Text

Annual Radioactive Environmental Operating Report for 2022
	ML23114A087
Person / Time
Site:	Oyster Creek
Issue date:	04/24/2023
From:	Fleming J; Holtec Decommissioning International
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	HDI-OC-23-024
	Download: ML23114A087 (1)
	v • d • e

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 HDI-OC-23-024 10 CFR 50 Appendix I April 24, 2023 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 2022 Enclosed with this cover letter is the Annual Radioactive Environmental Operating Report for the calendar year 2022 for the Oyster Creek Nuclear Generating Station. This submittal is made in accordance with the Oyster Creek Nuclear Generating Stations Defueled Safety Analysis Report (DSAR) Appendix B, paragraph B.2.1.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, Jean A. Fleming Vice President, Licensing, Regulatory Affairs, & PSA Holtec International 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 Jean A. Fleming Digitally signed by Jean A.

Fleming Date: 2023.04.24 09:48:34 -04'00'

Docket No: 50-219 OYSTER CREEK GENERATING STATION UNIT 1 Annual Radiological Environmental Operating Report 1 January through 31 December 2022 Prepared By Teledyne Brown Engineering Environmental Services Oyster Creek Generating Station Forked River, NJ 08731 April 2023

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i 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............................................................................................. 20 IV. Results and Discussion............................................................................................... 21 A. Aquatic Environment......................................................................................... 21 B. Atmospheric Environment................................................................................. 24 C. Ambient Gamma Radiation............................................................................... 27 D. Land Use Survey............................................................................................... 27 E. Summary of Results - Inter-laboratory Comparison Program.......................... 28 V. References................................................................................................................... 31 VI. Errata........................................................................................................................... 31

ii Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Oyster Creek Generating Station, 2022 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, 2022 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Oyster Creek Generating Station, 2022 Figures Figure B-1 Locations of REMP Stations within a 1-mile radius of the Oyster Creek Generating Station, 2022 Figure B-2 Locations of REMP Stations within a 1 to 5-mile radius of the Oyster Creek Generating Station, 2022 Figure B-3 Locations of REMP Stations greater than 5 miles from the Oyster Creek Generating Station, 2022 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, 2022 Table C-I.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-II.1 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-II.2 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-II.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-III.1 Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022

iii Table C-III.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-IV.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-IV.2 Concentrations of Gamma Emitters in Clam and Crab Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-VI.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 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, 2022 Table C-VI.3 Concentrations of Strontium in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-VI.4 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-VII.1 Concentrations of Strontium and Gamma Emitters in Vegetation Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table C-VIII.1 Quarterly OSLD Results for Oyster Creek Generating Station, 2022 Table C-VIII.2 Mean Quarterly OSLD Results for the Site Boundary, Intermediate, Special Interest, and Control Locations for Oyster Creek Generating Station, 2022 Table C-VIII.3 Summary of the Ambient Dosimetry Program for Oyster Creek Generating Station, 2022 Figures Figure C-1 Mean Cobalt-60 Concentration in Clams Oyster Creek Generating Station, 1983 - 2022 Figure C-2 Mean Cobalt-60 Concentration in Aquatic Sediment Oyster Creek Generating Station, 1984 - 2022 Figure C-3 Mean Cesium-137 Concentration in Aquatic Sediment Oyster Creek Generating Station, 1984 - 2022 Figure C-4 Mean Weekly Gross Beta Concentrations in Air Particulates Oyster Creek Generating Station, 2008 - 2022 Figure C-5 Mean Monthly Gross Beta Concentrations in Air Particulates Oyster Creek Generating Station, 1984 - 2022 Figure C-6 Mean Quarterly OSLD Gamma Dose Oyster Creek Generating Station, 2022

iv 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, 2022 Table D-I.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table D-II.1 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table D-II.2 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table D-II.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table D-III.1 Concentrations of Gamma Emitters in Clam Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table D-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Table D-V.1 Concentrations of Strontium and Gamma Emitters in Vegetation Samples Collected in the Vicinity of Oyster Creek Generating Station, 2022 Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2022 Table E-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2022 Table E-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2022 Table E-4 DOEs Mixed Analyte Performance Evaluation Program (MAPEP),

ATI Environmental, Inc. Midwest Laboratory, 2022 Table E-5 Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) RAD Study, ATI Environmental, Inc.

Midwest Laboratory, 2022 Appendix F Errata Data Appendix G Annual Radiological Groundwater Protection Program Report (ARGPPR)

1 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.

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

2 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 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.

3 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.

4 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.

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

5 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.

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

6 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%.

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 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

7 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 This simple diagram demonstrates some potential exposure pathways from Oyster Creek Generating Station.

8 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.

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

9 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, when 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.

10 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. 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.

11 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 2022 through 31 December 2022. During that time period, a total of 968 analyses were performed on 712 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 2022.

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), 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.

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

12 detected. All Sr-89 results were below the minimum detectable activity.

Strontium-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).

13 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 2022 through 31 December 2022.

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

14 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.

15 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 Environmental Protection Agency (EPA).

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

16 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 2022. 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 comprised of the flesh of predators and bottom feeders were collected semiannually at two locations (33 and 93) and annually at control location 94. 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 air particulate samples. Air particulate samples were collected and analyzed bi-weekly at seven locations (C, 20, 66, 71, 72, 73, and 111).

The control location was C. The samples were obtained at each location, using a vacuum pump with 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.

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 plant when the plant was operating, and while it is permanently shut down for

17 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 2022. The analytical procedures used by the laboratories are listed in Table B-3.

18 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 strontium in air particulates and vegetation Iodine analysis was discontinued beginning with the second calendar quarter of 2020. The iodine isotopes of interest (I-131, I-132, I-133, I-134, & I-135) have short half-lives and are generated by the nuclear fission process. No iodines were produced after permanent cessation of operation in September 2018. After they have undergone radioactive decay, there is no basis for sampling to detect them.

C. Data Interpretation For trending purposes, the radiological and direct radiation data collected during 2022 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 (a priori) estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact (a posteriori) 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.

19

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, 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 - six nuclides:

Mn-54, Co-60, Zn-65, Zr-95, Cs-134 and Cs-137 were reported.

For fish - six nuclides: K-40, Mn-54, Co-60, Zn-65, Cs-134, and Cs-137 were reported.

For clams - six nuclides: K-40, Mn-54, Co-60, Zn-65, Cs-134, and Cs-137 were reported.

For crabs - six nuclides: K-40, Mn-54, Co-60, Zn-65, Cs-134, and Cs-137 were reported.

For sediment - eight nuclides: Be-7, K-40, Mn-54, Co-60, Cs-134, Cs-137, Ra-226, and Th-228 were reported.

For air particulates - five nuclides: Be-7, Mn-54, Co-60, Cs-134, and Cs-137 were 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 2022, the OCGS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

Environmental Dosimetry

1. 07/07/22: TLD Q2 TLDs not found due to weed/brush overgrowth and Q3 TLDs not deployed. The TLDs were found during Q4 deployment.

2. 07/07/22: TLD Station was found empty. The resident closest to the station hung one TLD on the pole by a wire and the other TLD was lost. Q3 TLDs deployed with additional closure spring.

20 Air

1. 02/03/22: Station 72 - Sample pump found idle and unable to reset.

Sample was valid - no lost sample.

2. 09/08/22: Station C - While performing the week 40 sample collection, the station blew its fuse. Fuses replaced - no missed sample.

3. 12/13/22: Station 71 - While performing the bi-weekly sample collection, the pump was found not running. Spare pump installed and no sample was missed.

4. 12/13/22: Station 66 - The area power outage caused ~ 69 hours7.986111e-4 days 0.0192 hours 1.140873e-4 weeks 2.62545e-5 months of sample time to be lost. Sufficient sample was collected for analysis and no sample was lost.

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.

2022: Station 1S was not operational for the entire year.

03/24/22: Station 1N - The sample received at the QC lab was nearly empty with a loose cap. No additional sample to re-send. Will add waterproof tape around cap to prevent loosening in transit. (IR-OYS-02598)

Ground Water 02/01/22: One quarterly groundwater sample from MW-24-3A & W-3C were missed in the 2022 sample period. These wells are collected quarterly per the ODCM. During a change in frequency of sampling for RGPP wells, the vendor mistakenly assumed the same frequency change for REMP wells. This miscommunication was corrected and the quarterly samples for the 2nd, 3rd and 4th quarters were collected on schedule. (IR-OYS-03202)

Vegetation 2022 Season: No crop was recovered from the following stations:

Station 115 - cabbage (June, July), kale (June, August, September);

Station 66 - kale (June); and Station 36 - kale (June, July)

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 There were no program changes in 2022.

21 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.

Instrument improvements lowered the detection range to 200 pCi/L which was used to monitor tritium in ground water as a result of process leaks.

The MDC was changed to 2,000 pCi/L in November 2020 to reflect the reduction of risk since the plant has started actively decommissioning.

By comparing the 2022 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 grab samples were taken from three drinking water wells (1N, 37 and 38). 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, a Lacey Township Municipal Utility Authority well, is not likely to be impacted by effluents from the OCGS. This well is located generally up-gradient of the regional groundwater flow direction (southeast). In addition, because of the depth

22

(> 200 feet) and distance from the site (2.2 miles), it is 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 2022 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 22 of 36 samples and is attributed to natural sources and fallout residual from previous bomb testing. The values ranged from 1.7 to 3.5 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 predators (American eel, bullnose ray, striped bass, white perch, smooth dogfish, mullet 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 detected in 12 of

23 13 samples and ranged from 2,622 to 3,953 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 1,041 to 2,047 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 both stations with concentrations ranging from 2,093 to 2,428 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 detected in 8 of 10 samples ranged from 732 to 12,260 pCi/kg dry. Naturally occurring Th-228 was found at all 4 stations and ranged from 138 to 504 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)

24 The Figure C-3, Appendix C graph shows Cs-137 concentrations in sediment from 1984 through 2022 and Figure C-2, Appendix C graph shows Co-60 concentrations in sediment from 1984 through 2022.

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 2022 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 2022 and no adverse long-term trends are shown in the aquatic monitoring data.

B. Atmospheric Environment

1.

Airborne (Air Particulates)

Continuous air particulate samples were collected from seven locations on a bi-weekly basis. The seven 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). 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 28E-03 pCi/m3 with a mean of 16E-03 pCi/m3. The results from the Intermediate Distance locations (Group II) ranged from 6E-03 to 29E-03 pCi/m3 with a mean of 15E-03 pCi/m3. The results from the Distant locations (Group III) ranged from 7E-03 to 26E-03 pCi/m3 with a mean of 17E-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

25 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 2022 gross beta activity values ranged from <3E-03 to 29E-03 pCi/m3. The 2022 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-90 Samples were composited quarterly and analyzed for 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-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 28 of 28 samples. The values ranged from 42E-03 to 98E-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.

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 29 of 46 samples. The values ranged from 3.8 to 18.5 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 https://www.nrc.gov/docs/ML0721/ML072150423.pdf 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

26 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 1,119 to 6,648 pCi/kg wet. Naturally occurring Be-7 was detected in 2 of 46 samples and ranged from 192 to 459 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 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. Cesium-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,

27 nearly four miles from the OCGS, yields present-day Cs-137 concentrations ranging from 0.862 to 1.68 pCi/g.

In 2022, 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 2022 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 Luminescence Dosimeters (OSLD). Forty-four OSLD locations were monitored around the site with all measurements below 29 mRem/yr. Results of background corrected OSLD measurements are summarized in Tables C-IX.1 to C-IX.3 and Figure C-6.

The non-background corrected OSLD measurements ranged from 14.7 to 36.0 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 2022 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 2022 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

28 locations from the OCGS Reactor Building were determined using Global Positioning System (GPS) technology.

Gardens were in 13 of the 16 sectors. One change from the 2021 census -

two sectors with a garden closer to the plant were found in NNE and S sectors.

Seventeen new gardens previously not identified were noted within 3 miles of the facility. The results of this survey are summarized below:

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.

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

Garden* (ft.)

1 N

5,655 6,077 2

NNE 3,240 3,381 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 4,872 9

S 7,971 8,594 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 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, 142 out of 150 analyses performed met the specified acceptance criteria. Eight analyses did not meet the specified acceptance criteria and were addressed through the TBE Corrective Action Program.

NOTE: Two analyses (soil for Tc-99 and U-238) that did not meet acceptance criteria was performed for TBE information and is not on the list of required ICP analyses. A summary is found below:

1. The Analytics March 2022 AP Ce-141 result was evaluated as Not Acceptable. The reported value for Ce-141 was 60.9 pCi and the known result was 42.0 pCi/L (1.45 ratio of reported result vs. known; TBEs internal acceptance range is 0.70 - 1.30). This sample was used as the workgroup duplicate with a result of 45.7 (109% of known) and was also counted on a different detector with a result of 50.9 (121% of known).

This was TBEs first failure for AP Ce-141. (NCR 22-04)

2. The MAPEP February 2022 Urine U-234 & U-238 results were evaluated as Not Acceptable. TBEs reported values of 0.142 and 0.0254 were above the known upper ranges of 0.0096 and 0.0134 respectively for U-234 and U-238. These spiked values were below TBEs typical MDC for urine client samples. The samples were re-prepped using a larger sample

30 aliquot and counted for 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months as opposed to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The recount results were 0.00732 for U-234 and 0.0119 for U-238 (both within acceptable range). MAPEP urine samples will be flagged to use a larger sample aliquot and counting time than typical client samples. MAPEP did not include any urine cross-check samples in August. (NCR 22-05)

3. The ERA MRAD September 2022 AP Pu-238 was evaluated as Not Acceptable. The reported value was 38.8 pCi and the known result was 29.9 (acceptance range 22.6 - 36.7). The AP filter was cut in half prior to digestion (shared with Fe-55) but should have been complete digested together and aliquotted afterwards like typical client samples. This is the first failure for AP Pu-238. (NCR 22-19)

4. The ERA October 2022 water Uranium result was evaluated as Not Acceptable. The reported value was 10.54 pCi/L and the known was 8.53 (acceptance range 6.60 - 9.88) or 124% of the known (acceptable for TBE QC). The 2-sigma error was 3.2, placing the reported result well within the acceptable range. This sample was used as the workgroup duplicate with a result of 8.2 +/- 2.9 pCi/L (also within the acceptable range). All other QA was reviewed with no anomalies. (NCR 22-20)

5. The Analytics AP Co-60 result was evaluated as Not Acceptable. The reported value was 207 pCi and the known was 147 (141% of the known).

