < 3 < 2 < 2 MW-65 05/19/20 < 52 < 101 < 6 < 6 < 12 < 6 < 10 < 9 < 6 < 6 MW-65 08/18/20 < 58 < 85 < 6 < 7 < 10 < 7 < 10 < 11 < 8 < 6

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 MW-65 10/13/20 < 25 < 29 < 3 < 3 < 6 < 3 < 6 < 5 < 3 < 3 MW-67 01/28/20 < 15 < 30 < 2 < 2 < 4 < 2 < 4 < 3 < 2 < 2 MW-67 05/20/20 < 48 < 50 < 5 < 6 < 10 < 7 < 13 < 9 < 6 < 5 MW-67 08/18/20 < 59 < 65 < 6 < 7 < 16 < 8 < 13 < 10 < 6 < 8 MW-67 10/14/20 < 25 < 57 < 3 < 3 < 7 < 3 < 7 < 5 < 4 < 3 MW-71 05/21/20 < 54 < 130 < 6 < 6 < 10 < 9 < 15 < 11 < 6 < 6 MW-72 05/20/20 < 48 < 95 < 4 < 4 < 11 < 6 < 10 < 11 < 5 < 5 W-1A 05/21/20 < 60 < 107 < 8 < 6 < 15 < 7 < 14 < 13 < 7 < 7 W-3 05/19/20 < 57 < 106 < 5 < 7 < 13 < 6 < 14 < 10 < 7 < 6 W-4 05/19/20 < 60 < 81 < 6 < 7 < 16 < 7 < 12 < 10 < 7 < 5 W-4A 05/21/20 < 53 < 101 < 8 < 6 < 11 < 9 < 12 < 14 < 6 < 5 W-5 05/20/20 < 56 < 135 < 6 < 6 < 13 < 6 < 15 < 12 < 6 < 7 W-5 05/20/20 Duplicate < 52 < 111 < 6 < 3 < 4 < 5 < 14 < 11 < 8 < 6 W-5 05/20/20 EIML < 32 < 66 < 2 < 3 < 4 < 1 < 4 < 4 < 3 < 2 B-5 W-6 05/20/20 < 61 < 45 < 5 < 7 < 13 < 4 < 9 < 10 < 7 < 7 W-9 05/19/20 < 56 < 102 < 7 < 7 < 17 < 5 < 15 < 14 < 7 < 6 W-10 05/19/20 < 60 < 103 < 6 < 8 < 12 < 6 < 12 < 12 < 8 < 7 W-12 05/20/20 < 65 < 141 < 7 < 5 < 8 < 9 < 13 < 12 < 10 < 7 W-13 05/20/20 < 48 < 82 < 4 < 4 < 13 < 5 < 8 < 8 < 6 < 4 W-14 05/20/20 < 45 < 97 < 6 < 5 < 12 < 6 < 9 < 8 < 6 < 6 W-15 05/20/20 < 48 < 120 < 7 < 6 < 10 < 5 < 13 < 11 < 7 < 7 W-16 05/20/20 < 52 < 49 < 5 < 8 < 13 < 5 < 9 < 11 < 5 < 6 W-24 05/21/20 < 66 < 105 < 7 < 7 < 14 < 7 < 15 < 12 < 7 < 6 W-34 05/19/20 < 63 < 116 < 7 < 8 < 18 < 6 < 15 < 12 < 8 < 7

TABLE B-I.3 CONCENTRATIONS OF HARD-TO-DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 MW-65 08/18/20 < 0.19 < 0.07 < 0.19 < 0.13 < 0.09 2.5 +/- 0.7 < 0.19 2.3 +/- 0.7 < 101 < 4.9 MW-65 08/18/20 Reanalysis 1.5 +/- 0.4 < 0.08 2.1 +/- 0.5 B-6

TABLE B-II.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATE H-3 SECURITY STORM DRAIN 03/09/20 < 192 SEWER PIT 01/27/20 < 200 SEWER PIT 04/14/20 < 173 SEWER PIT 07/17/20 < 189 SEWER PIT 10/02/20 < 195 STORM DRAIN EAST 01/27/20 < 190 STORM DRAIN EAST 08/17/20 < 179 STORM DRAIN EAST 10/13/20 < 188 STORM DRAIN OUTFALL #2 01/15/20 < 193 STORM DRAIN OUTFALL #2 03/09/20 < 191 STORM DRAIN OUTFALL #2 08/17/20 < 186 STORM DRAIN OUTFALL #2 10/12/20 < 197 SW-1 01/27/20 < 184 SW-1 05/18/20 < 179 SW-1 08/17/20 < 180 SW-1 10/12/20 < 191 SW-2 01/27/20 < 176 SW-2 05/18/20 < 192 SW-2 08/17/20 < 182 SW-2 10/12/20 < 185 SW-3 01/27/20 < 194 SW-3 05/18/20 < 188 SW-3 08/17/20 < 183 SW-3 10/12/20 < 189 B-7

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 SW-1 05/18/20 < 25 186 +/- 48 < 3 < 3 < 7 < 3 < 6 < 5 < 4 < 3 SW-2 05/18/20 < 27 < 50 < 2 < 3 < 6 < 3 < 6 < 6 < 3 < 3 SW-3 05/18/20 < 27 < 54 < 3 < 3 < 7 < 3 < 6 < 6 < 3 < 3 B-8

TABLE B-II.3 CONCENTRATIONS OF HARD TO DETECTS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 NONE FOR 2020 B-9

TABLE B-III.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2020 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATE H-3 NONE FOR 2020 B-10