TBEs internal QC acceptance is 70 - 130%. All QA was reviewed with no anomalies. This sample was used as the workgroup duplicate and counted on a different detector with a result of 167 pCi (114% of the known). This is the first failure for AP Co average result ratio compared to the known is 109%. (NCR 22-21)

6. The MAPEP August 2022 water Tc-99 result was evaluated as Not Acceptable. The reported value was 1.86 +/- 0.414 Bq/L for this false positive test. The evaluation of the submitted result to the 3 times the uncertainty indicated a slight positive. This sample was used as the workgroup duplicate with a result of 0.88 +/- 0.374 Bq/L. All QC was reviewed, and no anomalies found. This is the first unacceptable since the resumption of reporting water Tc-99 for the 3rd quarter of 2020. TBE to known ratios have ranged from 94-109% during this time. (NCR 22-22)

Some environmental samples collected are sent to an independent lab from the Primary as a QC measure. For these secondary QC samples, Environmental Inc., Midwest Laboratories (EIML) analyzed samples for H-3, Gross Beta, Sr-90 and gamma nuclides (REMP). In addition, EIML performed Sr-89 and Gross Alpha analyses for the ARGPP (see Appendix H, Appendix B). For these nuclides, 50 out of 51 analyses performed met the specified acceptance criteria. The ERA January 2022 water Cs-137 did not meet ERAs acceptance criteria. It is believed that detector drift could have contributed to the original Cs-135 result landing outside the upper acceptance limit.

31 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 There was no errata data for 2022.

Intentionally left blank

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER:

50-219 LOCATION OF FACILITY: OCEAN COUNTY, NJ REPORTING PERIOD:

2022 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M)

MEAN (M)

STATION #

NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (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-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

DRINKING WATER H-3 36 2000

<LLD

<LLD 0

(PCI/LITER)

GR-B 36 4

2.3 2.6 2.6 37 CONTROL 0

(12/24)

(10/12)

BOOX RD AT LACEY MUA PUMPING STA 1.7 - 3.1 1.9 - 3.5 1.9 - 3.5 2.2 MILES NNE OF SITE GAMMA 36 MN-54 15

<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 6

2000

<LLD NA 0

(PCI/LITER)

GAMMA 6

MN-54 15

<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

FISH (BOTTOM FEEDER)

GAMMA 2

(PCI/KG WET)

K-40 NA 2757 NA 2757 33 INDICATOR 0

(2/2)

EAST OF RT 9 BRIDGE IN OCGS DISCHARGE 2622 - 2891 2622 - 2891 0.4 MILES ESE OF SITE MN-54 130

<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

LOCATION WITH HIGHEST ANNUAL MEAN (M)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2022 (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

A-1

NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER:

50-219 LOCATION OF FACILITY: OCEAN COUNTY, NJ REPORTING PERIOD:

2022 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M)

MEAN (M)

STATION #

NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F)

(F)

NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD)

RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS LOCATION WITH HIGHEST ANNUAL MEAN (M)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2022 FISH (PREDATOR)

GAMMA 11 (PCI/KG WET)

K-40 NA 3182 3449 3449 94 CONTROL 0

(10/10)

(1/1)

GREAT BAY/LITTLE EGG HARBOR 2720 - 3953 20.0 MILES SSW OF SITE MN-54 130

<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 1534 1163 1713 23 INDICATOR 0

(4/4)

(3/3)

(2/2)

BARNEGAT BAY OFF STOUTS CREEK 1270 - 2047 1041 - 1336 1379 - 2047 3.6 MILES ENE OF SITE MN-54 130

<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

CRABS GAMMA 2

(PCI/KG WET)

K-40 NA 2261 NA 2428 33 INDICATOR 0

(2/2)

(1/1)

EAST OF RT 9 BRIDGE IN OCGS DISCHARGE 2093 - 2428 0.4 MILES ESE OF SITE MN-54 130

<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

SEDIMENT GAMMA 10 (PCI/KG DRY)

BE-7 NA

<LLD

<LLD 0

K-40 NA 2332 8642 12210 94 CONTROL 0

(5/6)

(3/4)

(2/2)

GREAT BAY/LITTLE EGG HARBOR 732 - 5110 1505 - 12260 12160 - 12260 20.0 MILES SSW OF SITE MN-54 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

<LLD

<LLD 0

Th-228 NA 206 329 453 94 CONTROL (6/6)

(4/4)

(2/2)

GREAT BAY/LITTLE EGG HARBOR 0

138 - 270 175 - 504 402 - 504 20.0 MILES SSW OF SITE (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

A-2

NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER:

50-219 LOCATION OF FACILITY: OCEAN COUNTY, NJ REPORTING PERIOD:

2022 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M)

MEAN (M)

STATION #

NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F)

(F)

NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD)

RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS LOCATION WITH HIGHEST ANNUAL MEAN (M)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2022 AIR PARTICULATE GR-B 182 10 15 17 17 C CONTROL 0

(E-3 PCI/CU.METER)

(155/156)

(25/26)

JCP&L OFFICE - COOKSTOWN NJ 5 - 29 7 - 26 7 - 26 24.7 MILES NW OF SITE SR-90 28 10

<LLD

<LLD 0

GAMMA 28 BE-7 NA 59 60 69 66 INDICATOR 0

(24/24)

(4/4)

EAST OF RT 9 AND SOUTH OF OCGS DISCHG 42 - 98 54 - 66 53 - 98 0.4 MILES SE OF SITE MN-54 NA

<LLD

<LLD 0

CO-60 NA

<LLD

<LLD 0

CS-134 50

<LLD

<LLD 0

CS-137 60

<LLD

<LLD 0

VEGETATION SR-89 46 25

<LLD

<LLD 0

(PCI/KGWET)

SR-90 46 5

8.6 12.1 12.1 36 CONTROL 0

(23/33)

(6/13)

U-PICK FARM - NEW EGYPT NJ 3.8 - 18.5 8.1 - 16.3 8.1 - 16.3 23.1 MILES NW OF SITE GAMMA 46 BE-7 NA 325

<LLD 459 35 INDICATOR 0

(2/33)

(1/13)

EAST OF RT 9 AND NORTH OF OCGS DISCHG 192 - 459 0.4 MILES ESE OF SITE K-40 NA 3551 3514 5303 66 INDICATOR 0

(33/33)

(13/13)

(12/12)

EAST OF RT 9 AND SOUTH OF OCGS DISCHG 1119 - 6648 2265 - 5402 4153 - 6648 0.4 MILES SE OF SITE CS-134 60

<LLD

<LLD 0

CS-137 80

<LLD

<LLD 0

DIRECT RADIATION OSLD-QUARTERLY 380 NA 20.9 20.9 28.1 55 INDICATOR 0

(MILLIREM/STD.MO.)

(376/376)

(4/4)

SOUTHERN AREA STORES SECURITY FENCE 17.0 - 27.1 13.1 - 29.9 23.0 - 36.0 0.3 MILES W (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

A-3

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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 AQS = Aquatic Sediment Crab

= Crab DW

= Drinking Water Fish

= Fish GW

= Ground Water SWA = Surface Water OSLD = Optically Stimulated VEG

= Vegetation Luminescence Dosimetry 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, 2022 Sample Medium Station Code Distance (miles)

Azimuth (degrees)

Description 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 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, OSLD C

24.7 313 NW of site, JCP&L office in rear parking lot, Cookstown, NJ APT 20 0.7 95 East of site, on Finninger Farm on south side of access road, Forked River, NJ OSLD 22 1.6 145 SE of site, on Long John Silver Way, Skippers Cove, Waretown, NJ SWA, CLAM, AQS 23 3.6 64 ENE of site, Barnegat Bay off Stouts Creek, approximately 400 yards SE of 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, FISH, CRAB 33 0.4 123 ESE of site, east of Route 9 Bridge in OCGS Discharge Canal 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 OSLD 54 0.3 288 WNW of site, on the access road to Forked River site, Forked River, NJ B-2

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Oyster Creek Generating Station, 2022 Sample Medium Station Code Distance (miles)

Azimuth (degrees)

Description OSLD 55 0.3 263 West of site, on Southern Area Stores security fence, west of OCGS Switchyard, Forked River, NJ OSLD 56 0.3 249 WSW of site, on utility pole east of Southern Area Stores, west of the OCGS Switchyard, 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 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, OSLD, VEG 66 0.4 133 SE of site, east of Route 9 and south of the OCGS Discharge Canal, inside fence, Waretown, NJ OSLD 68 1.3 266 West of site, on Garden State Parkway North at mile marker 71.7, Lacey Township, NJ APT, OSLD 71 1.6 164 SSE of site, on Route 532 at the Waretown Municipal Building, Waretown, NJ APT, OSLD 72 1.9 25 NNE of site, on Lacey Road at Knights of Columbus Hall, Forked River, NJ APT, 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 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 B-3

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Oyster Creek Generating Station, 2022 Sample Medium Station Code Distance (miles)

Azimuth (degrees)

Description SWA, AQS, CLAM, FISH 94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor 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 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 B-4

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Oyster Creek Generating Station, 2022 Sample Medium Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Drinking Water Gamma Spectroscopy Monthly samples ER-OCGS-06, Collection of water samples for radiological analysis CY-OC-120-1200, REMP sample collection procedure - well water 1 gallon TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Drinking Water Tritium Monthly samples ER-OCGS-06, Collection of water samples for radiological analysis CY-OC-120-1200, REMP sample collection procedure - well water 1 gallon TBE, TBE-2011 Tritium in Drinking Water by Liquid Scintillation Env. Inc., T-02 Determination of tritium in water (direct method)

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

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

TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Clams and Crabs Gamma Spectroscopy Semi-annual and annual samples collected using clam tongs and traps.

ER-OCGS-16, Collection of clam and crab samples for radiological analysis 300 grams (wet)

TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis B-5

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Oyster Creek Generating Station, 2022 Sample Medium Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Sediment Gamma Spectroscopy Semi-annual grab samples ER-OCGS-03, Collection of aquatic sediment samples for radiological analysis 1000 grams (dry)

TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Particulates Gross Beta Two-week composite of continuous air sampling through glass fiber filter paper ER-OCGS-05, Collection of air iodine and air particulate samples for radiological analysis 1 filter (approximately 300 cubic meters weekly)

TBE, TBE-2008 Gross alpha and/or beta activity in various matrices Air Particulates Gamma Spectroscopy Quarterly composite of each station TBE, TBE-2023 Compositing of samples Env. Inc., AP-03 Procedure for compositing air particulate filters for gamma spectroscopic analysis 13 filters (approximately 4000 cubic meters)

TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Air Particulates Strontium-90 Quarterly composite of each station ER-OCGS-05, Collection of air iodine and air particulate samples for radiological analysis 13 filters (approximately 4000 cubic meters)

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

ER OCGS-02, Collection/Exchange of Field Dosimeters for Radiological Analysis 2 dosimeters Landauer Incorporated B-6

Figure B-1 Locations of REMP Stations within a 1-mile radius of the Oyster Creek Generating Station, 2022 B-7

Figure B-2 Locations of REMP Stations within a 1 to 5-mile radius of the Oyster Creek Generating Station, 2022 B-8

Figure B-3 Locations of REMP Stations greater than 5 miles from the Oyster Creek Generating Station, 2022 B-9

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APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

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Table C-I.1 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 23 24 33 94 01/25/22 - 01/26/22

< 191

< 181 02/23/22 - 02/23/22

< 189

< 178 03/22/22 - 03/22/22

< 293

< 274 04/19/22 - 04/19/22

< 270

< 248 05/23/22 - 05/24/22

< 183

< 180

< 500

< 518 06/23/22 - 06/23/22

< 293

< 338 07/28/22 - 07/28/22

< 507

< 498 08/17/22 - 08/17/22

< 493

< 495 09/22/22 - 09/22/22

< 559

< 536 10/10/22 - 10/10/22

< 185

< 188

< 572

< 616 11/22/22 - 11/22/22

< 538

< 530 12/28/22 - 12/28/22

< 181

< 188 MEAN CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 C-1

Table C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 23 05/24/22 - 05/24/22

< 6

< 8

< 13

< 7

< 8 10/10/22 - 10/10/22

< 3

< 6

< 5

< 3

< 3 MEAN 24 05/23/22 - 05/23/22

< 7

< 14

< 10

< 7

< 7 10/10/22 - 10/10/22

< 6

< 11

< 9

< 6

< 6 MEAN 33 01/26/22 - 01/26/22

< 6

< 5

< 9

< 10

< 5

< 5 02/23/22 - 02/23/22

< 6

< 7

< 15

< 12

< 8

< 7 03/22/22 - 03/22/22

< 7

< 14

< 8

< 5

< 7 04/19/22 - 04/19/22

< 5

< 7

< 12

< 11

< 5

< 6 05/25/22 - 05/25/22

< 4

< 5

< 16

< 10

< 7

< 7 06/23/22 - 06/23/22

< 6

< 9

< 15

< 13

< 8

< 8 07/28/22 - 07/28/22

< 6

< 5

< 10

< 9

< 5

< 5 08/17/22 - 08/17/22

< 7

< 6

< 14

< 12

< 7

< 7 09/22/22 - 09/22/22

< 7

< 10

< 14

< 13

< 6

< 8 10/26/22 - 10/26/22

< 6

< 11

< 15

< 13

< 8

< 7 11/22/22 - 11/22/22

< 3

< 4

< 8

< 6

< 4

< 4 12/28/22 - 12/28/22

< 7

< 6

< 16

< 12

< 9

< 7 MEAN 94 01/25/22 - 01/25/22

< 6

< 7

< 9

< 13

< 7

< 6 02/23/22 - 02/23/22

< 6

< 8

< 11

< 7

< 7 03/22/22 - 03/22/22

< 4

< 9

< 17

< 13

< 8

< 8 04/19/22 - 04/19/22

< 5

< 8

< 10

< 5

< 5 05/25/22 - 05/25/22

< 7

< 6

< 18

< 11

< 7

< 6 06/23/22 - 06/23/22

< 6

< 7

< 9

< 12

< 8

< 8 07/28/22 - 07/28/22

< 4

< 8

< 11

< 6

< 6 08/17/22 - 08/17/22

< 5

< 9

< 7

< 4

< 4 09/22/22 - 09/22/22

< 7

< 11

< 17

< 14

< 7

< 8 10/26/22 - 10/26/22

< 7

< 8

< 11

< 14

< 9

< 8 11/22/22 - 11/22/22

< 5

< 6

< 11

< 9

< 6

< 6 12/28/22 - 12/28/22

< 5

< 12

< 10

< 7

< 7 MEAN RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 C-2

Table C-II.1 COLLECTION PERIOD 1N 1S 37 38 01/18/22 - 01/25/22

< 181 (1) 02/01/22 - 02/23/22

< 179 (1) 03/08/22 - 03/22/22

< 184 (1) 04/19/22 - 04/19/22

< 265 (1) 05/03/22 - 05/03/22

< 311 (1) 06/23/22 - 06/23/22

< 175 (1) 07/27/22 - 07/27/22

< 482 (1) 08/17/22 - 08/17/22

< 494 (1) 09/22/22 - 09/22/22

< 512 (1) 10/25/22 - 10/25/22

< 570 (1) 11/22/22 - 11/22/22

< 525 (1) 12/28/22 - 12/28/22

< 177 (1)

MEAN Table C-II.2 COLLECTION PERIOD 1N 1S 37 38 01/18/22 - 01/25/22

< 1.7 (1) 1.9 +/- 1.2 2.7 +/- 1.2 02/01/22 - 02/23/22

< 1.6 (1) 2.1 +/- 1.2 2.5 +/- 1.2 03/08/22 - 03/22/22

< 1.7 (1) 2.8 +/- 1.2 2.0 +/- 1.2 04/19/22 - 04/19/22

< 1.8 (1)

< 1.6

< 1.6 05/03/22 - 05/03/22

< 1.8 (1) 2.4 +/- 1.2 1.7 +/- 1.1 06/23/22 - 06/23/22

< 1.8 (1) 2.2 +/- 1.2 2.0 +/- 1.1 07/27/22 - 07/27/22

< 1.7 (1) 3.0 +/- 1.1 2.7 +/- 1.1 08/17/22 - 08/17/22

< 1.9 (1) 3.5 +/- 1.4 1.8 +/- 1.1 09/22/22 - 09/22/22 2.0 +/- 1.2 (1) 2.9 +/- 1.2 2.8 +/- 1.2 10/25/22 - 10/25/22

< 1.6 (1) 2.8 +/- 1.1 2.2 +/- 1.1 11/22/22 - 11/22/22

< 1.8 (1)

< 1.8

< 1.8 12/28/22 - 12/28/22 2.6 +/- 1.1 (1) 2.8 +/- 1.1 3.1 +/- 1.2 MEAN +/- 2 STD DEV 2.3 +/- 0.9 2.6 +/- 0.9 2.4 +/- 1.0 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA 193 189 509 172 COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 498 599 181 499 182 182 288 241 529 COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES 193 273 523 856 558 326 527 319 491 200 183 C-3

Table C-II.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 1N 01/18/22 - 01/18/22

< 5

< 10

< 13

< 5

< 5 02/01/22 - 02/01/22

< 5

< 12

< 7

< 6 03/08/22 - 03/08/22

< 6

< 7

< 15

< 11

< 6

< 6 04/19/22 - 04/19/22

< 4

< 6

< 11

< 9

< 5

< 4 05/03/22 - 05/03/22

< 6

< 7

< 12

< 13

< 7

< 7 06/28/22 - 06/28/22

< 6

< 8

< 12

< 13

< 7

< 7 07/27/22 - 07/27/22

< 4

< 6

< 9

< 8

< 6

< 5 08/17/22 - 08/17/22

< 5

< 7

< 11

< 7

< 5

< 6 09/22/22 - 09/22/22

< 6

< 10

< 13

< 14

< 7

< 8 10/25/22 - 10/25/22

< 6

< 5

< 11

< 9

< 5

< 5 11/22/22 - 11/22/22

< 6

< 5

< 9

< 8

< 6

< 6 12/28/22 - 12/28/22

< 8

< 7

< 15

< 13

< 9

< 8 MEAN 1S (1) 37 01/25/22 - 01/25/22

< 7

< 16

< 14

< 8

< 9 02/23/22 - 02/23/22

< 6

< 11

< 10

< 6

< 6 03/22/22 - 03/22/22

< 7

< 9

< 12

< 13

< 7

< 9 04/20/22 - 04/20/22

< 5

< 6

< 11

< 8

< 5

< 5 05/25/22 - 05/25/22

< 6

< 8

< 12

< 9

< 8

< 6 06/23/22 - 06/23/22

< 5

< 7

< 14

< 9

< 6

< 7 07/28/22 - 07/28/22

< 4

< 10

< 6

< 5

< 5 08/17/22 - 08/17/22

< 5

< 9

< 7

< 5

< 5 09/22/22 - 09/22/22

< 6

< 15

< 9

< 7

< 6 10/26/22 - 10/26/22

< 5

< 12

< 8

< 5

< 7 11/22/22 - 11/22/22

< 6

< 5

< 12

< 9

< 6

< 6 12/28/22 - 12/28/22

< 7

< 8

< 16

< 10

< 7

< 5 MEAN 38 01/25/22 - 01/25/22

< 7

< 6

< 12

< 7

< 6 02/23/22 - 02/23/22

< 7

< 6

< 9

< 12

< 7

< 8 03/22/22 - 03/22/22

< 7

< 8

< 17

< 10

< 7

< 7 04/19/22 - 04/19/22

< 5

< 7

< 12

< 7

< 5 05/25/22 - 05/25/22

< 6

< 9

< 8

< 5

< 7 06/23/22 - 06/23/22

< 6

< 9

< 14

< 9

< 7

< 7 07/28/22 - 07/28/22

< 4

< 8

< 5

< 4 08/17/22 - 08/17/22

< 5

< 9

< 8

< 5

< 5 09/22/22 - 09/22/22

< 6

< 7

< 13

< 10

< 7

< 6 10/26/22 - 10/26/22

< 9

< 7

< 19

< 15

< 7

< 8 11/22/22 - 11/22/22

< 5

< 7

< 10

< 9

< 5

< 6 12/28/22 - 12/28/22

< 7

< 13

< 9

< 10

< 6 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA C-4

Table C-III.1 COLLECTION PERIOD 02/10/22 -

(1)

(1) 04/28/22 -

07/07/22 -

10/26/22 -

MEAN Table C-III.2 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 MW-24-3A 02/10/22 - 02/10/22 (1) 04/28/22 - 04/28/22

< 5

< 11

< 7

< 5

< 5 07/07/22 - 07/07/22

< 6

< 5

< 12

< 11

< 9

< 8 10/26/22 - 10/26/22

< 6

< 5

< 10

< 5

< 6 MEAN W-3C 02/10/22 - 02/10/22 (1) 04/28/22 - 04/28/22

< 7

< 14

< 10

< 7

< 6 07/07/22 - 07/07/22

< 5

< 6

< 11

< 10

< 8

< 6 10/26/22 - 10/26/22

< 6

< 4

< 13

< 11

< 7

< 6 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES 02/10/22 04/28/22 07/07/22 10/26/22 MW-24-3A 267 572 631 W-3C 273 528 636 C-5

Table C-IV.1 COLLECTION SITE PERIOD K-40 Mn-54 Co-60 Zn-65 Cs-134 Cs-137 33 PREDATOR 05/23/22 2795 +/- 807

< 54

< 39

< 99

< 53

< 49 10/07/22 2868 +/- 1170

< 57

< 71

< 161

< 47

< 41 10/10/22 3686 +/- 1105

< 63

< 64

< 118

< 70

< 60 10/10/22 3368 +/- 1061

< 71

< 76

< 124

< 86

< 75 10/10/22 3953 +/- 923

< 52

< 60

< 133

< 48

< 58 MEAN +/- 2 STD DEV 3334 +/- 1008 33 BOTTOM FEEDER 05/23/22 2891 +/- 1065

< 72

< 62

< 172

< 89

< 91 10/10/22 2622 +/- 1039

< 85

< 45

< 154

< 78

< 74 MEAN +/- 2 STD DEV 2757 +/- 380 93 PREDATOR 10/11/22 3706 +/- 1205

< 75

< 87

< 156

< 84

< 81 10/11/22 2720 +/- 993

< 54

< 57

< 116

< 67

< 70 10/11/22 3085 +/- 986

< 55

< 50

< 119

< 49

< 51 10/11/22 2737 +/- 1303

< 80

< 74

< 126

< 91

< 89 10/11/22 2906 +/- 1144

< 73

< 110

< 174

< 91

< 102 MEAN +/- 2 STD DEV 3031 +/- 811 94 PREDATOR 10/12/22 3449 +/- 926

< 61

< 45

< 140

< 58

< 52 MEAN +/- 2 STD DEV 3449 +/- 0 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM OYSTER CREEK GENERATING STATION, 2022 FEEDER (FISH) SAMPLES COLLECTED IN THE VICINITY OF C-6

Table C-IV.2 CONCENTRATIONS OF GAMMA EMITTERS IN CLAM AND CRAB SAMPLES COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Cs-134 Cs-137 23 Clams 05/24/22 1379 +/- 645

< 53

< 47

< 74

< 50

< 48 10/10/22 2047 +/- 607

< 44

< 59

< 103

< 44

< 50 MEAN +/- 2 STD DEV 1713 +/- 945 24 Clams 05/23/22 1270 +/- 784

< 43

< 52

< 101

< 73

< 42 10/10/22 1438 +/- 632

< 41

< 65

< 126

< 66

< 46 MEAN +/- 2 STD DEV 1354 +/- 238 94 Clams 05/25/22 1041 +/- 653

< 53

< 55

< 113

< 52

< 50 10/12/22 1336 +/- 920

< 54

< 70

< 129

< 61

< 64 MEAN +/- 2 STD DEV 1189 +/- 417 33 Crabs 10/07/22 2428 +/- 841

< 54

< 56

< 85

< 50

< 56 MEAN +/- 2 STD DEV 2428 +/- 0 93 Crabs 10/12/22 2093 +/- 1096

< 125

< 119

< 228

< 118

< 123 MEAN +/- 2 STD DEV 2093 +/- 0 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES K-40 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 C-7

Table C-V.1 COLLECTION SITE PERIOD Be-7 Mn-54 Co-60 Cs-134 Cs-137 23 05/24/22

< 628 5110 +/- 999

< 61

< 56

< 73

< 71

< 1513 198 +/- 140 10/10/22

< 572 2969 +/- 1025

< 66

< 41

< 83

< 86

< 1668 270 +/- 103 MEAN +/- 2 STD DEV 4040 +/- 3028 234 +/- 103 24 05/23/22

< 324

< 992

< 40

< 53

< 46

< 40

< 952 138 +/- 84 10/10/22

< 499 1517 +/- 636

< 56

< 63

< 59

< 54

< 1079 176 +/- 102 MEAN +/- 2 STD DEV 1517 +/- 0 157 +/- 55 33 05/23/22

< 502 732 +/- 672

< 52

< 42

< 63

< 66

< 1325 256 +/- 100 10/11/22

< 519 1330 +/- 745

< 51

< 71

< 79

< 56

< 1278 199 +/- 88 MEAN +/- 2 STD DEV 1031 +/- 846 228 +/- 81 94 05/26/22

< 724 12260 +/- 1720

< 81

< 93

< 79

< 92

< 2109 504 +/- 180 10/12/22

< 671 12160 +/- 1928

< 109

< 119

< 106

< 95

< 1948 402 +/- 187 MEAN +/- 2 STD DEV 12210 +/- 141 453 +/- 145 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES K-40 Th-228 Ra-226 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA C-8

Table C-VI.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTION PERIOD 20 66 111 71 72 73 C

12/30/21 - 01/13/22 17 +/- 3 18 +/- 3 17 +/- 3 16 +/- 3 21 +/- 3 18 +/- 3 24 +/- 5 01/12/22 - 01/26/22 21 +/- 3 21 +/- 3 21 +/- 3 21 +/- 3 29 +/- 8 21 +/- 3 24 +/- 3 01/26/22 - 02/10/22 16 +/- 3 12 +/- 2 12 +/- 2 10 +/- 2 14 +/- 3 11 +/- 2 15 +/- 3 02/10/22 - 02/23/22 14 +/- 3 11 +/- 3 10 +/- 3 11 +/- 3 14

+/- 5 10 +/- 3 12 +/- 3 02/23/22 - 03/10/22 17 +/- 3 17 +/- 3 15 +/- 3 16 +/- 3 8 +/- 2 16 +/- 3 17 +/- 3 03/10/22 - 03/22/22 17 +/- 4 14 +/- 3 16 +/- 3 12 +/- 3 11 +/- 3 16 +/- 3 16 +/- 3 03/22/22 - 04/04/22 11 +/- 3 14 +/- 3 10 +/- 3 10 +/- 3 8 +/- 3 11 +/- 3 11 +/- 3 04/04/22 - 04/20/22

< 3 7 +/- 2 8 +/- 2 13 +/- 3 10 +/- 2 11 +/- 2 10 +/- 2 04/20/22 - 05/02/22 16 +/- 3 17 +/- 3 17 +/- 3 19 +/- 3 16 +/- 3 16 +/- 3 19 +/- 3 05/02/22 - 05/16/22 8 +/- 2 9 +/- 3 5 +/- 2 8 +/- 3 7 +/- 3 7 +/- 3

< 3 05/16/22 - 05/31/22 13 +/- 3 15 +/- 3 28 +/- 3 14 +/- 3 13 +/- 3 11 +/- 3 13 +/- 3 05/31/22 - 06/14/22 13 +/- 3 15 +/- 3 14 +/- 3 12 +/- 3 14 +/- 3 12 +/- 3 19 +/- 3 06/14/22 - 06/27/22 6 +/- 3 6 +/- 3 8 +/- 3 8 +/- 3 6 +/- 3 6 +/- 3 7 +/- 3 06/27/22 - 07/12/22 14 +/- 3 11 +/- 3 11 +/- 3 13 +/- 3 13 +/- 3 12 +/- 3 14 +/- 3 07/12/22 - 07/26/22 23 +/- 3 21 +/- 3 22 +/- 3 24 +/- 3 23 +/- 3 16 +/- 3 26 +/- 3 07/26/22 - 08/09/22 14 +/- 3 16 +/- 3 17 +/- 3 15 +/- 3 17 +/- 3 17 +/- 3 18 +/- 3 08/09/22 - 08/23/22 18 +/- 3 12 +/- 3 16 +/- 3 15 +/- 3 17 +/- 3 12 +/- 3 16 +/- 3 08/23/22 - 09/07/22 21 +/- 3 19 +/- 3 20 +/- 3 20 +/- 3 21 +/- 3 18 +/- 3 21 +/- 3 09/07/22 - 09/20/22 19 +/- 3 16 +/- 3 17 +/- 3 18 +/- 3 17 +/- 3 16 +/- 3 18 +/- 3 09/20/22 - 10/06/22 9 +/- 2 13 +/- 3 13 +/- 3 13 +/- 3 14 +/- 3 10 +/- 3 12 +/- 2 10/06/22 - 10/19/22 20 +/- 3 20 +/- 3 19 +/- 3 23 +/- 3 21 +/- 3 22 +/- 3 26 +/- 5 10/19/22 - 10/31/22 12 +/- 3 12 +/- 3 12 +/- 3 13 +/- 3 13 +/- 3 14 +/- 3 14 +/- 3 10/31/22 - 11/14/22 17 +/- 3 15 +/- 3 16 +/- 3 14 +/- 3 14 +/- 3 15 +/- 3 15 +/- 3 11/14/22 - 11/29/22 21 +/- 3 25 +/- 3 19 +/- 3 21 +/- 3 19 +/- 3 23 +/- 3 22 +/- 3 11/29/22 - 12/13/22 19 +/- 3 18 +/- 3 19 +/- 3 17 +/- 3 21 +/- 3 17 +/- 3 21 +/- 3 12/13/22 - 12/27/22 21 +/- 3 25 +/- 3 21 +/- 3 19 +/- 3 21 +/- 3 18 +/- 3 21 +/- 3 MEAN +/- 2 STD DEV 16 +/- 9 15 +/- 10 15 +/- 10 15 +/- 9 15 +/- 11 14 +/- 8 17 +/- 10 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 GROUP I GROUP II GROUP III C-9

Table C-VI.2 COLLECTION MEAN COLLECTION MEAN COLLECTION MEAN PERIOD MIN MAX

+/- 2SD PERIOD MIN MAX

+/- 2SD 12/30/21 - 01/26/22 17 21 19 +/- 4 12/30/21 - 01/26/22 16 29 21 +/- 8 01/04/22 - 01/26/22 24 24 24 +/- 0 01/26/22 - 02/23/22 10 16 12 +/- 5 01/26/22 - 02/23/22 10 14 12 +/- 3 01/26/22 - 02/23/22 12 15 14 +/- 5 02/23/22 - 04/04/22 10 17 14 +/- 5 02/23/22 - 04/04/22 8

16 12 +/- 7 02/23/22 - 04/04/22 11 17 14 +/- 7 04/04/22 - 05/02/22 7

17 13 +/- 10 04/04/22 - 05/02/22 10 19 14 +/- 7 04/04/22 - 05/02/22 10 19 14 +/- 13 05/02/22 - 05/31/22 5

28 13 +/- 16 05/02/22 - 05/31/22 7

14 10 +/- 6 05/16/22 - 05/31/22 13 13 13 +/- 0 05/31/22 - 06/27/22 6

15 10 +/- 8 05/31/22 - 06/27/22 6

14 10 +/- 7 05/31/22 - 06/27/22 7

19 13 +/- 18 06/27/22 - 07/26/22 11 23 17 +/- 11 06/27/22 - 07/26/22 12 24 17 +/- 10 06/27/22 - 07/26/22 14 26 20 +/- 16 07/26/22 - 09/07/22 12 21 17 +/- 6 07/26/22 - 09/07/22 12 21 17 +/- 6 07/26/22 - 09/07/22 16 21 18 +/- 5 09/07/22 - 10/06/22 9

19 14 +/- 7 09/07/22 - 10/06/22 10 18 14 +/- 6 09/07/22 - 10/06/22 12 18 15 +/- 9 10/06/22 - 10/31/22 12 20 16 +/- 8 10/06/22 - 10/31/22 13 23 18 +/- 9 10/11/22 - 10/31/22 14 26 20 +/- 16 10/31/22 - 11/29/22 15 25 19 +/- 8 10/31/22 - 11/29/22 14 23 18 +/- 7 10/31/22 - 11/29/22 15 22 18 +/- 10 11/29/22 - 12/27/22 18 25 20 +/- 5 11/29/22 - 12/27/22 17 21 19 +/- 4 11/29/22 - 12/27/22 21 21 21 +/- 0 12/30/21 - 12/27/22 5

28 16 +/- 9 12/30/21 - 12/27/22 6

29 15 +/- 9 01/04/22 - 12/27/22 7

26 17 +/- 10 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES GROUP I - ON-SITE LOCATIONS GROUP II - INTERMEDIATE DISTANCE LOCATIONS GROUP III - CONTROL LOCATIONS MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA C-10

Table C-VI.3 CONCENTRATIONS OF STRONTIUM IN AIR PARTICULATE SAMPLES COLLECTION SITE PERIOD SR-90 20 12/30/21 - 04/04/22

< 7 04/04/22 - 06/27/22

< 6 06/27/22 - 10/06/22

< 6 10/06/22 - 12/27/22

< 8 MEAN 66 12/30/21 - 04/04/22

< 6 04/04/22 - 06/27/22

< 7 06/27/22 - 10/06/22

< 6 10/06/22 - 12/27/22

< 10 MEAN 71 12/30/21 - 04/04/22

< 6 04/04/22 - 06/27/22

< 9 06/27/22 - 10/06/22

< 6 10/06/22 - 12/27/22

< 7 MEAN 72 12/30/21 - 04/04/22

< 9 04/04/22 - 06/27/22

< 9 06/27/22 - 10/06/22

< 5 10/06/22 - 12/27/22

< 9 MEAN 73 12/30/21 - 04/04/22

< 7 04/04/22 - 06/27/22

< 7 06/27/22 - 10/06/22

< 6 10/06/22 - 12/27/22

< 9 MEAN 111 12/30/21 - 04/04/22

< 7 04/04/22 - 06/27/22

< 8 06/27/22 - 10/06/22

< 6 10/06/22 - 12/27/22

< 8 MEAN C

01/04/22 - 04/04/22

< 8 04/04/22 - 06/27/22

< 8 06/27/22 - 10/06/22

< 7 10/11/22 - 12/27/22

< 6 MEAN RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 C-11

Table C-VI.4 COLLECTION SITE PERIOD Mn-54 Co-60 Cs-134 Cs-137 20 12/30/21 - 04/04/22 66 +/- 14

< 2

< 3 2

< 2 04/04/22 - 06/27/22 69 +/- 16

< 2

< 3 3

< 3 06/27/22 - 10/06/22 47 +/- 19

< 2

< 2 2

< 2 10/06/22 - 12/27/22 49 +/- 22

< 2

< 3 3

< 3 MEAN +/- 2 STD DEV 58 +/- 23 66 12/30/21 - 04/04/22 66 +/- 17

< 2

< 3 2

< 2 04/04/22 - 06/27/22 98 +/- 28

< 3

< 4 3

< 2 06/27/22 - 10/06/22 53 +/- 24

< 2

< 2 2

< 1 10/06/22 - 12/27/22 59 +/- 18

< 1

< 3 3

< 3 MEAN +/- 2 STD DEV 69 +/- 40 71 12/30/21 - 04/04/22 47 +/- 16

< 2

< 2 2

< 2 04/04/22 - 06/27/22 78 +/- 30

< 4

< 5 3

< 3 06/27/22 - 10/06/22 63 +/- 20

< 3

< 2 2

< 2 10/06/22 - 12/27/22 53 +/- 26

< 3

< 4 4

< 4 MEAN +/- 2 STD DEV 60 +/- 27 72 12/30/21 - 04/04/22 58 +/- 15

< 2

< 2 3

< 2 04/04/22 - 06/27/22 50 +/- 19

< 4

< 4 4

< 4 06/27/22 - 10/06/22 65 +/- 19

< 3

< 2 3

< 2 10/06/22 - 12/27/22 50 +/- 19

< 1

< 3 3

< 2 MEAN +/- 2 STD DEV 56 +/- 14 73 12/30/21 - 04/04/22 56 +/- 16

< 1

< 1 2

< 2 04/04/22 - 06/27/22 66 +/- 23

< 2

< 2 2

< 2 06/27/22 - 10/06/22 48 +/- 15

< 2

< 2 1

< 2 10/06/22 - 12/27/22 54 +/- 30

< 3

< 3 4

< 3 MEAN +/- 2 STD DEV 56 +/- 15 111 12/30/21 - 04/04/22 68 +/- 16

< 2

< 2 2

< 2 04/04/22 - 06/27/22 64 +/- 17

< 3

< 2 2

< 2 06/27/22 - 10/06/22 53 +/- 15

< 2

< 1 2

< 2 10/06/22 - 12/27/22 42 +/- 18

< 2

< 4 2

< 2 MEAN +/- 2 STD DEV 57 +/- 24 C

01/04/22 - 04/04/22 66 +/- 18

< 3 3

2

< 2 04/04/22 - 06/27/22 54 +/- 19

< 2 2

2

< 2 06/27/22 - 10/06/22 64 +/- 21

< 2 3

2

< 2 10/11/22 - 12/27/22 54 +/- 29

< 4 3

3

< 3 MEAN +/- 2 STD DEV 59 +/- 13 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES Be-7 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA C-12

Table C-VII.1 COLLECTION SITE PERIOD Sr-89 Cs-134 35 Cabbage 06/30/22

< 15 6.7 +/- 1.9

< 353 2583 +/- 550

< 36

< 38 Kale 06/30/22

< 21 11.1 +/- 5.0

< 339 2910 +/- 722

< 43

< 40 Collard 06/30/22

< 24 4.8 +/- 2.4

< 362 2444 +/- 672

< 40

< 40 Cabbage 07/19/22

< 22 5.1 +/- 2.7

< 502 2439 +/- 919

< 59

< 67 Kale 07/19/22

< 21 14.1 +/- 3.1

< 361 3557 +/- 760

< 45

< 45 Collard 07/19/22

< 24 9.8 +/- 2.7

< 380 2316 +/- 599

< 49

< 45 Cabbage 08/30/22

< 19

< 2.7

< 275 1119 +/- 438

< 21

< 28 Kale 08/30/22

< 24 18.5 +/- 3.1

< 212 3789 +/- 478

< 25

< 26 Collard 08/30/22

< 19

< 4.5

< 189 1885 +/- 288

< 19

< 21 Cabbage 08/30/22

< 23 5.6 +/- 2.5

< 197 1949 +/- 354

< 23

< 23 Cabbage 09/27/22

< 24

< 3.5

< 196 1577 +/- 316

< 26

< 22 Kale 09/27/22

< 22 6.6 +/- 2.4

< 344 3030 +/- 727

< 48

< 44 Collard 09/27/22

< 22 6.2 +/- 3.0 459 +/- 240 2471 +/- 471

< 32

< 29 MEAN +/- 2 STD DEV 8.9 +/- 9.1 459 +/- 0 2467 +/- 1495 36 (Control)

Cabbage 06/30/22

< 20

< 4.5

< 226 2265 +/- 564

< 32

< 32 Collard 06/30/22

< 24

< 4.3

< 344 3104 +/- 755

< 32

< 39 Cabbage 07/19/22

< 21

< 3.9

< 229 2301 +/- 498

< 24

< 20 Collard 07/19/22

< 23 16.3 +/- 3.3

< 230 3798 +/- 532

< 33

< 23 Cabbage 08/30/22

< 14

< 3.3

< 222 3774 +/- 587

< 28

< 31 Kale 08/30/22

< 19

< 4.1

< 179 5402 +/- 461

< 23

< 23 Collard 08/30/22

< 22 11.8 +/- 3.3

< 156 3743 +/- 362

< 20

< 20 Cabbage 08/30/22

< 16

< 2.9

< 192 3242 +/- 525

< 27

< 26 Kale 08/30/22

< 19

< 3.7

< 291 4706 +/- 701

< 34

< 37 Collard 08/30/22

< 23 15.0 +/- 2.2

< 219 3156 +/- 477

< 30

< 29 Cabbage 09/27/22

< 22 8.1 +/- 2.7

< 156 2339 +/- 412

< 17

< 18 Kale 09/27/22

< 20 12.3 +/- 2.9

< 414 3970 +/- 922

< 50

< 59 Collard 09/27/22

< 22 9.4 +/- 2.8

< 330 3882 +/- 838

< 41

< 34 MEAN +/- 2 STD DEV 12.1 +/- 6.3 3514 +/- 1854 66 Cabbage 06/30/22

< 24 5.6 +/- 2.3

< 334 6162 +/- 873

< 44

< 37 Collard 06/30/22

< 20

< 4.0

< 299 4777 +/- 715

< 46

< 33 Cabbage 07/19/22

< 22

< 4.6

< 447 5154 +/- 1071

< 37

< 54 Kale 07/19/22

< 20 4.5 +/- 2.6

< 154 6204 +/- 464

< 17

< 19 Collard 07/19/22

< 19 3.8 +/- 2.1

< 282 5038 +/- 776

< 39

< 35 Cabbage 08/30/22

< 19

< 4.2

< 199 4210 +/- 520

< 21

< 24 Kale 08/30/22

< 14

< 3.3

< 225 5529 +/- 501

< 23

< 24 Collard 08/30/22

< 13

< 3.0

< 244 4867 +/- 507

< 28

< 25 Collard 08/30/22

< 21 5.4 +/- 2.5

< 340 5464 +/- 851

< 29

< 41 Cabbage 09/27/22

< 22 4.4 +/- 2.7

< 221 4153 +/- 512

< 28

< 25 Kale 09/27/22

< 18

< 4.3

< 425 6648 +/- 917

< 48

< 43 Collard 09/27/22

< 21

< 3.2

< 324 5430 +/- 809

< 45

< 28 MEAN +/- 2 STD DEV 4.7 +/- 1.5 5303 +/- 1541 115 Collard 06/30/22

< 19 13.7 +/- 2.2

< 271 2281 +/- 488

< 37

< 39 Kale 07/19/22

< 17 6.5 +/- 2.6

< 275 2373 +/- 554

< 34

< 41 Collard 07/19/22

< 25 14.7 +/- 3.1

< 425 4073 +/- 918

< 57

< 55 Cabbage 08/30/22

< 22 11.8 +/- 3.5 192 +/- 153 3080 +/- 418

< 22

< 25 Collard 08/30/22

< 21 6.8 +/- 3.0

< 217 2313 +/- 405

< 22

< 23 Collard 08/30/22

< 18 7.3 +/- 2.6

< 367 2579 +/- 573

< 42

< 44 Cabbage 09/27/22

< 23 13.3 +/- 3.1

< 496 2805 +/- 717

< 47

< 42 Collard 09/27/22

< 21 12.0 +/- 2.8

< 428 1976 +/- 578

< 43

< 48 MEAN +/- 2 STD DEV 10.8 +/- 6.7 192 +/- 0 2685 +/- 1311 OYSTER CREEK GENERATING STATION, 2022 IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES K-40 Sr-90 Be-7 Cs-137 C-13

Table C-VIII.1 STATION MEAN CODE

+/- 2 S.D.

JAN - MAR APR - JUN JUL - SEP OCT - DEC 1

1.0 +/- 1.7 0.9 2.0 0.9 0.0 6

1.2 +/- 2.0 0.7 2.7 0.6 0.7 8

-0.8 +/- 2.1

-1.6 0.6

-1.6

-0.7 9

-1.4 +/- 2.6

-2.1 0.5

-2.5

-1.6 22 2.2 +/- 3.0 1.9 4.3 0.7 2.0 51 2.0 +/- 3.0 1.3 4.2 0.8 1.9 52 3.4 +/- 2.1 3.6 4.8 2.6 2.7 53 1.5 +/- 2.8 1.9 3.3

-0.1 1.0 54

-0.9 +/- 2.2

-0.9 0.5

-1.3

-2.1 55 6.2 +/- 2.2 6.8 7.4 5.1 5.6 56 2.9 +/- 4.5 3.6 5.6 2.0 0.4 57

-0.3 +/- 3.4

-1.3 2.1

-1.7

-0.4 58

-1.4 +/- 2.9

-1.5 0.6

-2.9

-1.9 59 0.8 +/- 1.8 0.2 1.9 1.2

-0.1 61 0.0 +/- 2.4 (2) 1.3

-1.0

-0.4 62 0.1 +/- 2.0

-0.8 1.4

-0.5 0.4 63

-0.4 +/- 2.6

-1.7 (2)

-0.3 0.8 64 0.2 +/- 2.9 0.3 1.8

-1.7 0.4 65 0.3 +/- 2.2

-0.3 1.9 0.1

-0.6 66

-3.9 +/- 6.2

-8.0

-0.8

-4.4

-2.3 68

-0.6 +/- 1.6

-0.2 0.3

-1.2

-1.3 71 0.2 +/- 3.0 0.8 2.1

-1.0

-1.1 72

-1.0 +/- 2.5

-1.5 0.8

-2.2

-1.0 73

-0.3 +/- 2.7

-1.1 1.8

-0.9

-0.8 74 0.4 +/- 2.7 0.7 1.7

-1.5 0.8 75

-0.4 +/- 4.2

-0.4 2.3

-2.9

-0.5 78

-1.9 +/- 5.5

-5.9 0.5

-1.1

-1.2 79

-1.3 +/- 8.0

-7.1 0.5

-0.5 2.0 81

-6.3 +/- 14.4

-8.5

-15.5

-0.9

-0.3 98

-1.0 +/- 2.3

-2.3 0.3

-1.5

-0.4 99

-1.0 +/- 2.5

-0.4 0.3

-2.5

-1.6 T1 0.3 +/- 3.5 1.0 2.3

-0.1

-1.8 100

-0.2 +/- 3.8

-0.4 2.5

-1.8

-1.2 101

-0.6 +/- 1.7

-1.7 0.4

-0.8

-0.2 102

-3.0 +/- 5.4

-6.9

-0.9

-2.5

-1.6 103

-0.5 +/- 1.3

-0.5 0.4

-1.2

-0.6 104

-0.4 +/- 2.8

-0.1 1.2

-2.2

-0.5 106

-0.2 +/- 4.7 1.8 1.5

-3.4

-0.5 107 1.4 +/- 1.1 1.5 2.0 0.6 1.6 109 0.4 +/- 2.2 1.3 1.5

-0.7

-0.4 110

-1.2 +/- 3.5

-2.1 1.2

-2.7

-1.1 112 0.9 +/- 2.3 1.4 2.3

-0.2 0.1 113 0.9 +/- 4.0 0.6 3.0

-1.8 1.7 C

20.9 +/- 11.8 29.2 15.5 20.4 18.4 (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.

QUARTERLY OSLD RESULTS FOR OYSTER CREEK GENERATING STATION, 2022(1)

RESULTS IN UNITS OF MILLIREM/STD. QUARTER +/- 2 STANDARD DEVIATION (2) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-14

TABLE C-VIII.2 SITE BOUNDARY INTERMEDIATE SPECIAL INTEREST CONTROL

+/- 2 S.D.

0.6 +/- 4.6

-1.5 +/- 6.3

-1.8 +/- 7.2 29.2 +/- 0 2.5 +/- 3.6 0.5 +/- 7.4 1.0 +/- 1.9 15.5 +/- 0

-0.2 +/- 3.9

-1.5 +/- 2.6

-1.1 +/- 0.3 20.4 +/- 0 0.4 +/- 3.5

-0.5 +/- 2.2

-1.2 +/- 0.2 18.4 +/- 0 TABLE C-VIII.3 PERIOD PERIOD PERIOD MEAN MINIMUM MAXIMUM

+/- 2 S.D.

0.8 +/- 4.3

-0.7 +/- 5.3

-0.8 +/- 3.8 20.9 +/- 10.7 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.

CONTROL 16 13.1 29.9 7.4 INTERMEDIATE 184

-15.5 4.3 SPECIAL INTEREST 24

-5.9 2.1

-3.0 SAMPLES LOCATION ANALYZED SITE BOUNDARY 156 RESULTS IN UNITS OF MILLIREM PER STANDARD QUARTER +/- 2 STANDARD DEVIATION STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, INTERMEDIATE, SPECIAL INTEREST, AND CONTROL LOCATIONS FOR OYSTER CREEK GENERATING STATION, 2022(1)

RESULTS IN UNITS OF MILLIREM PER STANDARD QUARTER +/- 2 STANDARD DEVIATION JAN-MAR APR-JUN JUL-SEP OCT-DEC

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR OYSTER CREEK GENERATING STATION, 2022 C-15

FIGURE C-1 MEAN COBALT-60 CONCENTRATION IN CLAMS OYSTER CREEK GENERATING STATION, 1983 - 2022 0

5 10 15 20 1983 1992 2002 2012 2022 YEAR INDICATOR STATION BACKGROUND STATION picoCuries per kilogram (wet)

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.

C-16

FIGURE C-2 MEAN COBALT-60 CONCENTRATION IN AQUATIC SEDIMENT OYSTER CREEK GENERATING STATION, 1984 - 2022 0

50 100 150 200 250 300 1984 1987 1991 2004 2022 YEAR INDICATOR STATION MEAN BACKGROUND STATION MEAN picoCuries per kilogram (dry)

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.

C-17

FIGURE C-3 MEAN CESIUM-137 CONCENTRATION IN AQUATIC SEDIMENT OYSTER CREEK GENERATING STATION, 1984 - 2022 0

200 400 600 1984 1987 1991 2004 2022 YEAR INDICATOR BACKGROUND picoCuries per kilogram (dry)

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.

C-18

FIGURE C-4 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES OYSTER CREEK GENERATING STATION, 2008 - 2022 0

0.01 0.02 0.03 0.04 0.05 Indicator

Background

picoCuries per cubic meter Date C-19

FIGURE C-5 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES OYSTER CREEK GENERATING STATION, 1984 - 2022 0

0.02 0.04 0.06 0.08 0.1 0.12 0.14 0.16 Indicator Stations Background Station*

CHERNOBYL ACCIDENT

Data from Cookstown station ONLY after December 1996 YEAR picoCuries per cubic meter C-20

FIGURE C-6 MEAN QUARTERLY OSLD GAMMA DOSE OYSTER CREEK GENERATING STATION, 2022 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 0 TO 2 MILES 2 TO 5 MILES OVER 5 MILES DISTANCE RING FROM PLANT 1Q22 2Q22 3Q22 4Q22 millirem per Standard Quarter Oyster Creek's dosimetry changed from TLD to OSLD in 2012.

C-21

Intentionally left blank

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 COLLECTION PERIOD OC-24 (EIML) 05/24/22

< 180

< 184

< 158 10/10/22

< 188

< 157 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA 24 (TBE)

QCA (TBE)

D-1

Table D-I.2 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 24 05/23/22

< 7

< 14

< 10

< 7

< 7 (TBE) 10/10/22

< 6

< 11

< 9

< 6

< 6 QCA 05/23/22

< 7

< 6

< 13

< 9

< 8

< 7 (TBE) 10/10/22

< 5

< 6

< 13

< 11

< 7

< 6 OC-24 05/23/22

< 3

< 8 (1)

(1)

< 4 (EIML) 10/10/22

< 2

< 5 (1)

(1)

< 3 (1) Not reported CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA D-2

Table D-II.1 OC-QC1N (EIML) 01/18/22 - 01/25/22

< 181

< 161 02/01/22 - 02/23/22

< 179

< 161 03/08/22 - 03/22/22

< 184 (1) 04/19/22 - 04/19/22

< 265

< 165 05/03/22 - 05/03/22

< 311

< 163 06/23/22 - 06/23/22

< 175

< 161 07/27/22 - 07/27/22

< 482

< 161 08/17/22 - 08/17/22

< 494

< 163 09/22/22 - 09/22/22

< 512

< 162 10/25/22 - 10/25/22

< 570

< 165 11/22/22 - 11/22/22

< 525

< 160 12/28/22 -

12/28/22

< 177

< 157 Table D-II.2 1N (TBE)

OC-QC1N (EIML) 01/18/22 - 01/25/22

< 1.7

< 0.9 02/01/22 - 02/23/22

< 1.6

< 0.8 03/08/22 - 03/22/22

< 1.7 (1) 04/19/22 - 04/19/22

< 1.8

< 1.6 05/03/22 - 05/03/22

< 1.8

< 0.9 06/23/22 - 06/23/22

< 1.8

< 0.8 07/27/22 - 07/27/22

< 1.7

< 0.9 08/17/22 - 08/17/22

< 1.9

< 0.9 09/22/22 - 09/22/22 2.0 +/- 1.2

< 0.9 10/25/22 - 10/25/22

< 1.6

< 0.9 11/22/22 - 11/22/22

< 1.8

< 0.8 12/28/22 -

12/28/22 2.6 +/- 1.1

< 0.9 (1) SEE PROGRAM EXCEPTIONS FOR EXPLANATION 1N (TBE)

PERIOD COLLECTION CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD D-3

Table D-II.3 COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 SITE Mn-54 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 1N 01/18/22 - 01/18/22

< 5

< 10

< 13

< 5

< 5 (TBE) 02/01/22 - 02/01/22

< 5

< 12

< 7

< 6 03/08/22 - 03/08/22

< 6

< 7

< 15

< 11

< 6

< 6 04/19/22 - 04/19/22

< 4

< 6

< 11

< 9

< 5

< 4 05/03/22 - 05/03/22

< 6

< 7

< 12

< 13

< 7

< 7 06/28/22 - 06/28/22

< 6

< 8

< 12

< 13

< 7

< 7 07/27/22 - 07/27/22

< 4

< 6

< 9

< 8

< 6

< 5 08/17/22 - 08/17/22

< 5

< 7

< 11

< 7

< 5

< 6 09/22/22 - 09/22/22

< 6

< 10

< 13

< 14

< 7

< 8 10/25/22 - 10/25/22

< 6

< 5

< 11

< 9

< 5

< 5 11/22/22 - 11/22/22

< 6

< 5

< 9

< 8

< 6

< 6 12/28/22 - 12/28/22

< 8

< 7

< 15

< 13

< 9

< 8 OC-QC1N 01/18/22 - 01/18/22

< 1

< 3 (1)

(1)

< 1 (EIML) 02/01/22 - 02/01/22 (2) 03/08/22 - 03/08/22

< 2

< 3

< 4 (1)

(1)

< 3 04/19/22 - 04/19/22

< 1

< 2 (1)

(1)

< 1 05/03/22 - 05/03/22

< 1

< 3 (1)

(1)

< 1 06/28/22 - 06/28/22

< 2

< 5 (1)

(1)

< 2 07/27/22 - 07/27/22

< 2

< 3

< 4 (1)

(1)

< 2 08/17/22 - 08/17/22

< 2

< 1

< 3 (1)

(1)

< 2 09/22/22 - 09/22/22

< 2

< 5 (1)

(1)

< 3 10/25/22 - 10/25/22

< 3

< 2

< 4 (1)

(1)

< 2 11/22/22 - 11/22/22

< 4

< 3

< 7 (1)

(1)

< 2 12/28/22 - 12/28/22

< 1

< 4 (1)

(1)

< 2 (1) Not reported (2) SEE PROGRAM EXCEPTIONS FOR EXPLANATION PERIOD COLLECTION RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES D-4

Table D-III.1 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Cs-134 Cs-137 24 05/23/22 1270 +/- 784

< 43

< 52

< 101

< 73

< 42 (TBE)

QCA 05/23/22 1112 +/- 713

< 41

< 59

< 93

< 40

< 44 (TBE)

OC-24 05/23/22 1920 +/- 210

< 6

< 18 (1)

< 8 (EIML)

`

(1) Not reported K-40 IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 CONCENTRATIONS OF GAMMA EMITTERS IN CLAM SAMPLES COLLECTED D-5

Table D-IV.1 COLLECTION SITE PERIOD Mn-54 Co-60 Cs-134 Cs-137 Ra-226 24 05/23/22

< 324

< 992

< 40

< 53

< 46

< 40

< 952 138 +/- 84 (TBE) 10/10/22

< 499 1517 +/- 636

< 56

< 63

< 59

< 54

< 1079

+/- 636 176 +/- 102 QCA 05/23/22

< 362

< 1017

< 43

< 40

< 51

< 962 175 +/- 63 (TBE) 10/10/22

< 605 1505 +/- 707

< 68

< 58

< 99

< 70

< 1421

+/- 707 235 +/- 112 OC-24 05/17/21

< 391 776 +/- 229

< 17

< 11 (1)

< 15

< 414

< 1277 (EIML) 10/10/22

< 428 1160 +/- 290

< 15

< 7 (1)

< 18 827 +/- 401

< 1077 (1) Not reported CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED Be-7 Th-228 IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2021 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA K-40 D-6

TABLE D-V.1 COLLECTION SITE SITE PERIOD Sr-89 Sr-90 Be-7 K-40 Cs-134 Cs-137 35 TBE Cabbage 08/30/22

< 19

< 2.7

< 275 1119 +/- 438

< 21

< 28 TBE Cabbage 08/30/22

< 23 5.6 +/- 2.5

< 197 1949 +/- 354

< 23

< 23 EIML Cabbage 08/30/22 (1)

< 2.0

< 152 1865 +/- 302 (1)

< 14 36 (Control)

TBE Cabbage 08/30/22

< 3.3

< 222 3774 +/- 587

< 31

< 31 TBE Cabbage 08/30/22

< 2.9

< 192 3242 +/- 525

< 26

< 26 EIML Cabbage 08/30/22 (1)

< 2.0

< 94 3629 +/- 243 (1)

< 6 36 (Control)

TBE Kale 08/30/22

< 4.1

< 179 5402 +/- 461

< 23

< 23 TBE Kale 08/30/22

< 3.7

< 291 4706 +/- 701

< 37

< 37 EIML Kale 08/30/22 (1)

< 3.0

< 77 4302 +/- 186 (1)

< 7 36 (Control)

TBE Collard 08/30/22 11.8 11.8 +/- 3.3

< 156 3743 +/- 362

< 20

< 20 TBE Collard 08/30/22 15.0 15.0 +/- 2.2

< 219 3156 +/- 477

< 29

< 29 EIML Collard 08/30/22 (1)

< 1.0

< 97 11130 +/- 353 (1)

< 13 66 TBE Collard 08/30/22

< 3.0

< 244 4867 +/- 507

< 25

< 25 TBE Collard 08/30/22 5.4 5.4 +/- 2.5

< 340 5464 +/- 851

< 41

< 41 EIML Collard 08/30/22 (1)

< 3.0 261 +/- 50 4486 +/- 190 (1)

< 6 115 TBE Collard 08/30/22 6.8 6.8 +/- 3.0

< 217 2313 +/- 405

< 23

< 23 TBE Collard 08/30/22 7.3 7.3 +/- 2.6

< 367 2579 +/- 573

< 44

< 44 EIML Collard 08/30/22 (1)

< 2.0 211 +/- 51 2583 +/- 122 (1)

< 5 (1) Not reported CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA D-7

Intentionally left blank

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank

Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)

Ratio of TBE to Analytics Result Evaluation (b)

March 2022 E13706 Milk Sr-89 pCi/L 80.3 96.8 0.83 A

Sr-90 pCi/L 12.7 12.6 1.01 A

E13707 Milk Ce-141 pCi/L 62.3 65 0.96 A

Co-58 pCi/L 158 164 0.96 A

Co-60 pCi/L 286 302 0.95 A

Cr-51 pCi/L 314 339 0.93 A

Cs-134 pCi/L 155 182 0.85 A

Cs-137 pCi/L 210 223 0.94 A

Fe-59 pCi/L 211 185 1.14 A

I-131 pCi/L 88.0 96.7 0.91 A

Mn-54 pCi/L 169 164 1.03 A

Zn-65 pCi/L 238 246 0.97 A

E13708 Charcoal I-131 pCi 79.9 87.1 0.92 A

E13709 AP Ce-141 pCi 60.9 42.0 1.45 N(1)

Co-58 pCi 118 107 1.11 A

Co-60 pCi 218 196 1.11 A

Cr-51 pCi 251 221 1.14 A

Cs-134 pCi 129 118 1.09 A

Cs-137 pCi 156 145.0 1.07 A

Fe-59 pCi 124 120.0 1.03 A

Mn-54 pCi 120 107 1.12 A

Zn-65 pCi 162 160 1.01 A

E13710 Soil Ce-141 pCi/g 0.123 0.103 1.19 A

Co-58 pCi/g 0.254 0.263 0.97 A

Co-60 pCi/g 0.493 0.483 1.02 A

Cr-51 pCi/g 0.603 0.543 1.11 A

Cs-134 pCi/g 0.268 0.292 0.92 A

Cs-137 pCi/g 0.399 0.431 0.93 A

Fe-59 pCi/g 0.320 0.296 1.08 A

Mn-54 pCi/g 0.263 0.263 1.00 A

Zn-65 pCi/g 0.407 0.395 1.03 A

E13711 AP Sr-89 pCi 83.2 97.4 0.85 A

Sr-90 pCi 12.7 12.7 1.00 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 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services (Page 1 of 2)

Table E.1

Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)

Ratio of TBE to Analytics Result Evaluation (b)

Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services September 2022 E13712 Milk Sr-89 pCi/L 71.1 89.1 0.80 A

Sr-90 pCi/L 12.0 13.6 0.88 A

E13713 Milk Ce-141 pCi/L 148 161 0.92 A

Co-58 pCi/L 178 189 0.94 A

Co-60 pCi/L 229 260 0.88 A

Cr-51 pCi/L 486 456 1.07 A

Cs-134 pCi/L 220 252 0.87 A

Cs-137 pCi/L 203 222 0.92 A

Fe-59 pCi/L 174 173 1.01 A

I-131 pCi/L 75.9 94.2 0.81 A

Mn-54 pCi/L 269 282 0.95 A

Zn-65 pCi/L 364 373 0.97 A

E13714 Charcoal I-131 pCi 81.4 83.6 0.97 A

E13715 AP Ce-141 pCi 102 91 1.12 A

Co-58 pCi 118 107 1.11 A

Co-60 pCi 207 147 1.41 N(2)

Cr-51 pCi 310 257 1.21 W

Cs-134 pCi 148 142 1.04 A

Cs-137 pCi 137 125 1.10 A

Fe-59 pCi 115 98 1.18 A

Mn-54 pCi 168 159 1.05 A

Zn-65 pCi 240 211 1.14 A

E13716 Soil Ce-141 pCi/g 0.288 0.284 1.01 A

Co-58 pCi/g 0.320 0.334 0.96 A

Co-60 pCi/g 0.445 0.459 0.97 A

Cr-51 pCi/g 0.883 0.805 1.10 A

Cs-134 pCi/g 0.410 0.446 0.92 A

Cs-137 pCi/g 0.447 0.465 0.96 A

Fe-59 pCi/g 0.314 0.305 1.03 A

Mn-54 pCi/g 0.489 0.499 0.98 A

Zn-65 pCi/g 0.666 0.660 1.01 A

E13717 AP Sr-89 pCi 87.5 98.3 0.89 A

Sr-90 pCi 12.6 15.0 0.84 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)

Table E.1

Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)

Acceptance Range Evaluation (b)

February 2022 22-GrF46 AP Gross Alpha Bq/sample 0.402 1.20 0.36 - 2.04 A

Gross Beta Bq/sample 0.669 0.68 0.341 - 1.022 A

22-MaS46 Soil Ni-63 Bq/kg 645 780 546 - 1014 A

Tc-99 Bq/kg 526 778 545 - 1011 N(3) 22-MaSU46 Urine Cs-134 Bq/L 1.67 1.77 1.24 - 2.30 A

Cs-137 Bq/L 1.50 1.56 1.09 - 2.03 A

Co-57 Bq/L 4.93 5.39 3.77 - 7.01 A

Co-60 Bq/L 2.13 2.06 1.44 - 2.68 A

Mn-54 Bq/L 4.83 5.08 3.56 - 6.60 A

U-234 Bq/L 0.142 0.0074 0.0052 - 0.0096 N(4)

U-238 Bq/L 0.0254 0.0103 0.0072 - 0.0134 N(4)

Zn-65 Bq/L 4.71 4.48 3.14 - 5.82 A

22-MaW46 Water Ni-63 Bq/L 28.6 34.0 23.8 - 44.2 A

Tc-99 Bq/L 8.59 7.90 5.5 - 10.3 A

22-RdV46 Vegetation Cs-134 Bq/sample 6.61 7.61 5.33 - 9.89 A

Cs-137 Bq/sample 1.50 1.52 1.06 - 1.98 A

Co-57 Bq/sample 5.11 5.09 3.56 - 6.62 A

Co-60 Bq/sample 0.0162 (1)

A Mn-54 Bq/sample 2.42 2.59 1.81 - 3.37 A

Sr-90 Bq/sample 0.684 0.789 0.552 - 1.026 A

Zn-65 Bq/sample 1.44 1.47 1.03 - 1.91 A

August 2022 22-MaS47 Soil Ni-63 Bq/kg 14.6 (1)

A Tc-99 Bq/kg 994 1000 700 - 1300 A

22-MaW47 Water Ni-63 Bq/L 24.4 32.9 23.0 - 42.8 A

Tc-99 Bq/L 1.9 (1)

N(5) 25-RdV47 Vegetation Cs-134 Bq/sample 0.032 (1)

A Cs-137 Bq/sample 0.891 1.08 0.758 - 1.408 A

Co-57 Bq/sample 0.006 (1)

A Co-60 Bq/sample 4.04 4.62 3.23 - 6.01 A

Mn-54 Bq/sample 2.01 2.43 1.70 - 3.16 A

Sr-90 Bq/sample 1.25 1.60 1.12 - 2.08 W

Zn-65 Bq/sample 6.16 7.49 5.24 - 9.74 A

(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) Tc-99 soil cross-checks done for TBE information only - not required (4) See NCR 22-05 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering Environmental Services (Page 1 of 1)

Table E.2

Month/Year Identification Number Matrix Nuclide Units TBE Reported Value Known Value (a)

Acceptance Limits Evaluation (b)

March 2022 MRAD-36 Water Am-241 pCi/L 68.3 74.6 51.2 - 95.4 A

Fe-55 pCi/L 797 1140 670 - 1660 A

Pu-238 pCi/L 146 147 88.4 - 190 A

Pu-239 pCi/L 69.9 71.9 44.5 - 88.6 A

Soil Sr-90 pCi/kg 8050 6720 2090 - 10500 A

AP Fe-55 pCi/filter 148 127 46.4 - 203 A

Pu-238 pCi/filter 29.9 29.6 22.3 - 36.4 A

Pu-239 pCi/filter 51.6 49.7 37.2 - 60.0 A

U-234 pCi/filter 59.9 67.3 49.9 - 78.9 A

U-238 pCi/filter 59.0 66.7 50.4 - 79.6 A

GR-A pCi/filter 95.6 94.2 49.2 - 155 A

GR-B pCi/filter 71.2 66.8 40.5 - 101 A

April 2022 RAD-129 Water Ba-133 pCi/L 61.7 62.9 52.3 - 69.2 A

Cs-134 pCi/L 80.9 81.6 68.8 - 89.8 A

Cs-137 pCi/L 37.4 36.6 32.1 - 43.3 A

Co-60 pCi/L 103 97.4 87.7 - 109 A

Zn-65 pCi/L 318 302 272 - 353 A

GR-A pCi/L 26.9 20.8 10.4 - 28.3 A

GR-B pCi/L 49.7 51.0 34.7 - 58.1 A

U-Nat pCi/L 56.3 68.9 56.3 - 75.8 A

H-3 pCi/L 17,000 18,100 15,800 - 19,000 A

Sr-89 pCi/L 65.3 67.9 55.3 - 76.1 A

Sr-90 pCi/L 42.1 42.7 31.5 - 49.0 A

I-131 pCi/L 25.7 26.2 21.8 - 30.9 A

September 2022 MRAD-37 Water Am-241 pCi/L 111 96.2 66.0 - 123 A

Fe-55 pCi/L 850 926 544 - 1350 A

Pu-238 pCi/L 62.1 52.6 31.6 - 68.2 A

Pu-239 pCi/L 139.5 117 72.5 - 144 A

Soil Sr-90 pCi/kg 3350 6270 1950 - 9770 A

U-234 pCi/kg 1684 3350 1570 - 4390 A

U-238 pCi/kg 1658 3320 1820 - 4460 N(2)

AP Fe-55 pCi/filter 71.9 122 44.5 - 195 A

Pu-238 pCi/filter 38.8 29.9 22.6 - 36.7 N(1)

Pu-239 pCi/filter 14.5 13.0 9.73 - 15.7 A

U-234 pCi/filter 78.0 71.5 53.0 - 83.8 A

U-238 pCi/filter 79.7 70.9 53.5 - 84.6 A

GR-A pCi/filter 62.8 55.5 29.0 - 91.4 A

GR-B pCi/filter 70.9 64.8 39.3 - 97.9 A

October 2022 RAD-131 Water Ba-133 pCi/L 76.2 79.4 66.6 - 87.3 A

Cs-134 pCi/L 28.0 30.5 23.9 - 33.6 A

Cs-137 pCi/L 202 212 191 - 235 A

Co-60 pCi/L 52.4 51.4 46.3 - 59.1 A

Zn-65 pCi/L 216 216 194 - 253 A

GR-A pCi/L 19.7 16.9 8.28 - 23.7 A

GR-B pCi/L 49.8 53.0 36.1 - 60.0 A

U-Nat pCi/L 10.54 8.53 6.60 - 9.88 N(3)

H-3 pCi/L 13,900 15,100 13,200 - 16,600 A

Sr-89 pCi/L 59.7 64.5 52.3 - 72.5 A

Sr-90 pCi/L 32.9 37.3 27.4 - 43.0 A

I-131 pCi/L 26.9 24.4 20.2 - 28.9 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 22-19 (2) U soil cross-checks done for TBE information only - not required (3) See NCR 22-20 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services (Page 1 of 1)

Table E.3

TABLE E.4 Lab Code b Reference Date Analysis Laboratory Result Known Activity Control Limits c Acceptance MADW-408 02/01/22 GR-A 0.34 +/- 0.04 0.574 0.172 - 0.976 Pass MADW-408 02/01/22 GR-B 6.61 +/- 0.09 7.25 3.63 - 10.88 Pass MASO-504 02/01/22 Cs-134 738 +/- 8 890 623 - 1,157 Pass MASO-504 02/01/22 Cs-137 399 +/- 9 365 256 - 475 Pass MASO-504 02/01/22 Co-60 433 +/- 6 443 310 - 576 Pass MASO-504 02/01/22 Mn-54 1,258 +/- 606 1,140 798 - 1,482 Pass MASO-504 02/01/22 Zn-65

-2.11 +/- 4.44 0

NA c Pass MASO-504 02/01/22 K-40 641 +/- 40 596 417 - 775 Pass MADW-500 02/01/22 Cs-134

-0.06 +/- 0.11 0

NA c Pass MADW-500 02/01/22 Cs-137 8.09 +/- 0.33 7.6 5.35 - 9.93 Pass MADW-500 02/01/22 Co-60 8.91 +/- 0.27 9.3 6.5 - 12.1 Pass MADW-500 02/01/22 Mn-54 20.4 +/- 0.6 18.9 13.2 - 24.6 Pass MADW-500 02/01/22 Zn-65 28.65 +/- 0.94 26.2 18.3 - 34.1 Pass MADW-500 02/01/22 H-3 309 +/- 10 300 210 - 390 Pass MAVE-507 02/01/22 Cs-134 7.53 +/- 0.17 7.61 5.33 - 9.89 Pass MAVE-507 02/01/22 Cs-137 1.60 +/- 0.12 1.52 1.06 - 1.98 Pass MAVE-507 02/01/22 Co-60 0.01 +/- 0.03 0

NA c Pass MAVE-507 02/01/22 Mn-54 2.94 +/- 0.14 3

1.81 - 3.37 Pass MAVE-507 02/01/22 Zn-65 1.69 +/- 0.17 1.47 1.03 - 1.91 Pass MADW-2613 08/01/22 GR-A 1.39 +/- 0.10 0.90 0.27 - 1.53 Pass MADW-2613 08/01/22 GR-B 1.69 +/- 0.04 1.31 0.66 - 1.97 Pass MASO-2737 08/01/22 Cs-134 523 +/- 5 627 439 - 815 Pass MASO-2737 08/01/22 Cs-137 1.18 +/- 2.21 0

NA c Pass MASO-2737 08/01/22 Co-60

-0.04 +/- 1.07 0

NA c Pass MASO-2737 08/01/22 Mn-54 903 +/- 11 841 589 - 1,093 Pass MASO-2737 08/01/22 Zn-65 1,227 +/- 19 1,140 798 - 1,482 Pass MASO-2737 08/01/22 K-40 595 +/- 37 537 376 - 698 Pass MADW-2733 08/01/22 Cs-134 13.6 +/- 0.3 17.1 12.0 - 22.2 Pass MADW-2733 08/01/22 Cs-137 16.0 +/- 0.4 16.8 11.8 - 21.8 Pass MADW-2733 08/01/22 Co-60 14.4 +/- 0.3 17.0 11.9 - 22.1 Pass MADW-2733 08/01/22 Mn-54

-0.03 +/- 0.10 0

NA c Pass MADW-2733 08/01/22 Zn-65 11.5 +/- 0.6 11.3 7.9 - 14.7 Pass MADW-2733 08/01/22 Sr-90 6.79 +/- 0.32 7.7 5.41 - 10.05 Pass MAVE-2740 08/01/22 Cs-134 0.01 +/- 0.06 0

NA c Pass MAVE-2740 08/01/22 Cs-137 1.15 +/- 0.12 1.083 0.758 - 1.408 Pass MAVE-2740 08/01/22 Co-60 4.71 +/- 0.14 4.62 3.23 - 6.01 Pass MAVE-2740 08/01/22 Mn-54 2.67 +/- 0.19 2

1.70 - 3.16 Pass MAVE-2740 08/01/22 Zn-65 7.73 +/- 0.39 7.49 5.24 - 9.74 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.

Concentration a DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

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

TABLE E.5 Lab Code Date Analysis Laboratory Result ERA Result Control Limits Acceptance RAD-128 ERW-95 01/10/22 Cs-134 82.6 +/- 4.1 85 69.6 - 93.4 Pass ERW-95 01/10/22 Cs-137 35.4 +/- 4.6 29.3 25.2 - 35.3 Failb ERW-95 01/10/22 Co-60 104 +/- 4 102.0 91.8 - 114 Pass ERW-95 01/10/22 Zn-65 356 +/- 13 312.0 281 - 384 Pass ERW-95 01/10/22 GR-A 30.9 +/- 2.2 32.5 16.6 - 42.1 Pass ERW-95 01/10/22 GR-B 62.9 +/- 2.3 68.3 47.4 - 75.1 Pass ERW-95 01/10/22 H-3 23,600 +/- 700 22,200 19,500 - 24,400 Pass RAD-130 ERW-2087 08/25/22 Cs-134 81.8 +/- 3.9 88.6 72.7 - 97.5 Pass ERW-2087 08/25/22 Cs-137 174 +/- 6 170 153 - 189 Pass ERW-2087 08/25/22 Co-60 76.9 +/- 4.0 72.4 65.2 - 82.1 Pass ERW-2087 08/25/22 Zn-65 349 +/- 3 326 293 - 380 Pass ERW-2087 08/25/22 GR-A 52.8 +/- 2.4 60.2 31.5 - 74.8 Pass ERW-2087 08/25/22 GR-B 18.7 +/- 1.0 17.7 10.1 - 25.9 Pass ERW-2087 08/25/22 H-3 23,900 +/- 481 22,100 19,400 - 24,300 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).

b Explanation in IV. Results and Discussion, Section E ATI Environmental, Inc., Midwest Laboratory Interlaboratory Comparison Crosscheck Program Environmental Resource Associates (ERA)a RAD Study (Relevant Nuclides Only)

TeledyneConfidential;CommerciallySensitiveBusinessData

APPENDIX F ERRATA DATA

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There was no errata data for 2022.

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APPENDIX G ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

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Docket No:

50-219 OYSTER CREEK GENERATING STATION UNIT 1 Annual Radiological Groundwater Protection Program Report 1 January through 31 December 2022 Prepared By Teledyne Brown Engineering Environmental Services Oyster Creek Generating Station Forked River, NJ 08731 April 2023

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i 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

ii Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2022 Figures Figure A-1 Sampling locations - Selected Cohansey and Cape May Formation Wells, Oyster Creek Generating Station, 2022 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, 2022 Table B-I.2 Concentrations of Gamma Emitters in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2022 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, 2022 Table B-II.1 Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2022 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, 2022 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, 2022 Table B-III.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2022

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 2022 through 31 December 2022.

This report covers groundwater and surface water samples collected from the environment, both on and off station property in 2022. In 2022, 322 analyses were performed on 72 samples from 34 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 34 groundwater well sample locations or 6 surface water locations analyzed during 2022.

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 2022 tritium concentrations varied from <161 to 605 pCi/L. The well with the highest concentration was W-13.

Surface water samples were collected from onsite and offsite monitoring locations during 2022. 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 2022.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples in 2022. There were 30 samples taken from 20 groundwater well locations. Gross Alpha (dissolved) was detected in 2 samples. The concentrations ranged from 0.7 to 0.8 pCi/L. Gross Alpha (suspended) was detected in 5 samples and ranged from 1.3 to 6.6 pCi/L.

Gross Beta (dissolved) was detected in 30 samples and ranged from 1.1 to 17.4 pCi/L. Gross Beta (suspended) was detected in 8 samples and ranged from 2.2 to 28.0 pCi/L.

Hard-To-Detect (HTD) analyses were performed on one groundwater sample in 2022. 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), uranium-238 (U-238), iron-55 (Fe-55) and nickel-63 (Ni-63). All 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 2022.

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 2022.

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 2022. 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 (a priori) estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact (a posteriori) 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 2022. 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 in shallow aquifers is towards the intake and discharge canals.

Tritium Samples from 34 locations were analyzed for tritium activity. Tritium was detected in 14 of 63 samples. The values ranged from <LLD to 605 pCi/L.

The well with the highest concentration was W-13. (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 2022. (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 2022. There were 30 samples taken from 20 groundwater well locations. Gross Alpha (dissolved) was detected in 2 samples. The concentrations ranged from 0.7 to 0.8 pCi/L.

Gross Alpha (suspended) was detected in 5 samples and ranged from 1.1 to 6.6 pCi/L. Gross Beta (dissolved) was detected in 30 samples and ranged from 1.1 to 17.4 pCi/L. Gross Beta (suspended) was detected in 8 samples and ranged from 2.2 to 28.0 pCi/L. (Table B-I.1, Appendix B)

Gamma Emitters No gamma-emitting nuclides were detected in any groundwater sample in 2022. (Table B-I.2, Appendix B).

Hard-To-Detect Hard-To-Detect (HTD) analyses were performed on one groundwater sample in 2022. All 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 5 locations were analyzed for tritium activity. No H-3 was detected in any sample. (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 2022.

Gamma Emitters Naturally occurring K-40 was detected in one sample at a concentration of 115 pCi/L. No other gamma-emitting nuclides were detected in surface water samples during 2022. (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 2022.

D.

Precipitation Water Results No precipitation samples were collected in 2022. (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 2022 Oyster Creek AREOR. This report is part of the AREOR.

F.

Leaks, Spills, and Releases There were no leaks or spills during 2022.

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 (Historic)

Active remediation of tritium in groundwater due to the Condensate Storage Tank (CST) 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 Pumping well Cohansey October

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 2nd 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. GHD, Hydrogeologic Investigation Report, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, 2022

2. Conestoga Rovers and Associates, Hydrogeologic Investigation Report, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, 2016

3. Conestoga Rovers and Associates, Hydrogeologic Investigation Report, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, April 2011

4. Conestoga Rovers and Associates, Site Investigation Report, Oyster Creek Generating Station, Forked River, New Jersey, October 2009

5. Conestoga Rovers and Associates, Remedial Investigation Workplan, Oyster Creek Generating Station, Forked River, New Jersey, 2009

APPENDIX A LOCATION DESIGNATION

Intentionally left blank

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2022 Oyster Creek Generating Station RGPP Sample Point List Sample Identification Number Location Well GPS Coordinates (Northing/Easting)

Depth (ft)

RGPP Sample Point Designation Tritium Alert Value Aquifer or Water Body Monitored MW-1A-2A SW of MFOT Moat 357380.76 575043.44 24.0 D

2,000 pCi/L Cape May MW-1I-1A Roadway - NW of TWST 357598.17 574412.70 19.0 D

2,000 pCi/L Cape May MW-1I-2A Roadway - SE of TWST 357574.80 574493.50 17.5 D

2,000 pCi/L Cape May MW-15K-1A Roadway -

Intake 357297.90 574469.50 19.0 D

2,000 pCi/L Cape May MW-16D Yard - W of MAC Building 357573.30 574746.50 25.0 D

2,000 pCi/L Cape May SW-1 Intake Canal N/A N/A SW 2,000 pCi/L Surface Water SW-2 RT 9 South Bridge N/A N/A SW 2,000 pCi/L Surface Water SW-3 Fire Pond N/A N/A SW 2,000 pCi/L Surface Water W-1A North Yard Area 358311.70 574679.00 50.0 B

2,000 pCi/L Cohansey W-3 Intake - Access Road 357173.00 574499.10 24.0 D

2,000 pCi/L Cape May W-4 Intake - Access Road 357176.40 574497.70 55.0 D

2,000 pCi/L Cohansey W-4A SE of OCAB Building 356913.30 575387.10 50.0 B

2,000 pCi/L Cohansey W-5 NW Yard area, near Fire Water Tank 357510.95 574374.05 20.5 D

2,000 pCi/L Cape May W-6 NW Yard - near Fire Water Tank 357514.02 574373.77 52.0 D

2,000 pCi/L Cohansey W-9 Roadway - NE of SAS Building 357289.29 574892.74 20.0 D

2,000 pCi/L Cape May W-9 Roadway - NE of SAS Building 357289.29 574892.74 20.0 D

2,000 pCi/L Cape May W-10 NW of SAS Building 357286.29 574890.61 60.0 D

2,000 pCi/L Cape May W-12 Yard - NW of DWPC Building 357669.10 574755.60 20.0 D

2,000 pCi/L Cape May W-13 Yard - NW of DWPC Building 357666.00 574755.90 50.0 D

2,000 pCi/L Cape May W-14 Yard - SW of Warehouse 357702.41 575018.75 53.0 D

2,000 pCi/L Cape May W-15 Yard - SW of Warehouse 357705.83 575017.70 20.0 D

2,000 pCi/L Cape May A-1

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2022 Oyster Creek Generating Station RGPP Sample Point List Sample Identification Number Location Well GPS Coordinates (Northing/Easting)

Depth (ft)

RGPP Sample Point Designation Tritium Alert Value Aquifer or Water Body Monitored W-16 Yard - E of LLRW 357967.26 574933.03 20.0 D

2,000 pCi/L Cape May W-24 South of TB W of old Machine Shop 357128.94 574650.77 19.0 D

2,000 pCi/L Cape May W-34 South of TB W of old Machine Shop 357196.14 574649.43 40.0 D

2,000 pCi/L Cohansey MW-52 Near Intake Structure 357400.90 574353.00 20.0 D

2,000 pCi/L Cape May MW-53 Near end of CW discharge piping 357272.80 574447.60 20.0 D

2,000 pCi/L Cape May MW-54 Near Intake Structure 357276.20 574311.70 20.0 E

2,000 pCi/L Cape May MW-55 Between CST and Intake Structure 357354.88 574440.07 30.0 E

2,000 pCi/L Cape May MW-56I By NaOCl tanks 357305.30 574465.50 52.0 E

2,000 pCi/L Cohansey MW-57I Near Intake Structure 357343.71 574373.89 50.0 E

2,000 pCi/L Cohansey MW-59I Intake Roadway

- NW of CST 357422.14 574406.38 44.0 D

2,000 pCi/L Cohansey MW-61I Between CST and Intake Structure 357328.64 574444.45 72.0 E

2,000 pCi/L Cohansey MW-62 NW Corner of Turbine Bldg 357467.93 574524.10 25.0 D

2,000 pCi/L Cape May MW-64 Near Intake Structure 357343.96 574377.88 25.0 E

2,000 pCi/L Cape May MW-65 Intake Roadway

- NW of CST 357421.00 574402.55 25.0 D

2,000 pCi/L Cape May MW-67 West side of Turbine Bldg 357401.99 574540.38 25.0 E

2,000 pCi/L Cape May MW-68I SE of Reactor Bldg 357323.83 574897.64 100.0 D

2,000 pCi/L Cohansey MW-71 S of Reactor Bldg 357365.52 574841.89 25.0 D

2,000 pCi/L Cape May MW-72 N of Reactor Bldg 357549.87 574788.52 25.0 D

2,000 pCi/L Cape May KEY: B = Background D = Detection E = Elevated I = Idle/Standby P = Plume L = Long-Term Shutdown SW = Surface Water A-2

Figure A-1 RGPP Sample Locations Surface Water and Cape May Formation Oyster Creek Generating Station, 2022 A-3

Figure A-2 RGPP Sample Locations Cohansey Formation Oyster Creek Generating Station, 2022 A-4

Figure A-3 RGPP Sample Locations Cape May Groundwater Formation Oyster Creek Generating Station, 2022 A-5

Figure A-4 RGPP Sample Locations Cohansey Groundwater Formation Oyster Creek Generating Station, 2022 A-6

APPENDIX B DATA TABLES

Intentionally left blank

TABLE B-I.1 COLLECTION SITE DATE H-3 Sr-89 Sr-90 MW-1A-2A 04/27/22

< 167

< 5.6

< 0.8

< 0.5 1.3 +/- 0.8 2.7 +/- 0.6

< 1.7 MW-1I-1A 04/27/22

< 181 MW-1I-1A 10/25/22

< 191 MW-1I-2A 04/27/22

< 182

< 7.8

< 0.9

< 0.7

< 0.7 4.1 +/- 0.8

< 1.6 MW-1I-2A 10/25/22

< 189 MW-15K-1A 04/26/22

< 173

< 5.6

< 0.9

< 0.8

< 0.9 3.5 +/- 0.9

< 1.7 MW-15K-1A 10/25/22

< 190

< 7.6

< 0.9

< 0.5

< 1.1 4.2 +/- 0.8

< 1.5 MW-16D 04/27/22

< 177

< 5.3

< 0.9

< 0.8

< 0.7 3.7 +/- 0.9

< 1.6 MW-16D 04/27/22 Duplicate < 171

< 7.2

< 0.8

< 0.7 4.6 +/- 0.9

< 1.6 MW-16D 04/27/22 EIML

< 163

< 0.7

< 0.6 (1)

< 1.7 MW-16D 10/26/22

< 186 MW-16D 10/26/22 Duplicate < 177 MW-16D 10/26/22 EIML

< 166 MW-52 04/26/22

< 187 MW-53 04/26/22

< 180 MW-54 04/26/22 237 +/- 129 MW-55 04/26/22

< 172

< 6.3

< 0.9

< 0.5 2.6 +/- 1.1 1.9 +/- 0.7 2.2 +/- 1.3 MW-55 10/25/22

< 169

< 8.7

< 0.9

< 0.5 2.4 +/- 1.3 2.4 +/- 0.7 2.7 +/- 1.2 MW-56I 04/26/22 209 +/- 115

< 7.7

< 0.9

< 0.5

< 0.7 3.5 +/- 0.7

< 1.7 MW-56I 10/25/22 270 +/- 130

< 8.0

< 1.0

< 1.6

< 1.1 11.5 +/- 1.6

< 1.5 MW-57I 04/26/22 368 +/- 123

< 6.6

< 0.9

< 0.8

< 1.6 8.7 +/- 1.1

< 1.9 MW-57I 10/25/22

< 189

< 7.3

< 1.0 0.8 +/- 0.5

< 1.6 7.4 +/- 0.9 5.2 +/- 1.5 MW-59I 04/26/22 379 +/- 121

< 7.2

< 0.9

< 0.7

< 1.3 2.4 +/- 0.7

< 1.7 MW-59I 10/25/22

< 199 MW-61I 04/26/22 183 +/- 112

< 5.6

< 0.9

< 1.1

< 1.6 2.9 +/- 1.0 3.2 +/- 1.4 MW-61I 10/25/22 189 +/- 120 MW-62 04/26/22

< 193

< 5.8

< 0.9

< 1.2

< 1.7 17.4 +/- 1.6 2.4 +/- 1.4 MW-62 10/25/22

< 186 MW-64 04/26/22

< 180

< 7.0

< 0.9

< 0.6

< 3.6 2.4 +/- 0.8 12.8 +/- 2.7 MW-64 04/26/22 Duplicate < 162

< 7.7

< 0.9

< 0.4 4.9 +/- 3.0 3.0 +/- 0.8 15.3 +/- 2.9 MW-64 04/26/22 EIML

< 163

< 0.6

< 0.5 (1)

< 2.3 MW-64 10/25/22

< 176 MW-64 10/25/22 Duplicate < 191 MW-64 10/25/22 EIML

< 166 MW-65 04/26/22

< 172

< 6.7

< 0.9

< 0.8

< 1.4 4.9 +/- 1.1

< 1.8 MW-65 10/25/22

< 196

< 6.7

< 0.8

< 1.5

< 1.1 9.0 +/- 1.5

< 1.5 MW-67 04/26/22 236 +/- 115

< 5.3

< 0.8

< 0.7

< 0.9 12.0 +/- 1.3

< 1.9 MW-67 10/26/22

< 192

< 8.4

< 1.0 0.7 +/- 0.3

< 1.1 1.6 +/- 0.6

< 1.5 MW-71 04/27/22

< 164

< 6.9

< 0.8

< 0.6

< 0.9 3.7 +/- 0.9

< 1.9 MW-71 10/26/22

< 192 MW-72 04/27/22

< 161

< 8.0

< 0.8

< 0.4

< 0.9 2.3 +/- 0.7

< 1.9 MW-72 04/27/22 Duplicate < 165

< 8.0

< 0.8

< 0.4

< 0.9 2.1 +/- 0.7

< 1.9 MW-72 04/27/22 EIML

< 163

< 0.6

< 0.5 (1)

< 0.7 MW-72 10/26/22 204 +/- 130 W-1A 04/28/22

< 183 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, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Gr-B (Sus)

Gr-B (Dis)

Gr-A (Dis)

Gr-A (Sus)

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

B-1

TABLE B-I.1 COLLECTION SITE DATE H-3 Sr-89 Sr-90 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, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Gr-B (Sus)

Gr-B (Dis)

Gr-A (Dis)

Gr-A (Sus)

W-3 04/26/22 187 +/- 121

< 6.8

< 0.8

< 0.6

< 0.7 1.1 +/- 0.6

< 1.6 W-3C 04/28/22

< 163 W-3 10/25/22

< 196 W-3C 10/26/22 EIML

< 166 W-4 04/26/22

< 182 W-4A 04/28/22

< 179 W-5 04/26/22

< 191

< 5.7

< 0.9

< 0.4

< 0.7 2.4 +/- 0.6

< 1.7 W-5 04/26/22 Duplicate < 181

< 6.9

< 0.8

< 0.4

< 0.7 2.9 +/- 0.6

< 1.7 W-5 04/26/22 EIML

< 163

< 0.8

< 0.6 (1)

< 0.7 W-5 10/25/22

< 187 W-5 10/25/22 Duplicate 175 +/- 113 W-5 10/25/22 EIML

< 166 W-6 04/27/22

< 187 W-9 04/27/22

< 188

< 6.9

< 0.9

< 0.8

< 1.3 4.1 +/- 0.9

< 1.7 W-9 10/26/22

< 180 W-10 04/27/22

< 193 W-12 04/27/22

< 185

< 7.0

< 0.9

< 0.6 6.6 +/- 3.0 1.8 +/- 0.9 28.0 +/- 3.9 W-12 10/26/22

< 175 W-13 04/27/22 605 +/- 140 W-13 06/23/22 313 +/- 129 W-14 04/27/22

< 180 W-15 04/27/22

< 180 W-16 04/27/22 222 +/- 127 W-16 06/23/22

< 191 W-24 04/28/22

< 177 W-34 04/28/22

< 179

< 5.9

< 0.9

< 0.4

< 0.7 1.4 +/- 0.6

< 1.7 W-34 10/26/22

< 183 (1) Total Gross Alpha result reported (not dissolved/suspended)

B-2

TABLE B-I.2 COLLECTION SITE DATE Be-7 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 MW-1A-2A 04/27/22

< 40

< 74

< 4

< 5

< 11

< 4

< 7

< 8

< 4

< 5 MW-1I-1A 04/27/22

< 55

< 102

< 4

< 6

< 11

< 5

< 10

< 6

< 5 MW-1I-2A 04/27/22

< 54

< 122

< 7

< 8

< 6

< 10

< 13

< 6

< 6 MW-15K-1A 04/26/22

< 39

< 75

< 5

< 12

< 3

< 10

< 9

< 6

< 5 MW-15K-1A 10/25/22

< 56

< 111

< 5

< 6

< 14

< 7

< 16

< 10

< 5

< 6 MW-16D 04/27/22

< 63

< 113

< 7

< 9

< 15

< 8

< 14

< 13

< 8

< 5 MW-16D 04/27/22 Duplicate

< 50

< 110

< 5

< 6

< 13

< 5

< 11

< 8

< 6

< 5 MW-52 04/26/22

< 39

< 80

< 4

< 9

< 5

< 11

< 9

< 6

< 4 MW-53 04/26/22

< 44

< 77

< 5

< 12

< 5

< 7

< 10

< 7

< 5 MW-54 04/26/22

< 49

< 125

< 6

< 16

< 8

< 10

< 8

< 6

< 7 MW-55 04/26/22

< 58

< 117

< 6

< 7

< 15

< 6

< 9

< 11

< 7

< 6 MW-55 10/25/22

< 46

< 51

< 5

< 6

< 10

< 6

< 11

< 8

< 5

< 4 MW-56I 04/26/22

< 41

< 71

< 4

< 5

< 12

< 6

< 7

< 8

< 4

< 5 MW-56I 10/25/22

< 56

< 129

< 6

< 7

< 14

< 8

< 11

< 10

< 8

< 5 MW-57I 04/26/22

< 21

< 39

< 2

< 5

< 2

< 5

< 4

< 2

< 2 MW-57I 10/25/22

< 48

< 132

< 6

< 7

< 11

< 3

< 11

< 12

< 7

< 7 MW-59I 04/26/22

< 67

< 138

< 6

< 7

< 12

< 8

< 15

< 11

< 6

< 7 MW-61I 04/26/22

< 44

< 78

< 4

< 11

< 6

< 9

< 5

< 5 MW-62 04/26/22

< 23

< 20

< 3

< 5

< 2

< 6

< 5

< 3

< 3 MW-64 04/26/22

< 26

< 24

< 2

< 3

< 5

< 3

< 5

< 3

< 3 MW-64 04/26/22 Duplicate

< 56

< 92

< 7

< 8

< 18

< 7

< 12

< 11

< 6

< 7 MW-64 04/26/22 EIML

< 64

< 121

< 5 (1)

(1)

< 3

< 5 (1)

(1)

< 5 MW-65 04/26/22

< 20

< 22

< 2

< 5

< 2

< 4

< 2

< 2 MW-65 10/25/22

< 62

< 129

< 7

< 6

< 15

< 7

< 14

< 11

< 9

< 6 MW-67 04/26/22

< 47

< 82

< 4

< 8

< 5

< 9

< 7

< 5

< 5 MW-67 10/26/22

< 55

< 110

< 5

< 6

< 11

< 6

< 14

< 12

< 7

< 7 MW-71 04/27/22

< 44

< 82

< 5

< 13

< 6

< 10

< 7

< 4

< 4 MW-72 04/27/22

< 43

< 85

< 5

< 4

< 11

< 5

< 9

< 10

< 6

< 5 MW-72 04/27/22 Duplicate

< 49

< 82

< 5

< 4

< 11

< 6

< 10

< 9

< 6

< 6 MW-72 04/27/22 EIML

< 30

< 58

< 2 (1)

(1)

< 1

< 4 (1)

(1)

< 3 W-1A 04/28/22

< 68

< 67

< 6

< 8

< 13

< 8

< 14

< 9

< 8 W-3 04/26/22

< 46

< 134

< 6

< 14

< 8

< 12

< 14

< 7

< 6 W-3C 04/28/22 EIML

< 25

< 47

< 2 (1)

(1)

< 2

< 4 (1)

(1)

< 2 W-3C 10/26/22 EIML

< 29

< 45

< 2 (1)

(1)

< 2

< 6 (1)

(1)

< 3 K-40 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA (1) Result not reported B-3

TABLE B-I.2 COLLECTION SITE DATE Be-7 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 K-40 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA W-4 04/26/22

< 50

< 111

< 6

< 7

< 11

< 5

< 13

< 6

< 6 W-4A 04/28/22

< 69

< 127

< 6

< 8

< 12

< 5

< 17

< 12

< 10

< 8 W-5 04/26/22

< 48

< 89

< 5

< 6

< 13

< 6

< 11

< 5

< 6 W-5 04/26/22 Duplicate

< 51

< 101

< 7

< 8

< 12

< 8

< 13

< 7

< 7 W-6 04/27/22

< 43

< 44

< 4

< 5

< 11

< 5

< 9

< 5

< 5 W-9 04/27/22

< 30

< 61

< 5

< 9

< 4

< 8

< 7

< 4

< 4 W-10 04/27/22

< 47

< 86

< 5

< 6

< 11

< 6

< 12

< 10

< 7

< 4 W-12 04/27/22

< 54

< 98

< 4

< 6

< 7

< 5

< 10

< 5

< 5 W-13 04/27/22

< 53

< 120

< 5

< 7

< 9

< 6

< 10

< 9

< 6

< 6 W-14 04/27/22

< 67

< 121

< 6

< 7

< 14

< 7

< 12

< 13

< 8

< 7 W-15 04/27/22

< 49

< 106

< 5

< 11

< 6

< 11

< 6

< 5 W-16 04/27/22

< 23

< 54

< 2

< 3

< 6

< 2

< 5

< 3

< 3 W-24 04/28/22

< 71

< 124

< 7

< 16

< 6

< 14

< 13

< 8

< 8 W-34 04/28/22

< 70

< 150

< 7

< 8

< 13

< 8

< 18

< 10

< 7

< 9 (1) Result not reported B-4

TABLE B-I.3 COLLECTION SITE DATE Am-241 Cm-242 Pu-238 U-234 U-235 U-238 MW-15K-1A 04/26/22

< 0.14

< 0.04

< 0.19

< 0.13

< 0.1

< 0.13

< 56

< 4.2 CONCENTRATIONS OF HARD-TO-DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Cm-243/244 Pu-239/240 Fe-55 Ni-63 B-5

TABLE B-II.1 COLLECTION SITE DATE SEWER PIT 01/20/22

< 178 SEWER PIT 04/26/22

< 172 SEWER PIT 09/22/22

< 193 STORM DRAIN OUTFALL #2 10/24/22

< 193 SW-1 04/25/22

< 172 SW-1 10/26/22

< 197 SW-2 04/25/22

< 175 SW-2 10/24/22

< 182 SW-3 04/25/22

< 173 SW-3 10/24/22

< 190 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2022 H-3 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER B-6

TABLE B-II.2 COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Cs-134 SW-1 04/25/22

< 17 115 +/- 25

< 2

< 4

< 2

< 4

< 3

< 2

< 2 SW-2 04/25/22

< 20

< 22

< 2

< 6

< 2

< 5

< 4

< 2

< 2 SW-3 04/25/22

< 19

< 2

< 5

< 2

< 4

< 2

< 2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER Cs-137 B-7

TABLE B-II.3 CONCENTRATIONS OF HARD TO DETECTS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE COLLECTION SITE DATE Am-241 Cm-242 Pu-238 U-234 U-235 U-238 RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA NO SURFACE WATER HTD'S FOR 2022 Cm-243/244 Pu-239/240 Fe-55 Ni-63 B-8

TABLE B-III.1 COLLECTION SITE DATE H-3 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2022 NO PRECIPITATION SAMPLES FOR 2022 B-9

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